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Sample records for angra ii nuclear

  1. Study of the influencies of Angra-1 nuclear power plant construction in Angra dos Reis

    International Nuclear Information System (INIS)

    Ferreira Netto, L.

    1982-01-01

    The report presents a comprehensive evaluation of the influence caused by Angra-1 Nuclear Power Plants (Central Nuclear Almirante Alvaro Alberto) construction on the Angra dos Reis City - Rio de Janeiro - Brazil. The analysis performed adopts a multi-dimensional methodology with four analysis dimensions: political-institutional, physical-territorial, social-economic and temporal. (author)

  2. Study of sea surface temperature distribution, in Angra dos Reis Nuclear Plant region - Mission Angra 01

    International Nuclear Information System (INIS)

    Stevenson, M.R.; Steffen, C.A.; Villagra, H.M.I.

    1982-03-01

    A study of spectral and temporal variations of sea surface temperature, using data obtained from level of satellite, aircraft and surface, with the purpose of evaluate and plot the small scale variations of sea surface temperature, due to thermal discharge from a nuclear the results of the first mission called Angra 1. (maps). (C.G.C.)

  3. Angra 1 nuclear power plant full scope simulator development project

    International Nuclear Information System (INIS)

    Selvatici, Edmundo; Castanheira, Luiz Carlos C.; Silva Junior, Nilo Garcia da

    2015-01-01

    Specific Full Scope Simulators are an essential tool for training NPP control room operators, in the formation phase as well as for maintaining their qualifications. In the last years availability of a Plant specific simulator has also become a Regulator requirement for Nuclear Power Plant operation. By providing real-time practical training for the operators, the use of a simulator allows improving the operator's performance, reducing the number of unplanned shutdowns and more effective response to abnormal and emergency operating conditions. It can also be used, among other uses, to validate procedures, test proposed plant modifications, perform engineering studies and to provide operation training for the technical support staff of the plant. The NPP site, in Angra dos Reis-RJ, Brazil, comprises the two units in operation, Unit 1, 640 MWe, Westinghouse PWR and Unit 2, 1350 MWe, KWU/Areva PWR and one unit in construction, Unit 3, 1405 MWe, KWU/Areva PWR, of the same design of Angra 2. Angra 2 has had its full scope simulator from the beginning, however this was not the case of Angra 1, that had to train its operators abroad, due to lack of a specific simulator. Eletronuclear participated in all the phases of the project, from data supply to commissioning and validation. The Angra 1 full scope simulator encompasses more than 80 systems of the plant including the Primary system, reactor core and associated auxiliary systems, the secondary system and turbo generator as well as all the Plant operational and safety I and C. The Angra 1 Main Control Room panels were reproduced in the simulator control room as well as the remote shutdown panels that are outside the control room. This paper describes the project for development of the Angra 1 NPP Full Scope Simulator, supplied by Tecnatom S.A., in the period of Feb.2012 to Feb.2015. (author)

  4. Power control of the Angra-2 Nuclear Power Plant

    International Nuclear Information System (INIS)

    Souza Mendes, J.E. de

    1986-01-01

    The systems for the power control of the Nuclear Power Plant Angra 2 have a high degree of automation so that few operator actions are required during power operation. The power control strategy and the operation principles of the control systems, here presented, make possible a great flexibility of the Plant operation. (Author) [pt

  5. Angra nuclear plant - environmental control program

    International Nuclear Information System (INIS)

    Kircher, E.; Cruz, E.S. da

    1989-01-01

    The pre-operational studies, that were elaborated before the beginning of Angra I Power Plant operation, are described in particular the environmental radiological safety area till the fuel loading in the core reactor. Several aspects are included, as socio-economic survey, seismological analysis, Meteorological Program, marine biology, water cooling system, exposure measures of natural radiation, marine sediments characterization in the effluent dispersion area and Environmental Radiological Monitoring Program. The main environmental programs developed for the operational phase of the Angra I Plant are also presented, citing some considerations about the Meteorological Program, Marine Biology Control Program, Temperature and Chlorine Control in Piraquara de Fora Bay, Radiological Environmental Monitoring Program, Sanitary Effluent Control Program and Radiological Emergency Program. (C.G.C.). 2 refs

  6. Energy and exergy analyses of Angra-2 nuclear power plant

    Energy Technology Data Exchange (ETDEWEB)

    Marques, João G.O.; Costa, Antonella L.; Pereira, Claubia; Fortini, Ângela, E-mail: jgabrieloliveira2010@bol.com.br, E-mail: antonella@nuclear.ufmg.br, E-mail: claubia@nuclear.ufmg.br, E-mail: fortini@nuclear.ufmg.br [Universidade Federal de Minas Gerais (UFMG), Belo Horizonte, MG (Brazil). Departamento de Engenharia Nuclear

    2017-07-01

    Nuclear Power Plants (NPPs) based on Pressurized Water Reactors (PWRs) technology are considered an alternative to fossil fuels plants due to their reliability with low operational cost and low CO{sub 2} emissions. An example of PWR plant is Angra-2 built in Brazil. This NPP has a nominal electric power output of 1300 MW and made it possible for the country save its water resources during electricity generation from hydraulic plants, and improved Brazilian knowledge and technology in nuclear research area. Despite all these benefits, PWR plants generally have a relatively low thermal efficiency combined with a large amount of irreversibility generation or exergy destruction in their components, reducing their capacity to produce work. Because of that, it is important to assess such systems to understand how each component impacts on system efficiency. Based on that, the aim of this work is to evaluate Angra-2 by performing energy and exergy analyses to quantify the thermodynamic performance of this PWR plant and its components. The methodology consists in the development of a mathematical model in EES (Engineering Equation Solver) software based on thermodynamic states in addition to energy and exergy balance equations. According to the results, Angra 2 has energy efficiency of 36.18% and exergy efficiency of 49.24%. Reactor core is the most inefficient device in the NPP; it has exergy efficiency of 67.16% and is responsible for 63.88% of all exergy destroyed in Angra-2. (author)

  7. Energy and exergy analyses of Angra-2 nuclear power plant

    International Nuclear Information System (INIS)

    Marques, João G.O.; Costa, Antonella L.; Pereira, Claubia; Fortini, Ângela

    2017-01-01

    Nuclear Power Plants (NPPs) based on Pressurized Water Reactors (PWRs) technology are considered an alternative to fossil fuels plants due to their reliability with low operational cost and low CO 2 emissions. An example of PWR plant is Angra-2 built in Brazil. This NPP has a nominal electric power output of 1300 MW and made it possible for the country save its water resources during electricity generation from hydraulic plants, and improved Brazilian knowledge and technology in nuclear research area. Despite all these benefits, PWR plants generally have a relatively low thermal efficiency combined with a large amount of irreversibility generation or exergy destruction in their components, reducing their capacity to produce work. Because of that, it is important to assess such systems to understand how each component impacts on system efficiency. Based on that, the aim of this work is to evaluate Angra-2 by performing energy and exergy analyses to quantify the thermodynamic performance of this PWR plant and its components. The methodology consists in the development of a mathematical model in EES (Engineering Equation Solver) software based on thermodynamic states in addition to energy and exergy balance equations. According to the results, Angra 2 has energy efficiency of 36.18% and exergy efficiency of 49.24%. Reactor core is the most inefficient device in the NPP; it has exergy efficiency of 67.16% and is responsible for 63.88% of all exergy destroyed in Angra-2. (author)

  8. The marine environment monitoring in Saco Piraquara de Fora after the beginning of the Angra 2 nuclear power plant operation

    International Nuclear Information System (INIS)

    Tavares, P.G.; Souza, R.F.; Cardoso, S.N.M.

    2009-01-01

    The goal of this paper is to evaluate the environmental monitoring around the Almirante Alvaro Alberto Nuclear Power Station after the beginning the operation of Unit II, in July 2000. The Environmental Monitoring Laboratory collects several environmental samples and analyses them radiometrically to determine the presence of artificial radionuclides. In the Environmental Monitoring Laboratory, the samples are prepared and analysed following international procedures and the activities of the detectable radionuclides are obtained by gamma spectrometry. The Environmental Monitoring Laboratory analyses tritium in sea water as well. This paper will describe only the monitoring of the marine samples and the results of the measurements are compared with those obtained in pre-operational time of Angra 1 (1978 - 1982), Angra 2 (1996 - 2000) and those obtained in operational time of the units until 2008. The results show that, since 1982 until now, there is no impact on marine environment caused by the operation of Angra 1 and Angra 2. (author)

  9. Nuclear power plant Angra integrated enterprise management system

    International Nuclear Information System (INIS)

    Andrade, Ronaldo Barata de

    2009-01-01

    The characteristics and peculiarities of the Nuclear Power Plant ANGRA 3 enterprise, amongst which its technical complexity, the size of the project and of the supplies of goods and services contracted for for the Brazilian and foreign scopes, the variety of contractors and participants involved in the implementation, associated with the need of integrated management of all the activities of the enterprise, requires the setting of standardized criteria and procedures to be adopted by the enterprise Project Management Team and by all involved ELETRONUCLEAR (ETN) Units, Suppliers and Contractors for Brazilian and foreign goods and services for the execution of the activities related to overall enterprise planning. These criteria and procedures aim at covering the five Project Management Process Groups: Initiating Process Group, Planning Process Group, Execution Process Group, Monitoring and Controlling Process Group and Closing Process Group. For the ANGRA 3 enterprise, ETN developed the Integrated Enterprise Management System - INTEGRA, being the software 'Primavera Enterprise Project Management' a fundamental part of this system. The aim of this paper is to describe the main concepts involving the ANGRA 3 enterprise management, and the integration between the processes, including all disciplines in all phases of the enterprise life cycle, such as: Nuclear and Environmental Licensing, Infrastructure, National and Foreign Engineering, National and Import Supplies, Civil Works, Electromechanical Erection, Commissioning. (author)

  10. 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)

  11. Angra, Iguape and the nuclear question

    International Nuclear Information System (INIS)

    Simon, D.N.

    1984-01-01

    A chronological analysis of the main events occured in the Brazilian nuclear sector was done. The consequences of the nuclear energy utilization in the Brazilian electric power system were studied. Finally, some suggestions are made to the scientists and experts of some research areas based on the socio-political repercussions originated from the implantation of the Brazilian nuclear energy program. (E.G.) [pt

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

    Energy Technology Data Exchange (ETDEWEB)

    Viana, Ronaldo do Nascimento

    2006-07-01

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

  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. Subcritical reactivity measurement at Angra 1 nuclear power plant

    International Nuclear Information System (INIS)

    Kuramoto, Renato Yoichi Ribeiro; Miranda, Anselmo Ferreira

    2011-01-01

    In order to speed up the Angra 1 NPP physics tests, this work intends to develop a digital reactivity meter combined with a methodology of the modified Neutron Source Multiplication (NSM) method with correction factors for subcriticality measurements at Angra 1 NPP. In the first part of this work, we have applied the Modified Neutron Source Multiplication (MNSM) Method with fundamental mode extraction, in order to improve the monitoring of the subcriticality at Angra 1 NPP during the criticality approach. In the second part, we developed a preliminary subcritical reactivity meter algorithm based on the point-reactor inverse kinetic model with six delayed neutron groups and external neutron source. The source strength was obtained through the Least Squares Inverse Kinetics Method (LSIKM). (author)

  15. Economic-financial analysis of 'Angra 3 Nuclear Power Plant' project

    International Nuclear Information System (INIS)

    Andrade, Ronaldo Barata de

    2005-01-01

    This paper presents an economic-financial evaluation of 'Angra 3 Nuclear Power Plant' project and estimates the lowest power tariff value at which power potentially made available may be commercialized and yet ensure the project a profitability level agreeable to the interests of economic agents and shareholders. According to the 'project evaluation' practice, Angra 3 power generation was considered separately from ELETRONUCLEAR's operating plants (Angra 1 and Angra 2), thus preventing result distortions bound to occur if the economic-financial variables of the new project were analyzed associated with financial commitments and commercialization conditions resulting from the project implementation process and the generated power commercialization conditions, respectively. For this evaluation different technical and economic scenarios were devised, and the theory of Capital Asset Pricing Model for Own Capital cost and that of Weighted Average Cost of Capital were used in addition to the forecast of the Statement of Results and Free Cash flow of Shareholders throughout the power plant life, which is the estimate basis for the lowest power tariff value and the Internal Return Rate of the project. The evaluation conclusion is that Angra 3 project is technically and economically feasible and competitive as compared to the new large power generation projects planned for power supply in Brazil in the next decade, mainly in the Southeast. (author)

  16. Atmospheric dispersion in complex terrain: Angra-1 nuclear power plant

    International Nuclear Information System (INIS)

    Lima e Silva Filho, P.P. de

    1986-01-01

    The Angra 1 plant is located in a very complex terrain, what makes the environmental impact assessment very difficult, regarding to the atmospheric transport problem as well as to the diffusion problem. Three main characteristics are responsible for that situation: the location at the shoreline, the complex topography and the high roughness of the terrain. Those characteristics generate specific phenomena and utilization of parameters from other sites are not convenient. Considering financial and technical viabilities, we must look for the local parameters, disregarding the easy, although risky, attitude of applying parameters and models incovenient to the Angra site. Some of those aspects are more important, and among them we will discuss the Plume Rise, the Critical Height, the Drainage Flow and the Atmospheric Dispersion Coefficients. (Author) [pt

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

    Energy Technology Data Exchange (ETDEWEB)

    Silva, Paulo Adriano da

    2000-03-01

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

  18. The Brazilian experience in licensing Angra 2, a 'delayed' nuclear power plant

    International Nuclear Information System (INIS)

    Almeida, C.

    2001-01-01

    The Brazilian nuclear power programme comprises two nuclear power plants in operation from different supplier countries. Furthermore, the second plant, Angra 2, had its construction started in 1976 and only recently in 2000 has achieved full power operation. This paper presents the experience of the Brazilian Regulatory Body in licensing this utility with all the complications arising from the different technologies, and safety philosophy, and the changes in safety standards, owners, suppliers, contractors and operators during the 25 years of construction. The paper presents first a history of the construction and commissioning of Angra 2, and then highlights some of the problems encountered in the licensing process. Some of the difficulties faced by CNEN due to several reorganizations and loss of personnel are also discussed. (author)

  19. Assessment of occupational radiation protection conditions during power enhancement of the Angra-2 nuclear power plant

    International Nuclear Information System (INIS)

    Azevedo, Eduardo M.; Rocha, Antonio Carlos S.; Ferreira, Paulo R.R.; Mouco, Charles Dickens C.L.; Godoy, Jose M.O.; Matta, Luiz E.S.C.

    2001-01-01

    This paper intend to analyse the occupational radioprotection conditions of the Angra-2 nuclear power plant, from the startup up to reach 100% of the nominal power. To perform this work a group of dose rates measures was made including beta/gamma and neutron radiation, particulates and iodine monitoring, and surface contamination, during the whole process. These measures were made inside of the three main buildings: the reactor buildings (UJA - reactor core and UJB) and the Reactor Auxiliary Building (UKA). (author)

  20. Tritium dispersion around the Angra Nuclear Power Plant: boundary simplification by Diffeomorph Conformal Transformations

    International Nuclear Information System (INIS)

    Meneghetti, Andre; Bodmann, Bardo E.J.; Vilhena, Marco T. de

    2017-01-01

    We present progress on research concerning dispersion of tritium around the Angra Nuclear Power Plant (Angra dos Reis, Rio de Janeiro state, Brazil). In particular, we are interested in studying how dispersion behaves in scenarios with complex orography. Our proposal is to transform a problem with curvilinear boundaries into an equivalent problem with plane parallel boundaries. We modify the coordinate system through a diffeomorph conformal transformation. Consequently, the operators of the dynamical equations change according to the additional terms from the affine connection. To de ne the transformation it is necessary to satisfy strong constraints, i.e., boundaries shall be 'smooth'. Our main purpose is to solve problems using a semi-analytical resolution. Currently, semi-analytic resolutions are applied only in problems that have domain with parallel planes. As a rst step into this direction in this work we present a numerical resolution. Even with restrictions, our model can be implemented in several situations. A at region is a particular case of a curvilinear domain and can be studied, where the height of the boundary layer above rivers, lakes, basins is typically smaller and thus implies a varying boundary layer height, for instance. Thus, even in at regions variations in the boundary layer occur, which characterizes a case of a curvilinear domain. Our specific interest is the region around the Angra Nuclear Power Plant that need a large source of water for their operation. There are several nuclear power plants worldwide, that are located in mountainous regions, as for example in Japan and Brazil. As one step into a new direction we focus in this work on complex relieves. We present a simulation of tritium dispersion specifically in the area where the Angra 2 Nuclear Power Plant of is located and where the relief is characterized by a considerable complexity. (author)

  1. A model of objects based on KKS for the processing of alarms at the Angra 2 nuclear power plant

    International Nuclear Information System (INIS)

    Silva, Paulo Adriano da

    2000-03-01

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

  2. Public relations strategy for the completion of Angra 2 nuclear power plant

    International Nuclear Information System (INIS)

    Kepinski, Alessandra

    1998-01-01

    In the 60's, the general public in Brazil knew little about nuclear energy. The country was under Military Rule since 1964 and, in the public's ind, the Nuclear Program was closely linked to nuclear weapons, being viewed with distrust and, even, fear. Governmental policies in this field were secret - when the decisions were made to built Angra 1 in 1968 and to sign the Nuclear Cooperation Agreement with Germany in 1975 - the public learned about them as a 'fait accompli'. In the late 70's, people started to hear about the delays in the commissioning of Angra 1 and the problems in the construction of the pile foundations of Angra 2. In 1980, following the TMI accident, the Federal Government issued a set of regulations dealing with emergency planning, the Federal and State Civil Defense being responsible for the preparation of the Off-Site Emergency Plan. FURNAS first public information campaign in 1982 dealt with emergency procedures and was directed to the Angra NPP employees and their families; local residents were visited by Civil Defense officials in 1983. At that time, the Brazilian Nuclear Program began to be criticized by concerned scientists and by the press, primarily due to its lack of transparency and its large scope. Safety issues arising from the TMI accident, lack of decision for the radioactive waste storage and problems with some equipment and components that delayed the commissioning of Angra 1, were pointed out as technical arguments against the construction of Angra 2 and 3. A new Constitution, 1988, required that a nuclear projects must be approved by the National Congress and put forward some new provisions for the environmental licensing of major industrial installations. The completion of Angra 2 was considered of the utmost importance by the Brazilian Nuclear Energy Association - ABEN, which is a technical-scientific body comprising employees from the various organizations that form the Brazilian Nuclear Sector. As an independent, non

  3. Flow accelerated corrosion programme in Angra nuclear power plants Units 1 and 2

    International Nuclear Information System (INIS)

    Costa, Tomas D.S.

    2009-01-01

    Almirante Alvaro Alberto Nuclear Power Plant, referred herein as Angra NPP, comprises two generating units operated by ELETROBRAS Termonuclear S.A. - ELETRONUCLEAR. Unit 1, a Westinghouse designed PWR, operates commercially since 1982 generating 657 MW, while unit 2, designed by Siemens, is a 1350 MW PWR in operation since 2000. Flow Accelerated Corrosion (FAC) programme integrate a set of ageing related programmes established to control ageing effects on equipment and piping in order to ensure their capability to perform their functions during the plant remaining life. The objective of this paper is to describe ELETRONUCLEAR experience in developing and implementing a programme related to Flow Accelerated Corrosion, with focus on piping of the secondary sides of Angra NPP, explaining in detail the current situation for important pipings, and presenting updated results of the FAC control. Accurate inspections are the basis for an effective FAC programme. Wall thickness measurements establish the extent of wear in a given piping, providing data to support FAC trends, and to refine the predictive model. A permanently and clearly identify grid is makes re-inspection possible, at any time, at the same points. Supported by the computational system Comsy, some of its features as FAC potentially susceptible lines identification, wall thinning rates determination, inspection data recording, wear rates analyses, lifetime prediction and inspection scheduling will be showed in detail. This programme has started in 2004, and since this time it was applied in a total of six outages in Angra 1 NPP and three outages in Angra 2 NPP, with a large number of piping elements inspected and analyzed. Some of these results will be showed and discussed in this paper, regarding the potential of Flow Accelerated Corrosion occurrence. (author)

  4. Alternatives and costs for the decommissioning of Angra Nuclear Power Plants

    International Nuclear Information System (INIS)

    Carajilescov, Pedro; Moreira, Joao Manoel Losada; Maiorino, Jose Rubens

    2013-01-01

    The decommissioning of a nuclear reactor requires several actions involving legal basis, decommissioning strategies, planning, dismantling, packing, transport and storage of a large volume of radioactive materials, qualified personnel and financial resources. The paper discusses the several aspects of these actions for the decommissioning of Angra nuclear Power Plants, based on the international experiences. The main phases of the decommissioning process, the Brazilian regulation and cost estimations are also presented. Finally, two alternatives for the decommissioning of the plants, based on logistic aspects, are discussed. (author)

  5. Alternatives and costs for the decommissioning of Angra Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Carajilescov, Pedro; Moreira, Joao Manoel Losada; Maiorino, Jose Rubens, E-mail: pedro.carajilescov@ufabc.edu.br [Universidade Federal do ABC (UFABC), Santo Andre, SP (Brazil)

    2013-07-01

    The decommissioning of a nuclear reactor requires several actions involving legal basis, decommissioning strategies, planning, dismantling, packing, transport and storage of a large volume of radioactive materials, qualified personnel and financial resources. The paper discusses the several aspects of these actions for the decommissioning of Angra nuclear Power Plants, based on the international experiences. The main phases of the decommissioning process, the Brazilian regulation and cost estimations are also presented. Finally, two alternatives for the decommissioning of the plants, based on logistic aspects, are discussed. (author)

  6. Determination of the safety zones of Angra dos Reis Nuclear Power Plant, according to the model of radion diffusion in the atmosphere

    International Nuclear Information System (INIS)

    Santina, M.D.

    1978-01-01

    The safety distance for Angra dos Reis Nuclear Power Plant are calculated, based on the model of the maximum credible accident for PWR power reactors and on the calculation of the dose due to hypothetical accidental release of radioactivity, using the model of radiation dispersion in the atmosphere. The safety distances for the Angra dos Reis reactors are also calculated using the model of the nine accident categories of the Rasmussen Report. The values of probability associated to each type of accident are used with the respective fractions of radiation release to the atmosphere. The soil contamination is also calculated for all the accidents considered and for several conditions of atmospheric stability, according to the model developed by Chamberlain. The program ACRA-II is used for calculation of the diffusion of radiation in the atmosphere, and the doses associated to it [pt

  7. Proposal of a dry storage installation in Angra NPP for spent nuclear fuel

    International Nuclear Information System (INIS)

    Romanato, Luiz S.; Rzyski, Barbara M.

    2009-01-01

    When nuclear fuel is removed from a power reactor core after the depletion of efficiency in generating energy is called Spent Nuclear Fuel (SNF). After its withdrawal from the reactor core, SNF is temporarily stored in pools usually at the same site of the reactor. During this time, short-living radioactive elements and generated heat undergo decay until levels that allow removing the SNF from the pool and sending it for reprocessing or a temporary storage whether any of its final destinations has not yet been defined. It can be loaded in casks and disposed during years in a dry storage installations until be sent to a reprocessing plant or deep repositories. Before any decision, reprocessing or disposal, the SNF needs to be safely and efficiently isolated in one of many types of storages that exist around the world. Worldwide, the amount of SNF increases annually and in the next years this amount will be higher as a consequence of new Nuclear Power Plants (NPP) construction. In Brazil, that is about to construct the Angra 3 nuclear power reactor, a project about the final destination of the SNF is not yet ready. This paper presents a proposal for a dry storage installation in the Angra NPP site since it can be an initial solution for the Brazilian's SNF, until a final decision is taken. (author)

  8. Strontium and calcium determination in sea fishes in neighborhood of Angra nuclear power plant

    International Nuclear Information System (INIS)

    Ferreira, L.M.J.

    1985-01-01

    Strontium-90 is an important radionuclide present in the liquid effluents of the Angra Nuclear Power Plant, located in the coastline of Rio de Janeiro State. It has a long effective half-life, easy entry into food chain due to its chemical similarity to calcium and stays for a long time in solution. With the aim of calculating the concentration factor (CF) for 90 Sr and observed ratio (OR) in the most abundant local fish, it was determined the strontium and calcium content in the edible fraction of nine species and in sea water by atomic absorption spectrophotometry. (author)

  9. Evaluation of the Angra-2 nuclear power plant using a RELAP5-PARCS coupled model

    Energy Technology Data Exchange (ETDEWEB)

    Reis, Patrícia A.L.; Hamers, Adolfo R.; Pereira, Claubia; Costa, Antonella L.; Veloso, Maria A.F.; Verdú, Gumersindo [Universidade Federal de Minas Gerais (UFMG), Belo Horizonte, MG (Brazil). Departamento de Engenharia Nuclear; Miró, Rafael, E-mail: antonella@nuclear.ufmg.br, E-mail: dora@nuclear.ufmg.br, E-mail: rmiro@iqn.upv.es, E-mail: gverdu@iqn.upv.es [Departamento de Ingenieria Quimica y Nuclear, Universidad Politécnica de Valencia (Spain)

    2017-07-01

    Studies of complex transients in nuclear reactors have been improved by the use of thermal hydraulic (TH) and neutron kinetics (NK) coupled codes. This technique consists in incorporating three-dimensional (3D) neutron modeling of the reactor core into codes to possibility simulation of transients that involve asymmetric core spatial power distributions and strong feedback effects between neutronic and reactor thermal hydraulics. In this work, steady state results using the verified model of TH RELAP5 code and the NK PARCS code to predict the Angra 2 reactor behavior have been presented. (author)

  10. Description of the local dose rate measuring system for the Angra 2 nuclear power plant

    International Nuclear Information System (INIS)

    Costa, Lilian Rose Sobral da; Souza Mendes, Jorge Eduardo de

    1995-01-01

    The equipment used and the measured value processing involved in the Local Dose Rate Measuring System is described including the installation points for the measuring equipment in the reactor building, the auxiliary building and at the main gate of Angra 2 Nuclear Power Plant. Under normal operating conditions protecting of the personnel is ensured by measuring the local dose rate at those points which are generally accessible. In some cases , fixed sensors are not suitable so that mobile equipment is used. (author). 2 refs., 1 fig

  11. 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.

  12. 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.

  13. Second periodic safety review of Angra Nuclear Power Station, unit 1

    Energy Technology Data Exchange (ETDEWEB)

    Martins, Carlos F.O.; Crepaldi, Roberto; Freire, Enio M., E-mail: ottoncf@tecnatom.com.br, E-mail: emfreire46@gmail.com, E-mail: robcrepaldi@hotmail.com [Tecnatom do Brasil Engenharia e Servicos Ltda, Rio de Janeiro, RJ (Brazil); Campello, Sergio A., E-mail: sacampe@eletronuclear.gov.br [Eletrobras Termonuclear S.A. (ELETRONUCLEAR), Rio de Janeiro, RJ (Brazil)

    2015-07-01

    This paper describes the second Periodic Safety Review (PSR2-A1) of Angra Nuclear Power Station, Unit 1, prepared by Eletrobras Eletronuclear S.A. and Tecnatom do Brasil Engenharia e Servicos Ltda., during Jul.2013-Aug.2014, covering the period of 2004-2013. The site, in Angra dos Reis-RJ, Brazil, comprises: Unit 1, (640 MWe, Westinghouse PWR, operating), Unit 2 (1300 MWe, KWU/Areva, operating) and Unit 3 (1405 MWe, KWU/Areva, construction). The PSR2-A1 attends the Standards 1.26-Safety in Operation of Nuclear Power Plants, Brazilian Nuclear Regulatory Commission (CNEN), and IAEA.SSG.25-Periodic Safety Review of Nuclear Power Plants. Within 18 months after each 10 years operation, the operating organization shall perform a plant safety review, to investigate the evolution consequences of safety code and standards, regarding: Plant design; structure, systems and components behavior; equipment qualification; plant ageing management; deterministic and probabilistic safety analysis; risk analysis; safety performance; operating experience; organization and administration; procedures; human factors; emergency planning; radiation protection and environmental radiological impacts. The Review included 6 Areas and 14 Safety Parameters, covered by 33 Evaluations.After document evaluations and discussions with plant staff, it was generated one General and 33 Specific Guide Procedures, 33 Specific and one Final Report, including: Description, Strengths, Deficiencies, Areas for Improvement and Conclusions. An Action Plan was prepared by Electronuclear for the recommendations. It was concluded that the Unit was operated within safety standards and will attend its designed operational lifetime, including possible life extensions. The Final Report was submitted to CNEN, as one requisite for renewal of the Unit Permanent Operation License. (author)

  14. Analysis of the emergency plan of Angra dos Reis Nuclear Power Plants: a critical view related to accessibility and mobility of people with special needs

    International Nuclear Information System (INIS)

    Correa, Luanda C.A.; Correa, Samanda C.A.; Santos, Geissa; Souza, Edmilson M.

    2014-01-01

    This work intends to make a critical analysis of the emergency plan of the Angra dos Reis Nuclear Power Plants related to appropriate transportation, accommodation and infrastructure for people with special needs

  15. Applied to neuro-fuzzy models for signal validation in Angra 1 nuclear power plant

    International Nuclear Information System (INIS)

    Oliveira, Mauro Vitor de

    1999-06-01

    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)

  16. Assessment of occupational radiation protection conditions during power enhancement of the Angra-2 nuclear power plant; Avaliacao das condicoes de radioprotecao ocupacional durante a elevacao de potencia na Unidade 2 da Central Nuclear Almirante Alvaro Alberto - Angra-2

    Energy Technology Data Exchange (ETDEWEB)

    Azevedo, Eduardo M.; Rocha, Antonio Carlos S.; Ferreira, Paulo R.R.; Mouco, Charles Dickens C.L.; Godoy, Jose M.O.; Matta, Luiz E.S.C. [Instituto de Radioprotecao e Dosimetria (IRD), Rio de Janeiro, RJ (Brazil)

    2001-07-01

    This paper intend to analyse the occupational radioprotection conditions of the Angra-2 nuclear power plant, from the startup up to reach 100% of the nominal power. To perform this work a group of dose rates measures was made including beta/gamma and neutron radiation, particulates and iodine monitoring, and surface contamination, during the whole process. These measures were made inside of the three main buildings: the reactor buildings (UJA - reactor core and UJB) and the Reactor Auxiliary Building (UKA). (author)

  17. The civil design of the Angra Nuclear power plant, units 2 and 3

    International Nuclear Information System (INIS)

    Zuegel, L.C.; Diaz, B.E.; Cunha, M.T.

    1988-01-01

    The civil design of the Angra Nuclear Power Plant, Units 2 and 3 represents an important step in the technological development of Brazil, correlated to high technology enterprises. This design was developed in Brazil, by Brazilian technicians, in a comprehensive way. In all individual and global phases of the design, a full participation of the Brazilian state and private companies has been observed. In order to proceed with the design in this way, a group of Nuclen engineers has stayed for a while in Germany, in KWU's office, for a proper training. The Brazilian design companies, on the other hand, have received a special consulting support given by engineers of German construction companies, especialized in nuclear power plant construction. For the nuclear civil design, as well as for the dynamic analyses and structural design of reinforced concrete and steel structures, the design job assumes an important position in the Brazilian technical experience. The structural design of the reinforced concrete structures of the nuclear power plant, for instance, is the largest one ever performed in Brazil in terms of difficulty, complexity and amount of man-hours expediture. A summary of the civil design steps will be described in this paper. (author) [pt

  18. Central nuclear almirante Alvaro Alberto: study on the phytoplanktonic variation in the region of unity 1 - Angra dos Reis - RJ

    International Nuclear Information System (INIS)

    Souza, C.A.F. de; Pessoa, M.A.R.; Utchitel, S.

    1988-01-01

    By according of ''staff'' which has elaborated the first works in phitoplankton, in initial phasis (before operation) of Central Nuclear Almirante Alvaro Alberto - CNAAA Unidade 1, Angra dos Reis, Rio de Janeiro, Brazil we carry out a search about physic - chemicals parameters at same area, during the times of 11 months, too. The efluent region presents a phytoplanktonic comunity of reasonable environmental conditions. The evaluation of biological parameters, or in the words, a natural environment in equilibrium. (author) [pt

  19. Air temperature determination inside residual heat removal pump room of Angra-1 nuclear power plant after a design basic accident

    International Nuclear Information System (INIS)

    Siniscalchi, Marcio Rezende

    2005-01-01

    This work develops heat transfer theoretical models for determination of air temperature inside the Residual Heat Removal Pump Room of Angra 1 Nuclear Power Plant after a Design Basis Accident without forced ventilation. Two models had been developed. The differential equations are solved by analytical methods. A software in FORTRAN language are developed for simulations of temperature inside rooms for different geometries and materials. (author)

  20. Analysis of the emergency plan of Angra dos Reis Nuclear Power Plants: a critical view related to accessibility and mobility of people with special needs; Analise do plano de emergencia da Central Nuclear de Angra dos Reis: uma visao critica com relacao a acessibilidade e mobilidade de pessoas com necessidades especiais

    Energy Technology Data Exchange (ETDEWEB)

    Correa, Luanda C.A., E-mail: luanda.correa@yahoo.com.br [Universidade Candido Mendes, Rio de Janeiro, RJ (Brazil); Correa, Samanda C.A., E-mail: scorrea@cnen.gov.br [Comissao Nacional de Energia Nuclear (CNEN), Rio de Janeiro, RJ (Brazil); Santos, Geissa; Souza, Edmilson M., E-mail: edmilsonsouza@uezo.rj.gov.br, E-mail: geissasantosnaval@gmail.com [Universidade Estadual da Zona Oeste (UEZO), Rio de Janeiro, RJ (Brazil)

    2014-07-01

    This work intends to make a critical analysis of the emergency plan of the Angra dos Reis Nuclear Power Plants related to appropriate transportation, accommodation and infrastructure for people with special needs.

  1. Impact assessment for the aquatic biota arising from discharges of radioactive liquid effluents into the marine environment - Angra dos Reis nuclear power plants

    International Nuclear Information System (INIS)

    Lauria, D.C.; Peres, S.S.; Martins, S.F.

    2011-01-01

    The Piraquara de Fora Bay receives the liquid effluents from the two Brazilian nuclear power plants (NPPs): Angra I that has been operating since 1985 and Angra II that started operating in 2000. The monitoring data set obtained by IRD/CNEN for marine samples over a period of 25 years (from 1985 to 2010) were statistically evaluated. Despite the high presence of non detect observations, suitable statistical tests were applied to compare 60 Co levels in sediments between two periods of time and from different sampling locations. The natural dose and the dose derived from the NPPs routine radioactive releases on the marine biota were assessed by the Erica tool. The highest value of dose rate due to the naturally occurrence radionuclides was estimated to be around 0.6 μGy h -1 for phytoplankton, mainly due to internal dose contribution of 238 U, while fishes received the highest dose (value around 0.4 μGy h -1 ) due to the radionuclide discharges of the NPPs. Accordingly, the dose rates to the studied species (fish, crustacean, macroalgae, zooplankton and phytoplankton) were clearly below the Erica screening level of 10 μGy h -1 , indicating no significant radiological impact of NPPs on these species. (author)

  2. Importance of benthonic marine flora monitoring in the liquid effluent discharge form Angra-1 Nuclear Power Plant

    International Nuclear Information System (INIS)

    Bloise, G.C.; Araujo Costa, D. de

    1994-01-01

    Angra-1 Nuclear Power Plant use sea water to condenser the steam of the secondary circuit. This water capted from Itaorna bay is chlorined and discharged more heater in Piraquara de Fora small bay. The temperature, chlorinade concentration, marine flora and fauna are monitored frequently with the intend of value the impact caused by this discharge to marine environment. The macroscopic marines algae is very sensible to environment temperature variations, constitutes on of the main rink in the food chain and stay every time attach at the bottom. Because of this facts they are considered an important bio indicators. (author). 5 refs, 2 figs, 2 tabs

  3. Contaminant dispersion simulation with micrometeorological parameters generated by LES in the area around the Angra Nuclear Power Plant

    Energy Technology Data Exchange (ETDEWEB)

    Dorado, Rodrigo M.; Moreira, Davidson M., E-mail: dorado.engenharia@yahoo.com.b, E-mail: davidson@pq.cnpq.b [Universidade Federal do Pampa (UNIPAMPA), Bage, RS (Brazil). Centro de Ciencias Exatas e Tecnologicas

    2009-07-01

    In this work we report a numerical and statistical comparison between ADMM (Advection-Diffusion Multilayer Method) and GILTT (Generalized Integral Laplace Transform Technique) approaches to simulate radioactive pollutant dispersion in the atmosphere using micrometeorological parameters generated by LES (Large Eddy Simulation). To a better description of the wind profile for the irregular ground level terrain, we consider the wind profile as solution of the MesoNH model. Furthermore, we show the aptness of the discussed methods to solve contaminant dispersion problem in the atmosphere for more realistic micrometeorological parameters and wind field considering experimental data of the Angra I Nuclear Power Plant. (author)

  4. Contaminant dispersion simulation with micrometeorological parameters generated by LES in the area around the Angra Nuclear Power Plant

    International Nuclear Information System (INIS)

    Dorado, Rodrigo M.; Moreira, Davidson M.

    2009-01-01

    In this work we report a numerical and statistical comparison between ADMM (Advection-Diffusion Multilayer Method) and GILTT (Generalized Integral Laplace Transform Technique) approaches to simulate radioactive pollutant dispersion in the atmosphere using micrometeorological parameters generated by LES (Large Eddy Simulation). To a better description of the wind profile for the irregular ground level terrain, we consider the wind profile as solution of the MesoNH model. Furthermore, we show the aptness of the discussed methods to solve contaminant dispersion problem in the atmosphere for more realistic micrometeorological parameters and wind field considering experimental data of the Angra I Nuclear Power Plant. (author)

  5. Climatologia no Entorno da Central Nuclear de Angra dos Reis, RJ

    Directory of Open Access Journals (Sweden)

    João Batista Araujo Figueiredo

    Full Text Available Resumo Este trabalho tem por objetivo caracterizar os ciclos diurno e sazonal médios no entorno da Central Nuclear de Angra dos Reis. As condições médias são derivadas de dados horários, do período de janeiro de 2005 a dezembro de 2012. O local conta com quatro torres A, B, C e D. A Torre A mede vento e temperatura do ar a 10, 60 e 100 m e também precipitação, enquanto as demais torres medem somente vento a 15 m de altura. A atmosfera apresenta condições predominantemente estáveis ao longo do dia, com redução a partir das 6 e 7 h, sendo que condições instáveis predominam entre às 8 e 16 h no verão e primavera. Os ventos da região são predominantemente fracos, a maior frequência ocorre nas intensidades entre 1,5 e 2 m/s. O mínimo de intensidade dos ventos a 10 m ocorre no momento da entrada da brisa marítima, às 9 h. Os ventos catabáticos produzem um forte cisalhamento vertical dos ventos na região. Nas demais torres a máxima intensidade ocorre entre 13 e 15 h local. Ventos mais intensos e chuvas mais intensas foram registrados no outono (MAM, o que sugere ser este o período de tempestades mais intensas.

  6. Expertise and participation of the population in the context of nuclear risk: democracy and environmental licensing of Angra 3 nuclear power plant

    Directory of Open Access Journals (Sweden)

    Gláucia Silva

    2010-01-01

    Full Text Available This article discusses the specificity of citizens' "participation" in contexts of decision-making on the acceptance of nuclear risk, demonstrating that such acceptance depends on mediation by professionals who are willing to translate the typical scientific jargon of technical reports and/or produce their own reports, by way of counter-expertise; otherwise, lay people are unable to confer scientific legitimacy to their arguments. The basic empirical references for the current analysis are the recurrent themes from public hearings organized for the licensing of two Brazilian nuclear power plants using German technology, Angra 2 and Angra 3, with emphasis on the latter, now undergoing prior environmental licensing. The forms of "social control" engendered in France serve as a counterpoint for developing the article's argument.

  7. Study of ultimate heat sink to Angra-1,2 and 3 Nuclear Power Plants

    International Nuclear Information System (INIS)

    Moreira, R.M.; Pinto, A.M.F.

    1985-03-01

    This report presents the premises, results and conclusion of study done to ultimate heat sink of Angra 1,2 and 3 units, with base in postulated accidents that generate transient heat discharges to environment. It's explicitily presumed the eventuality of discharging heat water recirculation. (C.M.) [pt

  8. Radiological risk curves for the liquid radioactive waste transfer from Angra 1 to Angra 2 nuclear power plants by a container tank

    International Nuclear Information System (INIS)

    Alves, A.S.M.; Passos, E.M. dos; Duarte, J.P.

    2013-01-01

    Eletrobras Termonuclear has a radiowaste management program focused on reducing the produced volumes, for which it has considered to transfer Angra 1 liquid radioactive waste by a container tank to be processed and packed in Angra 2. This paper presents a radiological risk study for providing the necessary technical foundations to obtain the license from the regulatory agency for implementing this transfer operation. Out of the 92 accident scenarios identified with the help of a preliminary hazard analysis, the greatest risk of fatal cancer for members of the public was equal to 6.9 x 10 -13 fatalities/yr, which refers to the accident scenario involving intrinsic failures of valves, hoses, flanges, seals, gaskets and instrumentation lines, while filling the container tank at Angra 1 filling station. This risk figure is about ten million times less than the one adopted by Eletronuclear for such a waste transfer. The highest frequency was also associated with this type of scenario, and its value was equal to 1.4 x 10 -6 yr -1 . This paper also presents and discusses the radiological risk curves for the three possible in-plant transfer routes, the Angra 1 filling station and Angra 2 discharging station and the overall risk curve in order to allow for a broader perspective of the results obtained. These risk curves display the accident scenarios frequencies against radiation doses by considering relevant in-plant and surroundings release paths. In these curves, the extreme scenarios mentioned earlier can be clearly identified in terms of occurrence frequencies and radiation doses. (author)

  9. Analysis of burnup of Angra 2 PWR nuclear with addition of thorium dioxide fuel using ORIGEN-ARP

    International Nuclear Information System (INIS)

    Goncalves, Isadora C.; Wichrowski, Caio C.; Oliveira, Claudio L. de; Vellozo, Sergio O.; Baptista, Camila O.

    2017-01-01

    It is known that isotope 232 thorium is a fertile nuclide with the ability to convert into 233 uranium, a potentially fissile isotope, after absorbing a neutron. As there is a large stock of available thorium in the world, this element shows great promise in mitigate the world energy crisis, more particularly in the problem of uranium scarcity, besides being an alternative nuclear fuel for those currently used in reactors, and yet presenting advantages as an option for the non-proliferation movement, among others. In this study, the analysis of the remaining nuclides of burnup was carried out for the core configuration of a PWR (pressurized water reactor) reactor, specifically the Angra 2 reactor, using only uranium dioxide, its current configuration, and in different configurations including a mixed oxide of uranium and thorium in three concentrations, allowing a preliminary assessment of the feasibility of the modification of the fuel, the resulting production of 233 uranium, the emergence of 231 protactinium (an isotope that only occurs as a fission product of 232 Th) resulting from burning. The study was carried out using data obtained from FSAR (Final Safety Analysis Report) of Angra 2, using the SCALE 6.1, a modeling and simulation nuclear code, especially its ORIGEN-ARP module, which analyzes the depletion of isotopes presents in a reactor. (author)

  10. Specification and qualification of fire detectors used in very high radiation rooms at the Angra-2 nuclear power plant

    Energy Technology Data Exchange (ETDEWEB)

    Sá, Luís Gustavo S.; Oliveira, Alisson S. de; Donorato, Fernando da S.; Oliveira, Marcos Vinicius M. de, E-mail: luisg@eletronuclear.gov.br, E-mail: alison@eletronuclear.gov.br, E-mail: donora@eletronuclear.gov.br, E-mail: marcoso@eletronuclear.gov.br [Eletrobrás Termonuclear S.A. (ELETRONUCLEAR), Angra dos Reis, RJ (Brazil). Departamento GDD.O

    2017-07-01

    During the Operation cycle 11 of the Angra-2 Nuclear Power Plant, faults were observed in the optical and ionic fire detectors models installed in very high radiation rooms (pump reactor rooms and sump containment). It was observed that these models were already obsolete and no available for purchase. In addition, as during the operation cycle these rooms are not accessible for maintenance because of the high dose rates, corrective measures only were taken at Outage 2P11 where all detectors were replaced by the new neural fire detector model. This high-tech model was not sufficiently resistant to the high dose rates of the environment rooms and starts to fail in the beginning of the cycle 11. Thereafter, a specific engineering work was developed in partnership with IPEN - Institute of Energy and Nuclear Research to specify and qualify a new model compatible with the electronic Central of the Fire Detection System and Alarm and at the same time resistant to radiation. The fire detectors were subjected to a known gamma radiation rate at the laboratory facilities of IPEN through the gamma irradiation equipment with cobalt radiation source. In this way, it was possible to determine its useful life comparing the total dose absorbed for detector failure and the environmental dose where it was installed in Angra-2. The current approved model was installed during Outage 2P13, and until now, no spurious alarms or failure were observed during the current cycle. (author)

  11. Specification and qualification of fire detectors used in very high radiation rooms at the Angra-2 nuclear power plant

    International Nuclear Information System (INIS)

    Sá, Luís Gustavo S.; Oliveira, Alisson S. de; Donorato, Fernando da S.; Oliveira, Marcos Vinicius M. de

    2017-01-01

    During the Operation cycle 11 of the Angra-2 Nuclear Power Plant, faults were observed in the optical and ionic fire detectors models installed in very high radiation rooms (pump reactor rooms and sump containment). It was observed that these models were already obsolete and no available for purchase. In addition, as during the operation cycle these rooms are not accessible for maintenance because of the high dose rates, corrective measures only were taken at Outage 2P11 where all detectors were replaced by the new neural fire detector model. This high-tech model was not sufficiently resistant to the high dose rates of the environment rooms and starts to fail in the beginning of the cycle 11. Thereafter, a specific engineering work was developed in partnership with IPEN - Institute of Energy and Nuclear Research to specify and qualify a new model compatible with the electronic Central of the Fire Detection System and Alarm and at the same time resistant to radiation. The fire detectors were subjected to a known gamma radiation rate at the laboratory facilities of IPEN through the gamma irradiation equipment with cobalt radiation source. In this way, it was possible to determine its useful life comparing the total dose absorbed for detector failure and the environmental dose where it was installed in Angra-2. The current approved model was installed during Outage 2P13, and until now, no spurious alarms or failure were observed during the current cycle. (author)

  12. Analysis of burnup of Angra 2 PWR nuclear with addition of thorium dioxide fuel using ORIGEN-ARP

    Energy Technology Data Exchange (ETDEWEB)

    Goncalves, Isadora C.; Wichrowski, Caio C.; Oliveira, Claudio L. de; Vellozo, Sergio O.; Baptista, Camila O., E-mail: isadora.goncalves@ime.eb.br, E-mail: wichrowski@ime.eb.br, E-mail: d7luiz@yahoo.com.br, E-mail: vellozo@ime.eb.br, E-mail: camila.oliv.baptista@gmail.com [Instituto Militar de Engenharia (IME), Rio de Janeiro, RJ (Brazil). Secao de Engenharia Nuclear

    2017-11-01

    It is known that isotope {sup 232}thorium is a fertile nuclide with the ability to convert into {sup 233}uranium, a potentially fissile isotope, after absorbing a neutron. As there is a large stock of available thorium in the world, this element shows great promise in mitigate the world energy crisis, more particularly in the problem of uranium scarcity, besides being an alternative nuclear fuel for those currently used in reactors, and yet presenting advantages as an option for the non-proliferation movement, among others. In this study, the analysis of the remaining nuclides of burnup was carried out for the core configuration of a PWR (pressurized water reactor) reactor, specifically the Angra 2 reactor, using only uranium dioxide, its current configuration, and in different configurations including a mixed oxide of uranium and thorium in three concentrations, allowing a preliminary assessment of the feasibility of the modification of the fuel, the resulting production of {sup 233}uranium, the emergence of {sup 231}protactinium (an isotope that only occurs as a fission product of {sup 232}Th) resulting from burning. The study was carried out using data obtained from FSAR (Final Safety Analysis Report) of Angra 2, using the SCALE 6.1, a modeling and simulation nuclear code, especially its ORIGEN-ARP module, which analyzes the depletion of isotopes presents in a reactor. (author)

  13. Environmental monitoring during the ten years of operation of the Almirante Alvaro Alberto nuclear power plant in Angra dos Reis

    International Nuclear Information System (INIS)

    Nicoli, I.G.; Vetere, M.I.; Guimaraes, J.R.; Nouailhetas, Y.; Godoy, J.M.

    1993-01-01

    The operational environmental monitoring program of the Almirante Alvaro Alberto nuclear power station is part of the national nuclear energy commission (CNEN). The program was established in 1982, at the same time as the power station became operational and approximately four years after the application of the pre-operational environmental monitoring. The program/Angra-1 was elaborated based on the gaseous and liquid effluents compositions and on identification of the principal potential radiation exposition of man. For liquids effluents ocean water, fish and man were identified as the critical targets for the radionuclide cesium-137. Another route was the deposition of radionuclides from ocean waters onto the region's beach sand, cobalt-60 and cobalt-58 were the critical radionuclides. For the gaseous effluents the main targets from radioactivity transport were air, soil, grass and milk, through which the iodine-131 would reach the man. Besides, in the program/Angra 1 were included the physical radiation characteristics and the direct exposition. the paper presents an overview of both PMAPO and PMAO programmes. (B.C.A.). 11 refs, 07 figs

  14. An assessment of the inventory of uranium consumption and HLW production by the Angra 2 Nuclear Power Plant using the VISTA program

    Energy Technology Data Exchange (ETDEWEB)

    Goncalves, Leticia C.; Moreira, Joao M. L.; Maiorino, Jose R., E-mail: goncalves.leticia@ufabc.edu.br [Universidade Federal do ABC (UFABC), Santo Andre, SP (Brazil). Centro de Engenharia, Modelagem e Ciencias Sociais Aplicadas

    2017-11-01

    This article presents an estimation of the inventory of spent nuclear fuel from Angra 2 accumulated over the years. We consider for that two situations: a) the once-through fuel cycle, and b) a cycle with partial reprocessing to recycle the fissile material. The results show that there are currently about 400 ton of spent fuel stored in Angra 2, and that its storage limit will be exhausted in the next 9 years. This is a worrying issue because, without the intention of reprocessing the fuel, and without the license to build a definitive repository, in less than a decade, Angra 2 would be required to cease its operation. This may not occur if some storage facility is built in the CNAAA site. It is hoped, therefore, that more work like this will is carried out to alert the competent authorities about the damage that will ensue if measures are not established in due time. (author)

  15. Aspects related to the interaction of Angra I with the Furnas system; Aspectos relativos a interacao de Angra I com o sistema Furnas

    Energy Technology Data Exchange (ETDEWEB)

    Silva, Lourenca Francisca da

    1982-10-15

    This work studies the following aspects related to the interaction of the Angra I power plant with the Furnas electric network: reliability of alternative sources, 500 kV and 138 kV systems and emergency diesel generators; operation capacity of Angra I and performance of Angra I and the future power plants Angra II and III. In the first part, after the Furnas network and the main systems of the Angra I power plant (specially the electrical system) have been analysed, the reliability for each source was computed separately and then the results lumped together. The reliability computation for the 500 kV system was done employing the computer code CST-ELETROSUL (reliability or transmission system) and for the remaining computations the fault tree theory was used, resulting in a number that represents the approximate value of the alternative sources, referring to the assumed considerations. In the second part, some limitations in the operation capacity of Angra I were verified, suggesting that the power plant should operate in base-load for safety reasons. In order to determine the factors that define the performance of a Nuclear Power Plant, FDIS, FCON, FINP and FIP, the works already accomplished by Centrais Eletricas Brasileiras S/A - ELETROBRAS were taken as a basis and were implemented with more recent data about operation of the nuclear power plant PWR. The computer code SPSS (Statistical Package for the Social Sciences) was utilized for obtaining the factors concerning to power plant with the capacity of Angra I, II and III. From the obtained valves and with the static generation capacity theory, were composed the load permanency curves from the unity 1 and for the three unities lumped together in the CNAA site. (author)

  16. Determination of maximum water temperature within the spent fuel pool of Angra Nuclear Power Plant - Unit 3

    Energy Technology Data Exchange (ETDEWEB)

    Werner, F.L., E-mail: fernanda.werner@poli.ufrj.br [Universidade Federal do Rio de Janeiro (UFRJ), RJ (Brazil). Departamento de Engenharia Nuclear; Alves, A.S.M., E-mail: asergi@eletronuclear.gov.br [Eletrobras Termonuclear (Eletronuclear), Rio de Janeiro, RJ (Brazil); Frutuoso e Melo, P.F., E-mail: frutuoso@nuclear.ufrj.br [Coordenacao de Pos-Graduacao e Pesquisa de Engenharia (COPPE/UFRJ), Rio de Janeiro, RJ (Brazil)

    2017-07-01

    In this paper, a mathematical model for the determination of the maximum water temperature within the spent fuel pool of Angra Nuclear Power Plant – Unit 3 was developed. The model was obtained from the boundary layer analysis and the application of Navier-Stokes equation to a vertical flat plate immersed in a water flow under free convection regime. Both types of pressure loss coefficients through the flow channel were considers in the modeling, the form coefficient for fuel assemblies (FAs) and the loss due to rod friction. The resulting equations enabled the determination of a mixed water temperature below the storage racks (High Density Storage Racks) as well as the estimation of a temperature gradient through the racks. The model was applied to the authorized operation of the plant (power operation, plant outage and upset condition) and faulted conditions (loss of coolant accidents and external events). The results obtained are in agreement with Brazilian and international standards. (author)

  17. Expert system applied at the Angra-2 Nuclear Power Plant to assist in the resolution of limiting conditions for operation

    Energy Technology Data Exchange (ETDEWEB)

    Schechter, André D.; Nicolau, Andressa S.; Schirru, Roberto, E-mail: schechterandre@poli.ufrj.br, E-mail: andressa@lmp.ufrj.br, E-mail: schirru@lmp.ufrj.br [Coordenacao de Pos-Graduacao e Pesquisa de Engenharia (COPPE/UFRJ), Rio de Janeiro, RJ (Brazil). Programa de Engenharia Nuclear

    2017-07-01

    Expert Systems (ES) are widely used to help a common user act as an expert on a particular subject, the information is saved in the program database and the user introduces facts to be interpreted in real time. The inference engine will take these facts and return the answer of the expert. This tool is widely used, for example, in medicine to diagnose patients, game development, the mining industry, and the operation of nuclear power plants. In this article, a model of ES, of the real time, is development in order to treat the Limiting Conditions for Operation (LCO) of the Angra-2 Nuclear Power Plant. In this PWR plant, all information from the LCO comes from failure trees and the ES was adapted to be able to handle the facts with the values True, False, None and Null of the tree. The simulations results of this article and experiments with ES applied in LCOs show that it is an efficient computational tool to deal with this type of problem. The use of this type of technology in the operation of nuclear power plants can reduce the risk of an accident caused by human error, which is one of the most common causes in the history of the nuclear industry. (author)

  18. Expert system applied at the Angra-2 Nuclear Power Plant to assist in the resolution of limiting conditions for operation

    International Nuclear Information System (INIS)

    Schechter, André D.; Nicolau, Andressa S.; Schirru, Roberto

    2017-01-01

    Expert Systems (ES) are widely used to help a common user act as an expert on a particular subject, the information is saved in the program database and the user introduces facts to be interpreted in real time. The inference engine will take these facts and return the answer of the expert. This tool is widely used, for example, in medicine to diagnose patients, game development, the mining industry, and the operation of nuclear power plants. In this article, a model of ES, of the real time, is development in order to treat the Limiting Conditions for Operation (LCO) of the Angra-2 Nuclear Power Plant. In this PWR plant, all information from the LCO comes from failure trees and the ES was adapted to be able to handle the facts with the values True, False, None and Null of the tree. The simulations results of this article and experiments with ES applied in LCOs show that it is an efficient computational tool to deal with this type of problem. The use of this type of technology in the operation of nuclear power plants can reduce the risk of an accident caused by human error, which is one of the most common causes in the history of the nuclear industry. (author)

  19. Aspects related to the interaction of Angra I with the Furnas system

    International Nuclear Information System (INIS)

    Silva, Lourenca Francisca da

    1982-10-01

    This work studies the following aspects related to the interaction of the Angra I power plant with the Furnas electric network: reliability of alternative sources, 500 kV and 138 kV systems and emergency diesel generators; operation capacity of Angra I and performance of Angra I and the future power plants Angra II and III. In the first part, after the Furnas network and the main systems of the Angra I power plant (specially the electrical system) have been analysed, the reliability for each source was computed separately and then the results lumped together. The reliability computation for the 500 kV system was done employing the computer code CST-ELETROSUL (reliability or transmission system) and for the remaining computations the fault tree theory was used, resulting in a number that represents the approximate value of the alternative sources, referring to the assumed considerations. In the second part, some limitations in the operation capacity of Angra I were verified, suggesting that the power plant should operate in base-load for safety reasons. In order to determine the factors that define the performance of a Nuclear Power Plant, FDIS, FCON, FINP and FIP, the works already accomplished by Centrais Eletricas Brasileiras S/A - ELETROBRAS were taken as a basis and were implemented with more recent data about operation of the nuclear power plant PWR. The computer code SPSS (Statistical Package for the Social Sciences) was utilized for obtaining the factors concerning to power plant with the capacity of Angra I, II and III. From the obtained valves and with the static generation capacity theory, were composed the load permanency curves from the unity 1 and for the three unities lumped together in the CNAA site. (author)

  20. Ichthyofauna community from Saco de Piraquara de Fora area by the influence of liquid effluents from the Almirante Alvaro Alberto Nuclear Power in Angra dos Reis

    International Nuclear Information System (INIS)

    Almeida, A.F.V. de

    1995-01-01

    To verify if thermal and chemical effluents of Angra I Nuclear Power Plant are affecting the marine ictiofauna, Furnas Centrais Eletricas S.A. has implemented a monitoring program near the discharge area. Specific composition, frequency, specific relative abundance, specific diversity and others parameters are studied. The main target of this study is to check if the analyzed parametrers show any kind of impact on fish population. In this paper the results were presented. (author). 7 refs, 3 figs, 3 tabs

  1. Temperature distribution in the Piraquara de Fora Bay resulting from residual heat liberation of the Angra-1 Nuclear Power Plant in Angra dos Reis, RJ, Brazil and its possible ecological effects

    International Nuclear Information System (INIS)

    Mota Singer, E. da.

    1979-01-01

    A preliminary evaluation was done of the potential environmental consequences derived from the emission from the condenser cooling of the nuclear power plants at the Angra dos Reis site. The calculation of the temperature field starting from the point of emission of the coolant discharge was done using the model of Stolzenbach for three dimensional heated surface discharge. Considerations were made of the potential environmental damage to the marine life based on the calculated temperature increase. Special atention was given to the potential damage to the necton's life, by estimating the probability of occurance of higher than lethal temperature for the known species living at the site. These species were given in the Safety Analysis Report of the Unity I of the nuclear station. (Author) [pt

  2. Acoustoelastic evaluation of the 20 MnMoNi 55 structural material of the pressure vessels of Angra 2 and 3 nuclear reactors

    International Nuclear Information System (INIS)

    Dutra, Marco Aurelio Monteiro

    2009-01-01

    The pressure vessels of the Angra II and Angra III nuclear power plants, which are of large thickness, have as one of their structural components the 20 MnMo Ni 55 steel. The acoustoelastic evaluation carried out through non-destructive ultrasonic tests was based on the variation of the speed of ultrasonic shear waves of normal incidence as a function of the stress applied in the material using the acoustic birefringence technique, which considers the fractional difference of the speeds of two ultrasonic waves propagating in orthogonal directions. In this work two experiments were carried out. In the first one, a new method for acquisition of ultrasonic signals for joint application with this technique of stress analysis was evaluated by comparison with the conventional one. The aim was to determine its potential and limitations for application in materials up to 120 mm of thickness. In the second experiment, the acoustoelastic behavior of the 20 MnMo Ni 55 steel was studied. The new method of acquiring ultrasonic signals led to satisfactory results and was used in the study of the acoustoelastic behavior of the 20 MnMoNi 55 steel. The acoustoelastic analysis indicated that the material has an anisotropic and heterogeneous behavior. The acoustoelastic constant of this material, obtained experimentally from the analysis of the graphs of the material behavior (birefringence x stress) under compression tests performed on specimens of the 20 MnMo Ni 55 steel, was used for the quantitative stress analysis. A specimen of the 20 MnMo Ni 55 steel was subjected to a bending test to carry out a qualitative stress analysis through the difference between the values of the birefringence obtained during loading (B) and before loading (Bo) in every point studied. With the obtained results it was possible to identify qualitative and quantitatively the regions of the specimen under compressive and tensile stresses. The execution of these tests allowed to verify the efficiency of

  3. Simplified methodology for Angra 1 containment analysis

    International Nuclear Information System (INIS)

    Neves Conti, T. das; Souza, A.L. de; Sabundjian, G.

