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

Crystal-field spectra of fassaite from the Angra dos Reis meteorite

Energy Technology Data Exchange (ETDEWEB)

Mao, H K; Bell, P M; Virgo, D [Carnegie Institution of Washington, D.C. (USA)

1977-06-01

Fassaitic pyroxene from the Angra dos Reis meteorite has striking spectral properties. The /sup 57/Fe Moessbauer spectra show no Fe/sup 3 +/, and thus the absorption is thought to originate from a complex charge-transfer process. Intense absorption at 480 nm dominates the spectrum of the meteorite and may be important in the interpretation of telescope spectra of objects in space.

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)

Angra nuclear plant - environmental control program; Usina Nuclear de Angra: programa de controle ambiental

Energy Technology Data Exchange (ETDEWEB)

Kircher, E; Cruz, E.S. da [FURNAS, Rio de Janeiro, RJ (Brazil)

1990-12-31

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.

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)

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.)

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

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

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.

Economic-financial analysis of 'Angra 3 Nuclear Power Plant' project; Analise economico-financeira do empreendimento 'Usina Nuclear Angra 3'

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

2005-07-01

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)

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)

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

Energy Technology Data Exchange (ETDEWEB)

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

1996-07-01

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

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.

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

Radiological respiratory protection in Angra-1 Nuclear Power Plant

International Nuclear Information System (INIS)

Amaral, Marcos A. do

1996-01-01

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

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)

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)

The first accident simulation of Angra-1 power plant using the ALMOD computer code

International Nuclear Information System (INIS)

Camargo, C.T.M.

1981-01-01

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. (E.G.) [pt

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)

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

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

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

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)

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)

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)

Quality assurance of civil works during the construction of the nuclear power plant Unit II Angra dos Reis in Brazil

International Nuclear Information System (INIS)

Nellessen, H.G.

1980-01-01

The lecture summarizes the structure of the applied Quality Assurance Manual, which is subdivided into three sections: (1) Quality Assurance Program, (2) General Proceedings and (3) Inspection Programs. Since the power plant was designed according to DIN standards but supervision and construction are being performed following ASTM or Brazilian standards, the Quality Assurance Manual and the Quality Assurance organization were developed specifically for the Angra-Site. The applied system is illustrated by practical examples of pile foundations. Quality Assurance supervision and flow charts showing the interaction of the quality control organization. (orig.)

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)

Persistency of atmospheric diffusion conditions in Angra dos Reis - Brazil

International Nuclear Information System (INIS)

Nicolli, D.

1981-12-01

Based on a 2 year observation period, the diffusion conditions at the Almirante Alvaro Alberto N.P.P. site, in Angra dos Reis, are analized with respect to persistency as a function of the wind direction, the Pasquill stability class and the time of the day. The Pasquill stability class relates to the bulk vertical temperature gradient measured between 2m and 50m in the atmosphere; the wind direction is measured at 50m height. The persistency is defined in this report as the probability that the wind direction will remain longer than a given time in a sector without change in the diffusion category by more than a certain stage. During the day the persistency is mostly affected by the sea breeze with predominance of the unstable and neutral categories. At night the stable categories dominate. The alternating sea and land breezes disturb daily the trade wind field resulting in low persistency of the diffusion conditions. (Author) [pt

Nuclear power plants after Angra-3. Property and operation flexibility

International Nuclear Information System (INIS)

Deppe, Lothario

2008-01-01

The present work analyses the consequences that will be introduced with the modifications in the actual existing systematic related to the property and operation of nuclear power plants, coming from the legislation of 2004 that establishes that the electric energy distribution concessionaires acquire energy for attending its markets through bid in the modality of auction conducted by ANEEL - Brazilian Agency of Electric Energy. This systematic means that probably the Nuclear Power Plants after Angra-3 will be submitted to this auction process. The present report analyses all these questions and proposes solutions that seems to be the most obvious and viable

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)

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)

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.

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

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)

Utilization, maintenance and upgrading of the ANGRA-2 NPP simulator

International Nuclear Information System (INIS)

Rodrigues, J.C.

1997-01-01

In order to provide a highly qualified training for the future operation teams of the ANGRA-2 and 3 Nuclear Power Plants, ELECTRONUCLEAR has built a training center, at the Plant site, including a full-scope Simulator based on the Siemens/KWU design, PWR, 1300 MW ANGRA-2 Nuclear Power Plant. The Simulator is a full-scope replica of that of the ANGRA-2 Plant. The CTAS has implemented, since the beginning of its operation in Brazil, an extensive training program for operators, technical managers and commissioning and licensing personnel from foreign nuclear power plants, as well as specialists for national and foreign organizations involved with several activities related to nuclear installations and also with the operation of conventional electric power plants. After the installation of the Simulator in Brazil, the Simulator software had been continuously modified and updated. (author)

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)

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

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)

Commissioning of the nuclear power plant

International Nuclear Information System (INIS)

Furtado, P.M.; Rolf, F.

1984-01-01

Nuclear Power Plant Angra 2, located at Itaorna Beach-Angra dos Reis is the first plant of the Brazilian-German Agreement to be commissioned. The Nuclear Power Plant is a pressurized water reactor rated at 3765 Mw thermal/1325 Mw electrical. For commissioning purpose the plant is divided into 110 systems. Plant commissioning objective is to demonstrate the safe and correct operation of each plan component, system and of the whole plant in agreement with design conditions, licensing requirements and contractual obligations. This work gives a description of plant commissioning objectives, activities their time sequence, and documentation. (Author) [pt

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

Simulation spread sheet of Angra-1 secondary circuit

International Nuclear Information System (INIS)

Futuro, F.L.; Rucos, J.; Ogando, A.; Maprelian, E.; Bassel, W.S.; Baptista Filho, B.D.

2000-01-01

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)

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)

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}.

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

Energy Technology Data Exchange (ETDEWEB)

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

1997-12-31

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

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)

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

International Nuclear Information System (INIS)

Martins, Carlos F.O.; Crepaldi, Roberto; Freire, Enio M.; Campello, Sergio A.

2015-01-01

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)

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)

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

Experience with diagnostics at ANGRA I

International Nuclear Information System (INIS)

Feiner, F.R.

1997-01-01

Experience with maintenance and diagnostics at Angra 1 is described including the following issues: predictive maintenance program at Angra 1 NPP; Angra 1 predictive maintenance master list; maintenance evolution at Angra 1 NPP; MOVs evaluation program

Preoperational radiation measurements at the Angra-I nuclear power plant. Part 1

International Nuclear Information System (INIS)

Leao, J.L.B.; Barbosa, W.P.; Oberhofer, M.

1991-01-01

During December 10 and 11, 1980, γ-background measurements were performed at the Angra-I nuclear power plant within the reactor containment, within and outside the adjacent building complexes. The dose-rates within the containment averaged around 10,6 μR/h, within the auxiliary building around 14,4 μR/h. The lowest values, 6 μR/h, were measured within the reactor coolant pump and steam generator compartments, the highest value, 25 μR/h, in the charging pump valve operation room, elevation 8,65, close to area monitor No. 4. (author)

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

Special features of the safety concept and design requirements applied for Angra-2 and 3

International Nuclear Information System (INIS)

Anon.

1980-01-01

The special features and requirements which have been applied by NUCLEN (Nuclebras Engenharia S/A) for Angra 2 and Angra 3 and which depart somewhat from the KWU (Kraftwerk Union) standard plant, are presented. (E.G.) [pt

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)

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)

Simulation of a postulated 2% cold leg break in Angra 2 nuclear power plant

International Nuclear Information System (INIS)

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

2007-01-01

This paper presents the simulation of a 2% break in the cold leg pipe of Angra 2 nuclear power plant, with the computer code RELAP5/Mod3.3. The main boundary conditions specified for this simulation were: no injection from high pressure injection system; enhanced depressurization of the primary system by opening the pressure operated relief valve (PORV) and the safety relief valve (SRV) when core temperature reaches circa 100 K above saturation; and accumulator injection starting at 2.7 MPa. The specific objectives to be addressed with this simulation are: the core boil-off and dryout at relatively high pressure in the primary system; the phenomena during enhanced primary depressurization; the effectiveness of hot leg accumulator injection into the partially uncovered rod bundle; and the core rewetting. The results obtained were compared with the Lobi A1-93 test, which was performed under the same boundary conditions. This activity was executed in the scope of IAEA research project Evaluation of Uncertainties in the Simulation of Accidents in Angra 2 using RELAP5/MOD3 Code Applying CIAU Methodology (author)

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)

Evaluation of tests for coastdown of reactor coolant flow and measure of primary circuit flow of Angra-1 nuclear power plant

International Nuclear Information System (INIS)

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

1987-05-01

The Angra 1 Nuclear Power Plant first reload license was issued after several technical discussions among CNEN, FURNAS and KWU. During the license process CNEN has established that the plant could return to anormal operation if the requirements described in the letter CNEN-DExL-C 06/86 were satisfied. The requirements according to the CNEN Transient and Thermohydraulic Group Analysis were to do again the following tests: 'Primary Flow Measurement' to check if the excess flow measured in the first cycle was held; and Pump Coastdown' to check if the Westinghouse and KWU fuel elements are thermo-hydraulicaly compatibles during transients. The mixed core must keep at least the same safety margin presented on Angra 1 FSAR for the original core. The tests and the analysis of results are described. (Author) [pt

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)

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)

Prediction and attendance of Angra 2 nuclear power plant cycle extension

International Nuclear Information System (INIS)

Dias, Amory; Ferreira Junior, Decio Brandes M.; Morgado, Mario Monteiro; Santos, Barbara Oliveira dos; Oliveira, Monica Georgia Nunes

2007-01-01

The Report Project Nuclear and Thermohydraulic (RPNT) of the Nuclear Power Plant Angra 2 previews extension of the cycle, using a feedback of core reactor reactivity, through the reduction of the moderator average temperature and power. In this phase, the reactor power remains almost invariable. Furthermore, the extension of cycle can be stretch after the limit of the temperature reduction has been reached, through of reactor power fall until the determined date for the end cycle and the start outage for the next cycle. The proposal of this work is to show the Power Plant results during the phase of moderator temperature reduction and to compare with the predict values obtained from reactivity balance calculation methodology used for the Reactor Physics. In general, the results of this work can collaborate for the extension behavior evaluation of the cycles of the Nuclear Power Plant 2, being used the procedure of cooling reduction average temperature, as well as, it will also collaborate for methodology qualification applied for the Reactor Physics during the reactivity balance calculation. (author)

An economical analysis of stretch-out for Angra 1

International Nuclear Information System (INIS)

Sakai, M.; Mascarenhas, H.A.

1990-01-01

An economical assessment of Angra 1 fuel cycle stretch-out is performed by means of NUCOST 1.0, a PWR power cost calculation code. International basic costs and an interest rate of 10%a were utilized. During the natural part of the fuel cycle an hypothetical capacity factor of 70% and in the stretch-out part a decrease in Plant's thermal efficiency have also been taken into account. The neutronic data were generated by FASER, MULTIMEDIUM, MEDIUM and PINPOW code system, simulating Angra 1 in the CAOC (constant Axial-Offset Control) operation. Assumming no proplems in the Plant's strecth-out phase, an optimum extension pont of 1 MWd/kg would be attained, what affords an US$700,000 savings by cycle when fuel and operation and maintenance costs are considered. (author) [pt

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

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)

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)

Reactor limitation system improves the safety and availability of the Angra 2 nuclear power plant

International Nuclear Information System (INIS)

Souza Mendes, J.E. de

1987-01-01

Beyond the classic Reactor Protection System and Reactor Control System, nuclear plant Angra 2 has a third system called Reactor Limitation System which combines the intelligence features of the control systems with the high reliability of the protection systems. In determined events, which are not controlled by the control system (e.g.: load rejection, failure of one main reactor coolant pump), the Reactor Limitation System actuates automatically in order to lead the plant to a safe operating condition and so it avoids the actuation of the Reactor Protection System and consequently the reactor trip. This increases safety and availability of the plant and reduces component stresses. After the safe operating condition is reached, the process guidance automatically returns to the control systems. (Author) [pt

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

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

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)

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)

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

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)

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)

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

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

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.

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)

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)

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

The self assessment at ANGRA 1 NPP in Brazil

Energy Technology Data Exchange (ETDEWEB)

Werdine, H Jr [Furnas Centrais Eletricas S.A., Rio de Janeiro (Brazil)

1997-12-31

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.

Atmospherical experiment in Angra I plant for characterizing the effluent transport threw in the atmospheric

International Nuclear Information System (INIS)

Silva Lobo, M.A. da; Kronemberger, B.M.E.

1989-01-01

Available as short communication only. The Environmental Safety Division of the Nuclear Safety and Fuel Department from FURNAS Electric Station S.A. joint with the National Oceanic and Atmospheric Administration (NOAA), achieved a field experiment for characterizing the atmospheric transport and diffusion in the site complex of Angra I Nuclear Power Plant. The complex topography with the thick vegetation and the neighbour building bring problems for the modelling of the effluent transport and the dispersion. The actual meteorological measure system is automatic and compound with four towers. An intensive atmospheric measure with captive balloon is included, and the collected data shows that the site flux is strongly influenced by the topography and insolation. (C.G.C.). 2 figs

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)

A study of the large break loss-of-coolant accident in the Angra-1 nuclear power plant

International Nuclear Information System (INIS)

Borges, E.M.

1984-01-01

The simulation of the Angra-I nuclear power plant under the condition of large break loss of coolant accident is presented, the thermal-hydraulic analysis of the primary circuit during each phase of the acident and thermal analysis of the hottest fuel rod curing reflooding are shown. Computer codes RELAP4/MOD5 (options EM and FLOOD) and TOODEE 2 are used to perform these computations. Fuel rod peak temperatures reached during the simulation are below the permissible levels. However, during the reflooding phase; the maximum oxidation of the cladding exceeds the limit of 0.17 times the original cladding thickness. (Author) [pt

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

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)

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)

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

International Nuclear Information System (INIS)

Werner, F.L.; Frutuoso e Melo, P.F.

2017-01-01

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)

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

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

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)

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

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

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)

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

Energy Technology Data Exchange (ETDEWEB)

Santos, Roberto Carlos dos; Pereira, Iraci Martinez [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil); Justino, Marcelo C.; Silva, Marcos C., E-mail: rcsantos@ipen.br, E-mail: justino@eletronuclear.gov.br [Eletrobrás Termonuclear S.A. (ELETRONUCLEAR), Rio de Janeiro, RJ (Brazil)

2017-07-01

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)

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.

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

Analysis of the metallic containment integrity of Angra I

International Nuclear Information System (INIS)

Costa, J.R.

1981-01-01

The main goal of this work is to evaluate the pressure and temperature long-term behavior inside the metalic containment of a PWR building subjected to a postulated loss-of-coolant accident. The computer program used was CONDRU 4. Calculations were made for Angra I plant assuming the ocurrence of the worst accident to the containment integrity. The results obtained from CONDRU were compared with those from CONTEMPT-LT and COCO, which are codes similar to CONDRU. (Author) [pt

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

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

Modelling and thermal hydraulic analysis of the Angra-2 nuclear reactor using RELAP5-3D code

International Nuclear Information System (INIS)

González Mantecón, Javier

2015-01-01

The evaluation of Nuclear Power Plants (NPPs) performance during steady-state and accident conditions has been one of the main research subjects in the nuclear field. In order to simulate the behavior of water-cooled reactors, several complex thermal-hydraulic codes systems have been developed. Particularly, the RELAP5 code, developed by the Idaho National Laboratory, is a best-estimate thermal-hydraulic analysis tool and one of the most used in nuclear industry. The RELAP5-3D 3.0.0 code was used to develop a detailed model of Angra 2 nuclear reactor using reference data from the Final Safety Analysis Report. Angra 2 is the second Brazilian NPP, which began commercial operation in 2001. The plant is equipped with a Pressurized Water Reactor (PWR) type with 3771.0 MWt. Simulations of the reactor behavior during normal operation conditions and postulated accident conditions were performed. Results achieved in the reactor steady-state simulation were compared with nominal parameters of the NPP. These results proved to be in good agreement, with relative errors less than 1%. In the transient simulation, the obtained results were coherent and satisfactory. This study demonstrates that the RELAP5-3D model is capable to reproduce the thermal-hydraulic behavior of the Angra-2 PWR during diverse operation conditions and it can contribute for the process of the plant safety analysis. (author)

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

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

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)

Atmospherical experiment in Angra I plant for characterizing the effluent transport threw in the atmospheric; Experimento atmosferico no local da Usina Angra I para caracterizar o transporte de efluentes lancados na atmosfera

Energy Technology Data Exchange (ETDEWEB)

Silva Lobo, M.A. da [FURNAS, Rio de Janeiro, RJ (Brazil); Kronemberger, B M.E.

1990-12-31

Available as short communication only. The Environmental Safety Division of the Nuclear Safety and Fuel Department from FURNAS Electric Station S.A. joint with the National Oceanic and Atmospheric Administration (NOAA), achieved a field experiment for characterizing the atmospheric transport and diffusion in the site complex of Angra I Nuclear Power Plant. The complex topography with the thick vegetation and the neighbour building bring problems for the modelling of the effluent transport and the dispersion. The actual meteorological measure system is automatic and compound with four towers. An intensive atmospheric measure with captive balloon is included, and the collected data shows that the site flux is strongly influenced by the topography and insolation. (C.G.C.). 2 figs.

Description of leakage monitoring system at Angra 2 nuclear power plant primary circuit

International Nuclear Information System (INIS)

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

1999-01-01

This paper describes the Leakage Monitoring System installed in Angra 2 NPP. This system has the task of detecting, localizing and quantifying leaks in systems for which rupture preclusion is cited. These systems include the reactor coolant pressure boundary, the main steam and feedwater lines within the containment, and the main steam safety and relief valve station in the valve annex. (author)

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

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

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

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

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

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)

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)

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)

Monitoring nuclear reactors with anti-neutrino detectors: the ANGRA project

Energy Technology Data Exchange (ETDEWEB)

Chimenti, Pietro; Leigui, Marcelo Augusto [UFABC - Universidade Federal do ABC. Rua Santa Adelia, 166. Bairro Bangu. Santo Andre - SP (Brazil); Anjos, Joao; Azzi, Gabriel; Rafael, Gama; Ademarlaudo, Barbosa; Lima, Herman; VAZ, Mario; Villar, Arthur [Centro Brasileiro de Pesquisas Fisicas - CBPF, Rua Dr. Xavier Sigaud, 150, Urca, Rio de Janeiro, RJ - 22290-180 (Brazil); Gonzales, Luis Fernando; Bezerra, Thiago; Kemp, Ernesto [Unicamp, State University of Campinas, Cidade Universitaria ' Zeferino Vaz' , Barao Geraldo - Campinas, Sao Paulo (Brazil); Nunokawa, Hiroshi [Department of Physics, Pontifical Catholic University - PUC, Rua Marques de Sao Vicente, 225, 22451-900 Gavea - Rio de Janeiro - RJ (Brazil); Guedes, Germano; Faria, Paulo Cesar [Universidade Estadual de Feira de Santana - UEFS, Avenida Transnordestina, Novo Horizonte (Brazil); Pepe, Iuri [Universidade Federal da Bahia - UFBA (Brazil)

2010-07-01

We describe the status of the ANGRA Project, aimed at developing an anti-neutrino detector for monitoring nuclear reactors. Indeed the detection of anti-neutrinos provides a unique handle for non-invasive measurements of the nuclear fuel. This kind of measurements are of deep interest for developing new safeguards tools which may help in nuclear non-proliferation programs. The ANGRA experiment, placed at about 30 m from the core of the 4 GW Brazilian nuclear power reactor ANGRA II, is based on a water Cherenkov detector with about one ton target mass. A few thousand antineutrino interactions per day are expected. The latest results from simulations and the status of the construction are presented. (authors)

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

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

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

Realistic analysis of steam generator tube rupture accident in Angra-1 reactor

International Nuclear Information System (INIS)

Fontes, S.W.F.

1989-01-01

This paper presents the analysis of different scenarios for a Steam Generator Tube Rupture accident (SGTR) in Angra-1 NPP. The results and conclusions will be used as support in the preparation of the emergency situation programs for the plant. For the analysis a SGTR simulation was performed with RETRAN-02 code. The results indicated that the core integrity and the plant itself will not affect by small ruptures in SG tubes. For large ruptures the analysis demonstrated that the accident may have harmful consequences if the operator do not actuate effectively since the initial moments of the accidents. (author) [pt

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

Economical analysis of the second partial reload for Angra 1 with partial low-leakage

International Nuclear Information System (INIS)

Mascarenhas, H.A.; Teixeira, M.C.C.; Dias, A.M.

1990-01-01

Preliminary results for the Angra 1 second reload design with partial low-leakage were assessed with NUCOST 1.0, code for nuclear power costs calculation. In the proposed scheme, some partially burned fuel assemblies (FAs) are located at the core boundary, while new FAs occupy more internal positions. The nuclear design - utilizing the code system SAV (from Siemens/KWU Group, F.R. Germany) - has been performed with detail for the 3rd cycle while simpler approach has been utilized for subsequent reloads. Results of NUCOST 1.0 show that the partial low-leakage reload in the 3rd cycle of Angra 1 offers fuel costs 1% lower when compared to the Plant's actual reload scheme, what corresponds to an savings of about US$190.000. When operation and maintenance and capital costs are also considered, economies in the order of US$2.6 million are obrained. (author) [pt

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)

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

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)

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)

OS IMPACTOS AMBIENTAIS E O PROCESSO DE GESTÃO INTEGRADA: EXPERIÊNCIAS NA VILA DE ABRAÃO – ILHA GRANDE, ANGRA DOS REIS (RJ / The Environmental Impacts and The Process of Integrated Management: Experiences in The Vila de Abraão – Ilha Grande, Angra dos Reis (RJ

Directory of Open Access Journals (Sweden)

Sueli Maurício Leal Filha

2006-12-01

Full Text Available The Ilha Grande is situated at the intersection of the parallels 23°05' and 23°14' degrees Southlatitude with the meridians 44°05' and 44°23' West longitude, in Angra dos Reis county, at the Riode Janeiro state Southern coast. It has approximately 193Km² and has two districts, Araçatiba,situated at the western portion whose main villa of residents is Provetá, and Abraão, situated atthe East portion where detaches as the main village the Vila de Abraão. The Vila de Abraão isconsidered the “capital” of the Ilha Grande, where arrive and alter on a daily basis, inhabitants,visitors, public managers, researchers and environmental defenders. The present article considersenvironmental impacts in the Vila de Abraão as important vectors in the construction of managementprocess and territorial planning, mainly after the Island’s change of function - from federal prison(Instituto Penal Cândido Mendes and environmental conservation area it becomes the headoffice of the Centro de Estudos Ambientais e Desenvolvimento Sustentável, a State University ofRio de Janeiro (UERJ unit, which has both an institutional and environmental conservation use,however framed in touristic activity growth context.