    1991-08-01

    A simplified methodology of analysis was developed to simulate a Large Break Loss of Coolant Accident in the Angra 1 Nuclear Power Station. Using the RELAP5/MOD1, RELAP4/MOD5 and CONTEMPT-LT Codes, the time variation of pressure and temperature in the containment was analysed. The obtained data was compared with the Angra 1 Final Safety Analysis Report, and too those calculated by a Detailed Model. The results obtained by this new methodology such as the small computational time of simulation, were satisfactory when getting the preliminary evaluation of the Angra 1 global parameters. (author)

  4. From Angra to Tehran: Brazilian nuclear policy under Lula’s administration

    Directory of Open Access Journals (Sweden)

    Diego Santos Vieira de JESUS

    2011-11-01

    Full Text Available The aim of this article is to explain the positions taken by Brazil under Lula’s administration (2003-2010 on nuclear non-proliferation, disarmament and arms control. In order to strengthen its position in dispute settlement and to expand its participation in international institutions, Brazil wished to intermediate between nuclear-weapon and non-nuclear weapon States. The country also tried to pressure the nuclear weapon States to fulfill their disarmament obligations and to reduce asymmetries in relations with the strongest countries in the nuclear arena. The Brazilians also sought to maintain flexibility to ensure the safety of their own atomic program.

  5. Simulation of a postulated loss of coolant accident due to a break in the pressurizer surge line of Angra 2 Nuclear Power Plan; Calculo do acidente postulado de perda de refrigerante por uma ruptura na linha de surto do pressurizador da central nuclear Angra 2

    Energy Technology Data Exchange (ETDEWEB)

    Azevedo, Carlos V. Goulart de; Palmieri, Elcio T.; Aronne, Ivan D. [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN), Belo Horizonte, MG (Brazil)]. E-mail: cvga@cdtn.br; etp@cdtn.br; aroneid@cdtn.br

    2005-07-01

    This work presents the simulation of a postulated loss of coolant accident due to a 437 cm{sup 2} break in the pressurizer surge line of Angra 2 Nuclear Power Plant, as described in its Final Safety Analysis Report, section 15.6.4.1.3.11. This accident is characterized by a fast depressurization of the reactor coolant system followed by the actuation of the safety injection system. This work, which aims to develop and qualify a basic Angra 2 nodalization for RELAP5, was done in the framework of a CNEN internal technical cooperation involving three of its research centers (CDTN, IPEN and IEN) and its Reactors Division. This simulation is part of a comprehensive number of accidents and transients necessary to verify the adequacy of the modeled logic of the control and protection systems as well as the performance of the modeled thermal-hydraulic systems. Therefore this work contributes to the qualification process of the developed nodalization. (author)

  6. Study on the marine fouling communities near Central Nuclear Almirante Alvaro Alberto (CNAAA), Angra dos Reis, R.J. (Brazil)

    International Nuclear Information System (INIS)

    Nunes, A.J.B.

    1983-01-01

    The effects of chemical and thermal effluents from CNAAA (Angra 1 Reactor) on local biota are studied. The seasonal variations and the ecologic aspects are presented and the biota is used as pollution indicator. The biota taxonomic study is desctibed. (M.A.C.) [pt

  7. 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)

  8. The evolution and improvements of the external emergency plans of Angra dos Reis nuclear power plant

    Energy Technology Data Exchange (ETDEWEB)

    Goes, Alexandre Gromann de; Araujo, Jefferson Borges, E-mail: gromann@cnen.gov.br, E-mail: jeferson@cnen.gov.br [Comissao Nacional de Energia Nuclear (CNEN/CGRC), Rio de Janeiro, RJ (Brazil). Coordenacao Geral de Reatores e do Ciclo Combustivel

    2015-07-01

    The scenery that now has been configuring in the area of science and nuclear technology in the society, with their obstacles and their evolution tendencies, their philosophical discussions around fundamental concepts, and the necessity to evolve the capacity in emergency response is described in this paper. Some obstacles related to the acceptance of the nuclear energy are mentioned and some proposed strategies are also presented, as well as, specific politics for the analyzed case. One can conclude that it is imperative, that the opinion and public perception of the risk, associated with radioactive facilities should be considered and that the debate continues involving legislators, operators and the public in general. (author)

  9. The evolution and improvements of the external emergency plans of Angra dos Reis nuclear power plant

    International Nuclear Information System (INIS)

    Goes, Alexandre Gromann de; Araujo, Jefferson Borges

    2015-01-01

    The scenery that now has been configuring in the area of science and nuclear technology in the society, with their obstacles and their evolution tendencies, their philosophical discussions around fundamental concepts, and the necessity to evolve the capacity in emergency response is described in this paper. Some obstacles related to the acceptance of the nuclear energy are mentioned and some proposed strategies are also presented, as well as, specific politics for the analyzed case. One can conclude that it is imperative, that the opinion and public perception of the risk, associated with radioactive facilities should be considered and that the debate continues involving legislators, operators and the public in general. (author)

  10. Analysis of the loss of coolant accident due to the faiture in the open position of two pressurizer relief valves, for Angra-1 nuclear power plant

    International Nuclear Information System (INIS)

    Freire, C.F.

    1981-06-01

    A study of the modeling techniques adequate for simulating the loss of coolant accident caused by stuck open pressurizer relief valves, using the RELAP4-MOD5 code, is performed and the model developed is applied to the analysis of this kind of accident for the Central Nuclear Almirante Alvaro Alberto Unit (Angra 1). The thermal hydraulic behavior of the reactor cooling system, when subjected to a loss of main feedwater followed by the failure in the open position of two pressurizer relief valves, is determined. The relief valves are assumed to fail in the totally open position, delivering the maximum massflow through the discharge line. The RELAP4-MOD5 code is shown to be adequate for this kind of analysis, and the detailed prediction of the thermal hydraulic behavior of the Reactor Coolant System is thus possible. The eficiency of the emergency core cooling system of Angra 1 is demonstrated, the fuel elements remaining covered by the coolant during all the accident, and the peak clad temperatures are kept within design limites, ensuring the integrity of the core. (Author) [pt

  11. ANGRA 2 Commissioning and first two cycles

    International Nuclear Information System (INIS)

    Thome Filho, Zieli Dutra; Mathias, Sergio Goncalves

    2003-01-01

    After 20 years of delay caused by unavailability of financial resources, a final 'go ahead' for the construction of the German-design Angra 2 Nuclear Power Plant was given to the Brazilian utility Electronuclear, also responsible for the operation of the first nuclear power plant in the country (Angra 1). A concerted effort from Electronuclear and the companies involved in the project, engineering and construction allowed the plant to start its operational tests in July 21, 2000 and commercial operation on February 1, 2001. Angra 2's operational record has since then been excellent, and the plant has contributed to overcome a serious electrical energy shortage which occurred in 2001 and affected most of the country and, in particular, the Rio de Janeiro state, where the plant is located (author)

  12. An overview of acceptance and knowledge of Angra dos Reis city about the operation of the nuclear power plants considering the associated risks and benefits

    International Nuclear Information System (INIS)

    Araujo, Jefferson Borges; Delcourt, Jules H.

    2015-01-01

    The use of nuclear power plants for electricity supply is presently considered as an important factor to be considered in any energy matrix to ensure the diversification and availability criteria. Currently several countries resumed or started programs for the construction of nuclear power plants of new projects, with extremely improved security levels. Additionally, events and accidents in nuclear power plants have contributed substantially to the occurrence of design modifications and/or update the regulatory requirements to further enhance operational safety of these plants. Nowadays, one of the regulatory requirements necessary for the selection of a site for construction and operation of nuclear installations is the public hearing and discussion. The city of Angra dos Reis has two nuclear power plants in operation and a third one under construction. There are also, plans for the construction of more nuclear power plants in the country, to meet the growing demand for electricity. The first nuclear power plant in Brazil went into operation in 1983 and the second in 2000. The selection of the site for construction of these plants was due to political, economic and strategic factors, present in Brazil, in the decade of 70. The licensing process in de 70's decade did not involve an extensive participation of the society as a whole and of the local population, such as the occurrence of public hearings and the wide possibility for discussion and debate about the acceptance of the location of the plant. In the initial years of operation of the Angra 1 nuclear power plant, the level of knowledge of the local population was practically null, occurring mainly in local clarifications, made through seminars and lectures on special occasions, such as at the time of the annual exercises of the external emergency plan, specific information Programs or technical visits of educational institutions and the Government to Angra dos Reis Nuclear power plant. Since the

  13. An overview of acceptance and knowledge of Angra dos Reis city about the operation of the nuclear power plants considering the associated risks and benefits

    Energy Technology Data Exchange (ETDEWEB)

    Araujo, Jefferson Borges, E-mail: jeferson@cnen.gov.br [Comissao Nacional de Energia Nuclear (CNEN/CGRC), Rio de Janeiro, RJ (Brazil). Coordenacao Geral de Reatores e do Ciclo Combustivel; Ribeiro, Katia Maria Bruno; Medice Junior, Fabio, E-mail: Katiapsi.67@gmail.com [Universidade Estacio de Sa (UNESA), Angra dos Reis, RJ (Brazil); Delcourt, Jules H., E-mail: juleshd@gmail.com [Colegio Naval, Angra dos Reis, RJ (Brazil)

    2015-07-01

    The use of nuclear power plants for electricity supply is presently considered as an important factor to be considered in any energy matrix to ensure the diversification and availability criteria. Currently several countries resumed or started programs for the construction of nuclear power plants of new projects, with extremely improved security levels. Additionally, events and accidents in nuclear power plants have contributed substantially to the occurrence of design modifications and/or update the regulatory requirements to further enhance operational safety of these plants. Nowadays, one of the regulatory requirements necessary for the selection of a site for construction and operation of nuclear installations is the public hearing and discussion. The city of Angra dos Reis has two nuclear power plants in operation and a third one under construction. There are also, plans for the construction of more nuclear power plants in the country, to meet the growing demand for electricity. The first nuclear power plant in Brazil went into operation in 1983 and the second in 2000. The selection of the site for construction of these plants was due to political, economic and strategic factors, present in Brazil, in the decade of 70. The licensing process in de 70's decade did not involve an extensive participation of the society as a whole and of the local population, such as the occurrence of public hearings and the wide possibility for discussion and debate about the acceptance of the location of the plant. In the initial years of operation of the Angra 1 nuclear power plant, the level of knowledge of the local population was practically null, occurring mainly in local clarifications, made through seminars and lectures on special occasions, such as at the time of the annual exercises of the external emergency plan, specific information Programs or technical visits of educational institutions and the Government to Angra dos Reis Nuclear power plant. Since the

  14. Nuclear physics II

    International Nuclear Information System (INIS)

    Elze, T.

    1988-01-01

    This script consisting of two parts contains the matter of the courses Nuclear Pyhsics I and II, as they were presented in the winter term 1987/88 and summer term 1988 for students of physics at Frankfurt University. In the present part II the matter of the summer term is summarized. (orig.) [de

  15. 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

  16. Angra-1: Balance of an experience

    International Nuclear Information System (INIS)

    Salvo Brito, S. de

    1985-01-01

    An evaluation of experience got during the construction of Angra-1 nuclear power plant which had built by FURNAS CENTRAIS ELETRICAS S.A. is done. It is analyzed the problems in level of management, including technology transfer. A balance of the real costs and benefits from the definition of the specifications to energy generation is done. (M.C.K.) [pt

  17. Integrity evaluation of the pressure vessels of Angra-2 and Angra-3 reactors by stress analysis

    International Nuclear Information System (INIS)

    Gomes, E.

    1978-01-01

    The integrity of the reactor pressure vessel of the unit II/III of the Nuclear Power Station at 'Angras do Reis' is evaluated by stress analysis, through the dynamics relaxation method. For the solution of the problem an axisymmetric model is fixed. Initially, the data of the Oak Ridge Vessel V-7 is compared with those obtained by two computer programs used in this study. The methods used in the computer programs are FEM and DEM. A11 the results are compared with the ASME Code Section III 1974 edition. The range deviation is determined to 99% confidence limit, in order to minimize the error probabilities. Finally, the equivalent intensity stress obtained is calculated and compared with the acceptable values of the ASME Code Section III, 1974 edition [pt

  18. Simplified methodology for analysis of Angra-1 containing

    International Nuclear Information System (INIS)

    Neves Conti, T. das; Souza, A.L. de; Sabundjian, G.

    1988-01-01

    A simplified methodology of analysis was developed to simulate a Large Break Loss of Coolant Accident in the Angra 1 Nuclear Power Station. Using the RELAP5/MOD1, RELAP4/MOD5 and CONTEMPT-LT Codes, the time the variation of pressure and temperature in the containment was analysed. The obtained data was compared with the Angra 1 Final Safety Analysis Report, and too those calculated by a Detailed Model. The results obtained by this new methodology such as the small computational time of simulation, were satisfactory when getting the preliminar avaliation of the Angra 1 global parameters. (author) [pt

  19. Power distribution and hot channel factor used in Angra 1 (W) and Angra 2,3 (KWU)

    International Nuclear Information System (INIS)

    Fufier, E.B.

    1981-01-01

    In this report, the definition of hot channel factors and sub-factors used to quantify and qualify the nuclear power distribution and the thermal hydraulic performance of the core for KWU reactor (Angra 2 and 3) and Westinghouse (Angra 1), are presented. Some observations and comparisons are made in relation to the more important differences between criteria and models used in the determination of thermal hydraulic parameters. (author0 [pt

  20. Dispersion modeling of atmospheric contaminants in the Angra Nuclear Power Plant using LES and a new model for the CBL growth

    Energy Technology Data Exchange (ETDEWEB)

    Moreira, Davidson M.; Goulart, Antonio G., E-mail: davidson@pq.cnpq.b, E-mail: agoulart@pq.cnpq.b [Universidade Federal do Pampa (UNIPAMPA), Bage, RS (Brazil); Soares, Pedro M., E-mail: pmsoares@fc.ul.p [Universidade de Lisboa (Portugal). Centro de Geofisica; Vilhena, Marco T., E-mail: vilhena@pq.cnpq.b [Universidade Federal do Rio Grande do Sul (UFRGS), Porto Alegre, RS (Brazil). Programa de Pos-Graduacao em Engenharia Mecanica

    2009-07-01

    In the present work we report a comparison between experimental data and GILTT approach to simulate radioactive contaminant dispersion in the Atmospheric Boundary Layer using micrometeorological parameters generated by LES (Large Eddy Simulation) in the area around the Angra dos Reis Nuclear Power Plant. Furthermore, starting from the evolution equation for the turbulent energy density spectrum (EDS), we develop a new model for the growth of the turbulence in Convective Boundary Layer (CBL). We apply dimensional analysis to parameterize the unknown inertial transport and convective source term in the dynamic equation for the three-dimensional (3-D) spectrum. The non linear integro-differential equation is solved by Adomian decomposition method. The one-dimensional vertical spectrum is derived from the 3-D spectrum, employing a weight function. This allows us to select the magnitude of the vertical spectral component for the construction of the growing 3-D. Using the micrometeorological parameters generated by LES, for the first time, we employ the vertical component of the energy spectrum to calculate the eddy diffusivity (required in dispersion models). This new eddy diffusivity is used in the simulations of the ground-level concentrations considering experimental data of the Nuclear Power Plant. (author)

  1. Dispersion modeling of atmospheric contaminants in the Angra Nuclear Power Plant using LES and a new model for the CBL growth

    International Nuclear Information System (INIS)

    Moreira, Davidson M.; Goulart, Antonio G.; Soares, Pedro M.; Vilhena, Marco T.

    2009-01-01

    In the present work we report a comparison between experimental data and GILTT approach to simulate radioactive contaminant dispersion in the Atmospheric Boundary Layer using micrometeorological parameters generated by LES (Large Eddy Simulation) in the area around the Angra dos Reis Nuclear Power Plant. Furthermore, starting from the evolution equation for the turbulent energy density spectrum (EDS), we develop a new model for the growth of the turbulence in Convective Boundary Layer (CBL). We apply dimensional analysis to parameterize the unknown inertial transport and convective source term in the dynamic equation for the three-dimensional (3-D) spectrum. The non linear integro-differential equation is solved by Adomian decomposition method. The one-dimensional vertical spectrum is derived from the 3-D spectrum, employing a weight function. This allows us to select the magnitude of the vertical spectral component for the construction of the growing 3-D. Using the micrometeorological parameters generated by LES, for the first time, we employ the vertical component of the energy spectrum to calculate the eddy diffusivity (required in dispersion models). This new eddy diffusivity is used in the simulations of the ground-level concentrations considering experimental data of the Nuclear Power Plant. (author)

  2. Accident diagnosis of the Angra-2 nuclear power plant based on intelligent real-time acquisition agents and a logical tree model

    International Nuclear Information System (INIS)

    Paiva, Gustavo V.; Schirru, Roberto

    2017-01-01

    This work aims to create a model and a prototype, using the Python language, which with the application of an Expert System uses production rules to analyze the data obtained in real time from the plant and help the operator to identify the occurrence of transients / accidents. In the event of a transient, the program alerts the operator and indicates which section of the Operation Manual should be consulted to bring the plant back to its normal state. The generic structure used to represent the knowledge of the Expert System was a Fault Tree and the data obtained from the plant was done through intelligent acquisition agents that transform the data obtained from the plant into Boolean values used in the Fault Tree, including the use of Fuzzy Logic. In order to test the program, a simplified model of the Almirante Alvaro Alberto 2 Nuclear Power Plant (Angra-2) manuals was used and with this model, simulations were performed to analyze the program's operation and if it leads to the expected results. The results of the tests presented a quick identification of the events and great accuracy, demonstrating the applicability of the model to the problem. (author)

  3. Accident diagnosis of the Angra-2 nuclear power plant based on intelligent real-time acquisition agents and a logical tree model

    Energy Technology Data Exchange (ETDEWEB)

    Paiva, Gustavo V.; Schirru, Roberto, E-mail: gustavopaiva@poli.ufrj.br, E-mail: schirru@lmp.ufrj.br [Coordenacao de Pos-Graduacao e Pesquisa de Engenharia (COPPE/UFRJ), Rio de Janeiro, RJ (Brazil). Departamento de Engenharia Nuclear

    2017-07-01

    This work aims to create a model and a prototype, using the Python language, which with the application of an Expert System uses production rules to analyze the data obtained in real time from the plant and help the operator to identify the occurrence of transients / accidents. In the event of a transient, the program alerts the operator and indicates which section of the Operation Manual should be consulted to bring the plant back to its normal state. The generic structure used to represent the knowledge of the Expert System was a Fault Tree and the data obtained from the plant was done through intelligent acquisition agents that transform the data obtained from the plant into Boolean values used in the Fault Tree, including the use of Fuzzy Logic. In order to test the program, a simplified model of the Almirante Alvaro Alberto 2 Nuclear Power Plant (Angra-2) manuals was used and with this model, simulations were performed to analyze the program's operation and if it leads to the expected results. The results of the tests presented a quick identification of the events and great accuracy, demonstrating the applicability of the model to the problem. (author)

  4. Assessment of impact of a severe accident at nuclear power plant of Angra dos Reis with release of radionuclides to the atmosphere

    International Nuclear Information System (INIS)

    Aguiar, Andre Silva de

    2015-01-01

    This study had as purpose the assess the impact of a severe accident, and also analyze the dispersion of 131 I in the atmosphere, so that, through concentrating and inhaling dose of the plume, were possible to verify if the results are in accordance with the indicated data by the Plan of Emergency of the CNAAA regarding the Impact Zone and Control. This exercise was performed with the aid of an atmospheric model and a dispersion where to atmospheric modeling we used the data coupling WRF / CALMET and of dispersion, CALPUFF. The suggested accident consists of a Station Blackout at Nuclear Power of Angra (Unit 1), where through the total core involvement, will release 100% of the 131 I to the atmosphere. The value of the total activity in the nucleus to this radionuclide is 7.44 x 1017 Bq, that is relative on the sixth day of burning. This activity will be released through the chimney at a rate in Bq/s in the scenario of 12, 24, 48 and 72 hours of release. Applying the model in the proposed scenario, it is verified that the plume has concentrations of the order of 1020 Bq/m³ and dose of about 108 Sv whose value is beyond of the presented by Eletronuclear in your current emergency plan. (author)

  5. An economic analysis of stretch-out for Angra-1 reactor

    International Nuclear Information System (INIS)

    Sakai, M.

    1989-01-01

    An application of NUCOST code for calculating nuclear energy cost is presented. Ann optimization of stretch-out for Angra-1 reactor based on international costs of nuclear fuel, operation and maintenance is done. (M.C.K.)

  6. Evaluation of Iodine-131 dispersion after accident in Nuclear Angra Power Plant using the model of aquatic dispersion, SisBahia

    International Nuclear Information System (INIS)

    Aguiar, Andre Silva de; Alvim, Antonio Carlos Marques

    2014-01-01

    It was inserted, in the cooling system of the nucleus, a LOCA, where 431 m 3 of coolant was lost. Such an inventory contained 3,04 x 10 10 Bq / m 3 and iodine was released near the beach Itaorna, Angra dos Reis - RJ. Applying the model in the proposed scenario (Angra 1 and Angra 2 in operation and 3 in with varying capture and discharge with the discharge gradually reduced after the accident), the dilution of the specific activity of radionuclides reached lower values after 22 hours, the reference levels for seawater 131 I (7,40 x 10 2 Bq / m 3 ). After 54 hours, levels of the radionuclide, in the area of indirect influence, are already below minimum activity values detected by the laboratory for environmental monitoring of the CNAAA (5,0 x 10 1 Bq / m 3

  7. 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)

  8. Desde Angra hacia Teherán: la política nuclear brasileña bajo la administración Lula From Angra to Tehran: Brazilian nuclear policy under Lula’s administration

    Directory of Open Access Journals (Sweden)

    Diego Santos Vieira de JESUS

    2011-11-01

    Full Text Available El objetivo de este artículo es explicar las posiciones adoptadas por Brasil bajo la administración Lula (2003-2010 sobre la no proliferación, el desarme y el control de las armas nucleares. Con el objetivo de reforzar su posición de solucionador de controversias y ampliar su participación en las instituciones internacionales, Brasil deseó intermediar entre los Estados que contaban con armas nucleares así como también aquellos que no las tenían. Además, intentó presionar a los Estados con armas nucleares por el cumplimiento de sus obligaciones de desarme y por la reducción de las asimetrías en sus relaciones con los países más fuertes en el ámbito nuclear. Los brasileños también buscaron mantener la flexibilidad para garantizar la seguridad de su propio programa atómico.The aim of this article is to explain the positions taken by Brazil under Lula’s administration (2003-2010 on nuclear non-proliferation, disarmament and arms control. In order to strengthen its position in dispute settlement and to expand its participation in international institutions, Brazil wished to intermediate between nuclear-weapon and non-nuclear weapon States. The country also tried to pressure the nuclear weapon States to fulfill their disarmament obligations and to reduce asymmetries in relations with the strongest countries in the nuclear arena. The Brazilians also sought to maintain flexibility to ensure the safety of their own atomic program.

  9. Adjustments in the Almod 3W2 code models for reproducing the net load trip test in Angra I nuclear power plant

    International Nuclear Information System (INIS)

    Camargo, C.T.M.; Madeira, A.A.; Pontedeiro, A.C.; Dominguez, L.

    1986-09-01

    The recorded traces got from the net load trip test in Angra I NPP yelded the oportunity to make fine adjustments in the ALMOD 3W2 code models. The changes are described and the results are compared against plant real data. (Author) [pt

  10. Lagrangian modeling of atmospheric dispersion of radionuclides and geographical information systems as tools to support emergency planning in area of influence of nuclear complex of Angra dos Reis, RJ, Brazil; Modelagem Lagrangeana da dispersao atmoferica de radionuclideos e sistemas de informacao geografica como ferramentas de suporte ao planejamento de emergencia na area de influencia do complexo nuclear de Angra dos Reis, RJ

    Energy Technology Data Exchange (ETDEWEB)

    Silva, Corbiniano

    2013-07-01

    Industrial accidents generally endanger structures and the set of environmental influence area where the enterprises are located, especially when affected by atmospheric dispersion of their pollutants, whose concern with the evacuation of the population is the main goal in emergency situations. Considering the nuclear complex Angra dos Reis - RJ, based on computer modeling analysis of the mechanisms of pollutant dispersion in conjunction with geographic information systems were developed. Thus, information about the dispersion of radionuclides - from simulations performed on the HYSPLIT; meteorological data (direction, intensity and calm on the wind regime and analysis of the wind field in the region using WRF), occurrence of landslides and data on the environmental study area were integrated into a GIS database using ArcGIS platform. Aiming at the identification and definition of escape routes in case of evacuation from accidental events in CNAAA, the results point solutions for long-term planning, based on weather and landslides, and short-term, supported by simulations of the dispersion radionuclides, in order to support actions that assist local emergency planning. (author)

  11. Thermal hydraulic simulations of the Angra 2 PWR

    Directory of Open Access Journals (Sweden)

    González-Mantecón Javier

    2015-01-01

    Full Text Available Angra 2, the second Brazilian nuclear power plant, began the commercial operation in 2001. The plant is a pressurized water reactor (PWR type with electrical output of about 1350 MW. In the present work, the thermal hydraulic RELAP5-3D code was used to develop a model of this reactor. The model was performed using geometrical and material data from the Angra 2 final safety analysis report (FSAR. Simulations of the reactor behavior during steady state and loss of coolant accident were performed. Results of temperature distribution within the core, inlet and outlet coolant temperatures, coolant mass flow, and other parameters have been compared with the reference data and demonstrated to be in good agreement with each other. This study demonstrates that the developed RELAP5-3D model is capable of reproducing the thermal hydraulic behavior of the Angra 2 PWR and it can contribute to the process of the plant safety analysis.

  12. Technical subsidies for the operation of IRD/CNEN emergency vehicles in the case of a nuclear accident at the Angra Nuclear Power Plant with associated radioactive releases to the atmosphere

    International Nuclear Information System (INIS)

    Leao, J.L.B.

    1982-03-01

    Technical support is provided for the operation of an emergency vehicle of Instituto de Radioprotecao e Dosimetria/Comissao Nacional de Energia Nuclear, Rio de Janeiro, Brazil, in the event of uncontrolled release of radioactivity from the Angra Nuclear Power Plant (NPP) to the atmosphere. It is based on internationally adopted emergency decision process philosophy, the concept of 'Protective Action Guide' (PAG), the exposure pathways relevant to nuclear accidents, the measuring systems to be used in obtaining the exposure rate in the effluent 'plume', the methods utilized to predict dose to the population, radioiodine suppression measures, the monitoring instrumentation available to the emergency group, some post-accident considerations and finally, the monitoring that may be carried out from an aircraft. Information is given about the NPP operator's responsabilities with respect to the prediction of the consequences of an accident, as well as methods for thyroid and whole body dose estimation based on exposure to the radioiodine and noble gases present in the effluent plume. The example of the Three Mile Island's incident is used to formulate some observations regarding collective dose to the public estimates derived from measurements made from a helicopter. (Author) [pt

  13. Reactor inventory monitoring system for Angra-1 reactor

    International Nuclear Information System (INIS)

    S Neto, Joaquim A.; Silva, Marcos C.; Pinheiro, Ronaldo F.M.; Soares, Milton; Martinez, Aquilino; Comerlato, Cesar A.; Oliveira, Eugenio A.

    1996-01-01

    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)

  14. Simulation spread sheet of Angra-1 secondary circuit; Planilha de simulacao do circuito secundario de Angra-1

    Energy Technology Data Exchange (ETDEWEB)

    Futuro, F.L.; Rucos, J.; Ogando, A. [ELETROBRAS Termonuclear S.A. (ELETRONUCLEAR), Rio de Janeiro, RJ (Brazil). E-mail: jrucos@eletronuclear.gov.br; Maprelian, E.; Bassel, W.S.; Baptista Filho, B.D. [Instituto de Pesquisas Energeticas e Nucleares (IPEN), Sao Paulo, SP (Brazil). E-mail: emaprel@net.ipen.br

    2000-07-01

    The efficient operation of a Nuclear Power Plant (NPP) requires the continuous identification of derivations in the main operating parameters. The identification and analysis of those derivations allow someone to detect the degradation of instruments or even of any equipment. In order to study this problem the group of thermal generation of Angra 1 NPP, devised the use of a Microsoft Excel spread sheet for the automation of Angra 1 thermal balance. In the set of simulation spread sheets, measured values of the secondary system main parameters were compared with project values for a given reactor power level and condenser pressure. The spread sheets provide the turbines power and efficiency and do the plant thermal balance. This work presents a general description of the spread sheets set and a real case analysis of Angra 1 NPP, showing its precision and use easiness. (author)

  15. RELAP5 simulation of a large break Loss of Coolant Accident (LOCA) in the hot leg of the primary system in Angra 2 nuclear power plant

    International Nuclear Information System (INIS)

    Andrade, Delvonei Alves de; Sabundjian, Gaiane

    2004-01-01

    The objective of this work is to present the simulation of a large break loss of coolant accident - LBLOCA in the hot leg of the primary loop in Angra 2, with RELAP5/MOD3.2.2g code. This accident is described in the Final Safety Report Analysis of Angra 2 - FSAR and consists basically of the hot leg total break, in loop 20 of the plant. The area considered for the rupture is 4480 cm 2 , which corresponds to 100% of the pipe flow area. Besides, this work also has the objective of verifying the efficiency of the emergency core coolant system - ECCS in case of accidents and transients. The thermal-hydraulic processes inherent to the accident phenomenology, such as hot leg vaporization and consequently core vaporization causing an inappropriate flow distribution in the reactor core, can lead to a reduction in the liquid level, until the ECCS is capable to reflood it

  16. CNEN activities and brazilian nuclear power policy

    International Nuclear Information System (INIS)

    Costa, E.M. da

    1989-01-01

    The goal of the brazilian policy in nuclear power is to provide its use in a pacific way to promote the well being of our people. It is intended, as well, to finish the construction of Angra II and III and proceed with the implementation of the nuclear fuel cycle, progressively fomenting its nationalization. (A.C.A.S.)

  17. Evaluation of a postulated loss of coolant accident (LOCA) due to a 160 cm2 break in a cold leg of Angra 2 nuclear power plant

    International Nuclear Information System (INIS)

    Azevedo, Carlos Vicente Goulart de; Palmieri, Elcio Tadeu; Aronne, Ivan Dionysio

    2002-01-01

    The development of a qualified full nodalization of Angra2 NPP for RELAP5/Mod 3.2.2 gamma, aiming at the evaluation of a comprehensive number of accidents and transients, thus providing suitable safety analysis support for licensing purposes, is being carried out within the framework of CNEN internal technical cooperation, involving some of its institutes (CDTN, IPEN and IEN) and the Reactors Coordination (CODRE). This work presents a simulation of a postulated Angra2 small cold leg break loss of coolant accident (SBLOCA). A 160 cm 2 break is supposed to occur at one cold leg between the main coolant pump and the reactor vessel and is described in the Angra2 Final Safety Analysis Report, section 15.6.4.1.3.4. The simulation of several types of transients and accidents is necessary to verify the adequate performance of the modeled logic and systems. In general, the analysis of such and accident allows to demonstrate the safety Injection System performance and the reliable transition between the high pressure safety injection, the accumulator injection and the residual heat removal phases. Furthermore, it is assumed that some components are out of service due to fail or repair in order to make a conservative analysis. The results showed a compatible behavior of the molded systems and that the simulated Emergency Core Cooling System was able to provide sufficient cooling to avoid any damage to the core. (author)

  18. The Angra 1 fire PRA project

    International Nuclear Information System (INIS)

    Silva, Luiz E. Massiere de C.; Kassawara, Robert

    2009-01-01

    The Angra 1 Fire PRA (Probabilistic Risk Assessment) is under development by ELETRONUCLEAR jointly with EPRI (Electric Power Research Institute). The project was started January of 2007 and it is foreseen to be finished in the middle of the next year. The study is being conducted according to the newest methodology developed by EPRI and NRC/RES (U.S. Nuclear Regulatory Commission - Office of Regulatory Research) published in 2005 as Fire PRA Methodology for Nuclear Power Facilities (NUREG/CR-6850 or EPRI TR-1011989) [1]. Starting from the Internal Events Angra 1 PRA model Level 1 the project aims to be a comprehensive plant-specific fire analysis to identify the possible consequences of a fire in the plant vital areas which threaten the integrity of systems relevant to the safety, challenging the safety functions and representing a risk of accident that can lead to a core damage. The main tasks include the plant boundary and partitioning, the fire PRA component selection and the identification of the possible fire scenarios (ignition, propagation, detection, extinction and hazards) considering human failure events to establish the fire-induced risk model for quantification of the risk for nuclear core damage taking into account the plant design and its fire protection resources. This work presents a general discussion on the methodology applied to the completed steps of the project. (author)

  19. Establishment of criteria for classification of area remediation measures contaminated after an eventual radiation accident in Angra dos Reis, RJ, nuclear power plant

    International Nuclear Information System (INIS)

    Silva, Diogo Neves Gomes da

    2016-01-01

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

  20. Piping data bank and erection system of Angra 2: structure, computational resources and systems

    International Nuclear Information System (INIS)

    Abud, P.R.; Court, E.G.; Rosette, A.C.

    1992-01-01

    The Piping Data Bank of Angra 2 called - Erection Management System - Was developed to manage the piping erection of the Nuclear Power Plant of Angra 2. Beyond the erection follow-up of piping and supports, it manages: the piping design, the material procurement, the flow of the fabrication documents, testing of welds and material stocks at the Warehouse. The works developed in the sense of defining the structure of the Data Bank, Computational Resources and System are here described. (author)

  1. Radiological protection for the ANGRA 1 steam generator replacement outage

    International Nuclear Information System (INIS)

    Oliveira, Magno Jose de; Amaral, Marcos Antonio do; Minelli, Edson; Ferreira, William Alves

    2009-01-01

    The Angra 1 Nuclear Power Plant (NPP) is a Westinghouse two-loop plant with net output before its 1P16 Outage of 632 MWe, with the Old Steam Generators (OSG) type model D3, which were replaced by two new Steam Generators with feed water-ring system. Localized in Angra dos Reis, Rio de Janeiro - Brazil, Angra 1 started in commercial operation in 1985 and, from the beginning problems related to corrosion have appeared in the Inconel 600 alloy of the tubes. The corrosion problems indicated the necessity for a strong control of the tubes thicknesses and, after a time, the ELETRONUCLEAR decided to replace the OSG. In 2009, ELETRONUCLEAR initiated in January 24, the actions for the Steam Generators Replacement - SGR. During the SGR process, several controls were applied in field, which made possible to have no radiological accidents, no dose limits exceeded, and permitted to achieve a very good result in terms of Collective Dose. This paper describes the radiological controls applied for the Angra 1 Steam Generator Replacement Outage, the radiological protection team sizing and distribution and the obtained results. (author)

  2. Angra 3 - economic and financial evaluation of the enterprise

    International Nuclear Information System (INIS)

    Andrade, Ronaldo Barata de

    2006-01-01

    This paper presents an updated economic-financial evaluation of Angra 3 Nuclear Power Plant project and estimates the lowest power tariff value at which power potentially made available may be commercialized and yet ensures the project a profitability level agreeable to the interests of economic agents and shareholders. According to the project evaluation practice, Angra 3 power generation was considered separately from ELETRONUCLEAR operating plants (Angra 1 and Angra 2), thus preventing result distortions bound to occur if the economic-financial variables of the new project were analyzed associated with financial commitments and commercialization conditions resulting from the project implementation process and the generated power commercialization conditions, respectively. For this evaluation different technical and economic scenarios were devised, and the theory of Capital Asset Pricing Model (CAPM) for Own Capital cost and that of Weighted Average Cost of Capital (WACC) were used in addition to the forecast of the Statement of Results and Free Cash flow of Shareholders throughout the power plant life, which is the estimate basis for the lowest power tariff value and the Internal Return Rate (IRR) of the project. (author)

  3. Expertise e participação da população em contexto de risco nuclear: democracia e licenciamento ambiental de Angra 3

    Directory of Open Access Journals (Sweden)

    Gláucia Silva

    2009-01-01

    Full Text Available Dans cet article, on discute la spécificité de la "participation" des citoyens dans les cas de délibération sur l'acceptation du risque nucléaire, montrant que cette participation dépend de la médiation d'un professionnel capable de traduire le jargon scientifique des documents techniques ou établissant lui-même ses propres documents, à titre de contre-expertise; sinon, les profanes ne sauront légitimer leurs arguments scientifiquement. Dans ce travail, on prend comme base empirique les thèmes récurrents des audiences publiques organisées en vue du permis de fonctionnement des deux centrales nucléaires brésiliennes de technologie allemande - Angra 2 et Angra 3 -, surtout pour cette dernière, en cours de licence environnementale préalable. Les formes de "contrôle social" patriquées en France servent de contrepoint à la construction de ce qui est ici exposé.

  4. Angra-1 NPP thermal influence on liquid effluent discharge zone

    International Nuclear Information System (INIS)

    Costa, Daniel de Araujo

    1996-01-01

    The Angra I Nuclear Power Plant makes use of sea-water to condense the steam generated in its secondary circuit. This water, collected from Itaorna bay, is then chlorinated and discharged, with higher temperature, in the Piraquara de Fora bay. Aiming the study of the marine ecosystem, submitted to the effects of the Nuclear Power Plant discharge water, the temperature, residual chlorine, flora and fauna are periodically monitored. Being sensitive to temperature variations and to chemical products, macroscopic algae are also bio-accumulators and primary producers, because of this, they are considered the main link in the food chain and therefore important bio-indicator. This paper shows the variation of species from the brown algae near the discharge of Angra I Nuclear Power Plant. (author)

  5. Assessment of impact of a severe accident at nuclear power plant of Angra dos Reis with release of radionuclides to the atmosphere; Avaliacao do impacto de um acidente severo na usina de Angra dos Reis com liberacao de radionuclideos para a atmosfera

    Energy Technology Data Exchange (ETDEWEB)

    Aguiar, Andre Silva de

    2015-07-01

    This study had as purpose the assess the impact of a severe accident, and also analyze the dispersion of {sup 131}I in the atmosphere, so that, through concentrating and inhaling dose of the plume, were possible to verify if the results are in accordance with the indicated data by the Plan of Emergency of the CNAAA regarding the Impact Zone and Control. This exercise was performed with the aid of an atmospheric model and a dispersion where to atmospheric modeling we used the data coupling WRF / CALMET and of dispersion, CALPUFF. The suggested accident consists of a Station Blackout at Nuclear Power of Angra (Unit 1), where through the total core involvement, will release 100% of the {sup 131}I to the atmosphere. The value of the total activity in the nucleus to this radionuclide is 7.44 x 1017 Bq, that is relative on the sixth day of burning. This activity will be released through the chimney at a rate in Bq/s in the scenario of 12, 24, 48 and 72 hours of release. Applying the model in the proposed scenario, it is verified that the plume has concentrations of the order of 1020 Bq/m³ and dose of about 108 Sv whose value is beyond of the presented by Eletronuclear in your current emergency plan. (author)

  6. Angra 3 - economic and financial evaluation of the enterprise; Angra 3 - avaliacao economico-financeira do empreendimento

    Energy Technology Data Exchange (ETDEWEB)

    Andrade, Ronaldo Barata de [ELETROBRAS Termonuclear S.A. (ELETRONUCLEAR), Rio de Janeiro, RJ (Brazil)]. E-mail: rbarata@eletronuclear.gov.br

    2006-07-01

    This paper presents an updated economic-financial evaluation of Angra 3 Nuclear Power Plant project and estimates the lowest power tariff value at which power potentially made available may be commercialized and yet ensures the project a profitability level agreeable to the interests of economic agents and shareholders. According to the project evaluation practice, Angra 3 power generation was considered separately from ELETRONUCLEAR operating plants (Angra 1 and Angra 2), thus preventing result distortions bound to occur if the economic-financial variables of the new project were analyzed associated with financial commitments and commercialization conditions resulting from the project implementation process and the generated power commercialization conditions, respectively. For this evaluation different technical and economic scenarios were devised, and the theory of Capital Asset Pricing Model (CAPM) for Own Capital cost and that of Weighted Average Cost of Capital (WACC) were used in addition to the forecast of the Statement of Results and Free Cash flow of Shareholders throughout the power plant life, which is the estimate basis for the lowest power tariff value and the Internal Return Rate (IRR) of the project. (author)

  7. Environmental qualification program of electric equipment for Angra 1

    Energy Technology Data Exchange (ETDEWEB)

    Muzitano, Grazielle F.; Justino, Marcelo C.; Silva, Marcos C., E-mail: grazi@eletronuclear.gov.br, E-mail: justino@eletronuclear.gov.br, E-mail: candeia@eletronuclear.gov.br [Eletrobras Termonuclear S.A. (ELETRONUCLEAR), Rio de Janeiro, RJ (Brazil)

    2017-11-01

    This paper describes the development of the environmental qualification program for important electrical equipment (EQPEE) used for safety in Angra 1 Nuclear Power Plant (NPP). The environmental qualification program started in United States of America by the Nuclear Regulatory Commission (NRC) after the Three Mile Island (TMI) Nuclear Power Plant Accident in 1979. In that event, some equipment installed inside the reactor containment of TMI failed due the harsh conditions that occurred after the accident. Because of this fact, the NRC issued the Regulation 50.49 'Environmental qualification of electric equipment important to safety for nuclear power plants'. The Brazilian regulatory commission CNEN also asked Angra 1 to follow this regulation and to implement an EQPEE similar to the programs adopted by American and other NPPs around the world. Due to the importance to maintain the critical equipment operating in normal and abnormal environment conditions, the program aims to assure that this equipment remains qualified to work under the harsh conditions found inside the reactor containment. The aging of these components are also analyzed in this program that is important in the process to extend the operating life of Angra 1 for more 20 years, which is normally referred as Long Term Operation (LTO). (author)

  8. Environmental qualification program of electric equipment for Angra 1

    International Nuclear Information System (INIS)

    Muzitano, Grazielle F.; Justino, Marcelo C.; Silva, Marcos C.

    2017-01-01

    This paper describes the development of the environmental qualification program for important electrical equipment (EQPEE) used for safety in Angra 1 Nuclear Power Plant (NPP). The environmental qualification program started in United States of America by the Nuclear Regulatory Commission (NRC) after the Three Mile Island (TMI) Nuclear Power Plant Accident in 1979. In that event, some equipment installed inside the reactor containment of TMI failed due the harsh conditions that occurred after the accident. Because of this fact, the NRC issued the Regulation 50.49 'Environmental qualification of electric equipment important to safety for nuclear power plants'. The Brazilian regulatory commission CNEN also asked Angra 1 to follow this regulation and to implement an EQPEE similar to the programs adopted by American and other NPPs around the world. Due to the importance to maintain the critical equipment operating in normal and abnormal environment conditions, the program aims to assure that this equipment remains qualified to work under the harsh conditions found inside the reactor containment. The aging of these components are also analyzed in this program that is important in the process to extend the operating life of Angra 1 for more 20 years, which is normally referred as Long Term Operation (LTO). (author)

  9. 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

  10. 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

  11. The SEDA computer code and its utilization for Angra 1

    International Nuclear Information System (INIS)

    Fernandes Filho, T.L.

    1988-11-01

    The implementation of SEDA 2.0 computer code, developed at Ezeiza Atomic Center, Argentine for Angra 1 reactor is described. The SEDA code gives an estimate for radiological consequences of nuclear accidents with release of radiactive materials for the environment. This code is now available for an IBM PC-XT. The computer environment, the files used, data, the programining structure and the models used are presented. The input data and results for two sample case are described. (author) [pt

  12. Systematization of Angra-1 operation attendance - Maintenance and periodic testings

    International Nuclear Information System (INIS)

    Furieri, E.B.; Carvalho Bruno, N. de; Salaverry, N.A.

    1988-01-01

    A maintenance analysis, their types and their functions for the safety of nuclear power plants is done. Programs and present trends in the reactor maintenance, as well as the maintenance program and periodic tests of Angra I, are analysed. The necessities of safety analysis and a systematization for maintenance attendance are discussed and the periodic testing as well as the attendance of international experience. (M.C.K.) [pt

  13. Evaluation of Iodine-131 dispersion after accident in Nuclear Angra Power Plant using the model of aquatic dispersion, SisBahia; Avaliacao da dispersao de iodo-131 apos um acidente na usina de Angra utilizando o modelo de dispersao aquatica, SisBahia

    Energy Technology Data Exchange (ETDEWEB)

    Aguiar, Andre Silva de; Alvim, Antonio Carlos Marques, E-mail: aguiargm@gmail.com, E-mail: aalvim@gmail.com [Universidade Federal do Rio de Janeiro (UFRJ), Rio de Janeiro, RJ (Brazil). Centro de Tecnologia; Simoes Filho, Francisco Fernando Lamego, E-mail: flamego@ien.gov.br [Instituto de Engenharia Nuclear (IEN/CNEN-RJ), Rio de Janeiro, RJ (Brazil)

    2014-07-01

    It was inserted, in the cooling system of the nucleus, a LOCA, where 431 m{sup 3} of coolant was lost. Such an inventory contained 3,04 x 10{sup 10} Bq / m{sup 3} and iodine was released near the beach Itaorna, Angra dos Reis - RJ. Applying the model in the proposed scenario (Angra 1 and Angra 2 in operation and 3 in with varying capture and discharge with the discharge gradually reduced after the accident), the dilution of the specific activity of radionuclides reached lower values after 22 hours, the reference levels for seawater {sup 131}I (7,40 x 10{sup 2} Bq / m{sup 3}). After 54 hours, levels of the radionuclide, in the area of indirect influence, are already below minimum activity values detected by the laboratory for environmental monitoring of the CNAAA (5,0 x 10{sup 1} Bq / m{sup 3}.

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

    Energy Technology Data Exchange (ETDEWEB)

    Silva, Diogo Neves Gomes da

    2016-07-01

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

  15. 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

  16. Nuclear installations

    International Nuclear Information System (INIS)

    1998-01-01

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

  17. Development of a suitable weld geometry for pressure resistance welding of the leader test assembly (LTA's) 16NGF fuel assembly fuel rod at Angra-1 Nuclear Power Plant

    Energy Technology Data Exchange (ETDEWEB)

    Junqueira, Fabio da Silva; Silva, Josue Ribeiro, E-mail: fabiojunqueira@inb.gov.br, E-mail: josueribeiro@inb.gov.br [Industrias Nucleares do Brasil (GEPRDN/INB), Rio de Janeiro, RJ (Brazil). Gerencia do Produto

    2013-07-01

    The purpose of this work is to develop suitable weld geometry for pressure resistance welding of the zircaloy-4 end plug to the special zirconium alloy cladding tube, Ø 9,14mm, for demonstration at Angra-1 Nuclear Plant. Weld geometry development was carried out in two steps: at the first one, the influence caused by the variation of the welding process key parameters, the axial compression strength of the end plug against the cladding tube, projection of the cladding tube into the welding chamber and the welding current have been evaluated; at the second step, the influence of the variation of end-plug weld geometry area was checked. For the combination of welding parameters, the technique of factorial design was used. Results from mechanical and metallographic tests have indicated a strong and direct influence of weld geometry dimensional variation on the weld mechanical resistance, and a modest influence in relation to the range of key parameters used to carry out tests. (author)

  18. Lagrangian modeling of atmospheric dispersion of radionuclides and geographical information systems as tools to support emergency planning in area of influence of nuclear complex of Angra dos Reis, RJ, Brazil

    International Nuclear Information System (INIS)

    Silva, Corbiniano

    2013-01-01

    Industrial accidents generally endanger structures and the set of environmental influence area where the enterprises are located, especially when affected by atmospheric dispersion of their pollutants, whose concern with the evacuation of the population is the main goal in emergency situations. Considering the nuclear complex Angra dos Reis - RJ, based on computer modeling analysis of the mechanisms of pollutant dispersion in conjunction with geographic information systems were developed. Thus, information about the dispersion of radionuclides - from simulations performed on the HYSPLIT; meteorological data (direction, intensity and calm on the wind regime and analysis of the wind field in the region using WRF), occurrence of landslides and data on the environmental study area were integrated into a GIS database using ArcGIS platform. Aiming at the identification and definition of escape routes in case of evacuation from accidental events in CNAAA, the results point solutions for long-term planning, based on weather and landslides, and short-term, supported by simulations of the dispersion radionuclides, in order to support actions that assist local emergency planning. (author)

  19. 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

  20. Readout electronics validation and target detector assessment for the Neutrinos Angra experiment

    Energy Technology Data Exchange (ETDEWEB)

    Alvarenga, T.A. [Federal University of Juiz de Fora, Juiz de Fora-MG (Brazil); Anjos, J.C.; Azzi, G. [Brazilian Center for Research in Physics, Rio de Janeiro-RJ (Brazil); Cerqueira, A.S. [Federal University of Juiz de Fora, Juiz de Fora-MG (Brazil); Chimenti, P. [Federal University of ABC, Santo André-SP (Brazil); Costa, J.A.; Dornelas, T.I. [Federal University of Juiz de Fora, Juiz de Fora-MG (Brazil); Farias, P.C.M.A. [Federal University of Bahia, Salvador-BA (Brazil); Guedes, G.P. [State University of Feira de Santana, Feira de Santana-BA (Brazil); Gonzalez, L.F.G.; Kemp, E. [State University of Campinas, Campinas-SP (Brazil); Lima, H.P.; Machado, R. [Brazilian Center for Research in Physics, Rio de Janeiro-RJ (Brazil); Nóbrega, R.A., E-mail: rafael.nobrega@ufjf.edu.br [Federal University of Juiz de Fora, Juiz de Fora-MG (Brazil); Pepe, I.M. [Federal University of Bahia, Salvador-BA (Brazil); Ribeiro, D.B.S. [Federal University of Juiz de Fora, Juiz de Fora-MG (Brazil); Simas Filho, E.F. [Federal University of Bahia, Salvador-BA (Brazil); Valdiviesso, G.A. [Federal University of Alfenas, Poços de Caldas-MG (Brazil); Wagner, S. [Pontifical Catholic University of Rio de Janeiro, Rio de Janeiro-RJ (Brazil)

    2016-09-11

    A compact surface detector designed to identify the inverse beta decay interaction produced by anti-neutrinos coming from near operating nuclear reactors is being developed by the Neutrinos Angra Collaboration. In this document we describe and test the detector and its readout system by means of cosmic rays acquisition. In this measurement campaign, the target detector has been equipped with 16 8-in PMTs and two scintillator paddles have been used to trigger cosmic ray events. The achieved results disclosed the main operational characteristics of the Neutrinos Angra system and have been used to assess the detector and to validate its readout system.

  1. Reliability analysis of air recirculation and refrigeration systems of Angra-1 reactor contaiment: a reevaluation

    International Nuclear Information System (INIS)

    Oliveira, L.F.S. de; Fleming, P.V.; Frutuoso e Melo, P.F.F.

    1983-01-01

    A realiability analysis of the air refrigeration and recirculation containment systems (ARRCS) of Angra-1 nuclear power plants, were done, aiming to evaluate the probabilities of occurence of a several accident. The systems were analysed for a 24 hours accident, including time failures and demand failures [pt

  2. Model description for calculating the source term of the Angra 1 environmental control system

    International Nuclear Information System (INIS)

    Oliveira, L.F.S. de; Amaral Neto, J.D.; Salles, M.R.

    1988-01-01

    This work presents the model used for evaluation of source term released from Angra 1 Nuclear Power Plant in case of an accident. After that, an application of the model for the case of a Fuel Assembly Drop Accident Inside the Fuel Handling Building during reactor refueling is presented. (author) [pt

  3. First fuel re-load of Angra-1 reactor - Inspection and hearing plan

    International Nuclear Information System (INIS)

    Pollis, W.; Alvarenga, M.A.B.; Meldonian, N.L.; Paiva, R.L.C. de; Pollis, R.

    1985-01-01

    The plan of inspection and hearing of the first fuel reload of Angra-1 nuclear reactor is detailed. It consists in five steps: receiving and storage of the fuel; reload preparation; activities during; post-reload activities, and preliminary activities. (M.I.)

  4. Corrosão de liga 800GN em ambiente do circuito secundário da Central Nuclear de Angra 2

    OpenAIRE

    Fabio Abud Mansur

    2015-01-01

    A liga 800GN (grau nuclear) é um material utilizado na fabricação de geradores de vapor para reatores de água pressurizada (PWR) de usinas nucleares devido à sua elevada resistência à corrosão. A resistência à corrosão da liga 800GN é devida ao caráter protetor da película de óxido formada na superfície do tubo em contato com a água pressurizada à alta temperatura. No entanto, a corrosão tem sido a principal causa de falhas nos tubos dos geradores de vapor de usinas nucleares. Os problemas ge...

  5. Risk perception of workers at nuclear power plants from Angra dos Reis, Rio de Janeiro State: preliminary study of a reality on health

    International Nuclear Information System (INIS)

    Scliar, Claudio; Vasconcelos, Ana S.F.; Rodrigues, Anacely S.; Santos, Gloria R.R.; Albuquerque, Patricia O.; Carvalho, Sirlene L.A.; Oliveira, Simone

    1999-01-01

    The present paper analyses some social and occupational parameters that may have an influence on the risk perception levels of the workers in Brazilian Nuclear Power pLants, emphasizing possible relationship between the specificity of job tasks/literacy and risk perception. This study was based on two findings from the scientific literature: risk perception increases proportionally with literacy; risk perception decreases proportionally with the specificity of job tasks. The results of this pilot study indicates that risk perception levels of the workers in Brazilian Nuclear Power Plants increases proportionally with the literacy and specificity of their job tasks, contrasting with the american and european profiles. These results appears as a singular reality of those workers and the possibility of a new regard over the management and decision making process in the Brazilian Nuclear Power Plants. (author)

  6. Analysis of liquid radioactive wastes of Angra-1 reactor

    International Nuclear Information System (INIS)

    Martins, Nadia Soido F.; Peres, Sueli da Silva; S. Filho, Aluisio Mendes

    2001-01-01

    Any activity that produces or uses radioactive materials generates radioactive wastes. Normal operation of nuclear power plant produces radioactive waste that can be in gas, liquid or solid form and its level of radioactivity can vary. Gases and liquids wastes are treated and released into environment. The main source of radioactivity released to environment from Angra 1 are liquids from Waste Monitor Tanks. Those releases are under administrative control to meet the discharge limits established by Comissao Nacional de Energia Nuclear (CNEN). A representative sample of each batch is taken for analysis for principal gamma- emitting radionuclides and, if the analysis indicate that release can be made, the quantity of activity is recorded. Within the licensing process of Angra 1, monthly a proportional composite samples are made up with a aliquot of each batch and sent to Instituto de Radioprotecao e Dosimetria (IRD) to analyze and compare with the results reported. This comparative analyses showed that when the activity of that samples was very high, the activity measured on composite samples was higher than the sum of the activities measured on each batch. The operator was advised and requested to identify and solve the problem. This work presents the problem occurred and the solution found to improve the performance of measurements. (author)

  7. Evaluation of nuclear parameters measurements realized during the Angra-1 reactor start-up tests and the theoretical previsions of these parameters

    International Nuclear Information System (INIS)

    Fernandes, V.B.; Ponzoni Filho, P.; Perrotta, J.A.; Silva Ipojuca, T. da

    1982-01-01

    A summary of measuring techniques and the results of the follow nuclear parameters, are presented: a) reactivity of various control bank; b) capacity of reactor shutdown; c) critical concentrations of soluble boron for various core configurations; d) reactivity isothermal coefficients; e) power mapping; f) power reactivity coefficients. (E.G.) [pt

  8. Analysis of liquid radioactive wastes of Angra-1 reactor; Analise de efluentes liquidos radioativos de Angra-1

    Energy Technology Data Exchange (ETDEWEB)

    Martins, Nadia Soido F.; Peres, Sueli da Silva [Instituto de Radioprotecao e Dosimetria (IRD), Rio de Janeiro, RJ (Brazil); S. Filho, Aluisio Mendes [Central Nuclear Almirante Alvaro Alberto, Angra dos Reis, RJ (Brazil)

    2001-07-01

    Any activity that produces or uses radioactive materials generates radioactive wastes. Normal operation of nuclear power plant produces radioactive waste that can be in gas, liquid or solid form and its level of radioactivity can vary. Gases and liquids wastes are treated and released into environment. The main source of radioactivity released to environment from Angra 1 are liquids from Waste Monitor Tanks. Those releases are under administrative control to meet the discharge limits established by Comissao Nacional de Energia Nuclear (CNEN). A representative sample of each batch is taken for analysis for principal gamma- emitting radionuclides and, if the analysis indicate that release can be made, the quantity of activity is recorded. Within the licensing process of Angra 1, monthly a proportional composite samples are made up with a aliquot of each batch and sent to Instituto de Radioprotecao e Dosimetria (IRD) to analyze and compare with the results reported. This comparative analyses showed that when the activity of that samples was very high, the activity measured on composite samples was higher than the sum of the activities measured on each batch. The operator was advised and requested to identify and solve the problem. This work presents the problem occurred and the solution found to improve the performance of measurements. (author)

  9. Utilization of ''RASO'' for a historical survey of Angra-1 power from 26.10.88 for updating the inventory calculation

    International Nuclear Information System (INIS)

    Guimaraes, A.C.F.; Goes, A.G.

    1988-12-01

    The ''RASO'', an activity and operational situation report for Angra 1, is transmitted daily by phone to CNEN by inspectors living at Angra 1 site, anal shows the parameters about the operational status of the nuclear power plant. In the period of 26.10.88 to 04.12.88 a discretized power serie was determined for greater time intervals than the original serie, and then new concentrations were calculated using origem 2 computer code. (author) [pt

  10. Fishes of Saco do Piraquara de Fora, in a discharge area of liquid effluents from Angra-1 Nuclear Power Plant (CNAAA)

    International Nuclear Information System (INIS)

    Almeida, Ademar Ferrari Vaz de; Santoro, Maria Dulce Novaes

    1996-01-01

    Because the thermal effluents, released from the Unit I condenser system, it was implanted, at discharge area (Saco Piraquara de Fora), a Marine Fauna and Flora Monitoring Program, been necton area part of this, to verify possible impact over fish population, quantitative and qualitative studies were performed. Trichiurus lipeturus and Diapterus rhombeus were chosen as indicators because the high frequencies and abundances. Besides this, Furnas implanted a Radiological Monitoring Program, where samples of fish were collected and analysed by gamma spectrometry, showing the presence of Cs-137 since the pre-operational period, caused by fall out process at the region, from nuclear weapons test at atmosphere. (author)

  11. Preoperational environmental monitoring of the Angra reactor site

    International Nuclear Information System (INIS)

    Mendonca, A.H.; Nobrega, A.W.; Mulder, R.U.; Vianna, M.E.C.; Almeida, C.E. de; Winter, M.

    1983-03-01

    The Preoperational Environmental Monitoring Program for the Angra Nuclear power plant site as well as the single and summarized results obtained this program are presented and discussed in this report. For clarity, a description is given of the Angra site and of the program structure and a map of the region showing measurement and sampling locations is included. Preoperational monitoring was carried out over the period from September 1979 to September 1981. For direct measurements of background radiation levels a solid-state dosimeter network was used and the results were compared to measurements made with ionization chambers. Measurements were performed of natural and artificial radioactivity concentration levels in air, surface water, soil, grass, sea sediments, sea algae and various foodstuffs. Gross alpha and beta activity levels were determined as well as the concentration levels of individual natural radionuclides. The presence of cesium-137 originating from fallout was observed in manioc. Minimum detection limits for fission and activated corrosion products which are of interest during the reactor operational period were defined and determined for the instrumentation and methods used at the Institute of Radioprotection and Dosimetry. These limits have been included in the tables. (Author) [pt

  12. Consequence analysis and probabilistic safety analysis of Angra-1

    International Nuclear Information System (INIS)

    Guimaraes, A.C.F.

    1987-07-01

    A methodology for determining the environmental consequences in the site of nuclear power plants, is presented. The methodology obtains as final result the 'S' site matrix, which represents the probabilities of health damage. Two types of healt damages were analysed: the early fatalities and injury. The damages are calculated from the determination of radiation doses which the population in surrounding of the site could be submitted, in the case of severe accident with the core meltdown. The accidents are defined from an initial event, leading to the failure of reactor containment. The results presented the same magnitude order when they were compared with ones obtained in studies of the Zion Nuclear Power Plant. The Angra-1 was adopted as reference reactor and the CRAC-2 computer code was used. (M.C.K.) [pt

  13. Angra-1 chlorination system: chlorine gas versus sodium hypochlorite; Sistema de cloracao de Angra I: cloro gasoso versus hipoclorito de sodio

    Energy Technology Data Exchange (ETDEWEB)

    Brandao, Flavio E. do Rio; Leite, Nelri Ferreira [FURNAS Centrais Eletricas S.A., Rio de Janeiro, RJ (Brazil). Dept. de Engenharia e Combustivel Nuclear

    1996-07-01

    The objective of this paper is to present a study that was developed over the last two years at Angra I Nuclear Power Plant (Brazil). As a result we chose to change the chlorination system , replacing the actual process that utilizes chlorine gas, with on-site generation of sodium hypochlorite from seawater. The work presents the use of chlorine gas and its implications such as: industrial safety, handling, transportation, corrosion, operational and maintenance costs. It also demonstrates the sodium hypochlorite generation process from electrolysis of seawater and its aspects related to: safety operation, maintenance and costs. Also described are several tests done in Angra I utilizing chlorine gas and sodium hypochlorite, that evaluated the performance of the dosage of active chlorine in the intake canals, in the condensers and discharge, following the Brazilian environmental regulations. (author)

  14. A reliability model of the Angra 1 power system by the device of stages optimized by genetic algorithms

    International Nuclear Information System (INIS)

    Crossetti, Patricia Guimaraes

    2006-01-01

    This thesis proposes a probabilistic model to perform the reliability analysis of nuclear power plant systems under aging. This work analyses the Angra 1 power system. Systems subject to aging consist of components whose failure rates are not all constant, thus generating Non-Markovian models. Genetic algorithms were used for optimizing the application of the device of stages. Two approaches were used in the optimization, MCEF and MCEV. The results obtained for the Angra 1 power system show that the probability of a station blackout is negligible. (author)

  15. A first accident simulation for Angra-1 power plant using the ALMOD computer code

    International Nuclear Information System (INIS)

    Camargo, C.T.M.