Instalation of two emergency diesel groups in Angra-1

International Nuclear Information System (INIS)

Spitalnik, J.; Doria, L.

1990-01-01

As any technology that evolves, nuclear technology is no exception, mainly when new safety conditions of operation, more limited and restricted than previous ones, are introduced to assure increased protection to the public and the environment. NUCLEN has been actively involved in this type of activity in relation with the Angra-1 nuclear power plant. An important example is the Emergency Diesel Project to install in the power plant, two Diesel sets in addition to the existing ones. Experience gathered in this Project has also shown the way local firms, respectively in the fields of design engineering and power plant operation, were able to structure their teams to fulfill successfully a nuclear project both complex and pioneering. This report shows relevant aspects of the Diesel sets project design and erection, with special emphasis on the solution of problems related to the construction of a nuclear facility of the class-1 type, built under both German and US standards. (author) [pt

Santa Cruz thermic plant islanding with local loads

Energy Technology Data Exchange (ETDEWEB)

Nascimento, A R [Light Servicos de Eletricidade SA, Rio de Janeiro, RJ (Brazil); Gomes, Paulo; Almeida, Paulo C. de [ELETROBRAS, Rio de Janeiro, RJ (Brazil); Sereno, Marcos G [FURNAS, Rio de Janeiro, RJ (Brazil)

1988-12-31

This work looks into the feasibility of implementing a scheme for the islanding of the Santa Cruz Thermic Plant ( Rio de janeiro State) with LIGHT`s (Electric power public utility) loads fed by the Santa Cruz-Jacarepagua trunk connection, considering presently-existing system problems relative to a significant frequency drop when a loss occurs of a large generation block and which causes the blockade scheme of the mentioned Plant to work, thus aggravating the frequency control still further. An analysis is made of such scheme implementation implications on the scheme for islanding a Santa Cruz 84 MW machine to provide supply to the auxiliary services of The Angra dos Reis nuclear plant presently existing in the system. 2 refs., 9 figs.

Simulation of a loss of primary coolant accident due to a large break in Angra 2 Nuclear Power Plant with RELAP5/MOD3.2.2G code

International Nuclear Information System (INIS)

Sabunddjian, Gaiane; Andrade, Delvonei Alves de

2003-01-01

This work presents the simulation, with RELAP5/MOD.3.2.2G code, of the postulate accident with loss of coolant in the primary circuit for large break (LBLOCA), which is described in Chapter 15 of the Final Safety Analysis Report of Angra 2 FSAR. The accident consists basically of the total break of the cold leg (Loop 20) of Angra 2 Plant. The rupture area considered is 4418 cm 2 , which represents 100% of the primary circuit pipe flow area. The Emergency Core Cooling System (ECCS) efficiency is also verified for this accident. In this simulation, failure and repair criteria are adopted for the ECCS components, in order to verify the system operation, in carrying out its function as expected by the project to preserve the integrity of the reactor core and to guarantee its cooling. LBLOCA accidents are characterized by a fast blowdown in the primary circuit to values that the low pressure injection system is activated and then, followed by the water injection by the accumulators. The thermal-hydraulic processes inherent to the accident phenomenon, 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 core liquid level, until the ECCS is capable to reflood it. It is important to point out that the results do not represent an independent calculation for the licensing process, but a calculation to give support to the qualification process of Angra 2 transient basic nodalization (author)

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)

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)

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)

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)

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

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

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)

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)

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)

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)

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

Modelling of the tritium dispersion from postulated accidental release of nuclear power plants

International Nuclear Information System (INIS)

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

2011-01-01

This study has the aim to assess the impact of accidental release of tritium postulate from a nuclear power reactor through environmental modeling of aquatic resources. In order to do that it was used computational models to simulation of tritium dispersion caused by an accident in a Candu reactor located in the ongoing Angra 3 site. The Candu reactor is one that uses heavy water (D 2 O) as moderator and coolant of the core. It was postulated, then, the LOCA accident (without fusion), where was lost 66 m3 of soda almost instantaneously. This inventory contained 35 P Bq and was released a load of 9.7 TBq/s in liquid form near the Itaorna beach, Angra dos Reis - RJ. The models mentioned above were applied in two scenarios (plant stopped or operating) and showed a tritium plume with specific activities larger than the reference level for seawater (1.1 MBq/m 3 ) during the first 14 days after the accident. (author)

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

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

Anthropogenic impact on the sedimentation in coastal regions: an example in Saco do Bracui - Ribeira Bay, Angra dos Reis, Brazil; O impacto antropogenico sobre a sedimentacao em regioes costeiras: um exemplo no Saco do Bracui - Baia da Ribeira, Angra dos Reis, Brasil

Energy Technology Data Exchange (ETDEWEB)

Barbosa, Alayde Alfaia

2001-07-01

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{sup 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)

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)

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

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)

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)

Reliabitity study of the accumulator system for Angra-1 reactor

International Nuclear Information System (INIS)

Santos Maciel, C.C.R.

1980-01-01

The realibility of the Accumulator System of Angra 1 reactor is studied. The fault tree techniques is use for identification and evaluation of the probability of occurrence of the possible failure modes of the system. The study has as a guide the report WASH 1400 in which the analysis of the reliability of a Tipical PWR reactor of USA. Comparisons between results obtained for Accumulator System of Angra 1 and that published in the report WASH 1400 for the Accumulator System of the Typical Reactor are done. Critiques to the methodology used in the reportd WASH 1400 and an analysis of the sensitivity of the system in relation with its components are also done. (author) [pt

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.)

Distribution of cysts of Strongyluris sp. (Nematoda) in the pallial system of Achatina fulica Bowdich, 1822 from Vila Dois Rios and Vila do Abraão, Ilha Grande, Angra dos Reis, Rio de Janeiro.

Science.gov (United States)

Oliveira, J L; Santos, S B

2018-04-19

This work aimed to assessing Strongyluris sp. cysts distribution pattern in the several inner organs from pallial system of Achatina fulica Bowdich, 1822. Also we verified if there is a relationship between the mollusk size and the number of specimens from parasites collected from two touristic villages in Ilha Grande (Angra dos Reis, Rio de Janeiro state): Vila Dois Rios (VDR) and Vila do Abraão (ABR). The samples were obtained through a field work conducted bimonthly during 2007, 2008, 2010, and 2011, at both locations. Height and width were measured from shells collected, and the all specimens were classified in different classes: class 1 - biomass and a larger area of the pallial system, allowing an efficient parasite colonization. Other possible explanation could be the long exposure of the molluscs of class 3 to the parasites, which allowed a longer time to the larvae to allocate themselves.

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)

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)

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

International Nuclear Information System (INIS)

Del Pozzo, Andrea Sanchez; Andrade, Delvonei A. de; Sabundjian, Gaiane

2015-01-01

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)

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)

Holistic safety analysis for advanced nuclear power plants

International Nuclear Information System (INIS)

Alvarenga, M.A.B.; Guimaraes, A.C.F.

1992-01-01

This paper reviews the basic methodology of safety analysis used in the ANGRA-I and ANGRA-II nuclear power plants, its weaknesses, the problems with public acceptance of the risks, the future of the nuclear energy in Brazil, as well as recommends a new methodology, HOLISTIC SAFETY ANALYSIS, to be used both in the design and licensing phases, for advanced reactors. (author)

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

International Nuclear Information System (INIS)

Alvarenga, T.A.; Anjos, J.C.; Azzi, G.; Cerqueira, A.S.; Chimenti, P.; Costa, J.A.; Dornelas, T.I.; Farias, P.C.M.A.; Guedes, G.P.; Gonzalez, L.F.G.; Kemp, E.; Lima, H.P.; Machado, R.; Nóbrega, R.A.; Pepe, I.M.; Ribeiro, D.B.S.; Simas Filho, E.F.; Valdiviesso, G.A.; Wagner, S.

2016-01-01

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.

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

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

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.)

Angra 2 small break LOCA flow regime identification through RELAP5 code

Energy Technology Data Exchange (ETDEWEB)

Rocha, Marcelo da Silva; Sabundjian, Gaiane; Belchior Junior, Antonio; Andrade, Delvonei Alves de; Torres, Walmir Maximo; Conti, Thadeu das Neves; Macedo, Luiz Alberto; Umbehaun, Pedro Ernesto; Mesquita, Roberto Navarro de; Masotti, Paulo Henrique Ferraz, E-mail: msrocha@ipen.br, E-mail: gdjian@ipen.br, E-mail: abelchior@ipen.br, E-mail: delvonei@ipen.br, E-mail: wmtorres@ipen.br, E-mail: tnconti@ipen.br, E-mail: lamacedo@ipen.br, E-mail: umbehaun@ipen.br, E-mail: s, E-mail: rnavarro@ipen.br, E-mail: pmasotti@ipen.br [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-RJ), Rio de Janeiro, RJ (Brazil)

2012-07-01

The purpose of this paper is to identify the flow regimes in the core of Angra 2 nuclear reactor with RELAP5/MOD3.2.gamma code (RELAP5, 2001). The postulated accident is the loss of coolant through a small break in the primary circuit (SBLOCA), which is described in Chapter 15 of the Final Safety Analysis Report of Angra 2 - FSAR (ETN, 2006). As the primary circuit pressure decreases due to the loss of coolant, several alternating two phase flow regimes are established in the primary circuit. This paper analyses the coolant two-phase flow behavior in the nuclear reactor core during the postulated accident. (author)

Reliability analysis of Angra I safety systems

International Nuclear Information System (INIS)

Oliveira, L.F.S. de; Soto, J.B.; Maciel, C.C.; Gibelli, S.M.O.; Fleming, P.V.; Arrieta, L.A.

1980-07-01

An extensive reliability analysis of some safety systems of Angra I, are presented. The fault tree technique, which has been successfully used in most reliability studies of nuclear safety systems performed to date is employed. Results of a quantitative determination of the unvailability of the accumulator and the containment spray injection systems are presented. These results are also compared to those reported in WASH-1400. (E.G.) [pt

Structural design of the turbine building of Angra Nuclear Power Station, Unit 1

International Nuclear Information System (INIS)

Varella, L.N.; Reis, F.J.C.; Jurkiewicz, W.J.

1978-01-01

The Turbine Building of the Angra Nuclear Power Plant, Unit 1, and particularly its structure and structural design are described. The Turbine Building, as far as its structure is concerned, deviates from the standard structure of any turbine building due to the fact that huge ducts are provided in the foundation mat as to accomodate the circulating water system. This aspect and the fact that the building is founded upon a very deep strata of compacted and controlled fill, makes out of the building structure 'a concrete ship floating in the sea of sand', and by the same reason presents by itself an interesting structure, worth to be known to all engineers involved in design of power plants. This pape, suplemented by a few slides shown during presentation of the paper at the conference, covers the subject mainly from the designers' point of view. (Author)

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

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)

Case study of the 3D model in ANGRA 3 project

Energy Technology Data Exchange (ETDEWEB)

Faloppa, Altair A., E-mail: afaloppa@ipen.br [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil); Elias, Marcos V., E-mail: mvelias@eletronuclear.gov.br [Eletrobras Termonuclear S.A. (ELETRONUCLEAR), Rio de Janeiro, RJ (Brazil). Departamento GTP-T; Widuch, Lutzian, E-mail: Lutzian.Widuch@areva.com [AREVA GmbH, Engineering Methods and CAD Tools, Erlangen (Germany)

2015-07-01

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)

Some conclusions about the concrete strength of the bored piles of Angra 2 nuclear power plant

International Nuclear Information System (INIS)

Thomaz, E.C.S.; Joia, L.A.

1984-01-01

The concrete of the bored piles of Angra 2 was submitted to a deep control, so more than five thousand core samples were analyzed to verify the quality of the concrete. Based on these samples and using statistics regression theory some conclusions could be done. It was analyzed the dependence of the concrete strength upon the depth of the pile. Also based on these samples some probability distribution functions that could simulate the concrete strength were studied applying the Kolmogorov - Smirnov fitness test. Finally, a method for evaluating a confidence interval of one of the probability function (Weibull distribution) was developed adopting the Monte Carlo simulation technique. (Author) [pt

Incorporation of severe accidents in the licensing of nuclear power plants

International Nuclear Information System (INIS)

Alvarenga, Marco Antonio Bayout; Rabello, Sidney Luiz

2011-01-01

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)

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)

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

Modelling of the tritium dispersion from postulated accidental release of nuclear power plants; Modelagem da dispersao de tritio a partir de liberacoes acidentais postuladas de centrais nucleares

Energy Technology Data Exchange (ETDEWEB)

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

2011-07-01

This study has the aim to assess the impact of accidental release of tritium postulate from a nuclear power reactor through environmental modeling of aquatic resources. In order to do that it was used computational models to simulation of tritium dispersion caused by an accident in a Candu reactor located in the ongoing Angra 3 site. The Candu reactor is one that uses heavy water (D{sub 2}O) as moderator and coolant of the core. It was postulated, then, the LOCA accident (without fusion), where was lost 66 m3 of soda almost instantaneously. This inventory contained 35 P Bq and was released a load of 9.7 TBq/s in liquid form near the Itaorna beach, Angra dos Reis - RJ. The models mentioned above were applied in two scenarios (plant stopped or operating) and showed a tritium plume with specific activities larger than the reference level for seawater (1.1 MBq/m{sup 3}) during the first 14 days after the accident. (author)

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

Three-dimensional simulation of radioactive pollutant in the atmosphere from nuclear power plant

International Nuclear Information System (INIS)

Buske, Daniela; Vilhena, Marco Tullio de

2008-01-01

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)

Palinologia de espécies de Asteraceae de utilidade medicinal para a comunidade da Vila Dois Rios, Ilha Grande, Angra dos Reis, RJ, Brasil Pollen morpology of species of Asteraceae with medicinal utility for the community from Vila Dois Rios, Ilha Grande, Angra dos Reis, Rio de Janeiro State, Brazil

Directory of Open Access Journals (Sweden)

Marcelo Neto Galvão

2009-03-01

Full Text Available O trabalho trata da morfologia polínica e de descrições taxonômicas de 12 espécies de Asteraceae correspondentes em 12 diferentes gêneros, distribuídos em nove tribos. Todas as espécies estudadas são utilizadas como medicamentos pelos moradores da Vila Dois Rios, Ilha Grande, Angra dos Reis, Rio de Janeiro. Neste estudo objetivou-se caracterizar os tipos polínicos das espécies usadas por esta comunidade e fornecer chaves diagnósticas de caracteres macromorfológicos e micromorfológicos que auxiliem a identificação das mesmas. A identificação taxonômica e palinológica correta é pré-requisito para estudos que validem a eficácia e segurança terapêutica dessas espécies. Deve-se considerar, ainda, que a utilização desses conhecimentos é importante para a comunidade, como por exemplo, na melissopalinologia. Os grãos de pólen foram acetolisados, medidos, descritos e ilustrados sob microscopia de luz. Para observar detalhes da superfície e abertura, grãos de pólen não acetolisados foram analisados em microscópio eletrônico de varredura. Foram estudadas as características dos grãos de pólen como forma, tamanho, constituição da sexina e abertura. Os resultados mostraram que a morfologia polínica é bem definida entre as espécies estudadas, podendo ser usada para sua identificação e sustenta o caráter euripalinológico de Asteraceae.This study is a palynologycal characterization and taxonomic description of 12 species within 12 genera, distributed in nine tribes from Asteracaeae. All studied species are used as medicines by people from Vila Dois Rios and they occur in Ilha Grande. This work aimed to characterize the pollen grains of medicinal species of Asteraceae from Vila Dois Rios and provide diagnostic keys based on macromorphological and pollen characters to help their identification, since the correct taxonomic and palynological recognition of these species is necessary for further studies on therapeutic

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)

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

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

Fuel for the next Brazilian nuclear power plants

International Nuclear Information System (INIS)

Lameiras, Fernando S.; Faeda, Kelly Cristina Ferreira

2009-01-01

The conclusion of the Angra III nuclear power plant ends a cycle of the nuclear energy in Brazil that started about forty years ago. Nowadays the country is planning the installation of 4 GWe to 8 GWe of nuclear power up to the year 2030. The nuclear reactors considered for this new cycle should take into account the current technologic development and environment of the nuclear market. They certainly will have significant differences in relation to the Angra I, II, and III reactors. Important impacts may result on the nuclear fuel production chain, e. g., case high temperature reactors were chosen, which can deliver electricity and heat. The differences between the fuels of the candidate reactors after Angra III are analyzed and development lines are suggested to minimize these impacts. (author)

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

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

Micro-organisms and divers exposure to radioactivity in spent fuel pools at nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Muniz de A, D. [Underwater Construction Corporation, Latin America, Fortaleza, Ceara (Brazil); Silva, R. [Universidade Federal do Rio de Janeiro, Instituto de Biofisica Carlos Chagas Filho, 21941-902 Rio de Janeiro (Brazil); Gomes N, C. A., E-mail: dmuniz@uccdive.com [Universidade Federal do Rio de Janeiro, Instituto de Biologia, Environmental Engineering Program, 21941-902 Rio de Janeiro (Brazil)

2017-09-15

Many nuclear power plants (NPPs) around the world are in the process of extending their lifespan from 40 to 60 years of operation. The NPP; Angra 1 (Brazil) has performed a thorough evaluation of its Life Extension Engineering project. In this context, the spent fuel pool (SFP) was one of the areas studied in order to demonstrate the plants integrity for a life extension. Micro-organisms growing on the liner of the fuel transfer channel (Ftc) and SFP can form a film of bacteria, which is highly resistant to radiation. This paper aims to compare the micro-organisms found in NPP Angra 1 with those reported to other NPPs and also relates their occurrence with the radiation levels at the sites. It also compares divers exposure to radioactivity during underwater activities in the SFP. Fourteen samples were collected on the surface of the liners of the Ftc, the SFP and the drains within the fuel building (FB) of Angra 1. For the identification of the micro-organisms, a metagenomics analysis was performed by random sequencing (Shotgun) and the use of Ion Torrent PGM Sequence r. Twelve micro-organisms phyla were identified; Acido-bacteria, Actino-bacteria, Bacteroidetes, Chlamydiae, Chlorobi, Chloroflexi, Cyano-bacteria, Deinococcus-Thermus, Firmicutes, Planctomycetes, Proteo-bacteria, and Verrucomicrobia as well as organisms not classified. In the SFP of Angra 1, the bacteria survived the exposure to a radiation of 0.416 Gy/h (high radiation). Deinococcus-thermus, bacteria identified in Angra 1, has resisted an exposure to 30,000 Gy/h in another plant. (Author)

Micro-organisms and divers exposure to radioactivity in spent fuel pools at nuclear power plants

International Nuclear Information System (INIS)

Muniz de A, D.; Silva, R.; Gomes N, C. A.

2017-09-01

Many nuclear power plants (NPPs) around the world are in the process of extending their lifespan from 40 to 60 years of operation. The NPP; Angra 1 (Brazil) has performed a thorough evaluation of its Life Extension Engineering project. In this context, the spent fuel pool (SFP) was one of the areas studied in order to demonstrate the plants integrity for a life extension. Micro-organisms growing on the liner of the fuel transfer channel (Ftc) and SFP can form a film of bacteria, which is highly resistant to radiation. This paper aims to compare the micro-organisms found in NPP Angra 1 with those reported to other NPPs and also relates their occurrence with the radiation levels at the sites. It also compares divers exposure to radioactivity during underwater activities in the SFP. Fourteen samples were collected on the surface of the liners of the Ftc, the SFP and the drains within the fuel building (FB) of Angra 1. For the identification of the micro-organisms, a metagenomics analysis was performed by random sequencing (Shotgun) and the use of Ion Torrent PGM Sequence r. Twelve micro-organisms phyla were identified; Acido-bacteria, Actino-bacteria, Bacteroidetes, Chlamydiae, Chlorobi, Chloroflexi, Cyano-bacteria, Deinococcus-Thermus, Firmicutes, Planctomycetes, Proteo-bacteria, and Verrucomicrobia as well as organisms not classified. In the SFP of Angra 1, the bacteria survived the exposure to a radiation of 0.416 Gy/h (high radiation). Deinococcus-thermus, bacteria identified in Angra 1, has resisted an exposure to 30,000 Gy/h in another plant. (Author)

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

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)

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

Anticipated simulation of Angra-1 start-up physical tests

International Nuclear Information System (INIS)

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

1981-01-01

Some results foreseen by the Department of Nuclear Fuel (DCN. O) in Furnas for the measurements that will be realized during the start-up integrated tests for Angra-1 are presented. All the forecasting is based on a DCN.O proper correlation methodology, developed from basic physical principles, using computer codes developed by the authors or public computer codes adapted to this methodology. (E.G.) [pt

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.)

Fuel rod thermal analysis of the Angra-1 reactor during a postulated loss of coolant accident

International Nuclear Information System (INIS)

Praes, J.G.L.

1982-01-01

A thermal analysis of a fuel element is performed, as subject to the most severe cooling conditions, such as those occurring during a postulated Loss of Coolant Accident in the Angra-I reactor. Our objective was to ascertain whether the cooling of the core is assured according to 10 CRF - 50. According to the stated purpose, sensitivity analyses are necessary, using the swelling and rupture models of the cladding, and at the same time, an updating of the FLECHT heat transfer correlations in the computing program used, which is TOODEE-2 e 1 Version(28), with the purpose of adequating it to the Angra-I core analysis. In addition, we did sensitivity studies on heat transfer coefficient calculations for the steam cooling model. From the results obtained we conclude that the maximum temperature values of the cladding and the oxidation rate due to the Z sub(r) H 2 O reaction were kept well below the maximum allowable limits. Thus, the cooling of the Angra-I core is assured for the assumed accident. (Author) [pt

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

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.

Utilization of DRUFAN 01/MOD 02 computer code for the depressurization phase analysis of a postulated loss of coolant accident in Angra 2/3 Nuclear Power Plants

International Nuclear Information System (INIS)

Austregesilo Filho, H.; Figueiredo, P.J.M.

1985-08-01

The DRUFAN 01/Mod 2 developed by Gesellschaft fur Reaktorsicherheit (GRS) mbh to simulate thermohydraulic behavior of the primary circuit of PWR reactors, during the despressurization phase and initial refilling phase of loss of coolant accidents by great ruptures, is presented. The program simulates the system to be analysed by control volumes-concentrated parameters model - and it is based on numerical solution of conservation equations for mass of water, mass of vapor, quantities of motion and energy, and on the control volume homogeneity hypothesis. The possibilities of thermodynamic disequilibrium, determining mass transfer between liquid and vapor phases assuming that one saturated phase, are considered. The process of computer code implantation in the Honeywell Bull 64 DPS 7 system at CNEN, the modifications done into the program and the application to the despressurization phase analysis of a loss of coolant accident at Angra-2 and Angra-3 reactors are considered. (M.C.K.) [pt

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

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

Experience of analysis of the operational occurrences in Angra-1 during the commissioning phase

International Nuclear Information System (INIS)

Praes, J.G.L.; Borba, P.R.; Collussi, I.