    1981-02-01

    The acquisition of the Almod computer code from GRS-Munich to CNEN has permited doing calculations of transients in PWR nuclear power plants, in which doesn't occur loss of coolant. The implementation of the german computer code Almod and its application in the calculation of Angra-1, a nuclear power plant different from the KWU power plants, demanded study and models adaptation; and due to economic reasons simplifications and optimizations were necessary. The first results define the analytical potential of the computer code, confirm the adequacy of the adaptations done and provide relevant conclusions about the Angra-1 safety analysis, showing at the same time areas in which the model can be applied or simply improved. (Author) [pt

  16. Off-site emergency response plans in case of technological catastrophes: the case Angra dos Reis

    International Nuclear Information System (INIS)

    Souza Junior, M.D. de.

    1990-04-01

    In the first part of the thesis a discussion of the technical, operational and methodological features of the current practices for emergency planning in case of a nuclear fallout. Based on this general reference is possible to evaluate the features in the natural and social environment of Angra dos Reis that probably will obstruct the application of the protective countermeasures to the public. These critical points are enhanced to permit the discussion of a methodological approach that is supposed to be suitable to the reality of Angra dos Reis. The approach was developed specifically to this region and was introduced as a part of the general emergency off-site plan to the Central Nuclear Almirante Alvaro Alberto (CNAAA). Starting from this experience will be possible to enlarge this approach in a further research, in order to study this potential hazards of other industrial plants. (author)

  17. Electronuclear Medical Assistance Foundation: medical preparedness and response in Angra dos Reis / Brazil

    Energy Technology Data Exchange (ETDEWEB)

    Leite, Teresa C.S.B.; Maurmo, Alexandre M. [Fundacao Eletronuclear de Assistencia Medica, Angra dos Reis, RJ (Brazil)], e-mail: tleite@feam-etn.org.br, e-mail: maurmo@feam-etn.org.br

    2009-07-01

    This paper relates the health's experience in training and response to accidents involving ionizing radiation at Almirante Alvaro Alberto's Nuclear Power Plant in Angra dos Reis. The response system is organized in the same way of others health's system with pre-hospital attendance, local hospital and referential hospital .We also discussing how we training health workers about this kid of special response. (author)

  18. Quality control of the structural design of Angra 2 and 3 power reactor

    International Nuclear Information System (INIS)

    Merino, J.L.E.; Carvalho, S.R.B. de

    1985-01-01

    The quality control requirements for nuclear power plants are done by CNEN and might be followed by the organizations that are responsible for those activities, such as: design, suppliers, construction, fabrication, mounting, installation, commissioning, operation, maintenance, modification and decommissioning. The Promon's experience for using a quality control program in the structural design of Angra 2 and 3, and the verification system adopted, are presented. (E.G.) [pt

  19. Design of the safety related systems of Angra 2 and 3

    International Nuclear Information System (INIS)

    Maciel Filho, L.A.; Rolf, F.

    1984-01-01

    The safety related systems of the Angra 2 and 3 nuclear power plant, such as the reactor protection system, systems for power supply and mechanical systems, are important for the maintenance of their safety and availability. Their design takes into account their mutual influences and the necessity for testability during power operation in order to achieve a high level of reliability of the whole system. (Author) [pt

  20. Occupational analysis for the Angra-1 reactor

    International Nuclear Information System (INIS)

    Moraes, A.

    1991-01-01

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

  1. Simulation of the Angra I control and protection systems; Representacao dos sistemas automaticos de controle e de protecao de Angra

    Energy Technology Data Exchange (ETDEWEB)

    Borges, Ronaldo C.; Gebrim, Anibal N. [Comissao Nacional de Energia Nuclear (CNEN), Rio de Janeiro, RJ (Brazil). Coordenacao de Reatores]. E-mail: ronaldo@cnen.gov.br; anibal@cnen.gov.br

    1997-07-01

    The following automatic control systems for Angra I Nuclear Power Plant (NPP): rod control system, steam generator level control system, feedwater bypass valve control system, pressurizer pressure control system and pressurizer level control system and also the following protection system: over-temperature, overpower, pressurizer low pressure, pressurizer high pressure, pressurizer high water level, low primary coolant flow and low-low steam generator water level were simulated with the RELAP5/Mod2 code. The paper shows the results of three transients: a ten percent step load change; a five percent per minute ramp load change; and pump costdown. Satisfactory quantitative and qualitative results were obtained comparing these results with the setpoint study and FSAR results. (author)

  2. Fuel failures at Angra 1: Cause and mitigation

    International Nuclear Information System (INIS)

    Chapot, J.L.C.; Suano, R.; Couto, N. do; Perrotta, J.A.; Da Silva, J.E.R.; Terremoto, L.A.A.; Castanheira, M.

    2003-01-01

    Angra 1 Nuclear Power Plant, a Westinghouse-designed 657 MWe PWR, was prematurely shut down in cycle 4 due to high activity in the reactor coolant system. Inspections revealed failures in one-sixth of the fuel assemblies (FAs). According to the fuel vendors the grid-to-rod fretting failures were caused by grid spring force losses. In order to prevent the recurrence of the fretting failures, a new spring design was developed. A new reload batch using the new spring design was loaded in the core for cycle 5. In cycle 6, eight of these FAs failed, showing friction marks at outside strips of spacer grids, due to excessive amplitude of FA vibrations. Flow tests in laboratory were performed using a full-scale fuel assembly, and peaks of resonance due to flow induced vibration were observed. Analysis and modeling of the fuel assembly mechanical behavior can explain the resonance observed. All these analyses supported the need for a new fuel assembly design. In cycle 7, the reactor core was loaded with FAs of the same design inserted in cycle 5. Two leaking assemblies were detected during the fuel inspections conducted at the end of cycle 7. A new core was purchased from Angra 1 former fuel supplier (cycle 1), to load cycle 8. The use of a proven fuel design got rid of the fuel failures. The reload batch for the cycle 9 came also from the same origin as cycle 8. The zero-defect aim was also attained in cycle 9. For cycle 10 it was decided to use twelve once burned assemblies, which had composed cycle 7, with a damping system that, according to flow tests, could reduce the FAs vibration. Cycle 10 is presently under operation with no indication of fuel failures. This paper discusses Angra 1 fuel performance with emphasis to the fuel failures, the inspections and out-of-pile tests performed, the mechanical modeling, the corrective actions proposed by the fuel vendors and the failures mitigation. (author)

  3. Crud formation evaluation at the advanced fuel operating in Angra-1 NPP

    Energy Technology Data Exchange (ETDEWEB)

    Gomez, Diego; Palheiros, Franklin; Gomes, Sydney, E-mail: franklin@inb.gov.br, E-mail: diegogomez@inb.gov.br, E-mail: sydney@inb.gov.br [Indústrias Nucleares do Brasil (INB), Resende, RJ (Brazil). Superintendência de Engenharia do Combustível

    2017-07-01

    In nuclear engineering, 'crud' is a technical term. It stands for Chalk River Unidentified Deposit, originally found on the cladding surface of some fuel rods in the referred canadian reactor, for which it was named. The deposit can be flaky, porous, or hard depending on its chemical composition. In most cases, it reduces the power output of nuclear reactors - the deposits absorb boron and the neutrons that keep the fission reaction going, as well lead to a more corrosion scenario by increasing the oxide/metal interface surface temperature. This issue might been a concern at Angra 1 where many design alterations have been performed in the new Fuel assembly design. The so called 16NGF has a smaller fuel rod diameter, different burnable absorber - gadolinium instead of pyrex borosilicate glass, hydraulic mismatch compared to 16STD fuel, new IFM grids, higher FDeltaH and several other characteristics. All those features lead to a increase in the subcooled boiling rates, which might favour particles depositions in fuel cladding forming the undesired Crud deposits. In order to evaluate how those implementations could impact negatively the new fuel performance at Angra 1, a study has ben carried out using Thermal Hydraulic calculations. With that, an existing methodology was used to assess the associated risks and what could be the done to mitigate further development of crud in 16NGF Fuel in Angra 1. (author)

  4. European Nuclear Decommissioning Training Facility II

    International Nuclear Information System (INIS)

    Demeulemeester, Y.

    2005-01-01

    SCK-CEN co-ordinates a project called European Nuclear Decommissioning Training Facility II (EUNDETRAF II) in the Sixth Framework Programme on Community activities in the field of research, technological development and demonstration for the period 2002 to 2006. This was a continuation of the FP5 project EUNDETRAF. EUNDETRAF II is a consortium of main European decommissioners, such as SCK-CEN, EWN (Energie Werke Nord, Greifswald Germany), Belgatom (Belgium), SOGIN Societa Gestione Impiantio Nucleari, Italy), Universitaet Hannover (Germany), RWE NUKEM (United Kingdom), DECOM Slovakia Slovakia), CEA Centre d'Energie Atomique, France), UKAEA (United Kingdom's Atomic Energy Agency, United Kingdom) and NRG (Nuclear Research and consultancy Group, Netherlands). The primary objective of this project is to bring together this vast skill base and experience; to consolidate it for easy assimilation and to transfer to future generations by organising a comprehensive training programme.Each training course has a one-week theoretical and a one-week practical component. The theoretical part is for a broader audience and consists of lectures covering all the main aspects of a decommissioning. The practical part of the course includes site visits and desk top solutions of anticipated decommissioning problems. Due to operational constraints and safety considerations, the number of participants to this part of the course is strictly limited. The partners intend to organise altogether two two-week EUNDETRAF II training courses over a period of three years. Another goal is to disseminate the existing theory as well as the practical know-how to personnel of the third countries. Finally it is important to bring together the principal decommissioning organisations undertaking various decommissioning activities. The project creates a forum for regular contacts to exchange information and experiences for mutual benefit of these organisations as well as to enhance skill base in Europe to

  5. Quality assurance requirements for dedication process in Angra 1

    International Nuclear Information System (INIS)

    Baliza, Ana Rosa

    2015-01-01

    In Brazil the regulatory body is CNEN (Comissao Nacional de Energia Nuclear), according to its requirements, when there is not a Brazilian standard, the utilities shall follow the requirements of the designer. For Angra 1, the designer is an American company - Westinghouse. So, the requirements for dedication of U.S. NRC (United States Nuclear Regulatory Commission) shall be applied, these requirements are in 10CFR21 - Reporting of Defects and Noncompliance. According to 10CFR21, when applied to nuclear power plants licensed dedication is an acceptance process undertaken to provide reasonable assurance that a commercial grade item to be used as a basic component will perform its intended safety function and, in this respect, is deemed equivalent to an item designed and manufactured under a quality assurance program standard for nuclear power plant. This assurance is achieved by identifying the critical characteristics of the item and verifying their acceptability by inspections, tests, or analyses by the purchaser or third-party dedicating entity. (author)

  6. Quality assurance requirements for dedication process in Angra 1

    Energy Technology Data Exchange (ETDEWEB)

    Baliza, Ana Rosa, E-mail: baliza@eletronuclear.gov.br [Eletrobras Termonuclear S.A. (ELETRONUCLEAR), Angra dos Reis, RJ (Brazil). Departamento GQO.G; Morghi, Youssef, E-mail: ymo@cdtn.br [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)

    2015-07-01

    In Brazil the regulatory body is CNEN (Comissao Nacional de Energia Nuclear), according to its requirements, when there is not a Brazilian standard, the utilities shall follow the requirements of the designer. For Angra 1, the designer is an American company - Westinghouse. So, the requirements for dedication of U.S. NRC (United States Nuclear Regulatory Commission) shall be applied, these requirements are in 10CFR21 - Reporting of Defects and Noncompliance. According to 10CFR21, when applied to nuclear power plants licensed dedication is an acceptance process undertaken to provide reasonable assurance that a commercial grade item to be used as a basic component will perform its intended safety function and, in this respect, is deemed equivalent to an item designed and manufactured under a quality assurance program standard for nuclear power plant. This assurance is achieved by identifying the critical characteristics of the item and verifying their acceptability by inspections, tests, or analyses by the purchaser or third-party dedicating entity. (author)

  7. Risk-Based Allowed Outage Time and Surveillance Test Interval Extensions for Angra 1

    Directory of Open Access Journals (Sweden)

    Sonia M. Orlando Gibelli

    2012-01-01

    Full Text Available In this work, Probabilistic Safety Assessment (PSA is used to evaluate Allowed Outage Times (AOT and Surveillance Test Intervals (STI extensions for three Angra 1 nuclear power plant safety systems. The interest in such an analysis lies on the fact that PSA comprises a risk-based tool for safety evaluation and has been increasingly applied to support both the regulatory and the operational decision-making processes. Regarding Angra 1, among other applications, PSA is meant to be an additional method that can be used by the utility to justify Technical Specification relaxation to the Brazilian regulatory body. The risk measure used in this work is the Core Damage Frequency, obtained from the Angra 1 Level 1 PSA study. AOT and STI extensions are evaluated for the Safety Injection, Service Water and Auxiliary Feedwater Systems using the SAPHIRE code. In order to compensate for the risk increase caused by the extensions, compensatory measures as (1 test of redundant train prior to entering maintenance and (2 staggered test strategy are proposed. Results have shown that the proposed AOT extensions are acceptable for two of the systems with the implementation of compensatory measures whereas STI extensions are acceptable for all three systems.

  8. Probabilistic risk analysis of Angra-1 reactor

    International Nuclear Information System (INIS)

    Spivak, R.C.; Collussi, I.; Silva, M.C. da; Onusic Junior, J.

    1986-01-01

    The first phase of probabilistic study for safety analysis and operational analysis of Angra-1 reactor is presented. The study objectives and uses are: to support decisions about safety problems; to identify operational and/or project failures; to amplify operator qualification tests to include accidents in addition to project base; to provide informations to be used in development and/or review of operation procedures in emergency, test and maintenance procedures; to obtain experience for data collection about abnormal accurences; utilization of study results for training operators; and training of evaluation and reliability techniques for the personnel of CNEN and FURNAS. (M.C.K.) [pt

  9. Numerical simulation of the heating and start-up of PWR nuclear power station

    International Nuclear Information System (INIS)

    Faraco-Medeiros, M.A.; Leite, C.A.T.; Ramalho, F.P.

    1992-01-01

    The start-up of a PWR nuclear power plant must be done within safety criteria and requires a simulation. The design of some equipment, cost and time can be optimized. A computer simulator, which allows control of all the equipment and variables into the operation, has been developed and is presented in this paper. The KWU procedure and an alternative for Angra II were simulated. The results are showed up. 09 refs, 03 figs. (B.C.A.)

  10. Identification of flow regimes and heat transfer modes in Angra-2 core during the simulation of the small break loss of coolant accident of 250 cm{sup 2} in the cold leg of primary loop using RELAP5 code

    Energy Technology Data Exchange (ETDEWEB)

    Borges, Eduardo M.; Sabundjian, Gaiane, E-mail: borges.em@hotmail.com, E-mail: gdjian@ipen.br [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNE-SP), Sao Paulo, SP (Brazil)

    2017-07-01

    The aim of this paper is to identify the flow regimes, the heat transfer modes, and the correlations used by RELAP5/MOD3.2. gamma code in Angra-2 during the Small-Break Loss-of-Coolant Accident (SBLOCA) with a 250cm{sup 2} of rupture area in the cold leg of primary loop. The Chapter 15 of the Final Safety Analysis Report of Angra-2 (FSAR-A2) reports this specific kind of accident. The results from this work demonstrated the several flow regimes and heat transfer modes that can be present in the core of Angra-2 during the postulated accident. The results obtained for Angra-2 nuclear reactor core during the postulated accident were satisfactory when compared with the FSAR-A2. Additionally, the results showed the correct actuation of the ECCS guaranteeing the integrity of the reactor core. (author)

  11. Identification of flow regimes and heat transfer modes in Angra-2 core during the simulation of the small break loss of coolant accident of 250 cm2 in the cold leg of primary loop using RELAP5 code

    International Nuclear Information System (INIS)

    Borges, Eduardo M.; Sabundjian, Gaiane

    2017-01-01

    The aim of this paper is to identify the flow regimes, the heat transfer modes, and the correlations used by RELAP5/MOD3.2. gamma code in Angra-2 during the Small-Break Loss-of-Coolant Accident (SBLOCA) with a 250cm 2 of rupture area in the cold leg of primary loop. The Chapter 15 of the Final Safety Analysis Report of Angra-2 (FSAR-A2) reports this specific kind of accident. The results from this work demonstrated the several flow regimes and heat transfer modes that can be present in the core of Angra-2 during the postulated accident. The results obtained for Angra-2 nuclear reactor core during the postulated accident were satisfactory when compared with the FSAR-A2. Additionally, the results showed the correct actuation of the ECCS guaranteeing the integrity of the reactor core. (author)

  12. Experiments with radioactive nuclear beams II

    International Nuclear Information System (INIS)

    Aguilera R, E.F.; Martinez Q, E.; Gomez C, A.; Lizcano C, D.; Garcia M, H.; Rosales M, P.

    2001-12-01

    The studies of nuclear reactions with heavy ions have been carried out for years for the group of heavy ions of the laboratory of the Accelerator of the ININ. Especially in the last years the group has intruded in the studies of nuclear reactions with radioactive beams, frontier theme at world level. Presently Technical Report is presented in detailed form the experimental methods and the analysis procedures of the research activities carried out by the group. The chpater II is dedicated to the procedures used in the analysis of the last two experiments with radioactive beams carried out by the group. In the chapter III is presented the procedure followed to carrying out an extended analysis with the CCDEF code, to consider the transfer channel of nucleons in the description of the fusion excitation functions of a good number of previously measured systems by the group. Finally, in the chapter IV the more important steps to continue in the study of the reaction 12 C + 12 C experiment drifted to be carried out using the available resources of the Tandem Accelerator Laboratory of the ININ are described. At the end of each chapter some of the more representative results obtained in the analysis are presented and emphasis on the scientific production generated by the group for each case is made. (Author)

  13. Licensing of the first reload of Angra-1 reactor

    International Nuclear Information System (INIS)

    Alvarenga, M.A.B.

    1985-01-01

    The historical aspects related to the licensing of the first reload of Angra-1 reactor are presented. The dates, the institutions, the experts, as well as the documents generated during that process are presented. (M.I.)

  14. Simulation of the postulated stopping accident of the bombs of the primary circuit of Angra 2 with the code RELAP5/MOD3.2

    International Nuclear Information System (INIS)

    Andrade, Delvonei A.; Sabundjian, Gaiane; Madeira, Alzira A.; Pereira, Luiz Carlos M.; Borges, Ronaldo C.; Lapa, Nelbia S.

    2001-01-01

    This work presents the simulation of an anticipated transient for Angra 2 Nuclear Power Plant, where the coast down of the four reactor coolant pumps is verified. The best estimate thermal hydraulic system code RELAP5/MOD3.2 was used on this frame. A multi-purpose nodalization of Angra 2 was developed to simulate a comprehensive set of operational transients and accidents with RELAP5/MOD3.2 code. The overall objective of this work is to provide independent accident evaluation and further operational behavior follow-up to support the licensing process of the plant. (author)

  15. Insertion of control systems models in the Almod 3 computer code for the simulation of Angra I reactor start-up tests

    International Nuclear Information System (INIS)

    Camargo, C.T.M.

    1981-09-01

    The Almod 3 computer code was modified, aiming at the simulation of Angra I nuclear power plant behavior during some reactor start-up tests. The results obtained with the modified computer code (Almod 3W) are compared with those obtained with the Retran computer code. (E.G.) [pt

  16. Reliability analysis of air recirculation and-refrigeration systems of Angra-1 reactor containment

    International Nuclear Information System (INIS)

    Fernandes Filho, T.L.

    1982-10-01

    A reliability analysis of the air refrigeration and recirculation containment systems (ARRCS) of Angra-1 nuclear power plants, were done. The fault tree analysis was used. The failure primary data were taken out of Wash-1400 and IEEE. These data were processed by these following computer codes : Prep-Kitt, Sample, Trebil, Cressex and Streusl for the two stages of ARRCS operation. The design bases accident studied was a LOCA (loss of coolant). The component that more contribution give to the non-availability of ARRCS is the motor of the ARRCS. (E.G.) [pt

  17. Nuclear proliferation. II. Monopoly or cartel

    International Nuclear Information System (INIS)

    Baker, S.J.

    1976-01-01

    Increasing competition between a growing number of nations exporting nuclear technology and recent exporting of full fuel-cycle facilities raise fears of nuclear proliferation and widespread nuclear weapons. As a result of the 1973 oil crisis, industrial nations seeking a share in the international nuclear market in order to protect their economic interests must also cooperate to protect these same interests from nuclear risks. Disagreement over the form of cooperation centers on the competing exporters' tactics of undercutting safeguards and political restrictions. Monopoly was never an option for even the United States. Government intervention in the international nuclear market in the form of subsidies and financial incentives is a more practical approach than a free market. A cartel arrangement is appropriate to nuclear energy in the sense of reducing economic uncertainties, but political objections would be strong and there would be some risk of independent nuclear development. As a strategy to forestall proliferation, however, the cartel can control exports of enrichment and reprocessing facilities and make it more expensive for nations to independently develop nuclear weapons. An enlargement of safeguards arrangements by nuclear suppliers will require nations to trade some of their economic interests in order to achieve international political objectives

  18. Zinc addition at ANGRA 2 NPP. A preliminary report

    International Nuclear Information System (INIS)

    Silva e Souza, U.C.; Ruebenich, M.N.; Azevedo, I.S.

    2002-01-01

    As a result of an Eletronuclear and Siemens agreement planned to be applied in Angra 2 NPP zinc addition used data from the joint German utilities/Siemens qualification program were as well as operating gathered at the German lead pressurized water reactors plants. The qualification program main objective was to demonstrate the process efficiency, to investigate interactions between zinc and oxide layers, to elaborate a dosing concept, to provide compatibility assessment with systems and components and to develop implementation strategy, defining limiting values and diagnostic parameters and a surveillance program. Angra 2 NPP is the world's first power plant using this program since its start-up in July 15, 2001. Its design features (core design, reactor coolant pumps and others) were also reviewed and compared with corresponding data from German Siemens PWR's, adding zinc. The data showed that the compatibility of method with Angra 2 plant was ensured. (authors)

  19. Angra-1 probabilistic safety study-phase B

    International Nuclear Information System (INIS)

    Fernandes Filho, T.L.; Gibelli, S.M.O.

    1988-05-01

    This study represents the Phase B of the Angra-1 Probabilistic Safety Study and is the the final report prepared for the IAEA under Research Contract No. 3423/R2/RB. The three main items covered in this report are the establishment of interim safety goals, analysis of Angra-1 operational experience and development of emergency procedures to address severe accidents. For establishment of interim safety goals a methodology for calculating consequences and risks associated to the Angra-1 operation was developed based on the available data and codes. The proposed safety goals refer to the individual risk of early fatality for people living in the vicinity of the plant, colective risk of cancer fatalities for people living near the plant, the propobability of core melt occurrence and the probability of dominant accident sequences. (author) [pt

  20. Experiments with radioactive nuclear beams II; Experimentos con haces nucleares radiactivos II

    Energy Technology Data Exchange (ETDEWEB)

    Aguilera R, E.F.; Martinez Q, E.; Gomez C, A.; Lizcano C, D.; Garcia M, H.; Rosales M, P. [ININ, 52045 Ocoyoacac, Estado de Mexico (Mexico)

    2001-12-15

    The studies of nuclear reactions with heavy ions have been carried out for years for the group of heavy ions of the laboratory of the Accelerator of the ININ. Especially in the last years the group has intruded in the studies of nuclear reactions with radioactive beams, frontier theme at world level. Presently Technical Report is presented in detailed form the experimental methods and the analysis procedures of the research activities carried out by the group. The chpater II is dedicated to the procedures used in the analysis of the last two experiments with radioactive beams carried out by the group. In the chapter III is presented the procedure followed to carrying out an extended analysis with the CCDEF code, to consider the transfer channel of nucleons in the description of the fusion excitation functions of a good number of previously measured systems by the group. Finally, in the chapter IV the more important steps to continue in the study of the reaction {sup 12}C + {sup 12}C experiment drifted to be carried out using the available resources of the Tandem Accelerator Laboratory of the ININ are described. At the end of each chapter some of the more representative results obtained in the analysis are presented and emphasis on the scientific production generated by the group for each case is made. (Author)

  1. Energy paper II: Nuclear energy revival

    International Nuclear Information System (INIS)

    Anonymous

    2008-01-01

    ESI Energy paper is called 'Issue Paper' awarded by think-tank Energy Security Institute. The second issue focuses on the energy security of countries from the perspective of Renaissance of construction of nuclear power plants. Topicality is documented by fluctuations in fossil fuel prices on the world commodity markets and by extortionate potential, disposed by their main producers. The Slovak Republic is actively engaged into international dialogue on the need for the development of nuclear energy.

  2. Costs of construction, operation and maintenance of nuclear power plants - determinant factors

    International Nuclear Information System (INIS)

    Silva, R.A. da

    1981-01-01

    A study about the construction costs of the Angra-1 nuclear power plant, including direct costs, equipment costs, installation and indirect costs such as: engineering, job-training and administration is presented. The operation and maintenance costs of the Angra-1 nuclear power plant and costs of energy generation are still studied. (E.G.) [pt

  3. Radiation impact caused by the rupture of a radioactive tank within the Reactor Auxiliary Building of Angra 2

    International Nuclear Information System (INIS)

    Passos, Erivaldo Mario dos; Alves, Antonio Sergio de Martin

    2002-01-01

    This paper aims to show the methodology, the parameters and some results of the radionuclide migration simulation in order to determine the radiation impact to the biosphere due to an accidental radionuclide release associated with the rupture of a radioactive tank within the Reactor Auxiliary Building of Angra 2. After tank rupture, the radionuclides are supposed to reach the sea via the aquifer of the Angra 2 site. This radiological impact is evaluated with the aid of the activity concentration at the sea and dose received by members of the public. Activity concentration for each radionuclide is calculated according to the ANSI/ANS - 2.17 - 1980, which shows the methodology for calculation of activity concentration in the aquifer in case of accidental radionuclide releases of nuclear power plants, whereas the dose calculation follows recognized international procedures. The migration analysis for the mentioned radionuclides is performed through the aquifer and allows to estimate the maximum activity concentration near the sea boundary and the annual dose to the member of the public. Based on the safety analysis performed for the investigated case one can conclude the annual dose impact is lower than that corresponding to one year of normal operation of the Angra 2 plant. (author)

  4. Nuclear Fuel Cycle System Analysis (II)

    Energy Technology Data Exchange (ETDEWEB)

    Ko, Won Il; Kwon, Eun Ha; Yoon, Ji Sup; Park, Seong Won

    2007-04-15

    As a nation develops strategies that provide nuclear energy while meeting its various objectives, it must begin with identification of a fuel cycle option that can be best suitable for the country. For such a purpose, this paper takes four different fuel cycle options that are likely adopted by the Korean government, considering the current status of nuclear power generation and the 2nd Comprehensive Nuclear Energy Promotion Plan (CNEPP) - Once-through Cycle, DUPIC Recycle, Thermal Reactor Recycle and GEN-IV Recycle. The paper then evaluates each option in terms of sustainability, environment-friendliness, proliferation-resistance, economics and technologies. Like all the policy decision, however, a nuclear fuel cycle option can not be superior in all aspects of sustainability, environment-friendliness, proliferation-resistance, economics, technologies and so on, which makes the comparison of the options extremely complicated. Taking this into consideration, the paper analyzes all the four fuel cycle options using the Multi-Attribute Utility Theory (MAUT) and the Analytic Hierarchy Process (AHP), methods of Multi-Attribute Decision Making (MADM), that support systematical evaluation of the cases with multi- goals or criteria and that such goals are incompatible with each other. The analysis shows that the GEN-IV Recycle appears to be most competitive.

  5. Special safety requirements applied to Brazilian nuclear power plant

    International Nuclear Information System (INIS)

    Lepecki, W.P.S.; Hamel, H.J.E.; Koenig, N.; Vieira, P.C.R.; Fritzsche, J.C.

    1981-01-01

    Some safety aspects of the Angra 2 and 3 nuclear power plants are presented. An analysis of the civil and mechanical project of these nuclear power plant having in view a safety analysis is done. (E.G.) [pt

  6. Time response measurements of Rosemount Pressure Transmitters (model 3154) of Angra-1 power plant

    International Nuclear Information System (INIS)

    Santos, Roberto Carlos dos; Pereira, Iraci Martinez; Justino, Marcelo C.; Silva, Marcos C.

    2017-01-01

    This paper shows the Response of time five Rosemount model 3154N pressure transmitter from the Angra I Nuclear Power Plant. The tests were performed using the Hydraulic Ramp and Pressure Step Generator from the Sensor Response Time Measurement laboratory of CEN - Nuclear Engineering Center of IPEN. For each transmitter, damping was adjusted so that the time constant was less than or equal to 500 ms. This value has been determined so that the total value of the protection chain response time does not exceed the established maximum value of 2 seconds. For each transmitter ten tests were performed, obtaining mean values of time constant of 499.7 ms, 464.1 ms, 473.8 ms, 484.7 ms and 511.5 ms, with mean deviations 0.85%, 0.24%, 0.97%, 1.26% and 0.64% respectively. (author)

  7. Reliability of accumulators systems for Angra-I: a reavaluation

    International Nuclear Information System (INIS)

    Oliveira, L.F.S. de; Fleming, P.V.; Frutuoso e Melo, P.F.F.; Tayt-Sohn, L.C.

    1983-01-01

    A new evaluation of reliability analysis for accumulators systems of Angra-1, based on a study done in 1979/80 is done the methodology used is the same (WASH-1400). An additional point, a computer program was used to obtain the minimum cuts. (author) [pt

  8. Nuclear spectroscopy with direct relations II. Proceedings

    International Nuclear Information System (INIS)

    Throw, F. E.

    1964-01-01

    The Symposium on Nuclear Spectroscopy with Direct Reactions, sponsored and organized by Argonne National Laboratory under the auspices of the U. S. Atomic Energy Commission, was held on 9-11 March 1964 at the Center for Continuing Education, University of Chicago. The present volume contains the invited papers along with abstracts or summaries of the few short papers selected for their special relevance to the topics of the invited lecturers . Edited versions of the discussions are also included

  9. Nuclear spectroscopy with direct relations II. Proceedings

    Energy Technology Data Exchange (ETDEWEB)

    Throw, F. E. [ed.

    1964-03-01

    The Symposium on Nuclear Spectroscopy with Direct Reactions, sponsored and organized by Argonne National Laboratory under the auspices of the U. S. Atomic Energy Commission, was held on 9-11 March 1964 at the Center for Continuing Education, University of Chicago. The present volume contains the invited papers along with abstracts or summaries of the few short papers selected for their special relevance to the topics of the invited lecturers . Edited versions of the discussions are also included.

  10. Nuclear process heat system AVR-II

    International Nuclear Information System (INIS)

    Fassbender, J.; Altes, J.; Becker, S.; Bongartz, R.; Breitbach, G.; David, P.H.; Ehrhardt, K.D.; Hennings, W.; Jahn, W.; Katscher, W.; Koschmieder, D.; Kroeger, W.; Krohn, H.; Meessen, H.; Meister, G; Mertens, J.; Mohr, H.G.; Moormann, R.; Rehm, W.; Wolters, J.

    1983-03-01

    Concerning safety features, the AVR-II differs appreciably from the comprehensive systems with thermal output of several hundred megawatts that have been examined so far. The essential differences are: slender steel pressure vessel instead of a prestressed-concrete vessel; no seperate afterheat removal system; afterheat removal is possible through steel pressure vessel surface; control and shutdown over reflector rods only; little redundance of operational systems; simplified containment; areal cooler to cool the reactor cavern. Safety is basically founded on passive system characteristics; the requirements on active safety devices may therefore be reduced. The different plant design requires appropriate changes in the spectrum of incidents; in particular, there is a shift in the importance of certain typer of incidents. (orig./GL) [de

  11. Chlorination system of Angra I : generation of sodium hypochlorite from seawater, a new reality; Sistema de cloracao de Angra I: hipoclorito de sodio gerado a partir da agua do mar, uma nova realidade

    Energy Technology Data Exchange (ETDEWEB)

    Leite, Nelri Ferreira; Goncalves, Carlos Cabral [ELETROBRAS Termonuclear S.A., Rio de Janeiro, RJ (Brazil). Gerencia de Engenharia de Angra 1

    1999-11-01

    The objective of this paper is to present a study that was developed over the last two years at Angra I Nuclear Power Plant (Brazil). As a result we have chosen to change the chlorination system, replacing the actual process that utilizes chlorine gas, with on-site generation of sodium hypochlorite from seawater. The work presents the use of chlorine gas and its implications such as: industrial safety, handling, transportation, corrosion, operational and maintenance costs. It also demonstrates the sodium hypochlorite generation process from electrolysis of seawater and its aspects related to: safety operation, maintenance and costs. (author) 7 refs., 2 tabs.

  12. Analysis of the metallic containment integrity of Angra 2/3 reactor under the effects of the design basis accident

    International Nuclear Information System (INIS)

    Costa, J.R.

    1981-06-01

    The application of Condru 4 computer code, developed to determine the maximum values of pressure and temperature that occur inside the metallic containment building of PWR nuclear power plants, in case of a hypothetic accident - LOCA - considered as a Design Basic Accident - DBA. The hypothesis, input and results for the simulation of a loss of coolant in the hot leg of the Angra-2/3 reactors, considered as the most critical case for that Kind of project, are presented. The analysis was made with input provided by the manufacturer. (Author) [pt

  13. Analysis of the reliability of the active injection safety systems of Angra I

    International Nuclear Information System (INIS)

    Frutuoso e Melo, P.F.F.

    1981-01-01

    The reliability of the active emergency core cooling systems of Angra I nuclear power plant is evaluated. The fault tree analysis is employed. The unavailability of the above cited systems, is calculated. A parametric sensitivity analysis has been performed, due to the existing scattering in the failure and repair rate data of these system's components. The minimal cut sets were determined and, as a final step, a reliability importance analysis has been performed. This final step has required the development of a computer program. The methodology and data from the 'Reactor Safety Study' (Wash-1400) (in which the reliability of safety systems of a tipical PWR plant is calculated), is employed. The unavailability values for the safety systems analysed are too low, thus showing that in most cases the systems analysed are available to mitigate the effects of a loss-of-coolant accident. (Author) [pt

  14. Preliminary evaluation of the stress analysis reports for Angra I reactor coolant loop - part 1

    International Nuclear Information System (INIS)

    Ribeiro, S.V.G.; Andrade, J.E.L. de

    1980-03-01

    A methodology that will allow CNEN to approve the stress analysis reports of the components of the Brazilian nuclear power plants, was developed. The reactor coolant loop (RCL)of Angra I was checkd. This is the first part of the complete report and consists of the approval of the design documents, the approval of the equipment support models and the aproval of the steam generator dynamic model. The second part of this work is under way now and should contain the approval of the RCL stress and fatigue analysis according to ASME code section III. As shown in section 7 it appears necessary additional information from Westinghouse about the design of the RCL. (Author) [pt

  15. Unavailability of the residual system heat removal of Angra 1 by Bayesian networks considering dependent failures

    International Nuclear Information System (INIS)

    Gomes, Many R.S.; Melo, Paulo F.F.F. e

    2015-01-01

    This work models by Bayesian networks the residual heat removal system (SRCR) of Angra I nuclear power plant, using fault tree mapping for systematically identifying all possible modes of occurrence caused by a large loss of coolant accident (large LOCA). The focus is on dependent events, such as the bridge system structure of the residual heat removal system and the occurrence of common-cause failures. We used the Netica™ tool kit, Norsys Software Corporation and Python 2.7.5 for modeling Bayesian networks and Microsoft Excel for modeling fault trees. Working with dependent events using Bayesian networks is similar to the solutions proposed by other models, beyond simple understanding and ease of application and modification throughout the analysis. The results obtained for the unavailability of the system were satisfactory, showing that in most cases the system will be available to mitigate the effects of an accident as described above. (author)

  16. Measurement of the meteorological parameters in Almirante Alvaro Alberto nuclear power plant using captive balloon

    International Nuclear Information System (INIS)

    Silva Lobo, M.A. da; Lima e Silva Filho, P.P. de; Eschebach, B.M.

    1984-01-01

    A methodology to obtain the meteorological parameters in the vicinity of the Almirante Alvaro Alberto nuclear power plant is presented. The study of the atmospheric dispersion is done by the analysis of the results and it is a complement of the meteorological operation of Angra-1 and pre-operation of Angra-2 and 3 program. (M.C.K.) [pt

  17. Generic nuclear power plant component failure data bank

    International Nuclear Information System (INIS)

    Araujo Goes, A.G. de; Gibelli, S.M.O.

    1988-11-01

    This report consist in the development of a generic nuclear power plant component failure data bank. This data bank was implemented in a PC-XT microcomputer, IBM compatible, using the Open Access II program. Generic failure data tables for Westinghouse nuclear power plants and for general PWR power plants are presented. They are the final product of a research which included a preselection and a selection of data collected from the available sources in the library of CNEN (National Nuclear Energy Commission) and from the CIN/CNEN (Neclear Information Center). Futhermore, a proposal of evaluating models of average failure rates of pumps and valves are also presented. Through the electronic data bank one can easily have a generic view of failure rate ranges as well as failure models foe a certain component. It is very importante to develop procedures to collect and store generic failure data that can be quickly accessed, in order to update the Probabilistic Safety Study of Angra-1 and to used in studies which may have component failures of nuclear power plant safety systems. In the future, data specialization can be achieved by means of statistical calculations involving specific data collected from the operational experience of Angra-1 nuclear power plant and the generic data bank. (author) [pt

  18. Tools to improve Angra 1/2 general training program

    International Nuclear Information System (INIS)

    Barroso, Haroldo Jr.

    2003-01-01

    Since Brazil restarted Angra 2 construction in 1995, as a result of the studies of future energy consumption, the Training Department of Eletronuclear developed the training program for site personnel. This new situation has demanded additional efforts and new routines. In the following paragraphs there is a description of significant aspects in this concern. Most of them are now under discussion in the Training Department and some alternative solutions are being adopted in order to face the new challenges. (author)

  19. Criticality analysis for mixed thorium-uranium fuel in the Angra-2 PWR reactor using KENO-VI

    Energy Technology Data Exchange (ETDEWEB)

    Wichrowski, Caio C.; Gonçalves, Isadora C.; Oliveira, Claudio L.; Vellozo, Sergio O.; Baptista, Camila O., E-mail: wichrowski@ime.eb.br, E-mail: isadora.goncalves@ime.eb.br, E-mail: d7luiz@yahoo.com.br, E-mail: vellozo@ime.eb.br, E-mail: camila.oliv.baptista@gmail.com [Instituto Militar de Engenharia (IME), Rio de Janeiro, RJ (Brazil). Seção de Engenharia Nuclear

    2017-07-01

    The increasing energy demand associated to the current sustainability challenges have given the thorium nuclear fuel cycle renewed interest in the scientific community. Studies have focused on energy production in different reactor designs through the fission of uranium 233, the product of thorium fertilization by neutrons. In order to make it possible for near future applications a strategy based on the adaptation of current nuclear reactors for the use of thorium fuels is being considered. In this work, bearing in mind these limitations, a code was used to evaluate the effect on criticality (k{sub inf}) of the mixing of thorium and uranium in different proportions in the fuel of a PWR, the German designed Angra-2 Brazilian reactor in order to scrutinise its behaviour and determine the feasibility of an adapted ThO{sub 2}-UO{sub 2} mixed fuel cycle using current PWR technology. The analysis is performed using the KENO-VI module in the SCALE 6.1 nuclear safety analysis simulation code and the information is taken from the Angra-2 FSAR (Final Security Analysis Report). (author)

  20. Simulation of the first step of the coupling of the PARCS/RELAP5 codes to ANGRA 2 facility

    Energy Technology Data Exchange (ETDEWEB)

    Del Pozzo, Andrea Sanchez; Andrade, Delvonei A. de; Sabundjian, Gaiane, E-mail: delvonei@ipen.br, E-mail: gdjian@ipen.br [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

    2015-07-01

    Since the Three Mile Island (1979) and Chernobyl (1986) accidents, the International Agency of Energy Atomic (IAEA) has worked with the authorities of other countries that use nuclear power plants in order to guarantee the safe of those facilities. The utilities have simulated design basic accidents to verify the integrity of the nuclear power plant to these events. However, after Fukushima accident in Japan (2011), the people have felt insecure and been afraid in relation to nuclear power plants. Today, the international and national organizations, such as the International Agency of Energy Atomic (IAEA) and Comissao Nacional de Energia Nuclear (CNEN), respectively, have worked very hard to prevent some accidents and transients in nuclear power plants in order to ensure the security of the general population. In case of accidents, as the Rod Ejection Accident (REA), it is very important to do the coupling between neutronic and thermal hydraulic areas of nuclear reactors. To solve this type of problem there is the coupling between PARCS/RELAP5 codes. However, to perform this analysis it is necessary to simulate three steps. The first step is simulating the steady state of one nuclear power plant by using RELAP5 code. The second step is to run the steady state of this reactor using the coupling PARCS/RELAP5, and the final step is simulating the REA of this facility with PARCS/RELAP5 coupling. The aim of this work is to show the results of the first step of this analysis, i.e., by means of simulation the steady state of Angra 2 nuclear power plant using RELAP5 version 3.3. In this case, the modeling from the core was more detailed than in the original version developed some years ago for Angra 2. The results obtained in this work were satisfactory. (author)

  1. Farewell to the nuclear energy program

    International Nuclear Information System (INIS)

    Sangmeister, H.

    1986-01-01

    In summer 1985 Brazil, presided over by Jose Sarney, definitely decided not to go on with the building preparations for Angra III, a third nuclear power plant, and to suspend the planning and projecting of Iguape I and II (Sao Paulo). In view of decisions such as these there is no doubt about the fact that the Brazilian government soon after entering upon its office attaches but secondary importance to the establishment and extension of a national nuclear power industry. The trend already revealed in its rudiments towards the end of the last Brazilian military government of Joao Figueiredo has meanwhile taken on its definite character and direction: financial cuts and retardation of the ambitious nuclear energy program initiated in the 70s with the aim of corroborating Brazil's position as a dynamic promising industrial nation and hegemonial power of the Latin American subcontinent. (orig.) [de

  2. Experiments on radionuclide accumulation by fishes from the Angra Dos Reis region of Brazil

    International Nuclear Information System (INIS)

    Guimaraes, J.R.D.

    1988-11-01

    To follow the bioaccumulation and tissue distribution of 137 Cs and 60 Co in fish from tropical waters near the Angra nuclear power station in Brazil, juvenile grouper (Epinephelus sp.) were exposed under laboratory conditions to Angra sea water containing the two radionuclides initially added in chloride form. During the 4-month exposure period, the sea water was not changed and the fish received regular rations of non-radioactive food. Following uptake, the fish were dissected and composite tissue samples monitored for radioactivity. 137 Cs concentration factors (CFs) were 3 and 5 in whole fish and muscle, respectively. The highest concentration of 137 Cs was found in the muscle which accounted for 66% of the total body burden. In contrast, the highest concentration and greatest fraction (19%) of 60 Co was located in the liver. Whole body and muscle CFs for 60 Co, 0.2 and 0.08 respectively, were much lower than those for 137 Cs. Compared with published data, only very small amounts of both radionuclides were taken up by bone in the present study. This observation and the fact that much higher 137 Cs CFs have been reported in fish from field studies suggests that uptake through the food chain is the principal pathway for bioaccumulation in nature. Elution of freshly-prepared and previously-used radioactive sea water through chelating resins indicated that 60 Co added in the cationic form was almost totally converted to neutral or anionic forms after four months. Additional experiments carried out with the previously-used experimental media demonstrated that the possibly ligand-bound 60 Co was approximately 2.5 times more available for uptake by grouper than the cationic forms initially present. It is concluded that the uptake of 60 Co by fish exposed to radioactive effluents would be a function of the different forms of 60 Co present. 20 refs, 2 figs, 2 tabs

  3. The monitoring of the terrestrial environment around Almirante Alvaro Alberto nuclear power station

    Energy Technology Data Exchange (ETDEWEB)

    Tavares, P.G.; Souza, R.F.; Cardoso, S.N.M., E-mail: pgtares@eletronuclear.gov.b, E-mail: rfsouza@eletronuclear.gov.b, E-mail: sergion@eletronuclear.gov.b [ELETROBRAS Eletronuclear S.A., Paraty, RJ (Brazil). Lab. de Monitoracao Ambiental

    2011-07-01

    The goal of this paper is to evaluate the environmental monitoring around Almirante Alvaro Alberto Nuclear Power Station after the beginning the operation of Unit II, in July 2000. The Environmental Monitoring Laboratory (EML) has, for purpose, to monitor the environment around the station to verify if there is a potential impact caused by the operation of the units. The EML collects several environmental samples and analyses radiometrically to determine the presence of artificial radionuclides. The types of the samples are marine samples (sea water, fish, algae, beach sand and sediments), terrestrial (milk, banana, soil, grass, superficial and underground water and river water and sediment) and aerial samples (rain water, airborne for iodine and particulate). This paper only describes the monitoring of terrestrial samples. At the EML, the samples are prepared and analysed following international procedures. The samples of milk, banana, soil, grass, surface and underground water, river water and river sediment are analysed by gamma spectrometry in a multi-channel analyser GENIE-2000 System with High-purity Germanium (HpGe) detectors to determine the activities of the detectable radionuclides. The EML also analyses tritium in surface water by liquid scintillation counting. In addition, analysis of {sup 89}Sr/{sup 90}Sr, by beta counting and {sup 131}I by gamma spectrometry are performed in the processed milk. The results are, then, compared with those obtained in pre-operational time of Angra 1 (1978 - 1982) and those obtained in operational time of the units until 2010. The results show us that, from 1982 until now, there is no impact in terrestrial environment caused by the operation neither of Angra 1 nor both Angra 1 and Angra 2. (author)

  4. Thermohidraulic model for a typical steam generator of PWR Nuclear Power Plants

    International Nuclear Information System (INIS)

    Braga, C.V.M.

    1980-06-01

    A model of thermohidraulic simulation, for steady state, considering the secondary flow divided in two parts individually homogeneous, and with heat and mass transferences between them is developed. The quality of the two-phase mixture that is fed to the turbine is fixed and, based on this value, the feedwater pressure is determined. The recirculation ratio is intrinsically determined. Based on this model it was developed the GEVAP code, in Fortran-IV language. The model is applied to the steam generator of the Angra II nuclear power plant and the results are compared with KWU'S design parameters, being considered satisfactory. (Author) [pt

  5. TIBER II/ETR: Nuclear Performance Analysis Group Report

    International Nuclear Information System (INIS)

    1987-09-01

    A Nuclear Performance Analysis Group was formed to develop the nuclear technology mission of TIBER-II under the leadership of Argonne National Laboratory reporting to LLNL with major participation by the University of California - Los Angeles (test requirements, R and D needs, water-cooled test modules, neutronic tests). Additional key support was provided by GA Technologies (helium-cooled test modules), Hanford Engineering Development Laboratory (material-irradiation tests), Sandia National Laboratory - Albuquerque (high-heat-flux component tests), and the Idaho National Engineering Laboratory (safety tests). Support also was provided by Rennselaer Polytechnic Institute, Grumman Aerospace Corporation, and the Canadian Fusion Fuels Technology Program. This report discusses these areas and provides a schedule for their completion

  6. Dispersion modelling studies: the 1984 experiment in Angra dos Reis

    International Nuclear Information System (INIS)

    Martano, P.; Paschoa, A.S.

    1997-01-01

    The results of a numerical modelling of an atmospheric dispersion in Angra dos Reis (RJ, Brazil) are considered. A comparison between model results and monitored field concentrations is discussed from the point of view of its statistical as well as physical significance. Particular attention has been paid to the effects of the lack of homogeneity in the spatial scale (horizontal and vertical) and in the time scale (stationarity in the local meteorology), as they can be critical in coastal areas. Some suggestions are made about a real time modelling of the atmospheric dispersion on the considered site. (author)

  7. Neutronic calculations for Angra-1 steam line break accident

    International Nuclear Information System (INIS)

    Ponzoni Filho, Pedro; Sato, Sadakatu

    2000-01-01

    The reduction of boron concentration in the Boron Injection Tank (BIT), to the room temperature solubility level, makes necessary a reanalysis of the steam line break accident of Angra 1 NPP. This paper describes the neutronic calculation related to this reanalysis. The main steps of the work were: review of reactivity parameters used in the accident simulation; search of xenon profiles that cause the most severe core power distribution; calculation of hot channel factors and other neutronic parameters necessary for DNBR determination. The final conclusion, related to the steam line break accident, states the BIT concentration may be reduced to 2000 ppm. (author)

  8. The self assessment at ANGRA 1 NPP in Brazil

    International Nuclear Information System (INIS)

    Werdine, H. Jr.

    1996-01-01

    Angra 1 considers the Self-Assessment concept an extremely valuable tool to enhance plant safety and plant performance. A formal guidance procedure to apply this methodology does not exist at our plant and should be developed and implemented as soon as possible. Some portions of this methodology already exist with different names. The root cause analysis of in-house incident reports is a heavy portion of a sound self-assessment approach. International related experience from top performance plants should be used. International meetings, such as this one, should be convened and formal guidance from the IAEA should be written

  9. Role of nuclear hexokinase II in DNA repair

    International Nuclear Information System (INIS)

    Khanna, S.; Bhatt, A.N.; Dwarakanath, B.S.; Kalaiarasan, P.; Brahmachari, V.

    2012-01-01

    A common signature of many cancer cells is a high glucose catabolic rate primarily due to the over expression of Type II hexokinase (HKII; responsible for the phosphorylation of glucose), generally known as cytosolic and mitochondrial bound enzyme that also suppresses cell death. Although, nuclear localization and transcriptional regulation of HKII has been reported in yeast; we and few others have recently demonstrated its nuclear localization in malignant cell lines. Interestingly, modification of a human glioma cell line (BMG-1) for enhancing glycolysis through mitochondrial respiration (OPMBMG cells) resulted in a higher nuclear localization of HKII as compared to the parental cells with concomitant increase in DNA repair and radio-resistance. Further, the glucose phosphorylation activity of the nuclear HKII was nearly 2 folds higher in the relatively more radioresistant HeLa cells (human cervical cancer cell line) as compared to MRC-5 cells (human normal lung fibroblast cell line). Therefore, we hypothesize that nuclear HKII facilitates DNA repair, in a hither to unknown mechanism, that may partly contribute to the enhanced resistance of highly glycolytic cells to radiation. Sequence alignment studies suggest that the isoenzymes, HKI and HKII share strong homology in the kinase active site, which is also found in few protein kinases. Interestingly HKI has been shown to phosphorylate H2A in-vitro. Further, in-silico protein-protein interaction data suggest that HKII can interact with several DNA repair proteins including ATM. Taken together; available experimental evidences as well as in-silico predictions strongly suggest that HKII may play a role in DNA repair by phosphorylation of certain DNA repair proteins. (author)

  10. Welded joints engineering design of the primary circuit, surge line and main steam piping of the Angra 2 reactor; Projeto de engenharia das juntas soldadas do circuito primario, linha de surto e linha de vapor principal de Angra 2

    Energy Technology Data Exchange (ETDEWEB)

    Volta, Angelo Roberto; Couto, Jose Gonzalo Villaverde [NUCLEN, Rio de Janeiro, RJ (Brazil)

    1995-12-31

    The erection of nuclear systems of a Nuclear Power Station is under international requests, that results in a detailed elaboration of documents for the performance of welds. NUCLEN as an engineering design company, responsible for the erection of Angra 2, developed a suitable software program for the elaboration of welding procedure qualifications, tests and examination sequence plans and heat treatment plans applied to primary circuit, surgeline and main steam piping. The paper shows the employed methodology for the elaboration of these documents, as well as the requested engineering design of welding technology and testability in order to assure the stipulated quality level, according to requirements of the specifications, codes and norms. (author). 6 refs.

  11. Emission of 14C by the Almirante Alvaro Alberto Nuclear Power Plant 1 and 2 and their local effects on the environmental levels

    International Nuclear Information System (INIS)

    Dias, Cintia Melazo

    2006-01-01

    14 C is a is a long-lived beta-emitting nuclide (T 1/2 = 5730 years) produced naturally in the upper atmosphere as a result of reactions between neutrons and stable 14 N( 14 N(n,p) 14 C). Although in a lesser extent, nuclear power plants produce 14 C as well during their routine operation. Since it is converted in 14 CO 2 and mixed throughout the atmosphere, it is incorporated into plant tissues, via photosynthesis process, and hence in food chain. Because of the biological importance of 14 C and long half-life, it is of interest to quantify the amounts released by nuclear industry. The Brazilian nuclear central named Nuclear Central Admiral Alvaro Alberto (CNAAA) has two nuclear reactors of PWR type in operation, Angra I (657 MWe) and Angra II (1350 MWe), and one under construction, Angra III (1309 MWe PWR). The aim of this study was to determine the strength of the sources and the 14 C content in the environment through analyses of air, vegetation and soils taken within 5 km (the influenced area) of CNAAA. The thesis consists of an extensive review about the subject (part one) and of four papers (part two). The first paper is about the determination of 14 C concentrations released by reactors (source strength). For Angra I, a device was developed in order to sample the gaseous effluents and for Angra II, a commercial monitoring system had already been implemented since its initial operation (2001). The 14 C can be emitted as hydrocarbons, CO or CO 2 , depending on the type of reactor. For PWRs, the main chemical form released is hydrocarbons (80 %). The monitoring system of Angra I was planned to determine both CO 2 and hydrocarbon fractions but in Angra II, all hydrocarbons are converted to CO 2 by using a Pd/Al 2 O 3 catalyst at 450 deg C. The liquid scintillation was the method employed to measure the samples. The second one concerns the atmospheric dispersion of the released radiocarbon through measurements of air samples taken with 3 km from power plants, in

  12. Probabilistic analysis of reactor safety - The auxiliary feedwater system of Angra I

    International Nuclear Information System (INIS)

    Oliveira, L.C.R. da L.C. de.

    1981-09-01

    The unavailability of the auxiliary feedwater system (AFWS) of Angra-1, was calculated. The fault tree analysis technique was used, considering two diferent types of contribution to system unavailability: The one due to hard-ware failure and the contribution due to test and maintenance which was separately analysed. The COMBO-and SAMPLE computer codes were used. The results have shown that the AFWS of Angra-1 contains enough redundancy to guarantee a safe operation under the conditions analysed, best values having been obtained for the unavailability of AFWS of Angra 1 with those codes than with the WASH-1400. (E.G.) [pt

  13. Welded joints engineering design of the primary circuit, surge line and main steam piping of the Angra 2 reactor

    International Nuclear Information System (INIS)

    Volta, Angelo Roberto; Couto, Jose Gonzalo Villaverde

    1995-01-01

    The erection of nuclear systems of a Nuclear Power Station is under international requests, that results in a detailed elaboration of documents for the performance of welds. NUCLEN as an engineering design company, responsible for the erection of Angra 2, developed a suitable software program for the elaboration of welding procedure qualifications, tests and examination sequence plans and heat treatment plans applied to primary circuit, surgeline and main steam piping. The paper shows the employed methodology for the elaboration of these documents, as well as the requested engineering design of welding technology and testability in order to assure the stipulated quality level, according to requirements of the specifications, codes and norms. (author). 6 refs

  14. Emission of {sup 14}C by the Almirante Alvaro Alberto Nuclear Power Plant 1 and 2 and their local effects on the environmental levels; Emissao de {sup 14}C pelas unidades 1 e 2 da Central Nuclear Almirante Alvaro Alberto (CNAAA) e seu efeito local nos niveis ambientais

    Energy Technology Data Exchange (ETDEWEB)

    Dias, Cintia Melazo

    2006-07-01

    {sup 14}C is a is a long-lived beta-emitting nuclide (T{sub 1/2} = 5730 years) produced naturally in the upper atmosphere as a result of reactions between neutrons and stable {sup 14}N({sup 14}N(n,p){sup 14}C). Although in a lesser extent, nuclear power plants produce {sup 14}C as well during their routine operation. Since it is converted in {sup 14}CO{sub 2} and mixed throughout the atmosphere, it is incorporated into plant tissues, via photosynthesis process, and hence in food chain. Because of the biological importance of {sup 14}C and long half-life, it is of interest to quantify the amounts released by nuclear industry. The Brazilian nuclear central named Nuclear Central Admiral Alvaro Alberto (CNAAA) has two nuclear reactors of PWR type in operation, Angra I (657 MWe) and Angra II (1350 MWe), and one under construction, Angra III (1309 MWe PWR). The aim of this study was to determine the strength of the sources and the {sup 14}C content in the environment through analyses of air, vegetation and soils taken within 5 km (the influenced area) of CNAAA. The thesis consists of an extensive review about the subject (part one) and of four papers (part two). The first paper is about the determination of {sup 14}C concentrations released by reactors (source strength). For Angra I, a device was developed in order to sample the gaseous effluents and for Angra II, a commercial monitoring system had already been implemented since its initial operation (2001). The {sup 14}C can be emitted as hydrocarbons, CO or CO{sub 2}, depending on the type of reactor. For PWRs, the main chemical form released is hydrocarbons (80 %). The monitoring system of Angra I was planned to determine both CO{sub 2} and hydrocarbon fractions but in Angra II, all hydrocarbons are converted to CO{sub 2} by using a Pd/Al{sub 2}O{sub 3} catalyst at 450 deg C. The liquid scintillation was the method employed to measure the samples. The second one concerns the atmospheric dispersion of the released

  15. Procedure for the qualification of a manufacturer of ingot iron pieces for application in nuclear power plant components

    International Nuclear Information System (INIS)

    Rahn, K.M.M.; Jusevicius, E.; Michael, H.

    1981-01-01

    The process for the qualification of 'Sao Caetano do Sul (Acos Villares S/A)' Plant as manufacturers of ingot iron pieces for application in components of Angra 2 and Angra 3 Nuclear Power Plants, is presented. The qualification was executed by IBQN - Instituto Brasileiro de Qualidade Nuclear - the organ officially in charge of the execution of qualification of suppliers of materials for the nuclear industry. (E.G.) [pt

  16. Time series analysis of nuclear instrumentation in EBR-II

    Energy Technology Data Exchange (ETDEWEB)

    Imel, G.R.

    1996-05-01

    Results of a time series analysis of the scaler count data from the 3 wide range nuclear detectors in the Experimental Breeder Reactor-II are presented. One of the channels was replaced, and it was desired to determine if there was any statistically significant change (ie, improvement) in the channel`s response after the replacement. Data were collected from all 3 channels for 16-day periods before and after detector replacement. Time series analysis and statistical tests showed that there was no significant change after the detector replacement. Also, there were no statistically significant differences among the 3 channels, either before or after the replacement. Finally, it was determined that errors in the reactivity change inferred from subcritical count monitoring during fuel handling would be on the other of 20-30 cents for single count intervals.

  17. Time series analysis of nuclear instrumentation in EBR-II

    International Nuclear Information System (INIS)

    Imel, G.R.

    1996-01-01

    Results of a time series analysis of the scaler count data from the 3 wide range nuclear detectors in the Experimental Breeder Reactor-II are presented. One of the channels was replaced, and it was desired to determine if there was any statistically significant change (ie, improvement) in the channel's response after the replacement. Data were collected from all 3 channels for 16-day periods before and after detector replacement. Time series analysis and statistical tests showed that there was no significant change after the detector replacement. Also, there were no statistically significant differences among the 3 channels, either before or after the replacement. Finally, it was determined that errors in the reactivity change inferred from subcritical count monitoring during fuel handling would be on the other of 20-30 cents for single count intervals

  18. A reavaluation of the reliability analysis of the low pressure injection system for Angra-1

    International Nuclear Information System (INIS)

    Oliveira, L.F.S. de; Fleming, P.V.; Frutuoso e Melo, P.F.F.; Tayt-Sohn, L.C.

    1983-01-01

    The emergency core cooling system of Angra 1 is analysed aiming at the low pressure injection systems, using the fault tree technique. All the failure mode of the components are considered for this analyse. (author) [pt

  19. Nuclear material inventory estimation in solvent extraction contractors II

    International Nuclear Information System (INIS)

    Beyerlein, A.

    1987-11-01

    The effectiveness of near-real-time nuclear materials accounting in reprocessing facilities can be limited by inventory variations in the separations contactors. Investigations are described in three areas: (i) Improvements in the model that the authors have described previously for the steady state inventory estimation in mixer-settler contactors, (ii) extension for the model for steady state inventory estimation to transient inventory estimation for non-steady state conditions, and (iii) the development of a computer model CUSEP (Clemson University Solvent Extraction Program) for simulating the concentration profiles and nuclear material inventories in pulsed column contactors. Improvements in the steady state model that are described in this report are the simplification of the methods for evaluating model parameters and development of methods for reducing the equation which estimates the total inventory of the set of contactors directly. The pulsed column computer model CUSEP (Clemson University Solvent Extraction Program) was developed. Concentration profiles and inventories calculated from CUSEP are compared with measured data from pilot scale contactors containing uranium. Excellent agreement between measured and simulated data for both the concentration profile and inventories is obtained, demonstrating that the program correctly predicts the concentration dispersion caused by pulsing and the dispersed phase holdup within the contactor. Further research to investigate (i) correction of the MUF (Material Unaccounted For) and CUMUF (Cumulative Material Unaccounted For) tests for mixer-settler contactor inventory using the simplified model developed in this work, (ii) development of a simple inventory estimation model for pulsed column contactors similar to that developed for mixer-settler contactors using CUSEP to provide necessary database, and (iii) sources of bias appearing in the MUF and CUMUF tests using computer simulation techniques are planned. Refs

  20. Case study of the 3D model in ANGRA 3 project

    International Nuclear Information System (INIS)

    Faloppa, Altair A.; Elias, Marcos V.