1984-01-01

It is presented a methodology and analysis to determine the importance level of the operational occurences. It is included a description and evaluation of a operational occurence in Angra-1 during the commissioning. (M.C.K.) [pt

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)

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

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

Frequency probabilistic analysis of a small break LOCA due to a power operated relief valve (PORV) for Angra-1 pre-TMI and post-TMI

International Nuclear Information System (INIS)

Onusic Junior, J.

1986-01-01

After the TMI event efforts were aimed towards improvements in the operational and administrative procedures related to the power operated relief valves (PORVs) in order to decrease the probability of a small-break loss-of-coolant accident (LOCA) caused by stuck-open power operated relief valve. This paper presents a frequency probabilistic analysis of a small break LOCA due to a stuck open PORV and safety valve to the Angra I nuclear power plant in operating conditions pre-TMI and post-TMI. (Author) [pt

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

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

The utilization of Quabox/Cubox computer program for calculating Angra 1 Reactor core

International Nuclear Information System (INIS)

Pina, C.M. de.

1981-01-01

The utilization of Quabox/Cubox computer codes for calculating Angra 1 reactor core is studied. The results shows a dependency between the spent CPU time and the curacy of thermal power distribution in function of the polinomial expansion used. Comparison were mode between Citation code and some results from Westinghouse [pt

Choosing the best meteorological conditions for atmospheric diffusion experiments at the Angra site

International Nuclear Information System (INIS)

Nicolli, D.; Thomas, P.

1983-01-01

The most appropriate meteorological conditions and time of the day advisable for carrying out diffusion experiments at the Angra site are described. Two emission points were defined, and the sampling area was determined with easy access to the complex terrain taken into consideration. The onsite meteorological measuring system is briefly described. (Author) [pt

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

Analysis of the rod drop accident for Angra-1

International Nuclear Information System (INIS)

Veloso, M.A.; Atayde, P.A.

1989-01-01

The aim of this work is to present a rod drop accident analysis for the third cycle of the Angra-1 nuclear power plant operating in the automatic control mode. In this analysis all possible configurations for dropped rods caused by a single failure in the controller circuits have been considered. The dropped rod worths, power distributions and excore detector tilts were determined by using the Siemens/KWU neutronic code system, in particular the MEDIUM2, PINPOW and DETILT codes. The transient behaviour of the plant during the rod drop event was simulated with the SACI2/MOD0 code, developed at CDTN. Determinations related to the DNBR design limit were conducted by utilizing the CDTN PANTERA-1P subchannel code. The transient analysis indicated that for dropped rod worths greater than about 425 pcm reactor trip from negative neutron flux rate will take place independently of core conditions. In the range from 0 to 425 pcm large power overshoots may occur as a consequence of the automatic control system action. The magnitude of the maximum power peaking during the event increases with the dropped rod worth, as far as the control bank is able to compensate the initial reactivity decrease. Thermal-hydraulic evaluations carried out with the PANTERA-1P code show that for all the relevant dropped rod worths the minimum DNBR will remain above a limit value of 1.365. Even if this conservative limit is met, the calculated nuclear power peaking factors, F N AH , will be at least 6% higher than the allowable F N AH -values. Therefore, the DNBR design margin will be preserved at the event of rod drop. (author)

A general advection-diffusion model for radioactive substance dispersion released from nuclear power plants

International Nuclear Information System (INIS)

Buske, D.

2011-01-01

The present contribution focuses on the question of radioactive material dispersion after discharge from a nuclear power plant in the context of micro-meteorology, i.e. an atmospheric dispersion model. The advection-diffusion equation with Fickian closure for the turbulence is solved for the atmospheric boundary layer where the eddy diffusivity coefficients and the wind profile are assumed to be space dependent. The model is solved in closed form using integral transform and spectral theory. Convergence of the solution is discussed in terms of a convergence criterion using a new interpretation of the Cardinal Theorem of Interpolation theory and Parseval's theorem. The solution is compared to other methods and model adequacy is analyzed. Model validation is performed against experimental data from a controlled release of radioactive material at the Itaorna Beach (Angra dos Reis, Rio de Janeiro state, Brazil, 1985). (author)

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)

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

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

Adjustments in Almod3W2 transient analysis code to fit Angra 1 NPP experimental data

International Nuclear Information System (INIS)

Madeira, A.A.; Camargo, C.T.M.

1988-01-01

Some little modifications were introduced in ALMOD3W2 code, as consequence of the interest in reproducing the full load rejection test in Angra 1 NPP. Such modifications showed to be adequate when code results were compared with experimental data. (author) [pt

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)

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

Energy Technology Data Exchange (ETDEWEB)

Gomes, Many R.S.; Melo, Paulo F.F.F. e, E-mail: mgomes@con.ufrj.br, E-mail: frutuoso@nuclear.ufrj.br [Universidade Federal do Rio de Janeiro (UFRJ), RJ (Brazil). Programa de Pos-Graduacao em Engenharia Nuclear

2015-07-01

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)

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

Structural analysis strategies of the pressurized relief and safety valves discharge piping of NPP Angra 1

International Nuclear Information System (INIS)

Lima, Maria Ines Prates de; Kuramoto, Edson; Suanno, Rodolfo

2002-01-01

The pressurizer relief and safety valve system provides the reactor coolant system overpressure protection and, therefore, it is fundamental for the security of a nuclear plant. This paper discusses the safety valve loop seal strategies adopted by others nuclear power plants over the world in order to attend the recommendations of NUREG-0578 (TMI-2 Lessons Learned Task Force Status Report and Short Term Recommendations). The technical option adopted for Angra 1 consists in making specific modifications on the original piping and support configuration of the pressurizer relief and safety valve system. These modifications were proposed in order to reduce the high stress levels induced by the thermal-hydrodynamic loads caused by the discharge of the sub-cooled water during the opening of the relief or the safety valves. Several thermal-hydraulic models were tested to assess the influence of the seal water heating and the simultaneous opening of the valves in order to minimize the thermal hydrodynamic loads effects. The piping structural analysis was performed, using the computer program system KWUROHR, to satisfy the requirements of the appropriate equations of the code ASME Section III, Subsections NB3650 and NC3650. (author)

Modelling for great breaks accident analysis in the primary system of Angra 1 reactor

International Nuclear Information System (INIS)

Serrano, M.A.B.; Vanni, E.A.

1981-01-01

An analysis is made for a break in the cold leg, of the guillotine type with discharge coefficient C sub(D)=1.0, for the Angra 1 reactor. The computer codes, geometrical models and options used are described. A comparison between the method used and the requirements in the Appendix K of 10 CRF 50 is done. (Author) [pt

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

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

PD and I works to improve the waste solidification performance of Angra 1

International Nuclear Information System (INIS)

Tello, Cledola C.O. de; Gomes, Nelson J.P.O.

2009-01-01

Angra 1 Power Plant is the first Brazilian NPP, and started its commercial operation in 1985. The wastes from its operation are spent ion exchange resins, expended filter cartridges, boric acid evaporator concentrates; and solid wastes such as gloves, cleaning tools, plastics and protective clothing. Liquid waste streams are treated by evaporation to reduce the volume, and the concentrate is solidified in cement. The original cementation unit was designed to meet the US product acceptance criteria of the early seventies, when environmental and safety requirements were less restrictive than now. This system had a very low efficiency, and the waste product quality was very poor. A new solidification plant was bought, and R and D project was carried out to study and develop a suitable cementation process and the PCP - process control program - to guarantee the licensing of the plant and maximize its efficiency using Brazilian materials. To accomplish these objectives, a huge amount of experiments were carried on. Tests were performed to determine the main properties of the process and the product, e.g. the workability, set time, compressive strength (stress resistance) and leachability. After reaching the established parameters, the mixture system was optimized. The paddle and container designs were modified and also the motor specifications, so that the process efficiency could be improved. The performance of this new system is increased allowing solidifying from 56 till 69% in volume of waste, much better in comparison of the old one, whose maximum value was about 20%. (author)

Safety analysis of nuclear power plants

International Nuclear Information System (INIS)

Selvatici, E.

1981-01-01

A study about the safety analysis of nuclear power plant, giving emphasis to how and why to do is presented. The utilization of the safety analysis aiming to perform the licensing requirements is discussed, and an example of the Angra 2 and 3 safety analysis is shown. Some presented tendency of the safety analysis are presented and examples are shown.(E.G.) [pt

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

Development of a mobile game based on virtual reality tools to sensitize the population about the nuclear power plant's emergency plan

Energy Technology Data Exchange (ETDEWEB)

Ferreira, Lucas H.H.; Mol, Antônio C. de A.; Santo, André C. do E.; Legey, Ana Paula [Instituto de Engenharia Nuclear (IEN/CNEN-RJ), Rio de Janeiro, RJ (Brazil); Centro Universitário Carioca (Unicarioca), Rio de Janeiro, RJ (Brazil)

2017-07-01

The Angra dos Reis Nuclear Power Plant's emergency plan, it is the bunch of instructions that every citizen must adopt in case of an emergency situation. It is highly important, that all the people living in the power plant's surroundings truly understand every single step of the plan, because only in this way people will know how to react in case of a necessity. To hit this goals, the Brazil's Electronuclear, made educational booklets, in the shape of comic books, trying to guide the population about the plan. On the other hand, we have an increasingly connected world, making possible that digital games, be very well accepted by the population. So this project has as an objective, developing a digital tool, in form of a mobile game that shows in a playful and interactive way for the user, the emergency plan, complementing the educational process and social actions made by many institutions. With the information taken from the booklets, objects and buildings were modeled in Autodesk 3Ds Max, allied with the Unity 3D Game Engine, to make a city, inspired in Angra do Reis (RJ). The player has to follow all the security protocols giving by the Eletronuclear according with the rules provided by the National Nuclear Energy Commission. Is expected, with this game that will be available for the Eletronuclear that more people have the chance to know and believe in the efficiency of the emergency plan already established. (author)

Development of a mobile game based on virtual reality tools to sensitize the population about the nuclear power plant's emergency plan

International Nuclear Information System (INIS)

Ferreira, Lucas H.H.; Mol, Antônio C. de A.; Santo, André C. do E.; Legey, Ana Paula

2017-01-01

The Angra dos Reis Nuclear Power Plant's emergency plan, it is the bunch of instructions that every citizen must adopt in case of an emergency situation. It is highly important, that all the people living in the power plant's surroundings truly understand every single step of the plan, because only in this way people will know how to react in case of a necessity. To hit this goals, the Brazil's Electronuclear, made educational booklets, in the shape of comic books, trying to guide the population about the plan. On the other hand, we have an increasingly connected world, making possible that digital games, be very well accepted by the population. So this project has as an objective, developing a digital tool, in form of a mobile game that shows in a playful and interactive way for the user, the emergency plan, complementing the educational process and social actions made by many institutions. With the information taken from the booklets, objects and buildings were modeled in Autodesk 3Ds Max, allied with the Unity 3D Game Engine, to make a city, inspired in Angra do Reis (RJ). The player has to follow all the security protocols giving by the Eletronuclear according with the rules provided by the National Nuclear Energy Commission. Is expected, with this game that will be available for the Eletronuclear that more people have the chance to know and believe in the efficiency of the emergency plan already established. (author)

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)

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

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

Adaptation of Toodee-2 computer code for reflood analysis in Angra-1 reactor

International Nuclear Information System (INIS)

Praes, J.G.L.; Onusic Junior, J.

1981-01-01

A method of calculation the heat transfer coefficient used in Toodee-2 computer code for core reflood analysis in a loss of coolant accident, is presented. Preliminary results are presented with the use of heat transfer correlations based on FLECHT experiments adequate to a geometric arrangement such as 16 x 16 (Angra I). Optional calculations are suggested for the heat transfer coefficients when the cooling of fuel cladding by steam is used. (Author) [pt

Aging effects in PWR power plants components

Energy Technology Data Exchange (ETDEWEB)

Borges, Diogo da S.; Guimaraes, Antonio C.F.; Moreira, Maria de Lourdes, E-mail: diogosb@outlook.com, E-mail: tony@ien.gov.br, E-mail: malu@ien.gov.br [Instituto de Engenharia Nuclear (IEN/CNEN-RJ), Rio de Janeiro, RJ (Brazil)

2013-07-01

This paper presents a contribution to the study of aging process of components in commercial plants of Pressurized Water Reactors (PWRs). The analysis is made through application of the Fault Trees Method, Monte Carlo Method and Fussell-Vesely Importance Measure. The approach of the study of aging in nuclear power plants, besides giving attention to the economic factors involved directly with the extent of their operational life, also provide significant data on security issues. The latest case involving process of life extension of a PWR could be seen in Angra 1 Nuclear Power Plant through investing of $27 million for the installation of a new reactor lid. The corrective action has generated an estimated operating life extension of Angra I in twenty years, offering great economy compared with building cost of a new plant and anterior decommissioning, if it had reached the time operating limit of forty years. The Extension of the operating life of a nuclear power plant must be accompanied by a special attention to the components of the systems and their aging process. After the application of the methodology (aging analysis of the injection system of the containment spray) proposed in this work, it can be seen that 'the increase in the rate of component failure, due the aging process, generates the increase in the general unavailability of the system that containing these basic components'. The final results obtained were as expected and may contribute to the maintenance policy, preventing premature aging process in Nuclear Plant Systems. (author)

Modeling of the dispersion of tritium from postulated accidental releases from nuclear power plants

International Nuclear Information System (INIS)

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

2013-01-01

This study has the aim to assess the impact of accidental release of tritium postulate from a nuclear power reactor through environmental modeling of aquatic resources. In order to do that it was used computational models of hydrodynamics and transport for the simulation of tritium dispersion caused by an accident in a CANDU reactor located in the ongoing Angra 3 site. It was postulated, then, the LOCA - Loss of Coolant Accident -, accident in the emergency cooling system of the nucleus ( without fusion), where was lost 66m 3 of soda almost instantaneously. This inventory contained 35 PBq and was released a load of 9.7 TBq/s in liquid form near the Itaorna beach, Angra dos Reis - RJ. The models mentioned above were applied in two scenarios ( plant stopped or operating) and showed a tritium plume with specific activities larger than the reference level for seawater (1.1MBq/m 3 ), during the first 14 days after the accident. The main difference between the scenario without and with seawater recirculation (pumping and discharge) is based on the enhancement of dilution of the highest concentrations in the last one. This dilution enhancement resulting in decreasing concentrations was observed only during the first two weeks, when they ranged from 1x10 9 to 5x10 5 Bq/m 3 close to the Itaorna beach spreading just to Sandri Island. After 180 days, the plume could not be detected anymore in the bay, because their activities would be lower than the minimum detectable value ( 3 ). (author)

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)

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)

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

First atmospheric diffusion experiment compaign at the Angra site. Analysis of the data measured

International Nuclear Information System (INIS)

Nicolli, D.

1986-07-01

An analysis of the data measured during the first atmospheric diffusion experiment campaign at the Angra site is presented. Some time before the diffusion experiments, with tritiated water vapor used as a tracer (HTO) could be started, many preparatory studies had to be concluded due to the local complex terrain surrounded by steep hills on three sides and a bay in the southern direction. An introductory account of these previous steps is given. Tritiated water vapor was released from a 100m-high tower and air humidity sampled at 25 locations as far as 1Km downwind of the source. An elaborated isoconcentration analysis indicates the plume spread has a Gaussian distribution in the horizontal plane up to the edge of the site's area bordered by the hill's top (about 1Km far-off). Nevertheless the Gaussian model has a restricted applicability at some parts of the site because of the terrain unevenness. In general, the results are comparable to those obtained in other countries for complex terrain. Meanwhile, the Angra's experiments seem only to validate the Gaussian model for short range dispersion from an elevated source. For releases in the lowest layer, the Gaussian model might not be valid. The isoconcentration analysis strengthens the assumption of sea breeze recirculation on the site. (Author) [pt

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)

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)

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

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)

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)

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

Initiating events in the safety probabilistic analysis of nuclear power plants

International Nuclear Information System (INIS)

Stasiulevicius, R.

1989-01-01

The importance of the initiating event in the probabilistic safety analysis of nuclear power plants are discussed and the basic procedures necessary for preparing reports, quantification and grouping of the events are described. The examples of initiating events with its occurence medium frequency, included those calculated for OCONEE reactor and Angra-1 reactor are presented. (E.G.)

The CONNIE experiment

Energy Technology Data Exchange (ETDEWEB)

Aguilar-Arevalo, A.; et al.

2016-10-19

The CONNIE experiment uses fully depleted, high resistivity CCDs as particle detectors in an attempt to measure for the first time the Coherent Neutrino-Nucleus Elastic Scattering of antineutrinos from a nuclear reactor with silicon nuclei.This talk, given at the XV Mexican Workshop on Particles and Fields (MWPF), discussed the potential of CONNIE to perform this measurement, the installation progress at the Angra dos Reis nuclear power plant, as well as the plans for future upgrades.

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)

Public relations policy: The Electronuclear experience

International Nuclear Information System (INIS)

Soares, Luiz

2000-01-01

This presentation discusses the following topics: Historical and Cultural Aspects of Electrical Sector in Brazil; Nuclear Power and Public Acceptance in Brazil; The chances decision of Angra 3; Community Activities of the ELETRONUCLEAR Regional Programs and Emergency Planning Department whose function is to promote activities with or for the communities of Angra dos Reis region; Public Relations Actions

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)

Study of a proposal for the insertion of operational experience as a tool for support the training plan for nuclear power plants

International Nuclear Information System (INIS)

Fonseca, Renato Alves da

2009-05-01

The main objectives of this work are: to determine, through the operational experience analysis of Angra 1 nuclear power plant, the plant operational vulnerabilities that affect its staff training and to propose a modeling to plan a training program to address these vulnerabilities. This analysis utilizes the Angra 1 document entitled 'Ocorrencia de Relato Obrigatorio', which reports the plant event occurrences. Through this document, as well as the opinion of specialists on the most probably root causes of the reported events, the backdrop of the operational experience analysis of internal events was built. The modeling using the SAT method and has as a guideline the internal operational experience analysis. Moreover, this modeling encompasses techniques of event and second generation human reliability analysis, both specific of the nuclear area. The development of this work shows that: the internal operational experience analysis provides a realistic view of the vulnerabilities present in the plant in all areas (technical and organizational), which must be addressed to the plan of the training program and the modeling, based on realistic view of the plant, is dynamic, not linear, and is always up to date on events in the plant, its causes and consequences. (author)

Modelling of tritium dispersion from postulated accidental release of nuclear power plants

International Nuclear Information System (INIS)

Soares, Abner Duarte

2010-01-01

This study has the aim to assess the impact of accidental release of tritium postulate from a nuclear power reactor through environmental modeling of aquatic resources. In order to do that it was used computational models of hydrodynamics and transport for the simulation of tritium dispersion caused by an accident in a CANDU reactor located in the ongoing Angra 3 site. This exercise was accomplished with the aid of a code system (SisBAHIA) developed in the Rio de Janeiro Federal University (COPPE/UFRJ). The CANDU reactor is one that uses heavy water (D 2 O) as moderator and coolant of the core. It was postulated, then, the LOCA (Loss of Coolant Accident) accident in the emergency cooling system of the nucleus (without fusion), where was lost 66 m 3 of soda almost instantaneously. This inventory contained 35 PBq and was released a load of 9.7 TBq/s in liquid form near the Itaorna beach, Angra dos Reis - RJ. The models mentioned above were applied in two scenarios (plant stopped and operating) and showed a tritium plume with specific activities larger than the reference level for seawater (1.1 MBq/m 3 ) during the first 14 days after the accident. The main difference between the scenario without and with seawater recirculation (pumping and discharge) is based on the enhancement of dilution of the highest concentrations in the last one. This dilution enhancement resulting in decreasing concentrations was observed only during the first two weeks, when they ranged from 1x10 9 to 5x10 5 Bq/m 3 close to the Itaorna beach spreading just to Sandri Island. After 180 days, the plume could not be detected anymore in the bay, because their activities would be lower than the minimum detectable value ( 3 ). (author)

Leishmaniose tegumentar americana na Ilha Grande. Rio de Janeiro: V. Observações sobre a biologia dos transmissores em condiçoes naturais

Directory of Open Access Journals (Sweden)

Nelson A. de Araújo Filho

1981-12-01

Full Text Available Durante um surto de Leishmaniose Tegumentar Americana (LTA na Praia Vermelha, Ilha Grande, município de Angra dos Reis, Rio de Janeiro, foram coletados 4.192 exemplares de flebotomíneos em ambiente domiciliar e silvestre, com isca animal e outros abrigos naturais, durante o período de janeiro de 1976 a abril de 1977. Entre o total de 11 espécies coletadas encontraram-se 2.493 exemplares de Lutzomyia intermedia, 1.594 de Lutzomyia migonei e 105 exemplares de outras espécies. A L. intermedia apresentou densidade mais elevada no domicílio humano, enquanto a L. migonei apresentou coletas mais rendosas com iscas animais e galinheiros. O sinantropismo e a elevada densidade no ambiente domiciliar incriminam as espécies L. intermedia e L. migonei como as prováveis vetoras da LTA na Ilha Grande.During an outbreak of mucocutaneous leishmaniasis in Praia Vermelha, Ilha Grande (Great Island in the county of Angra dos Reis, State of Rio de Janeiro, 4.192 species of Phlebotomus were collected in domestic and wild environment with the use of animal baits and other natural shelters from January 1976 to April 1977. In a total of 11 species collected, 2.493 samples of Lutzomyia intermedia, 1.594 of Lutzomyia migonei and 105 samples of other species were found. The Lutzomyia intermedia presented a higher density in human dwellings, while the Lutzomyia migonei presented better results with animal baits and chicken-coops. The sinantropism and high density found in the houses incriminate the species L. intermedia and L. migonei as the probable vectors of Mucocutaneous Leishmaniasis in Ilha Grande.

Computer codes for simulation of Angra 1 reactor steam generator

International Nuclear Information System (INIS)

Pinto, A.C.

1978-01-01

A digital computer code is developed for the simulation of the steady-state operation of a u-tube steam generator with natural recirculation used in Pressurized Water Reactors. The steam generator is simulated with two flow channel separated by a metallic wall, with a preheating section with counter flow and a vaporizing section with parallel flow. The program permits the changes in flow patterns and heat transfer correlations, in accordance with the local conditions along the vaporizing section. Various sub-routines are developed for the determination of steam and water properties and a mathematical model is established for the simulation of transients in the same steam generator. The steady state operating conditions in one of the steam generators of ANGRA 1 reactor are determined utilizing this programme. Global results obtained agree with published values [pt

Experience report: a training center for health response

International Nuclear Information System (INIS)

Maurmo, Alexandre M.; Leite, Teresa C.S.B.