    2015-01-01

    The 3D modeling has been increasingly used in NPP - Nuclear Power Plant from its design to its life cycle management. This paper presents experiences and developments regarding the methods applied for 3D Model in the Angra 3 NPP design using proprietary software PDS® - Plant Design System, and complementary in-house software developed by ETN. A description of the adopted methodology in all disciplines such as piping, piping support, equipment, civil, steel structure, HVAC and electrical will be detailed. The PDS® system is a comprehensive, intelligent computer-aided design/engineering application for plant design, construction, and operations. The use of PDS® and the developed tools has resulted in optimization in the design process as well as the project execution. After the design phase during the erection, commissioning and start-up of the plant, the 3D Model will be strongly helpful to obtain basic data about plant components such as piping, supports, valves, equipment and pumps. They can be easily found, opened, visualized and their properties analyzed in seconds. A corresponding data-base can also provide several different information queries. Furthermore the detailed 3D Model in the as-built condition can be used during operation and in-service inspections, reducing maintenance costs and improving safety of workers. It can also be used as an additional tool in training new operators.(author)

  1. Nuclear Technology Series. Course 17: Radiation Protection II.

    Science.gov (United States)

    Center for Occupational Research and Development, Inc., Waco, TX.

    This technical specialty course is one of thirty-five courses designed for use by two-year postsecondary institutions in five nuclear technician curriculum areas: (1) radiation protection technician, (2) nuclear instrumentation and control technician, (3) nuclear materials processing technician, (4) nuclear quality-assurance/quality-control…

  2. Design of nuclear power plants

    International Nuclear Information System (INIS)

    Lobo, C.G.

    1987-01-01

    The criteria of design and safety, applied internationally to systems and components of PWR type reactors, are described. The main criteria of the design analysed are: thermohydraulic optimization; optimized arrangement of buildings and components; low costs of energy generation; high level of standardization; application of specific safety criteria for nuclear power plants. The safety criteria aim to: assure the safe reactor shutdown; remove the residual heat and; avoid the release of radioactive elements for environment. Some exemples of safety criteria are given for Angra-2 and Angra-3 reactors. (M.C.K.) [pt

  3. Pokhran II and Beyond (Emerging Indian Nuclear Posture)

    National Research Council Canada - National Science Library

    Mishra, Jeetendra

    2002-01-01

    .... The nuclear forces, however, are sought only to be minimum possible to credibly deter nuclear weapons use or coercion against India, Considering the imperatives of the Indian deterrence posture...

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

    International Nuclear Information System (INIS)

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

  5. Review of the KBS II plan for handling and final storage of unreprocessed spent nuclear fuel

    International Nuclear Information System (INIS)

    1980-01-01

    The Swedish utilities programme for disposal of spent nuclear fuel elements (KBS II) is summarized. Comments and criticism to the programme are given by experts from several foreign or international institutions. (L.E.)

  6. NUCLEAR MYOSIN II REGULATES THE ASSEMBLY OF PREINITIATION COMPLEX FOR ICAM-1 GENE TRANSCRIPTION

    Science.gov (United States)

    Li, Qingjie; Sarna, Sushil K.

    2009-01-01

    Background and Aims Actin-myosin II motor converts chemical energy into force/motion in muscle and non-muscle cells. The phosphorylation of regulatory light chain (MLC20) is critical to the cytoplasmic functions of these motors. We do not know whether myosin II and actins in the nucleus function as motors to generate relative motion, such as that between RNA polymerase II holoenzyme and DNA, for assembly of the preinitiation complex. Methods The experiments were performed on primary cultures of human colonic circular smooth muscle cells (HCCSMCs) and rat colonic circular muscle strips. Results We show that myosin II and α- and β-actins are present in the nuclei of colonic smooth muscle cells. The nuclear myosin II is tethered to recognition sequence AGCTCC (−39/−34) in the ICAM-1 core promoter region. The actins are known to complex with RNA polymerase II and they are tethered to the nucleoskeleton. The dephosphorylation of MLC20 increases the transcription of ICAM-1, whereas its phosphorylation decreases it. Colonic inflammation suppresses nuclear MLCK, which increases the unphosphorylated form of nuclear MLC20, resulting in enhanced transcription of ICAM-1. Conclusions 1) Myosin II is a core transcription factor; 2) the phosphorylation/dephosphorylation of nuclear MLC20 results in the sliding of myosin and actin molecules past each other producing relative motion between the DNA bound to the myosin II and RNA polymerase II holoenzyme bound to actins and nucleoskeleton. PMID:19328794

  7. Systems for planning and controlling the assembly of the electric, instrumentation and control and telecommunications parts of Angra 2 and 3; Sistemas de planejamento e de acompanhamento e controle da montagem para as areas eletrica, instrumentacao e controle e telecomunicacoes de Angra 2 e 3

    Energy Technology Data Exchange (ETDEWEB)

    Andrade, Ronaldo Barata de [NUCLEN, Rio de Janeiro, RJ (Brazil)

    1993-12-31

    The management tools developed for the assembly of the mechanical and electric equipment, instrumentation and control, and telecommunication systems of Angra-2 and Angra-3 reactors are presented. These tools were adapted from similar ones used in Germany. 1 fig.

  8. Fabrication of mechanical components and piping design for Brazilian nuclear reactors

    International Nuclear Information System (INIS)

    Deppe, L.O.

    1987-01-01

    The supply of Brazilian equipment and piping design for Angra 2 (and Angra 3 in some cases) have reached an advanced status in spite of the continuous outside difficulties which affect these nuclear power plants. The achieved quality is similar to the quality achieved in foreign countries and the nationalization program foreseen in 1975 is being largely surpassed. In this paper the actual situation is presented as well as the future perspectives. (Author) [pt

  9. A model for reliability avaliation of the electrical supply source of the 1A3 and 1A4 control rods assemblies of Angra I reactor

    International Nuclear Information System (INIS)

    Yang, T.

    1978-01-01

    The reliability of the electrical power supply to the 4.16KV buses for the safety system operation of a nuclear power plant was studied. Particularly, Angra Unit I system was focused. Initially, reliability of each electrical supply source was estimated. Using a probabilistic approach based on the Markov processes, the system reliability was evaluated in terms of frequency and duration of loss of power supply and of the system failure probability evolution when one or more sources remained unavailable. Based on these results, certain reactor operating rules were proposed concerning later shutdown of the plant without compromising the nuclear reactor safety. A sensitivity analysis was also performed to show the different reliability parameter influences on final results. This analysis showed that the diesel system performs an important role in the power supply for a nuclear power plant [pt

  10. Impact evaluation of the accident with release of a PWR coolant. Case study: Angra 3

    International Nuclear Information System (INIS)

    Aguiar, Andre Silva de; Simoes Filho, Francisco Fernando Lamego; Soares, Abner Duarte; Lapa, Celso Marcelo Franklin

    2011-01-01

    It was postulated in the cooling system, a LOCA where was lost 431 m 3 of coolant. The inventory was 1.87 x 10 10 Bq/m 3 of tritium, 2.22 x 10 7 Bp/m 3 of cobalt and 3.48 x 10 8 Bq/m 3 of cesium and was launched near tue Itaorna beach, Angra dos Reis, RJ, Brazil. By applying the model in the proposed scenery (Angra 1 and 2 functioning and Angra 3 with variation of water taking and discharge with a progressive reduction after the accident), the dilution of specific activity of the radionuclides reached inferior values after 22 hours, to the reference values. After 54 hours, the levels of radionuclides, in the indirect influence are already below the minimum values of activity detected by the laboratory of environmental monitoring of the CNAAA

  11. Proton nuclear magnetic resonance and spectrophotometric studies of nickel(II)-iron(II) hybrid hemoglobins

    International Nuclear Information System (INIS)

    Shibayama, N.; Inubushi, T.; Morimoto, H.; Yonetani, T.

    1987-01-01

    Ni(II)-Fe(II) hybrid hemoglobins, α(Fe) 2 β(Ni) 2 and α(Ni) 2 β(Fe) 2 , have been characterized by proton nuclear magnetic resonance with Ni(II) protoporphyrin IX (Ni-PP) incorporated in apoprotein, which serves as a permanent deoxyheme. α(Fe) 2 β(Ni) 2 , α(Ni) 2 β(Fe) 2 , and NiHb commonly show exchangeable proton resonances at 11 and 14 ppm, due to hydrogen-bonded protons in a deoxy-like structure. Upon binding of carbon monoxide (CO) to α(Fe) 2 β(Ni) 2 , these resonances disappear at pH 6.5 to pH 8.5. On the other hand, the complementary hybrid α(Ni) 2 β(Fe-CO) 2 showed the 11 and 14 ppm resonances at low pH. Upon raising pH, the intensities of both resonances are reduced, although these changes are not synchronized. Electronic absorption spectra and hyperfine-shifted proton resonances indicate that the ligation of CO in the β(Fe) subunits induced changes in the coordination and spin states of Ni-PP in the α subunits. In a deoxy-like structure, the coordination of Ni-PP in the α subunits is predominantly in a low-spin (S = 0) four-coordination state, whereas in an oxy-like structure the contribution of a high-spin (S = 1) five-coordination state markedly increased. Ni-PP in the β subunits always takes a high-spin five-coordination state regardless of solution conditions and the state of ligation in the partner α(Fe) subunits. In the β(Ni) subunits, a significant downfield shift of the proximal histidyl N/sub δ/H resonance and a change in the absorption spectrum of Ni-PP were detected, upon changing the quaternary structure of the hybrid. The chemical shifts were analyzed in terms of the E11-Val methyls vs. the porphyrin rings in hybrid Hbs

  12. Nuclear legislation analytical study. Regulatory and institutional framework for nuclear activities in OECD member countries. Volume II

    International Nuclear Information System (INIS)

    1984-01-01

    This study is part of a series of analytical studies of the major aspects of nuclear legislation in OECD Member countries and is published in two volumes. This volume II of the study is a revision and an expansion of a 1969 study concerning the organisation and general regime governing nuclear activities. The national studies were prepared, to the extent possible, following a standard plan for all countries to facilitate information retrieval and comparison. This volume also contains tables of international conventions of relevance to the nuclear field. (NEA) [fr

  13. Aseismic design of the Heysham II Nuclear Power Station

    International Nuclear Information System (INIS)

    Day, J.W.

    1983-01-01

    A brief description of the seismic criteria established for use with the Steam Generating Heavy Water Reactor (SCHWR) and taken for the Heysham II Project is given. The qualification strategy adopted for Heysham II is described, and a brief overview is given of some of the more important design changes required for seismic purposes on that station

  14. Supervisory system for the turbine generator set of Angra 1 NPP

    International Nuclear Information System (INIS)

    Prates, Carlos L.M.; Siniscachi, Marcio R.

    2009-01-01

    The original analogue vibration monitoring system of the Steam Turbine Generator Line in Angra 1 Nuclear Power Plant had become obsolete and it was difficult to find spare parts. ELETRONUCLEAR decided to have a new digital system to substitute the original one and to provide automatic warning and prediction of developing faults. The new system was specified by the plant supporting group together with the plant engineers. It was installed to measure shaft and bearing vibrations, absolute and relative expansions as well as bearing and oil temperatures. It performs auto diagnosis, automatically interpreting all condition monitoring data to reveal and warn the staff about potential faults under development. Advanced condition monitoring may help revealing potential risks, making it possible to plan corrective actions at the scheduled production stops for safety inspections. The main goal is to increase the reliability of the production by identifying machinery problems in an early development stage and by providing the organization with information to increased safety. Already during the initial implementation phase valuable conclusions could be made for several issues such as misalignment, bearing tolerances, imbalance and bearing rub. The information directs inspections to those parts of the machine that really need it and avoids inspections where it is not required. This typically minimizes scheduled downtime for maintenance work. The system issued an automatic auto diagnosis warning about a short rub of a journal bearing during a coast down. The machine is designed to deal with these types of rub, but they should not happen repeatedly. The operators have to know about these rubs in order to conduct further analysis to determine the seriousness for future maintenance activities. The system informs whether any rubs occur, enabling them to judge whether they need to make an inspection at the next planned outage. This means, in other words, pro-active maintenance

  15. Supervisory system for the turbine generator set of Angra 1 NPP

    Energy Technology Data Exchange (ETDEWEB)

    Prates, Carlos L.M. [Eletrobras Termonuclear S.A. - ELETRONUCLEAR, Rio de Janeiro, RJ (Brazil). Dept. GAN.T], e-mail: prates@eletronuclear.gov.br; Siniscachi, Marcio R. [Eletrobras Termonuclear S.A. - ELETRONUCLEAR, Angra dos Reis , RJ (Brazil). Dept. GDU.O], e-mail: oicram@eletronuclear.gov.br

    2009-07-01

    The original analogue vibration monitoring system of the Steam Turbine Generator Line in Angra 1 Nuclear Power Plant had become obsolete and it was difficult to find spare parts. ELETRONUCLEAR decided to have a new digital system to substitute the original one and to provide automatic warning and prediction of developing faults. The new system was specified by the plant supporting group together with the plant engineers. It was installed to measure shaft and bearing vibrations, absolute and relative expansions as well as bearing and oil temperatures. It performs auto diagnosis, automatically interpreting all condition monitoring data to reveal and warn the staff about potential faults under development. Advanced condition monitoring may help revealing potential risks, making it possible to plan corrective actions at the scheduled production stops for safety inspections. The main goal is to increase the reliability of the production by identifying machinery problems in an early development stage and by providing the organization with information to increased safety. Already during the initial implementation phase valuable conclusions could be made for several issues such as misalignment, bearing tolerances, imbalance and bearing rub. The information directs inspections to those parts of the machine that really need it and avoids inspections where it is not required. This typically minimizes scheduled downtime for maintenance work. The system issued an automatic auto diagnosis warning about a short rub of a journal bearing during a coast down. The machine is designed to deal with these types of rub, but they should not happen repeatedly. The operators have to know about these rubs in order to conduct further analysis to determine the seriousness for future maintenance activities. The system informs whether any rubs occur, enabling them to judge whether they need to make an inspection at the next planned outage. This means, in other words, pro-active maintenance

  16. Thermal hydraulic and neutron kinetic simulation of the Angra 2 reactor using a RELAP5/PARCS coupled model

    Energy Technology Data Exchange (ETDEWEB)

    Reis, Patricia A.L.; Costa, Antonella L.; Hamers, Adolfo R.; Pereira, Claubia; Rodrigues, Thiago D.A.; Mantecon, Javier G.; Veloso, Maria A.F., E-mail: patricialire@yahoo.com.br, E-mail: antonella@nuclear.ufmg.br, E-mail: adolforomerohamers@hotmail.com, E-mail: claubia@nuclear.ufmg.br, E-mail: thiagodanielbh@gmail.com, E-mail: mantecon1987@gmail.com, E-mail: dora@nuclear.ufmg.br [Universidade Federal de Minas Gerais (UFMG), Belo Horizonte, MG (Brazil). Departamento de Engenharia Nuclear; Instituto Nacional de Ciencias e Tecnologia de Reatores Nucleares Inovadores (INCT/CNPq), Belo Horizonte (Brazil); Miro, Rafael; Verdu, Gumersindo, E-mail: rmiro@iqn.upv.es, E-mail: gverdu@iqn.upv.es [Universidad Politecnica de Valencia (Spain). Departamento de Ingenieria Quimica y Nuclear

    2015-07-01

    The computational advances observed in the last two decades have been provided direct impact on the researches related to nuclear simulations, which use several types of computer codes, including coupled between them, allowing representing with very accuracy the behavior of nuclear plants. Studies of complex scenarios in nuclear reactors have been improved by the use of thermal-hydraulic (TH) and neutron kinetics (NK) coupled codes. This technique consists in incorporating three-dimensional (3D) neutron modeling of the reactor core into codes, mainly to simulate transients that involve asymmetric core spatial power distributions and strong feedback effects between neutronics and reactor thermal-hydraulics. Therefore, this work presents preliminary results of TH RELAP5 and the NK PARCS calculations applied to model of the Angra 2 reactor. The WIMSD-5B code has been used to generate the macroscopic cross sections used in the NK code. The results obtained are satisfactory and represent important part of the development of this methodology. The next step is to couple the codes. (author)

  17. Specific safety aspects of the water-steam cycle important to nuclear power plant project

    International Nuclear Information System (INIS)

    Lobo, C.G.

    1986-01-01

    The water-steam cycle in a nuclear power plant is similar to that used in conventional power plants. Some systems and components are required for the safe nuclear power plant operation and therefore are designed according to the safety criteria, rules and regulations applied in nuclear installations. The aim of this report is to present the safety characteristics of the water-steam cycle of a nuclear power plant with pressurized water reactor, as applied for the design of the nuclear power plants Angra 2 and Angra 3. (Author) [pt

  18. Modeling of the core of Atucha II nuclear power plant

    International Nuclear Information System (INIS)

    Blanco, Anibal

    2007-01-01

    This work is part of a Nuclear Engineer degree thesis of the Instituto Balseiro and it is carried out under the development of an Argentinean Nuclear Power Plant Simulator. To obtain the best representation of the reactor physical behavior using the state of the art tools this Simulator should couple a 3D neutronics core calculation code with a thermal-hydraulics system code. Focused in the neutronic nature of this job, using PARCS, we modeled and performed calculations of the nuclear power plant Atucha 2 core. Whenever it is possible, we compare our results against results obtained with PUMA (the official core code for Atucha 2). (author) [es

  19. Workshop on future instruments for nuclear and particle physics and methods at the FRM-II

    International Nuclear Information System (INIS)

    Neuhaus, J.

    2002-01-01

    Conference report: The 'Workshop on Future Instruments for Nuclear and Particle Physics and Methods' at the FRM-II took place on April 12th, 2002 in Garching. The scope of the workshop was to bring together different groups of interest in the field of nuclear and particle physics as well as nuclear methods in view of the future experimental facilities at the new German neutron source FRM-II. Besides the conventional neutron sources, the FRM-II will provide new sources for neutron rich fission fragments, positrons and ultra cold neutrons. They will extend intensities from existing sources by orders of magnitude. Throughout the workshop the speakers pointed out the urgent need to start the operation of the FRM-II immediately in order not to lose this unique advantage. (orig.)

  20. Joining of Tungsten Cermet Nuclear Fuel, Phase II

    Data.gov (United States)

    National Aeronautics and Space Administration — Nuclear Thermal Propulsion (NTP) has been identified as a critical technology needed for human missions to Mars and beyond due to its increased specific impulse...

  1. Superconducting Electric Boost Pump for Nuclear Thermal Propulsion, Phase II

    Data.gov (United States)

    National Aeronautics and Space Administration — Design, fabrication, assembly and test of the Florida Turbine Technologies, Inc. (FTT) concept for a submersible, superconducting electric boost pump during Phase II...

  2. Different pathways for the nuclear import of yeast RNA polymerase II.

    Science.gov (United States)

    Gómez-Navarro, Natalia; Estruch, Francisco

    2015-11-01

    Recent studies suggest that RNA polymerase II (Pol II) has to be fully assembled before being imported into the nucleus, while other reports indicate a distinct mechanism to import large and small subunits. In yeast, Iwr1 binds to the holoenzyme assembled in the cytoplasm and directs its nuclear entry. However, as IWR1 is not an essential gene, Iwr1-independent pathway(s) for the nuclear import of Pol II must exist. In this paper, we investigate the transport into the nucleus of several large and small Pol II subunits in the mutants of genes involved in Pol II biogenesis. We also analyse subcellular localization in the presence of drugs that can potentially affect Pol II nuclear import. Our results show differences in the cellular distribution between large and small subunits when Pol II biogenesis was impaired. Our data suggest that, in addition to the fully assembled holoenzyme, Pol II subunits can be imported to the nucleus, either independently or as partial assemblies, through different pathways, including passive diffusion for the small subunits. © 2015 Elsevier B.V. All rights reserved.

  3. Analysis of environmental impact due to gaseous wastes releasing during Angra-1 operation

    International Nuclear Information System (INIS)

    Cruz, E.S. da; Kircher, E.

    1986-01-01

    The results of environmental monitoring, carried out in six terrestrial stations around the Angra-1 reactor are presented. The radiation doses were measured using calcium fluoride thermoluminescent dosemeters. A statistical treatment for data obtained by dosemeters to avoid background radiations was done. (M.C.R.) [pt

  4. Hydro - nuclear strategy in the expansion of the North and Northeast regions interconnected system

    International Nuclear Information System (INIS)

    Lima, J.O.V.

    1981-04-01

    The settlement of nuclear power plants in the North and Northeast Regions Interconnected System, taking into consideration merely economic analysis, is studied. Assuming that the system isn't connected with the Southeast Region, expansion alternatives were defined supported by an optimization model which mathematical formulation was based on a Linear Programming. The main model conditioning was the eletric energy market requirements evolution of the mentioned regions, estimated up to 2010, regarding tendencies presented by forecast elaborated by ELETROBRAS. The system was designed to assure its continuously attendance, even in the case of occurrence of a critical hidrological period, employing as generation sources hidroeletric plants and PWR nuclear power plants of 1245 MWe, similar to ANGRA II. (Author) [pt

  5. Delays in nuclear power plant construction. Volume II. Final report

    International Nuclear Information System (INIS)

    Mason, G.E.; Larew, R.E.; Borcherding, J.D.; Okes, S.R. Jr.; Rad, P.F.

    1977-01-01

    The report identifies barriers to shortening nuclear power plant construction schedules and recommends research efforts which should minimize or eliminate the identified barriers. The identified barriers include (1) Design and Construction Interfacing Problems; (2) Problems Relating to the Selection and Use of Permanent Materials and Construction Methods; (3) Construction Coordination and Communication Problems; and (4) Problems Associated with Manpower Availability and Productivity

  6. Pulsating deuterium-lithium nuclear power station II

    International Nuclear Information System (INIS)

    Fischer, A.G.

    1975-01-01

    A progressive version of the nuclear fusion reactor proposed by the same author in the German patent application 2400274 is dealt with. In the present paper a coaxial condenser of special construction is used in relation to the fusion plasma column. Furthermore, the deuterium gas bubble curtain for shockwave attenuation is produced via vertical holes in the electrode supports. (GG/LH) [de

  7. Delays in nuclear power plant construction. Volume II. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Mason, G.E.; Larew, R.E.; Borcherding, J.D.; Okes, S.R. Jr.; Rad, P.F.

    1977-12-14

    The report identifies barriers to shortening nuclear power plant construction schedules and recommends research efforts which should minimize or eliminate the identified barriers. The identified barriers include (1) Design and Construction Interfacing Problems; (2) Problems Relating to the Selection and Use of Permanent Materials and Construction Methods; (3) Construction Coordination and Communication Problems; and (4) Problems Associated with Manpower Availability and Productivity.

  8. Commercial Nuclear Steam-Electric Power Plants, Part II

    Science.gov (United States)

    Shore, Ferdinand J.

    1974-01-01

    Presents the pros and cons of nuclear power systems. Includes a discussion of the institutional status of the AEC, AEC regulatory record, routine low-level radiation hazards, transport of radioactive materials, storage of wastes, and uranium resources and economics of supply. (GS)

  9. Transient analysis models for nuclear power plants

    International Nuclear Information System (INIS)

    Agapito, J.R.

    1981-01-01

    The modelling used for the simulation of the Angra-1 start-up reactor tests, using the RETRAN computer code is presented. Three tests are simulated: a)nuclear power plant trip from 100% of power; b)great power excursions tests and c)'load swing' tests.(E.G.) [pt

  10. Analysis of some nuclear waste management options. Volume II. Appendices

    Energy Technology Data Exchange (ETDEWEB)

    Berman, L.E.; Ensminger, D.A.; Giuffre, M.S.; Koplik, C.M.; Oston, S.G.; Pollak, G.D.; Ross, B.I.

    1978-10-10

    This report describes risk analyses performed on that portion of a nuclear fuel cycle which begins following solidification of high-level waste. Risks associated with handling, interim storage and transportation of the waste are assessed, as well as the long term implications of disposal in deep mined cavities. The risk is expressed in terms of expected dose to the general population and peak dose to individuals in the population. This volume consists of appendices which provide technical details of the work performed.

  11. Recent applications of nuclear medicine in diagnostics: II part

    Directory of Open Access Journals (Sweden)

    Giorgio Treglia

    2013-04-01

    Full Text Available Introduction: Positron-emission tomography (PET and single photon emission computed tomography (SPECT are effective diagnostic imaging tools in several clinical settings. The aim of this article (the second of a 2-part series is to examine some of the more recent applications of nuclear medicine imaging techniques, particularly in the fields of neurology, cardiology, and infection/inflammation. Discussion: A review of the literature reveals that in the field of neurology nuclear medicine techniques are most widely used to investigate cognitive deficits and dementia (particularly those associated with Alzheimer disease, epilepsy, and movement disorders. In cardiology, SPECT and PET also play important roles in the work-up of patients with coronary artery disease, providing accurate information on the state of the myocardium (perfusion, metabolism, and innervation. White blood cell scintigraphy and FDG-PET are widely used to investigate many infectious/inflammatory processes. In each of these areas, the review discusses the use of recently developed radiopharmaceuticals, the growth of tomographic nuclear medicine techniques, and the ways in which these advances are improving molecular imaging of biologic processes at the cellular level.

  12. The Argentine nuclear policy: evaluation and proposals of the National Atomic Energy Commission. Privatization of the nuclear power plants and the situation of Atucha II. Addendum 1

    International Nuclear Information System (INIS)

    2001-01-01

    An analysis is made of the possible privatization of the nuclear power plants in Argentina. The urgent definition of a nuclear policy for the short, medium and long term is strongly recommended to the Government together with the conclusion of the construction of the Atucha II nuclear power plant

  13. Fabrication and Testing of Nuclear-Thermal Propulsion Ground Test Hardware, Phase II, Phase II

    Data.gov (United States)

    National Aeronautics and Space Administration — Efficient nuclear-thermal propulsion (NTP) requires heating a low molecular weight gas, typically hydrogen, to high temperature and expelling it through a nozzle....

  14. Technology development in materials working for nuclear sector and its consequences for the Brazilian market

    International Nuclear Information System (INIS)

    Volta, A.R.

    1992-01-01

    The technology transfer model adopted in materials development for Brazilian nuclear sector is described. Materials are very important for the industrial development and the National nuclear program has contributed with others areas, for example, metallurgical, siderurgical, equipment sectors, etc. Grafenrheinfeld Power Plant is used like reference plant for Angra-1, a Brazilian nuclear power plant. (M.V.M.)

  15. Cardiac nuclear medicine, part II: diagnosis of coronary artery diseas

    International Nuclear Information System (INIS)

    Polak, J.F.; Holman, B.L.

    1981-01-01

    Diagnosing coronary artery disease is difficult and requires careful consideration of the roles and limitations of the tests used. Standard ECG tests are not reliable indicators of the presence of disease in asymptomatic patients. Thallium stress testing to assess ischemia and exercise ventriculography to assess functional status of the heart are limited in sensitivity and specificity. This is the second of a three-part series on cardiac nuclear medicine. Part I (Med. Instrum., May-June, 1981) focused on the commonly used examinations in cardiac physiology and pathophysiology. Part III will focus on myocardial infarction and other cardiac diseases

  16. NUCLEBRAS' experience in the implantation of a nuclear power plants simulator

    International Nuclear Information System (INIS)

    Spitalnik, J.; Fonseca, G.

    1985-01-01

    The experiences gained by NUCLEBRAS in the setting up of a Nuclear Power Plant Simulator Training Center, cover the design and manufacture of the simulator for the Angra-2 type nuclear power plants, the training of the simulator operation and maintenance personnel, in preparation for the training of the Brazilian nuclear power plant operators, the development of the simulator training programs and materials, the temporary installation and utilization of the simulator in the FRG, including the training of operators of the Trillo nuclear power plant, in Spain. The simulator shall be finally installed in Brazil, at the vicinity of the Angra-2 site, in 1985, when it is foreseen to start the training of the Angra-2 operators. (Author) [pt

  17. Reactor building design of nuclear power plant ATUCHA II, Argentina

    International Nuclear Information System (INIS)

    Rufino, R.E.; Hermann, E.R.; Richter, E.

    1984-01-01

    It is presented the civil engineering project carried out by the joint venture Hochtief - Techint-Bignoli (HTB) for the reactor building at the Atucha II power plant (PHWR of 745 MWe) in Buenos Aires. All the other civil projects at Atucha II are also being carried out by HTB. This building has the same general characteristics of the PWR plants developed by KWU in Germany, known for the spherical steel containment 56m in diameter. Nevertheless, it differs from those principally in the equipment lay-out and the remarkable foundation depth. From the basic engineering provided by ENACE, the joint venture has had to face the challenge of designing a tridimensional structure of large size. This has necessitated using simplified models which had to be superimposed, since the use of only one spatial mode would be highly inadequate, lacking the flexibility necessary to absorb the numerous modifications that this type of project undergoes during construction. In addition, this procedure has eliminated resorting to numerous and costly computer processings. (Author) [pt

  18. Proceedings of the 1984 DOE nuclear reactor and facility safety conference. Volume II

    International Nuclear Information System (INIS)

    1984-01-01

    This report is a collection of papers on reactor safety. The report takes the form of proceedings from the 1984 DOE Nuclear Reactor and Facility Safety Conference, Volume II of two. These proceedings cover Safety, Accidents, Training, Task/Job Analysis, Robotics and the Engineering Aspects of Man/Safety interfaces

  19. Proceedings of the 1984 DOE nuclear reactor and facility safety conference. Volume II

    Energy Technology Data Exchange (ETDEWEB)

    1984-01-01

    This report is a collection of papers on reactor safety. The report takes the form of proceedings from the 1984 DOE Nuclear Reactor and Facility Safety Conference, Volume II of two. These proceedings cover Safety, Accidents, Training, Task/Job Analysis, Robotics and the Engineering Aspects of Man/Safety interfaces.

  20. CHARACTERIZATION OF FLUORESCENT NUCLEAR TRACK DETECTORS AS CRITICALITY DOSIMETERS II.

    Science.gov (United States)

    Harrison, J; Moreno, B; Van Hoey, O; Mihailescu, L-C; Vanhavere, F; Million, M; Fomenko, V; Akselrod, M

    2017-10-21

    Fluorescent nuclear track detectors (FNTDs) as criticality dosimeters for both neutrons and gamma are further characterized in terms of angular dependence and quick dose assessment. The power spectrum integral depth profiles obtained from stacks of fluorescent images acquired within FNTDs exposed to a broad spectrum neutron field at various angles are analyzed to determine a calibration curve for angular dependence. MCNPX simulations were shown to be in good agreement with experimental results. A prototype triage reader was also designed and tested for quick assessment of dose. An unfolding technique incorporating both energy dependence and angular dependence is discussed. The advantages and shortcomings of using FNTDs in the event of a criticality excursion accident are analyzed. © The Author 2017. Published by Oxford University Press. All rights reserved. For Permissions, please email: journals.permissions@oup.com.

  1. Comparative studies of the pressure - and temperature temporal behavior in the Angra I containment when submitted to the design basic accident

    International Nuclear Information System (INIS)

    Costa, J.R.

    1980-12-01

    A computer code - CONDRU 4 - was brought from Germany, that is being used for the determination of pressure - and temperature temporal behavior that occurs inside the metallic containment of PWR type reactors before the loss of coolant accident (LOCA). Simulation for Angra-1 reactor was made, considering the ocurrence of the worst postulated accident for the containment integrity. The results obtained with CONDRU 4 computer code were compared with those obtained by the CONTEMPT-LT-and COCO computer code for the same nuclear power plant. The discrepancy found among the results were due mainly to the different modes adopted in the several codes for the steam-water separation of coolant injected in the containment. (Author) [pt

  2. 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)

  3. Angra-1 operational control systems representation with RELAP5/MOD2 code; Representacao dos sistemas de controle operacional de Angra-1 com o codigo RELAP5/MOD2

    Energy Technology Data Exchange (ETDEWEB)

    Borges, Ronaldo C.; Gebrim, Anibal M. [Comissao Nacional de Energia Nuclear (CNEN), Rio de Janeiro, RJ (Brazil)

    1997-12-01

    The following automatic control systems for Angra-1 NPP were simulated with the RELAP5/MOD2 code: rod control system, steam generator level control system, feedwater bypass valve control system, pressurizer pressure control system and pressurizer level control system. The paper shows the results of two transients: a ten percent step load change and a five percent per minute ramp load change. Satisfactory quantitative and qualitative results were obtained when comparing these results with thermal-hydraulic NPP programmed-values. (author). 7 refs., 13 figs.

  4. Nuclear reactions with radioactive and stable beams (Part II)

    International Nuclear Information System (INIS)

    Aguilera R, E.F.; Martinez Q, E.; Gomez C, A.; Lizcano, D.

    2005-12-01

    At the present time there is a great interest at world level in experiments, with accelerated nuclei of short half life. The dispersion, fusion, transfer and break processes in the interaction of weakly light projectiles bounded with targets of Z great its have been object of intense recent investigation, at world level. Our group, in collaboration with the University of Notre Dame, it has measured and analyzed these processes for weakly bound systems as: 6 He + 209 Bi, 8 Li + 208 Pb, 10 Be + 208 Pb. On the other hand a research line that has wakened up great interest, it is that of studies of resonant reactions using the Inverse Kinematics technique with thick targets. The use of this technique allows to measure an entire excitation function with a single bombardment. Our group has carried out, in the ININ, preliminary bombardments for the system 12 C + 4 He. This allowed to establish the feasibility of implementing this technique in our Laboratory. The application of this and other techniques to different systems like 18 O + 4 He, 12 C + 12 C, 12 C + 16 O, 16 O + 16 O, it opens the possibility to measure the fusion of these systems at very low energy and to deepen in the knowledge of the nuclear structure and the nuclear astrophysics. In this technical report, the activities carried out by our group during the second stage of this project, considered for 2005 are described. Also in that year, our group carries out a research stay in the University of Notre Dame, during this stay, the angular distribution of the projectiles of 8 B dispersed in an enriched target of 58 Ni was measured. The same as in the previous experiments, in this occasion it was also possible to measure those angular distributions of the projectiles of 7 Be and 6 Li dispersed in this same target. In this same one our stay group participates in other three experiments proposed by collaborators of other institutions (University of Notre Dame, University of Sao Paulo), where the products of the

  5. Seismic fragility of nuclear power plant components (Phase II)

    International Nuclear Information System (INIS)

    Bandyopadhyay, K.K.; Hofmayer, C.H.; Kassir, M.K.; Pepper, S.E.

    1990-02-01

    As part of the Component Fragility Program which was initiated in FY 1985, three additional equipment classes have been evaluated. This report contains the fragility results and discussions on these equipment classes which are switchgear, I and C panels and relays. Both low and medium voltage switchgear assemblies have been considered and a separate fragility estimate for each type is provided. Test data on cabinets from the nuclear instrumentation/neutron monitoring system, plant/process protection system, solid state protective system and engineered safeguards test system comprise the BNL data base for I and C panels (NSSS). Fragility levels have been determined for various failure modes of switchgear and I ampersand C panels, and the deterministic results are presented in terms of test response spectra. In addition, the test data have been evaluated for estimating the respective probabilistic fragility levels which are expressed in terms of a median value, an uncertainty coefficient, a randomness coefficient and an HCLPF value. Due to a wide variation of relay design and the fragility level, a generic fragility level cannot be established for relays. 7 refs., 13 figs., 12 tabs

  6. Multiparticle Production in Particle and Nuclear Collisions. II

    Science.gov (United States)

    Kanki, T.; Kinoshita, K.; Sumiyoshi, H.; Takagi, F.

    The dominant phenomenon in high-energy particle and nuclear collisions is multiple production of hadrons. This had attracted may physicists in 1950's, the period of the first remarkable development of particle physics. Multiparticle production was already observed in cosmic-ray experiments and expected to be explained as a natural consequence of the strong Yukawa interaction. Statistical and hydrodynamical models were then proposed by Fermi, Landau and others. These theories are still surviving even today as a prototype of modern ``fire-ball'' models. After twenty years, a golden age came in this field of physics. It was closely related to the rapid development of accelerator facilities, especially, the invention of colliding-beam machines which yield high enough center-of-mass energies for studying reactions with high multiplicity. Abundant data on final states of multiparticle production have been accumulated mainly by measuring inclusive cross sections and multiplicity distributions. In super high-energy bar{p}p collisions at CERN S pmacr pS Collider, we confirmed the increasing total cross section and found violations of many scaling laws which seemed to be valid at lower energies. This suggests a fundamental complexity of the multiparticle phenomena and offers new materials for further development of theoretical investigations. In the same period, studies of constituent (quark-gluon) structure of hadrons had also been develped. Nowadays, pysicists believe that the quantum chromodynamics (QCD) is the fundamental law of the hadronic world. Multiparticle dynamics should also be described by QCD. We have known that the hard-jet phenomena are well explained by the perturbative QCD. On the other hand, the soft processes are considered to be non-perturbative phenomena which have not yet been solved, and related to the mechanism of the color confinement and formation of strings or color-flux tubes. Multiparticle production would offer useful information on this

  7. Evaluation of uncertainties treatment of DNBR calculation for Angra-1 reactor core

    International Nuclear Information System (INIS)

    Pontedeiro, A.C.; Galetti, M.R.S.

    1986-01-01

    The results of DNBR sensitivity analysis for NPP Angra 1 are presented in this report. Sensitivity study was carried out using computer code COBRAIIIP and all the sensitivity factors were calculated for the nominal condition as the reference case. These sensitivity factors were used according to the Westinghouse methodology 'Improved Thermal Design Procedure', to calculate a statistical uncertainty factor. In this methodology the best estimate DNBR is penalized by the uncertainty factor and compared with a statistical limit to the minimum DNBR. Westinghouse has been using this statistical uncertainty treatment in the core thermal design to get a better operation flexibility of the plant in order to keep the same design basis established in Angra 1 FSAR methodology. (Author) [pt

  8. Comparative analysis of three atmospheric dispersion coefficient systems at the Angra dos Reis, RJ, region

    International Nuclear Information System (INIS)

    Biagio, Rosa Maria de Souza

    1982-01-01

    A comparative analysis was made in this work among Pasquill-Gifford (PG) atmospheric dispersion coefficients and those determined at the Juelich and Karlsruhe sites with the purpose of suggesting which one would be the most applicable to the Angra site. Each one of the three systems was determined by different experiments, carried out over sites with diversified features. The systems of Juelich and Karlsruhe were obtained over sites with high surface roughness and from stacks (elevated releases), while the PG system was obtained over sites with a small surface roughness and from ground level releases. The results of the application of these systems at a complex site like Angra,which has a highly diversified structure encompassing sea, vegetation, predominance of light winds and stable stability classes, show that the PG system, the most used in the world, is still the best choice. (author)

  9. Sensitivity analysis on the component cooling system of the Angra 1 NPP

    International Nuclear Information System (INIS)

    Castro Silva, Luiz Euripedes Massiere de

    1995-01-01

    The component cooling system has been studied within the scope of the Probabilistic Safety Analysis of the Angra I NPP in order to assure that the proposed modelling suits as close as possible the functioning system and its availability aspects. In such a way a sensitivity analysis was performed on the equivalence between the operating modes of the component cooling system and its results show the fitness of the model. (author). 4 refs, 3 figs, 3 tabs

  10. Environmental control integrated system for abnormal conditions of CNAAA-Angra-1 operation

    International Nuclear Information System (INIS)

    Kircher, E.; Silva, R.A. da.

    1986-01-01

    A system of computer codes named NUCSICA (Calculation Nucleus of Environmental Control Integrated System) to be used in the Environmental Control Integrated System (SICA) and integrated to the supervision system of Safety Parameters (SSPS), is described. The system is based on a model compatible with local characteristics of Angra-I reactor, relating to micrometeorology, topography, population distribution and socio-economic activities. The model was constructed to foresee the environmental impact. (M.C.K.) [pt

  11. Independent Safety Assessment of the TOPAZ-II space nuclear reactor power system (Revised)

    International Nuclear Information System (INIS)

    1993-09-01

    The Independent Safety Assessment described in this study report was performed to assess the safety of the design and launch plans anticipated by the U.S. Department of Defense (DOD) in 1993 for a Russian-built, U.S.-modified, TOPAZ-II space nuclear reactor power system. Its conclusions, and the bases for them, were intended to provide guidance for the U.S. Department of Energy (DOE) management in the event that the DOD requested authorization under section 91b. of the Atomic Energy Act of 1954, as amended, for possession and use (including ground testing and launch) of a nuclear-fueled, modified TOPAZ-II. The scientists and engineers who were engaged to perform this assessment are nationally-known nuclear safety experts in various disciplines. They met with participants in the TOPAZ-II program during the spring and summer of 1993 and produced a report based on their analysis of the proposed TOPAZ-II mission. Their conclusions were confined to the potential impact on public safety and did not include budgetary, reliability, or risk-benefit analyses

  12. Nuclear reactions with radioactive and stable beams (Part II); Reacciones nucleares con haces radiactivos y estables (Parte II)

    Energy Technology Data Exchange (ETDEWEB)

    Aguilera R, E.F.; Martinez Q, E.; Gomez C, A.; Lizcano, D. [ININ, 52045 Ocoyoacac, Estado de Mexico (Mexico)

    2005-12-15

    At the present time there is a great interest at world level in experiments, with accelerated nuclei of short half life. The dispersion, fusion, transfer and break processes in the interaction of weakly light projectiles bounded with targets of Z great its have been object of intense recent investigation, at world level. Our group, in collaboration with the University of Notre Dame, it has measured and analyzed these processes for weakly bound systems as: {sup 6}He + {sup 209}Bi, {sup 8}Li + {sup 208}Pb, {sup 10}Be + {sup 208}Pb. On the other hand a research line that has wakened up great interest, it is that of studies of resonant reactions using the Inverse Kinematics technique with thick targets. The use of this technique allows to measure an entire excitation function with a single bombardment. Our group has carried out, in the ININ, preliminary bombardments for the system {sup 12}C + {sup 4}He. This allowed to establish the feasibility of implementing this technique in our Laboratory. The application of this and other techniques to different systems like {sup 18}O + {sup 4}He, {sup 12}C + {sup 12}C, {sup 12}C + {sup 16}O, {sup 16}O + {sup 16}O, it opens the possibility to measure the fusion of these systems at very low energy and to deepen in the knowledge of the nuclear structure and the nuclear astrophysics. In this technical report, the activities carried out by our group during the second stage of this project, considered for 2005 are described. Also in that year, our group carries out a research stay in the University of Notre Dame, during this stay, the angular distribution of the projectiles of {sup 8}B dispersed in an enriched target of {sup 58}Ni was measured. The same as in the previous experiments, in this occasion it was also possible to measure those angular distributions of the projectiles of {sup 7}Be and {sup 6}Li dispersed in this same target. In this same one our stay group participates in other three experiments proposed by collaborators of

  13. Human Reliability analysis for digitized nuclear power plants: Case study on the LingAo II nuclear power plant

    Energy Technology Data Exchange (ETDEWEB)

    Zou, Yan Hua; Zhang, Li [Institute of Human Factors Engineering AND Safety Management, Hunan Institute of Technology, Hengyang (China); Dai, Cao; Li, Peng Cheng; Qing, Tao [Human Factors Institute, University of South China, Hengyang (China)

    2017-03-15

    The main control room (MCR) in advanced nuclear power plants (NPPs) has changed from analog to digital control system (DCS). Operation and control have become more automated, centralized, and accurate due to the digitalization of NPPs, which has improved the efficiency and security of the system. New issues associated with human reliability inevitably arise due to the adoption of new accident procedures and digitalization of main control rooms in NPPs. The LingAo II NPP is the first digital NPP in China to apply the state-oriented procedure. In order to address issues related to human reliability analysis for DCS and DCS + state-oriented procedure, the Hunan Institute of Technology conducted a research project based on a cooperative agreement with the LingDong Nuclear Power Co. Ltd. This paper is a brief introduction to the project.

  14. Human Reliability Analysis for Digitized Nuclear Power Plants: Case Study on the LingAo II Nuclear Power Plant

    Directory of Open Access Journals (Sweden)

    Yanhua Zou

    2017-03-01

    Full Text Available The main control room (MCR in advanced nuclear power plants (NPPs has changed from analog to digital control system (DCS. Operation and control have become more automated, centralized, and accurate due to the digitalization of NPPs, which has improved the efficiency and security of the system. New issues associated with human reliability inevitably arise due to the adoption of new accident procedures and digitalization of main control rooms in NPPs. The LingAo II NPP is the first digital NPP in China to apply the state-oriented procedure. In order to address issues related to human reliability analysis for DCS and DCS + state-oriented procedure, the Hunan Institute of Technology conducted a research project based on a cooperative agreement with the LingDong Nuclear Power Co. Ltd. This paper is a brief introduction to the project.

  15. Moraceae da Ilha Grande, Angra dos Reis, Rio de Janeiro, Brasil. Moraceae of Ilha Grande, Angra dos Reis, Rio de Janeiro, Brazil.

    Directory of Open Access Journals (Sweden)

    Leandro Cardoso PEDERNEIRAS

    2012-06-01

    Full Text Available Este trabalho apresenta o levantamento florístico das espécies nativas de Moraceae ocorrentes na Ilha Grande, município de Angra dos Reis, Estado do Rio de Janeiro, Brasil. Com base na análise de coleções científicas, revisão da literatura e excursões a campo, foram registradas 11 espécies nativas: Brosimum guianense, Dorstenia arifolia, Ficus adhatodifolia, F. arpazusa, F. cyclophylla, F. gomelleira, F. nevesiae, F. organensis, F. pulchella, Sorocea hilarii, S. guilleminiana. Apresentamos, também, a chave de identificação para os táxons, descrições, ilustrações, informações sobre a distribuição geográfica e comentários sobre as espécies. This work presents a floristic survey of native species of Moraceae occurring in Ilha Grande, municipality of Angra dos Reis, Rio de Janeiro state, Brazil. It was based on analysis of herbarium collections, literature review and the field excursions, resulting in 11 native species: Brosimum guianense, Dorstenia arifolia, Ficus adhatodifolia, F. arpazusa, F. cyclophylla, F. gomelleira, F. nevesiae, F. organensis, F. pulchella, Sorocea hilarii, S. guilleminiana. We also present the identification key to the taxa, descriptions, illustrations, information about geographic distribution and comments on these species that enriched the results.

  16. Lists I and II, nuclear medical diagnostics. As of January 18, 1983

    International Nuclear Information System (INIS)

    1983-01-01

    The information booklet presents the guidelines of the Federal Association of Panel Doctors, concerning the minimum equipment required for nuclear medical diagnostics practices (nuclear medical equipment guidelines), in the amended version of May 18, 1981; it also contains the list I (modern commercially available equipment) and the list II (older types of equipment). The devices specified in these lists are products of firms that are members of the ZVEI, and are in compliance with the guidelines of the Panel Doctors' Association. Combinations of older computer equipment/cameras with up-to-date equipment, also come up to the standards given in the guidelines if specifically mentioned therein. The list of manufacturers gives addresses of the manufacturers of the equipment stated in list I and II. An appendix up-dates the information to the date of October 1, 1986. (orig./HP) [de

  17. 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

    International Nuclear Information System (INIS)

    2000-01-01

    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

  18. Temperature variation on the Mediterranean Sea by the exploitation of the Vandellos II Nuclear Power Plant

    International Nuclear Information System (INIS)

    Villarreal Romero, M.; Ribes Hernandez, G.; Esparza Martin, J. L.

    2010-01-01

    The aim of this study is to verify the compliance with the Resolution of 7th February MAH/285/2007 Departament de Medi Ambient I Habitatge de la Generalitat de Catalunya establishing discharges limits to the Mediterranean Sea and, in particular, the section that references the thermal rise. The study area include about 1.5 km coastline, which is located in the vicinity of the Vandellos II Nuclear Power Plant.

  19. Nuclear warning: the dangerous obscure arguments. Is the History repeating again?

    International Nuclear Information System (INIS)

    Zylbersztajn, D.; Bernini, E.J.

    1993-01-01

    Some considerations about the continuity of Angra-2 Nuclear Power Plant building are presented, with a warning by the authors to the environment and human dangers involved. The real cost and investments for nuclear power in Brazil are also described. (C.G.C.)

  20. Nuclear indecision: loss in the past and a risk for the future

    International Nuclear Information System (INIS)

    Mattos, Joao Roberto Loureiro de; Dias, Marcio Soares; Vasconcelos, Vanderley de; Jordao, Elizabete

    2006-01-01

    Presently the Brazil have a new opportunity exploring the nuclear option for providing a more diversification and reliability to the brazilian electric system and the first step is the conclusion of Angra 3, followed by another nuclear installations, giving priority to the northeast of the country which is the region with lack of primary sources and therefore with risk of deficit

  1. Impact evaluation of the accident with release of a PWR coolant. Case study: Angra 3; Avaliacao do impacto de acidente com liberacao do refrigerante de reator PWR. Estudo de caso: Angra 3

    Energy Technology Data Exchange (ETDEWEB)

    Aguiar, Andre Silva de; Simoes Filho, Francisco Fernando Lamego; Soares, Abner Duarte; Lapa, Celso Marcelo Franklin, E-mail: flamego@ien.gov.b, E-mail: asoares@cnen.gov.b, E-mail: lapa@ien.gov.b [Instituto de Engenharia Nuclear (IEN/CNEN-RJ), Rio de Janeiro, RJ (Brazil)

    2011-10-26

    It was postulated in the cooling system, a LOCA where was lost 431 m{sup 3} of coolant. The inventory was 1.87 x 10{sup 10} Bq/m{sup 3} of tritium, 2.22 x 10{sup 7} Bp/m{sup 3} of cobalt and 3.48 x 10{sup 8} Bq/m{sup 3} of cesium and was launched near tue Itaorna beach, Angra dos Reis, RJ, Brazil. By applying the model in the proposed scenery (Angra 1 and 2 functioning and Angra 3 with variation of water taking and discharge with a progressive reduction after the accident), the dilution of specific activity of the radionuclides reached inferior values after 22 hours, to the reference values. After 54 hours, the levels of radionuclides, in the indirect influence are already below the minimum values of activity detected by the laboratory of environmental monitoring of the CNAAA

  2. The problem of licensing and safety of nuclear power plants

    International Nuclear Information System (INIS)

    Silva, R.A. da.

    1987-01-01

    The historical evolution of licensing process of nuclear power plants is presented. The designs carried out by FURNAS for constructing Angra-1 reactor and its contribution to the Brazilian CNEN in de licensing process, are evaluated. The aims of FURNAS Research Programs are determined and the safety goals are established. (M.C.K.) [pt

  3. Nuclear Shell Structure and Beta Decay I. Odd A Nuclei II. Even A Nuclei

    Science.gov (United States)

    Mayer, M.G.; Moszkowski, S.A.; Nordheim, L.W.

    1951-05-01

    In Part I a systematics is given of all transitions for odd A nuclei for which sufficiently reliable data are available. The allowed or forbidden characters of the transitions are correlated with the positions of the initial and final odd nucleon groups in the nuclear shell scheme. The nuclear shells show definite characteristics with respect to parity of the ground states. The latter is the same as the one obtained from known spins and magnetic moments in a one-particle interpretation. In Part II a systematics of the beta transitions of even-A nuclei is given. An interpretation of the character of the transitions in terms of nuclear shell structure is achieved on the hypothesis that the odd nucleon groups have the same structure as in odd-A nuclei, together with a simple coupling rule between the neutron and proton groups in odd-odd nuclei.

  4. Approval tests in a nuclear power plant

    International Nuclear Information System (INIS)

    Barreto, V.; Rolf, F.

    1984-01-01

    The supplier contract of a Nuclear Power plant establishes the values of Netto electrical Power, specific heat rate and the steam humidity at the outlet of the steam generator. Based on the Nuclear Plant Angra 2 and 3 (1300 MW) the methodology of evaluation and execution of the tests is shown as well as the location of the measuring instruments and the results of the measurements including tolerances. (Author) [pt

  5. 14N nuclear quadrupole interaction in Cu(II) doped L-alanine

    International Nuclear Information System (INIS)

    Murgich, J.; Calvo, R.; Oseroff, S.B.; Instituto Venezolano de Investigaciones Cientificas, Caracas. Dept. de Quimica)

    1980-01-01

    The 14 N nuclear quadrupole interaction tensor Psub(N) measured by ENDOR in Cu(II) doped L-alanine is analyzed in terms of the Townes and Daily theory assuming a tetra-hedrally bonded N atom. The results of this analysis are compared with those for the 14 N in pure L-alanine and it is found that the principal directions of the Psub(N) tensor are drastically changed upon metal complexation as a consequence of the higher electron affinity of Cu(II) with respect to C and H. Comparison of the corresponding bond populations in pure and Cu(II) doped L-alanine indicates that the Cu draws 0.11 more electron from the N than the substituted H atom. (orig.)

  6. Multi-Nuclear NMR Investigation of Nickel(II), Palladium(II), Platinum(II) and Ruthenium(II) Complexes of an Asymmetrical Ditertiary Phosphine

    Energy Technology Data Exchange (ETDEWEB)

    Raj, Joe Gerald Jesu [Institut National de la Recherche Scientifique, Quebec (China); Pathak, Devendra Deo [Indian School of Mines, Dhanbad (India); Kapoor, Pramesh N. [Univ. of Delhi, Delhi (India)

    2013-12-15

    Complexes synthesized by reacting alkyl and aryl phosphines with different transition metals are of great interest due to their catalytic properties. Many of the phosphine complexes are soluble in polar solvents as a result they find applications in homogeneous catalysis. In our present work we report, four transition metal complexes of Ni(II), Pd(II), Pt(II) and Ru(II) with an asymmetrical ditertiaryphosphine ligand. The synthesized ligand bears a less electronegative substituent such as methyl group on the aromatic nucleus hence makes it a strong σ-donor to form stable complexes and thus could effectively used in catalytic reactions. The complexes have been completely characterized by elemental analyses, FTIR, {sup 1}HNMR, {sup 31}PNMR and FAB Mass Spectrometry methods. Based on the spectroscopic evidences it has been confirmed that Ni(II), Pd(II) and Pt(II) complexes with the ditertiaryphosphine ligand showed cis whereas the Ru(II) complex showed trans geometry in their molecular structure.

  7. Survey II of public and leadership attitudes toward nuclear power development in the United States

    International Nuclear Information System (INIS)

    Anon.

    1976-01-01

    In August 1975, Ebasco Services Incorporated released results of a survey conducted by Louis Harris and Associates, Inc. to determine attitudes of the American public and its leaders toward nuclear power development in the U.S. Results showed, among other things, that the public favored building nuclear power plants; that they believed we have an energy shortage that will not go away soon; that they were not willing to make environmental sacrifices; and that, while favoring nuclear power development, they also had concerns about some aspects of nuclear power. Except for the environmental group, the leadership group felt the same way the public does. A follow-up survey was made in July 1976 to measure any shifts in attitudes. Survey II showed that one of the real worries that remains with the American public is the shortage of energy; additionally, the public and the leaders are concerned about the U.S. dependence on imported oil. With exception of the environmentalists, the public and its leaders support a host of measures to build energy sources, including: solar and oil shale development; speeding up the Alaskan pipeline; speeding up off-shore drilling; and building nuclear power plants. The public continues to be unwilling to sacrifice the environment. There is less conviction on the part of the public that electric power will be in short supply over the next decade. The public believes the days of heavy dependence on oil or hydroelectric power are coming to an end. By a margin of 3 to 1, the public favors building more nuclear power plants in the U.S., but some concerns about the risks have not dissipated. Even though the public is worried about radioactivity escaping into the atmosphere, they consider nuclear power generation more safe than unsafe

  8. COMURHEX II, a 610 million euro investment to meet tomorrow's nuclear power needs

    International Nuclear Information System (INIS)

    2007-01-01

    The worldwide development of nuclear power will lead to increasing demands for uranium. To meet its customers' growing requirements, AREVA has chosen to invest in COMURHEX II to renew and modernize its industrial conversion tool. An entirely new plant is to be built on the Tricastin site to the north of the existing COMURHEX plant. The plant, together with other large-scale investment projects such as the future Georges Besse II enrichment plant - also located on the Tricastin site - and the modernization of the FBFC fuel fabrication facilities in the south of France, will enable AREVA to strengthen its position as a long-standing and fully integrated player at the Front End of the nuclear fuel cycle. These major investments confirm the group's strong commitment to the global development of nuclear power. Converting uranium ore into uranium hexafluoride (UF 6 ) is a key stage before the enrichment and fabrication of nuclear fuel. AREVA is gearing up for market changes, increasing its uranium production from 15,000 tons per year to 21,000 tons per year to match market needs. Today the conversion units of the different industrial operators are showing their age. They will need replacing in the medium term to increase production capacity and keep abreast of the economic, regulatory and environmental conditions of tomorrow's market. Its euros 610 million investment in the Narbonne and Pierrelatte sites in southern France will make AREVA the first uranium converter to overhaul its industrial tool. Thus indicating the group's intention of remaining world leader in UF 6 conversion. The COMURHEX II project will involve the modernization and upgrading of our installations on the basis of tried-and-tested processes and techniques, while incorporating technological innovations that will improve the production performance, reinforce nuclear safety in the facilities, while further reducing the environmental impact of their activities. The first industrial production on the

  9. Comparison between theoretical values foreseen and measured during the commissioning of second cycle of Angra-1

    International Nuclear Information System (INIS)

    Angelkorte, G.; Dias, A.M.; Sakai, M.

    1988-01-01

    The purpose of this paper is to present the most important results of the comparison of the data measured during the start-up tests for the second cycle of Angra 1 with the calculated values for this cycle. This short comparison considered the following quantities: Critical boron concentration, Control rod worths, Isothermal temperature coefficient, Reaction rates of the incore detector system. The calculated results showed good agreement with the measured ones remaining within the acceptation criteria limits, confirming the fuel management calculations for the second cycle, namely that for the reload scheme obtained, the core is capable of operating at nominal power safety and without restrictions. (author) [pt

  10. Failures probability calculation of the energy supply of the Angra-1 reactor rods assembly

    International Nuclear Information System (INIS)

    Borba, P.R.

    1978-01-01

    This work analyses the electric power system of the Angra I PWR plant. It is demonstrated that this system is closely coupled with the safety engineering features, which are the equipments provided to prevent, limit, or mitigate the release of radioactive material and to permit the safe reactor shutdown. Event trees are used to analyse the operation of those systems which can lead to the release of radioactivity following a specified initial event. The fault trees technique is used to calculate the failure probability of the on-site electric power system [pt

  11. Decreased nuclear matrix DNA topoisomerase II in human leukemia cells resistant to VM-26 and m-AMSA

    International Nuclear Information System (INIS)

    Fernandes, D.J.; Danks, M.K.; Beck, W.T.

    1990-01-01

    CEM leukemia cells selected for resistance to VM-26 (CEM/VM-1) are cross-resistant to various other DNA topoisomerase II inhibitors but not to Vinca alkaloids. Since DNA topoisomerase II is a major protein of the nuclear matrix, the authors asked if alterations in nuclear matrix topoisomerase II might be important in this form of multidrug resistance. Pretreatment of drug-sensitive CEM cells for 2 h with either 5 μM VM-26 or 3 μM m-AMSA reduced the specific activity of newly replicated DNA on the nuclear matrix by 75 and 50%, respectively, relative to that of the bulk DNA. The decatenating and unknotting activities of DNA topoisomerase II were 6- and 7-fold lower, respectively, in the nuclear matrix preparations from the CEM/VM-1 cells compared to parental CEM cells. Western blot analysis revealed that the amount of immunoreactive topoisomerase II in the nuclear matrices of the CEM/VM-1 cells decreased 3.2-fold relative to that in CEM cells. Increasing the NaCl concentration used in the matrix isolation procedure from 0.2 to 1.8 M resulted in a progressive decrease in the specific activity of topoisomerase II in matrices of CEM/VM-1 but not CEM cells, which suggested that the association of the enzyme with the matrix is altered in the resistant cells. These data support the hypothesis that resistance to VM-26 and m-AMSA is directly related to the decreased activity of nuclear matrix topoisomerase II. In CEM/VM-1 cells the interaction of either VM-26 or m-AMSA with nuclear matrix topoisomerase II is specifically diminished

  12. Fishes of Saco do Piraquara de Fora, in a discharge area of liquid effluents from Angra-1 Nuclear Power Plant (CNAAA); Peixes do Saco Piraquara de Fora, ocorrentes na area sob influencia dos efluentes liquidos da CNAAA - indicador biologico e radiologico

    Energy Technology Data Exchange (ETDEWEB)

    Almeida, Ademar Ferrari Vaz de; Santoro, Maria Dulce Novaes [Furnas Centrais Eletricas S.A., Angra dos Reis, RJ (Brazil). Lab. de Monitoracao Ambiental

    1996-07-01

    Because the thermal effluents, released from the Unit I condenser system, it was implanted, at discharge area (Saco Piraquara de Fora), a Marine Fauna and Flora Monitoring Program, been necton area part of this, to verify possible impact over fish population, quantitative and qualitative studies were performed. Trichiurus lipeturus and Diapterus rhombeus were chosen as indicators because the high frequencies and abundances. Besides this, Furnas implanted a Radiological Monitoring Program, where samples of fish were collected and analysed by gamma spectrometry, showing the presence of Cs-137 since the pre-operational period, caused by fall out process at the region, from nuclear weapons test at atmosphere. (author)

  13. 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.)

  14. METHUSELAH II - A Fortran program and nuclear data library for the physics assessment of liquid-moderated reactors

    International Nuclear Information System (INIS)

    Brinkworth, M.J.; Griffiths, J.A.

    1966-03-01

    METHUSELAH II is a Fortran program with a nuclear data library, used to calculate cell reactivity and burn-up in liquid-moderated reactors. It has been developed from METHUSELAH I by revising the nuclear data library, and by introducing into the program improvements relating to nuclear data, improvements in efficiency and accuracy, and additional facilities which include a neutron balance edit, specialised outputs, fuel cycling, and fuel costing. These developments are described and information is given on the coding and usage of versions of METHUSELAH II for the IBM 7030 (STRETCH), IBM 7090, and KDF9 computers. (author)

  15. Nuclear fission, today and tomorrow. From renaissance to technological breakthrough (generation IV) - Part II

    International Nuclear Information System (INIS)

    Van Goethem, Georges

    2010-01-01

    This paper is an overview of the current Euratom FP-7 research and training actions in innovative nuclear fission reactors and fuel cycle technologies, including partitioning and transmutation. It is based on the more than 40 invited lectures that were delivered by research project coordinators and by keynote speakers at the FISA-2009 Conference, organised by the European Commission DG Research/Euratom. The education and training programmes in nuclear fission and radiation protection are also discussed, aiming at continuously increasing the level of nuclear competences across the EU. It is necessary to consider the most recent nuclear fission technologies (Generations of Nuclear Power Plants): - GEN II: safety and reliability of nuclear facilities and energy independence; - GEN III: continuous improvement of safety and reliability, and increased industrial competitiveness in a growing energy market; - GEN IV: for increased sustainability, and proliferation resistance. The focus in this paper is on the design objectives and research issues associated to Generations IV systems that have been agreed upon internationally. Their benefits are discussed according to a series of ambitious criteria or technology goals established at the international level. One will have to produce not only electricity at lower costs but also heat at very high temperatures, while exploiting a maximum of fissile and fertile matters, and recycling all actinides, under safe and reliable conditions. Scientific viability studies and technological performance tests for each Generation IV system are now being carried out in many laboratories world-wide, in line with the intergovernmental GIF agreement. The ultimate phase of commercial deployment is foreseen for 2040. (orig.)

  16. Study and application of ANISN and DOT-II nuclear cores in reactor physics problems

    International Nuclear Information System (INIS)

    Dias, Artur Flavio

    1980-01-01

    To solve time-independent neutrons and/or gamma rays transport problems in nuclear reactors, two codes available at IPEN were studied and applied to solve benchmark problems. The ANISN code solves the one-dimensional Boltzmann transport equation for neutrons or gamma rays, in plane, spherical, or cylindrical geometries. The DOT-II code solves the same equation in two-dimensional space for plane, cylindrical and circular geometries. General anisotropic scattering allowed in both codes. Moreover, pointwise convergence criteria, and alternate step function difference equations are also used in order to remove the oscillating flux distributions, sometimes found in discrete ordinates solutions. Basic theories and numerical techniques used in these codes are studied and summarized. Benchmark problems have been solved using these codes. Comparisons of the results show that both codes can be used with confidence in the analysis of nuclear problems. (author)

  17. Combined Electrical, Optical and Nuclear Investigations of Impurities and Defects in II-VI Semiconductors

    CERN Multimedia

    2002-01-01

    % IS325 \\\\ \\\\ To achieve well controlled bipolar conductivity in II-VI semiconductors represents a fundamental problem in semiconductor physics. The doping problems are controversely discussed, either in terms of self compensation or of compensation and passivation by unintentionally introduced impurities. \\\\ \\\\It is the goal of our experiments at the new ISOLDE facility, to shed new light on these problems and to look for ways to circumvent it. For this aim the investigation of impurities and native defects and the interaction between each other shall be investigated. The use of radioactive ion beams opens the access to controlled site selective doping of only one sublattice via nuclear transmutation. The compensating and passivating mechanisms will be studied by combining nuclear, electrical and optical methods like Perturbed Angular Correlation~(PAC), Hall Effect~(HE), Deep Level Transient Spectroscopy~(DLTS), Photoluminescence Spectroscopy~(PL) and electron paramagnetic resonance (EPR). \\\\ \\\\We intend to ...

  18. Potential safety enhancements to nuclear plant control: proof testing at EBR-II

    International Nuclear Information System (INIS)

    Lindsay, R.W.; Chisholm, G.H.

    1984-01-01

    Future changes in nuclear plant control and protective systems will reflect an evolutionary improvement through increased use of computers coupled with a better integration of man and machine. Before improvements can be accepted into the licensed commercial plant environment, significant testing must be accomplished to answer safety questions and to prove the worth of new ideas. The Experimental Breeder Reactor-II (EBR-II) is being used as a test-bed for both in-house development and testing for others in a DOE sponsored Man-Machine Integration program. The ultimate result of the development and testing would be a control system for which safety credit could be taken in the licensing process

  19. Concept and structure of instrumentation and control of the Atucha II nuclear power plant

    International Nuclear Information System (INIS)

    Garzon, D.; Roca, J.L.

    1987-01-01

    The general structure of instrumentation and control of Atucha II nuclear power plant as well as the technologies used, are described: concepts of functional decentralization and physical centralization; concept of functional group and functional complex; description of the technologies used (physical support) in the project of plant instrumentation and control; description of the different automation levels on the basis of concepts of control interface, automatism, regulation, group and subgroup controls; principles of signal conditioning; concept of announcement of alarms and state: supervisory computer, description of HAS (Hard wired Alarm System) and CAS (Computer Alarm System); application of the above mentioned structure to the project of another type of plants. (Author)

  20. Transient analysis of rod drop accident for third fuel cycle for Angra-1 reactor using SACI2/MOD0

    International Nuclear Information System (INIS)

    Atayde, P.A. de.

    1989-01-01

    The rod drop accident for 3 0 fuel cycle of Angra-1 reactor is analysed, evaluating de position effect of detectors on the measurement of reactor power. The transient calculation was done using SAC12/MOD0 code for thermo-hydraulic analysis of reactor core, aiming to evaluate safe conditions during the accident. (M.C.K.)

  1. Work responsability evaluation of a nuclear power plant operator during an emergency event

    International Nuclear Information System (INIS)

    Silva, Nilo Garcia da

    2002-01-01

    In this work, a method to evaluate the Man - Machine Interface, using the Model of Human Process utilized by the Combustion Engineer-CE was used in the Licensing Process of a Nuclear Power Plant, applying methodology in the emergency procedure of a SGTR for Angra 1 NPP. The time needed for the operators to perform the tasks step by step in this procedure was calculated. This time was compared to that found in the GOMS model, by which it is possible to perform an evaluation of workload for this accident. The criteria of the Standard ANSI/58.8-1994 was used to establish the reaction and execution times for these tasks. Practical measures in a Angra 2 NPP full scope simulator were done some steps of the SGTR emergency procedure. The time evaluation in the GOMS model has identified that three was a concentration of tasks, with the execution time near the limits regulated in the Standard above as compared with the times from the CE methodology. Finally, after a comparison of the results from Angra 1 and Angra 2, recommendations were done to the Angra 1 NPP utility in order to improve these identified points. (author)

  2. Development of a safety parameter supervision system for Angra-1

    International Nuclear Information System (INIS)

    Silva, R.A. da; Thome Filho, Z.D.; Schirru, R.; Martinez, A.S.; Oliveira, L.F.S. de

    1986-01-01

    The Safety Parameter Supervision System (SSPS) which is a computerized system for monitoring essential parameters in real time, determining the safety status and emergency procedures for returning normal reactor operation, in case of an anomaly occurrence, is presented. The SSPS consists of three sub-systems: Integrated parameter monitoring system which gives to operators an integrated vision of values of a parameter set, able to detect any deviation of normal reactor operation; safety critical function system which evaluates safety status in terms of a safety critical function set appointed in advance, and in case of violation of any critical function, it initiates the adequate emergency procedure to return normal operation; and safety parameter computer system which carries out the arquirement of analogic and digital control signals of nuclear power plant. (M.C.K.) [pt

  3. Compact sodium cooled nuclear power plant with fast core (KNK II- Karlsruhe), Safety Report

    International Nuclear Information System (INIS)

    1977-09-01

    After the operation of the KNK plant with a thermal core (KNK I), the installation of a fast core (KNK II) had been realized. The planning of the core and the necessary reconstruction work was done by INTERATOM. Owner and customer was the Nuclear Research Center Karlsruhe (KfK), while the operating company was the Kernkraftwerk-Betriebsgesellschaft mbH (KBG) Karlsruhe. The main goals of the KNK II project and its special experimental test program were to gather experience for the construction, the licensing and operation of future larger plants, to develop and to test fuel and absorber assemblies and to further develop the sodium technology and the associated components. The present safety report consists of three parts. Part 1 contains the description of the nuclear plant. Hereby, the reactor and its components, the handling facilities, the instrumentation with the plant protection, the design of the plant including the reactor core and the nominal operation processes are described. Part 2 contains the safety related investigation and measures. This concerns the reactivity accidents, local cooling perturbations, radiological consequences with the surveillance measures and the justification of the choice of structural materials. Part three finally is the appendix with the figures, showing the different buildings, the reactor and its components, the heat transfer systems and the different auxiliary facilities [de

  4. Phase II: Field Detector Development For Undeclared/Declared Nuclear Testing For Treaty Verfiation Monitoring

    Energy Technology Data Exchange (ETDEWEB)

    Kriz, M. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Hunter, D. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Riley, T. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

    2015-10-02

    Radioactive xenon isotopes are a critical part of the Comprehensive Nuclear Test Ban Treaty (CTBT) for the detection or confirmation of nuclear weapons tests as well as on-site treaty verification monitoring. On-site monitoring is not currently conducted because there are no commercially available small/robust field detector devices to measure the radioactive xenon isotopes. Xenon is an ideal signature to detect clandestine nuclear events since they are difficult to contain and can diffuse and migrate through soils due to their inert nature. There are four key radioxenon isotopes used in monitoring: 135Xe (9 hour half-life), 133mXe (2 day half-life), 133Xe (5 day half-life) and 131mXe (12 day half-life) that decay through beta emission and gamma emission. Savannah River National Laboratory (SRNL) is a leader in the field of gas collections and has developed highly selective molecular sieves that allow for the collection of xenon gas directly from air. Phase I assessed the development of a small, robust beta-gamma coincidence counting system, that combines collection and in situ detection methodologies. Phase II of the project began development of the custom electronics enabling 2D beta-gamma coincidence analysis in a field portable system. This will be a significant advancement for field detection/quantification of short-lived xenon isotopes that would not survive transport time for laboratory analysis.

  5. Generation IV nuclear energy systems: road map and concepts. 2. Generation II Measurement Systems for Generation IV Nuclear Power Plants

    International Nuclear Information System (INIS)

    Miller, Don W.

    2001-01-01

    need for substantial research. As we consider I and C systems in Generation IV reactors, we have the opportunity to take a much less 'timid' design philosophy than was taken in the design of I and C systems in the ALWRs. We need to make use of advanced technology to design an I and C system for the Generation IV multi-unit plant designs currently being considered. Such a design should accomplish the following: 1. provides for multi-unit control; 2. contributes to a plant design objective of a very low core damage frequency; 3. maximizes plant thermal efficiency (>50%); 4. maximizes plant capacity factor (>90%); 5. optimizes operability; 6. maximizes maintainability; 7. provides for on-line monitoring, calibration, and diagnostics; 8. provides optimum response to disturbances; 9. provides excellent load-following capability. When we consider the current situation in operating Generation I and II nuclear power plants and even Generation III ALWR design, we conclude that Generation IV reactors should employ at least Generation II measurement systems. Let us first consider data transmission, which is a form of communication, and ask the question: Do new communication-transferring methods by electrons flow in copper wires? The obvious answer is no. Virtually all new communication systems are using some electromagnetic method, such as light, microwaves, HF or VHF radio signals, and virtually no copper wires. When we envision Generation IV nuclear power plants, we should minimize the use of copper wires for data transmission. We should transmit data primarily by fiber optics and various wireless methods, some of which can penetrate thick barriers. Now let us consider sensors. If we use light for data transmission, then we should also use optical-based sensors. We should also take advantage of microprocessors, which provide opportunities to embed 'intelligence' in the sensor that can be used to increase accuracy, stability, and tolerance to external stressors (i.e., radiation

  6. Distribution of the sea surface temperature in the area of the Angra dos Reis Power Plant: final report for missions 1,2 and 3

    International Nuclear Information System (INIS)

    Stevenson, M.R.; Inostrosa V, H.M.; Steffen, C.A.

    1984-02-01

    This final report presents results from a cooperative study between CNPq/INPE and CNEN, to monitor spatial and temporal variations on sea surface temperature in the vicinity of Angra dos Reis power plant. (author)

  7. Concept of voltage monitoring for a nuclear power plant emergency power supply system (PWR 1300 MWe)

    International Nuclear Information System (INIS)

    Andrade, R.B. de

    1988-01-01

    Voltage monitoring concept for a Nuclear Power Plant Emergency Power Supply Systems (PWR 1300 MWe) is described based on the phylosophy adopted for Angra 2 and 3 NPP's. Some suggested setpoints are only guidance values and can be modified during plant commissioning for a better performance of the whole protection system. (author) [pt

  8. Nuclear knowledge management at the IAEA

    International Nuclear Information System (INIS)

    Yanev, Y.

    2004-01-01

    Nuclear Knowledge Management as a part of the IAEA mission and its aim to help organizations to achieve competitive advantage; costs reduction; accelerated time to market in companies and large private sector organisations; innovation, supports error free decision making are discussed. The most important outputs such as nuclear knowledge management methodology; identifying endangered areas of nuclear science and technology; developing knowledge repositories; knowledge preservation technology; dedicated projects with Member States, (Atucha, Angra, KNK2, ) are presented. A brief review of the currently implemented with Agency's assistance project ANENT (Asian Network for Education in Nuclear Technology) is also given

  9. Nuclear proliferation and civilian nuclear power. Report of the Nonproliferation Alternative Systems Assessment Program. Volume II. Proliferation resistance

    International Nuclear Information System (INIS)

    1980-06-01

    The purpose of this volume is limited to an assessment of the relative effects that particular choices of nuclear-power systems, for whatever reasons, may have on the possible spread of nuclear-weapons capabilities. This volume addresses the concern that non-nuclear-weapons states may be able to initiate efforts to acquire or to improve nuclear-weapons capabilities through civilian nuclear-power programs; it also addresses the concern that subnational groups may obtain and abuse the nuclear materials or facilities of such programs, whether in nuclear-weapons states (NWS's) or nonnuclear-weapons states (NNW's). Accordingly, this volume emphasizes one important factor in such decisions, the resistance of nuclear-power systems to the proliferation of nuclear-weapons capabilities

  10. A weldability study of the structural steel of the Angra II reactor containment

    International Nuclear Information System (INIS)

    Santos Pinto, M. dos.

    1980-01-01

    A weldability study of the german steel WSTE-51 based on mechanical, metallographic, hardness as well as special tests such as the CTS, the Tekken, for cold cracking, and the Vinckier test for reheat cracking is presented. The welding process used was the manual metal arc with low hydrogen eletrodes. In order to broaden the scope of this study the properties of weldments fabricated by submerged arc welding with high and low heat input were analized by means of mechanical and metallographic tests. The results showed that the joints had good quality and emphasize the necessity of special care in order to avoid cold cracking as well as the use of a temperbead in order to avoid reheat cracking. The submerged arc welding study concludes that higher impact resistance in the HAZ is obtained with low heat imput. (Author) [pt

  11. ALPHA/PHOENIX-P/ANC system validation for Angra-1 neutronic calculations

    International Nuclear Information System (INIS)

    Ponzoni Filho, Pedro; Sato, Sadakatu; Santos, Teresinha Ipojuca Cardoso; Fernandes, Vanderlei Borba; Fetterman, R.J.

    1995-01-01

    The ALPHA/PHOENIX-P/ANC (APA) code package is an advanced neutronic calculation system for pressurized water reactor (PWR). PHOENIX-P generates the required cross sections for the fuel, burnable absorbers, control rods and baffle/reflector region. The ALPHA code is used to automate the generation of these cross-sections as well as process the PHOENIX-P results to generate the ANC model input. ANC is a three dimensional advanced nodal code used for the modeling of the, depletion of the fuel in the core, and for the calculation of power distributions, rod worths and other reactivity parameters. This paper provides brief overview of the APA methodology for reload core design of Angra Unit 1 Cycles 1 and 2. Results included are predicted power distributions, control rod worths and other reactivity parameters compared to plant measurements. These results demonstrate that the APA system can be used for the reload core design. (author). 7 refs, 9 figs

  12. Determination of the protection set-points lines for the Angra-1 reactor core

    International Nuclear Information System (INIS)

    Furieri, E.B.

    1980-03-01

    In this work several thermo-hidraulic calculation were performed to obtain Protection set-points lines for the Angra-1 reactor core in order to compare with the values presented by the vendor in the FSAR. These lines are the locus of points where DNBR min = 1,3 and power = 1,18 x P nominal as a function of ΔT m and T m , the temperature difference and the average coolant temperature between hot and cold legs. A computation scheme was developed using COBRA-IIIF as a subroutine of a new main program and adding new subroutines in order to obtain the desired DNBR. The solution is obtained through a convergentce procedure using parameters estimated in a sensivity study. (author) [pt

  13. Reliability analysis of the recirculation phase of the safety injection system of Angra-1

    International Nuclear Information System (INIS)

    Rivera, R.R.J.M.

    1981-09-01

    The calculation of several reliability parameters-failure probability, unavailability and unreliability - of the recirculation phase of the safety injection system of Angra-1, was done. This system has two distinct modes of operation (short term and long term) which were fault tree analysed both separately and as a whole. To obtain quantitative results the computer codes SAMPLE and PRET-KITT were utilized. The former was used to consider the uncertainties in the failure data (drawn integrally from WASH-1400) and the latter to obtain time dependent unreliability values. Hardware failures and common-mode failures were considered. Altough the analysis methods employed here differ somewhat from those used in WASH-1400, the results which could be compared were found to have the order of magnitude. A viability study of some suggestions of system's modifications was performed, and it has shown that some significant reliability improvements can be achieved with reasonably simple changes. (Author) [pt

  14. ALPHA/PHOENIX-P/ANC system validation for Angra-1 neutronic calculations

    Energy Technology Data Exchange (ETDEWEB)

    Ponzoni Filho, Pedro; Sato, Sadakatu; Santos, Teresinha Ipojuca Cardoso; Fernandes, Vanderlei Borba [FURNAS, Rio de Janeiro, RJ (Brazil); Fetterman, R.J. [Westinghouse Electric Corp., Pittsburgh, PA (United States)

    1995-12-31

    The ALPHA/PHOENIX-P/ANC (APA) code package is an advanced neutronic calculation system for pressurized water reactor (PWR). PHOENIX-P generates the required cross sections for the fuel, burnable absorbers, control rods and baffle/reflector region. The ALPHA code is used to automate the generation of these cross-sections as well as process the PHOENIX-P results to generate the ANC model input. ANC is a three dimensional advanced nodal code used for the modeling of the, depletion of the fuel in the core, and for the calculation of power distributions, rod worths and other reactivity parameters. This paper provides brief overview of the APA methodology for reload core design of Angra Unit 1 Cycles 1 and 2. Results included are predicted power distributions, control rod worths and other reactivity parameters compared to plant measurements. These results demonstrate that the APA system can be used for the reload core design. (author). 7 refs, 9 figs.

  15. Probabilistic safety analysis of the containment spray system of Angra-1 reactor

    International Nuclear Information System (INIS)

    Gibelli, S.M.O.

    1981-02-01

    The calculation of the unavailability of the containment spray system of Angra-1, is done. The referred system has two different modes of operation (injection and recirculation) which were separately studied using the fault tree methodology. Besides equipment and human error failures, the contributions of test, maintenance and common-mode failures have also been considered. The quantitative evaluation was carried out by the computer code SAMPLE, which considers the uncertainties in the failures data and gives a distribution for the top event unavailability. The input data were obtained from the well-known Rasmussen Report. An importance analysis of the basic events of the trees was performed and a study of the viability of some suggestions for system design modification was also conducted. A comparison between the results obtained in this work and the corresponding ones in the Rasmussen Report has shown the fact that the unavailability of both systems are of the same order of magnitude. (Author) [pt

  16. Experience gathered from the transport of a fuel element prototype of the CNA-II (Atucha-II nuclear power plant) type

    International Nuclear Information System (INIS)

    Pastorini, A.; Belinco, C.G.; El Bis, E.D.; Sacchi, M.A.; Mayans, C.O.; Martin Ghiselli, A.; Marcora, G.R.

    1990-01-01

    This work describes the needs to materialize the transport of a fuel element prototype of the CNA-II (Atucha-II nuclear power plant) type, under special conditions, from the Fabrication Pilot Plant sited at the Constituyentes Atomic Center and the Ezeiza Atomic Center, for its subsequent analysis at the High Pressure Experimental Loop. The special conditions under which the transport has been made responded to the fact that the prototype presents a fragile adjustment between rods and separators, necessary to be preserved. (Author) [es

  17. Comparative analysis of three atmospheric dispersion coefficient systems at the Angra dos Reis, RJ, region; Analise comparativa de tres sistemas de coeficientes de dispersao atmosferica na regiao de Angra dos Reis, RJ

    Energy Technology Data Exchange (ETDEWEB)

    Biagio, Rosa Maria de Souza

    1982-07-01

    A comparative analysis was made in this work among Pasquill-Gifford (PG) atmospheric dispersion coefficients and those determined at the Juelich and Karlsruhe sites with the purpose of suggesting which one would be the most applicable to the Angra site. Each one of the three systems was determined by different experiments, carried out over sites with diversified features. The systems of Juelich and Karlsruhe were obtained over sites with high surface roughness and from stacks (elevated releases), while the PG system was obtained over sites with a small surface roughness and from ground level releases. The results of the application of these systems at a complex site like Angra,which has a highly diversified structure encompassing sea, vegetation, predominance of light winds and stable stability classes, show that the PG system, the most used in the world, is still the best choice. (author)

  18. Calculation of Departure from Nucleate Boiling Ratio (DNBR) minimum for accident analysis of main steam line break at Angra-1; Calculo do minimo DNBR para analise do acidente de ruptura da linha principal de vapor em Angra-1

    Energy Technology Data Exchange (ETDEWEB)

    Machado, Marcio Dornellas [ELETROBRAS Termonuclear S.A. (ELETRONUCLEAR), Rio de Janeiro, RJ (Brazil). E-mail: mdorne@eletronuclear.gov.br

    2000-07-01

    The maintenance costs, the operational problems and the failures possibilities of the boron injection system, composed by pumps, valves, heated lines and the boron injection tank, make this tank removal or the boron concentration reduction advisable for Angra 1 Power Plant. The main accident from chapter XV of the final safety analysis report affected by this modification is the main steam line break. It is necessary the interaction of the areas of Accidents and Transients Analysis (RETRAN 02/Mod 5.1 code), Neutronics (APA System) and Thermohydraulics (COBRA IIIC/MIT) to analyse this accident. The present Angra 1 boron concentration is 20000 ppm and it could be reduced to 2000 ppm as a result of the present study. The Departure from Nucleate Boiling Ratio (DNBR) is the restrictive parameter of this accident, which is calculated from the initials and boundary conditions obtained from the Transients and Accidents Analysis and Neutronics areas. (author)

  19. Measurement of Nuclear Recoils in the CDMS II Dark Matter Search

    Energy Technology Data Exchange (ETDEWEB)

    Fallows, Scott Mathew [Univ. of Minnesota, Minneapolis, MN (United States)

    2014-12-01

    The Cryogenic Dark Matter Search (CDMS) experiment is designed to directly detect elastic scatters of weakly-interacting massive dark matter particles (WIMPs), on target nuclei in semiconductor crystals composed of Si and Ge. These scatters would occur very rarely, in an overwhelming background composed primarily of electron recoils from photons and electrons, as well as a smaller but non-negligible background of WIMP-like nuclear recoils from neutrons. The CDMS II generation of detectors simultaneously measure ionization and athermal phonon signals from each scatter, allowing discrimination against virtually all electron recoils in the detector bulk. Pulse-shape timing analysis allows discrimination against nearly all remaining electron recoils taking place near detector surfaces. Along with carefully limited neutron backgrounds, this experimental program allowed for \\background- free" operation of CDMS II at Soudan, with less than one background event expected in each WIMP-search analysis. As a result, exclusionary upper-limits on WIMP-nucleon interaction cross section were placed over a wide range of candidate WIMP masses, ruling out large new regions of parameter space.

  20. SNMSP II: A system to fully automate special nuclear materials accountability reporting for electric utilities

    International Nuclear Information System (INIS)

    Pareto, V.; Venegas, R.

    1987-01-01

    The USNRC requires each licensee who is authorized to possess Special Nuclear Materials (SNM) to prepare and submit reports concerning SNM received, produced, possessed, transferred, consumed, disposed of, or lost. These SNM accountability reports, which need to be submitted twice a year, contain detailed information on the origin, quantity, and type of SNM for several locations. The amount of detail required makes these reports very time consuming and error prone when prepared manually. Yankee Atomic is developing an IBM PC-based computer code that fully automates the process of generating SNM accountability reports. The program, called SNMSP II, prints a number of summaries including facsimiles of the NRC/DOE-741, 742, 742C, and RW-859 reports in a format that can be submitted directly to the NRC/DOE. SNMSP II is menu-driven and is especially designed for people with little or no computer training. Input can be either from a mainframe-based corporate data base or manually through user-friendly screens. In addition, extensive quality assurance features are available to ensure the security and accuracy of the data. This paper discusses the major features of the code and describes its implementation at Yankee

  1. Tri- and tetra-nuclear polypyridyl ruthenium(II) complexes as antimicrobial agents.

    Science.gov (United States)

    Gorle, Anil K; Feterl, Marshall; Warner, Jeffrey M; Wallace, Lynne; Keene, F Richard; Collins, J Grant

    2014-11-28

    A series of inert tri- and tetra-nuclear polypyridylruthenium(II) complexes that are linked by the bis[4(4'-methyl-2,2'-bipyridyl)]-1,n-alkane ligand ("bb(n)" for n = 10, 12 and 16) have been synthesised and their potential as antimicrobial agents examined. Due to the modular nature of the synthesis of the oligonuclear complexes, it was possible to make both linear and non-linear tetranuclear ruthenium species. The minimum inhibitory concentrations (MIC) of the ruthenium(II) complexes were determined against four strains of bacteria--Gram positive Staphylococcus aureus (S. aureus) and methicillin-resistant S. aureus (MRSA), and Gram negative Escherichia coli (E. coli) and Pseudomonas aeruginosa (P. aeruginosa). In order to gain an understanding of the relative antimicrobial activities, the cellular uptake and water-octanol partition coefficients (log P) were determined for a selection of the ruthenium complexes. Although the trinuclear complexes were the most lipophilic based upon log P values and showed the greatest cellular uptake, the linear tetranuclear complexes were generally more active, with MIC values complexes were slightly more lipophilic and were taken up to a greater extent by the bacteria, they were consistently less active than their linear counterparts. Of particular note, the cellular accumulation of the oligonuclear ruthenium complexes was greater in the Gram negative strains compared to that in the Gram positive S. aureus and MRSA. The results demonstrate that the lower antimicrobial activity of polypyridylruthenium(II) complexes towards Gram negative bacteria, particularly P. aeruginosa, is not strongly correlated to the cellular accumulation but rather to a lower intrinsic ability to kill the Gram negative cells.

  2. Characterization of topoisomerase I and II activities in nuclear extracts during callogenesis in immature embryos of Zea mays.

    Science.gov (United States)

    Carballo, M; Giné, R; Santos, M; Puigdomènech, P

    1991-01-01

    We have characterized the topoisomerase I and II activities in nuclear extracts from immature embryos of Zea mays and the effect of the treatment with 2,4-dichlorophenoxyacetic acid (2,4-D) and abscisic acid (ABA). These extracts were shown to be essentially devoid of protease and nuclease activities and they were tested for their ability to relax supercoiled DNA, unknotting P4 DNA and catenate circular duplex DNA under catalytic conditions. Unknotting and catenation reactions are strictly magnesium- and ATP-dependent, but not the relaxation of circular supercoiled DNA allowing the detection of both topoisomerase I and II activities. Two cytotoxic drugs, camptothecin, a plant alkaloid that inhibits eukaryotic topoisomerase I, and epipodophyllotoxin VM-26 (teniposide) that inhibits topoisomerase II, have been assayed in our extracts showing similar inhibitory effects on topoisomerase enzymes. Alkaline phosphatase treatment of nuclear extracts abolishes both topoisomerase activities. Nuclear extracts from embryos treated with 2,4-D showed 200% increase on topoisomerase II activity as compared with untreated ones, but only residual activity was detected in ABA-treated embryos. Nuclear extracts from hormone-treated and untreated embryos showed similar topoisomerase I activity with deviations of less than 25%. These differences are discussed in terms of possible post-translational modifications of the enzymes associated with the increase in proliferation activity of calli.

  3. Genetic association analysis of 13 nuclear-encoded mitochondrial candidate genes with type II diabetes mellitus: The DAMAGE study

    DEFF Research Database (Denmark)

    Reiling, Erwin; van Vliet-Ostaptchouk, Jana V; van 't Riet, Esther

    2009-01-01

    Mitochondria play an important role in many processes, like glucose metabolism, fatty acid oxidation and ATP synthesis. In this study, we aimed to identify association of common polymorphisms in nuclear-encoded genes involved in mitochondrial protein synthesis and biogenesis with type II diabetes...

  4. Safety Evaluation Report related to the final design approval of the GESSAR II BWR/6 Nuclear Island design, Docket No. 50-447

    International Nuclear Information System (INIS)

    1983-04-01

    The Safety Evaluation Report for the application filed by General Electric Company for the Final Design Approval for the General Electric Standard Safety Analysis Report (GESSAR II FSAR) has been prepared by the Office of Nuclear Reactor Regulation of the Nuclear Regulatory Commission. This report summarizes the results of the staff's safety review of the GESSAR II BWR/6 Nuclear Island Design. Subject to favorable resolution of items discussed in the Safety Evaluation Report, the staff concludes that the facilities referencing GESSAR II, subject to approval of the balance-of-plant design, can conform with the provisions of the Act and the regulations of the Nuclear Regulatory Commission

  5. Safety Evaluation Report related to the final design approval of the GESSAR II BWR/6 Nuclear Island Design (Docket No. 50-447). Supplement No. 3

    International Nuclear Information System (INIS)

    1985-01-01

    Supplement 3 to the Safety Evaluation Report (SER) for the application filed by General Electric Company for the final design approval for the GE BWR/6 nuclear island design has been prepared by the Office of Nuclear Reactor Regulation of the Nuclear Regulatory Commission. This report supplements the GESSAR II SER (NUREG-0979), issued in April 1983, summarizing the results of the staff's safety review of the GESSAR II BWR/6 nuclear island design. Subject to favorable resolution of the items discussed in this supplement, the staff concludes that the GESSAR II design satisfactorily addresses the severe-accident concerns described in draft NUREG-1070

  6. Concept of voltage and frequency monitoring for a nuclear power plant normal power supply system - PWR 1300 MWe

    International Nuclear Information System (INIS)

    Andrade, R.B. de

    1990-01-01

    Voltage and frequency monitoring concept for a Nuclear Power Plant Normal Power Supply System (PWR 1300 MWe) is described based on the phylosophy adopted for Angra 2 and e NPP's. Some suggested setpoints are only guidance values and can be modified during plant commissioning for a better performance of the whole protection system. (author) [pt

  7. SCOPE 28: Environmental consequences of nuclear war. Volume II. Ecological and agricultural effects

    International Nuclear Information System (INIS)

    Harwell, M.A.; Hutchinson, T.C.; Cropper, W.P. Jr.; Harwell, C.C.; Grover, H.D.

    1985-01-01

    This book presents papers on the environmental and biological impacts of nuclear weapons. Topics considered include ecological principles relevant to nuclear war, the vulnerability of ecological systems to the climatic effects of nuclear war, additional potential effects of nuclear war on ecological systems, the potential effects of nuclear war on agricultural productivity, food availability after nuclear war, experiences and extrapolations from Hiroshima and Nagasaki, and the integration of effects on human populations

  8. The Gpn3 Q279* cancer-associated mutant inhibits Gpn1 nuclear export and is deficient in RNA polymerase II nuclear targeting.

    Science.gov (United States)

    Barbosa-Camacho, Angel A; Méndez-Hernández, Lucía E; Lara-Chacón, Bárbara; Peña-Gómez, Sonia G; Romero, Violeta; González-González, Rogelio; Guerra-Moreno, José A; Robledo-Rivera, Angélica Y; Sánchez-Olea, Roberto; Calera, Mónica R

    2017-11-01

    Gpn3 is required for RNA polymerase II (RNAPII) nuclear targeting. Here, we investigated the effect of a cancer-associated Q279* nonsense mutation in Gpn3 cellular function. Employing RNAi, we replaced endogenous Gpn3 by wt or Q279* RNAi-resistant Gpn3R in epithelial model cells. RNAPII nuclear accumulation and transcriptional activity were markedly decreased in cells expressing only Gpn3R Q279*. Wild-type Gpn3R localized to the cytoplasm but a fraction of Gpn3R Q279* entered the cell nucleus and inhibited Gpn1-EYFP nuclear export. This property and the transcriptional deficit in Gpn3R Q279*-expressing cells required a PDZ-binding motif generated by the Q279* mutation. We conclude that an acquired PDZ-binding motif in Gpn3 Q279* caused Gpn3 nuclear entry, and inhibited Gpn1 nuclear export and Gpn3-mediated RNAPII nuclear targeting. © 2017 Federation of European Biochemical Societies.

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

    International Nuclear Information System (INIS)

    Ferreira, P.S.B.

    1988-01-01

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

  10. Aging of snubbers in nuclear service: Phase I study results and Phase II plans

    International Nuclear Information System (INIS)

    Goodman, R.L.; Bush, S.H.; Page, R.E.

    1988-01-01

    Two major research areas were investigated in the Phase I snubber aging studies. The first area involved a preliminary evaluation of the effects of various aging mechanisms on snubber operation; failure modes of mechanisms were identified and their contributions to aging degradation were assessed relative to other failure modes. The second area involved estimating the efficacy of existing tests and examinations that are intended to determine the effects of aging and degradation. Available data on snubber behavior and operating experience were reviewed, using licensee event reports and other historical data for the 10-year period from 1973 through 1983. Value-impact was considered in terms of (1) exposure of workers to radioactive environments for examination/testing and (2) the cost for expansion of the snubber testing program due to failed snubbers. Results from the Phase I studies identified the need to modify or improve examination and testing procedures to enhance snubber reliability. Based on the results of the Phase I snubber studies, the seals and fluids were identified as the two principal elements affected by aging degradation in hydraulic snubbers. Phase II work, which was initiated in FY 1987, will develop cooperative activities between PNL and operating utilities through the Snubber Utility Group (SNUG), who will work to establish a strong data and experience base for both hydraulic and mechanical snubbers based on actual operating and maintenance history at nuclear power plants. Application guidelines for snubbers will be recommended based on the study results

  11. The development of the nuclear physics in Latvia II. The building of the Research Nuclear Reactor IRT

    International Nuclear Information System (INIS)

    Ulmanis, U.

    2004-01-01

    Nuclear research reactor IRT of the Academy of Sciences was built near Riga in Salaspils. IRT is pool aqueous - aqueous reactor with nuclear fuel U-235 contained elements, located in the core at a depth of ∼ 7 m under distilled water. Ten horizontal and 10-15 vertical experimental channels are employed in experimental research with the use of neutron fluxes. For the research with gamma rays is constructed radiation loop facility with liquid In-Ga-SN solid solution as intensive gamma-ray sources. Main activities of IRT are to conduct research in nuclear spectroscopy, neutron activation analysis, neutron diffraction and radiation physics, chemistry and biology. (authors)

  12. MAP kinase-signaling controls nuclear translocation of tripeptidyl-peptidase II in response to DNA damage and oxidative stress

    International Nuclear Information System (INIS)

    Preta, Giulio; Klark, Rainier de; Chakraborti, Shankhamala; Glas, Rickard

    2010-01-01

    Research highlights: → Nuclear translocation of TPPII occurs in response to different DNA damage inducers. → Nuclear accumulation of TPPII is linked to ROS and anti-oxidant enzyme levels. → MAPKs control nuclear accumulation of TPPII. → Inhibited nuclear accumulation of TPPII decreases DNA damage-induced γ-H2AX expression. -- Abstract: Reactive oxygen species (ROS) are a continuous hazard in eukaroytic cells by their ability to cause damage to biomolecules, in particular to DNA. Previous data indicated that the cytosolic serine peptidase tripeptidyl-peptidase II (TPPII) translocates into the nucleus of most tumor cell lines in response to γ-irradiation and ROS production; an event that promoted p53 expression as well as caspase-activation. We here observed that nuclear translocation of TPPII was dependent on signaling by MAP kinases, including p38MAPK. Further, this was caused by several types of DNA-damaging drugs, a DNA cross-linker (cisplatinum), an inhibitor of topoisomerase II (etoposide), and to some extent also by nucleoside-analogues (5-fluorouracil, hydroxyurea). In the minority of tumor cell lines where TPPII was not translocated into the nucleus in response to DNA damage we observed reduced intracellular ROS levels, and the expression levels of redox defense systems were increased. Further, treatment with the ROS-inducer γ-hexa-chloro-cyclohexane (γ-HCH, lindane), an inhibitor of GAP junctions, restored nuclear translocation of TPPII in these cell lines upon γ-irradiation. Moreover, blocking nuclear translocation of TPPII in etoposide-treated cells, by using a peptide-derived inhibitor (Z-Gly-Leu-Ala-OH), attenuated expression of γ-H2AX in γ-irradiated melanoma cells. Our results indicated a role for TPPII in MAPK-dependent DNA damage signaling.

  13. MAP kinase-signaling controls nuclear translocation of tripeptidyl-peptidase II in response to DNA damage and oxidative stress

    Energy Technology Data Exchange (ETDEWEB)

    Preta, Giulio; Klark, Rainier de; Chakraborti, Shankhamala [Center for Molecular Medicine (CMM), Department of Medicine, Karolinska Institutet, Karolinska University Hospital, 171 76 Stockholm (Sweden); Glas, Rickard, E-mail: rickard.glas@ki.se [Center for Molecular Medicine (CMM), Department of Medicine, Karolinska Institutet, Karolinska University Hospital, 171 76 Stockholm (Sweden)

    2010-08-27

    Research highlights: {yields} Nuclear translocation of TPPII occurs in response to different DNA damage inducers. {yields} Nuclear accumulation of TPPII is linked to ROS and anti-oxidant enzyme levels. {yields} MAPKs control nuclear accumulation of TPPII. {yields} Inhibited nuclear accumulation of TPPII decreases DNA damage-induced {gamma}-H2AX expression. -- Abstract: Reactive oxygen species (ROS) are a continuous hazard in eukaroytic cells by their ability to cause damage to biomolecules, in particular to DNA. Previous data indicated that the cytosolic serine peptidase tripeptidyl-peptidase II (TPPII) translocates into the nucleus of most tumor cell lines in response to {gamma}-irradiation and ROS production; an event that promoted p53 expression as well as caspase-activation. We here observed that nuclear translocation of TPPII was dependent on signaling by MAP kinases, including p38MAPK. Further, this was caused by several types of DNA-damaging drugs, a DNA cross-linker (cisplatinum), an inhibitor of topoisomerase II (etoposide), and to some extent also by nucleoside-analogues (5-fluorouracil, hydroxyurea). In the minority of tumor cell lines where TPPII was not translocated into the nucleus in response to DNA damage we observed reduced intracellular ROS levels, and the expression levels of redox defense systems were increased. Further, treatment with the ROS-inducer {gamma}-hexa-chloro-cyclohexane ({gamma}-HCH, lindane), an inhibitor of GAP junctions, restored nuclear translocation of TPPII in these cell lines upon {gamma}-irradiation. Moreover, blocking nuclear translocation of TPPII in etoposide-treated cells, by using a peptide-derived inhibitor (Z-Gly-Leu-Ala-OH), attenuated expression of {gamma}-H2AX in {gamma}-irradiated melanoma cells. Our results indicated a role for TPPII in MAPK-dependent DNA damage signaling.

  14. Utilization of a full-scope simulation for training the operating personel of nuclear power plants

    International Nuclear Information System (INIS)

    Mathias, S.G.

    1987-01-01

    A full-scope simulator of the Angra-2 Nuclear Power Plant has been installed at the NUCLEBRAS Training Center in Mambucaba - close to the site where that Plant is being built -, the goal of providing training for the operating personnel of the KWU-design nuclear power plants to be installed in Brazil. Due to the delays which occurred in the construction of Angra-2, NUCLEBRAS has established an extensive program for the utilization of the simulator for the training of operators for German nuclear power plants and for Spain's Trillo Plant. Besides yielding profits to NUCLEBRAS, that program is resulting in considerable experience in the area of nuclear power plant operators' training generating international recognition to the NUCLEBRAS Training Center. (Author) [pt

  15. 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)

  16. Incorporation of severe accidents in the licensing of nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Alvarenga, Marco Antonio Bayout; Rabello, Sidney Luiz, E-mail: bayout@cnen.gov.b, E-mail: sidney@cnen.gov.b [Comissao Nacional de Energia Nuclear (CNEN) Rio de Janeiro, RJ (Brazil)

    2011-07-01

    Severe accidents are the result of multiple faults that occur in nuclear power plants as a consequence from the combination of latent failures and active faults, such as equipment, procedures and operator failures, which leads to partial or total melting of the reactor core. Regardless of active and latent failures related to the plant management and maintenance, aspects of the latent failures related to the plant design still remain. The lessons learned from the TMI accident in the U.S.A., Chernobyl in the former Soviet Union and, more recently, in Fukushima, Japan, suggest that severe accidents must necessarily be part of design-basis of nuclear power plants. This paper reviews the normative basis of the licensing of nuclear power plants concerning to severe accidents in countries having nuclear power plants under construction or in operation. It was addressed not only the new designs of nuclear power plants in the world, but also the design changes in plants that are in operation for decades. Included in this list are the Brazilian nuclear power plants, Angra-1, Angra-2, and Angra-3. This paper also reviews the current status of licensing in Brazil and Brazilian standards related to severe accidents. It also discusses the impact of severe accidents in the emergency plans of nuclear power plants. (author)

  17. Seismic detection. Part II. Nuclear events. Volume II. 1973--1974 (a bibliography with abstracts). Report for 1973--74

    International Nuclear Information System (INIS)

    Habercom, G.E. Jr.

    1976-03-01

    Methods of seismic detection of nuclear events are investigated in these Government-sponsored research reports. (This updated bibliography contains 124 abstracts, none of which are new entries to the previous edition.) For general seismic detection, see Part 1, NTIS/PS-76/0206

  18. Assessment of RELAP5/MOD2 against a main feedwater turbopump trip transient in the Vandellos II Nuclear Power Plant

    International Nuclear Information System (INIS)

    Llopis, C.; Casals, A.; Perez, J.; Mendizabal, R.

    1993-12-01

    The Consejo de Seguridad Nuclear (CSN) and the Asociacion Nuclear Vandellos (ANV) have developed a model of Vandellos II Nuclear Power Plant. The ANV collaboration consisted in the supply of design and actual data, the cooperation in the simulation of the control systems and other model components, as well as in the results analysis. The obtained model has been assessed against the following transients occurred in plant: A trip from the 100% power level (CSN); a load rejection from 100% to 50% (CSN); a load rejection from 75% to 65% (ANV); and, a feedwater turbopump trip (ANV). This copy is a report of the feedwater turbopump trip transient simulation. This transient actually occurred in the plant on June 19, 1989

  19. Automatic optimization of a nuclear reactor reload using the algorithm Ant-Q; A otimizacao automatica da recarga nuclear utilizando o algoritmo Ant-Q

    Energy Technology Data Exchange (ETDEWEB)

    Machado, Liana; Schirru, Roberto [Universidade Federal, Rio de Janeiro, RJ (Brazil). Coordenacao dos Programas de Pos-graduacao de Engenharia. Programa de Engenharia Nuclear

    2002-07-01

    The nuclear fuel reload optimization is a NP-Complete combinatorial optimization problem. For decades this problem was solved using an expert's knowledge. From the eighties, however there have been efforts to automatic fuel reload and the more recent ones show the Genetic Algorithm's (GA) efficiency on this problem. Following this trend, our aim is to optimization nuclear fuel reload using Ant-Q, artificial theory based algorithms. Ant-Q's results on the Traveling salesman Problem, which is conceptuality similar to fuel reload, are better than GA's. Ant-Q was tested in real application on the cycle 7 reload of Angra I. Comparing Ant-Q result with the GA's, it can be verified that, even without a local heuristics, the former algorithm, as it superiority comparing the GA in Angra I show. Is a valid technique to solve the nuclear fuel reload problem. (author)

  20. The phosphatidylserine receptor from Hydra is a nuclear protein with potential Fe(II dependent oxygenase activity

    Directory of Open Access Journals (Sweden)

    Stiening Beate

    2004-06-01

    Full Text Available Abstract Background Apoptotic cell death plays an essential part in embryogenesis, development and maintenance of tissue homeostasis in metazoan animals. The culmination of apoptosis in vivo is the phagocytosis of cellular corpses. One morphological characteristic of cells undergoing apoptosis is loss of plasma membrane phospholipid asymmetry and exposure of phosphatidylserine on the outer leaflet. Surface exposure of phosphatidylserine is recognised by a specific receptor (phosphatidylserine receptor, PSR and is required for phagocytosis of apoptotic cells by macrophages and fibroblasts. Results We have cloned the PSR receptor from Hydra in order to investigate its function in this early metazoan. Bioinformatic analysis of the Hydra PSR protein structure revealed the presence of three nuclear localisation signals, an AT-hook like DNA binding motif and a putative 2-oxoglutarate (2OG-and Fe(II-dependent oxygenase activity. All of these features are conserved from human PSR to Hydra PSR. Expression of GFP tagged Hydra PSR in hydra cells revealed clear nuclear localisation. Deletion of one of the three NLS sequences strongly diminished nuclear localisation of the protein. Membrane localisation was never detected. Conclusions Our results suggest that Hydra PSR is a nuclear 2-oxoglutarate (2OG-and Fe(II-dependent oxygenase. This is in contrast with the proposed function of Hydra PSR as a cell surface receptor involved in the recognition of apoptotic cells displaying phosphatidylserine on their surface. The conservation of the protein from Hydra to human infers that our results also apply to PSR from higher animals.

  1. Comparison between Ag (I and Ni (II Removal from Synthetic Nuclear Power Plant Coolant Water by Iron Oxide Nanoparticles

    Directory of Open Access Journals (Sweden)

    Mohammad Hossein Salmani

    2013-07-01

    Full Text Available The impact of effective parameters such as iron oxide nanoparticles dosage, contact time and solution pH was optimized for removal of Ag(I and Ni(II in the nuclear cooling system and the best conditions were compared. Nearly complete removal (97% of Ni(II and Ag(I were obtained at adsorbent dosage of 40 and 20 g/L, respectively. Experiments showed that 4 hours was a good choice as optimum contact time for two ions removal. The effective parameter was pH, so that maximum removal efficiency was obtained for Ag(I in acidic pH=3 and for Ni(II in basic pH=10. It seems that removal of Ag(I was controlled by adsorption-reduction mechanism, but Ni(II could place only adsorption. Langmuir and Freundlich model was more suitable for nickel and silver removal by this adsorbent, respectively. Ag(I and Ni(II removal efficiency trend by this adsorbent is similar at periods but different in the concentrations, pHs and equilibrium model. The obtained results were very promising, as both Ag(I and Ni(II were effectively removed from synthetic wastewater and there was a possibility to remove Ag(I very fast. Hence, the idea of using nanoparticles for application of metal ions removal from wastewaters seems to be very efficient and quite promising.

  2. Safety Evaluation Report related to the final design approval of the GESSAR II BWR/6 nuclear island design (Docket No. 50-447). Supplement No. 4

    International Nuclear Information System (INIS)

    1985-07-01

    Supplement 4 to the Safety Evaluation Report (SER) for the application filed by General Electric Company for the final design approval for the GE BWR/6 nuclear island design (GESSAR II) has been prepared by the Office of Nuclear Reactor Regulation of the Nuclear Regulatory Commission. This report supplements the GESSAR II SER (NUREG-0979) issued in April 1983 summarizing the results of the staff's safety review of the GESSAR II BWR/6 nuclear island design; Supplement 1, issued in July 1983; Supplement 2, issued in November 1984; and Supplement 3, issued in January 1985. Subject to favorable resolution of the items discussed in this supplement, the staff concludes that the GESSAR II design satisfactorily addresses the severe-accident concerns described in the Commission's Policy Statement on Severe Reactor Accidents Regarding Future Designs and Existing Plants

  3. 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

    International Nuclear Information System (INIS)

    2000-01-01

    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

  4. CINCH-II project. Next step in the coordination of education in nuclear- and radiochemistry in Europe

    International Nuclear Information System (INIS)

    John, Jan; Cuba, Vaclav; Nemec, Mojmir

    2013-01-01

    Any of the potential options for the nuclear power – both the renaissance, if any, or the phase out – will require significant numbers of the respective specialists, amongst others the nuclear and/or radiochemists. In parallel, a significant demand exists for these specialists in non-energy fields, such as environmental protection, radiopharmacy, nuclear medicine, biology, authorities, etc. Since the numbers of staff in teaching and the number of univerzities with facilities licensed for the work with open sources of ionizing radiation has decreased on or sometimes even below the critical level, coordination and collaboration are required to maintain the necessary teaching and training capabilities. The CINCH-II project, aiming at the Coordination of education and training In Nuclear CHemistry in Europe, will be a direct continuation of the CINCH-I project which, among others, identified the EuroMaster in Nuclear Chemistry quality label recognized and guaranteed by the European Chemistry Thematic Network Association as an optimum common mutual recognition system in the field of education in Nuclear Chemistry in Europe, surveyed the status of Nuclear Chemistry in industry / the needs of the end-users, developed an efficient system of education/training compact modular courses, or developed and tested two electronic tools as a basis of a future efficient distance learning system. In the first part of this paper, the achievements of the CINCH-I project will be described. This description will cover both the status review and the development activities of this Collaboration. In the status review field, the results of a detailed survey of the universities and curricula in nuclear- and radiochemistry in Europe and Russia will be presented. Another survey mapped the nuclear- and radiochemistry in industry – specifically the training and education needs of the end users. In the development activities field, the main achievements of the CINCH-project will be presented

  5. Rare earth elements in Angra dos Reis and Lewis Cliff 86010, two meteorites with similar but distinct magma evolutions

    Science.gov (United States)

    Crozaz, Ghislaine; Mckay, Gordon

    1990-01-01

    Data are presented on ion microprobe measurements of REE and selected trace element abundances in individual grains of merrillite, fassaite, olivine, kirschsteinite, and plagioclase of Lewis Cliff 86010 (LEW 86010) meteorite and in merrillite and fassaite grains of Angra dos Reis (ADOR). Results show a close relationship between the two meteorites and support a magmatic origin for LEW 86010. However, the measurements indicate that, despite numerous common characteristics, the two meteorites must have been produced in separate magmatic events involving similar but distinct processes and parent melts.

  6. Wind directing correlation and vertical temperature gradient correlation with the wind direction amplitud variation at Angra dos Reis site

    International Nuclear Information System (INIS)

    Nicolli, D.

    1982-08-01

    Two studies are presented: an analysis of air flow characteristics at the Itaorna site, in Angra dos Reis by correlation of wind directions measured simultaneosly on four meteorological masts, and a tentative correlation of vertical temperature gradient with the wind fluctuation standard deviation. It's concluded that the wind directions change vertical and horizontally and the wind direction fluctuation amplitude holds no correlation with the vertical temperature gradient, and therefore it should not be used as an alternative for determination of stability categories. (Author) [pt

  7. Studies on the radioactive contamination due to nuclear detonations II. Preliminary findings on the radioactive fallout due to nuclear detonations

    International Nuclear Information System (INIS)

    Nishiwaki, Yasushi

    1961-01-01

    Since we have detected a considerable amount of artificial radioactivity in the rain in spring 1954, it has become one of the most important items, from the health physics point of view, to continue measurements of radioactivity in the rain and in the atmosphere. To watch out the radioactive contamination of our environment due to repeated nuclear weapons testings in other countries was also considered to be important from the nuclear engineering point of view, in the sense that the permissible allowances of the radioactivity for the peaceful uses of atomic energy might be lowered if the degree of radioactive contamination due to nuclear testings should continue to increase gradually and indefinitely. If the permissible level were lowered, the cost for radiation protection may be expected to increase at the peaceful uses of atomic energy and should the radioactive contamination increase seriously in the future, it was anticipated that we may have to face a very difficult situation in designing the atomic energy facilities for peaceful purposes in our country. From these points of views, we have been continuing measurements of the radioactivity in the rain in Osaka, Japan since the spring of 1954. Some of the preliminary findings are introduced in this paper

  8. DNA damage response (DDR) induced by topoisomerase II poisons requires nuclear function of the small GTPase Rac.

    Science.gov (United States)

    Wartlick, Friedrich; Bopp, Anita; Henninger, Christian; Fritz, Gerhard

    2013-12-01

    Here, we investigated the influence of Rac family small GTPases on mechanisms of the DNA damage response (DDR) stimulated by topoisomerase II poisons. To this end, we examined the influence of the Rac-specific small molecule inhibitor EHT1864 on Ser139 phosphorylation of histone H2AX, a widely used marker of the DDR triggered by DNA double-strand breaks. EHT1864 attenuated the doxorubicin-stimulated DDR in a subset of cell lines tested, including HepG2 hepatoma cells. EHT1864 reduced the level of DNA strand breaks and increased viability following treatment of HepG2 cells with topo II poisons. Protection by EHT1864 was observed in both p53 wildtype (HepG2) and p53 deficient (Hep3B) human hepatoma cells and, furthermore, remained unaffected upon pharmacological inhibition of p53 in HepG2. Apparently, the impact of Rac on the DDR is independent of p53. Protection from doxorubicin-induced DNA damage by EHT1864 comprises both S and G2 phase cells. The inhibitory effect of EHT1864 on doxorubicin-stimulated DDR was mimicked by pharmacological inhibition of various protein kinases, including JNK, ERK, PI3K, PAK and CK1. EHT1864 and protein kinase inhibitors also attenuated the formation of the topo II-DNA cleavable complex. Moreover, EHT1864 mitigated the constitutive phosphorylation of topoisomerase IIα at positions S1106, S1213 and S1247. Doxorubicin transport, nuclear import/export of topoisomerase II and Hsp90-related mechanisms are likely not of relevance for doxorubicin-stimulated DDR impaired by EHT1864. We suggest that multiple kinase-dependent but p53- and heat shock protein-independent Rac-regulated nuclear mechanisms are required for activation of the DDR following treatment with topo II poisons. © 2013.

  9. Rubisco in marine symbiotic dinoflagellates: form II enzymes in eukaryotic oxygenic phototrophs encoded by a nuclear multigene family.

    Science.gov (United States)

    Rowan, R; Whitney, S M; Fowler, A; Yellowlees, D

    1996-03-01

    Genes encoding ribulose-1,5-bisphosphate carboxylase/oxygenase (Rubisco) were cloned from dinoflagellate symbionts (Symbiodinium spp) of the giant clam Tridacna gigas and characterized. Strikingly, Symbiodinium Rubisco is completely different from other eukaryotic (form I) Rubiscos: it is a form II enzyme that is approximately 65% identical to Rubisco from Rhodospirillum rubrum (Rubisco forms I and II are approximately 25 to 30% identical); it is nuclear encoded by a multigene family; and the predominantly expressed Rubisco is encoded as a precursor polyprotein. One clone appears to contain a predominantly expressed Rubisco locus (rbcA), as determined by RNA gel blot analysis of Symbiodinium RNA and sequencing of purified Rubisco protein. Another contains an enigmatic locus (rbcG) that exhibits an unprecedented pattern of amino acid replacement but does not appear to be a pseudogene. The expression of rbcG has not been analyzed; it was detected only in the minor of two taxa of Symbiodinium that occur together in T. gigas. This study confirms and describes a previously unrecognized branch of Rubisco's evolution: a eukaryotic form II enzyme that participates in oxygenic photosynthesis and is encoded by a diverse, nuclear multigene family.

  10. Nuclear dawn F. E. Simon and the race for atomic weapons in World War II

    CERN Document Server

    McRae, Kenneth D

    2014-01-01

    This book provides a rounded biography of Franz (later Sir Francis) Simon, his early life in Germany, his move to Oxford in 1933, and his experimental contributions to low temperature physics approximating absolute zero. After 1939 he switched his research to nuclear physics, and is credited with solving the problem of uranium isotope separation by gaseous diffusion for the British nuclear programme Tube Alloys. The volume is distinctive for its inclusion of source materials not available to previous researchers, such as Simon's diary and his correspondence with his wife, and for a fresh, well-informed insider voice on the five-power nuclear rivalry of the war years. The work also draws on a relatively mature nuclear literature to attempt a comparison and evaluation of the five nuclear rivals in wider political and military context, and to identify the factors, or groups of factors, that can explain the results.

  11. ANGRA-1 neutron kinetics model at BOL using WIMSD-5B and PARCS V2.7 codes

    Energy Technology Data Exchange (ETDEWEB)

    Hamers, Adolfo R.; Reis, Patricia A.L.; Rodrigues, Thiago D.A.; Pereira, Claubia; Costa, Antonella L., E-mail: adolforomerohamers@hotmail.com, E-mail: patricialire@yahoo.com.br, E-mail: claubia@nuclear.ufmg.br, E-mail: antonella@nuclear.ufmg.br [Universidade Federal de Minas Gerais (UFMG), Belo Horizonte (Brazil). Departamento de Engenheria Nuclear; Miro, R.; Verdu, G., E-mail: rmiro@iqn.upv.es, E-mail: gverdu@iqn.upv.es [Universitat Politecnica de Valencia (Spain)

    2015-07-01

    A steady-state neutron kinetics model of the Angra-1 NPP at BOL (Beginning Of Life) has been developed with the PARCS V2.7 neutron diffusion code. The information of the burnable poison rods, fuel enrichments and control rod banks distributions within the core have been taken from the Angra-1 FSAR (Final Safety Analysis Report) and implemented in the model. The macroscopic cross sections for the fast and thermal neutron groups have been calculated with the WIMSD-5B lattice cell code. The cross sections were obtained for the rodded and unrodded cases for each composition in the core. In order to establish the initial steady-state, an eigenvalue was made with the PARCS V2.7 code for three steady-state scenario cases reported at the FSAR; a K{sub eff} of 1.0733 was obtained for the unrodded case, K{sub eff} of 1.0718 for a 24% of bank D inserted case and K{sub eff} of 0.8512 for the full rodded case. The normalized core power density distributions were obtained and compared with the corresponding FSAR case. (author)

  12. ANGRA-1 neutron kinetics model at BOL using WIMSD-5B and PARCS V2.7 codes

    International Nuclear Information System (INIS)

    Hamers, Adolfo R.; Reis, Patricia A.L.; Rodrigues, Thiago D.A.; Pereira, Claubia; Costa, Antonella L.

    2015-01-01

    A steady-state neutron kinetics model of the Angra-1 NPP at BOL (Beginning Of Life) has been developed with the PARCS V2.7 neutron diffusion code. The information of the burnable poison rods, fuel enrichments and control rod banks distributions within the core have been taken from the Angra-1 FSAR (Final Safety Analysis Report) and implemented in the model. The macroscopic cross sections for the fast and thermal neutron groups have been calculated with the WIMSD-5B lattice cell code. The cross sections were obtained for the rodded and unrodded cases for each composition in the core. In order to establish the initial steady-state, an eigenvalue was made with the PARCS V2.7 code for three steady-state scenario cases reported at the FSAR; a K eff of 1.0733 was obtained for the unrodded case, K eff of 1.0718 for a 24% of bank D inserted case and K eff of 0.8512 for the full rodded case. The normalized core power density distributions were obtained and compared with the corresponding FSAR case. (author)

  13. Review of first line supervisory positions in nuclear power plants - Phase II

    International Nuclear Information System (INIS)

    Mackenzie, C.W.; Huntley, M.

    1995-10-01

    This report provides an overview of first line supervisory activities at Ontario Hydro nuclear generating stations (Pickering 'A' and Bruce 'B') and the Point Lepreau nuclear generating station in New Brunswick. Activity profiles describing the range of first line supervisory roles and responsibilities for nuclear operators have been developed from survey data and flowcharting methods. These activity profiles have then been compared with formal job responsibilities as identified in job descriptions, supervisory training provided and assessment criteria used to evaluate supervisors. Finally, this report relates the findings of supervisory practices in the group under study with the findings in the current literature relating to supervisory functioning. (author). 32 tabs., 2 figs

  14. High-Speed Neutron and Gamma Flux Sensor for Monitoring Surface Nuclear Reactors, Phase II

    Data.gov (United States)

    National Aeronautics and Space Administration — NASA needs compact nuclear reactors to power future bases on the moon and/or Mars. These reactors require robust automatic control systems using low mass, rapid...