2009-01-01

The Professor Nelson Valverde Training Center was created within FEAM (The ELETRONUCLEAR Medical Assistance Foundation) with the objective of capacitating Radio Nuclear Accident Responders for the Health Area in the Almirante Alvaro Alberto Nuclear Central (Angra dos Reis - RJ - Brazil). The first step was structuring the contents for this training using IAEA's Manuals as base (EPR Medical - 2005, EPR First Responders - 2006 and TMT - Handbook - 2009) and data from REAC/TS. The second step was to capacitate instructors. The third step was the integration with the Company's Radiological Protection Division, giving radiological assessment. Finally, the development of training applications, ending with Drills, Tests and Assessment, gathering data and suggestions, objectifying the constant improvement. Training Programs with pre and post evaluations have been started. Since 2004 training internal courses were ministered for 125 professionals with annual re-training and were ministered to 130 professionals from several external institutions. During the same period training courses were ministered to 140 trainees from the Radiological Protection Division of The Nuclear Power Plant of Angra dos Reis, as First Lay Responders, objectifying the improvement of the quality of the emergency response. (author)

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

137Cs, 60Co and 125I bioaccumulation by seaweeds from the Angra dos Reis nuclear power plant region

International Nuclear Information System (INIS)

Guimaraes, J.R.; Penna-Franca, E.

1985-01-01

As part of a broad research program on the behaviour of critical radionuclides to be discharged into the sea by the first Brazilian nuclear power plant, the uptake, accumulation and loss of 137 Cs, 60 Co and 125 I by locally abundant seaweed species was studied. Uptake in static 12 liter aquarium experiments reached apparent steady-state in 2 to 7 days ( 60 Co and 125 I), or 2 to 3 weeks ( 137 Cs). Elimination followed a reverse pattern, being comparatively fast for 137 Cs and slow for 60 Co and 125 I. Dry weight bioaccumulation factors (BFs) were variable, falling in the 10 1 range for 137 Cs, 10 3 for 125 I and 10 3 to 10 4 for 60 Co. Various short-term experiments, performed over a 16 month period, showed marked temporal variations of 60 Co BFs for all species. The results demonstrated that the studied species may play an important role in the transfer of the critical radionuclides through local food webs and can be employed as useful monitors for routine or accidental radionuclide releases. (author)

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)

Time response prediction of Brazilian Nuclear Power Plant temperature sensors using neural networks

Energy Technology Data Exchange (ETDEWEB)

Santos, Roberto Carlos dos; Pereira, Iraci Martinez, E-mail: rcsantos@ipen.br [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

2011-07-01

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)

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)

Nuclear power plants documentation system

International Nuclear Information System (INIS)

Schwartz, E.L.

1991-01-01

Since the amount of documents (type and quantity) necessary for the entire design of a NPP is very large, this implies that an overall and detailed identification, filling and retrieval system shall be implemented. This is even more applicable to the FINAL QUALITY DOCUMENTATION of the plant, as stipulated by IAEA Safety Codes and related guides. For such a purpose it was developed a DOCUMENTATION MANUAL, which describes in detail the before mentioned documentation system. Here we present the expected goals and results which we have to reach for Angra 2 and 3 Project. (author)

Upper nozzle welding development transfer of Angra 2/00 fuel element to F.E.C. (Fabrica de Elemento Combustivel)

International Nuclear Information System (INIS)

Lorenzo, R.F. di; Almeida, R.C.

1985-01-01

The technology development of upper nozzle welding of Angra-2 Combustible element, done at CDTN (Centro de Desenvolvimento da Tecnologia Nuclear), this technology transfer to FEC (Fabrica de Elemento Combustivel), the welders training of FEC in nozzle welding, the radiographic control of nozzle welds and the FEC personnel training in this nozzle welds radiography are presented is this report. (C.M.) [pt

Extension of cycle 8 of Angra-1 reactor, optimization of electric power generation reduction

International Nuclear Information System (INIS)

Miranda, Anselmo Ferreira; Moreira, Francisco Jose; Valladares, Gastao Lommez

2000-01-01

The main objective of extending fuel cycle length of Angra-1 reactor, is in fact of that each normal refueling are changed about 40 fuel elements of the reactor core. Considering that these elements do not return for the reactor core, this procedure has became possible a more gain of energy of these elements. The extension consists in, after power generation corresponding to a cycle burnup of 13700 MWD/TMU or 363.3 days, to use the reactivity gain by reduction of power and temperature of primary system for power generation in a low energy patamar

Study of low leakage reload schedulle without burnable posion for Angra-1

International Nuclear Information System (INIS)

Sakai, M.; Dias, A.

1989-01-01

At the moment, there is a world trend to design larger cycles for PWR. Then the reload batches are increased, the enrichment in 235 U is increased and/or advanced fuel management strategies with radial low neutron leakage are applied. For the low leakage reloads of Angra-1 calculations were performed for different number of fuel assemblies for reaload batch, 32,36,40,44 and 48, from the 4th cycle up to equilibrium cycle for two different enrichments 3,4 W/O and 3,9 W/O in 235 U. The results showed that for the enrichments used without burnable posion it is possible to reach an increase in cycle lenghts between 3% and 8% for the same conditions. (author) [pt

Transit and absorption of nuclear industry derivatives by marine biota

International Nuclear Information System (INIS)

Mayr, L.; Moraes, R.; Lopes, M.A.; Vicente, C.; Mauro, J.N.

1988-01-01

A broard research program on radionuclides became necessary due to the construction of the Nuclear Power Plant at Angra dos Reis. As part of this program the research developped by the Marine Biology Departament, UFRJ, aimed at estimating the radiation doses to wich the population of the region might be exposed and to determine biological indicators to radioactive contamination. Up to the present moment, the bioacumulation factors (BFs) of 60 Co, 137 Cs and 131 I by ''clam'' (Anomalocardia brasiliana) and the biological half-life of cobalt and cesium in this animal were determined, as well as the B.F. of 85 Sr by ''snail'' (Strombus pugilis) and by ''barnacle'' (Megabalanus tintinnabulum). The remobilization of 60 Co by microbiological activity in marine sediment was also studied. These studies were made using the standard methodology for bioaccumulation and elimination in closed water systems. The results showed an important microbiological activity in the remobilization of elements in the sediment. Due to the low bioaccumulation factors obtained the studied organisms were not considered ideal biological indicators for radioactive pollution. However, their importance as edible animals in the Angra dos Reis region recommends their radiometry for routine radiological monitoring. Studies on other organisms and/or radionuclides are now in progress at the Marine Biology Departament (UFRJ). (author) [pt

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)

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 "2"3"2thorium is a fertile nuclide with the ability to convert into "2"3"3uranium, 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 "2"3"3uranium, the emergence of "2"3"1protactinium (an isotope that only occurs as a fission product of "2"3"2Th) 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)

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.

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

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

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

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

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

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

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

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

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

Modelling of tritium dispersion from postulated accidental release of nuclear power plants; Modelagem da dispersao de tritio a partir de liberacoes acidentais postuladas de centrais nucleares

Energy Technology Data Exchange (ETDEWEB)

Soares, Abner Duarte

2010-07-01

This study has the aim to assess the impact of accidental release of tritium postulate from a nuclear power reactor through environmental modeling of aquatic resources. In order to do that it was used computational models of hydrodynamics and transport for the simulation of tritium dispersion caused by an accident in a CANDU reactor located in the ongoing Angra 3 site. This exercise was accomplished with the aid of a code system (SisBAHIA) developed in the Rio de Janeiro Federal University (COPPE/UFRJ). The CANDU reactor is one that uses heavy water (D{sub 2}O) as moderator and coolant of the core. It was postulated, then, the LOCA (Loss of Coolant Accident) accident in the emergency cooling system of the nucleus (without fusion), where was lost 66 m{sup 3} of soda almost instantaneously. This inventory contained 35 PBq and was released a load of 9.7 TBq/s in liquid form near the Itaorna beach, Angra dos Reis - RJ. The models mentioned above were applied in two scenarios (plant stopped and operating) and showed a tritium plume with specific activities larger than the reference level for seawater (1.1 MBq/m{sup 3} ) during the first 14 days after the accident. The main difference between the scenario without and with seawater recirculation (pumping and discharge) is based on the enhancement of dilution of the highest concentrations in the last one. This dilution enhancement resulting in decreasing concentrations was observed only during the first two weeks, when they ranged from 1x10{sup 9} to 5x10{sup 5} Bq/m{sup 3} close to the Itaorna beach spreading just to Sandri Island. After 180 days, the plume could not be detected anymore in the bay, because their activities would be lower than the minimum detectable value (< 11 kBq/m{sup 3}). (author)

Design study of a PWR of 1.300 MWe of Angra-2 type operating in the thorium cycle

International Nuclear Information System (INIS)

Andrade, E.P.; Carneiro, F.A.N.; Schlosser, G.J.

1984-01-01

The utilization of the thorium-highly enriched uranium and thorium-plutonium mixed oxide fuels in an unmodified PWR is analysed. The PWR of 1300 MWe from KWU (Angra-2 type) is taken as the reference reactor for the study. Reactor core design calculations for both types of fuels considering once-through and recycle fuels. The calculations were performed with the KWU design codes FASER-3 and MEDIUM 2.2 after introduction of the thorium chain and some addition of nuclide data in FASER-3. A two-energy group scheme and a two-dimensional (XY) representation of the reactor core were utilized. (Author) [pt

Risk-based evaluation of allowed outage time and surveillance test interval extensions for nuclear power plants

International Nuclear Information System (INIS)

Gibelli, Sonia Maria Orlando

2008-03-01

The main goal of this work is, through the use of Probabilistic Safety Analysis (PSA), to evaluate Technical Specification (TS) Allowed Outage Times (AOT) and Surveillance Test Intervals (STI) extensions for Angra 1 nuclear power plant. PSA has been incorporated as an additional tool, required as part of NPP licensing process. The risk measure used in this work is the Core Damage Frequency (CDF), obtained from the Angra 1 PSA Level 1. AOT and STI extensions are calculated for the Safety Injection System (SIS), Service water System (SAS) and Auxiliary Feedwater System (AFS) through the use of SAPHIRE code. In order to compensate for the risk increase caused by the extensions, compensatory measures as test of redundant train prior to entering maintenance and staggered test strategy are proposed. Results have shown that the proposed AOT extensions are acceptable for the SIS and SAS with the implementation of compensatory measures. The proposed AOT extension is not acceptable for the AFS. The STI extensions are acceptable for all three systems. (author)

Utilization of the RELAP4/MOD5/SAS code version in loss of coolant accident in the Angra 1 nuclear power station

International Nuclear Information System (INIS)

Sabundjian, G.; Freitas, R.L.

1991-09-01

A new version of computer code RELAP4/MOD5 was developed to improve the output. The new version, called RELAP4/MOD5/SAS, prints the main variables in graphical form. In order to check the program, a 36 - volume simulation of the Loss-of-Coolant Accident for Angra - I was performed and the results compared to those of a existing 44 - volume simulation showed a satisfactory agreement with a substantial reduction in computing time. (author)

Containment of Angra 2 - control and correction of form derivative during the assembling

International Nuclear Information System (INIS)

Noack, B.J.A.; Leaes, J.

1990-01-01

The erection of the containment of Angra 2 has been concluded in JUN, 89. It is a 56m diameter shperical steel vessel, involves the primary circuit and has the purpose to isolate this from the environment. At its construction, besides the aspects of quality of the material and welds, its geometrical shape is relevant. This taking into account that at locations with abrupt changes of the shape may arise stress disturbances and buckling problems. Besides, an adequate shape is a primary condition to have a smooth development of the erection. In a general way, the shape deviations are limited to a value in the range of 50mm, which compared with the 56m diameter of the containment gives an idea about the precautions to be taken during erection. It will be presented the parameters and methods of shape control during erection, the detected shape deviations, the methods applied to correct excessive deviations and the results of complementary stress analysis. (author) [pt

Use of 'tail' as spent fuel dilution factor of Angra-1 (PWR) for use in the Embalse (Candu) reactor

International Nuclear Information System (INIS)

Mai, Luiz Antonio; Maiorino, Jose Rubens

1995-01-01

This work purposes a process to use the tail of isotopic enrichment as a factor of dilution (blending) for the burned fuel of Angra-I reactor (PWR) for final utilization in the Embalse (Candu). It was made use of the same technic in previous works that used natural uranium. For this purpose, it was made a tail parametrization inside of the traditional limits of enrichment (between 0.2 and 0.3%). The study showed that the tail utilization represents great savings for the uranium supplies and environment and economic advantages. (author). 8 refs, 4 figs, 11 tabs

Simulation of a Nuclear Steam Supply System (NSSS) of a PWR nuclear power plant

International Nuclear Information System (INIS)

Reis Martins Junior, L.L. dos.

1980-01-01

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

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

Expert system in OPS5 for intelligent processing of the alarms in nuclear plants

International Nuclear Information System (INIS)

Cavalcante Junior, Jose Airton Chaves

1997-11-01

This work intends to establish a model of knowledge representation based on a expert system to supervise either security or operating to be applied generally on monitoring and detecting faults of industrial processes. The model structure proposed here let the system represent the knowledge related to faults on a process using a combination of rules either basic or associative. Besides, the model proposed has a mechanism of propagation of events in real time that acts on this structure making it possible to have an intelligent alarm processing. The rules used by the system define faults from the data acquired by instrumentation (basic rules), or from the establishment of a conjunction of faults already existent (associate rules). The computing implementation of the model defined in this work was developed in OPS5. It was applied on an example consisting of the shutdown of the Angra-I's power plant and was called FDAX (FDA Extended). For the simulated tests the FDAX was connected to the SICA (Integrated System of Angra-I Computers). It results save validity to the model, confirming thus its performance to real time applications. (author)

Leishmaniose tegumentar americana na Ilha Grande. Rio de Janeiro: V. Observações sobre a biologia dos transmissores em condiçoes naturais

Directory of Open Access Journals (Sweden)

Nelson A. de Araújo Filho

1981-12-01

Full Text Available Durante um surto de Leishmaniose Tegumentar Americana (LTA na Praia Vermelha, Ilha Grande, município de Angra dos Reis, Rio de Janeiro, foram coletados 4.192 exemplares de flebotomíneos em ambiente domiciliar e silvestre, com isca animal e outros abrigos naturais, durante o período de janeiro de 1976 a abril de 1977. Entre o total de 11 espécies coletadas encontraram-se 2.493 exemplares de Lutzomyia intermedia, 1.594 de Lutzomyia migonei e 105 exemplares de outras espécies. A L. intermedia apresentou densidade mais elevada no domicílio humano, enquanto a L. migonei apresentou coletas mais rendosas com iscas animais e galinheiros. O sinantropismo e a elevada densidade no ambiente domiciliar incriminam as espécies L. intermedia e L. migonei como as prováveis vetoras da LTA na Ilha Grande.

Verification of SACI-2 computer code comparing with experimental results of BIBLIS-A and LOOP-7 computer code

International Nuclear Information System (INIS)

Soares, P.A.; Sirimarco, L.F.

1984-01-01

SACI-2 is a computer code created to study the dynamic behaviour of a PWR nuclear power plant. To evaluate the quality of its results, SACI-2 was used to recalculate commissioning tests done in BIBLIS-A nuclear power plant and to calculate postulated transients for Angra-2 reactor. The results of SACI-2 computer code from BIBLIS-A showed as much good agreement as those calculated with the KWU Loop 7 computer code for Angra-2. (E.G.) [pt

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)

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)

Design of the connection pieces between concrete and valves of the cooling water system in the Angra I NPP turbine building

International Nuclear Information System (INIS)

Diaz, B.E.; Carvalho, L.J. de

1988-01-01

This work describes the design characteristics of the Transition Pieces between concrete galleries and valves of the Cooling Water System of the Turbine Building of the Angra NPP-Unit I. Design details concerning the structure and procedures for the structural analysis are presented. It is emphasized that the usual simplified design rules for the flange and bolts can not be used in the case of non existent polar symmetry for the structure and applied loads. A more sophisticated design based on finite elements models is required in these cases. (author) [pt

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.)

Nuclear power plant performance monitoring using Data Validation and Reconciliation (DVR). Application at the Brazilian Angra 2 PWR plant

International Nuclear Information System (INIS)

Tran Quang, Anh Tho; Closon, Hervé; Chares, Robert; Azola, Edson

2011-01-01

Operational decisions related to plant performance monitoring mainly result from raw process measurement analysis. When first signs of sub-optimal behavior occur, traditional methods mainly focus on the observation of selective pieces of information. The main disadvantages of these methods are: Investigation efforts are required to localize the problems, entailing time losses and costs; Validity and reliability of the pieces of information cannot be checked as long as the measurements are observed individually. The problem is not the lack of methods and techniques but rather a lack of reliable and consistent data and information across the entire plant. To overcome drawbacks of traditional methods, measurements are considered as interacting with one another. When related to the other measurements of the plant, the observed information becomes of an interest: its incoherency to the others identifies and localizes a problem. The Data Validation and Reconciliation technology (DVR) is based on an advanced process data coherency treatment. By using all available plant information and by closing the plant heat and mass balances based on rigorous thermodynamics, the method generates: A single set of reliable and most accurate plant process data; Alarms for incoherent measurements, highlighting potential problems; Alarms for equipment and process performance degradation; Alarms for faulty and drifting measurements. The use of the advanced DVR software package VALI offers various benefits as it allows to base operational decisions on reliable and accurate data. (author)

SARDAN- A program for the transients simulation in a typical PWR plant

International Nuclear Information System (INIS)

Mattos Santos, R.L.P. de.

1979-10-01

A program in FORTRAN-IV language was developed that simulates the behaviour of the primary circuit in a typical PWR plant during condition II transients, in particular uncontrolled withdrawal of a control rod set, control rod set drops and uncontrolled boron dilution. It the mathematical model adopted the reactor core, the hot piping to which a pressurizer is coupled, the steam generator and the cold piping are considered. The results obtained in the analysis of the mentioned accidents are compared to those present at the Final Safety Analysis Report (FSAR) of the Angra-1 reactor and are considered satisfactory. (F.E.) [pt

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

Detecção de ácido ocadaico em cultivo de mexilhões Perna perna, Angra dos Reis, RJ Okadaic acid detection in mussel cultivation Perna perna, Angra dos Reis, RJ

Directory of Open Access Journals (Sweden)

Geisi Ferreira Mariné

2010-02-01

Full Text Available A ficotoxina ácido ocadaico (AO é produzida por um grupo de microalgas conhecidas como dinoflagelados. Os mexilhões, ao se alimentarem dessas microalgas, acumulam a toxina em sua glândula digestiva, desencadeando a Síndrome ou Envenenamento Diarreico por Moluscos (EDM no ser humano. Os sintomas se apresentam em torno de 30 minutos após o consumo do molusco contaminado, variando entre náuseas, dores abdominais, vômitos e diarreia. Quando a ingestão da toxina acontece em quantidades inferiores a 48µg g-1, os sintomas não se desenvolvem, porém seu consumo continuado favorece o surgimento de tumores no trato gastrointestinal em razão do poder carcinogênico do AO. Este estudo pretendeu detectar e quantificar a toxina diarreica AO em mexilhões Perna perna coletados entre os meses de maio e outubro de 2006. A detecção do AO nos mexilhões foi realizada por Cromatografia Líquida de Alta Eficiência com Detecção Fluorimétrica (CLAE-DF. Os resultados cromatográficos indicaram a presença da toxina AO em baixas concentrações, em todas as amostras de mexilhões obtidas de maio a outubro de 2006. Os resultados indicam a necessidade da elaboração e aplicação efetiva de um programa de controle higiênico-sanitário dos moluscos, assim como o monitoramento do ambiente aquático, objetivando, acima de tudo, a segurança da saúde pública.Okadaic acid (OA is a phycotoxin produced by a group of microalgae known as Dino-flagellates. When mussels feed themselves from this micro seaweed the toxin accumulates in their hepatopancreas, triggering the Syndrome or Diarrhetic Shellfish Poisoning (DSP in the human being. The symptoms appear around 30 minutes after the consumption of contaminated mussels and include abdominal nauseas, pains, vomits and diarrhea. When the toxin ingestion happens in amounts lower than 48µg g-1, the above described symptoms do not develop. However, the continued consumption favors the emergence of tumors in the

Plant species visited by the Horned Sungem Heliactin bilophus (Aves, Trochilidae at Chapada dos Veadeiros, during the rainy season

Directory of Open Access Journals (Sweden)

Gabriel Baruffaldi Ghiringhello

2009-12-01

Full Text Available The feeding habits of the Horned Sungem remain little known. This study aimed to identify the plant species most often visited by H. bilophus with feeding purposes (consumption of nectar during the rainy season at Chapada dos Veadeiros National Park, Goiás. Observations were made during two rainy seasons (January 2006 and February 2008. The methodology consisted of walking through trails within two areas of campo sujo and two areas of campo rupestre. The record of an individual consuming the nectar of a flowering plant was considered to constitute a visit. A total of 296 visits were observed, comprising eight species of shrubs and herbs. The most often visited plant species were Bauhinia tenella (Caesalpinoideae and Vochysia pumila (Vochysiaceae in campo sujo, and Lychnophora ericoides (Asteraceae in campo rupestre. These three species were commonly found at the study sites. In both physiognomies, Heliactin bilophus consumed the nectar of few plant species. The most frequently visited species bore high numbers of flowers.

Development of a mobile unit for 'in loco' sistematic decontamination in nuclear power plants components

International Nuclear Information System (INIS)

Camargo, G.A.M.

1986-01-01

A mobile decontamination unit was developed to perform 'in situ' decontamination of tanks and pressure vessels belonging to the reactor auxiliary and ancillary systems. The whole system, including a control desk, is assembled in 6 trolleys which can be moved inside the plant, thus enabling component decontamination by injecting demineralized water at a pressure of approx. 50 bar and temperatures up to 90 0 , with or without chemical additives. Considering the versatility and easy handling demonstrated after extensive testing, this new system shall be used in Angra 2 and 3. (Author) [pt

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

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

CNAAA spent fuel complementary storage building (UFC) construction and licensing: an overview of current status

International Nuclear Information System (INIS)

Lima Neto, Bertino do Carmo; Pacifi, Cicero Durval

2013-01-01

The reprocessing of nuclear fuel assemblies could be a valuable solution in order to make available additional energy resources and also to decrease the volume of discarded materials. After the burning of nuclear fuel assemblies to produce electrical energy, these components have to be stored in the spent fuel pools of each unit, for at least 10 years, in order to decrease their residual heat. Even after this initial 10 year-period, these spent fuel assemblies still have a great amount of energy, which can be reused. Nowadays, the spent fuel materials can be reprocessed in order to produce electrical energy, or be stored to provide, in the future, an opportunity to decide how these materials will be treated. At the present moment, Brazil does not plan to reprocess these spent fuels assemblies, as performed by some other countries. Thus, Brazil intends to build a spent fuel long term intermediate storage facility to allow the chance to make a decision in the future, taking into account the available technology at that time. Considering the three CNAAA units (Angra 1, 2 and 3 of Central Nuclear Almirante Alvaro Alberto, the Brazilian nuclear power plant, located at Angra dos Reis county, Rio de Janeiro state) have a life time estimated in 60 years, and the intrinsical spent fuel pools storage capacity of these units, a Spent Fuel Complementary Storage Building - UFC has to be foreseen in order to increase the storage capacity of CNAAA. Therefore, the Spent Fuel Complementary Storage Building shall be in operation in 2018, capable to receive the first spent fuel assemblies from Angra 2 and, in the next year, from Angra 1. The same procedure will be applied for the spent fuel assemblies of Angra 3, currently in construction. The Spent Fuel Complementary Storage Building will be constructed and operated by Eletrobras Eletronuclear - the CNAAA owner - and will be located at the same site of the plant. Conceptually, the UFC will be built as a wet storage modality

Development phase of corrosion program in aquatic ecosystems

International Nuclear Information System (INIS)

Moreira, P.A.