  15. Hydrogen Wave Heater for Nuclear Thermal Propulsion Component Testing, Phase II

    Data.gov (United States)

    National Aeronautics and Space Administration — NASA has identified Nuclear Thermal Propulsion (NTP) as an approach that can provide the fastest trip times to Mars and as the preferred concept for human space...

  16. The nuclear engineering programmes at the Royal Military College of Canada. Part II

    Energy Technology Data Exchange (ETDEWEB)

    Bonin, H.W. [Royal Military College of Canada, Dept. of Chemistry and Chemical Engineering, Kingston, Ontario (Canada)

    2002-08-01

    The coverage of the activities within the nuclear science and engineering programmes at RMC reveals the dynamism of the College which is still growing at a fast rate. Being the only completely bilingual university in Canada and a true national institution gathering students and staff from all parts of the country. RMC continues in its mission to support the Canadian Forces, the Department of National Defence, the people of Canada and Canadian Industry that includes the nuclear sector. It is in this spirit that the staff has been actively involved with organizations such as the Canadian Nuclear Society and the Canadian Nuclear Association, having hosted four of the Student conferences and three major topical conferences of the CNS.

  17. The nuclear engineering programmes at the Royal Military College of Canada. Part II

    International Nuclear Information System (INIS)

    Bonin, H.W.

    2002-01-01

    The coverage of the activities within the nuclear science and engineering programmes at RMC reveals the dynamism of the College which is still growing at a fast rate. Being the only completely bilingual university in Canada and a true national institution gathering students and staff from all parts of the country. RMC continues in its mission to support the Canadian Forces, the Department of National Defence, the people of Canada and Canadian Industry that includes the nuclear sector. It is in this spirit that the staff has been actively involved with organizations such as the Canadian Nuclear Society and the Canadian Nuclear Association, having hosted four of the Student conferences and three major topical conferences of the CNS

  18. Cofilin Regulates Nuclear Architecture through a Myosin-II Dependent Mechanotransduction Module

    OpenAIRE

    Wiggan, O?Neil; Schroder, Bryce; Krapf, Diego; Bamburg, James R.; DeLuca, Jennifer G.

    2017-01-01

    Structural features of the nucleus including shape, size and deformability impact its function affecting normal cellular processes such as cell differentiation and pathological conditions such as tumor cell migration. Despite the fact that abnormal nuclear morphology has long been a defining characteristic for diseases such as cancer relatively little is known about the mechanisms that control normal nuclear architecture. Mounting evidence suggests close coupling between F-actin cytoskeletal ...

  19. Proceeding of the National Seminar on Research and Management of Nuclear Equipment: Book II

    International Nuclear Information System (INIS)

    Tjipto Sujitno; Syarip; Agus Taftazani; Elisabeth Supriyatni; Prayitno; MV Purwani; Budi Setiawan; Prajitno; Rany Saptaaji; Bambang Siswanto; Eko Priyono; Jumari

    2013-09-01

    The scientific meeting and presentation on accelerator technology and its applications was held by PTAPB BATAN on 11 September 2013. This meeting aims to promote the technology and its applications to accelerator scientists, academics, researchers and technology users as well as accelerator-based accelerator research that have been conducted by researchers in and outside BATAN. This proceeding contains 49 papers about , chemistry, physics, accelerator, nuclear instrument and nuclear reactor, etc. (PPIKSN)

  20. Nuclear Thermal Rocket Element Environmental Simulator (NTREES) Phase II Upgrade Activities

    Science.gov (United States)

    Emrich, William J.; Moran, Robert P.; Pearson, J. Bose

    2013-01-01

    To support the on-going nuclear thermal propulsion effort, a state-of-the-art non nuclear experimental test setup has been constructed to evaluate the performance characteristics of candidate fuel element materials and geometries in representative environments. The facility to perform this testing is referred to as the Nuclear Thermal Rocket Element Environment Simulator (NTREES). This device can simulate the environmental conditions (minus the radiation) to which nuclear rocket fuel components will be subjected during reactor operation. Test articles mounted in the simulator are inductively heated in such a manner so as to accurately reproduce the temperatures and heat fluxes which would normally occur as a result of nuclear fission and would be exposed to flowing hydrogen. Initial testing of a somewhat prototypical fuel element has been successfully performed in NTREES and the facility has now been shutdown to allow for an extensive reconfiguration of the facility which will result in a significant upgrade in its capabilities. Keywords: Nuclear Thermal Propulsion, Simulator

  1. A role for nuclear translocation of tripeptidyl-peptidase II in reactive oxygen species-dependent DNA damage responses

    International Nuclear Information System (INIS)

    Preta, Giulio; Klark, Rainier de; Glas, Rickard

    2009-01-01

    Responses to DNA damage are influenced by cellular metabolism through the continuous production of reactive oxygen species (ROS), of which most are by-products of mitochondrial respiration. ROS have a strong influence on signaling pathways during responses to DNA damage, by relatively unclear mechanisms. Previous reports have shown conflicting data on a possible role for tripeptidyl-peptidase II (TPPII), a large cytosolic peptidase, within the DNA damage response. Here we show that TPPII translocated into the nucleus in a p160-ROCK-dependent fashion in response to γ-irradiation, and that nuclear expression of TPPII was present in most γ-irradiated transformed cell lines. We used a panel of nine cell lines of diverse tissue origin, including four lymphoma cell lines (T, B and Hodgkins lymphoma), a melanoma, a sarcoma, a colon and two breast carcinomas, where seven out of nine cell lines showed nuclear TPPII expression after γ-irradiation. Further, this required cellular production of ROS; treatment with either N-acetyl-Cysteine (anti-oxidant) or Rotenone (inhibitor of mitochondrial respiration) inhibited nuclear accumulation of TPPII. The local density of cells was important for nuclear accumulation of TPPII at early time-points following γ-irradiation (at 1-4 h), indicating a bystander effect. Further, we showed that the peptide-based inhibitor Z-Gly-Leu-Ala-OH, but not its analogue Z-Gly-(D)-Leu-Ala-OH, excluded TPPII from the nucleus. This correlated with reduced nuclear expression of p53 as well as caspase-3 and -9 activation in γ-irradiated lymphoma cells. Our data suggest a role for TPPII in ROS-dependent DNA damage responses, through alteration of its localization from the cytosol into the nucleus.

  2. A role for nuclear translocation of tripeptidyl-peptidase II in reactive oxygen species-dependent DNA damage responses

    Energy Technology Data Exchange (ETDEWEB)

    Preta, Giulio; Klark, Rainier de [Center for Molecular Medicine (CMM), Department of Medicine, Karolinska Institutet, Karolinska University Hospital, 171 76 Stockholm (Sweden); Glas, Rickard, E-mail: rickard.glas@ki.se [Center for Molecular Medicine (CMM), Department of Medicine, Karolinska Institutet, Karolinska University Hospital, 171 76 Stockholm (Sweden)

    2009-11-27

    Responses to DNA damage are influenced by cellular metabolism through the continuous production of reactive oxygen species (ROS), of which most are by-products of mitochondrial respiration. ROS have a strong influence on signaling pathways during responses to DNA damage, by relatively unclear mechanisms. Previous reports have shown conflicting data on a possible role for tripeptidyl-peptidase II (TPPII), a large cytosolic peptidase, within the DNA damage response. Here we show that TPPII translocated into the nucleus in a p160-ROCK-dependent fashion in response to {gamma}-irradiation, and that nuclear expression of TPPII was present in most {gamma}-irradiated transformed cell lines. We used a panel of nine cell lines of diverse tissue origin, including four lymphoma cell lines (T, B and Hodgkins lymphoma), a melanoma, a sarcoma, a colon and two breast carcinomas, where seven out of nine cell lines showed nuclear TPPII expression after {gamma}-irradiation. Further, this required cellular production of ROS; treatment with either N-acetyl-Cysteine (anti-oxidant) or Rotenone (inhibitor of mitochondrial respiration) inhibited nuclear accumulation of TPPII. The local density of cells was important for nuclear accumulation of TPPII at early time-points following {gamma}-irradiation (at 1-4 h), indicating a bystander effect. Further, we showed that the peptide-based inhibitor Z-Gly-Leu-Ala-OH, but not its analogue Z-Gly-(D)-Leu-Ala-OH, excluded TPPII from the nucleus. This correlated with reduced nuclear expression of p53 as well as caspase-3 and -9 activation in {gamma}-irradiated lymphoma cells. Our data suggest a role for TPPII in ROS-dependent DNA damage responses, through alteration of its localization from the cytosol into the nucleus.

  3. Study on the utilization of the cognitive architecture EPIC to the task analysis of a nuclear power plant operator

    International Nuclear Information System (INIS)

    Soares, Herculano Vieira

    2003-02-01

    This work presents a study of the use of the integrative cognitive architecture EPIC - Executive-Process - Interactive-Control, designed to evaluate the performance of a person performing tasks in parallel in a man-machine interface, as a methodology for Cognitive Task Analysis of a nuclear power plant operator. A comparison of the results obtained by the simulation by EPIC and the results obtained by application of the MHP model to the tasks performed by a shift operator during the execution of the procedure PO-E-3 - Steam Generator Tube Rupture of Angra 1 Nuclear Power Plant is done. To subsidize that comparison, an experiment was performed at the Angra 2 Nuclear Power Plant Full Scope Simulator in which three operator tasks were executed, its completion time measured and compared with the results of MHP and EPIC modeling. (author)

  4. Pile foundation of nuclear power plant structures

    International Nuclear Information System (INIS)

    Jurkiewicz, W.J.; Thomaz, E.; Rideg, P.; Girao, M.

    1978-01-01

    The subject of pile foundation used for nuclear power plant structures, considering the experience gained by the designers of the Angra Nuclear Power Plant, Units 2 and 3 in Brazil is dealt with. The general concept of the pile foundations, including types and execution of the piles, is described briefly. Then the two basic models, i.e. the static model and the dynamic one, used in the design are shown, and the pertinent design assumptions as related to the Angra project are mentioned. The criteria which established the loading capacity of the piles are discussed and the geological conditions of the Angra site are also explained briefly, justifying the reasons why pile foundations are necessary in this project. After that, the design procedures and particularly the tools - i.e. the computer programs - are described. It is noted that the relatively simple but always time consuming job of loading determination calculations can be computerized too, as it was done on this project through the computer program SEASA. The interesting aspects of soil/structure interaction, applicable to static models, are covered in detail, showing the theoretical base wich was used in the program PILMAT. Then the advantage resulting from computerizing of the job of pile reinforcement design are mentioned, describing briefly the jobs done by the two special programs PILDES and PILTAB. The point is stressed that the effort computerizing the structural design of this project was not so much due to the required accuracy of the calculations, but mainly due to the need to save on the design time, as to allow to perform the design task within the relatively tight time schedule. A conclusion can be drawn that design of pile foundations for nuclear power plant structures is a more complex task than the design of bearing type of foundation for the same structures, but that the task can be always made easier when the design process can be computerized. (Author)

  5. GTP-dependent binding and nuclear transport of RNA polymerase II by Npa3 protein

    DEFF Research Database (Denmark)

    Staresincic, Lidija; Walker, Jane; Dirac-Svejstrup, A Barbara

    2011-01-01

    transport of RNAPII. Surprisingly, we were unable to detect interactions between Npa3 and proteins in the classical importin a/ß pathway for nuclear import. Interestingly, Npa3-RNAPII binding is significantly increased by the addition of GTP or its slowly hydrolyzable analogue guanosine 5'-3-O......-(thio)triphosphate (GTP¿S). Moreover, the Npa3 mutant that binds GTP, but cannot hydrolyze it, binds RNAPII even in the absence of added GTP, whereas the mutant that cannot bind GTP is unable to bind the polymerase. Together, our data suggest that Npa3 defines an unconventional pathway for nuclear import of RNAPII, which...

  6. Work Analysis of the nuclear power plant control room operators (II): The classes of situation

    International Nuclear Information System (INIS)

    Alengry, P.

    1989-03-01

    This report presents a work analysis of nuclear power plant control room operators focused on the classes of situation they can meet during their job. Each class of situation is first described in terms of the process variables states. We then describe the goals of the operators and the variables they process in each class of situation. We report some of the most representative difficulties encountered by the operators in each class of situation. Finally, we conclude on different topics: the nature of the mental representations, the temporal dimension, the monitoring activity, and the role of the context in the work of controlling a nuclear power plant [fr

  7. Nuclear data for reactors. Proceedings of the second international conference. Vol. II

    International Nuclear Information System (INIS)

    1970-01-01

    The Second International Conference on Nuclear Data for Reactors, held in Helsinki at the invitation of the Finnish Government, was convened by the International Atomic Energy Agency from 15 to 19 June 1970. The Conference, held as a result of recommendations made by the International Nuclear Data Committee, was attended by 163 participants from 28 countries and four international organizations, and 21 invited and 98 contributed papers were presented. This Conference was the second held by the IAEA on Nuclear Data for Reactors. Almost four years have elapsed since the first was held in Paris in 1966. During these years gratifying progress has been made by reactor, nuclear and evaluation physicists, whose collaboration has been greatly enhanced. As a result, many laboratories have concentrated their efforts on items of particular importance for reactor research and development, and many measurements are now available. The main purpose of this Conference was to provide an opportunity to review results of recent basic neutron-physics investigations against a background need for basic information, especially concerning reactors. The Conference itself, together with the preparatory meetings of IAEA experts in Studsvik on the status of α( 239 Pu) and the ν-bar-values for fissionable nuclei, showed an emphasis on the nuclear data aspects most important for nuclear technology. Most contributors dealt with the measurement and analysis of neutron cross-sections. This extensive new cross-section information can be attributed to several factors, the most important being the development and systematic exploitation of high-intensity neutron sources, such as modern linear accelerators, modern cyclotrons and underground nuclear explosions, improvements in instrumentation and in sample preparation techniques, and other technical improvements. Compared with the first IAEA Conference on Nuclear Data for Reactors this one has many more contributions on neutron data evaluation. Many

  8. Nuclear abnormalities in buccal mucosa cells of patients with type I and II diabetes treated with folic acid.

    Science.gov (United States)

    Gómez-Meda, B C; Zamora-Perez, A L; Muñoz-Magallanes, T; Sánchez-Parada, M G; García Bañuelos, J J; Guerrero-Velázquez, C; Sánchez-Orozco, L V; Vera-Cruz, J M; Armendáriz-Borunda, J; Zúñiga-González, G M

    2016-02-01

    Diabetes mellitus (DM) is characterized by high blood glucose. Excessive production of free radicals may cause oxidative damage to DNA and other molecules, leading to complications of the disease. It may be possible to delay or reduce such damage by administration of antioxidants such as folic acid (FA). The objective of this study was to determine the effect of FA on nuclear abnormalities (NAs) in the oral mucosa of patients with DM. NAs (micronucleated cells, binucleated cells, pyknotic nuclei, karyorrhexis, karyolysis, abnormally condensed chromatin, and nuclear buds) were analyzed in 2000 cells from 45 healthy individuals (control group) and 55 patients with controlled or uncontrolled type I or II DM; 35 patients in the latter group were treated with FA. Samples were taken from the FA group before and after treatment. An increased rate of NAs was found in patients with DM in comparison with that of the control group (Pabnormally condensed chromatin, karyolysis, and nuclear buds produced by FA supplementation in DM patients (P<0.02) are consistent with the idea that free radicals are responsible for the increased frequency of NAs in DM patients. Copyright © 2015 Elsevier B.V. All rights reserved.

  9. Nuclear Analysis and Technology Assessment of Radar Concepts. Volume II. Radiation Vulnerability Assessment of Radar Components.

    Science.gov (United States)

    1981-05-20

    on Nuclear Science, Vol. NS-21, No. 6, (Cece"ber, 1974). 140.) "Development of a Hard Microcontroller" P.R. Measel , L.L. Sivo, ’W.E. Quilitz, and...Myers; Electronics, March 16, 1978. 147.) "Radiation Response of Several Memory Device Types" P.R. Measel , R.B. Gregor, and K.L. Wahlin; IEEE

  10. Long-term consequences of and prospects for recovery from nuclear war: Two views. View II

    International Nuclear Information System (INIS)

    Anspaugh, L.R.

    1986-01-01

    The author comments on the information presented in this volume and speculates on the long-term consequences of nuclear war and the prospects for recovery. In order to do that, it might be useful to define long term. To him this means time frames of years to perhaps even hundreds of years in terms of the ultimate response and recovery of large-scale ecosystems. Such long time frames may seem excessive, but if some of the speculated efforts of nuclear war are actually realized, it may indeed take centuries before native ecosystems restabilize. Also, when referring to long-term effects of the magnitude required to have a major impact on entire ecosystems, it is clear that the driving force would not be the direct effects of nuclear war. Of potentially greater significance would be the secondary effects mediated by the intermediate-term impacts on global climate. Specifically, he refers to the speculative impacts of major decreases in the heat and light fluxes reaching the Earth's surface. Such changes are commonly referred to as ''nuclear winter.''

  11. Final environmental statement. Final addendum to Part II: Manufacture of floating nuclear power plants by Offshore Power Systems. DOCKET-STN--50-437

    International Nuclear Information System (INIS)

    1978-06-01

    This Addendum to Part II of the Final Environmental Statement related to manufacture of floating nuclear power plants by Offshore Power Systems (OPS), NUREG-0056, issued September 1976, was prepared by the U.S. Nuclear Regulatory Commission (NRC), Office of Nuclear Reactor Regulation. The staff's basic evaluation is presented in NUREG-0056. The current Addendum provides further consideration of a number of topics discussed in NUREG-0056, particularly additional consideration of shore zone siting at estuarine and ocean regions. This Summary and Conclusions recapitulates and is cumulative for Part II of the FES and the current Addendum. Augmentations to the Summary and Conclusions presented in Part II of the FES and arising from the evaluations contained in this Addendum are italicized

  12. Tripeptidyl Peptidase II Mediates Levels of Nuclear Phosphorylated ERK1 and ERK2

    NARCIS (Netherlands)

    Wiemhoefer, Anne; Stargardt, Anita; van der Linden, Wouter A; Renner, Maria C; van Kesteren, Ronald E; Stap, Jan; Raspe, Marcel A; Tomkinson, Birgitta; Kessels, Helmut W; Ovaa, Huib; Overkleeft, Herman S; Florea, Bogdan; Reits, Eric A

    Tripeptidyl peptidase II (TPP2) is a serine peptidase involved in various biological processes, including antigen processing, cell growth, DNA repair, and neuropeptide mediated signaling. The underlying mechanisms of how a peptidase can influence this multitude of processes still remain unknown. We

  13. Tripeptidyl Peptidase II Mediates Levels of Nuclear Phosphorylated ERK1 and ERK2

    NARCIS (Netherlands)

    Wiemhoefer, Anne; Stargardt, Anita; van der Linden, Wouter A.; Renner, Maria C.; van Kesteren, Ronald E.; Stap, Jan; Raspe, Marcel A.; Tomkinson, Birgitta; Kessels, Helmut W.; Ovaa, Huib; Overkleeft, Herman S.; Florea, Bogdan; Reits, Eric A.

    2015-01-01

    Tripeptidyl peptidase II (TPP2) is a serine peptidase involved in various biological processes, including antigen processing, cell growth, DNA repair, and neuropeptide mediated signaling. The underlying mechanisms of how a peptidase can influence this multitude of processes still remain unknown. We

  14. Vulnerability Assessment of the nuclear power plant Vandellos II before a tornado

    International Nuclear Information System (INIS)

    Fernandez, A.; Encabo, J.; Vaz-Romero, A.; Moran, M. A.; Roch, M.; Nicolas, P.; Barrera, N.

    2010-01-01

    The purpose of this work was the study of vulnerability to tornado event Vandellos II NPP. To do this, we have evaluated all structures (buildings), security systems and components to the installation of wind stresses, depression and impact of projectiles, generated by a tornado on the site.

  15. Analytical mass formula and nuclear surface properties in the ETF approximation. Part II: asymmetric nuclei

    Science.gov (United States)

    Aymard, François; Gulminelli, Francesca; Margueron, Jérôme

    2016-08-01

    We have recently addressed the problem of the determination of the nuclear surface energy for symmetric nuclei in the framework of the extended Thomas-Fermi (ETF) approximation using Skyrme functionals. We presently extend this formalism to the case of asymmetric nuclei and the question of the surface symmetry energy. We propose an approximate expression for the diffuseness and the surface energy. These quantities are analytically related to the parameters of the energy functional. In particular, the influence of the different equation of state parameters can be explicitly quantified. Detailed analyses of the different energy components (local/non-local, isoscalar/isovector, surface/curvature and higher order) are also performed. Our analytical solution of the ETF integral improves previous models and leads to a precision of better than 200 keV per nucleon in the determination of the nuclear binding energy for dripline nuclei.

  16. Health effects models for off-site radiological consequence analysis on nuclear reactor accidents (II)

    Energy Technology Data Exchange (ETDEWEB)

    Homma, Toshimitsu [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment; Takahashi, Tomoyuki [Kyoto Univ., Kumatori, Osaka (Japan). Research Reactor Inst; Yonehara, Hidenori [National Inst. of Radiological Sciences, Chiba (Japan)] [eds.

    2000-12-01

    This report is a revision of JAERI-M 91-005, 'Health Effects Models for Off-Site Radiological Consequence Analysis of Nuclear Reactor Accidents'. This revision provides a review of two revisions of NUREG/CR-4214 reports by the U.S. Nuclear Regulatory Commission which is the basis of the JAERI health effects models and other several recent reports that may impact the health effects models by international organizations. The major changes to the first version of the JAERI health effects models and the recommended parameters in this report are for late somatic effects. These changes reflect recent changes in cancer risk factors that have come from longer followup and revised dosimetry in major studies on the Japanese A-bomb survivors. This report also provides suggestions about future revisions of computational aspects on health effects models. (author)

  17. Health effects models for off-site radiological consequence analysis on nuclear reactor accidents (II)

    International Nuclear Information System (INIS)

    Homma, Toshimitsu

    2000-12-01

    This report is a revision of JAERI-M 91-005, 'Health Effects Models for Off-Site Radiological Consequence Analysis of Nuclear Reactor Accidents'. This revision provides a review of two revisions of NUREG/CR-4214 reports by the U.S. Nuclear Regulatory Commission which is the basis of the JAERI health effects models and other several recent reports that may impact the health effects models by international organizations. The major changes to the first version of the JAERI health effects models and the recommended parameters in this report are for late somatic effects. These changes reflect recent changes in cancer risk factors that have come from longer followup and revised dosimetry in major studies on the Japanese A-bomb survivors. This report also provides suggestions about future revisions of computational aspects on health effects models. (author)

  18. Evaluation of the setpoints of the overtemperature ΔT tripping function for Angra 1. PT.1

    International Nuclear Information System (INIS)

    1980-12-01

    This report is the first of two-part series that review the setpoints of the overtemperature ΔT tripping functions for Angra I. These results, obtained with a modidied COBRA-IIIC computer program version, are for typical subchannels in steady state situation or during short-term transients (min-hrs). In order to study the consequences of some approximations, the analysis started from model for DNBR calculation with an inadequate subchannels and equivalent rods array. For the determination of DNBR=1.30 curves a more realistic array was used. The overtemperature ΔT trip setpoints are conservatively below the DNBR=1.30 curves calculated in this part of the review. (author) [pt

  19. Applications of artificial intelligence and expert systems in ANGRA-I emergency preparedness - The Brazilian case

    International Nuclear Information System (INIS)

    Alvarenga, M.A.B.; Guimaraes, A.C.F.

    1991-01-01

    This study describes a system to follow a nuclear accident and points the areas where the presence of artificial intelligence could be necessary: diagnostics systems, emergency classification, accident management strategies and protective actions. Logical rules could be combined with deterministic equations to provide an expert system prototype to manage a nuclear emergency preparedness for nuclear reactors (fast or thermal) in the Brazilian Nuclear Energy National Commission. (CNEN). (author)

  20. Underwater Nuclear Fuel Disassembly and Rod Storage Process and Equipment Description. Volume II

    International Nuclear Information System (INIS)

    Viebrock, J.M.

    1981-09-01

    The process, equipment, and the demonstration of the Underwater Nuclear Fuel Disassembly and Rod Storage System are presented. The process was shown to be a viable means of increasing spent fuel pool storage density by taking apart fuel assemblies and storing the fuel rods in a denser fashion than in the original storage racks. The assembly's nonfuel-bearing waste is compacted and containerized. The report documents design criteria and analysis, fabrication, demonstration program results, and proposed enhancements to the system

  1. Meson dynamics and the nuclear many-body problem. II. Finite density Hartree-Fock

    International Nuclear Information System (INIS)

    Wilets, L.; Puff, R.D.; Chiang, D.; Nutt, W.T.

    1976-01-01

    The field-theoretic many-nucleon problem is formulated, and an analysis which sums all ''uncrossed meson line'' diagrams is investigated in detail. The calculation of energy per nucleon, after proper identification of infinite mass renormalization terms, exhibits effects of nuclear recoil, relativistic kinematics, and retardation. Numerical results are presented for π and ω mesons, and the nucleon interaction energies obtained are compared with the traditional static limit of infinite nucleon mass

  2. Probabilistic risk assessment on maritime spent nuclear fuel transportation (Part II: Ship collision probability)

    International Nuclear Information System (INIS)

    Christian, Robby; Kang, Hyun Gook

    2017-01-01

    This paper proposes a methodology to assess and reduce risks of maritime spent nuclear fuel transportation with a probabilistic approach. Event trees detailing the progression of collisions leading to transport casks’ damage were constructed. Parallel and crossing collision probabilities were formulated based on the Poisson distribution. Automatic Identification System (AIS) data were processed with the Hough Transform algorithm to estimate possible intersections between the shipment route and the marine traffic. Monte Carlo simulations were done to compute collision probabilities and impact energies at each intersection. Possible safety improvement measures through a proper selection of operational transport parameters were investigated. These parameters include shipment routes, ship's cruise velocity, number of transport casks carried in a shipment, the casks’ stowage configuration and loading order on board the ship. A shipment case study is presented. Waters with high collision probabilities were identified. Effective range of cruising velocity to reduce collision risks were discovered. The number of casks in a shipment and their stowage method which gave low cask damage frequencies were obtained. The proposed methodology was successful in quantifying ship collision and cask damage frequency. It was effective in assisting decision making processes to minimize risks in maritime spent nuclear fuel transportation. - Highlights: • Proposes a probabilistic framework on the safety of spent nuclear fuel transportation by sea. • Developed a marine traffic simulation model using Generalized Hough Transform (GHT) algorithm. • A transportation case study on South Korean waters is presented. • Single-vessel risk reduction method is outlined by optimizing transport parameters.

  3. Nuclear Energy Center study. Phase II. Site suitability analysis. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Fellows, W.S.; Sharp, J.M.; Benator, B.I.

    1978-06-01

    A site screening study was conducted to identify a site or sites for detailed, site-specific study as a nuclear energy center. Using technical criteria of water requirements, geotechnical constraints, and projected load center and transmission considerations as well as environmental and institutional considerations, five potential study sites in the State of South Carolina were identified, evaluated against established criteria, and ranked according to their acceptability as potential nuclear energy center study sites. Consideration of what is ''representative'' of a site as well as the ranking score was factored into site recommendations, since the site deemed easiest to license and permit may not be the most desirable site for future study of the technical and institutional feasibility and practicality of a specific site. The sites near Lake Hartwell and the Savannah River Plant (SRP) of the Department of Energy were selected as potential study sites after consideration of the above criteria. Because the Lake Hartwell site offers the opportunity to consider institutional issues which may be more representative of other possible NEC sites, it is recommended that the Lake Hartwell site be studied to establish the feasibility and practicality of the nuclear energy concept on a site-specific basis.

  4. Nuclear Energy Center study. Phase II. Site suitability analysis. Final report

    International Nuclear Information System (INIS)

    Fellows, W.S.; Sharp, J.M.; Benator, B.I.

    1978-06-01

    A site screening study was conducted to identify a site or sites for detailed, site-specific study as a nuclear energy center. Using technical criteria of water requirements, geotechnical constraints, and projected load center and transmission considerations as well as environmental and institutional considerations, five potential study sites in the State of South Carolina were identified, evaluated against established criteria, and ranked according to their acceptability as potential nuclear energy center study sites. Consideration of what is ''representative'' of a site as well as the ranking score was factored into site recommendations, since the site deemed easiest to license and permit may not be the most desirable site for future study of the technical and institutional feasibility and practicality of a specific site. The sites near Lake Hartwell and the Savannah River Plant (SRP) of the Department of Energy were selected as potential study sites after consideration of the above criteria. Because the Lake Hartwell site offers the opportunity to consider institutional issues which may be more representative of other possible NEC sites, it is recommended that the Lake Hartwell site be studied to establish the feasibility and practicality of the nuclear energy concept on a site-specific basis

  5. Visual examination program of the TRIGA Mark II reactor Vienna with the nuclear underwater telescope

    International Nuclear Information System (INIS)

    Boeck, H.; Hammer, J.; Varga, K.

    1985-12-01

    The visual inspection programm carried out during a three month shut-period at the TRIGA Mark II reactor Vienna is described. Optical inspection of all welds inside the reactor tank was carried out with an underwater telescope developed by the Central Research Institute of Physics, Budapest, Hungary. It is shown that even after 23 years of reactor operation all tank internals were found to be in good condition and minor defects can be easily repaired by remote handling tools. (Author)

  6. Relocalization of nuclear DNA helicase II during the growth period of bovine oocytes

    Czech Academy of Sciences Publication Activity Database

    Baran, V.; Kovářová, Hana; Klíma, Jiří; Hozák, Pavel; Motlík, Jan

    2006-01-01

    Roč. 125, 1-2 (2006), s. 155-164 ISSN 0948-6143 R&D Projects: GA ČR GA523/03/0857 Grant - others:Slovenská Akademie věd(SK) VEGA 2/3065/23 Institutional research plan: CEZ:AV0Z50450515; CEZ:AV0Z50390512 Keywords : DNA helicase II * fibroblasts * oocytes Subject RIV: EB - Genetics ; Molecular Biology Impact factor : 3.220, year: 2006

  7. HDACs class II-selective inhibition alters nuclear receptor-dependent differentiation.

    Science.gov (United States)

    Nebbioso, Angela; Dell'Aversana, Carmela; Bugge, Anne; Sarno, Roberta; Valente, Sergio; Rotili, Dante; Manzo, Fabio; Teti, Diana; Mandrup, Susanne; Ciana, Paolo; Maggi, Adriana; Mai, Antonello; Gronemeyer, Hinrich; Altucci, Lucia

    2010-10-01

    Epigenetic deregulation contributes to diseases including cancer, neurodegeneration, osteodystrophy, cardiovascular defects, and obesity. For this reason, several inhibitors for histone deacetylases (HDACs) are being validated as novel anti-cancer drugs in clinical studies and display important anti-proliferative activities. While most inhibitors act on both class I, II, and IV HDACs, evidence is accumulating that class I is directly involved in regulation of cell growth and death, whereas class II members regulate differentiation processes, such as muscle and neuronal differentiation. Here, we show that the novel class II-selective inhibitor MC1568 interferes with the RAR- and peroxisome proliferator-activated receptor γ (PPARγ)-mediated differentiation-inducing signaling pathways. In F9 cells, this inhibitor specifically blocks endodermal differentiation despite not affecting retinoic acid-induced maturation of promyelocytic NB4 cells. In 3T3-L1 cells, MC1568 attenuates PPARγ-induced adipogenesis, while the class I-selective MS275 blocked adipogenesis completely thus revealing a different mode of action and/or target profile of the two classes of HDACs. Using in vivo reporting PPRE-Luc mice, we find that MC1568 impairs PPARγ signaling mostly in the heart and adipose tissues. These results illustrate how HDAC functions can be dissected by selective inhibitors.

  8. Nuclear reactors and fuel cycle

    International Nuclear Information System (INIS)

    2014-01-01

    The Nuclear Fuel Center (CCN) of IPEN produces nuclear fuel for the continuous operation of the IEA-R1 research reactor of IPEN. The serial production started in 1988, when the first nuclear fuel element was delivered for IEA-R1. In 2011, CCN proudly presents the 100 th nuclear fuel element produced. Besides routine production, development of new technologies is also a permanent concern at CCN. In 2005, U 3 O 8 were replaced by U 3 Si 2 -based fuels, and the research of U Mo is currently under investigation. Additionally, the Brazilian Multipurpose Research Reactor (RMB), whose project will rely on the CCN for supplying fuel and uranium targets. Evolving from an annual production from 10 to 70 nuclear fuel elements, plus a thousand uranium targets, is a huge and challenging task. To accomplish it, a new and modern Nuclear Fuel Factory is being concluded, and it will provide not only structure for scaling up, but also a safer and greener production. The Nuclear Engineering Center has shown, along several years, expertise in the field of nuclear, energy systems and correlated areas. Due to the experience obtained during decades in research and technological development at Brazilian Nuclear Program, personnel has been trained and started to actively participate in design of the main system that will compose the Brazilian Multipurpose Reactor (RMB) which will make Brazil self-sufficient in production of radiopharmaceuticals. The institution has participated in the monitoring and technical support concerning the safety, licensing and modernization of the research reactors IPEN/MB-01 and IEA-R1. Along the last two decades, numerous specialized services of engineering for the Brazilian nuclear power plants Angra 1 and Angra 2 have been carried out. The contribution in service, research, training, and teaching in addition to the development of many related technologies applied to nuclear engineering and correlated areas enable the institution to fulfill its mission that is

  9. Nuclear Energy Center Site Survey, 1975. Part II. The U.S. electric power system and the potential role of nuclear energy centers

    International Nuclear Information System (INIS)

    1976-01-01

    Information related to Nuclear Energy Centers (NEC) in the U.S. is presented concerning the U.S. electric power system today; electricity demand history and forecasts; history and forecasts of the electric utility industry; regional notes; the status, history, and forecasts of the nuclear role; power plant siting problems and practices; nuclear facilities siting problems and practices; origin and evolution of the nuclear energy center concept; conceptualized description of nuclear energy centers; potential role of nuclear energy centers; assumptions, criteria, and bases; typical evolution of a nuclear energy center; and the nuclear fuel cycle

  10. Hydrogeological modelling of the eastern region of Areco river locally detailed on Atucha I and II nuclear power plants area

    International Nuclear Information System (INIS)

    Grattone, Natalia I.; Fuentes, Nestor O.

    2009-01-01

    Water flow behaviour of Pampeano aquifer was modeled using Visual Mod-flow software Package 2.8.1 with the assumption of a free aquifer, within the region of the Areco river and extending to the rivers of 'Canada Honda' and 'de la Cruz'. Steady state regime was simulated and grid refinement allows obtaining locally detailed calculation in the area of Atucha I and II Nuclear power plants, in order to compute unsteady situations as the consequence of water flow variations from and to the aquifer, enabling the model to study the movement of possible contaminant particles in the hydrogeologic system. In this work the effects of rivers action, the recharge conditions and the flow lines are analyzed, taking always into account the range of reliability of obtained results, considering the incidence of uncertainties introduced by data input system, the estimates and interpolation of parameters used. (author)

  11. Geological disposal of nuclear waste: II. From laboratory data to the safety analysis – Addressing societal concerns

    International Nuclear Information System (INIS)

    Grambow, Bernd; Bretesché, Sophie

    2014-01-01

    Highlights: • Models for repository safety can only partly be validated. • Long term risks need to be translated in the context of societal temporalities. • Social sciences need to be more strongly involved into safety assessment. - Abstract: After more than 30 years of international research and development, there is a broad technical consensus that geologic disposal of highly-radioactive waste will provide for the safety of humankind and the environment, now, and far into the future. Safety analyses have demonstrated that the risk, as measured by exposure to radiation, will be of little consequence. Still, there is not yet an operating geologic repository for highly-radioactive waste, and there remains substantial public concern about the long-term safety of geologic disposal. In these two linked papers, we argue for a stronger connection between the scientific data (paper I, Grambow et al., 2014) and the safety analysis, particularly in the context of societal expectations (paper II). In this paper (II), we assess the meaning of the technical results and derived models (paper I) for the determination of the long-term safety of a repository. We consider issues of model validity and their credibility in the context of a much broader historical, epistemological and societal context. Safety analysis is treated in its social and temporal dimensions. This perspective provides new insights into the societal dimension of scenarios and risk analysis. Surprisingly, there is certainly no direct link between increased scientific understanding and a public position for or against different strategies of nuclear waste disposal. This is not due to the public being poorly informed, but rather due to cultural cognition of expertise and historical and cultural perception of hazards to regions selected to host a geologic repository. The societal and cultural dimension does not diminish the role of science, as scientific results become even more important in distinguishing

  12. (14)C, delta(13)C and total C content in soils around a Brazilian PWR nuclear power plant.

    Science.gov (United States)

    Dias, Cíntia Melazo; Telles, Everaldo C; Santos, Roberto Ventura; Stenström, Kristina; Nícoli, Iêda Gomes; da Silveira Corrêa, Rosangela; Skog, Göran

    2009-04-01

    Nuclear power plants release (14)C during routine operation mainly as airborne gaseous effluents. Because of the long half-life (5730 years) and biological importance of this radionuclide (it is incorporated in plant tissue by photosynthesis), several countries have monitoring programs in order to quantify and control these emissions. This paper compares the activity of (14)C in soils taken within 1km from a Brazilian nuclear power plant with soils taken within a reference area located 50km away from the reactor site. Analyses of total carbon, delta(13)C and (137)Cs were also performed in order to understand the local soil dynamics. Except for one of the profiles, the isotopic composition of soil organic carbon reflected the actual forest vegetation present in both areas. The (137)Cs data show that the soils from the base of hills are probably allocthonous. The (14)C measurements showed that there is no accumulation due to the operation of the nuclear facility, although excess (14)C was found in the litter taken in the area close to power plant. This indicates that the anthropogenic signal observed in the litter fall has not been transferred yet to the soil. This study is part of an extensive research programme in which other samples including air, vegetation and gaseous effluents (taken in the vent stack of the Brazilian nuclear power reactors Angra I and II) were also analyzed. The present paper aimed to evaluate how (14)C emissions from the nuclear power plant are transferred and stored by soils present in the surroundings of the reactor site. This is the first study concerning anthropogenic (14)C in soils in Brazil.

  13. Microstructural and Fractographic Characterization of a Thermally Embrittled Nuclear Grade Steel: Part II - Quenching and Tempering

    Directory of Open Access Journals (Sweden)

    José R. Tarpani

    2002-09-01

    Full Text Available A nuclear reactor pressure vessel steel was submitted to different quenching and tempering heat treatments aimed at simulating neutron irradiation damage. The obtained microstructures were mechanically tested and submitted to metallographic and fractographic survey. The relevant microstructural and fractographic aspects were employed in the interpretation of the mechanical performance of the thermally embrittled microstructures. A well defined correlation was determined between the elastic-plastic fracture toughness parameter J-integral and the Charpy impact energy, which was achieved for some of the Q&T microstructures.

  14. Effects of AT1 receptor-mediated endocytosis of extracellular Ang II on activation of nuclear factor-kappa B in proximal tubule cells.

    Science.gov (United States)

    Zhuo, Jia L; Carretero, Oscar A; Li, Xiao C

    2006-12-01

    Angiotensin II (Ang II) exerts powerful proinflammatory and growth effects on the development of Ang II-induced hypertensive glomerulosclerosis and tubulo-interstitial fibrosis. The proinflammatory and growth actions of Ang II are primarily mediated by activation of cell surface type 1 receptors (AT(1)) and the transcription factor nuclear factor-kappaB (NF-kappaB). However, binding of cell surface receptors by extracellular Ang II also induces receptor-mediated endocytosis of the agonist-receptor complex in renal cells. The purpose of the present study was to determine whether AT(1) receptor-mediated endocytosis of extracellular Ang II is required for Ang II-induced NF-kappaB activation and subsequent proliferation of rabbit renal proximal tubule cells. Expression of AT(1) (primarily AT(1a) or human AT(1)) receptors in these cells was confirmed by Western blot, showing that transfection of a human AT(1) receptor-specific 20-25 nucleotide siRNA knocked down more than 70% of AT(1) receptor protein (P cells by Ang II (1 nM) induced fourfold increases in NF-kappaB activity (P 55%, P cell proliferation and DNA synthesis, and the effect was also attenuated by coadministration of losartan and colchicine (P extracellular Ang II may be required for Ang II-induced NF-kappaB activation and subsequent cell proliferation in renal proximal tubule cells.

  15. AIRDOS-II computer code for estimating radiation dose to man from airborne radionuclides in areas surrouding nuclear facilities

    International Nuclear Information System (INIS)

    Moore, R.E.

    1977-04-01

    The AIRDOS-II computer code estimates individual and population doses resulting from the simultaneous atmospheric release of as many as 36 radionuclides from a nuclear facility. This report describes the meteorological and environmental models used is the code, their computer implementation, and the applicability of the code to assessments of radiological impact. Atmospheric dispersion and surface deposition of released radionuclides are estimated as a function of direction and distance from a nuclear power plant or fuel-cycle facility, and doses to man through inhalation, air immersion, exposure to contaminated ground, food ingestion, and water immersion are estimated in the surrounding area. Annual doses are estimated for total body, GI tract, bone, thyroid, lungs, muscle, kidneys, liver, spleen, testes, and ovaries. Either the annual population doses (man-rems/year) or the highest annual individual doses in the assessment area (rems/year), whichever are applicable, are summarized in output tables in several ways--by nuclides, modes of exposure, and organs. The location of the highest individual doses for each reference organ estimated for the area is specified in the output data

  16. The nuclear estrogen receptor R-II of the goat uterus: distinct possibility that the R-II is the deglycosylated form of the nonactivated estrogen receptor (naER).

    Science.gov (United States)

    Karthikeyan, N; Thampan, R V

    1995-08-20

    Structural and functional characteristics of the goat uterine nuclear estrogen receptor R-II have been subjected to comparison with those of the nonactivated estrogen receptor (naER), purified from the cytosol. The two proteins have the same molecular mass, 66 kDa; they display identical peptide maps and are both recognized by anti-estrogen receptor (R-I) IgG. Both are tyrosine kinases and bind with equal affinity to a column of anti-phosphotyrosine IgG-Sepharose. On the other hand, while naER is a glycoprotein, the R-II does not show any sign of glycosylation. Unlike the naER, the R-II is incapable of dimerization with estrogen receptor activation factor (E-RAF) and, as a consequence, bind to the DNA. R-II has a higher estradiol binding capacity and the resultant reduction in its affinity for the hormone in comparison with the naER. Further, the sedimentation behavior and the Stokes radius of the naER indicate a globular nature in the shape of the protein. The corresponding data for the R-II reveal that the protein has a distinct nonglobular shape. Deglycosylation of the naER using a glycopeptidase resulted in the total conversion of the distinct physical features of the naER to the R-II category. This treatment resulted, without effecting any reduction in its molecular mass, in the loss of the E-RAF dimerization capacity of the naER. The Stokes radius and the sedimentation coefficient of the protein underwent drastic changes and became closely similar to those of the R-II. In addition, the deglycosylation introduced a several-fold enhancement in the capacity of the naER to bind estradiol with a concomitant decrease in its affinity, similar to the corresponding properties of the R-II. The R-II is shown to have a conformational structure different from that of the naER, to interact with the nuclear RNA polymerase II. It is also shown here that the R-II phosphorylates two subunits (molecular mass 91 and 20 kDa) in the RNA polymerase II, in addition to the 40-k

  17. Poisson regression analysis of the mortality among a cohort of World War II nuclear industry workers

    International Nuclear Information System (INIS)

    Frome, E.L.; Cragle, D.L.; McLain, R.W.

    1990-01-01

    A historical cohort mortality study was conducted among 28,008 white male employees who had worked for at least 1 month in Oak Ridge, Tennessee, during World War II. The workers were employed at two plants that were producing enriched uranium and a research and development laboratory. Vital status was ascertained through 1980 for 98.1% of the cohort members and death certificates were obtained for 96.8% of the 11,671 decedents. A modified version of the traditional standardized mortality ratio (SMR) analysis was used to compare the cause-specific mortality experience of the World War II workers with the U.S. white male population. An SMR and a trend statistic were computed for each cause-of-death category for the 30-year interval from 1950 to 1980. The SMR for all causes was 1.11, and there was a significant upward trend of 0.74% per year. The excess mortality was primarily due to lung cancer and diseases of the respiratory system. Poisson regression methods were used to evaluate the influence of duration of employment, facility of employment, socioeconomic status, birth year, period of follow-up, and radiation exposure on cause-specific mortality. Maximum likelihood estimates of the parameters in a main-effects model were obtained to describe the joint effects of these six factors on cause-specific mortality of the World War II workers. We show that these multivariate regression techniques provide a useful extension of conventional SMR analysis and illustrate their effective use in a large occupational cohort study

  18. Communication and surrounding of Asco and Vandellos II nuclear power plants

    International Nuclear Information System (INIS)

    2004-01-01

    The Asco and Vandellos-II power plants have always been integrated into the regions where they are located, and they take an active part in the development of surrounding towns through quality employment provided by our facilities, social and cultural support and aid to development promoted by regional councils. Communication to media is a corporate priority defined in our strategic plant, to ensure openness, rigour and punctuality. We also attend to the visitors who want to learn more about our facilities in the visitor center, and we have agreements with agrarian institutions in the area so that students can de practical training in the farms we own for agricultural production. (Author)

  19. Synthetic seismograms - II. Synthesis of amplitude spectra and seismograms of P waves from underground nuclear explosions

    International Nuclear Information System (INIS)

    Banghar, A.R.

    1980-01-01

    As a part of programme of seismic detection of underground nuclear explosions, step by step variations in the amplitude spectra and waveforms of P wave signal, as it propagates from source to receiver region, are investigated. Influences on the amplitude spectra and waveforms of teleseismic p waves due to : (1) variation in the shape of reduced displacement potential, (2) variation of mantle Q values, (3) change in depth, (4) various yields, (5) spalling, and (6) variation of crustal structure at source as well as at receiver are studied. The results show that for a yield of 85 kilotons, the time structure of seismograms is nearly same for four types of reduced displacement potentials considered here. The duration of waveforms is affected both by crustal structure at source as well as due to spalling. In general, effect of receiver crust on seismograms is found to be minor. Synthesized and observed P wave seismograms for Longshot, Milrow and Cannikin underground nuclear explosions are computed at various seismometer array stations of the UKAEA. Computed seismograms compare well with the recorded ones. It is seen that: (1) overburden P wave velocity inferred from seismograms is less as compared to its value obtained from on-site measurements, and (2) the source function, the source crust transfer function, the mantle transfer function and the spalling function are the most important factors that influence shaping of spectra and seismograms. (M.G.B.)

  20. Disasters and mass casualties: II. explosive, biologic, chemical, and nuclear agents.

    Science.gov (United States)

    Born, Christopher T; Briggs, Susan M; Ciraulo, David L; Frykberg, Eric R; Hammond, Jeffrey S; Hirshberg, Asher; Lhowe, David W; O'Neill, Patricia A; Mead, Joann

    2007-08-01

    Terrorists' use of explosive, biologic, chemical, and nuclear agents constitutes the potential for catastrophic events. Understanding the unique aspects of these agents can help in preparing for such disasters with the intent of mitigating injury and loss of life. Explosive agents continue to be the most common weapons of terrorists and the most prevalent cause of injuries and fatalities. Knowledge of blast pathomechanics and patterns of injury allows for improved diagnostic and treatment strategies. A practical understanding of potential biologic, chemical, and nuclear agents, their attendant clinical symptoms, and recommended management strategies is an important prerequisite for optimal preparation and response to these less frequently used agents of mass casualty. Orthopaedic surgeons should be aware of the principles of management of catastrophic events. Stress is less an issue when one is adequately prepared. Decontamination is essential both to manage victims and prevent further spread of toxic agents to first responders and medical personnel. It is important to assess the risk of potential threats, thereby allowing disaster planning and preparation to be proportional and aligned with the actual casualty event.

  1. Nuclear inelastic scattering study of a dinuclear iron(II) complex showing a direct spin transition

    Energy Technology Data Exchange (ETDEWEB)

    Wolny, J. A., E-mail: wolny@physik.uni-kl.de [University of Kaiserslautern, Department of Physics (Germany); Garcia, Y. [Université Catholique de Louvain, Institute of Condensed Matter and Nanosciences, Molecules, Solids and Reactivity (IMCN/MOST) (Belgium); Faus, I.; Rackwitz, S. [University of Kaiserslautern, Department of Physics (Germany); Schlage, K.; Wille, H.-C. [DESY (Germany); Schünemann, V. [University of Kaiserslautern, Department of Physics (Germany)

    2016-12-15

    The results of the nuclear inelastic scattering (NIS)/nuclear resonance vibrational spectroscopy (NRVS) for the powder spectra of dimeric [Fe {sub 2}L{sub 5}(NCS) {sub 4}] (L = N-salicylidene-4-amino-1,2,4-triazole) complex are presented. This system is spin crossover (SCO) material tagged with a fluorophore that can sense or “feel” the SCO signal ripping through the molecular network and thereby providing an opportunity to register the SCO transition. The spectra have been measured for the low-spin and high-spin phases of the complex. The high-spin isomer reveals one broad band above 200 cm {sup −1}, while the low-spin one displays two intense bands in the range from 390 to 430 cm {sup −1}, accompanied by a number of weaker bands below this area and one at ca. 490 cm {sup −1}. A normal coordinate analysis based on density functional calculations yields the assignment of the spin marker bands to particular molecular modes. In addition the vibrational contribution to the spin transition has been estimated.

  2. Radiological environmental monitoring program for Angra I: basis and methodology proposed for executing the requirements of the regulatory member and to assure the population safety

    International Nuclear Information System (INIS)

    Kircher, E.; Dezordi, W.L.

    1984-01-01

    It is presented, applyed to Angra-1, a methodology for implanting the monitoring program of the vicinity level radiation exposure to the installation. The method considers two kinds of radioactive effluents in the environment: gaseous (in the atmosphere) and liquid (in the marine aquatic environment). It is based on the generation and ordering of the important relation: radiation exposure pathway/radionuclide group. (M.C.K.) [pt

  3. Selection of bioindicators for 90-Sr among the benthic marine algae from the Saco do Piraquara de Fora, Angra dos Reis, RJ (preliminary results)

    International Nuclear Information System (INIS)

    Azevedo, H.L.P. de; Vianna, M.E.C.; Monteiro, D.; Fernandes, H.; Gusmao Pedrini, A. de

    1983-01-01

    With the aim of pre-selecting bioindicators for Sr-90 among the marine algae, monthly sampling in three different fixed locations, have benn done and strontium and calcium concentrations have been determined in the most abundant species of algae in the region of Angra dos Reis. In order to establish the influence of seasonal variations, the sea water salinity and strontium and calcium concentrations have also been analysed. (E.G.) [pt

  4. Beznau II nuclear power plant: Expertise on NOK's request for the removal of the time limitation for the operation licence; KKW Beznau II: Gutachten zum Gesuch der NOK um Aufhebung der Befristung der Betriebsbewilligung

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2004-03-15

    The Federal Agency for the Safety of Nuclear Installations (HSK) is the Swiss authority responsible for nuclear safety and protection against radioactivity in nuclear power plants. It has to examine the request of the North-East Swiss Power Corporation (NOK) concerning the removal of the operational time limitation for the Beznau-II reactor (KKB-II). In the present report HSK reviews the enterprise management and the safety of KKB-II on the basis of the results of the Periodic Safety Review. The Beznau nuclear power plant exhibits a very high degree of technical and organisational safety. During the past 10 years the plant has been operated in a safe manner. At the same time the plant has been improved and this guarantees that the mechanisms of ageing degradation are systematically identified and that measures can be taken that are possibly necessary. Under such conditions, the safety of KKB-II can be guarantied at all times. As a result of the management of quality, environmental and working safety conditions, the correct application and the continuous improvement of all processes important to safety are ensured. With these measures KKB has shown that safety is given priority over and against all other working goals. The examination by HSK of the Periodic Safety Review has shown that, in the past, KKB has applied modernisation measures independent of the licensing situation of the two reactor blocks. These modernisation measures largely contribute to the fact that the HSK examination did not reveal any significant safety deficiencies. Other improvement measures allow risk reduction or can bee seen as an adaptation to experience gained and to the state of the technological art. In conclusion, HSK states that no safety-relevant facts have been found which could prevent the removal of the time limitation on the operational licence for KKB-II. From the point of view of HSK, KKB-II fulfils the conditions for the safe continuation of operation

  5. In the matter of the application of the Westinghouse Electric Corporation for the export of pressurized water reactor to Asociacion Nuclear ASCO II, Barcelona, Spain

    International Nuclear Information System (INIS)

    Rowden, M.A.; Mason, E.A.; Gilinsky, V.; Kennedy, R.T.

    1976-01-01

    The paper contains the text of a decision of the US NRC that the export of the ASCO nuclear power unit II to Spain would not be inimical to the common defense and security of the United States, so that there are no objections to issue the license to Westinghouse Electric Corporation. Furthermore the paper contains the dissenting opinion of Commissioner Gilinsky. (HP) [de

  6. Reason analysis for contamination of protective clothes during the first outage of unit 1 at Qinshan Nuclear Power Plant phase II

    International Nuclear Information System (INIS)

    Wang Chuan; Wang Dezhong; Zheng Weiyan

    2007-01-01

    More contamination events of protective clothes were occurred during the first outage of Unit 1 at Qinshan Nuclear Power Plant phase II. As a result, contaminated protective clothes were accumulated. This paper describes the amount and conditions of protective clothes analyses and discussies the reason of contamination. The measures for protecting protective clothes agaist contamination were put forward. (authors)

  7. A probabilistic seismic risk assessment procedure for nuclear power plants: (II) Application

    Science.gov (United States)

    Huang, Y.-N.; Whittaker, A.S.; Luco, N.

    2011-01-01

    This paper presents the procedures and results of intensity- and time-based seismic risk assessments of a sample nuclear power plant (NPP) to demonstrate the risk-assessment methodology proposed in its companion paper. The intensity-based assessments include three sets of sensitivity studies to identify the impact of the following factors on the seismic vulnerability of the sample NPP, namely: (1) the description of fragility curves for primary and secondary components of NPPs, (2) the number of simulations of NPP response required for risk assessment, and (3) the correlation in responses between NPP components. The time-based assessment is performed as a series of intensity-based assessments. The studies illustrate the utility of the response-based fragility curves and the inclusion of the correlation in the responses of NPP components directly in the risk computation. ?? 2011 Published by Elsevier B.V.

  8. Safety probabilistic study of Almirante Alvaro Alberto nuclear power plant-Unit I

    International Nuclear Information System (INIS)

    Lederman, L.; Arrieta, L.A.I.; Fernandes Filho, T.L.; Gibelli, S.M.O.; Berthoud, J.S.; Ambros, P.C.; Soares, H.V.; Camargo, C.T.M.

    1985-04-01

    The phase A of probabilistic safety study of Angra I nuclear power plant is presented, to be used by CNEN and FURNAS Centrais Eletricas S.A. as standard model in operational and safety analysis. The methodology applied is a modernization of WASH 1400/2.11/ study. Angra I safety systems are described. The selection and qualification of initiating sequence accident events which can damage the reactor core are done. The accident scenes are developed using the method of event trees. The reactor in subcritical condition (pressure, fuel temperature within limits and controlled level of reactor vessel) is studied during 24 hours. The uncertainness in failure probabilities of systems and in the determination of sequence frequencies for core danification are evaluated. Total frequency of sequences which cause the fusion of reactor core are presented. (M.C.K.) [pt

  9. Purification and characterization of nuclear type II [(3)H]estradiol binding sites from the rat uterus: covalent labeling with [(3)H]luteolin.

    Science.gov (United States)

    Markaverich, B M; Shoulars, K; Brown, M A

    2001-09-01

    Type II [3H]estradiol binding sites play an important role in normal and malignant cell growth and proliferation and the delineation of the precise function of the type II site in cell growth has been hampered by the inability to purify, sequence and or clone this protein. The present manuscript describes methodology for the solubilization, purification and tentative identification of type II sites from the estrogen-treated rat uterus. This protein(s) chromatographs as a single major peak on DNA-cellulose, Affigel Blue dye affinity resin and during high performance liquid chromatography (HPLC) on hydroxyapatite. The purified fractions from these columns elicited classical [3H]estradiol binding characteristics (sigmoidal saturation curve, hyperbolic Scatchard plot, and Hill coefficient of approximately 4) for type II sites that are typically observed in crude or highly purified nuclear fractions or extracts. The type II binding activity also eluted as a single major component from a ligand affinity resin (GT-18-Sepharose) prepared by coupling 2,6-bis((3-methoxy-4-hydroxyphenyl)methylene)-cyclohexanone to epoxy-activated Sepharose (Pharmacia). The molecular weight of the type II site ([3H]estradiol binding activity) under non-denaturing or denaturing conditions was estimated to be approximately 10-15 kDa by gel filtration HPLC. Similarly, nuclear type II sites covalently labeled with the bioflavonoid, [3H]luteolin, migrated in the 10 kDa range on SDS PAGE. Thus, under these various experimental conditions, nuclear type II sites detected by [3H]estradiol or [3H]luteolin labeling techniques displayed little heterogeneity and appear much smaller than ERalpha or ERbeta or other steroid hormone receptors.

  10. Model of automatic fuel management for the Atucha II nuclear central with the PUMA IV code

    International Nuclear Information System (INIS)

    Marconi G, J.F.; Tarazaga, A.E.; Romero, L.D.

    2007-01-01

    The Atucha II central is a heavy water power station and natural uranium. For this reason and due to the first floor reactivity excess that have this type of reactors, it is necessary to carry out a continuous fuel management and with the central in power (for the case of Atucha II every 0.7 days approximately). To maintain in operation these centrals and to achieve a good fuels economy, different types of negotiate of fuels that include areas and roads where the fuels displace inside the core are proved; it is necessary to prove the great majority of these managements in long periods in order to corroborate the behavior of the power station and the burnt of extraction of the fuel elements. To carry out this work it is of great help that a program implements the approaches to continue in each replacement, using the roads and areas of each administration type to prove, and this way to obtain as results the one regulations execution in the time and the average burnt of extraction of the fuel elements, being fundamental this last data for the operator company of the power station. To carry out the previous work it is necessary that a physicist with experience in fuel management proves each one of the possible managements, even those that quickly can be discarded if its don't fulfill with the regulatory standards or its possess an average extraction burnt too much low. For this it is of fundamental help that with an automatic model the different administrations are proven and lastly the physicist analyzes the more important cases. The pattern in question not only allows to program different types of roads and areas of fuel management, but rather it also foresees the possibility to disable some of the approaches. (Author)

  11. Enhancement of organizational resilience in light of the Fukushima Dai-ichi Nuclear Power Plant accident (4). Consideration of nurturing attitude to achieve the safety-II

    International Nuclear Information System (INIS)

    Oba, Kyoko; Yoshizawa, Atsufumi; Kitamura, Masaharu

    2015-01-01

    The Fukushima nuclear plant accident has been examined aiming at clarifying the factors influencing responding which is one of the four cornerstones of resilience engineering. Among the causal factors of responding, such as attitude, skill, health and environment, particular attention has been paid on the role of attitude. In addition, the case of Tokai Dai-ni nuclear plant, which was the success case despite tsunami attack, and the case of Fukushima Dai-ichi nuclear plant have been examined focusing on preparatory actions taken prior to the tsunami attack. Through the comparative examinations, attitudes of several kinds have been identified as key factors contributing to enhance organizational resilience. Moreover, the importance of safety-II concept proposed in conjunction with the methodology of resilience engineering has been clearly exemplified. As a whole, it can be concluded that the methodology of resilience engineering and the concept of safety-II are quite effective when utilized with the structured model. (author)

  12. Safety Evalution Report related to the final design approval of the GESSAR II BWR/6 nuclear island design (Docket No. 50-447)

    International Nuclear Information System (INIS)

    1984-11-01

    This report supplements the GESSAR II SER (NUREG-0979), issued in April 1983, summarizing the results of the staff's safety review of the GESSAR II BWR/6 nuclear island design. The review is carried out in accordance with the procedures for demonstrating the acceptability of the design for the severe-accident concerns described in draft NUREG-1070, NRC Policy on Future Reactor Designs: Decisions on Severe Accident Issues in Nuclear Power Plant Regulation. Supplement 2 also provides more recent information regarding resolution or update of the confirmatory items and FDA-1 conditions identified in SSER 1. Subject to favorable resolution of the items discussed in this supplement, the staff concludes that the GESSAR II design satisfactorily addresses the severe-accident concerns described in draft NUREG-1070

  13. The European Research on Severe Accidents in Generation-II and -III Nuclear Power Plants

    Directory of Open Access Journals (Sweden)

    Jean-Pierre Van Dorsselaere

    2012-01-01

    Full Text Available Forty-three organisations from 22 countries network their capacities of research in SARNET (Severe Accident Research NETwork of excellence to resolve the most important remaining uncertainties and safety issues on severe accidents in existing and future water-cooled nuclear power plants (NPP. After a first project in the 6th Framework Programme (FP6 of the European Commission, the SARNET2 project, coordinated by IRSN, started in April 2009 for 4 years in the FP7 frame. After 2,5 years, some main outcomes of joint research (modelling and experiments by the network members on the highest priority issues are presented: in-vessel degraded core coolability, molten-corium-concrete-interaction, containment phenomena (water spray, hydrogen combustion…, source term issues (mainly iodine behaviour. The ASTEC integral computer code, jointly developed by IRSN and GRS to predict the NPP SA behaviour, capitalizes in terms of models the knowledge produced in the network: a few validation results are presented. For dissemination of knowledge, an educational 1-week course was organized for young researchers or students in January 2011, and a two-day course is planned mid-2012 for senior staff. Mobility of young researchers or students between the European partners is being promoted. The ERMSAR conference is becoming the major worldwide conference on SA research.

  14. TRIGA Mark II nuclear reactor facility. Final report, 1 July 1980--30 June 1995

    Energy Technology Data Exchange (ETDEWEB)

    Ryan, B.C.

    1997-05-01

    This report is a final culmination of activities funded through the Department of Energy`s (DOE) University Reactor Sharing Program, Grant DE-FG02-80ER10273, during the period 1 July 1980 through 30 June 1995. Progress reports have been periodically issued to the DOE, namely the Reactor Facility Annual Reports C00-2082/2219-7 through C00-2082/10723-21, which are contained as an appendix to this report. Due to the extent of time covered by this grant, summary tables are presented. Table 1 lists the fiscal year financial obligations of the grant. As listed in the original grant proposals, the DOE grant financed 70% of project costs, namely the total amount spent of these projects minus materials costs and technical support. Thus the bulk of funds was spent directly on reactor operations. With the exception of a few years, spending was in excess of the grant amount. As shown in Tables 2 and 3, the Reactor Sharing grant funded a immense number of research projects in nuclear engineering, geology, animal science, chemistry, anthropology, veterinary medicine, and many other fields. A list of these users is provided. Out of the average 3000 visitors per year, some groups participated in classes involving the reactor such as Boy Scout Merit Badge classes, teacher`s workshops, and summer internships. A large number of these projects met the requirements for the Reactor Sharing grant, but were funded by the University instead.

  15. TRIGA Mark II nuclear reactor facility. Final report, 1 July 1980--30 June 1995

    International Nuclear Information System (INIS)

    Ryan, B.C.

    1997-05-01

    This report is a final culmination of activities funded through the Department of Energy's (DOE) University Reactor Sharing Program, Grant DE-FG02-80ER10273, during the period 1 July 1980 through 30 June 1995. Progress reports have been periodically issued to the DOE, namely the Reactor Facility Annual Reports C00-2082/2219-7 through C00-2082/10723-21, which are contained as an appendix to this report. Due to the extent of time covered by this grant, summary tables are presented. Table 1 lists the fiscal year financial obligations of the grant. As listed in the original grant proposals, the DOE grant financed 70% of project costs, namely the total amount spent of these projects minus materials costs and technical support. Thus the bulk of funds was spent directly on reactor operations. With the exception of a few years, spending was in excess of the grant amount. As shown in Tables 2 and 3, the Reactor Sharing grant funded a immense number of research projects in nuclear engineering, geology, animal science, chemistry, anthropology, veterinary medicine, and many other fields. A list of these users is provided. Out of the average 3000 visitors per year, some groups participated in classes involving the reactor such as Boy Scout Merit Badge classes, teacher's workshops, and summer internships. A large number of these projects met the requirements for the Reactor Sharing grant, but were funded by the University instead

  16. Development of advanced nuclear core analysis system applicable to various reactor types (II)

    International Nuclear Information System (INIS)

    Kaneko, Kunio

    2003-03-01

    A 900 group cross section library based on the specification determined last year was produced for 27 nuclei of the fast reactor benchmark problem evaluated in nuclear data file JENDL-3.2. In addition, the new SLAROM code, which has been developed as an advanced detail analysis system, was revised so as to make cell calculations effectively with the above 900 group library. Furthermore, new functions were added to the SLAROM so that the SLAROM evaluates assembly parameters using effective cross sections derived by the SLAROM and produces any condensed effective cross section set for core performance analysis. With the 900 group cross section library and the revised SALROM, three cell calculations for fast and medium neutron speed reactors having different neutron spectrum were performed, and the results were compared with those calculated by the continuos energy Monte Carlo code MVP. By the comparisons, it is concluded that the newly revised SLAROM and a 900 group cross section library give accuracy comparable to MVP for predicting core performances. (author)

  17. Radiation effects in concrete for nuclear power plants, Part II: Perspective from micromechanical modeling

    International Nuclear Information System (INIS)

    Le Pape, Y.; Field, K.G.; Remec, I.

    2015-01-01

    Highlights: • A micromechanical model for irradiated concrete is proposed. • Confrontation with literature data is successful. • Neutron radiation-induced volumetric expansion is a predominant degradation mode. • The nature of the aggregate alters the severity of damage to irradiated concrete. - Abstract: The need to understand and characterize the effects of neutron irradiation on concrete has become urgent because of the possible extension of service life of many nuclear power generating stations. Current knowledge is primarily based on a collection of data obtained in test reactors. These data are inherently difficult to interpret because materials and testing conditions are inconsistent. A micromechanical approach based on the Hashin composite sphere model is presented to derive a first-order separation of the effects of radiation on cement paste and aggregate, and, also, on their interaction. Although the scarcity of available data limits the validation of the model, it appears that, without negating a possible gamma-ray induced effect, the neutron-induced damage and swelling of aggregate plays a predominant role on the overall concrete expansion and the damage of the cement paste. The radiation-induced volumetric expansion (RIVE) effects can also be aided by temperature elevation and shrinkage in the cement paste

  18. Quantitative analysis of the radioactive wastes to be generated in the Brazilian nuclear power plants

    International Nuclear Information System (INIS)

    Santos, Jose Mauro Esteves dos

    1979-01-01

    In the nuclear fuel cycle radioactive waste requiring special treatment (processing, transportation and disposal) is produced. For the implementation of a waste management program, parameters such as volume, specific activity, thermal power, gamma power, (alpha,η) and spontaneous fission neutron production rates are required. In this work, we have calculated: a) The specific activity, thermal power, gamma power and neutron production rate for the irradiated fuel of Angra II; b) The volumes of radioactive waste that will be produced in the nuclear fuel cycle in Brazil; c) The specific activity, thermal power, gamma power and neutron production rate for the high-level waste that will be produced during fuel reprocessing. In the short-term it is concluded that the major problems that will require solution will be the disposal of the low-level waste (volume V L ) and the interim storage of the irradiated fuel elements (volume V F ) generated in the nuclear power plants. For the years 1990 and 2010 these volumes are: (1990) V L = 16149 m 3 ; V F = 1287 m 3 and (2010) V L = 690506 m 3 , V F = 55051 m 3 . In the medium-term the problem of the interim storage of the high-level waste (volume V H ) must be solved. The volumes of this waste we have calculated for the years 2000 and 2010 are: (2000) V H = 50 m 3 and (2010) V H = 1265 m 3 . Long term evaluation of high-level waste disposal must be analysed to aid in initial studies of this problem. Several parameters of this waste have been calculated as a function of time after reprocessing. (author)

  19. Sucessão vegetal em uma encosta reflorestada com leguminosas arbóreas em Angra dos Reis, RJ Natural succession under a nitrogen-fixing legume trees stand in a hillside at Angra dos Reis - RJ, Brazil

    Directory of Open Access Journals (Sweden)

    Sylvia de Souza Chada

    2004-12-01

    Full Text Available Em uma encosta reflorestada há sete anos com leguminosas arbóreas (Acacia auriculiformis, A. mangium e Mimosa tenuiflora em Angra dos Reis, RJ, foi avaliada a composição florística e fitossociológica da regeneração natural, comparando-as com as de um fragmento de Mata Secundária situado a 200 m de distância. Foram considerados os três terços da encosta, com declividades decrescentes. Em 12 parcelas de 200 m², quatro em cada terço da encosta, foram amostrados 699 indivíduos vegetais a partir de 40 cm de altura, distribuídos em 25 famílias e 50 espécies. As famílias com maior nº de indivíduos foram Meliaceae (298, Euphorbiaceae (70, Piperaceae (64 e Lauraceae (41. Já as famílias com maior nº de espécies foram Solanaceae (7, Melastomataceae (5 e Myrtaceae (5. As leguminosas plantadas não estavam regenerando na própria área. A evolução da sucessão natural apresentou um gradiente de desenvolvimento em razão da menor declividade e menor distância dos remanescentes florestais, com maior densidade de indivíduos e maior riqueza de espécies na área de menor declividade.The floristic composition and natural regeneration under a 7-year-old legume tree plantation (Acacia auriculiformis, A. mangium e Mimosa tenuiflora was investigated in comparing with a secondary forest 200 m away at Angra dos Reis, RJ. The hillside was divided in 3 parts following the slope. The lower part of the hillside was the nearest to the natural forest remnant. In 12 plots with 200 m² each, 4 of them in each section of the hillside, 699 plants larger then 40 cm height were observed, distributed in 25 families and 50 species. The families with the most individuals were Meliaceae (298, Euphorbiaceae (70, Piperaceae (64 and Lauraceae (41. The families with the most species were Solanaceae (7, Melastomataceae (5 and Myrtaceae (5. None of the legume species introduced in the area had produced natural regeneration. The evolution of natural succession

  20. Ageing management program of wires for Atucha II Nuclear Power Plant

    International Nuclear Information System (INIS)

    Zorrilla, J.; Antonaccio, E.; Luraschi, C.; Simionato, E.; Nieto, H.

    2012-01-01

    Electrical cables constitute one of the most important components of NPP in terms o maintenance, safety and availability of the plant. Due to their large extension (thousands of kilometers) it is impossible to fully replace them and aging management becomes essential for long term operation of NPP. Since Atucha II is under construction there was a good opportunity to establish and implement a holistic cable aging management program from the beginning according to the state of the art in this field. The scope of this program involves safety related cables, including EQ cables and non EQ cables as well. Due to the diversity of the installed cables is impossible to address an aging management program of every single specimen. However it is possible to establish 'cables families' of similar aging behavior based on insulation and jacket material, manufacture, etc Several aging management strategies were set for the different 'cables families'. These strategies include cables deposit in plant, elaboration of procedures of visual and tactile inspection, NDE techniques, etc Currently the aging management program is being implemented covering topic such as: Cable screening and grouping. Review of EQ documentation and conventional qualification information referring to the installed cables. Establishment of base line of condition monitoring techniques. Calibration and set up of test parameters for NDE techniques. Aging mechanism characterization and determination of. Design construction and installation of cable deposit in plant (author)

  1. Report of the Secretary of Defense Task Force on DoD Nuclear Weapons Management. Phase II: Review of the DoD Nuclear Mission

    National Research Council Canada - National Science Library

    Schlesinger, James R; Carns, Michael P; Crouch, II, J. D; Gansler, Jacques S; Giambastiani, Jr., Edmund P; Hamre, John J; Miller, Franklin C; Williams, Christopher A; Blackwell, Jr, James A

    2008-01-01

    Incidents related to the Air Force's mishandling of nuclear weapons and components led to the creation of the Task Force in June 2008 to provide advice on nuclear matters for the Secretary of Defense...

  2. Proceeding of the Scientific Meeting and Presentation on Basic Research in Nuclear Science and Technology part II : Nuclear Chemistry, Process Technology, Radioactive Waste Management and Environment

    International Nuclear Information System (INIS)

    Sukarsono, R.; Ganang Suradjijo

    2002-01-01

    Scientific Meeting and Presentation on Basic Research in Nuclear Science and Technology is a routine activity held by Centre for Research and Development of Advanced Technology, National Nuclear Energy Agency, for monitoring the research activity which achieved in National Nuclear Energy Agency. This proceedings contains a proposal about basic research in nuclear technology which has environment. This proceedings is the second part of the two parts which published in series. There are 57 articles which have separated index. (PPIN)

  3. DJ-1 Modulates Nuclear Erythroid 2-Related Factor-2-Mediated Protection in Human Primary Alveolar Type II Cells in Smokers.

    Science.gov (United States)

    Bahmed, Karim; Messier, Elise M; Zhou, Wenbo; Tuder, Rubin M; Freed, Curt R; Chu, Hong Wei; Kelsen, Steven G; Bowler, Russell P; Mason, Robert J; Kosmider, Beata

    2016-09-01

    Cigarette smoke (CS) is a main source of oxidative stress and a key risk factor for emphysema, which consists of alveolar wall destruction. Alveolar type (AT) II cells are in the gas exchange regions of the lung. We isolated primary ATII cells from deidentified organ donors whose lungs were not suitable for transplantation. We analyzed the cell injury obtained from nonsmokers, moderate smokers, and heavy smokers. DJ-1 protects cells from oxidative stress and induces nuclear erythroid 2-related factor-2 (Nrf2) expression, which activates the antioxidant defense system. In ATII cells isolated from moderate smokers, we found DJ-1 expression by RT-PCR, and Nrf2 and heme oxygenase (HO)-1 translocation by Western blotting and immunocytofluorescence. In ATII cells isolated from heavy smokers, we detected Nrf2 and HO-1 cytoplasmic localization. Moreover, we found high oxidative stress, as detected by 4-hydroxynonenal (4-HNE) (immunoblotting), inflammation by IL-8 and IL-6 levels by ELISA, and apoptosis by terminal deoxynucleotidyl transferase dUTP nick end labeling (TUNEL) assay in ATII cells obtained from heavy smokers. Furthermore, we detected early DJ-1 and late Nrf2 expression after ATII cell treatment with CS extract. We also overexpressed DJ-1 by adenovirus construct and found that this restored Nrf2 and HO-1 expression and induced nuclear translocation in heavy smokers. Moreover, DJ-1 overexpression also decreased ATII cell apoptosis caused by CS extract in vitro. Our results indicate that DJ-1 activates the Nrf2-mediated antioxidant defense system. Furthermore, DJ-1 overexpression can restore the impaired Nrf2 pathway, leading to ATII cell protection in heavy smokers. This suggests a potential therapeutic strategy for targeting DJ-1 in CS-related lung diseases.

  4. Reliability analysis of the service water system of Angra 1 reactor

    International Nuclear Information System (INIS)

    Tayt-Sohn, L.C.; Oliveira, L.F.S. de.

    1984-01-01

    A reliability analysis of the service water system is done aiming to use in the evaluation of the non reliability of the Component Cooling System (SRC) for great loss of cooling accidents in nuclear power plants. (E.G.) [pt

  5. Reliability analysis of the service water system of Angra 1 reactor

    International Nuclear Information System (INIS)

    Oliveira, L.F.S. de; Fleming, P.V.; Frutuoso e Melo, P.F.F.; Tayt-Sohn, L.C.

    1983-01-01

    A reliability analysis of the service water system is done aiming to use in the evaluation of the non reliability of the component cooling system (SRC) for great loss of cooling accidents in nuclear power plants. (E.G.) [pt

  6. Novel homo- and hetero-nuclear copper(II) complexes of tetradentate Schiff bases: synthesis, characterization, solvent-extraction and catalase-like activity studies.

    Science.gov (United States)

    Dede, Bülent; Karipcin, Fatma; Cengiz, Mustafa

    2009-04-30

    Twelve homo- and hetero-nuclear copper(II) complexes of tetradentate Schiff base ligands containing N(4) donor sets have been prepared by employing several steps. The characterization and nature of bonding of the complexes have been deduced from elemental analysis, FT-IR, molar conductivity, magnetic moment measurements and thermal analysis. The three Schiff base ligands were further identified using (1)H and (13)C NMR spectra. All copper(II) complexes are 1:2 electrolytes as shown by their molar conductivities (Lambda(M)) in DMF and paramagnetic. The subnormal magnetic moment values of the di- and tri-nuclear complexes explained by a very strong anti-ferromagnetic interaction. The extraction ability of the ligands has been examined by the liquid-liquid extraction of selected transition metal (Mn(2+), Co(2+), Ni(2+), Cu(2+), Zn(2+), Pb(2+), Cd(2+), Hg(2+)) cations. The ligands show strong binding ability toward copper(II) ion. Furthermore the homo- and hetero-nuclear copper(II) complexes were each tested for their ability to catalyse the disproportionation of hydrogen peroxide in the presence of the added base imidazole.

  7. Nuclear Waste Management under Approaching Disaster: A Comparison of Decommissioning Strategies for the German Repository Asse II.

    Science.gov (United States)

    Ilg, Patrick; Gabbert, Silke; Weikard, Hans-Peter

    2017-07-01

    This article compares different strategies for handling low- and medium-level nuclear waste buried in a retired potassium mine in Germany (Asse II) that faces significant risk of uncontrollable brine intrusion and, hence, long-term groundwater contamination. We survey the policy process that has resulted in the identification of three possible so-called decommissioning options: complete backfilling, relocation of the waste to deeper levels in the mine, and retrieval. The selection of a decommissioning strategy must compare expected investment costs with expected social damage costs (economic, environmental, and health damage costs) caused by flooding and subsequent groundwater contamination. We apply a cost minimization approach that accounts for the uncertainty regarding the stability of the rock formation and the risk of an uncontrollable brine intrusion. Since economic and health impacts stretch out into the far future, we examine the impact of different discounting methods and rates. Due to parameter uncertainty, we conduct a sensitivity analysis concerning key assumptions. We find that retrieval, the currently preferred option by policymakers, has the lowest expected social damage costs for low discount rates. However, this advantage is overcompensated by higher expected investment costs. Considering all costs, backfilling is the best option for all discounting scenarios considered. © 2016 Society for Risk Analysis.

  8. Temperature variation on the Mediterranean Sea by the exploitation of the Vandellos II Nuclear Power Plant; Variacion de temperatura en el mar mediterraneo por la explotacion de la C.N. de Vandellos II

    Energy Technology Data Exchange (ETDEWEB)

    Villarreal Romero, M.; Ribes Hernandez, G.; Esparza Martin, J. L.

    2010-07-01

    The aim of this study is to verify the compliance with the Resolution of 7th February MAH/285/2007 Departament de Medi Ambient I Habitatge de la Generalitat de Catalunya establishing discharges limits to the Mediterranean Sea and, in particular, the section that references the thermal rise. The study area include about 1.5 km coastline, which is located in the vicinity of the Vandellos II Nuclear Power Plant.

  9. Flow regimes and heat transfer modes identification in ANGRA 2 core, during small break in the primary loop with area of 100 cm2, simulated with RELAP5 code

    International Nuclear Information System (INIS)

    Borges, Eduardo M.; Sabundjian, Gaiane

    2015-01-01

    Identifying the flow regimes and the heat transfer modes is important for the analysis of accidents such as the Loss-of-Coolant Accident (LOCA). The aim of this paper is to identify the flow regimes, the heat transfer modes, and the correlations used in the RELAP5/MOD3.2.gama code in ANGRA 2 during the Small-Break Loss-of-Coolant Accident (SBLOCA) with a 100cm 2 -rupture area in the cold leg of primary loop. The Chapter 15 of the Final Safety Analysis Report of ANGRA 2 (FSAR - A2) reports this specific kind of accident. The results from this work demonstrated the several flow regimes and heat transfer modes that can be present in the core of ANGRA 2 during the postulated accident. (author)

  10. Flow regimes and heat transfer modes identification in ANGRA 2 core, during small break in the primary loop with area of 100 cm{sup 2}, simulated with RELAP5 code

    Energy Technology Data Exchange (ETDEWEB)

    Borges, Eduardo M.; Sabundjian, Gaiane, E-mail: gdgian@ipen.br, E-mail: borges.em@hotmail.com [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

    2015-07-01

    Identifying the flow regimes and the heat transfer modes is important for the analysis of accidents such as the Loss-of-Coolant Accident (LOCA). The aim of this paper is to identify the flow regimes, the heat transfer modes, and the correlations used in the RELAP5/MOD3.2.gama code in ANGRA 2 during the Small-Break Loss-of-Coolant Accident (SBLOCA) with a 100cm{sup 2}-rupture area in the cold leg of primary loop. The Chapter 15 of the Final Safety Analysis Report of ANGRA 2 (FSAR - A2) reports this specific kind of accident. The results from this work demonstrated the several flow regimes and heat transfer modes that can be present in the core of ANGRA 2 during the postulated accident. (author)

  11. Influence of marine sediments in the distribution of the main radionuclides of the effluent from the nuclear power plant Almirante Alvaro Alberto (Unit 1)

    International Nuclear Information System (INIS)

    Brugnara, Miriam

    1977-01-01

    This study aimed to: 1) Characterize bottom sediments of the Angra dos Reis region, in the dispersion area of the effluent of the central Almirante Nuclear Alvaro Alberto, Unit 1. 2) Determining the adsorption capacity of these sediments to the long half-life and mean radionuclides to be released in the reactor effluent in a higher concentration. 3) Estimate the fraction of the different studied radionuclides that will be immobilized in sediments. 4) Identify critical radionuclides available for food chain

  12. Analysis of Particle Production in the Municipalities of Angra dos Reis, Campos and Petropolis in Rio de Janeiro

    Directory of Open Access Journals (Sweden)

    Sebastião Lourenço dos Santos João

    2014-12-01

    Full Text Available The productive clusters are currently constant reference in the research lines turn into strategic issue. Cities with production clusters have differentiated development in relation to other cities. This development has a direct influence on the location / installation and management of companies. This factor allows the organization gain a competitive advantage due to proximity to their suppliers and direct contact with the local population. With supplier companies increase the mobility of its supply chain and benefit from the existence of quality equipment in the network. This study aims to analyze, evaluate and classify the productive clusters of cities in the State of Rio de Janeiro, particularly in the municipalities of Angra dos Reis, Campos and Petropolis, to achieve balanced local development that benefits all stakeholders by product / city services. Productive clusters must necessarily contribute to improving the level of service offered to the customer. The methodology adopted was proposed by the Suzigan et al (2003 and Britto and Albuquerque (2002, to assess, analyze and classify the clusters in addition to bibliographic survey to support the study. The results show that depending on the importance of economic activity for the city, the production clusters greatly contribute to local development and increase the range of options for the local consumer.

  13. Report of the Secretary of Defense Task Force on DoD Nuclear Weapons Management. Phase II: Review of the DoD Nuclear Mission

    Science.gov (United States)

    2008-12-01

    Tennessee SSBN 734(Blue) – Rear Admiral Stephen Johnson , Director Strategic Systems Program, USN – The Honorable Dale Klein, Former Assistant Secretary...Defense Science Board Permanent Task Force on Nuclear Weapons Surety – Lieutenant Colonel Dwayne Whiteside, Commanding Officer Marine Corps Security...and Cooperation.” Stanford University, Stanford, CA, February 8, 2008. Johnson , Stephen E. “Navy Inventory and Assessment: Nuclear Weapons and Nuclear

  14. Proceedings of the Scientific Meeting and Presentation on Basic Researchin Nuclear Science and Technology part II: Nuclear Chemistry, Process Technology, Radioactive Waste Management and Environment

    International Nuclear Information System (INIS)

    Sukarsono, R.; Karmanto, Eko-Edy; Suradjijo, Ganang

    2000-01-01

    Scientific Meeting and Presentation on Basic Research in Nuclear Scienceand Technology is an annual activity held by Centre for Research and Development of Advanced Technology, National Nuclear Energy Agency, for monitoring research activities achieved by the Agency. The papers presented in the meeting were collected into proceedings. These are the second part of the proceedings that contain 71 articles in the fields of nuclear chemistry, process technology, radioactive waste management, and environment (PPIN).

  15. Proceeding of the Scientific Meeting and Presentation on Basic Research in Nuclear of the Scientific and Technology Part II : Nuclear Chemistry; Process Technology and Radioactive Waste Management; Environment

    International Nuclear Information System (INIS)

    Sudjatmoko; Karmanto, Eko Edy; Endang-Supartini

    1996-04-01

    Scientific Meeting and Presentation on Basic Research in Nuclear Science and Technology is a routine activity was held by Yogyakarta Nuclear Research Centre, National Atomic Energy Agency (BATAN) for monitoring the research activity which achieved in BATAN. The Proceeding contains a proposal about basic which has Nuclear Chemistry, Process Technology, Radioactive Waste Management and Environment. This proceeding is the second part from two part which published in series. There are 61 articles which have separated index

  16. Report of the joint seminar on heavy-ion nuclear physics and nuclear chemistry in the energy region of tandem accelerators (II)

    International Nuclear Information System (INIS)

    1986-04-01

    A meeting of the second joint seminar on Heavy-Ion Nuclear Physics and Nuclear Chemistry in the Energy Region of Tandem Accelerators was held after an interval of two years at the Tokai Research Establishment of the JAERI, for three days from January 9 to 11, 1986. In the seminar, about 70 nuclear physicists and nuclear chemists of JAERI and other Institutes participated, and 38 papers were presented. These include general reviews and topical subjects which have been developed intensively in recent years, as well as the new results obtained by using the JAERI tandem accelerator. This report is a collection of the papers presented to the seminar. (author)

  17. Proceedings of the Scientific Meeting and Presentation on Basic Research in Nuclear of the Science and Technology part II : Nuclear Chemistry and Process Technology

    International Nuclear Information System (INIS)

    Kamsul Abraha; Yateman Arryanto; Sri Jauhari S; Agus Taftazani; Kris Tri Basuki; Djoko Sardjono, Ign.; Sukarsono, R.; Samin; Syarip; Suryadi, MS; Sardjono, Y.; Tri Mardji Atmono; Dwiretnani Sudjoko; Tjipto Sujitno, BA.

    2007-08-01

    The Scientific Meeting and Presentation on Basic Research in Nuclear Science and Technology is a routine activity held by Centre for Accelerator Technology and Material Process, National Nuclear Energy Agency, for monitoring the research activity which achieved in National Nuclear Energy Agency. The Meeting was held in Yogyakarta on July 10, 2007. The proceedings contains papers presented on the meeting about Nuclear Chemistry and Process Technology and there are 47 papers which have separated index. The proceedings is the second part of the three parts which published in series. (PPIN)

  18. The role of the decomissioning process on the development of the Brazilian nuclear program

    International Nuclear Information System (INIS)

    Mattos, Joao Roberto L. de; Dias, Marcio S.

    2009-01-01

    The National Energy Plan 2030, issued by the Energy Research Company of the Brazilian Ministry of Mines and Energy (EPE, 2007), formalized a reference scenario for the renaissance of the nuclear option in Brazil. This scenario includes the completion of Angra 3 Nuclear Power Plant up to 2014 and the construction of four additional nuclear power plants of 1000 MWe: a fourth unit by 2020, a fifth unit by 2025 and the sixth and seventh plants by 2030. Worldwide, the energy demand and the renaissance of nuclear energy as a primary source for electric power generation are leading the industry toward new constructions as well as uprates and operational life extensions. In this new scenario the decommissioning is pushed further into the future and Brazil is not an exception, considering that Angra 1 NPP is under a process of uprating and certainly will apply for and will receive license renewals allowing its operation for 20 or more years beyond its original project. Thus, why to focus on decommissioning in the present? What is the importance of decommissioning for the development of the Brazilian nuclear industry considering the existing reactors? Should the decommissioning be considered in the design of the new nuclear power plants? What would be the decommissioning plan for the Brazilian Nuclear Power Plants? The present paper is intended to contextualize the decommissioning in the present scenarios as well as to try to answer the above questions. (author)

  19. Proceeding of the Scientific Meeting and Presentation on Basic Research of Nuclear Science and Technology: Book II. Nuclear Chemistry, Process Technology, and Radioactive Waste Processing and Environment

    International Nuclear Information System (INIS)

    1996-06-01

    The proceeding contains papers presented on Scientific Meeting and Presentation on on Basic Research of Nuclear Science and Technology, held in Yogyakarta, 25-27 April 1995. This proceeding is second part of two books published for the meeting contains papers on nuclear chemistry, process technology, and radioactive waste management and environment. There are 62 papers indexed individually. (ID)

  20. FINESSE: study of the issues, experiments and facilities for fusion nuclear technology research and development. Interim report. Volume II

    Energy Technology Data Exchange (ETDEWEB)

    Abdou, M.

    1984-10-01

    The Nuclear Fusion Issues chapter contains a comprehensive list of engineering issues for fusion reactor nuclear components. The list explicitly defines the uncertainties associated with the engineering option of a fusion reactor and addresses the potential consequences resulting from each issue. The next chapter identifies the fusion nuclear technology testing needs up to the engineering demonstration stage. (MOW)

  1. FINESSE: study of the issues, experiments and facilities for fusion nuclear technology research and development. Interim report. Volume II

    International Nuclear Information System (INIS)

    Abdou, M.

    1984-10-01

    The Nuclear Fusion Issues chapter contains a comprehensive list of engineering issues for fusion reactor nuclear components. The list explicitly defines the uncertainties associated with the engineering option of a fusion reactor and addresses the potential consequences resulting from each issue. The next chapter identifies the fusion nuclear technology testing needs up to the engineering demonstration stage

  2. Nuclear materials safeguards. Volume II. 1975--March 1976 (a bibliography with abstracts). Report for 1975--Mar 1976

    International Nuclear Information System (INIS)

    Grooms, D.W.

    1976-03-01

    Citations cover the methods of safeguarding nuclear materials through effective management, accountability, nondestructive assays, instrumentation, and automated continuous inventory systems. Problem areas and recommendations for improving the management of nuclear materials are included. (Contains 88 abstracts) See also NTIS/PS-76/0200, Nuclear Materials Safeguards. Vol. 1. 1964-1974 (A title bibliography)

  3. Nuclear power plant simulators for operator licensing and training. Part I. The need for plant-reference simulators. Part II. The use of plant-reference simulators

    International Nuclear Information System (INIS)

    Rankin, W.L.; Bolton, P.A.; Shikiar, R.; Saari, L.M.

    1984-05-01

    Part I of this report presents technical justification for the use of plant-reference simulators in the licensing and training of nuclear power plant operators and examines alternatives to the use of plant-reference simulators. The technical rationale is based on research on the use of simulators in other industries, psychological learning and testing principles, expert opinion and user opinion. Part II discusses the central considerations in using plant-reference simulators for licensing examination of nuclear power plant operators and for incorporating simulators into nuclear power plant training programs. Recommendations are presented for the administration of simulator examinations in operator licensing that reflect the goal of maximizing both reliability and validity in the examination process. A series of organizational tasks that promote the acceptance, use, and effectiveness of simulator training as part of the onsite training program is delineated

  4. p53 nuclear accumulation and multiploidy are adverse prognostic factors in surgically resected stage II colorectal cancers independent of fluorouracil-based adjuvant therapy.

    Science.gov (United States)

    Buglioni, S; D'Agnano, I; Vasselli, S; Perrone Donnorso, R; D'Angelo, C; Brenna, A; Benevolo, M; Cosimelli, M; Zupi, G; Mottolese, M

    2001-09-01

    To identify the prognostically highest risk patients, DNA content and p53 nuclear or cytoplasmic accumulation, evaluated by monoclonal antibody DO7 and polyclonal antibody CM1, were determined in 94 surgically resected stage II (Dukes B2) colorectal cancers, treated or not with adjuvant 5-fluorouracil-based chemotherapy. Sixty-one (65%) of the tumors were aneuploid, 16 (17%) of which had a multiploid DNA content; 50 (53%) displayed DO7 nuclear p53 accumulation, and 44 (47%) showed cytoplasmic CM1 positivity. In multivariate analysis, only multiploidy and p53 nuclear positivity emerged as independent prognostic indicators of a poorer outcome. Positivity for p53 was associated with shorter survival in 5-fluorouracil-treated and untreated patients. Therefore, in patients with Dukes B2 colorectal cancer, a biologic profile based on the combined evaluation of DNA multiploidy and p53 status can provide valuable prognostic information, identifying patients to be enrolled in alternative, more aggressive therapeutic trials.

  5. Mortality pattern of the surrounding population of the Central Nuclear Almirante Alvaro Alberto / 1986 to 2007

    International Nuclear Information System (INIS)

    Leite, Teresa Cristina Sampaio de Barros; Silva, Ilson Peixoto Medeiros da; Jannuzzi, Denise Maria Souza; Higino, Thiago Nunes; Santos, Tatiana Rodrigues dos

    2011-05-01

    This paper aims to update two earlier epidemiological studies on the mortality profile of the resident population in the influence area of the Central Nuclear Almirante Alvaro Alberto. The main objective is analyze and compare the profile of mortality among the population classified in areas with the distance from source of exposure in three strata. Municipalities contained within a radius of 30 km of the nuclear power, neighboring municipalities, contained within a radius of 30 to 50 km, municipalities contained within 50 to 100 km, beyond Cabo Frio, which presents similar characteristics to the municipality of Angra dos Reis

  6. Behavior of Cs and Co in marine sediments of Enseada de Piraquara de Fora, Angra dos Reis, RJ, Brazil; Comportamento Cs e Co em sedimentos marinhos da Enseada de Piraquara de Fora - Angra dos Reis

    Energy Technology Data Exchange (ETDEWEB)

    Ferreira, I. M.; Carvalho, F. M.; Lauria, D.C., E-mail: dejanira@ird.gov.br [Instituto de Radioproteção e Dosimetria (IRD/CNEN-RJ), Rio de Janeiro - RJ (Brazil)

    2017-07-01

    The release of {sup 137}Cs and {sup 60}Co in the liquid effluents from the Angra dos Reis power plants could radiologically impact the Saco de Piraquara de Fora (SPF) inlet. The mobility and trend of the radionuclides in the water-sediment compartment were investigated by studies of thermodynamic and sorption-desorption. The values of distribution coefficients (Kd) were around 500 L. kg{sup -1} for {sup 60}Co and 400 L. kg{sup -1} for {sup 137}Cs that are lower than the literature values. The predominance of kaolinite in the clay fraction may have played a major role in the low observed Kd values. For both radionuclides, the sorption was higher for the sediment with higher cation exchange capacity, and the equilibrium conditions were reached only after the third day. Despite the relatively low Kd values and low sorption rates, both can considerably be accumulated in sediments, and the sorption reactions are partially irreversible. {sup 60}Co and {sup 137}Cs accumulate in orders of magnitude of 1010 and 109 Bq g{sup -1} sediment, respectively, which shows the ability of the sediments to remove and retain much of the {sup 137}Cs and {sup 60}Co released by the power plants. Considering the range of temperature of the SPF water, both sorption and desorption of the two metals increase with temperature. However, in general, the retention rates of the radionuclides in sediments remain constant. The sorption sites are heterogeneous since the sorption data can be adjusted by the Langmuir and Freündlich isotherms. The sorption of Co and Cs are endothermic processes, which are spontaneous at low temperature. (author)

  7. Acoustoelastic evaluation of welding and heat treatment stress relieving of pressure vessel steel for Angra 3

    Energy Technology Data Exchange (ETDEWEB)

    Moraes, Bruno C. de, E-mail: bruno.cesar@nuclep.gov.br [Nuclebras Equipamentos Pesados S.A (NUCLEP), Itaguai, RJ (Brazil); Bittencourt, Marcelo de S.Q., E-mail: bruno.cesar@nuclep.gov.br, E-mail: bittenc@ien.gov.br [Instituto de Engenharia Nuclear (IEN/CNEN-RJ), Rio de Janeiro, RJ (Brazil)

    2015-07-01

    Currently the knowledge of non-destructive techniques allows to evaluate the stresses on components and mechanical structures, aiming at physical security, preservation of the environment and avoid financial losses associated with the construction and operation of industrial plants. The search for new techniques, especially applied in the nuclear industry to assess status more accurately, voltage safety and to ensure structural integrity, for example, core components of the primary circuit, such as the reactor pressure vessel and steam generator has become of great importance within the community of non-destructive testing .This paper aims to contribute to the non-destructive technique development in order to ensure the structural integrity of nuclear components. One acoustoelastic evaluation of steel 20 MnMoNi 55, used in pressure vessels of nuclear power plants were performed. The acoustic birefringence technique was use to evaluate the acoustoelastic behavior of the test material in the as received condition, after welding and after the stress relief heat treatment. The constant acoustoelastic material was obtained by an uniaxial loading test. It was found a slight anisotropy in the material as received. After welding, a marked variation of acoustic birefringence in the region near the weld bead was observed. The heat treatment indicated a new change of acoustic birefringence. Obtaining the acoustoelastic constant allowed the evaluation of stress in the different conditions of the weld and treated material. (author)

  8. In vivo inhibition of nuclear factor of activated T-cells leads to atherosclerotic plaque regression in IGF-II/LDLR-/-ApoB100/100 mice.

    Science.gov (United States)

    Blanco, Fabiana; Heinonen, Suvi E; Gurzeler, Erika; Berglund, Lisa M; Dutius Andersson, Anna-Maria; Kotova, Olga; Jönsson-Rylander, Ann-Cathrine; Ylä-Herttuala, Seppo; Gomez, Maria F

    2018-03-01

    Despite vast clinical experience linking diabetes and atherosclerosis, the molecular mechanisms leading to accelerated vascular damage are still unclear. Here, we investigated the effects of nuclear factor of activated T-cells inhibition on plaque burden in a novel mouse model of type 2 diabetes that better replicates human disease. IGF-II/LDLR -/- ApoB 100/100 mice were generated by crossbreeding low-density lipoprotein receptor-deficient mice that synthesize only apolipoprotein B100 (LDLR -/- ApoB 100/100 ) with transgenic mice overexpressing insulin-like growth factor-II in pancreatic β cells. Mice have mild hyperglycaemia and hyperinsulinaemia and develop complex atherosclerotic lesions. In vivo treatment with the nuclear factor of activated T-cells blocker A-285222 for 4 weeks reduced atherosclerotic plaque area and degree of stenosis in the brachiocephalic artery of IGF-II/LDLR -/- ApoB 100/100 mice, as assessed non-invasively using ultrasound biomicroscopy prior and after treatment, and histologically after termination. Treatment had no impact on plaque composition (i.e. muscle, collagen, macrophages). The reduced plaque area could not be explained by effects of A-285222 on plasma glucose, insulin or lipids. Inhibition of nuclear factor of activated T-cells was associated with increased expression of atheroprotective NOX4 and of the anti-oxidant enzyme catalase in aortic vascular smooth muscle cells. Targeting the nuclear factor of activated T-cells signalling pathway may be an attractive approach for the treatment of diabetic macrovascular complications.

  9. Anthropogenic impact on the sedimentation in coastal regions: an example in Saco do Bracui - Ribeira Bay, Angra dos Reis, Brazil

    International Nuclear Information System (INIS)

    Barbosa, Alayde Alfaia

    2001-01-01

    The Saco do Bracui, located in the littoral zone of the Brazilian southeast, receives run off from the region of Angra dos Reis. Anthropological intervention in this area has modified local morphology during the last 40 years. These modifications include an intense deforestation of mangrove regions, construction of the Bracui Boat Yard, the dredging of part of the draining basin and development of the coastal plain. Results from seismic surveys identify three different stratigraphic units separated by two reflectors as well as Holocenic paleodeltas and paleochannels of the Bracui and Gratau rivers. Results from this study and previous work indicate an age of 6800 years for the top of the superior unit. Areal photographs from the years 1964, 1965, 1978 and 1991 reveal the principal modifications occurring during the last 40 years in the area. Field observations from this study as well as bathymetric profiles based on the nautical maps of 1980 and 1944 reveal shoaling and erosion areas in the Saco do Bracui. Sedimentation rates, using lead-210 profiles, are between 0,17 - 1,90 cm/year and lead-210 inventory values are between 16-6-dpm/cm 2 /year. The results for sedimentation rate and inventory show a high accumulation around Bracui, Gratau and Frade mouth rivers and agree with results from the bathymetric profiles with respect to the site of erosion and shoaling in the Saco do Bracui. The results for grain size and lead-210 analyses support the idea that the Saco do Bracui is suffering shoaling processes in specific sites and erosion in others. Comparison between long term sedimentation rates obtained by seismic results and short term rates obtained by lead-210 shows an increase of the sedimentary discharge in the 1960's, when the intense anthropological intervention in the area began. (author)

  10. Vulnerability Assessment of the nuclear power plant Vandellos II before a tornado; Evaluacion de vulnerabilidad de C.N. Vandellos II ante tornado

    Energy Technology Data Exchange (ETDEWEB)

    Fernandez, A.; Encabo, J.; Vaz-Romero, A.; Moran, M. A.; Roch, M.; Nicolas, P.; Barrera, N.

    2010-07-01

    The purpose of this work was the study of vulnerability to tornado event Vandellos II NPP. To do this, we have evaluated all structures (buildings), security systems and components to the installation of wind stresses, depression and impact of projectiles, generated by a tornado on the site.

  11. Report of the generation of the nuclear bank 'L1PG9121' of the SVEA-96 'collapsed' assemble for the FCS-II program with the FMS codes

    International Nuclear Information System (INIS)

    Alonso V, G.

    1992-01-01

    In this work it is described in a general way the form in that was generated the collapsed bank of the SVEA-96 fuel for Laguna Verde. The formation of the bank it was carried out with the ECLIPSE 86-2D, RECORD 89-1A and POLGEN 88-1B codes of the FMS package installed in the VAX system of the office of the National Commission of Nuclear Safety and Safeguards in Mexico D.F. The formed bank is denominated 'LlPG9121'. All this one carries out following the procedure '6F3/I/CN029/90/P1'. To generate the bank, both RECORD 'cells' that compose the assemble its were 'collapsed' in an alone one, representing this, the complete assemble in what refers to the distribution of fuel bar and enrichment. The collapsed of the assemble was made averaging the content of UO 2 and Gd 2 O 3 in each fuel bar of the one assemble. By this way the x-y array of fuel bars is conserved but a representative fuel cell of all the one assemble is obtained, being this the studied RECORD cell. In accordance with the requirements of nuclear information of FCS-II, the nuclear information generated with RECORD only was of the defined type as series 1 in the generation procedure of nuclear banks '6F3/I/CN029/90/P1'. This only means that only was generated nuclear information as function of the fuel burnt and of the vacuum in the fuel cell. Although the nuclear bank (L1PG9121) it was generated in these circumstances, it was also generates information of the defined type as series 2 with the present control bar for possible reactor analysis under these conditions. (Author)

  12. Mortality pattern of the surrounding population of the Central Nuclear Almirante Alvaro Alberto / 1986 to 2007; Padrao da mortalidade da populacao circunvizinha a Central Nuclear Almirante Alvaro Alberto / 1986 a 2007

    Energy Technology Data Exchange (ETDEWEB)

    Leite, Teresa Cristina Sampaio de Barros; Silva, Ilson Peixoto Medeiros da; Jannuzzi, Denise Maria Souza; Higino, Thiago Nunes; Santos, Tatiana Rodrigues dos [Fundacao Eletronuclear de Assistencia Medica (CIRA/FEAM), Angra dos Reis, RJ (Brazil). Centro de Informacoes sobre Radioepidemiologia; Xavier, Diego Ricardo [Fundacao Inst. Oswaldo Cruz (FIOCRUZ), Rio de Janeiro, RJ (Brazil). lnst. de Comunicacao e Informacao Cientifica e Tecnologica; Silva, Roseli Monteiro da [Fundacao Inst. Oswaldo Cruz (FIOCRUZ), Rio de Janeiro, RJ (Brazil)

    2011-05-15

    This paper aims to update two earlier epidemiological studies on the mortality profile of the resident population in the influence area of the Central Nuclear Almirante Alvaro Alberto. The main objective is analyze and compare the profile of mortality among the population classified in areas with the distance from source of exposure in three strata. Municipalities contained within a radius of 30 km of the nuclear power, neighboring municipalities, contained within a radius of 30 to 50 km, municipalities contained within 50 to 100 km, beyond Cabo Frio, which presents similar characteristics to the municipality of Angra dos Reis

  13. A Conserved Nuclear Cyclophilin Is Required for Both RNA Polymerase II Elongation and Co-transcriptional Splicing in Caenorhabditis elegans.

    Directory of Open Access Journals (Sweden)

    Jeong H Ahn

    2016-08-01

    Full Text Available The elongation phase of transcription by RNA Polymerase II (Pol II involves numerous events that are tightly coordinated, including RNA processing, histone modification, and chromatin remodeling. RNA splicing factors are associated with elongating Pol II, and the interdependent coupling of splicing and elongation has been documented in several systems. Here we identify a conserved, multi-domain cyclophilin family member, SIG-7, as an essential factor for both normal transcription elongation and co-transcriptional splicing. In embryos depleted for SIG-7, RNA levels for over a thousand zygotically expressed genes are substantially reduced, Pol II becomes significantly reduced at the 3' end of genes, marks of transcription elongation are reduced, and unspliced mRNAs accumulate. Our findings suggest that SIG-7 plays a central role in both Pol II elongation and co-transcriptional splicing and may provide an important link for their coordination and regulation.

  14. Estudio y diseño de la planta de ósmosis inversa de la Central Nuclear de Vandellós II

    OpenAIRE

    Maldonado Fernández, David

    2016-01-01

    En la actualidad, la Central Nuclear de Vandellós II dispone de una planta móvil de ósmosis inversa para la desmineralización del agua con una tecnología y membranas de los años 90. Esta planta, perteneciente a la empresa General Electric y con contrato vigente con la Asociación Nuclear de Vandellós, distribuye agua desmineralizada a través de la red para todos los procesos en la que es requerida. Así pues el presente proyecto tiene como objetivos el diseño de una instalación de desmineraliza...

  15. Nukes II: the nuclear power industry wants another chance. This time, it promises to do things right

    International Nuclear Information System (INIS)

    De Young, H.G.

    1985-01-01

    Anticipating a comback for nuclear power, the nuclear industry points to the need for reliable supplies of electricity to provide over 35% of US energy requirements. The industry faces both technical and institutional problems, in contrast to the mature industry of other countries, and promises to improve its performance in safety design and efficiency. Pointing to design advances, robotics, computerized simulation and other techniques, the industry feels that regulation will be more reasonable and costs will be reduced. Economic solutions include building smaller plants and using modular construction. The biggest uncertainty, however, is whether the public will buy either the need for additional capacity or nuclear power to fill that need

  16. Computational Analysis of Nuclear Safety Parameters of 3 MW TRIGA Mark-II Research Reactor Based on Evaluated Nuclear Data Libraries JENDL-3.3 and ENDF/B-VII.0

    International Nuclear Information System (INIS)

    Khan, Jahirul Haque

    2013-01-01

    The objective of this study is to explain the main nuclear safety parameters of 3 MW TRIGA Mark-II Research Reactor at AERE, Savar, Dhaka, Bangladesh from the viewpoint of reactor safety and also reactor operator. The most important nuclear reactor physics safety parameters are power distribution, power peaking factors, shutdown margin, control rod worth, excess reactivity and fuel temperature reactivity coefficient. These parameters are calculated using the chain of the computer codes the SRAC-PIJ for cell calculation based on neutron transport theory and the SRAC-CITATION for core calculation based on neutron diffusion equation. To achieve this objective the TRIGA model is developed by the 3-D diffusion code SRAC-CITATION based on the group constants that come from the collision probability transport code SRAC-PIJ. In this study the evaluated nuclear data libraries JENDL-3.3 and ENDF/B-VII.0 are used. The calculated most important reactor physics parameters are compared to the safety analysis report (SAR) values as well as earlier published MCNP results (numerically benchmark). It was found that the calculated results show a good agreement between the said libraries. Besides, in most cases the calculated results reveal a reasonable agreement with the SAR values (by General Atomic) as well as the MCNP results. In addition, this analysis can be used as the inputs for thermal-hydraulic calculations of the TRIGA fresh core in the steady state and pulse mode operation. Because of power peaking factors, power distributions and temperature reactivity coefficients are the most important reactor safety parameters for normal operation and transient safety analysis in research as well as in power reactors. They form the basis for technical specifications and limitations for reactor operation such as loading pattern limitations for pulse operation (in TRIGA). Therefore, this analysis will be very important to develop the nuclear safety parameters data of 3 MW TRIGA Mark-II

  17. Dynamic Isotope Power System (DIPS) Applications Study. Volume II. Nuclear Integrated Multimission Spacecraft (NIMS) design definition. Final report

    International Nuclear Information System (INIS)

    1979-11-01

    The design requirements for the Nuclear Integrated Multimission Spacecraft. (NIMS) are discussed in detail. The requirements are a function of mission specifications, payload, control system requirements, electric system specifications, and cost limitations

  18. Emergency planning of the city of Munich with reference to nuclear facilities, especially the nuclear power stations Isar I and II, resp. the reactor in Garching

    International Nuclear Information System (INIS)

    1990-01-01

    During the hearing of Munich's city council of 13.7.1990 thirteen experts were heard on the following subjects: Hazard potential of Isar reactors and FRM reactor and appropriate radioactive waste transports; responsibilities in emergency planning. Some of the experts cannot visualize a major accident and propose not to cater for it. Shelters and evacuation are not planned for Munich, both solutions not being realizable for all inhabitants. Nuclear phaseout is seen by some as a measure of prevention. (HSCH) [de

  19. New Nuclear Materials Including Non Metallic Fuel Elements. Vol. II. Proceedings of the Conference on New Nuclear Materials Technology, Including Non Metallic Fuel Elements

    International Nuclear Information System (INIS)

    1963-01-01

    One of the major aims of the International Atomic Energy Agency in furthering the peaceful uses of atomic energy is to encourage the development of economical nuclear power. Certainly, one of the more obvious methods of producing economical nuclear power is the development of economical fuels that can be used at high temperatures for long periods of time, and which have sufficient strength and integrity to operate under these conditions without permitting the release of fission products. In addition it is desirable that after irradiation these new fuels be economically reprocessed to reduce further the cost of the fuel cycle. As nuclear power becomes more and more competitive with conventional power the interest in new and more efficient higher-temperature fuels naturally increases rapidly. For these reasons, the Agency organized a Conference on New Nuclear Materials Technology, Including Non-Metallic Fuel Elements, which was held from 1 to 5 July 1963 at the International Hotel, Prague, with the assistance and co-operation of the Government of the Czechoslovak Socialist Republic. A total of 151 scientists attended, from 23 countries and 4 international organizations. The participants heard and discussed more than 60 scientific papers. The Agency wishes to thank the scientists who attended this Conference for their papers and for many spirited discussions that truly mark a successful meeting. The Agency wishes also to record its gratitude for the assistance and generous hospitality accorded the Conference, the participants and the Agency's staff by the Government of the Czechoslovak Socialist Republic and by the people of Prague. The scientific information contained in these Proceedings should help to quicken the pace of progress in the fabrication of new and m ore economical fuels, and it is hoped that these proceedings will be found useful to all workers in this and related fields

  20. Communication and surrounding of Asco and Vandellos II nuclear power plants; La comunicacion y el entorno de las centrales de Asco y Vandellos II

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2004-07-01

    The Asco and Vandellos-II power plants have always been integrated into the regions where they are located, and they take an active part in the development of surrounding towns through quality employment provided by our facilities, social and cultural support and aid to development promoted by regional councils. Communication to media is a corporate priority defined in our strategic plant, to ensure openness, rigour and punctuality. We also attend to the visitors who want to learn more about our facilities in the visitor center, and we have agreements with agrarian institutions in the area so that students can de practical training in the farms we own for agricultural production. (Author)

  1. Development and Validation of Methodology to Model Flow in Ventilation Systems Commonly Found in Nuclear Facilities - Phase II

    Energy Technology Data Exchange (ETDEWEB)

    Strons, Philip [Argonne National Lab. (ANL), Argonne, IL (United States); Bailey, James L. [Argonne National Lab. (ANL), Argonne, IL (United States); Davis, John [Argonne National Lab. (ANL), Argonne, IL (United States); Grudzinski, James [Argonne National Lab. (ANL), Argonne, IL (United States); Hlotke, John [Argonne National Lab. (ANL), Argonne, IL (United States)

    2016-03-01

    In this report we present the results of the Phase II analysis and testing of the flow patterns encountered in the Alpha Gamma Hot Cell Facility (AGHCF), as well as the results from an opportunity to expand upon field test work from Phase I by the use of a Class IIIb laser. The addition to the Phase I work is covered before proceeding to the results of the Phase II work, followed by a summary of findings.

  2. Applications of Nuclear Physics

    OpenAIRE

    Hayes, Anna C.

    2017-01-01

    Today the applications of nuclear physics span a very broad range of topics and fields. This review discusses a number of aspects of these applications, including selected topics and concepts in nuclear reactor physics, nuclear fusion, nuclear non-proliferation, nuclear-geophysics, and nuclear medicine. The review begins with a historic summary of the early years in applied nuclear physics, with an emphasis on the huge developments that took place around the time of World War II, and that und...

  3. Nuclear war and nuclear peace

    Energy Technology Data Exchange (ETDEWEB)

    Segal, G.; Moreton, E.; Freedman, L.; Baylis, J.

    1983-01-01

    This book is an in-depth examination of East-West tactical and strategic nuclear weapons policy. The contributors explore such issues as the history and implications of tactical weapons in Europe, the general conflicts that have characterized US and Soviet interaction, the development of British nuclear weapons policy, and arms control including SALT I and II and the START talks.

  4. Three-dimensional simulation of radioactive pollutant in the atmosphere from nuclear power plant

    Energy Technology Data Exchange (ETDEWEB)

    Buske, Daniela [Universidade Federal de Pelotas (UFPel), RS (Brazil). Inst. de Fisica e Matematica. Dept. de Matematica e Estatistica]. E-mail: danielabuske@gmail.com; Morreira, Davidson Martins [Universidade Federal do Pampa (Unipampa), Bage, RS (Brazil); E-mail: davidson@pq.cnpq.br; Vilhena, Marco Tullio de [Universidade Federal do Rio Grande do Sul (UFRGS), Porto Alegre, RS (Brazil). Programa de Pos-Graduacao em Engenharia Mecanica (PROMEC)]. E-mail: vilhena@pq.cnpq.br

    2008-07-01

    In this work we report numerical simulations using the GILTT (Generalized Integral Laplace Transform Technique) approach to simulate radioactive pollutant dispersion in the Planetary Boundary Layer (PBL). To study the dispersion and the possible scenarios arising from accidental emissions, the results obtained with the GILTT method are compared with experimental data obtained at the Nuclear Power Plant of Angra dos Reis under neutral/moderately unstable conditions. Furthermore, to a better description of the wind profile for the irregular ground level terrain, we consider the wind profile as solution of the MM5 mesoscale model. The statistical indices point out a reasonable good agreement is obtained between experimental data and GILTT model. (author)

  5. Occupational exposure analysis at the unit 1 of Almirante Alvaro Alberto nuclear power plant

    International Nuclear Information System (INIS)

    Moraes, A.

    1985-01-01

    In order to obtain a complete knowledge of occupational conditions in a PWR nuclear power station, the individual and collective dose distributions are being analysed during the Angra I (Rio de Janeiro - Brazil) station activities. Work conditions with identification of critical areas and groups as well as classification of tasks related to reactor maintenance and startup periods are also studied. This paper analyses radiological data measured at different power levels of the reactor and during maintenance and repair services as well as the refueling operation. (author)

  6. Calculation of static harmonics of a nuclear reactor using CITATION code

    International Nuclear Information System (INIS)

    Belchior Junior, A.; Moreira, J.M.L.

    1989-01-01

    The CITATION code, which solves the multigroup diffusion equation by the finite difference method, calculates the fundamental λ-mode (harmonic) for nuclear reactors. In this work, two fission source correction methods are attempted to obtain higher λ-modes through the CITATION code. The two methods are compared, their advantages and disadvantages analysed and verified against analytical solutions. Two dimensional harmonic modes are calculated for the IEA-R1 research reactor and for the ANGRA-I power reactor. The results are shown in graphics and tables. (author) [pt

  7. Safety philosophy and design principles for systems and components of nuclear power plant: external event

    International Nuclear Information System (INIS)

    Lopes, J.P.G.

    1986-01-01

    In nuclear power plants, some systems and components are designed to withstand external impacts. Such systems and components are those which have to perform their functions even during and after the occurrences of an earthquake, for example, fulfilling the safety objectives and avoiding the release of radioactive material to the environment. The aim of this report is to introduce the safety philosophy and design principles for systems/components to perform their functions during and after the occurrence of an earthquake, as applied by NUCLEN for Angra 2 and 3. (Author) [pt

  8. Scoping of material damage with FISPACT-II and different nuclear data libraries: transmutation, activation, and PKAs

    International Nuclear Information System (INIS)

    Gilbert, M.R.; Sublet, J.-Ch.

    2016-01-01

    The uncertainty associated with nuclear data, and the simulated predictions of transmutation, activation, and primary damage events derived from them, is not only that derived based on the quantified errors in a particular nuclear library. Uncertainty also manifests in comparisons between different libraries – if they do not produce the same results, then, since it often impossible to know a priori which library is best, predicted results must be considered to have an uncertainty (at least) as much as the variation between libraries. Of course, this situation is further complicated by the fact that it is not always possible, or practical, to produce results with multi-libraries. There is thus a need, within the nuclear data community, to assess different libraries, and make recommendations about the best choice of library for particular applications, in this case material science

  9. Fabrication and testing of a 4-node micro-pocket fission detector array for the Kansas State University TRIGA Mk. II research nuclear reactor

    Science.gov (United States)

    Reichenberger, Michael A.; Nichols, Daniel M.; Stevenson, Sarah R.; Swope, Tanner M.; Hilger, Caden W.; Unruh, Troy C.; McGregor, Douglas S.; Roberts, Jeremy A.

    2017-08-01

    Advancements in nuclear reactor core modeling and computational capability have encouraged further development of in-core neutron sensors. Micro-Pocket Fission Detectors (MPFDs) have been fabricated and tested previously, but successful testing of these prior detectors was limited to single-node operation with specialized designs. Described in this work is a modular, four-node MPFD array fabricated and tested at Kansas State University (KSU). The four sensor nodes were equally spaced to span the length of the fuel-region of the KSU TRIGA Mk. II research nuclear reactor core. The encapsulated array was filled with argon gas, serving as an ionization medium in the small cavities of the MPFDs. The unified design improved device ruggedness and simplified construction over previous designs. A 0.315-in. (8-mm) penetration in the upper grid plate of the KSU TRIGA Mk. II research nuclear reactor was used to deploy the array between fuel elements in the core. The MPFD array was coupled to an electronic support system which has been developed to support pulse-mode operation. Neutron-induced pulses were observed on all four sensor channels. Stable device operation was confirmed by testing under steady-state reactor conditions. Each of the four sensors in the array responded to changes in reactor power between 10 kWth and full power (750 kWth). Reactor power transients were observed in real-time including positive transients with periods of 5, 15, and 30 s. Finally, manual reactor power oscillations were observed in real-time.

  10. Nuclear model parameter testing for nuclear data evaluation (Reference Input Parameter Library: Phase II). Summary report of the third research co-ordination meeting

    International Nuclear Information System (INIS)

    Herman, M.

    2002-04-01

    This report summarises the results and recommendations of the third Research Co-ordination Meeting on improving and testing the Reference Input Parameter Library: Phase II. A primary aim of the meeting was to review the achievements of the CRP, to assess the testing of the library and to approve the final contents. Actions were approved that will result in completion of the file and a draft report by the end of February 2002. Full release of the library is scheduled for July 2002. (author)

  11. Neutron beam experiments using nuclear research reactors: honoring the retirement of professor Bernard W. Wehring -II. 6. Nuclear Analytical Applications in a Semiconductor Materials Characterization Laboratory

    International Nuclear Information System (INIS)

    Hossain, Tim Z.

    2001-01-01

    A typical semiconductor materials characterization laboratory is heavily loaded with surface analytical tools such as SEM, TEM, TXRF, secondary ion mass spectrometry (SIMS), AFM, and XPS. However, there are analytical needs that cannot be addressed by the aforementioned methods and often require a bulk analysis technique such as ICP/MS. Nuclear analytical methods can play a very important complementary role and provide advantages over nonnuclear techniques because of higher sensitivity, simplicity of sample preparation, and highly quantitative answers. An overwhelming majority of the semiconductor industry uses silicon as the base material for the integrated circuit (IC) manufacturing, and silicon, incidentally, has very favorable nuclear parameters. Silicon, for example, does not have a high neutron capture cross section; thus, matrix activity induced during a neutron irradiation is not very high, and more importantly, the half-life of the major radioisotope 31 Si is only 2.6 h. This short half-life provides a good opportunity to study induced radioactivities of other impurities such as iron, zinc, and nickel. So, neutron activation analysis (NAA) can achieve a very high sensitivity with most transition metals and other important impurities such as copper, gold, and tungsten. NAA is very complementary to other methods of analysis in providing trace-level metals analysis of both silicon wafer and non-wafer samples such as quartz parts used in the diffusion furnaces. Data from NAA of quartz materials used in the diffusion furnaces will be described. In addition, the NAA techniques such as prompt gamma activation analysis are especially useful for the analysis of bulk hydrogen. Another nuclear method, nuclear reaction analysis (NRA), has also been widely used for this purpose. With NRA, a depth profile similar to the ones obtained by SIMS can be achieved. An important nuclear analysis in the semiconductor industry is the depth profiling of boron by neutron depth

  12. Cd(II) complexes with different nuclearity and dimensionality based on 3-hydrazino-4-amino-1,2,4-triazole

    Energy Technology Data Exchange (ETDEWEB)

    Xu, Cai-Xia; Zhang, Jian-Guo, E-mail: zjgbit@bit.edu.cn; Yin, Xin; Jin, Xin; Li, Tong; Zhang, Tong-Lai; Zhou, Zun-Ning

    2015-03-15

    A series of zero- to two-dimensional Cd(II) coordination compounds have been synthesized by the reaction of Cd(II) salts and 3-hydrazino-4-amino-1,2,4-triazole di-hydrochloride (HATr·2HCl). [CdCl{sub 2}(HATr){sub 2}] (1) and [Cd{sub 2}Cl{sub 4}(HATr){sub 2}(H{sub 2}O){sub 2}] (2) have discrete mononuclear and binuclear structures, respectively. [Cd(HATr){sub 2}(ClO{sub 4}){sub 2}]{sub n} (3) presents polymeric 1-D chain and [Cd{sub 2}(NO{sub 3}){sub 2}Cl{sub 2}(HATr){sub 2}]{sub n} (4) shows 2-D frameworks. All Cd(II) ions exhibit distorted octahedral configurations in 1–3, whilst both hexa and heptacoordinated Cd(II) are formed in 4. The HATr ligands adopt chelating coordinated mode in 1, while tri-dentate bridging–chelating mode in 2–4. The chloride ion is a mono-coordinated ligand in 1 and 2, but it bridges two adjacent metal ions in 4. Furthermore, thermal behaviors have been investigated and the results reveal that all complexes have good thermal stability. The impact sensitivity test indicates that complex 3 is sensitive to impact stimuli. - Graphical abstract: Four Cd(II) complexes based on 3-hydrazino-4-amino-1,2,4-triazole ligands exhibit diverse structures from mononuclear to 2D networks. - Highlights: • Cd(II) complexes containing 3-hydrazino-4-amino-1,2,4-triazole ligands. • Mononuclear, binuclear, 1-D and 2-D structures. • Good thermal stability. • Thermal decomposition kinetics.