1983-01-01

Providences adopted to implantation of corrosion program in aquatic ecosystems, developed by CDTN, NUCLEN and FURNAS are presented. The area, the atmospheric exposition station of Angra dos Reis, the marine floating, the material to test specimen and its preparation are described. (C.M.) [pt

Produced water treatment and discharge solutions in TRANSPETRO maritime terminals; Solucoes de tratamento e descarte de agua produzida nos terminais aquaviarios da TRANSPETRO

Energy Technology Data Exchange (ETDEWEB)

Mansor, Leonardo Mitidiero; Burburan, Alexandre; Rodrigues, Fernanda Fonseca; Cerqueira, Ana Claudia F.P. de [TRANSPETRO - PETROBRAS Transporte S.A., Rio de Janeiro, RJ (Brazil); Padilha, Carlos Frederico [PETROBRAS, Rio de Janeiro, RJ (Brazil)

2008-07-01

The PETROBRAS produced water programme, conducted by PETROBRAS S.A. is the response to the challenge faced in handling, treating and discharging produced water associated to oil production that comes from Campos Basin mainly. After run modeling studies in oil and produced water associated through 2015 scenario, it was identified the total amount of produced water that will be handle monthly, increasing from 215.000 m{sup 3} up to 420.000 m{sup 3}. To achieve the goals of treating e discharging that huge amount of water, the program understood the following main actions: built 5 produced water plants (Sao Sebastiao, Macae-Cabiunas, Angra dos Reis, Sao Francisco do Sul and Osorio) and 2 reinjection sites (Cabiunas and Lagoa Parda). These plants and sites will be able to treat monthly the total produced water amount of 677.000 m{sup 3}. (author)

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

Auto-avaliação de escolas e produção de conhecimento científico com o projecto QUALIS

OpenAIRE

Arroz, Ana Margarida Moura

2010-01-01

2º Colóquio Avaliação de Escolas. Angra do Heroísmo Universidade dos Açores, Campus do Pico da Urze, Angra do Heroísmo, Açores, Portugal, 2 de Outubro de 2010. Dado que a estrutura do modelo permite uma considerável margem de manobra das equipas de auto-avaliação na selecção e ênfase atribuída aos diferentes aspectos do funcionamento da escola no relatório que elaboram… "interessa-nos estudar até que ponto a informação que as equipas de auto-avaliação mobilizam no processo avaliativo e os ...

An radiotoxicity evaluation of high level wastes for a scenery of Brazilian Nuclear Power Plants in accordance with the Energy Expansion Brazilian Plan 2030

International Nuclear Information System (INIS)

Guilhem, Andres C.; Maiorino, Jose R.

2011-01-01

This paper is a part of the author scientific initiation, and makes an evaluation of the radiotoxicity which would be produced by the Brazilian nuclear power plants in a scenery of 7 power plants operating in 2030, in according to the official expansion plans which point out the additional introduction of 4000 MW(e), or 4 ne power plant additionally to the Angra I, II and III. Considering that all reactors would be a PWR reactors. The calculated parameter was the relative toxicity of the low and intermediate level nuclear wastes (LLPP - long lived fission products and HLW - high level waste related to the radiotoxicity of natural uranium versus time. All the calculation used the ORIGEN-S code. (author)

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

Genesis of the Brazilian nuclear power plants program

International Nuclear Information System (INIS)

Syllus, G.; Lepecki, W.

1996-01-01

The genesis of the Brazilian Nuclear Power Program is described by the authors - who participated in the events - from the beginning of the sixties, until the definition and the start of the implementation in 1975 of the Reference Nuclear Power Program. A description is made of the main events, studies and decisions that contributed to the evolution of the Program: the GTRP (Nuclear Power Plant Working Group); the Thorium Group; the Lane Group; the decision about Angra 1; CNEN's analyses about the reactor line and, finally, the creation of CBTN (Nuclear Technology Brazilian Company), which elaborated the studies that resulted in the final definition of the Program and led to the Brazilian German Agreement and the establishment of NUCLEBRAS. (author)

Study of the environmental costs to nuclear power plants using the SIMPACTS program

Energy Technology Data Exchange (ETDEWEB)

Menzel, Francine; Sabundjian, Gaiane; Mutarelli, Rita de Cassia, E-mail: fmenzel@ipen.b, E-mail: gdjian@ipen.b [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

2011-07-01

The nuclear energy presents advantages in comparison with other kinds of energy sources, when their externalities are evaluated. Externality is a term that represents the side effects of production of goods or services on other people not directly involved in the activity. The externalities can be identified and related to the term environmental cost. The environmental cost is a externality that somehow affects the environment, converted into economic terms, to then be compared with other costs of an action or enterprise. The environmental cost can be calculated through programs for that purpose, however for the nuclear area is the most used SIMPACTS, developed by the International Atomic Energy Agency (IAEA). The motivation for this work arose from the need to have a complete assessment of environmental costs from nuclear power reactors, although it is known that this kind of form of energy generation show an advantage over others with regard to externalities. This work is the first step in implementing the program SIMPACTS in plant Angra 2 in order to calculate the environmental cost of their operation. The objective is to develop a methodology for calculating environmental cost for nuclear power reactors. SIMPACTS program will be used to identify the advantages and disadvantages of a cost analysis of environmental and perform the calculation of environmental costs for Angra 2, with the aim of minimizing the environmental impacts of its operation. From an extensive literature search, is presented in this paper the methodology for calculating the environmental cost of the program SIMPACTS and some results of calculations with the environmental cost in international power reactors other power generation plants. (author)

Study of the environmental costs to nuclear power plants using the SIMPACTS program

International Nuclear Information System (INIS)

Menzel, Francine; Sabundjian, Gaiane; Mutarelli, Rita de Cassia

2011-01-01

The nuclear energy presents advantages in comparison with other kinds of energy sources, when their externalities are evaluated. Externality is a term that represents the side effects of production of goods or services on other people not directly involved in the activity. The externalities can be identified and related to the term environmental cost. The environmental cost is a externality that somehow affects the environment, converted into economic terms, to then be compared with other costs of an action or enterprise. The environmental cost can be calculated through programs for that purpose, however for the nuclear area is the most used SIMPACTS, developed by the International Atomic Energy Agency (IAEA). The motivation for this work arose from the need to have a complete assessment of environmental costs from nuclear power reactors, although it is known that this kind of form of energy generation show an advantage over others with regard to externalities. This work is the first step in implementing the program SIMPACTS in plant Angra 2 in order to calculate the environmental cost of their operation. The objective is to develop a methodology for calculating environmental cost for nuclear power reactors. SIMPACTS program will be used to identify the advantages and disadvantages of a cost analysis of environmental and perform the calculation of environmental costs for Angra 2, with the aim of minimizing the environmental impacts of its operation. From an extensive literature search, is presented in this paper the methodology for calculating the environmental cost of the program SIMPACTS and some results of calculations with the environmental cost in international power reactors other power generation plants. (author)

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)

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)

The foundation of the units 2 and 3 of the nuclear power plant Angra dos Reis/Brasil

International Nuclear Information System (INIS)

Bokemeyer, R.; Linder, W.R.

1979-01-01

The report describes the extraordinarily difficult and comprehensive foundation activities which started in Summer 1977. Because of the high building weight, and the gigantic soft superimposed layers prevailing on the site, a bay, a foundation on more than 2500 large-scale drilling posts for both units is planned. The posts have to be inserted into loose marine sediments, gneiss decomposition grounds and weather-worn rocks down to an average of 36 m, and often down to 60 m, into competent rocks, mostly gneiss or granite. Because of the size and the changing consistency of the weather-worn rocks and the great amount of the hard boulders which are deposited in the soft layers enormous technical difficulties have to be surmounted as the drilling work has to be accomplished within a very short time. It has not been necessary yet to cope with difficulties of this dimension. (orig./HP) [de

Cobalt adsorption/desorption on sediments from Piraquara de Fora bay, Angra dos Reis, Brazil

International Nuclear Information System (INIS)

Ferreira, Ingryd M.; Carvalho, Franciane M.; Ribeiro, Fernando C.A.; Martins, Nadia S.F.; Peres, Sueli S.; Lauria, Dejanira C.

2015-01-01

Among the radionuclides released with the liquid effluents from PWR power plants, cobalt isotopes ( 60 Co and 58 Co) play an important role for risk and environmental impact assessments. The laboratory experiments on radionuclide adsorption-desorption, followed by the use of adsorption isotherms are useful tools for prediction of transport, distribution, accumulation, and fate of a contaminant into a specific medium. Adsorption and desorption experiments were carried out in batches, using two sediment samples collected in Piraquara de Fora Bay, near the discharge channel of the liquid effluents from CNAAA. Aiming the assessment of the radioisotope adsorption mechanisms, sediment samples were shaken with solutions containing cobalt chloride which concentrations ranged between 10 -10 and 10 -3 M. In order to estimate the efficiency of adsorption, 100 Bq of 60 Co were used as radioactive tracer. The experimental data fitted well with Freundlich and Langmuir isotherms. Results point out a favorable and high cobalt adsorption on the sediments, although smaller than the ones reported in literature studies. Such smaller trend of adsorption coefficients may be caused by the low exchange capacity of the prevailing clay, kaolinite. The maximum adsorption capacities were found to be 10 and 17 moles/g for sediments in PT-01 and PT-02, respectively. Values lower than 8% of the adsorbed cobalt underwent desorption and this amount decreased to 4%, with time, which show the high retention capacity of these sediments. (author)

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

Preliminary version of corrosion program to be done among CDTN, NUCLEN and FURNAS

International Nuclear Information System (INIS)

Moreira, P.A.P.

1982-01-01

The corrosion at atmospheric exposition Program developed by CDTN (Centro de Desenvolvimento da Tecnologia Nuclear) in galvanized materials, that serve as model for implantation a similar Program in Angra dos Reis area is presented. A materials list that will be tested and necessary costs to project elaboration are still presented. (C.M.) [pt

Seismic analysis of the pile foundation of the reactor building of the NPP ANGRA 2

International Nuclear Information System (INIS)

Wolf, J.P.; Arx, G.A. von; Barros, F.C.P. de; Kakubo, M.

1981-01-01

A pile foundation subjected to dynamic loads interacts with the surrounding soil. Frequency-dependent stiffness and radiation damping must be properly taken into account in pile-soil-pile interaction. Assuming that the soil consists of horizontal layers of elastic material with hysteretic damping, the dynamic stiffness of a group of (even battered) piles can be determined, accounting rigorously for the cavities where the soil is subsequently replaced by the piles. By way of illustration, this substructure procedure, which works in the frequency domain, is applied to the final design of the pile foundation of the Reactor Building of Angra 2 in Brazil. Below the basemat, a strongly horizontally-layered compressive soil of 36 m thickness rests on bedrock. The reactor building is founded on 202 endbearing piles and 88 floating piles of 15 m length. Every pile is modelled. Along each pile, compatibility between the pile and the soil in all three directions is formulated in seven nodes. The basemat is assumed to be rigid. On the level of bedrock a broad-banded response spectrum specifies the excitation (outcropping). (orig./WL)

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}.

Study of a loss of coolant accident of a PWR reactor through a Full Scope Simulator and computational code RELAP

International Nuclear Information System (INIS)

Soares, Alexandre de Souza

2014-01-01

The present paper proposes a study of a loss of coolant accident of a PWR reactor through a Full Scope Simulator and computational code RELAP. To this end, it considered a loss of coolant accident with 160 cm 2 breaking area in cold leg of 20 circuit of the reactor cooling system of nuclear power plant Angra 2, with the reactor operating in stationary condition, to 100% power. It considered that occurred at the same time the loss of External Power Supply and the availability of emergency cooling system was not full. The results obtained are quite relevant and with the possibility of being used in the planning of future activities, given that the construction of Angra 3 is underway and resembles the Angra 2. (author)

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

Analysis of neutronic parameters related to reduction in fuel rod diameter for Angra-1 reactor fuel elements

International Nuclear Information System (INIS)

Faria, Eduardo F.; Sadde, Luciano M.; Sakai, Massao; Gomes, Sydney da S.

2000-01-01

The actual fuel element design for Angra-1 PWR satisfies in a very conservative way the design limits established for the critical heat flux as well as for the energy stored in the fuel rod. However, that is not an optimized design under neutronic considerations. The conservative ratio of the H and U atomic densities gives rise to a harder neutron spectrum which reduces its reactivity. In this report, a reduction in fuel rod diameters has been analyzed, keeping however the same rod pitch for geometrical compatibility reasons. By increasing the H/U ratio it is possible to obtain a net gain in reactivity. The optimized diameter in its turn should not jeopardize the reactor safety requirements. The actual trends of the nuclear industry is to extend the cycles and the enrichment by using advanced fuel design. It must be emphasized that this design change gives rise to economical advantages, for example, reduced costs for uranium utilization and enrichment with a net gain in reactivity. (author)

One safety critical indicators model for regulatory actions on nuclear power plants based on a level 1 PSA

International Nuclear Information System (INIS)

Araujo, Jefferson Borges

2006-03-01

This study presents a general methodology to the establishment, selection and use of safety indicators for a two loop PWR plant, as Angra 1. The study performed identifies areas considered critical for the plant operational safety. For each of these areas, strategic sub-areas are defined. For each strategic sub-area, specific safety indicators are defined. These proposed Safety Indicators are based on the contribution to risk considering a quantitative risk analysis. For each safety indicator, a goal, a bounded interval and proper bases are developed, to allow for a clear and comprehensive individual behavior evaluation. Additionally, an integrated evaluation of the indicators, using expert systems, was done to obtain an overview of the plant general safety. This methodology can be used for identifying situations where the plant safety is challenged, by giving a general overview of the plant operational condition. Additionally, this study can also identify eventual room for improvements by generating suggestions and recommendations, as a complement for regulatory actions and inspections, focusing resources on eventual existing weaknesses, in order to increase or maintain a high pattern of operational safety. (author)

Comparative study of design of piping supports class 1, 2 and 3 considering german code KTA and ASME III - NF

International Nuclear Information System (INIS)

Faloppa, Altair A.; Fainer, Gerson; Mattar Neto, Miguel; Elias, Marcos V.

2013-01-01

The objective of this paper is developing a comparative study of the design criteria for class 1, 2, 3 piping supports considering the American Code ASME Section III - NF and the German Code KTA 3205.1 to the Primary Circuit, KTA 3205.2 to the others systems and KTA 3205.3 series-production standards supports of a PWR nuclear power plant. An additional purpose of the paper is a general analysis of the main design concepts of the American Code ASME Boiler and Pressure Vessel Code, Section III, Division 1 and German Nuclear Design Code KTA that was performed in order to aid the comparative study proposed. The relevance of this study is to show the differences between codes ASME and KTA since they were applied in the design of the Nuclear Power Plants Angra 1 and Angra 2, and to the design of Angra 3, which is at the moment under construction. It is also considered their use in the design of nuclear installations such as RMB - Reator MultiProposito Brasileiro and LABGENE - Laboratorio de Geracao Nucleoeletrica. (author)

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

Energy Technology Data Exchange (ETDEWEB)

Reis Martins Junior, L.L. dos.

1980-01-01

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

A new concept of safety parameter display system

International Nuclear Information System (INIS)

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

1986-07-01

A general description of Angra-1 Parameter Display System (SSPA), a real time and on-line computerized monitoring system for the parameters related to the power plant safety is presented. This system has the main purpose of diminish the load on the Angra-1 power plant operators at an emergency event by supplying them with the additional tools serving as the basis for a prompt identification of the accident. The SSPA is a kind of safety parameter display system whose concept was introduced after Three Mile Island accident in USA. The SSPA comprises two nuclear applications independently considered. They are included into the Parameters Monitoring Integrated System (SIMP) and the safety critical function system (SFCS). (Author) [pt

Insucessos em empreendimentos nucleares devido a falhas em processos de Comunicação Pública

OpenAIRE

Ferreira,Vinícius V. M.; Soares,Wellington A.

2012-01-01

A energia nuclear é um tema amplamente discutido em todo o mundo. O acidente nuclear de Chernobyl e o acidente radiológico de Goiânia contribuíram decisivamente para que a sociedade brasileira tivesse uma imagem negativa sobre o tema. A operação da usina de Angra 3, atualmente em obras, está vinculada à construção de um repositório para armazenar os rejeitos radioativos, o que provavelmente será explorado pelos opositores do setor nuclear. Um dos grandes desafios dos profissionais envolvidos ...

Uncertainty propagation in probabilistic safety analysis of nuclear power plants

International Nuclear Information System (INIS)

Fleming, P.V.

1981-09-01

The uncertainty propagation in probabilistic safety analysis of nuclear power plants, is done. The methodology of the minimal cut is implemented in the computer code SVALON and the results for several cases are compared with corresponding results obtained with the SAMPLE code, which employs the Monte Carlo method to propagate the uncertanties. The results have show that, for a relatively small number of dominant minimal cut sets (n approximately 25) and error factors (r approximately 5) the SVALON code yields results which are comparable to those obtained with SAMPLE. An analysis of the unavailability of the low pressure recirculation system of Angra 1 for both the short and long term recirculation phases, are presented. The results for the short term phase are in good agreement with the corresponding one given in WASH-1400. (E.G.) [pt

Utilization of a statistical procedure for DNBR calculation and in the survey of reactor protection limits

International Nuclear Information System (INIS)

Pontedeiro, A.C.; Camargo, C.T.M.; Galetti, M.R. da Silva.

1987-01-01

A new procedure is applied to Angra 1 NPP, which is related to DNBR calculations, considering the design parameters statistically: Improved Thermal Design Procedure (ITDP). The ITDP application leads to the determination of uncertainties in the input parameters, the sensitivity factors on DNBR. The DNBR limit and new reactor protection limits. This was done to Angra 1 with the subchannel code COBRA-IIIP. The analysis of limiting accident in terms of DNB confirmed a gain in DNBR margin, and greater operation flexibility of the plant, decreasing unnecessary trips of the reactor. (author) [pt

Calculation methods for analysing nuclear power plant accidents and its qualification

International Nuclear Information System (INIS)

Sacco, W.

1986-01-01

A methodology of transient and accident analyses able to carried out calculations for all transients and accidents required to support operation and operation licensing of Angra-1 reactor reload, is presented. (M.C.K.) [pt

Soil sampling in emergency situations

International Nuclear Information System (INIS)

Carvalho, Zenildo Lara de; Ramos Junior, Anthenor Costa

1997-01-01

The soil sampling methods used in Goiania's accident (1987) by the environmental team of Brazilian Nuclear Energy Commission (CNEN) are described. The development of this method of soil sampling to a emergency sampling method used in a Nuclear Emergency Exercise in Angra dos Reis Reactor Site (1991) is presented. A new method for soil sampling based on a Chernobyl environmental monitoring experience (1995) is suggested. (author)

Genetic algorithms applied to the nuclear power plant operation

International Nuclear Information System (INIS)

Schirru, R.; Martinez, A.S.; Pereira, C.M.N.A.

2000-01-01

Nuclear power plant operation often involves very important human decisions, such as actions to be taken after a nuclear accident/transient, or finding the best core reload pattern, a complex combinatorial optimization problem which requires expert knowledge. Due to the complexity involved in the decisions to be taken, computerized systems have been intensely explored in order to aid the operator. Following hardware advances, soft computing has been improved and, nowadays, intelligent technologies, such as genetic algorithms, neural networks and fuzzy systems, are being used to support operator decisions. In this chapter two main problems are explored: transient diagnosis and nuclear core refueling. Here, solutions to such kind of problems, based on genetic algorithms, are described. A genetic algorithm was designed to optimize the nuclear fuel reload of Angra-1 nuclear power plant. Results compared to those obtained by an expert reveal a gain in the burn-up cycle. Two other genetic algorithm approaches were used to optimize real time diagnosis systems. The first one learns partitions in the time series that represents the transients, generating a set of classification centroids. The other one involves the optimization of an adaptive vector quantization neural network. Results are shown and commented. (orig.)

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.)

DOS.

Science.gov (United States)

Traven, Bill

1988-01-01

Discusses using the DOS PATH command (for MS-DOS) to enable the microcomputer user to move from directory to directory on a hard drive. Lists the commands to be programed, gives examples, and explains the use of each. (MVL)

Considerations about the impact of the Convention on Nuclear Safety on the regulatory action of the CNEN in Brazilian nuclear power plants

International Nuclear Information System (INIS)

Camargo, Claudio; Pontedeiro, Auro

1995-01-01

Preliminary discussion is conducted about the impact of the terms of the Convention on Nuclear safety, adopted by Diplomatic Conference in September 1994 in the International Atomic Energy Agency, on the regulatory action of Brazilian Nuclear Regulatory Body - CNEN. Following the Convention articles structure, the paper emphasizes technical aspects of the nuclear safety standards adopted in the licensing process of Brazilian Nuclear Power Plants. The recent experience in the issuance of Angra-1 NPP Permanent Operation Authorization is used to demonstrate that current safety standards in Brazil are in compliance with the international compromises and in agreement with what is expected by the so called Safety Culture. (author). 9 refs

A model to simulate the dynamic of a PWR pressurizer using the CSMP program

International Nuclear Information System (INIS)

Woiski, E.R.

1981-01-01

A mathematical model has been developed to simulate the dynamic behavior of a PWR pressurizer using the CSMP program. A two-control-volume formulation non-equilibrium model has been used for this purpose. Thermodynamic states are obtained after each integration cycle. The code was tested against experimental results of Shippingport and NPD (Nuclear Power Demonstration Plant) pressurizers. It was also tested against available data from Angra I and Angra II/III safety analysis report. Despite the model simplicity, the lack of important data and the low reliability or the experimental curves, the calculated and experimental results compared well. (Author) [pt

Modelling the transport of radionuclides released in the Ilha Grande bay (Brazil) after a Large Break Loca ion the primary system of a PWR

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 of the core, a LOCA, where 431 m 3 of soda almost instantaneously was lost. This inventory contained 1.87x10 10 Bq/m 3 of tritium, 2.22x10 7 Bq/m 3 of cobalt,3.48x10 8 Bq/m 3 of cesium and 3.44x10 10 Bq/m 3 of iodine and was released in liquid form near the Itaorna cove, Angra dos Reis - RJ. Applying the model in the proposed scenario (Angra 1 and 2 in operation and Angra 3 progressively reducing the capture and discharge after the accident), the simulated dilution of the specific activity of radionuclide spots, reached values much lower than report levels for seawater (1,1x10 6 Bq/m 3 , 1,11x10 4 Bq/m 3 and 1,85x10 3 Bq/m 3 ) after 22 hours, respectively for 3 H, 60 Co, 131 I and 137 Cs. From the standpoint of public exposure to radionuclide dispersion, the results of activity concentration obtained by the model suggest that the observed radiological impact is negligible. Based on these findings, we conclude that there would be no radiological impact related to a further release of controlled effluent discharges into Itaorna cove. (author)

Use of segregation techniques to reduce stored low level waste

International Nuclear Information System (INIS)

Nascimento Viana, R.; Vianna Mariano, N.; Antonio do Amaral, M.