  13. Cd(II) complexes with different nuclearity and dimensionality based on 3-hydrazino-4-amino-1,2,4-triazole

    International Nuclear Information System (INIS)

    Xu, Cai-Xia; Zhang, Jian-Guo; Yin, Xin; Jin, Xin; Li, Tong; Zhang, Tong-Lai; Zhou, Zun-Ning

    2015-01-01

    A series of zero- to two-dimensional Cd(II) coordination compounds have been synthesized by the reaction of Cd(II) salts and 3-hydrazino-4-amino-1,2,4-triazole di-hydrochloride (HATr·2HCl). [CdCl 2 (HATr) 2 ] (1) and [Cd 2 Cl 4 (HATr) 2 (H 2 O) 2 ] (2) have discrete mononuclear and binuclear structures, respectively. [Cd(HATr) 2 (ClO 4 ) 2 ] n (3) presents polymeric 1-D chain and [Cd 2 (NO 3 ) 2 Cl 2 (HATr) 2 ] n (4) shows 2-D frameworks. All Cd(II) ions exhibit distorted octahedral configurations in 1–3, whilst both hexa and heptacoordinated Cd(II) are formed in 4. The HATr ligands adopt chelating coordinated mode in 1, while tri-dentate bridging–chelating mode in 2–4. The chloride ion is a mono-coordinated ligand in 1 and 2, but it bridges two adjacent metal ions in 4. Furthermore, thermal behaviors have been investigated and the results reveal that all complexes have good thermal stability. The impact sensitivity test indicates that complex 3 is sensitive to impact stimuli. - Graphical abstract: Four Cd(II) complexes based on 3-hydrazino-4-amino-1,2,4-triazole ligands exhibit diverse structures from mononuclear to 2D networks. - Highlights: • Cd(II) complexes containing 3-hydrazino-4-amino-1,2,4-triazole ligands. • Mononuclear, binuclear, 1-D and 2-D structures. • Good thermal stability. • Thermal decomposition kinetics

  14. AtnMat2, a nuclear-encoded maturase required for splicing of group-II introns in Arabidopsis mitochondria

    OpenAIRE

    Keren, Ido; Bezawork-Geleta, Ayenachew; Kolton, Max; Maayan, Inbar; Belausov, Eduard; Levy, Maggie; Mett, Anahit; Gidoni, David; Shaya, Felix; Ostersetzer-Biran, Oren

    2009-01-01

    Mitochondria (mt) in plants house about 20 group-II introns, which lie within protein-coding genes required in both organellar genome expression and respiration activities. While in nonplant systems the splicing of group-II introns is mediated by proteins encoded within the introns themselves (known as “maturases”), only a single maturase ORF (matR) has retained in the mitochondrial genomes in plants; however, its putative role(s) in the splicing of organellar introns is yet to be established...

  15. Seismic detection. Part II. Nuclear events. Volume III. 1975 (a bibliography with abstracts). Report for 1975--Feb 1976

    International Nuclear Information System (INIS)

    Habercom, G.E. Jr.

    1976-03-01

    Methods of seismic detection of nuclear events are investigated in the Government sponsored research reports. (This updated bibliography contains 145 abstracts, all of which are new entries to the previous edition.) For general seismic detection, see Part 1, NTIS/PS-76/0206

  16. Concentration of heavy metals in benthic algae from Ribera Bay, Angra dos Reis, R.J. State, Brazil, suggesting monitor species

    International Nuclear Information System (INIS)

    Guimaraes, J.R.D.; Lacerda, L.D. de; Teixeira, V.L.; Faculdade de Biologia e Psicologia Maria Thereza, Niteroi

    1982-01-01

    Concentrations of Cu, Cr, Cd, Zn, Mn, Co, Pb and Ni were determined in benthic algae of Bay of Ribeira, Angra dos Reis, SE Brazilian coast. The results showed that these elements are concentrate under different degrees depending on the algae species considered: Galaxaura marginata and Caulerpa racemosa presented the highest concentrations (ppm) for Cu (5,2), Cd (1,5), Mn (91,5), Co (6,2) and Ni (8,0) and Cr (7,9) and Pb (21,9) respectively. These algae are then suggested as potential monitor species for these metals in tropical coastal waters. The estimated bioaccumulation factors varied from 10 2 for Ni to 10 5 for Pb, falling within the range reported in the literature, with the exception of Cd, which was found to be two orders of magnitude greater. (Author) [pt

  17. The funding of dangerous nuclear projects. Nuclear trade and safety: the role of French private banks. What are we talking about?

    International Nuclear Information System (INIS)

    Philippe, Isabelle

    2011-01-01

    Countries which export nuclear technologies, notably France, have developed mechanisms of financial support to incite private banks to finance the sale of reactors to foreign countries, notably EPRs in the case of France. After having briefly introduced this issue, and dealing with the French case, this publication indicates the concerned banks, and outlines that some of them finance nuclear projects which have been assessed by NGOs as dangerous in terms of nuclear safety. It notably presents the Angra 3 project in Brazil: its cost, its planning, its main safety problems (obsolete technology, building authorization awarded without any actual safety analysis, situation of conflict of interest for the Brazilian regulator). It also presents the Jaitapur project in India in which Areva is as well involved: costs, funding, planning, main risks (seismic risk area, safety level much lower than the one required in France, controversy on the impact study). The document finally explains why banks must not fund nuclear projects

  18. Biologically relevant mono- and di-nuclear manganese II/III/IV complexes of mononegative pentadentate ligands

    DEFF Research Database (Denmark)

    Baffert, Carole; Collomb, Marie-Nöelle; Deronzier, Alain

    2003-01-01

    ,2-diamine) have been prepared. The crystal structure of the Mn(II)-aqua complex of 1, shows it to be dimeric via (mu-kappaO)-bridging through one carboxylate oxygen atom of each of the two ligands. The non-coordinated carboxylate oxygen atoms are H-bonded to the water ligands on the adjacent Mn ion......Manganese(II) complexes of mononegative pentadentate N4O ligands [Mn2(mgbpen)(2)(H2O)(2)](ClO4)(2) (1), (mgbpen(-) = N-methyl-N'-glycyl-N,N'-bis(2-pyridylmethyl)ethane-1,2-diamine) and [Mn-2(bzgbpen)(2)(H2O)(2)](ClO4)(2) ( 2), (bzgbpen(-)=N-benzyl-N'-glycyl-N,N'-bis(2-pyridylmethyl)ethane-1......-bridged dimanganese(III) and di-mu-oxo-dimanganese(II) complexes, depending on solvent. The [Mn(III)-OR](+), R = H or CH3 complexes are generated in water or methanol, respectively, and are potentially useful spectroscopic models for active Mn-lipoxygenases. In acetonitrile, di-mu-oxo-dimanganese(II) complexes...

  19. Biologically relevant mono- and di-nuclear manganese II/III/IV complexes of mononegative pentadentate ligands

    DEFF Research Database (Denmark)

    Baffert, Carole; Collomb, Marie-Nöelle; Deronzier, Alain

    2003-01-01

    were characterised by UV-visible spectroscopy, ESI mass spectrometry and cyclic voltammetry. In addition, III-IV and II-III species were electrochemically generated. Thus the new mononegative pentadentate ligand systems display significant flexibility in the range of Mn oxidation states and species...

  20. Chemical Effects of Nuclear Transformations. Vol. II. Proceedings of the Symposium on Chemical Effects Associated with Nuclear Reactions and Radioactive Transformations

    International Nuclear Information System (INIS)

    1965-01-01

    The study of the chemical changes consequent upon the nuclear transformation of an atom that is linked with other atoms in a molecule and surrounded by other similar or dissimilar molecules has intrigued chemists for a number of years. This interest is certainly not static but if anything is increasing. The main theme of this meeting was a discussion of the suggestions and theories that have been advanced to explain the wealth of experimental observations on the behaviour of atoms at energies and in situations not normally accessible in the laboratory. Though the subject has some practical implications in the preparation of radioisotopes, this was not an important consideration at this Symposium. The first Symposium on hot-atom chemistry organized by the Agency was held in Prague in October 1960. Comparison of the past and the present state of the subject shows that a greater variety and sophistication of techniques are now being applied as the simpler approaches used in the past have been shown to be inadequate. Progress has been made in the understanding of the simpler gas system, but in liquids and solids there is still much to clarify. It is also of interest that for the majority of the work reported in these Proceedings a reactor was the radiation source, and in this field much experimental work still remains to be done. The Symposium on Chemical Effects Associated with Nuclear Reactions and Radioactive Transformations was held from 7 to 11 December 1964 in Vienna, and was attended by 136 participants from 29 countries and 4 international organizations. It was organized by the International Atomic Energy Agency in co-operation with the Joint Commission on Applied Radioactivity. The publication of these Proceedings makes the content of the papers and discussion available to a wider audience than was possible at the meeting in Vienna

  1. Considerations about the licensing process of special nuclear industrial facilities

    Energy Technology Data Exchange (ETDEWEB)

    Talarico, M.A., E-mail: talaricomarco@hotmail.com [Marinha do Brasil, Rio de Janeiro, RJ (Brazil). Coordenacao do Porgrama de Submarino com Propulsao Nuclear; Melo, P.F. Frutuoso e [Coordenacao dos Programas de Pos-Graduacao em Engenharia (COPPE/UFRJ), Rio de Janeiro, RJ (Brazil). Programa de Engenharia Nuclear

    2015-07-01

    This paper brings a discussion about the challenges involved in the development of a new kind of nuclear facility in Brazil, a naval base for nuclear submarines, with attention to the licensing process and considerations about the risk-informed decision making application to the licensing process. Initially, a model of such a naval base, called in this work, special industrial facility, is proposed, with its systems and respective sets of basic requirements, in order to make it possible the accomplishment of the special industrial facility support function to the nuclear submarine. A discussion about current challenges to overcome in this project is presented: the challenges due to the new characteristics of this type of nuclear facility; existence of several interfaces between the special industrial facilities systems and nuclear submarine systems in design activities; lack of specific regulation in Brazil to allow the licensing process of special industrial facilities by the nuclear safety authority; and comments about the lack of information from reference nuclear facilities, as is the case with nuclear power reactors (for example, the German Grafenrheinfeld nuclear plant is the reference plant for the Brazilian Angra 2 nuclear plant). Finally, in view of these challenges, an analysis method of special industrial facility operational scenarios to assist the licensing process is proposed. Also, considerations about the application of risk-informed decision making to the special industrial facility activity and licensing process in Brazil are presented. (author)

  2. Considerations about the licensing process of special nuclear industrial facilities

    International Nuclear Information System (INIS)

    Talarico, M.A.; Melo, P.F. Frutuoso e

    2015-01-01

    This paper brings a discussion about the challenges involved in the development of a new kind of nuclear facility in Brazil, a naval base for nuclear submarines, with attention to the licensing process and considerations about the risk-informed decision making application to the licensing process. Initially, a model of such a naval base, called in this work, special industrial facility, is proposed, with its systems and respective sets of basic requirements, in order to make it possible the accomplishment of the special industrial facility support function to the nuclear submarine. A discussion about current challenges to overcome in this project is presented: the challenges due to the new characteristics of this type of nuclear facility; existence of several interfaces between the special industrial facilities systems and nuclear submarine systems in design activities; lack of specific regulation in Brazil to allow the licensing process of special industrial facilities by the nuclear safety authority; and comments about the lack of information from reference nuclear facilities, as is the case with nuclear power reactors (for example, the German Grafenrheinfeld nuclear plant is the reference plant for the Brazilian Angra 2 nuclear plant). Finally, in view of these challenges, an analysis method of special industrial facility operational scenarios to assist the licensing process is proposed. Also, considerations about the application of risk-informed decision making to the special industrial facility activity and licensing process in Brazil are presented. (author)

  3. Preface [13. international workshop on hadron physics, Angra dos Reis, RJ (Brazil), 22-27 March 2015

    International Nuclear Information System (INIS)

    2016-01-01

    The Hadron Physics series of workshops, which started in 1988, take place every two or three years. They have the format of an advanced school, consisting of didactic courses, thematic seminars and the presentation of posters on frontier topics in the physics of strong interactions. It is characterized by the active participation of graduate students and postdocs, and also promotes collaboration between reserach groups in Latin America and others distributed worldwide. The XIII International Workshop on Hadron Physics - XIII Hadron Physics - was held from 22-27 March 2015, in Hotel do Bosque, Mambucaba, near the city of Angra dos Reis, Rio de Janeiro state. With good weather, a beach and splendid natural beauty, the surroundings offered all the conditions for a fruitful and pleasant meeting. The scientific program of the XIII Hadron Physics workshop was composed of courses, seminars and contributed papers. The courses consisted of four sets of lectures of three hours each, which are all reproduced in the present volume, thanks to the kind efforts of the lecturers, for the use and appreciation of a wider public. These courses provided a pedagogical and updated account of recent developments that gave support to the discussion of frontier problems in the physics of strong interactions. Organizers and participants are aware that the lecturers bore primary responsibility for the success of the workshop and are especially grateful to them. The seminars reviewed recent developments in theory, computational techniques and experimentations investigating QCD in nonperturbative and high density regimes. Most of these seminars are reproduced in this volume. The Organizing Committee is thankful to the invited speakers for the quality of the presentations, which contributed to the success of the workshop. The contributed papers, mainly representing the scientific activity of young physicists, were exhibited as posters all throughout the event in the breakout area, and are also

  4. Development of Intelligent Database Program for PSI/ISI Data Management of Nuclear Power Plant (Part II)

    International Nuclear Information System (INIS)

    Park, Un Su; Park, Ik Keun; Um, Byong Guk; Lee, Jong Po; Han, Chi Hyun

    2000-01-01

    In a previous paper, we have discussed the intelligent Windows 95-based data management program(IDPIN) which was developed for effective and efficient management of large amounts of pre-/in-service inspection(PSI/ISI) data of Kori nuclear power plants. The IDPIN program enables the prompt extraction of previously conducted PSI/ISI conditions and results so that the time-consuming data management, painstaking data processing and analysis of the past are avoided. In this study, the intelligent Windows based data management program(WS-IDPIN) has been developed as an effective data management of PSI/ISI data for the Wolsong nuclear power plants. The WS-IDPIN program includes the modules of comprehensive management and analysis of PSI/ISI results, statistical reliability assessment program of PSI/ISI results(depth and length sizing performance etc), standardization of UT report form and computerization of UT results. In addition, the program can be further developed as a unique PSI/ISI data management expert system which can be part of the PSI/ISI total support system for Korean nuclear power plants

  5. Evolution of seismic monitoring systems of nuclear power plants. Improvements and practical applications; Evolucion de los sistemas de vigilancia sismica de las II.NN. Mejoras introducidas y aplicaciones practicas

    Energy Technology Data Exchange (ETDEWEB)

    Sanchez Cabanero, J. G.; Jimenez Juan, A.

    2010-07-01

    The II. NN. Spanish have a seismic monitoring system (SVS) covering two objectives relevant to nuclear security: determining earthquake leave operation, and specific data that serve to limit or reduce the uncertainties associated with the seismic source, the site and design. Since its construction, the major SVS II. NN. have been equipped with the best time of seismic instrumentation to record earthquakes strong, but with limited resolution for recording in the free field and appropriately moderate earthquakes.

  6. Thermodynamics. Vol. II. Proceedings of the Symposium on Thermodynamics with Emphasis on Nuclear Materials and Atomic Transport in Solids

    International Nuclear Information System (INIS)

    1966-01-01

    Knowledge of the thermodynamics of nuclear materials is vital to the design of reactor fuels and moderating and cooling systems, in fact all facets of nuclear plant operation that involve mixtures of, or contact between, two or more elements in single- or multi-phase systems. The steep thermal gradients and the high temperatures involved in nuclear technology pose special problems for engineers and thermodynamicists, who have found that extrapolation of low-temperature data to high temperatures very often proves invalid. For this reason, standard thermodynamic techniques such as calorimetry and EMF-methods have been extended into high-temperature regions. Since the Agency's last conference on this subject, also held in Vienna (Thermodynamics of Nuclear Materials, 1962), there have been notable advances in calorimetry performed at temperatures greater than 1000°C, and in the use of EMF cells with solid electrolytes operated at similar temperatures. Significant advances have also been made in measuring diffusion parameters at the higher temperatures. An important field covered in this Symposium was the correlation of such atomic transport data with thermodynamic data, a prerequisite if the nuclear engineer is to incorporate diffusion results into his normal process- assessment techniques. Finally the Symposium suggested the requirements for good critical tables. The mere compiling of such data is no longer sufficient; the compiler must have free access to all the data of a particular experiment, he must have an intimate knowledge of experimental work in this field and he must weight every figure quoted in the light of his experience. As a step in this direction, the Agency has called on the services of many well-known experts and is preparing a number of monographs giving critical assessments of thermodynamic data and phase-diagrams for many of the elements of interest in reactor design. Most of the countries engaged in research in thermodynamics were represented at

  7. New signal acquisition and processing system for the execution of initial criticality after refueling and physical tests at low power in Angra-2, with the incorporation of the real time resolution of the inverse point kinetic equation - IPK

    Energy Technology Data Exchange (ETDEWEB)

    Júnior, Décio Brandes M.F.; Oliveira, Mônica Georgia N.; Silva, Cristiano da, E-mail: deciobr@eletronuclear.gov.br, E-mail: mongeor@eletronuclear.gov.br, E-mail: cdsilva@eletronuclear.gov.br [Eletrobrás Termonuclear S.A. (ELETRONUCLEAR), Angra dos Reis, RJ (Brazil). Departamento DDD.O - Física de Reatores

    2017-07-01

    The goal of this work is present the new System of Acquisition and Signal Processing for the execution of the initial criticality after refueling and physical tests at low power with the incorporation of the real time resolution of Inverse Point Kinetic Equations (IPK). The system was developed using cRIO 9082 hardware (compactRIO), which is a programmable logic controller (PLC) and, the National Lab's LabVIEW programming language. The developed system enabled a better visualization and monitoring interface of the neutron flux evolution during the first criticality of cycle and following the low power physical tests, which allows the Reactor Physics Group and Reactor Operators of Angra 2 guide faster and accurately the reactivity variations at physical tests. The digital reactivity meter developed reinforces in Angra-2 the set of operational practices of reactivity management. (author)

  8. New signal acquisition and processing system for the execution of initial criticality after refueling and physical tests at low power in Angra-2, with the incorporation of the real time resolution of the inverse point kinetic equation - IPK

    International Nuclear Information System (INIS)

    Júnior, Décio Brandes M.F.; Oliveira, Mônica Georgia N.; Silva, Cristiano da

    2017-01-01

    The goal of this work is present the new System of Acquisition and Signal Processing for the execution of the initial criticality after refueling and physical tests at low power with the incorporation of the real time resolution of Inverse Point Kinetic Equations (IPK). The system was developed using cRIO 9082 hardware (compactRIO), which is a programmable logic controller (PLC) and, the National Lab's LabVIEW programming language. The developed system enabled a better visualization and monitoring interface of the neutron flux evolution during the first criticality of cycle and following the low power physical tests, which allows the Reactor Physics Group and Reactor Operators of Angra 2 guide faster and accurately the reactivity variations at physical tests. The digital reactivity meter developed reinforces in Angra-2 the set of operational practices of reactivity management. (author)

  9. Comparison between dispersed nuclear power plants and a nuclear energy center at a hypothetical site on Kentucky Lake, Tennessee. Volume II. Transmission of power

    International Nuclear Information System (INIS)

    Reister, D.B.; Zelby, L.W.

    1976-05-01

    A comparison is made among power transmission systems required to serve a single set of load center demands from four modes of siting the generating facilities: a single generation site with an ultimate generation capacity of 48,000 MW; four generation sites each with a generation capacity of 12,000 MW; 10 generation sites each with a generation capacity of 4,800 MW; and a system that resulted when the existing utility plan for future generation was logically expanded. The time period for the study is from the year 1985 to the year 2020, when the full 48,000 MW of new capacity from the single large nuclear energy center is on-line. The load centers served are Huntsville, Alabama; Evansville, Indiana; Paducah, Kentucky; and Chattanooga, Nashville, and Memphis, Tennessee. Generation sites are real locations but are hypothetical in terms of miles of transmission lines, the product of the amount of power transmitted and the distance transmitted (GW-miles), and cost

  10. Nuclear inelastic scattering of 1D polymeric Fe(II) complexes of 1,2,4-aminotriazole in their high-spin and low-spin state

    Energy Technology Data Exchange (ETDEWEB)

    Wolny, Juliusz A., E-mail: wolny@physik.uni-kl.de; Rackwitz, Sergej [University of Kaiserslautern, Department of Physics (Germany); Achterhold, Klaus [Technische Universitaet Muenchen, Department of Physics (Germany); Muffler, Kai; Schuenemann, Volker [University of Kaiserslautern, Department of Physics (Germany)

    2012-03-15

    The vibrational properties of Fe(II) 1D spin crossover polymers have been characterized by nuclear inelastic scattering (NIS). The complexes under study were the tosylate and perchlorate salts of ([Fe(4-amino-1,2,4-triazole){sub 3}] <{sup +2}){sub n} complexes. The complexes have LS (S = 0) marker bands in the range of 300-500 cm{sup - 1}, while the marker bands corresponding to the HS (S = 2) state are detected between 200 cm{sup - 1} and 300 cm{sup - 1}, in line with the decreasing Fe-N bond strengths during the transition from LS to HS. Accompanying DFT calculations using the functional B3LYP and the basis set CEP-31G confirm these assignments.

  11. Nuclear energy generation and the safety criteria for Brazilian power plants

    International Nuclear Information System (INIS)

    Silva, Gustavo Brandão e

    2016-01-01

    The purpose of this paper is to show how the use of nuclear technology can help to diversify the national electricity matrix in a sustainable and efficient way. For this, an analysis of the current situation of the Brazilian electric sector will be made, exposing its fragilities and highlighting the advantages of the nuclear source as an alternative to integrate the necessary thermoelectric base to the reliable supply of electricity in the country. In addition, the objective of the work is to detail the process of exploiting atomic energy in Brazil from raw material mining, through the stages involving the manufacture of nuclear fuel, to the current operation and situation of Brazilian power plants. By taking the Angra 2 Nuclear Power Plant as a case study, the safety criteria adopted in its design and operation will be highlighted. Particular attention will also be given to the electric supply alternatives and to the active safety systems of the plant

  12. Risks and losses from nuclear indecision

    International Nuclear Information System (INIS)

    Mattos, Joao Roberto Loureiro de; Dias, Marcio Soares

    2007-01-01

    The nuclear option until recently defended in its purely strategic dimension is now being considered as an important contribution to obtain complementarity, competitiveness and thermoelectric regulation which are necessary to confer reliability to the Brazilian electricity generation system. In the past, the indecision regarding the full implementation of the nuclear sector have incurred in losses that result from the under exploitation of the existent human resources and infrastructure, as well as a low exploitation of an abundant, cheap and available primary energy source from the Brazilian subsoil: the uranium. Presently, Brazil has a new chance to explore the nuclear option in order to confer greater diversification and reliability to the Brazilian electricity generation system, whose first step is the conclusion of the ANGRA 3 Nuclear Power Plant that is to be followed by the constructions of other nuclear installations. The new NPP's can be oriented to the northeast that is the region with bigger lack in primary sources and, therefore, with bigger risk of energy deficit. (author)

  13. Plasma Physics and Controlled Nuclear Fusion Research. Vol. II. Proceedings of a Conference on Plasma Physics and Controlled Physics Research

    International Nuclear Information System (INIS)

    1966-01-01

    Research on controlled nuclear fusion was first disclosed at the Second United Nations Conference on the Peaceful Uses of Atomic Energy, held at Geneva in 1958. From the information given, it was evident that a better understanding of the behaviour of hot dense plasmas was needed before the goal of economic energy release from nuclear fusion could be reached. The fact that research since then has been most complex and costly has enhanced the desirability of international co-operation and exchange of information and experience. Having organized its First Conference on Plasma Physics and Controlled Nuclear Fusion Research at Salzburg in 1961, the International Atomic Energy Agency again provided the means for such cooperation in organizing its Second Conference on this subject on 6-10 September, 1965, at Culham, Abingdon, Berks, England. The meeting was arranged with the generous help of the United Kingdom Atomic Energy Authority at their Culham Laboratory, where the facilities and assistance of the staff were greatly appreciated. At the meeting, which was attended by 268 participants from 26 member states and three international organizations, significant results from many experiments, including those from the new and larger machines, became available. It has now become feasible to intercorrelate data obtained from a number of similar machines; this has led to a more complete understanding of plasma behaviour. No breakthrough was reported nor had been expected towards the economical release of the energy from fusion, but there was increased understanding of the problems of production, control and containment of high-density and high-temperature plasmas

  14. A study on nuclear heat load tolerable for NET/TF coils cooled by internal flow of helium II

    International Nuclear Information System (INIS)

    Hofmann, A.

    1988-02-01

    NbTi cables cooled by internal flow of superfluid helium are considered an option for the design of NET/TF coils with about 11 T peak fields. Starting from an available winding cross section of 0.61x0.61 m 2 for a 8 MA turns coil made of a 16 kA conductor it is shown that sufficient hydraulic cross section can be provided within such cables to remove the expected thermal load resulting from nuclear heating with exponential decay from inboard to outboard side of the winding. The concept is a pancake type coil with 1.8 K helium fed-in the high field region of each pancake. The temperature distribution within such coils is calculated, and the local safety margin is determined from temperature and field. The calculation takes account of nuclear and a.c. heating, and of thermal conductance between the individual layers and the coil casing. It is shown that operation with 1.8 K inlet and about 3 K outlet temperature is possible. The electrical insulation with about 0.5 mm thickness proves to provide sufficient thermal insulation. No additional thermal shield is required between the coil casing and the winding package. Two different types of conductors are being considered: a) POLO type cable with quadratic cross section and a central circular coolant duct, and b) an LCT type cable with two conductors wound in hand. Both concepts with about 500 m length of the cooland channels are shown to meet the requirements resulting from a peak nuclear heat load of 0.3 mW/cm 3 in the inboard turns. The hydraulic diameters are sufficient to operate each coils with self-sustained fountain effect pumps. Even appreciably higher heat loads with up to 3 mW/cm 3 of nuclear heating can be tolerated for the POLO type cable when the hydraulic diameter is enlarged to its maximum of 17 mm. (orig.) [de

  15. Irradiation positions for fission-track dating in the University of Pavia TRIGA Mark II nuclear reactor

    International Nuclear Information System (INIS)

    Oddone, Massimo; Meloni, Sandro; Balestrieri, Maria Laura; Bigazzi, Giulio

    2002-01-01

    An irradiation position arranged is described in the present paper for fission-track dating in the Triga Mark II reactor of the University of Pavia. Fluence values determined using the NIST glass standard SRM 962a for fission-track dating and the traditional metal foils are compared. Relatively good neutron thermalization (φ th /φ f = 0.956) and lack of significant fluence spatial gradients are good factors for fission-track dating. Finally, international age standards (or putative age standards) irradiated in this new position yielded results consistent with independent reference ages. (author)

  16. Proceedings of the Fiber Optics in the Nuclear Environment Symposium 25-27 March 1980. Volume II. Radiation Physics,

    Science.gov (United States)

    1980-04-30

    IV FIEE I(TMS a MLYTICAL FIT U0 T -------------------------------------------------------- 0 10 too ISO too 250 ZOO 350 400 410 Fig. 4 Fourier unfold...of transmission data for 4 m of T-103 fiber 77 E XPEIENTAL. 4m LENGTH RCALCULATED. 4m LFNOGfl zc goh I- o o 100 IS O too ISO to 350 t(nsscl Fig. 5...Recombination Function (- 5 ns1l)and Convolution of Function with Norma - lized Febetron Current Pulse. 109 Al 4,,0a. II 300 I i 200 F Fiber ITT T303

  17. Phase II, Title I engineering assessment of inactive uranium mill tailings, Phillips/United Nuclear Site, Ambrosia Lake, New Mexico

    International Nuclear Information System (INIS)

    1977-12-01

    An engineering assessment was performed of the problems resulting from the existence of radioactive uranium mill tailings at the Phillips/United Nuclear site at Ambrosia Lake, New Mexico. Services included the preparation of topographic maps, the performance of core drillings sufficient to determine areas and volumes of tailings, and radiometric measurements to determine radium-contaminated materials, the evaluation of resulting radiation exposures of individuals and nearby populations, the investigation of site hydrology and meteorology, and the evaluation and costing of alternative corrective actions. Radon gas release from the 2.6 million tons of tailings at the Phillips/United Nuclear site constitutes the most significant environmental impact, although windblown tailings and external gamma radiation are also factors. The estimated radiological health effects to the general population are considered to be minimal. The two alternative actions presented are: dike stabilization, fencing, and maintenance; and adding 2 ft of stabilization cover material. Both options include remedial action at off-site structures and on-site decontamination around the tailings pile. Cost estimates for the two options are $920,000 and $2,230,000, respectively

  18. Material control in nuclear fuel fabrication facilities. Part II. Accountability, instrumentation and measurement techniques in fuel fabrication facilities

    International Nuclear Information System (INIS)

    Borgonovi, G.M.; McCartin, T.J.; McDaniel, T.; Miller, C.L.; Nguyen, T.

    1978-01-01

    This report describes the measurement techniques, the instrumentation, and the procedures used in accountability and control of nuclear materials, as they apply to fuel fabrication facilities. A general discussion is given of instrumentation and measurement techniques which are presently used being considered for fuel fabrication facilities. Those aspects which are most significant from the point of view of satisfying regulatory constraints have been emphasized. Sensors and measurement devices have been discussed, together with their interfacing into a computerized system designed to permit real-time data collection and analysis. Estimates of accuracy and precision of measurement techniques have been given, and, where applicable, estimates of associated costs have been presented. A general description of material control and accounting is also included. In this section, the general principles of nuclear material accounting have been reviewed first (closure of material balance). After a discussion of the most current techniques used to calculate the limit of error on inventory difference, a number of advanced statistical techniques are reviewed. The rest of the section deals with some regulatory aspects of data collection and analysis, for accountability purposes, and with the overall effectiveness of accountability in detecting diversion attempts in fuel fabrication facilities. A specific example of application of the accountability methods to a model fuel fabrication facility is given. The effect of random and systematic errors on the total material uncertainty has been discussed, together with the effect on uncertainty of the length of the accounting period

  19. Protective role of Nigella sativa against experimentally induced type-II diabetic nuclear damage in Wistar rats

    Directory of Open Access Journals (Sweden)

    T. J. Sheikh

    2013-07-01

    Full Text Available Aim: To identify the anti-mutagenic effect of Nigella sativa on the experimentally induced chronic diabetes (type – II in Wistar rats.Materials and Methods: The anti-mutagenic effect was evaluated in Nigella sativa treated diabetic rats against the streptozotocin - nicotinamide (STZ-NA (at a dose rate of 45-110 i.p mg/kg b.wt for 90 days induced type-II diabetes mellitus using bone marrow micronucleus tests. The antioxidant status was tested by estimating the serum levels of lipid peroxidation and superoxide dismutase.Results: Our results indicated that diabetic rats treated with Nigella sativa decreased the frequency of micronuclei in the erythrocytes of bone marrow (P < 0.05 and enhanced the antioxidant status (P < 0.05 in the treated diabetic rats as compared to controls.Conclusion: The observations indicated that the diabetic patients are more prone to cell mutations which are related to the level of cellular oxidative status and it could be reduced by Nigella sativa.

  20. Methods and Model Development for Coupled RELAP5/PARCS Analysis of the Atucha-II Nuclear Power Plant

    Directory of Open Access Journals (Sweden)

    Andrew M. Ward

    2011-01-01

    Full Text Available In order to analyze the steady state and transient behavior of CNA-II, several tasks were required. Methods and models were developed in several areas. HELIOS lattice models were developed and benchmarked against WIMS/MCNP5 results generated by NA-SA. Cross-sections for the coupled RELAP5/PARCS calculation were extracted from HELIOS within the GenPMAXS framework. The validation of both HELIOS and PARCS was performed primarily by comparisons to WIMS/PUMA and MCNP for idealized models. Special methods were developed to model the control rods and boron injection systems of CNA-II. The insertion of the rods is oblique, and a special routine was added to PARCS to treat this effect. CFD results combined with specialized mapping routines were used to model the boron injection system. In all cases there was good agreement in the results which provided confidence in the neutronics methods and modeling. A coupled code benchmark between U of M and U of Pisa is ongoing and results are still preliminary. Under a LOCA transient, the best estimate behavior of the core appears to be acceptable.

  1. Methods and Model Development for Coupled RELAP5/PARCS Analysis of the Atucha-II Nuclear Power Plant

    International Nuclear Information System (INIS)

    Ward, A.M.; Collins, B.S.; Xu, Y.; Downar, Th.J.; Madariaga, M.

    2011-01-01

    In order to analyze the steady state and transient behavior of CNA-II, several tasks were required. Methods and models were developed in several areas. HELIOS lattice models were developed and benchmarked against WIMS/MCNP5 results generated by NA-SA. Cross-sections for the coupled RELAP5/PARCS calculation were extracted from HELIOS within the Gen PMAXS framework. The validation of both HELIOS and PARCS was performed primarily by comparisons to WIMS/PUMA and MCNP for idealized models. Special methods were developed to model the control rods and boron injection systems of CNA-II. The insertion of the rods is oblique, and a special routine was added to PARCS to treat this effect. CFD results combined with specialized mapping routines were used to model the boron injection system. In all cases there was good agreement in the results which provided confidence in the neutronics methods and modeling. A coupled code benchmark between U of M and U of Pisa is ongoing and results are still preliminary. Under a LOCA transient, the best estimate behavior of the core appears to be acceptable

  2. Separation and solidification of radioactive cesium from nuclear waste solutions with potassium cobalt hexacyanoferrate (II) ion exchanger

    International Nuclear Information System (INIS)

    Lehto, J.; Harjula, R.

    1992-01-01

    The purpose of this study was to develop a separation and solidification process for 137 Cs, present in nuclear waste solutions. In this process cesium is selectively separated from the solutions by columns packed with granular potassium cobalt hexacyanoferrate. The process has been tested both in laboratory and pilot-plant experiments and the full scale industrial plant at the Loviisa NPP will be in operation in 1991. In this plant potassium cobalt hexacyanoferrate columns are used for the separation 134,137 Cs from an evaporator concentrate solution. Results on the column performance are given in this report. In addition, preparation, structure and ion exchange properties, as well as, resistance to radiation and elevated temperatures, of potassium cobalt hexacyanoferrate are described. A short description of the final disposal concept for the columns loaded with cesium is also given. (author). 16 refs, 13 figs, 2 tabs

  3. Future Industrialization of the World and the Necessity of Nuclear Power, Part II: How Limited are Resources?

    International Nuclear Information System (INIS)

    Jovanovich, Jovan V.

    1997-01-01

    Will the future world be forever divided into an industrial, developed and 'rich' on one side, and the primitive, undeveloped, and poor on the other? Is an industrial, affluent and sustainable world of 10-15 billion people owning 5-10 billion cars physically possible to exist? Can the world have enough food, minerals and energy to support such a widespread affluence in a sustainable manner? In previous papers I have argued that even without any major breakthroughs in science and technology, an industrialized, sustainable and affluent world can be created within the next half a century to a century, but only if breeder nuclear power is widely used throughout the world. In this paper I elaborate on the question of future availability of some basic natural resources. (author)

  4. Fermionic quantum systems. Part I: Phase transitions in quantum dots. Part II: Nuclear matter on a lattice

    Science.gov (United States)

    Muller, Hans-Michael

    1999-11-01

    In the first part I perform Hartree-Fock calculations to show that quantum dots (i.e., two-dimensional systems of up to twenty interacting electrons in an external parabolic potential) undergo a gradual transition to a spin-polarized Wiper crystal with increasing magnetic field strength. The phase diagram and ground state energies have been determined. I tried to improve the ground state of the Wigner crystal by introducing a Jastrow ansatz for the wave function and performing a variational Monte Carlo calculation. The existence of so called magic numbers was also investigated. Finally, I also calculated the heat capacity associated with the rotational degree of freedom of deformed many-body states and suggest an experimental method to detect Wigner crystals. The second part of the thesis investigates infinite nuclear matter on a cubic lattice. The exact thermal formalism describes nucleons with a Hamiltonian that accommodates on-site and next-neighbor parts of the central, spin-exchange and isospin-exchange interaction. Using auxiliary field Monte Carlo methods, I show that energy and basic saturation properties of nuclear matter can be reproduced. A first order phase transition from an uncorrelated Fermi gas to a clustered system is observed by computing mechanical and thermodynamical quantities such as compressibility, heat capacity, entropy and grand potential. The structure of the clusters is investigated with the help two-body correlations. I compare symmetry energy and first sound velocities with literature and find reasonable agreement. I also calculate the energy of pure neutron matter and search for a similar phase transition, but the survey is restricted by the infamous Monte Carlo sign problem. Also, a regularization scheme to extract potential parameters from scattering lengths and effective ranges is investigated.

  5. Sorption of {sup 60}Co and {sup 137}Cs in sediments at Piraquara de Fora, Angra dos Reis, RJ, Brazil; Sorcao de {sup 60}Co e {sup 137}Cs em sedimentos do Saco de Piraquara de Fora - Angra dos Reis

    Energy Technology Data Exchange (ETDEWEB)

    Carvalho, Franciane M.; Martins, Nadia S.F.; Lauria, Dejanira D., E-mail: francian@ird.gov.br, E-mail: nadia@ird.gov.br, E-mail: dejanira@ird.gov.br [Instituto de Radioprotecao e Dosimetria (IRD/CNEN-RJ), Rio de Janeiro, RJ (Brazil); Ferreira, Ingryd M., E-mail: ingrydmarques@hotmail.com [Instituto Federal do Rio de Janeiro (IFRJ), RJ (Brazil); Azevedo, Izabella M.A.P., E-mail: izabella_azevedo@id.uff.br [Universidade Federal Fluminense (UFF), Niteroi, RJ (Brazil)

    2013-07-01

    In this study, sediment of Piraquara de Fora, located near the launch area of the effluents of the Central Nuclear Almirante Alvaro Alberto - CNAAA Nuclear Power Plants, were collected. It were determined the parameters particle size and cationic exchange capacity (CTC). From the sorption curves of {sup 60}Co and {sup 137}Cs, obtained experimentally in the laboratory, were estimated preliminary values of Kd at equilibrium, for these radionuclides in order of magnitude of 10{sup 2}.

  6. U.S. Department Of Energy's nuclear engineering education research: highlights of recent and current research-II. 5. Automation of Nuclear Fuel Pellet Quality Control

    International Nuclear Information System (INIS)

    Keyvan, Shahla; Song, Xiaolong

    2001-01-01

    At the present time, nuclear fuel pellet inspection is performed by humans using the naked eye for judgment and decision making as to whether to accept or reject the pellet. Unnecessary re-fabrication of pellets will be costly, and having too many low-quality pellets in a fuel assembly is unacceptable. The current practice of pellet inspection by humans is tedious and subject to inconsistencies and error. In addition, manual inspection is cumbersome since the inspector must keep the pellet at arm's length and must wear glasses to protect the lenses of his or her eyes. The pellets are taken from a pellet sizing machine, dumped onto a rack, and shaken into rows; they are then viewed as a group. The entire group is rotated 90 deg four times to provide the inspector with a 360-deg view of each pellet. The pellets are examined for certain types of cracks, chips, and unusual markings, i.e., water stains and machine banding. These defects appear at any location on the pellet surface image with different intensity, size, shape, and background noise. Figure 1 shows typical defective fuel pellets with chip, banded, and end defects. The goal of this work is to automate the pellet inspection process. A prototype of such an inspection system is developed. The system examines photographic images of pellets using various artificial intelligence techniques for image analysis and defect classification. Figure 2 shows the user interface of this inspection system, which is built using Java programming language. A total of 252 pellets with various defects was available for this research. Each pellet was photographed four times at rotations of 90 deg. The resultant black-and-white negatives were scanned into the computer in 256 gray scale mode. The inspection of a fuel pellet by image analysis involves several steps, as described in Fig. 3 and as follows: Step 1-On-line image conversion: This process involves on-line digitization of the input image. Step 2-Reference model: The second

  7. Time response prediction of Brazilian Nuclear Power Plant temperature sensors using neural networks

    International Nuclear Information System (INIS)

    Santos, Roberto Carlos dos; Pereira, Iraci Martinez

    2011-01-01

    This work presents the results of the time constants values predicted from ANN using Angra I Brazilian nuclear power plant data. The signals obtained from LCSR loop current step response test sensors installed in the process presents noise end fluctuations that are inherent of operational conditions. Angra I nuclear power plant has 20 RTDs as part of the protection reactor system. The results were compared with those obtained from traditional way. Primary coolant RTDs (Resistance Temperature Detector) typically feed the plant's control and safety systems and must, therefore, be very accurate and have good dynamic performance. An in-situ test method called LCSR - loop current step response test was developed to measure remotely the response time of RTDs. In the LCSR method, the response time of the sensor is identified by means of the LCSR transformation that involves the dynamic response modal time constants determination using a nodal heat transfer model. For this reason, this calculation is not simple and requires specialized personnel. This work combines the two methodologies, Plunge test and LCSR test, using neural networks. With the use of neural networks it will not be necessary to use the LCSR transformation to determine sensor's time constant and this leads to more robust results. (author)

  8. Fault diagnosis of generation IV nuclear HTGR components – Part II: The area error enthalpy–entropy graph approach

    International Nuclear Information System (INIS)

    Rand, C.P. du; Schoor, G. van

    2012-01-01

    Highlights: ► Different uncorrelated fault signatures are derived for HTGR component faults. ► A multiple classifier ensemble increases confidence in classification accuracy. ► Detailed simulation model of system is not required for fault diagnosis. - Abstract: The second paper in a two part series presents the area error method for generation of representative enthalpy–entropy (h–s) fault signatures to classify malfunctions in generation IV nuclear high temperature gas-cooled reactor (HTGR) components. The second classifier is devised to ultimately address the fault diagnosis (FD) problem via the proposed methods in a multiple classifier (MC) ensemble. FD is realized by way of different input feature sets to the classification algorithm based on the area and trajectory of the residual shift between the fault-free and the actual operating h–s graph models. The application of the proposed technique is specifically demonstrated for 24 single fault transients considered in the main power system (MPS) of the Pebble Bed Modular Reactor (PBMR). The results show that the area error technique produces different fault signatures with low correlation for all the examined component faults. A brief evaluation of the two fault signature generation techniques is presented and the performance of the area error method is documented using the fault classification index (FCI) presented in Part I of the series. The final part of this work reports the application of the proposed approach for classification of an emulated fault transient in data from the prototype Pebble Bed Micro Model (PBMM) plant. Reference data values are calculated for the plant via a thermo-hydraulic simulation model of the MPS. The results show that the correspondence between the fault signatures, generated via experimental plant data and simulated reference values, are generally good. The work presented in the two part series, related to the classification of component faults in the MPS of different

  9. Applications of nuclear physics

    Science.gov (United States)

    Hayes, A. C.

    2017-02-01

    Today the applications of nuclear physics span a very broad range of topics and fields. This review discusses a number of aspects of these applications, including selected topics and concepts in nuclear reactor physics, nuclear fusion, nuclear non-proliferation, nuclear-geophysics, and nuclear medicine. The review begins with a historic summary of the early years in applied nuclear physics, with an emphasis on the huge developments that took place around the time of World War II, and that underlie the physics involved in designs of nuclear explosions, controlled nuclear energy, and nuclear fusion. The review then moves to focus on modern applications of these concepts, including the basic concepts and diagnostics developed for the forensics of nuclear explosions, the nuclear diagnostics at the National Ignition Facility, nuclear reactor safeguards, and the detection of nuclear material production and trafficking. The review also summarizes recent developments in nuclear geophysics and nuclear medicine. The nuclear geophysics areas discussed include geo-chronology, nuclear logging for industry, the Oklo reactor, and geo-neutrinos. The section on nuclear medicine summarizes the critical advances in nuclear imaging, including PET and SPECT imaging, targeted radionuclide therapy, and the nuclear physics of medical isotope production. Each subfield discussed requires a review article unto itself, which is not the intention of the current review; rather, the current review is intended for readers who wish to get a broad understanding of applied nuclear physics.

  10. Applications of nuclear physics

    International Nuclear Information System (INIS)

    Hayes-Sterbenz, Anna Catherine

    2017-01-01

    Today the applications of nuclear physics span a very broad range of topics and fields. This review discusses a number of aspects of these applications, including selected topics and concepts in nuclear reactor physics, nuclear fusion, nuclear non-proliferation, nuclear-geophysics, and nuclear medicine. The review begins with a historic summary of the early years in applied nuclear physics, with an emphasis on the huge developments that took place around the time of World War II, and that underlie the physics involved in designs of nuclear explosions, controlled nuclear energy, and nuclear fusion. The review then moves to focus on modern applications of these concepts, including the basic concepts and diagnostics developed for the forensics of nuclear explosions, the nuclear diagnostics at the National Ignition Facility, nuclear reactor safeguards, and the detection of nuclear material production and trafficking. The review also summarizes recent developments in nuclear geophysics and nuclear medicine. The nuclear geophysics areas discussed include geo-chronology, nuclear logging for industry, the Oklo reactor, and geo-neutrinos. The section on nuclear medicine summarizes the critical advances in nuclear imaging, including PET and SPECT imaging, targeted radionuclide therapy, and the nuclear physics of medical isotope production. Lastly, each subfield discussed requires a review article unto itself, which is not the intention of the current review; rather, the current review is intended for readers who wish to get a broad understanding of applied nuclear physics.

  11. Proof of fatigue strength of nuclear components part II: Numerical fatigue analysis for transient stratification loading considering environmental effects

    International Nuclear Information System (INIS)

    Krätschmer, D.; Roos, E.; Schuler, X.; Herter, K.-H.

    2012-01-01

    For the construction, design and operation of nuclear components and systems the appropriate technical codes and standards provide detailed analysis procedures which guarantee a reliable behaviour of the structural components throughout the specified lifetime. Especially for cyclic stress evaluation the different codes and standards provide different fatigue analyses procedures to be performed considering the various mechanical and thermal loading histories and geometric complexities of the components. To consider effects of light water reactor coolant environments, new design curves included in report NUREG/CR-6909 for austenitic stainless steels and for low alloy steels have been presented. For the usage of these new design curves an environmental fatigue correction factor for incorporating environmental effects has to be calculated and used. The application of this environmental correction factor to a fatigue analysis of a nozzle with transient stratification loads, derived by in-service monitoring, has been performed. The results are used to compare with calculated usage factors, based on design curves without taking environmental effects particularly into account. - Highlights: ► We model an nozzle for fatigue analysis und mechanical and thermal loading conditions. ► A simplified as well as a general elastic–plastic fatigue analysis considering environmental effects is performed. ► The influence of different factors calculating the environmental factor F en are shown. ► The presented numerical evaluation methodology allows the consideration of all relevant parameters to assess lifetime.

  12. Sorption of 60Co and 137Cs in sediments at Piraquara de Fora, Angra dos Reis, RJ, Brazil

    International Nuclear Information System (INIS)

    Carvalho, Franciane M.; Martins, Nadia S.F.; Lauria, Dejanira D.; Ferreira, Ingryd M.; Azevedo, Izabella M.A.P.

    2013-01-01

    In this study, sediment of Piraquara de Fora, located near the launch area of the effluents of the Central Nuclear Almirante Alvaro Alberto - CNAAA Nuclear Power Plants, were collected. It were determined the parameters particle size and cationic exchange capacity (CTC). From the sorption curves of 60 Co and 137 Cs, obtained experimentally in the laboratory, were estimated preliminary values of Kd at equilibrium, for these radionuclides in order of magnitude of 10 2

  13. DJ-1 Modulates Nuclear Erythroid 2–Related Factor-2–Mediated Protection in Human Primary Alveolar Type II Cells in Smokers

    Science.gov (United States)

    Bahmed, Karim; Messier, Elise M.; Zhou, Wenbo; Tuder, Rubin M.; Freed, Curt R.; Chu, Hong Wei; Kelsen, Steven G.; Bowler, Russell P.; Mason, Robert J.

    2016-01-01

    Cigarette smoke (CS) is a main source of oxidative stress and a key risk factor for emphysema, which consists of alveolar wall destruction. Alveolar type (AT) II cells are in the gas exchange regions of the lung. We isolated primary ATII cells from deidentified organ donors whose lungs were not suitable for transplantation. We analyzed the cell injury obtained from nonsmokers, moderate smokers, and heavy smokers. DJ-1 protects cells from oxidative stress and induces nuclear erythroid 2–related factor-2 (Nrf2) expression, which activates the antioxidant defense system. In ATII cells isolated from moderate smokers, we found DJ-1 expression by RT-PCR, and Nrf2 and heme oxygenase (HO)-1 translocation by Western blotting and immunocytofluorescence. In ATII cells isolated from heavy smokers, we detected Nrf2 and HO-1 cytoplasmic localization. Moreover, we found high oxidative stress, as detected by 4-hydroxynonenal (4-HNE) (immunoblotting), inflammation by IL-8 and IL-6 levels by ELISA, and apoptosis by terminal deoxynucleotidyl transferase dUTP nick end labeling (TUNEL) assay in ATII cells obtained from heavy smokers. Furthermore, we detected early DJ-1 and late Nrf2 expression after ATII cell treatment with CS extract. We also overexpressed DJ-1 by adenovirus construct and found that this restored Nrf2 and HO-1 expression and induced nuclear translocation in heavy smokers. Moreover, DJ-1 overexpression also decreased ATII cell apoptosis caused by CS extract in vitro. Our results indicate that DJ-1 activates the Nrf2-mediated antioxidant defense system. Furthermore, DJ-1 overexpression can restore the impaired Nrf2 pathway, leading to ATII cell protection in heavy smokers. This suggests a potential therapeutic strategy for targeting DJ-1 in CS-related lung diseases. PMID:27093578

  14. Human factors analysis and design methods for nuclear waste retrieval systems. Volume II. A compendium of human factors design data

    International Nuclear Information System (INIS)

    Casey, S.M.

    1980-04-01

    This document is a compilation of human factors engineering design recommendations and data, selected and organized to assist in the design of a nuclear waste retrieval system. Design guidelines from a variety of sources have been evaluated, edited, and expanded for inclusion in this document, and, where appropriate, portions of text from selected sources have been included in their entirety. A number of human factors engineering guidelines for equipment designers have been written over the past three decades, each tailored to the needs of the specific system being designed. In the case of this particular document, a review of the preliminary human operator functions involved in each phase of the retrieval process was performed, resulting in the identification of areas of design emphasis upon which this document should be based. Documents containing information and design data on each of these areas were acquired, and data and design guidelines related to the previously identified areas of emphasis were extracted and reorganized. For each system function, actions were first assigned to operator and/or machine, and the operator functions were then described. Separate lists of operator functions were developed for each of the areas of retrieval activities - survey and mapping, remining, floor flange emplacement, plug and canister overcoring, plug and canister removal and transport, and CWSRS activity. These functions and the associated man-machine interface were grouped into categories based on task similarity, and the principal topics of human factors design emphasis were extracted. These topic areas are reflected in the contents of the 12 sections of this document

  15. A localized navigation algorithm for Radiation Evasion for nuclear facilities. Part II: Optimizing the “Nearest Exit” Criterion

    International Nuclear Information System (INIS)

    Khasawneh, Mohammed A.; Al-Shboul, Zeina Aman M.; Jaradat, Mohammad A.; Malkawi, Mohammad I.

    2013-01-01

    Highlights: ► A new navigation algorithm for Radiation Evasion around nuclear facilities. ► An optimization criteria minimized under algorithm operation. ► A man-borne device guiding the occupational worker towards paths that warrant least radiation × time products. ► Benefits of using localized navigation as opposed to global navigation schemas. ► A path discrimination function for finding the navigational paths exhibiting the least amounts of radiation. -- Abstract: In this extension from part I (Khasawneh et al., in press), we modify the navigation algorithm which was presented with the objective of optimizing the “Radiation Evasion” Criterion so that navigation would optimize the criterion of “Nearest Exit”. Under this modification, algorithm would yield navigation paths that would guide occupational workers towards Nearest Exit points. Again, under this optimization criterion, algorithm leverages the use of localized information acquired through a well designed and distributed wireless sensor network, as it averts the need for any long-haul communication links or centralized decision and monitoring facility thereby achieving a more reliable performance under dynamic environments. As was done in part I, the proposed algorithm under the “Nearest Exit” Criterion is designed to leverage nearest neighbor information coming in through the sensory network overhead, in computing successful navigational paths from one point to another. For comparison purposes, the proposed algorithm is tested under the two optimization criteria: “Radiation Evasion” and “Nearest Exit”, for different numbers of step look-ahead. We verify the performance of the algorithm by means of simulations, whereby navigational paths are calculated for different radiation fields. We, via simulations, also, verify the performance of the algorithm in comparison with a well-known global navigation algorithm upon which we draw our conclusions

  16. A localized navigation algorithm for Radiation Evasion for nuclear facilities. Part II: Optimizing the “Nearest Exit” Criterion

    Energy Technology Data Exchange (ETDEWEB)

    Khasawneh, Mohammed A., E-mail: mkha@ieee.org [Department of Electrical Engineering, Jordan University of Science and Technology (Jordan); Al-Shboul, Zeina Aman M., E-mail: xeinaaman@gmail.com [Department of Electrical Engineering, Jordan University of Science and Technology (Jordan); Jaradat, Mohammad A., E-mail: majaradat@just.edu.jo [Department of Mechanical Engineering, Jordan University of Science and Technology (Jordan); Malkawi, Mohammad I., E-mail: mmalkawi@aimws.com [College of Engineering, Jadara University, Irbid 221 10 (Jordan)

    2013-06-15

    Highlights: ► A new navigation algorithm for Radiation Evasion around nuclear facilities. ► An optimization criteria minimized under algorithm operation. ► A man-borne device guiding the occupational worker towards paths that warrant least radiation × time products. ► Benefits of using localized navigation as opposed to global navigation schemas. ► A path discrimination function for finding the navigational paths exhibiting the least amounts of radiation. -- Abstract: In this extension from part I (Khasawneh et al., in press), we modify the navigation algorithm which was presented with the objective of optimizing the “Radiation Evasion” Criterion so that navigation would optimize the criterion of “Nearest Exit”. Under this modification, algorithm would yield navigation paths that would guide occupational workers towards Nearest Exit points. Again, under this optimization criterion, algorithm leverages the use of localized information acquired through a well designed and distributed wireless sensor network, as it averts the need for any long-haul communication links or centralized decision and monitoring facility thereby achieving a more reliable performance under dynamic environments. As was done in part I, the proposed algorithm under the “Nearest Exit” Criterion is designed to leverage nearest neighbor information coming in through the sensory network overhead, in computing successful navigational paths from one point to another. For comparison purposes, the proposed algorithm is tested under the two optimization criteria: “Radiation Evasion” and “Nearest Exit”, for different numbers of step look-ahead. We verify the performance of the algorithm by means of simulations, whereby navigational paths are calculated for different radiation fields. We, via simulations, also, verify the performance of the algorithm in comparison with a well-known global navigation algorithm upon which we draw our conclusions.

  17. Deep repository for spent nuclear fuel. SR-97-Post-closure safety. Main Report. Volume I and II

    International Nuclear Information System (INIS)

    Hedin, A.

    1999-11-01

    In preparation for coming site investigations for siting of a deep repository for spent nuclear fuel, the Swedish Government and nuclear regulatory authorities have requested an assessment of the repository's long-term safety. The purpose is to demonstrate whether the risk of harmful effects in individuals in the vicinity of the repository complies with the acceptance criterion formulated by the Swedish regulatory authorities, i.e. that the risk may not exceed 10 -6 per year. Geological data are taken from three sites in Sweden to shed light on different conditions in Swedish granitic bedrock. The future evolution of the repository system is analyzed in the form of five scenarios. The first is a base scenario where the repository is postulated to be built entirely according to specifications and where present-day conditions in the surroundings are postulated to persist. The four other scenarios show how the evolution of the repository differs from that in the base scenario if the repository contains a few initially defective canisters, in the event of climate change, earthquakes, and future inadvertent human intrusion. The time horizon for the analyses is at most one million years, in accordance with preliminary regulations. By means of model studies and calculations, the base scenario analyzes how the radioactivity of the fuel declines with time, the repository's thermal evolution as a result of the decay heat in the fuel, the hydraulic evolution in buffer and backfill when they become saturated with water, and the long-term groundwater flow in the geosphere on the three sites. The overall conclusion of the analyses in the base scenario is that the copper canisters isolating capacity is not threatened by either the mechanical or chemical stresses to which it is subjected. The safety margins are great even in a million-year perspective. The internal evolution in initially defective canisters and the possible resultant migration of radionuclides in buffer, geosphere

  18. 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

  19. Deep repository for spent nuclear fuel. SR-97-Post-closure safety. Main Report. Volume I and II

    Energy Technology Data Exchange (ETDEWEB)

    Hedin, A. [ed.

    1999-11-01

    In preparation for coming site investigations for siting of a deep repository for spent nuclear fuel, the Swedish Government and nuclear regulatory authorities have requested an assessment of the repository's long-term safety. The purpose is to demonstrate whether the risk of harmful effects in individuals in the vicinity of the repository complies with the acceptance criterion formulated by the Swedish regulatory authorities, i.e. that the risk may not exceed 10{sup -6} per year. Geological data are taken from three sites in Sweden to shed light on different conditions in Swedish granitic bedrock. The future evolution of the repository system is analyzed in the form of five scenarios. The first is a base scenario where the repository is postulated to be built entirely according to specifications and where present-day conditions in the surroundings are postulated to persist. The four other scenarios show how the evolution of the repository differs from that in the base scenario if the repository contains a few initially defective canisters, in the event of climate change, earthquakes, and future inadvertent human intrusion. The time horizon for the analyses is at most one million years, in accordance with preliminary regulations. By means of model studies and calculations, the base scenario analyzes how the radioactivity of the fuel declines with time, the repository's thermal evolution as a result of the decay heat in the fuel, the hydraulic evolution in buffer and backfill when they become saturated with water, and the long-term groundwater flow in the geosphere on the three sites. The overall conclusion of the analyses in the base scenario is that the copper canisters isolating capacity is not threatened by either the mechanical or chemical stresses to which it is subjected. The safety margins are great even in a million-year perspective. The internal evolution in initially defective canisters and the possible resultant migration of radionuclides in

  20. Kaposi's Sarcoma-Associated Herpesvirus Latency-Associated Nuclear Antigen Inhibits Major Histocompatibility Complex Class II Expression by Disrupting Enhanceosome Assembly through Binding with the Regulatory Factor X Complex.

    Science.gov (United States)

    Thakker, Suhani; Purushothaman, Pravinkumar; Gupta, Namrata; Challa, Shanthan; Cai, Qiliang; Verma, Subhash C

    2015-05-01

    Major histocompatibility complex class II (MHC-II) molecules play a central role in adaptive antiviral immunity by presenting viral peptides to CD4(+) T cells. Due to their key role in adaptive immunity, many viruses, including Kaposi's sarcoma-associated herpesvirus (KSHV), have evolved multiple strategies to inhibit the MHC-II antigen presentation pathway. The expression of MHC-II, which is controlled mainly at the level of transcription, is strictly dependent upon the binding of the class II transactivator (CIITA) to the highly conserved promoters of all MHC-II genes. The recruitment of CIITA to MHC-II promoters requires its direct interactions with a preassembled MHC-II enhanceosome consisting of cyclic AMP response element-binding protein (CREB) and nuclear factor Y (NF-Y) complex and regulatory factor X (RFX) complex proteins. Here, we show that KSHV-encoded latency-associated nuclear antigen (LANA) disrupts the association of CIITA with the MHC-II enhanceosome by binding to the components of the RFX complex. Our data show that LANA is capable of binding to all three components of the RFX complex, RFX-associated protein (RFXAP), RFX5, and RFX-associated ankyrin-containing protein (RFXANK), in vivo but binds more strongly with the RFXAP component in in vitro binding assays. Levels of MHC-II proteins were significantly reduced in KSHV-infected as well as LANA-expressing B cells. Additionally, the expression of LANA in a luciferase promoter reporter assay showed reduced HLA-DRA promoter activity in a dose-dependent manner. Chromatin immunoprecipitation assays showed that LANA binds to the MHC-II promoter along with RFX proteins and that the overexpression of LANA disrupts the association of CIITA with the MHC-II promoter. These assays led to the conclusion that the interaction of LANA with RFX proteins interferes with the recruitment of CIITA to MHC-II promoters, resulting in an inhibition of MHC-II gene expression. Thus, the data presented here identify a novel