2000-01-01

This paper describes the use of segregation techniques in reducing the stored Low Level Waste on Intermediate Waste Repository 1, at Angra Nuclear Power Plant Site, from 1701 to 425 drums of compacted waste. (author)

Soil sampling in emergency situations; Amostragem de solos em situacoes de emergencia

Energy Technology Data Exchange (ETDEWEB)

Carvalho, Zenildo Lara de [Instituto de Radioprotecao e Dosimetria (IRD), Rio de Janeiro, RJ (Brazil); Ramos Junior, Anthenor Costa [Comissao Nacional de Energia Nuclear (CNEN), Rio de Janeiro, RJ (Brazil). Superintendencia de Licenciamento e Controle

1997-12-31

The soil sampling methods used in Goiania`s accident (1987) by the environmental team of Brazilian Nuclear Energy Commission (CNEN) are described. The development of this method of soil sampling to a emergency sampling method used in a Nuclear Emergency Exercise in Angra dos Reis Reactor Site (1991) is presented. A new method for soil sampling based on a Chernobyl environmental monitoring experience (1995) is suggested. (author) 15 refs.

Definition of thermal-hydraulics parameters of a naval PWR via energy balance of a Westinghouse PWR

Energy Technology Data Exchange (ETDEWEB)

Chaves, Luiz C.; Curi, Marcos F., E-mail: marcos.curi@cefet-rj.br [Centro Federal de Educação Tecnológica Celso Suckow da Fonseca (CEFET-RJ), Rio de Janeiro, RJ (Brazil). Department of Mechanical Engineering

2017-07-01

In this work, we used the operational parameters of the Angra 1 nuclear power plant, designed by Westinghouse, to estimate the thermal-hydraulic parameters for naval nuclear propulsion, focusing on the analysis of the reactor and steam generator. A thermodynamics analysis was made to reach the operational parameters of primary circuit such as pressure, temperature, power generated among others. Previous studies available in literature of 2-loop Westinghouse Nuclear Power Plants, which is based on a PWR and similar to Angra-1, support this analysis in the sense of a correct procedure to deal with many complex processes to energy generation from a nuclear source. Temperature profiles in reactor and steam generator were studied with concepts of heat transfer, fluid mechanics and also some concepts of nuclear systems, showing the behavior into them. In this simulation, the Angra 1 primary circuit was reduced on a scale of 1: 3.5 to fit in a Scorpène-class submarine. The reactor generates 85.7 MW of total thermal power. The maximum power and temperatures reached were lower than the operational safe limits established by Westinghouse. The number of tubes of the steam generator was determined in 990 U-tubes with 6.3 m of average length. (author)

A summary of the Three Mile Island accident: from zero hour to lessons for the future

International Nuclear Information System (INIS)

Oliveira, L.F.S. de; Oliveira Barroso, A.C. de

The accident that occured at the Three Mile Island nuclear power plant, unit 2 (TMI-2) in March 1979 is analysed. The main events that occured during the accident are described in detail. The main project features of TMI-2 and Angra-1 nuclear power plant, Brazil are compared and analysed. (L.F.S.) [pt

Uranium producer region of Lagoa Real, Brazil. Guarantee of supply of uranium concentrated (DUA) for the brazilian needs

International Nuclear Information System (INIS)

Matos, Evandro Carele de; Franco, Jamyle Praxedes

2008-01-01

This work focus at the Uranium Province of Lagoa Real, notably considering the geological reserves of uranium already defined (100,000 tones of U 3 O 8 ) and the respective autonomy in providing raw material needed for making fuel elements. The province, based on geo economical parameters, supported by three main vectors (geological model/grade, mining/process route, investment/finance) has been elected to supply the required brazilian demand. Supplying of uranium for the brazilian power plants is in charge of Industrias Nucleares do Brasil - INB and is based on national production. Thus the Industrial Complex of Caetite has been implemented in the state of Bahia, aiming primarily to supply the needs of Angra 1 and Angra 2 power plants. This new production center has the capacity of producing up to 400 tones/yr. of U 3 O 8 . (author)

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

International Nuclear Information System (INIS)

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

1998-01-01

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

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

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.)

Probabilistic methods applied to the safety of nuclear power plant: annual report - 1980. Part. 1: theoretical fundaments

International Nuclear Information System (INIS)

Oliveira, L.F.S. de; Hesles, J.B.S.; Milidiu, R.L.; Maciel, C.C.; Gibelli, S.M.O.; Oliveira, L.C.; Fleming, P.V.; Rivera, R.R.J.

1981-02-01

The probabilistic Safety Analysis Group from COPPE was founded in 1980. This first part of the report shows the theoretical fundaments used for reliability analysis of some safety systems for Angra-1 [pt

Evaluation of the properties of bitumen and cement pastes and mortars used in the immobilization of waste radioactive

International Nuclear Information System (INIS)

Vieira, Vanessa Mota; de Tello, Cledola Cassia Oliveira

2013-01-01

The Project RBMN was launched in November 2008 and aims to establish, manage and execute all tasks for implementing the Brazilian Repository, from its conception to its construction. The concept to be adopted will be a near-surface repository. The inventory includes wastes from the operation of nuclear power plants, fuel cycle facilities and from the use of radionuclides in medicine, industry and activities research and development. The implementation of the national repository is an important technical requirement, and a legal requirement for the entry into operation of the nuclear power plant Angra 3. In Brazil, for the immobilization and solidification of radioactive waste of low and intermediate level of radiation from NPPs are used cement, in Angra 1, and bitumen, in Angra 2. Studies indicate serious concerns about the risks associated with bituminization radioactive waste, much related to the process as the product. There are two major problems due to the presence of products bituminization in repositories, swelling of the waste products and their degradation in the long term. To accommodate the swelling, filling the drums must be limited to 70 - 90% of its volume, which reduces the structural stability of the repository and the optimization of deposition. This study aims to evaluate of the properties of bitumen and cement pastes and mortars used in the immobilization of waste radioactive. (author)

Empleo de plantas medicinales en usuarios de dos hospitales referenciales del Cusco, Perú Use of medicinal plants among people attending two reference hospitals in Cusco, Peru

Directory of Open Access Journals (Sweden)

Gladys Oblitas

2013-03-01

Full Text Available Con el fin de determinar la frecuencia de empleo de plantas medicinales y describir las características de su uso en pacientes de dos hospitales referenciales de la ciudad de Cusco, se realizó un estudio transversal entre agosto y septiembre de 2011. Para el recojo de datos se construyó un instrumento, validado por juicio de expertos. El tamaño de la muestra fue de 250 personas seleccionadas no probabilísticamente. El 83,2 y 75,3% informaron haber empleado plantas medicinales alguna vez en su vida y en el último mes, respectivamente; además, el 85,7 señaló que desearía que su médico le recete plantas medicinales. Sus usos más frecuentes son para problemas digestivos (62,4%; urinarios (42,4%, y respiratorios (40,4%. Se concluye que el empleo de plantas medicinales se encuentra bastante difundido entre los usuarios de dos hospitales referenciales de la ciudad de Cusco. Los patrones de empleo revelan que los pacientes desean que los médicos del sistema de salud prescriban plantas medicinales en su acto médicoIn order to determine the frequency and characteristics of the use of medicinal plants in patients from two third-level hospitals in the city of Cusco, a cross-sectional study was conducted between August and September 2011. For data collection, an instrument was built and validated through experts’ judgment. The sample included 250 people selected in a non-probabilistic way. 83.2 and 75.3% informed having had used medicinal plants sometime during their lives and in the last month, respectively; additionally, 85.7 indicated that they wished their doctor would have prescribed them medicinal plants. Their most frequent uses include digestive problems (62.4% as well as urinary (42.4% and respiratory problems (40.4%. We conclude that the use of medicinal plants is widely spread among users of two hospitals in the city of Cusco. Utilization patterns show that patients wished the physicians of the health system prescribed medicinal

Use of the buble rise model in the simulation of the pressurizer in ALMOD 3 computer code

International Nuclear Information System (INIS)

Madeira, A.A.; Camargo, C.T.M.

1984-01-01

The implementation of the buble rise model in the ALMOD 3 computer code to simulate the pressurizer of a nuclear power plant is presented. Some transients for Angra I were calculated and results obtained from the original and modified models were compared. (E.G.) [pt

Effect of tube plugging in the thermalhydraulic performance of 'U' tube steam generators

International Nuclear Information System (INIS)

Braga, C.V.M.; Carajilescov, P.

1981-05-01

The thermalhydraulic performance of Angra II steam generator has been simulated using the model developed by Braga, C.V.M., 'Thermohydraulic model for steam generator of PWR power plants', in steady state, with plugging up to 40% of total number of tubes. (E.G.) [pt

Project and implementation of the human/system interface laboratory

International Nuclear Information System (INIS)

Carvalho, Paulo Victor R. de; Obadia, Isaac Jose; Vidal, Mario Cesar Rodriguez

2002-01-01

Analog instrumentation is being increasingly replaced by digital technology in new nuclear power plants, such as Angra III, as well as in existing operating plants, such as Angra I and II, for modernization and life-extension projects. In this new technological environment human factors issues aims to minimize failures in nuclear power plants operation due to human error. It is well known that 30% to 50% of the detected unforeseen problems involve human errors. Presently, human factors issues must be considered during the development of advanced human-system interfaces for the plant. IAEA has considered the importance of those issues and has published TECDOC's and Safety Series Issues on the matter. Thus, there is a need to develop methods and criteria to asses, compare, optimize and validate the human-system interface associated with totally new or hybrid control rooms. Also, the use of computer based operator aids is en evolving area. In order to assist on the development of methods and criteria and to evaluate the effects of the new design concepts and computerized support systems on operator performance, research simulators with advanced control rooms technology, such the IEN's Human System Interface Laboratory, will provide the necessary setting. (author)

Application of perturbation methods for sensitivity analysis for nuclear power plant steam generators

International Nuclear Information System (INIS)

Gurjao, Emir Candeia

1996-02-01

The differential and GPT (Generalized Perturbation Theory) formalisms of the Perturbation Theory were applied in this work to a simplified U-tubes steam generator model to perform sensitivity analysis. The adjoint and importance equations, with the corresponding expressions for the sensitivity coefficients, were derived for this steam generator model. The system was numerically was numerically solved in a Fortran program, called GEVADJ, in order to calculate the sensitivity coefficients. A transient loss of forced primary coolant in the nuclear power plant Angra-1 was used as example case. The average and final values of functionals: secondary pressure and enthalpy were studied in relation to changes in the secondary feedwater flow, enthalpy and total volume in secondary circuit. Absolute variations in the above functionals were calculated using the perturbative methods, considering the variations in the feedwater flow and total secondary volume. Comparison with the same variations obtained via direct model showed in general good agreement, demonstrating the potentiality of perturbative methods for sensitivity analysis of nuclear systems. (author)

Seismic risk map for Southeastern Brazil

International Nuclear Information System (INIS)

Mioto, J.A.

1984-01-01

During the last few years, some studies regarding seismic risk were prepared for three regions of Brazil. They were carried on account of two basic interests: first, toward the seismic history and recurrence of Brazilian seismic events; second, in a way as to provide seismic parameters for the design and construction of hydro and nuclear power plants. The first seismic risk map prepared for the southeastern region was elaborated in 1979 by 6he Universidade de Brasilia (UnB-Brasilia Seismological Station). In 1981 another seismic risk map was completed on the basis of seismotectonic studies carried out for the design and construction of the Nuclear power plants of Itaorna Beach (Angra dos Reis, Rio de Janeiro) by IPT (Mining and Applied Geology Division). In Brazil, until 1984, seismic studies concerning hydro and nuclear power plants and other civil construction of larger size did not take into account the seismic events from the point of view of probabilities of seismic recurrences. Such analysis in design is more important than the choice of a level of intensity or magnitude, or adoption of a seismicity level ased on deterministic methods. In this way, some considerations were made, concerning the use of seisms in Brazilian designs of hydro and nuclear power plants, as far as seismic analysis is concerned, recently altered over the current seismic risk panorama. (D.J.M.) [pt

One safety critical indicators model for regulatory actions on nuclear power plants based on a level 1 PSA; Um modelo de indicadores criticos de seguranca para acoes regulatorias em usinas nucleares baseado em uma APS nivel 1

Energy Technology Data Exchange (ETDEWEB)

Araujo, Jefferson Borges

2006-03-15

This study presents a general methodology to the establishment, selection and use of safety indicators for a two loop PWR plant, as Angra 1. The study performed identifies areas considered critical for the plant operational safety. For each of these areas, strategic sub-areas are defined. For each strategic sub-area, specific safety indicators are defined. These proposed Safety Indicators are based on the contribution to risk considering a quantitative risk analysis. For each safety indicator, a goal, a bounded interval and proper bases are developed, to allow for a clear and comprehensive individual behavior evaluation. Additionally, an integrated evaluation of the indicators, using expert systems, was done to obtain an overview of the plant general safety. This methodology can be used for identifying situations where the plant safety is challenged, by giving a general overview of the plant operational condition. Additionally, this study can also identify eventual room for improvements by generating suggestions and recommendations, as a complement for regulatory actions and inspections, focusing resources on eventual existing weaknesses, in order to increase or maintain a high pattern of operational safety. (author)

FURNAS activities in safety and quality assurance

International Nuclear Information System (INIS)

Dezordi, W.L.; Correa Filho, S.M.; Sacco, W.; Morais, L.H.G. de

1980-01-01

The aspects involved in the quality assurance performed by FURNAS for Nuclear Power Plant - Angra Unit I, are shown. Furnas' responsabilities in the licensing regarding reactor safety are also discussed. A summary of the computer codes used in the licensing process is given. (e.G.) [pt

Economy: the sector crisis grew in 87 and one rate more in 88

International Nuclear Information System (INIS)

Servant-Vildary, S.; Soguio, K.

1988-01-01

The crisis in the Brazilian electric power sector is analysed, making forecasting for the year of 1995. An overview of the hydroelectric power plants is presented, including some consideration about investments and market. Some commentary about the necessity of Angra-2 operation are also cited. (author)

Os organismos geneticamente modificados e a rotulagem dos alimentos - uma análise a partir dos direitos dos consumidores

Directory of Open Access Journals (Sweden)

Marcello Vitor Rocha Cota

2015-11-01

Full Text Available Ao longo do presente trabalho serão analisados os organismos geneticamente modificados (OGMs frente aos riscos à saúde alimentar e ao meio ambiente, sobretudo o princípio da precaução e a rotulagem dos produtos. A partir de uma dimensão comparativa de três realidades distintas, isto é, a estadunidense, a europeia, com ênfase mercado ao português, e a brasileira – sob um prisma ambiental, a rotulagem dos produtos será confrontada com os direitos dos consumidores, embora em determinadas ocasiões, diante da inexistência de informações adequadas e claras dos produtos, que estão sendo ofertados e consumidos, os consumidores não sabem o que estão consumindo.

Autonomia profissional dos professores

OpenAIRE

Guerra, Teresa P.; Veiga, Feliciano

2007-01-01

Este estudo pretendeu analisar as representações dos professores acerca da sua autonomia em contexto escolar, com recurso a uma amostra de 203 professores de ambos os sexos, pertencentes a escolas dos distritos de Lisboa, Setúbal, Leiria e Aveiro. Utilizou-se a Escala de Autonomia Profissional dos Professores (EAPP).

Modelling the transport of radionuclides released in the Ilha Grande bay (Brazil) after a Large Break Loca ion the primary system of a PWR

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 (LIMA/IEN/CNEN-RJ), Rio de Janeiro, RJ (Brazil)

2011-07-01

It was postulated, in the cooling system of the core, a LOCA, where 431 m{sup 3} of soda almost instantaneously was lost. This inventory contained 1.87x10{sup 10} Bq/m{sup 3} of tritium, 2.22x10{sup 7} Bq/m{sup 3} of cobalt,3.48x10{sup 8} Bq/m{sup 3} of cesium and 3.44x10{sup 10} Bq/m{sup 3} of iodine and was released in liquid form near the Itaorna cove, Angra dos Reis - RJ. Applying the model in the proposed scenario (Angra 1 and 2 in operation and Angra 3 progressively reducing the capture and discharge after the accident), the simulated dilution of the specific activity of radionuclide spots, reached values much lower than report levels for seawater (1,1x10{sup 6} Bq/m{sup 3}, 1,11x10{sup 4} Bq/m{sup 3} and 1,85x10{sup 3} Bq/m{sup 3}) after 22 hours, respectively for {sup 3}H, {sup 60}Co, {sup 131}I and {sup 137}Cs. From the standpoint of public exposure to radionuclide dispersion, the results of activity concentration obtained by the model suggest that the observed radiological impact is negligible. Based on these findings, we conclude that there would be no radiological impact related to a further release of controlled effluent discharges into Itaorna cove. (author)

Fluxo de seiva e fotossíntese em laranjeira 'Natal' com clorose variegada dos citros Sap flow and photosynthesis of 'Natal' sweet orange plants with citrus variegated chlorosis

Directory of Open Access Journals (Sweden)

Eduardo Caruso Machado

2006-06-01

Full Text Available O objetivo deste trabalho foi avaliar os efeitos da clorose variegada dos citros (CVC, no fluxo de seiva, trocas gasosas e atividade fotoquímica em laranjeira 'Natal', com e sem CVC, em condição de campo. O curso diário do fluxo de seiva, potencial da água na folha, assimilação de CO2, transpiração, condutância estomática e eficiência quântica máxima e efetiva do fotossistema II foram avaliados. O delineamento experimental foi em blocos ao acaso com cinco repetições. O fluxo de seiva foi 1,9 vez superior nas plantas sadias em relação às doentes. Em plantas doentes ocorreu queda de 43, 28 e 33% na assimilação de CO2, condutância estomática e transpiração, respectivamente. As plantas com CVC apresentaram fotoinibição dinâmica. Uma vez que a eficiência quântica efetiva apresentou um padrão de resposta semelhante, durante o dia, em ambos os tratamentos, o efeito protetor da fotorrespiração no aparato fotoquímico em plantas com CVC é discutido. As quedas de assimilação de CO2, transpiração e de fluxo de seiva, nas plantas com CVC, foram decorrentes do menor valor da condutância estomática, possivelmente causado pela colonização dos vasos do xilema pela Xylella fastidiosa.The objective of this work was to evaluate the effects of citrus variegated chlorosis (CVC on sap flow, gas exchanges and photochemical activity in 'Natal' sweet orange plants with and without CVC under field condition. Diurnal courses of sap flow, leaf water potential, CO2 assimilation rate and transpiration, stomatal conductance, potential and effective quantum efficiency of photosystem II were evaluated. The experiment was arranged in a random block design with five repetitions. Healthy plants showed sap flow values around 1.9 times higher than injured ones. Injured plants exhibited reductions of 43, 28 and 33% in CO2 assimilation rate, stomatal conductance and leaf transpiration, respectively. CVC-affected plants showed dynamic

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)

Long term storage effects of irradiated fuel elements on power distribution and reactivity

Energy Technology Data Exchange (ETDEWEB)

Ponzoni Filho, P.; Sato, Sadakatu; Santos, Teresinha Ipojuca Cardoso T.I.C.; 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 was used to calculate the pin by pin power distribution and reactivity for Angra 1 Power Plant, Cycle 5. The Angra 1 Cycle 5 core was loaded with several irradiated fuel elements which were stored in the Spent Fuel Pool (SFP) for more than 8 years. Generally, neutronic codes take into account the buildup and depletion of just a few key fission, products such as Sm-149. In this paper it is shown that the buildup effects of other fission products must be considered for fuel which has been out of the core for significant periods of time. Impacts of these other fission products can change core reactivity and power distribution. (author). 3 refs, 4 figs, 4 tabs.

Long term storage effects of irradiated fuel elements on power distribution and reactivity

International Nuclear Information System (INIS)

Ponzoni Filho, P.; Sato, Sadakatu; Santos, Teresinha Ipojuca Cardoso T.I.C.; Fernandes Vanderlei Borba; Fetterman, R.J.

1995-01-01

The ALPHA/PHOENIX-P/ANC (APA) code package was used to calculate the pin by pin power distribution and reactivity for Angra 1 Power Plant, Cycle 5. The Angra 1 Cycle 5 core was loaded with several irradiated fuel elements which were stored in the Spent Fuel Pool (SFP) for more than 8 years. Generally, neutronic codes take into account the buildup and depletion of just a few key fission, products such as Sm-149. In this paper it is shown that the buildup effects of other fission products must be considered for fuel which has been out of the core for significant periods of time. Impacts of these other fission products can change core reactivity and power distribution. (author). 3 refs, 4 figs, 4 tabs

Radionuclide dispersion and hydrodynamics of Ilha Grande Bay (Angra dos Reis, RJ) simulated from hypothetical accidental releases of liquid wastes

International Nuclear Information System (INIS)

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

2011-01-01

This study has the aim to assess the impact of accidental release of radionuclides postulate from a nuclear power reactor through environmental modeling of aquatic resources. In order to do that it was used computational models of hydrodynamic circulation and transport for the simulation of tritium dispersion caused by an accidental release in Ilha Grande Bay from the site of the future third plant in two circulation scenarios. The main difference between the scenarios is based on the enhancement of dilution of the highest concentrations in the last one. This dilution enhancement resulting in decreasing concentrations was observed only during the first two weeks, when they ranged from 1 x 10 9 to 5 x 10 5 Bq/m³ close to the Itaorna beach spreading just to Sandri Island. After 180 days, the plume could not be detected anymore in the bay, because their activities would be lower than the minimum detectable value (< 11 kBq/m³). (author)

DOS cones along atomic chains

International Nuclear Information System (INIS)

Kwapiński, Tomasz

2017-01-01

The electron transport properties of a linear atomic chain are studied theoretically within the tight-binding Hamiltonian and the Green’s function method. Variations of the local density of states (DOS) along the chain are investigated. They are crucial in scanning tunnelling experiments and give important insight into the electron transport mechanism and charge distribution inside chains. It is found that depending on the chain parity the local DOS at the Fermi level can form cone-like structures (DOS cones) along the chain. The general condition for the local DOS oscillations is obtained and the linear behaviour of the local density function is confirmed analytically. DOS cones are characterized by a linear decay towards the chain which is in contrast to the propagation properties of charge density waves, end states and Friedel oscillations in one-dimensional systems. We find that DOS cones can appear due to non-resonant electron transport, the spin–orbit scattering or for chains fabricated on a substrate with localized electrons. It is also shown that for imperfect chains (e.g. with a reduced coupling strength between two neighboring sites) a diamond-like structure of the local DOS along the chain appears. (paper)

DOS cones along atomic chains

Science.gov (United States)

Kwapiński, Tomasz

2017-03-01

The electron transport properties of a linear atomic chain are studied theoretically within the tight-binding Hamiltonian and the Green’s function method. Variations of the local density of states (DOS) along the chain are investigated. They are crucial in scanning tunnelling experiments and give important insight into the electron transport mechanism and charge distribution inside chains. It is found that depending on the chain parity the local DOS at the Fermi level can form cone-like structures (DOS cones) along the chain. The general condition for the local DOS oscillations is obtained and the linear behaviour of the local density function is confirmed analytically. DOS cones are characterized by a linear decay towards the chain which is in contrast to the propagation properties of charge density waves, end states and Friedel oscillations in one-dimensional systems. We find that DOS cones can appear due to non-resonant electron transport, the spin-orbit scattering or for chains fabricated on a substrate with localized electrons. It is also shown that for imperfect chains (e.g. with a reduced coupling strength between two neighboring sites) a diamond-like structure of the local DOS along the chain appears.

Entre a sanfona e a guitarra : hibridismos e identidades no rock'n'roll e heavy metal nacionais dos anos 90

OpenAIRE

Anselmo Sobrinho, Jorge Alexandre Fernandes

2013-01-01

O presente trabalho investiga as interações entre Música e História. O que pode uma ensinar à outra? É possível investigar uma época tendo uma canção como ponto de partida? Nossa proposta, portanto, é compreender como os grupos Angra, Sepultura e Raimundos representaram o Brasil em seus trabalhos da década de 1990. Tratou-se de investigar o choque entre o local (a música brasileira) e o global (os estilos de rock e metal de ca...

Waste transport and storage: Packaging refused due to failure in fulfilling QC/QA requirements

International Nuclear Information System (INIS)

Bruno, N.C.; Brandao, R.O.; Cavalcante, V.L.

2001-01-01

The Brazilian Nuclear Programme comprises several nuclear and radioactive facilities including Angra I Nuclear Power Plant, in operation since 1981, and Angra II, scheduled to start its operation by the end of 1999. Among the other ones there are uranium mining and milling facilities, four research reactors and one industrial facility of monazite sands processing. The already existing waste generation and near future ones claim to a solution regarding waste disposal. Although site selection criteria for waste repository in Brazil has already been defined, political and psychosocial aspects have strong impact. Trauma generated by Goiania's radiological accident has led to difficulties when decisions about this matter have to be taken. As a consequence, the waste generated by Angra I is still in a provisional facility at the plant's site. Wastes from the medical sources are stored in research institutes while waste generated from monazite sands is kept in a dam system. In order to overpack non-qualified packages containing waste of Angra I NPP, 70 lost concrete shielding packagings had to be provided. Based on successfully designed and tested prototype, packagings and respective lids specifications were written, approved and released for serial production. As part of packaging certification process, Brazilian Competent Authority performed a regulatory inspection and audit. Various findings, such as weaknesses in quality control and quality assurance records, unacceptable test results as well as failure in modify the concrete composition during a testified packaging manufacturing, led Competent Authority to refuse the packagings as containers until complementary tests could be performed. Further tests and evaluations led the Competent Authority to conclude that the manufacturer failed to both comply with requirements established in packaging specification and fulfill quality control/quality assurance requirements. As responsible by federal law for the reception and

Transient study of a PWR pressurizer

International Nuclear Information System (INIS)

Sotoma, H.

1973-01-01

An appropriate method for the calculation and transient performance of the pressurizer of a pressurized water reactor is presented. The study shows a digital program of simulation of pressurizer dynamics based on the First Law of Thermodynamic and Laws of Heat and Mass Transfer. The importance of the digital program that was written for a pressurizer of PWR, lies in the fact that, this can be of practical use in the safety analysis of a reactor of Angra dos Reis type with a power of about 500 M We. (author)

Gregarine Cephaloidophora communis mawrodiadi, 1908 in the barnacle Euraphia rhyzophorae, Oliveira, 1940 from Brazil

Directory of Open Access Journals (Sweden)

Lacombe Dyrce

2002-01-01

Full Text Available The gregarine Cephaloidophora communis was observed for the first time in Brazil in the barnacles Euraphia rhyzophorae collected in Angra dos Reis, Rio de Janeiro, Brazil, between 1990 and 1996. Histological studies showed growth phases of the parasite in specific parts of the digestive system. The intracellular forms occurred in the vacuoles of the intestinal cells. Syzygy was frequent, and the most common form following syzygy was cylindrical, with a single membrane. The cytoplasm of the gregarines was always irregular, dense, and occasionally presenting a dark stoch area.

Calculation of the external dose rate in the spent fuel pool for the case to use compact racks

International Nuclear Information System (INIS)

Passos, E.M. dos; Alves, A.S.M.

1988-01-01

The possible introduction of compact racks in the spent fuel pool of the Angra 1 Nuclear Power Plant largely inreases its storage capacity, but originates an increase of the gamma radiation sources. The precise evaluation of the effects of the adoption of this option on the external gamma dose rates and also on the thickness of the concrete shielding requires the utilization of sofisticated computer codes (QAD, ANISN), which allow the calculation of the gamma dose rates through thick shielding walls. This paper describes the utilized methodology for the calculation of the modified pool shieldings, showing the obtained results for the Angra 1 NPP case. The gamma dose rate was calculated with the point Kernel model, first analytically, and later through utilization of the tridimensional multigroup QAD computer code. (author) [pt

Plantas medicinais no tratamento do transtorno de ansiedade generalizada: uma revisão dos estudos clínicos controlados Medicinal plants for the treatment of generalized anxiety disorder: a review of controlled clinical studies

Directory of Open Access Journals (Sweden)

Thalita Thais Faustino

2010-12-01

Full Text Available OBJETIVO: Revisar os estudos clínicos controlados sobre a efetividade de plantas medicinais/fitoterápicos no transtorno de ansiedade generalizada. MÉTODO: Realizou-se uma busca (Medline, Web of Science, SciELO, Biblioteca Cochrane por artigos originais utilizando as palavras ["plant OR phytomed* OR extract OR herbal OR medicinal (OR specific name plants"] AND ("anxie* OR anxioly* OR tranquil* OR GAD", delimitada a "human OR clinical trial OR randomized controlled trial OR meta-analysis OR review" e à língua inglesa. Os critérios de inclusão foram: estudos randomizados, comparativos e duplo-cegos. RESULTADOS: Foram selecionados sete dos 267 artigos encontrados. O Piper methysticum (kava-kava foi o fitoterápico mais estudado, sendo sugerido um efeito ansiolítico. Entretanto, a maioria destes estudos incluiu outros transtornos de ansiedade e os dois estudos com transtorno de ansiedade generalizada apresentaram resultados contraditórios. Estudos isolados envolvendo Ginkgo biloba, Galphimia glauca, Matricaria recutita (camomila, Passiflora incarnata e Valeriana officinalis indicaram potencial efeito ansiolítico no transtorno de ansiedade generalizada. A Ginkgo biloba e a Matricaria recutita apresentaram um effect size ('d' de Cohen = 0,47 e 0,87 similar ou superior ao dos ansiolíticos atuais (0,17-0,38. Não foram localizados estudos com outras plantas. CONCLUSÃO: Apesar do potencial terapêutico dos fitoterápicos no transtorno de ansiedade generalizada, poucos ensaios clínicos controlados foram identificados, com a maioria apresentando limitações metodológicas.OBJECTIVE: This work aimed to identify controlled trials, which evaluated effectiveness of herbal medicines in subjects suffering generalized anxiety disorder. METHOD: Controlled studies (randomized, comparative with placebo and/or standard drug, double-blind were sought through electronic and hand-searches. The word strategy used "plant OR phytomed* OR extract OR herbal OR

REDUÇÃO DOS CUSTOS DA QUALIDADE COM MELHORIA DOS PROCESSOS: UM ESTUDO DE CASO

OpenAIRE

Oliveira, Gabriel Rech; Universidade de Caxias do Sul; Motta, Marta Elisete Ventura; Universidade de Caxias do Sul; Camargo, Maria Emilia; Universidade de Caxias do Sul; Tondolo, Vilmar Antonio Gonçalves; Universidade Federal de Rio Grande; Zanadrea, Gabriela; Universidade de Caxias do Sul; Russo, Suzana Leitão; Universidade Federal de Sergipe

2016-01-01

Com o objetivo de se tornarem competitivas, as empresas impulsionam a redução dos custos dos processos que impactam diretamente no preço do produto, destacando-se os custos de qualidade. Neste cenário, a busca pela qualidade total torna-se o caminho para a sobrevivência, devido ao fato da crescente exigência dos clientes para produtos com qualidade superior e preços baixos. Dentre os principais gastos que contribuem para o aumento dos custos da qualidade destacam-se a sucata e retrabalho de p...

Self-regulating the effortful "social dos".

Science.gov (United States)

Cortes, Kassandra; Kammrath, Lara K; Scholer, Abigail A; Peetz, Johanna

2014-03-01

In the current research, we explored differences in the self-regulation of the personal dos (i.e., engaging in active and effortful behaviors that benefit the self) and in the self-regulation of the social dos (engaging in those same effortful behaviors to benefit someone else). In 6 studies, we examined whether the same trait self-control abilities that predict task persistence on personal dos would also predict task persistence on social dos. That is, would the same behavior, such as persisting through a tedious and attentionally demanding task, show different associations with trait self-control when it is framed as benefitting the self versus someone else? In Studies 1-3, we directly compared the personal and social dos and found that trait self-control predicted self-reported and behavioral personal dos but not social dos, even when the behaviors were identical and when the incentives were matched. Instead, trait agreeableness--a trait linked to successful self-regulation within the social domain--predicted the social dos. Trait self-control did not predict the social dos even when task difficulty increased (Study 4), but it did predict the social don'ts, consistent with past research (Studies 5-6). The current studies provide support for the importance of distinguishing different domains of self-regulated behaviors and suggest that social dos can be successfully performed through routes other than traditional self-control abilities. (PsycINFO Database Record (c) 2014 APA, all rights reserved).

Representações e expectativas dos profissionais dos serviços de pediatria do Hospital de Braga relativamente à intervenção dos "Doutores Palhaços"

OpenAIRE

Almeida, Isabel Cristina Ferreira de

2012-01-01

Dissertação de mestrado em Estudos da Criança (área de especialização em Intervenção Psicossocial com Crianças, Jovens e Famílias) Neste estudo são dadas a conhecer as representações e expetativas dos profissionais de saúde dos serviços de pediatria do Hospital de Braga, relativamente ao trabalho dos palhaços profissionais da Operação Nariz Vermelho: os “Doutores Palhaços” (DP). A recolha dos dados realizou-se cerca de um mês antes do início da intervenção dos DP naquela unidad...

PCRELAP5: data calculation program for RELAP 5 code; PCRELAP5: programa de calculo dos dados de entrada para o codigo RELAP5

Energy Technology Data Exchange (ETDEWEB)

Silvestre, Larissa Jacome Barros

2016-07-01

Nuclear accidents in the world led to the establishment of rigorous criteria and requirements for nuclear power plant operations by the international regulatory bodies. By using specific computer programs, simulations of various accidents and transients likely to occur at any nuclear power plant are required for certifying and licensing a nuclear power plant. Based on this scenario, some sophisticated computational tools have been used such as the Reactor Excursion and Leak Analysis Program (RELAP5), which is the most widely used code for the thermo-hydraulic analysis of accidents and transients in nuclear reactors in Brazil and worldwide. A major difficulty in the simulation by using RELAP5 code is the amount of information required for the simulation of thermal-hydraulic accidents or transients. The preparation of the input data requires a great number of mathematical operations to calculate the geometry of the components. Thus, for those calculations performance and preparation of RELAP5 input data, a friendly mathematical preprocessor was designed. The Visual Basic for Application (VBA) for Microsoft Excel demonstrated to be an effective tool to perform a number of tasks in the development of the program. In order to meet the needs of RELAP5 users, the RELAP5 Calculation Program (Programa de Calculo do RELAP5 - PCRELAP5) was designed. The components of the code were codified; all entry cards including the optional cards of each one have been programmed. In addition, an English version for PCRELAP5 was provided. Furthermore, a friendly design was developed in order to minimize the time of preparation of input data and errors committed by users. In this work, the final version of this preprocessor was successfully applied for Safety Injection System (SIS) of Angra 2. (author)

Plantas medicinais usadas para a saúde bucal pela comunidade do bairro Santa Cruz, Chapada dos Guimarães, MT, Brasil Medicinal plants used for oral health in the Santa Cruz neighborhood, Chapada dos Guimarães, Mato Grosso State, Brazil

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Aneliza Meireles Borba

2006-12-01

Full Text Available Em Mato Grosso, populações tradicionais recorrem ao uso de espécies vegetais como alternativa terapêutica. Na cidade de Chapada dos Guimarães, o bairro Santa Cruz se destaca por abrigar famílias nascidas em áreas urbanas ou rurais que conservam esses conhecimentos transmitidos por gerações. Esta pesquisa tem como objetivo o levantamento das plantas medicinais utilizadas pela comunidade local, indicações terapêuticas, preparos e modos de uso visando a manutenção e recuperação da saúde bucal. Foram entrevistados 40 residentes, através de abordagem qualitativa, usando entrevista semi-estruturada. As espécies catalogadas foram depositadas para identificação no UFMT/Herbário Central. Foram citadas 87 espécies pertencentes a 48 famílias utilizadas na saúde bucal, encontradas no bioma Cerrado ou cultivadas nas residências. Conforme as afecções bucais citadas, as espécies utilizadas são: para erupção dentária: camomila (Matricaria chamomilla L.; candidíases, estomatites, gengivites e afta: açafrão (Crocus sativus L.; dor de dente: arnica-da-serra (Brickelia brasiliensis (Spreng. Robinson. A folha foi a parte da planta mais usada e o chá, por decocção, modo de preparo mais comum. Pessoas idosas, líderes comunitários, parteiras e benzedeiras entrevistados apresentaram um maior conhecimento sobre o assunto. Constatou-se que a comunidade utiliza espécies vegetais, nativas do cerrado ou exóticas, com finalidade terapêutica para manutenção e recuperação da saúde bucal, sendo uma alternativa tradicional, econômica e atuante.In the State of Mato Grosso, traditional populations turn to the use of many plant species as a therapeutic alternative. In the city of Chapada dos Guimarães, the Santa Cruz neighborhood is well known for harboring families from urban and rural communities who preserve this knowledge passed down through many generations. The objective of this research was to survey the medicinal plants used

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)

Preliminary evaluation of SACI-O code for the analysis of transients in a pressurized water reactor core

International Nuclear Information System (INIS)

Soares, P.A.; Sirimarco, L.F.; Veloso, M.A.F.

1979-03-01

SACI-O is a computer code which deals with the dynamics of the core of pressurized light water reactors (PWR). Its applicability is determined by the evaluation of the models used in the simulation of the several phenomena and processes which occur in the core during transients. This report presents a comparison between the results obtained with SACI-O and those presented in the Final Safety Analysis Report (FSAR) of Angra dos Reis Nuclear Station, Unit 1. Although some data used in the calculations done by Westinghouse are not known, there was a good agreement between the mentioned results. (Author) [pt

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

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

OS SACRAMENTAIS, SACRAMENTOS DOS POBRES

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Victor Codina

1990-01-01

Full Text Available Basta ter tido um pouco de experiência pastoral com setores populares, concretamente na América Latina, para constatar a importância dos sacramentais na vida cristã do povo. Além das manifestações de piedade popular que se costuma estudar sob a rubrica de religiosidade popular (peregrinações, festas de padroeiro, procissões..., gostaria de destacar aqui outros elementos mais estreitamente ligados ao mundo dos sacramentos, ainda que não formem parte dos sete sacramentos tridentinos.

Camponeses e esquecimento na Antiguidade Tardia: as revoltas dos bagaudas e dos circunceliões

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Uiran Gebara da Silva

2016-12-01

Full Text Available Esse artigo apresenta alguns dos problemas com os quais eu tive de lidar ao realizar um estudo comparativo entre dois conjuntos de revoltas rurais do Império Romano tardio: as revoltas dos bagaudas na Gália e dos circunceliões na África. O artigo toma como eixo articulador a hipótese lançada por E. A. Thompson sobre o papel do esquecimento na produção dos relatos antigos sobre os bagaudas e a problematiza. Num segundo momento o artigo trata do problema relacionado à compreensão do caráter social de ambos os grupos, levando em consideração os múltiplos relatos presentes nas fontes antigas e as divergentes interpretações modernas sobre eles, enfatizando a necessidade de se reconhecer a tópica da inversão social como um elemento que diferencia os relatos sobre os revoltosos daqueles sobre a bandidagem. Outro elemento importante é o reconhecimento da heterogeneidade dos discursos cristãos com relação às classes subalternas e aos revoltosos, que apontam não para um fortalecimento do patronato rural, mas para o enfraquecimento ou para a crise dessas relações no campo tardo-romano.

Effects of aging in containment spray injection system of PWR reactor containment; Efeitos do envelhecimento no sistema de injecao de borrifo da contencao de reatores a agua pressurizada

Energy Technology Data Exchange (ETDEWEB)

Borges, Diogo da S.; Lava, Deise D.; Affonso, Renato R.W.; Guimaraes, Antonio C.F.; Moreira, Maria de L., E-mail: diogosb@outlook.com, E-mail: deise_dy@hotmail.com, E-mail: raoniwa@yahoo.com.br, E-mail: tony@ien.gov.br, E-mail: malu@ien.gov.br [Instituto de Engenharia Nuclear (IEN/CNEN-RJ), Rio de Janeiro, RJ (Brazil)

2014-07-01

This paper presents a contribution to the study of the components aging process in commercial plants of Pressurized Water Reactors (PWR). The analysis is done by applying the method of Fault trees, Monte Carlo Method and Fussell-Vesely Importance Measurement. The study on the aging of nuclear plants, is related to economic factors involved directly with the extent of their operational life, and also provides important data on issues of safety. The most recent case involving the process of extending the life of a PWR plant can be seen in Angra 1 Nuclear Power Plant by investing $ 27 million in the installation of a new reactor cover. The corrective action generated an extension of the useful life of Angra 1 estimated in twenty years, and a great savings compared to the cost of building a new plant and the decommissioning of the first, if it had reached the operation time out 40 years. The extension of the lifetime of a nuclear power plant must be accompanied by special attention from the most sensitive components of the systems to the aging process. After the application of the methodology (aging analysis of Containment Spray Injection System (CSIS)) proposed in this paper, it can be seen that increasing the probability of failure of each component, due to the aging process, generate an increased general unavailability of the system that contains these basic components. The final results obtained were as expected and can contribute to the maintenance policy, preventing premature aging in nuclear power systems.

Effects of aging in containment spray injection system of PWR reactor containment

International Nuclear Information System (INIS)

Borges, Diogo da S.; Lava, Deise D.; Affonso, Renato R.W.; Guimaraes, Antonio C.F.; Moreira, Maria de L.

2014-01-01

This paper presents a contribution to the study of the components aging process in commercial plants of Pressurized Water Reactors (PWR). The analysis is done by applying the method of Fault trees, Monte Carlo Method and Fussell-Vesely Importance Measurement. The study on the aging of nuclear plants, is related to economic factors involved directly with the extent of their operational life, and also provides important data on issues of safety. The most recent case involving the process of extending the life of a PWR plant can be seen in Angra 1 Nuclear Power Plant by investing $ 27 million in the installation of a new reactor cover. The corrective action generated an extension of the useful life of Angra 1 estimated in twenty years, and a great savings compared to the cost of building a new plant and the decommissioning of the first, if it had reached the operation time out 40 years. The extension of the lifetime of a nuclear power plant must be accompanied by special attention from the most sensitive components of the systems to the aging process. After the application of the methodology (aging analysis of Containment Spray Injection System (CSIS)) proposed in this paper, it can be seen that increasing the probability of failure of each component, due to the aging process, generate an increased general unavailability of the system that contains these basic components. The final results obtained were as expected and can contribute to the maintenance policy, preventing premature aging in nuclear power systems

REDUÇÃO DOS CUSTOS DA QUALIDADE COM MELHORIA DOS PROCESSOS: UM ESTUDO DE CASO

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Gabriel Rech Oliveira

2016-06-01

Full Text Available Com o objetivo de se tornarem competitivas, as empresas impulsionam a redução dos custos dos processos que impactam diretamente no preço do produto, destacando-se os custos de qualidade. Neste cenário, a busca pela qualidade total torna-se o caminho para a sobrevivência, devido ao fato da crescente exigência dos clientes para produtos com qualidade superior e preços baixos. Dentre os principais gastos que contribuem para o aumento dos custos da qualidade destacam-se a sucata e retrabalho de produtos durante o processo produtivo. Devido à ocorrência desses fatores, este trabalho tem como finalidade analisar os custos da qualidade e propor melhorias no processo produtivo utilizando ferramentas da qualidade para reduzir os desperdícios com sucata. As fases do projeto envolvem o comprometimento e dedicação de equipes para levantar as principais causas dos principais problemas do processo de produção de tubos capilares em cobre, resultando na redução dos gastos com sucata e aumento da produtividade. As metodologias utilizadas para atingir os objetivos foram baseadas pesquisa exploratória e estudo de caso. A partir da redução de custo e aumento da produtividade alcançada, constata-se a importância deste trabalho envolvendo equipes responsáveis para a obtenção de resultados em curto prazo.

Modelling of the knowledge for monitoring expert systems in nuclear power plant safety

International Nuclear Information System (INIS)

Machado, Liana; Schirru, Roberto; Martinez, Aquilino S.

1997-01-01

Safety operation support systems for NPP faced problems of difficult solutions along their development. This work presents possible solution to such problems, and contribute to enhance the reliability and performance of such system using Artificial Intelligence. Knowledge representation is capital in this work since it express the dependence on variables in a rather natural way. therefore, it makes intrinsic the concepts of synchronism and concurrence in real-time approach. Other advantages are easy V and V processes and simplification of the system maintenance procedures. The inference process is carried out through the rules that are generated from knowledge base. These rules are charged following a conflict resolution optimized for time-real approach. The real application used to validate the model efficiency, consists in part of SICA (Integrated System of the Angra-1 Computers). The application results revealed very positive reducing the quantity of the SICA conventional software code programming. As far the system performance. the knowledge structures and the conflict resolution strategy adopted allowed for guarantee not only the time control for inference, but also a response time compatible with that requested for power plant safety support. (author) 12 refs., 4 figs

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

Energy Technology Data Exchange (ETDEWEB)

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

1997-12-31

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

The victory against Greenpeace-Brazil

International Nuclear Information System (INIS)

Anon.

2001-01-01

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

Neurobiologia dos transtornos do controle dos impulsos The neurobiology of impulse control disorders

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Wendol A Williams

2008-05-01

Full Text Available OBJETIVO: Revisar os artigos sobre substratos neurobiológicos dos transtornos do controle dos impulsos. O jogo patológico é o foco central desta revisão na medida em que a maioria dos estudos biológicos dos formalmente classificados como transtornos do controle dos impulsos examinou este transtorno. MÉTODO: Foi feita uma busca no banco de dados Medline de artigos publicados de 1966 até o presente para identificar aqueles relevantes para serem revisados neste artigo. DESFECHOS: Estudos pré-clínicos sugerem que a neuromodulação das monoaminas cerebrais está associada à tomada de decisões impulsivas e aos comportamentos de risco. Os estudos clínicos implicam diversos sistemas de neurotransmissores (serotoninérgico, dopaminérgico, adrenérgico e opióide na fisiopatologia do jogo patológico e de outros transtornos do controle dos impulsos. Estudos de neuroimagem preliminares têm indicado o córtex pré-frontal ventromedial e o estriato ventral como atuantes na fisiopatologia do jogo patológico e de outros transtornos do controle dos impulsos. As contribuições genéticas para o jogo patológico parecem substanciais e os estudos iniciais têm relacionado esse transtorno a polimorfismos alélicos específicos, ainda que os achados de varredura genômica ainda tenham que ser publicados. CONCLUSÃO: Mesmo que tenham sido logrados avanços significativos em nossa compreensão sobre os transtornos do controle dos impulsos, mais pesquisas são necessárias para ampliar o conhecimento existente e traduzir esses achados em avanços clínicos.OBJECTIVE: To review the neurobiological substrates of impulse control disorders. Pathological gambling is a main focus of the review in that most biological studies of the formal impulse control disorders have examined this disorder. METHOD: The medical database Medline from 1966 to present was searched to identify relevant articles that were subsequently reviewed to generate this manuscript

Participação dos Pais na Psicoterapia da Criança: Práticas dos Psicoterapeutas

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Luiz Ronaldo Freitas de Oliveira

Full Text Available Resumo A participação dos pais na psicoterapia de crianças é um tema controverso na literatura. Há autores a favor de uma abordagem mais intervencionista em relação aos pais e outros que circunscrevem seu papel à manutenção do tratamento e provimento de informações sobre a criança. O objetivo deste estudo exploratório, de levantamento, transversal, foi identificar experiências de psicoterapeutas de crianças brasileiros quanto às formas de inclusão dos pais no tratamento. Participaram 76 psicólogos, que responderam a um questionário on-line e as análises contemplaram estatística descritiva e análise de conteúdo. De acordo com os resultados, os respondentes foram predominantemente mulheres (89,5%, residentes na Região Sul (86,8%, entre 26 e 35 anos (53,9% e com até três anos de experiência clínica (43,4%. De maneira geral, os participantes incluem os pais na psicoterapia (76,3%; em entrevistas específicas (90,8%; coleta de informações (88,2%, para aconselhamento/orientação (72,4%; e para fortalecer a aliança terapêutica (61,8%. Riscos e benefícios da participação dos pais foram reportados e constituíram seis categorias: a criança como sintoma dos conflitos familiares; resistência dos pais à psicoterapia e às mudanças; cumprimento do contrato pelos pais; aliança terapêutica; compreensão da dinâmica familiar e dos sintomas da criança; e fortalecimento dos vínculos pais-filhos. Conclui-se que há tendência de inclusão dos pais, por parte dos psicoterapeutas, no processo de psicoterapia de crianças.

Safety indicators as a tool for operational safety evaluation of nuclear power plants

International Nuclear Information System (INIS)

Araujo, Jefferson Borges; Melo, Paulo Fernando Ferreira Frutuoso e; Schirru, Roberto

2009-01-01

Performance indicators have found a wide use in the conventional and nuclear industries. For the conventional industry, the goal is to optimize production, reducing loss of time with accidents, human error and equipment downtimes. In the nuclear industry, nuclear safety is an additional goal. This paper presents a general methodology to the establishment, selection and use of safety indicators for a two loop PWR plant, as Angra 1. The use of performance indicators is not new. The NRC has its own methodology and the IAEA presents methodology suggestions, but there is no detailed documentation about indicators selection, criteria and bases used. Additionally, only the NRC methodology performs a limited integrated evaluation. The study performed identifies areas considered critical for the plant operational safety. For each of these areas, strategic sub-areas are defined. For each strategic sub-area, specific safety indicators are defined. These proposed Safety Indicators are based on the contribution to risk considering a quantitative risk analysis. For each safety indicator, a goal, a bounded interval and proper bases are developed, to allow for a clear and comprehensive individual behavior evaluation. On the establishment of the intervals and boundaries, a probabilistic safety study, operational experience, international and national standards and technical specifications were used. Additionally, an integrated evaluation of the indicators, using expert systems, was done to obtain an overview of the plant general safety. This evaluation uses well-defined and clear rules and weights for each indicator to be considered. These rules were implemented by means of a computational language, on a friendly interface, so that it is possible to obtain a quick response about operational safety. This methodology can be used to identify situations where the plant safety is challenged, by giving a general overview of the plant operational condition. Additionally, this study can

Ação dos herbicidas atrazine e glufosinate de amônio no aproveitamento de nitrogênio pelas plantas de milho Herbicides atrazine and ammonium glufosinate action on nitrogen usage by corn plants

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N.G. Fleck

2001-08-01

Full Text Available A absorção vegetal do nitrogênio (N presente no solo ou fornecido via fertilização é regulada por um complexo enzimático que age de forma conjunta e ordenada na planta. O objetivo desta pesquisa foi investigar efeitos dos herbicidas atrazine e glufosinate de amônio na absorção do N pelas plantas e os efeitos que exercem em características de plantas de milho. Em um dos experimentos (experimento 1 foram testadas três doses de atrazine (0, 200 e 2.000 g i.a. ha-1 e de glufosinate de amônio (0; 40 e 80 g i.a. ha-1 e duas doses de N (0 e 90 kg ha-1. No segundo experimento (experimento 2 foram testados três tratamentos herbicidas (atrazine, 200 g i.a. ha-1; glufosinate de amônio, 40 g i.a. ha-1; atrazine + glufosinate de amônio, 200 + 40 g i.a. ha-1; e testemunha, duas fontes de N (uréia e nitrato de amônio e duas doses de N (0 e 100 kg ha-1. Os efeitos dos tratamentos foram avaliados aos 10 e 20 dias após a aplicação (DAA dos herbicidas, no experimento 1, e quando as plantas de milho apresentavam 10 folhas desenvolvidas (15 DAA e no pendoamento do milho (40 DAA, no experimento 2. A partir da análise dos resultados obtidos, constatou-se que aplicação de N em cobertura na cultura do milho promove aumento na maioria dos componentes do rendimento e incrementa em 35% o rendimento de grãos e que esse efeito ocorre de forma independente da fonte de N utilizada: uréia ou nitrato de amônio. Não ocorre interação entre os fatores relacionados aos herbicidas inibidores do fotossistema II (atrazine e da síntese de glutamina (glufosinate de amônio e aplicação de N em cobertura no milho. O uso destes herbicidas em doses reduzidas (abaixo da recomendada, aplicados isoladamente ou combinados, não afetou o rendimento de grãos nem os componentes do rendimento da cultura do milho. O herbicida atrazine tem pequena influência nos teores de clorofila e de N em milho, mas, em algumas situações, sua ação é favorável, especialmente

Influência de variáveis laborais na qualidade de vida dos anestesiologistas da cidade de João Pessoa

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Maria de Fátima Oliveira dos Santos

2011-06-01

Full Text Available JUSTIFICATIVA E OBJETIVOS: O anestesiologista trabalha sob grande pressão, por lidar com doença, dor, sofrimento e morte. A exposição desse profissional aos efeitos de fadiga, fatores físicos, químicos e biológicos pode causar transtornos físicos e psicológicos. Este estudo objetivou conhecer as influências das variáveis laborais na qualidade de vida (QV dos anestesiologistas da cidade de João Pessoa. MÉTODO: Estudo descritivo, de corte transversal e com abordagem quantitativa, composto por 83 médicos que responderam ao instrumento genérico para avaliar a QV, proposto pela Organização Mundial da Saúde. Os dados foram analisados por estatísticas descritivas e testes de comparação de média. O nível de significância adotado para as análises foi de 5%. RESULTADOS: As análises demonstraram que as variáveis laborais relacionadas ao total de horas de plantões semanais, às horas trabalhadas, ao hábito de dormir no pós-plantão e nos intervalos dos plantões e à prática de atividade física pelo profissional se correlacionaram com a QV. Verificou-se também que há diferença estatisticamente significativa entre os domínios da escala de QV e o número de horas de trabalho dos participantes. Por outro lado, a renda mensal exerce influência sobre a QV (p < 0,05 apenas no domínio meio ambiente. CONCLUSÕES: Observou-se que as variáveis laborais correlacionam-se significativamente com a QV. Além de haver diferença estatística expressiva entre os domínios da escala de QV e o número de horas de trabalho dos participantes, verificou-se que há também essa mesma divergência quanto ao domínio meio ambiente e à renda mensal.

Meteoritic basalts: the nakhlites, their parental magmas, cooling rates, and equivalents on Earth. Final technical report

International Nuclear Information System (INIS)

Treiman, A.H.

1987-07-01

Proposed one-bar phase equilibrium experiments, designed to determine the compositions of the nakhlites' parental magmas, are in progress. Proposed field studies on Earth, designed to find occurrences of rocks like the nakhlites, were extraordinarily successful. Other work supported in the past year included: attendance at the 1986 national meeting of the Geological Society of America; attendance at the 18th Lunar and Planetary Science Conference; completion and publication of a study of core formation in the SNC parent body; initiation of a study of the flux of SNC meteorites onto the Earth; and initiation of petrologic study of the Angra dos Reis achondrite

Informatividade dos lucros contábeis e divulgação dos ativos biológicos: evidências brasileiras

OpenAIRE

Holanda, Allan Pinheiro

2013-01-01

A pesquisa tem o objetivo de investigar a influência exercida pela divulgação dos ativos biológicos na informatividade dos lucros contábeis nas firmas brasileiras listadas na BM&FBovespa, considerando-se o período de 2010 a 2011. Para a investigação da informatividade dos ativos biológicos foi utilizada a adaptação dos modelos propostos por Easton e Harris (1991) e Francis e Schipper (1999). Os ativos biológicos, por sua vez, foram mensurados de duas maneiras, pela simples existência da c...

Comparison of computational performance of GA and PSO optimization techniques when designing similar systems - Typical PWR core case

Energy Technology Data Exchange (ETDEWEB)

Souza Lima, Carlos A. [Instituto de Engenharia Nuclear - Divisao de Reatores/PPGIEN, Rua Helio de Almeida 75, Cidade Universitaria - Ilha do Fundao, P.O. Box: 68550 - Zip Code: 21941-972, Rio de Janeiro (Brazil); Instituto Politecnico, Universidade do Estado do Rio de Janeiro, Pos-Graduacao em Modelagem Computacional, Rua Alberto Rangel - s/n, Vila Nova, Nova Friburgo, Zip Code: 28630-050, Nova Friburgo (Brazil); Lapa, Celso Marcelo F.; Pereira, Claudio Marcio do N.A. [Instituto de Engenharia Nuclear - Divisao de Reatores/PPGIEN, Rua Helio de Almeida 75, Cidade Universitaria - Ilha do Fundao, P.O. Box: 68550 - Zip Code: 21941-972, Rio de Janeiro (Brazil); Instituto Nacional de Ciencia e Tecnologia de Reatores Nucleares Inovadores (INCT) (Brazil); Cunha, Joao J. da [Eletronuclear Eletrobras Termonuclear - Gerencia de Analise de Seguranca Nuclear, Rua da Candelaria, 65, 7 andar. Centro, Zip Code: 20091-906, Rio de Janeiro (Brazil); Alvim, Antonio Carlos M. [Universidade Federal do Rio de Janeiro, COPPE/Nuclear, Cidade Universitaria - Ilha do Fundao s/n, P.O.Box 68509 - Zip Code: 21945-970, Rio de Janeiro (Brazil); Instituto Nacional de Ciencia e Tecnologia de Reatores Nucleares Inovadores (INCT) (Brazil)

2011-06-15

Research highlights: > Performance of PSO and GA techniques applied to similar system design. > This work uses ANGRA1 (two loop PWR) core as a prototype. > Results indicate that PSO technique is more adequate than GA to solve this kind of problem. - Abstract: This paper compares the performance of two optimization techniques, particle swarm optimization (PSO) and genetic algorithm (GA) applied to the design a typical reduced scale two loop Pressurized Water Reactor (PWR) core, at full power in single phase forced circulation flow. This comparison aims at analyzing the performance in reaching the global optimum, considering that both heuristics are based on population search methods, that is, methods whose population (candidate solution set) evolve from one generation to the next using a combination of deterministic and probabilistic rules. The simulated PWR, similar to ANGRA 1 power plant, was used as a case example to compare the performance of PSO and GA. Results from simulations indicated that PSO is more adequate to solve this kind of problem.

A class-based search for the in-core fuel management optimization of a pressurized water reactor

International Nuclear Information System (INIS)

Alvarenga de Moura Meneses, Anderson; Rancoita, Paola; Schirru, Roberto; Gambardella, Luca Maria

2010-01-01

The In-Core Fuel Management Optimization (ICFMO) is a prominent problem in nuclear engineering, with high complexity and studied for more than 40 years. Besides manual optimization and knowledge-based methods, optimization metaheuristics such as Genetic Algorithms, Ant Colony Optimization and Particle Swarm Optimization have yielded outstanding results for the ICFMO. In the present article, the Class-Based Search (CBS) is presented for application to the ICFMO. It is a novel metaheuristic approach that performs the search based on the main nuclear characteristics of the fuel assemblies, such as reactivity. The CBS is then compared to the one of the state-of-art algorithms applied to the ICFMO, the Particle Swarm Optimization. Experiments were performed for the optimization of Angra 1 Nuclear Power Plant, located at the Southeast of Brazil. The CBS presented noticeable performance, providing Loading Patterns that yield a higher average of Effective Full Power Days in the simulation of Angra 1 NPP operation, according to our methodology.

A class-based search for the in-core fuel management optimization of a pressurized water reactor

Energy Technology Data Exchange (ETDEWEB)

Alvarenga de Moura Meneses, Anderson, E-mail: ameneses@lmp.ufrj.b [Federal University of Rio de Janeiro, COPPE, Nuclear Engineering Program, CP 68509, CEP 21.941-972, Rio de Janeiro, RJ (Brazil); Rancoita, Paola [IDSIA (Dalle Molle Institute for Artificial Intelligence), Galleria 2, 6982 Manno-Lugano, TI (Switzerland); Mathematics Department, Universita degli Studi di Milano (Italy); Schirru, Roberto [Federal University of Rio de Janeiro, COPPE, Nuclear Engineering Program, CP 68509, CEP 21.941-972, Rio de Janeiro, RJ (Brazil); Gambardella, Luca Maria [IDSIA (Dalle Molle Institute for Artificial Intelligence), Galleria 2, 6982 Manno-Lugano, TI (Switzerland)

2010-11-15

The In-Core Fuel Management Optimization (ICFMO) is a prominent problem in nuclear engineering, with high complexity and studied for more than 40 years. Besides manual optimization and knowledge-based methods, optimization metaheuristics such as Genetic Algorithms, Ant Colony Optimization and Particle Swarm Optimization have yielded outstanding results for the ICFMO. In the present article, the Class-Based Search (CBS) is presented for application to the ICFMO. It is a novel metaheuristic approach that performs the search based on the main nuclear characteristics of the fuel assemblies, such as reactivity. The CBS is then compared to the one of the state-of-art algorithms applied to the ICFMO, the Particle Swarm Optimization. Experiments were performed for the optimization of Angra 1 Nuclear Power Plant, located at the Southeast of Brazil. The CBS presented noticeable performance, providing Loading Patterns that yield a higher average of Effective Full Power Days in the simulation of Angra 1 NPP operation, according to our methodology.

O dimorfismo dos ramos em Coffea arabica L.

Directory of Open Access Journals (Sweden)

A. Carvalho

1950-06-01

principal da planta ; (às vêzes também aí ocorrem gemas de um terceiro tipo, que dão origem a inflorescências; e as axilas das fôlhas dos ramos plagiotrópicos sòmente encerram gemas que dão nascimento a ramos plagiotrópicos ou a inflorescências, mas nunca a ramos ortotrópicos ; em algumas combinações genéticas, as gemas de inflorescências não se desenvolvem, sendo intensa a produção de ramos laterais secundários na época normal de florescimento do cafeeiro. Foram feitas várias combinações de enxertos, verificando-se que não há mudanças no hábito de crescimento dos ramos. A diferenciação dos ramos plagiotrópicos revelou ser permanente e imutável. O mesmo fenômeno se verifica em estacas enraizadas. Depois de se mencionar a variabilidade do ângulo que os ramos laterais formam com a haste principal, fêz-se referência especial à variedade erecta de Coffea arabica, que constitui uma mutação dominante em relação ao tipo normal, caraterizando-se por possuir ramos laterais verticais. As experiências de enxertia revelaram que, mesmo nesta variação, persiste o dimorfismo, pois as plantas obtidas pela enxertia de ramos laterais só formam arbustos baixos, apesar de os ramos crescerem em sentido vertical. Também aqui, para se obter uma planta enxertada erecta normal, é preciso enxertar a extremidade de um ramo ponteiro. Foram citadas algumas hipóteses que talvez expliquem êsse fenômeno. Chamou-se a atenção para o fato de a diferenciação já se processar nas gemas, apesar de os dois tipos de gemas vegetativas coexistirem, como acontece nas axilas das fôlhas, ao longo da haste principal.Dimorphism has been noted to occur in the branches of various plant genera such as Gossypium, Theobroma, Hedera, Musa, Araucária, Castilla and also in Coffea. This phenomenon is characterised by a somatic differentiation, which is usually of a permanent nature and can be propagated vegetatively . With Coffea, this dimorphism is characterised by

O Jardim dos Sonhos

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RAUL CÂNOVAS

2010-06-01

Full Text Available O jardim dos sonhos sempre foi um ideal dos homens. No Antigo Egito, já se falava em um jardim sempre verde para onde as pessoas de bom coração iam após a morte. E na mitologia grega, um lindo jardim era palco das festas bucólicas dos deuses. As grandes religiões também citavam jardins como paraísos, como o Jardim do Éden. Neste artigo, Raul Cânovas nos leva a refletir sobre o sentido de um “jardim perfeito”, sem tratar a perfeição como apenas plástica e estruturada com exatidão, mas referindo-se a um jardim que nos inspire e emocione, emancipado de modismos passageiros. O paisagista também nos alerta sobre as condições mutáveis de um jardim, que nunca está finalizado. O paisagismo não é apenas técnica; é também sensibilidade, utilidade, sustentabilidade e equilíbrio das forças da natureza.

Os Fungos no Funcionamento dos Ecossistemas Florestais

OpenAIRE

Santos-Silva, Celeste; Machado, Helena

2011-01-01

Os fungos no funcionamento dos ecossistemas Florestais: Papel dos fungos sapróbios na degradação da matériaorgânica Papel dos fungos micorrízicos na nutrição e saúde das árvores Diversidade fúngica e estabilidade das florestas Relações entre os fungos e os animais Doenças radiculares associadas ao declínio do montado de sobro e azinho

Reduction of radioactive waste volumes by using supercompaction technique

International Nuclear Information System (INIS)

Santos, John Wagner A.; Lima, Sandro Leonardo N. de

2007-01-01

The Radioactive Waste Management Program from ELETRONUCLEAR comprises the use of techniques and technologies to reduce the volumes of processed radwaste, which aims to improve the storage capacity and also assure the protection for the environment, as part of ELETRONUCLEAR's business strategy. The Angra site stores radwaste in temporary storage facilities, named Store number 1 and Store number 2, which are routinely managed and surveyed periodically by the ELETRONUCLEAR's Radiological Protection Division and submitted to frequent CNEN inspections. Medium level and low level radwastes are stored on those storage facilities. In January 2005, ELETRONUCLEAR decided to realize the Supercompaction of drums with compacted radwaste, mostly from Angra 1 and a little from Angra 2. By that time, the Store 1 was near to achieve its nominal capacity; this situation demanded a prompt response, and the chosen option was to proceed the supercompaction by using a mobile supercompactor unit. In April, 2006, two thousand and twenty seven drums of 200 liters were supercompacted at the plant site, and as a result, the initial storage area became sufficient to store drums for about five more years of operation. The supercompaction process is achieved by using a hydraulic press with extra high force. The pellets (crashed drums) were placed inside a special metallic box with 2500 liters of capacity (the overpack). This operation produced 128 full boxes, varying from 12 to 19 pellets inside each box, and the boxes were stored inside the Store 1. (author)

A percepção dos trabalhadores de enfermagem sobre o manejo dos resíduos químicos perigosos

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Taiza Florêncio Costa

2012-12-01

Full Text Available Este estudo objetivou identificar a percepção dos trabalhadores de enfermagem sobre o manejo dos resíduos químicos perigosos no Hospital Universitário da Universidade de São Paulo e elaborar uma proposta para o manejo desses resíduos. Trata-se de pesquisa de abordagem qualitativa, cuja amostra foi intencional, composta por dezoito trabalhadores de enfermagem. A coleta de dados foi realizada por meio da técnica de grupo focal. Com a análise temática foram identificadas quatro categorias que evidenciaram a deficiência de treinamento nas etapas do manejo, como a primeira dificuldade expressa, tendo aparecido ainda o desconhecimento da exposição e impactos, assim como o uso dos equipamentos de proteção individual em detrimento da proteção coletiva, seguidos das sugestões quanto às medidas de competência institucional e dos trabalhadores para o manejo seguro dos resíduos químicos perigosos. Esses dados permitiram recomendar propostas para o manejo adequado dos resíduos químicos perigosos pela enfermagem.

A percepção dos trabalhadores de enfermagem sobre o manejo dos resíduos químicos perigosos

Directory of Open Access Journals (Sweden)

Taiza Florêncio Costa

Full Text Available Este estudo objetivou identificar a percepção dos trabalhadores de enfermagem sobre o manejo dos resíduos químicos perigosos no Hospital Universitário da Universidade de São Paulo e elaborar uma proposta para o manejo desses resíduos. Trata-se de pesquisa de abordagem qualitativa, cuja amostra foi intencional, composta por dezoito trabalhadores de enfermagem. A coleta de dados foi realizada por meio da técnica de grupo focal. Com a análise temática foram identificadas quatro categorias que evidenciaram a deficiência de treinamento nas etapas do manejo, como a primeira dificuldade expressa, tendo aparecido ainda o desconhecimento da exposição e impactos, assim como o uso dos equipamentos de proteção individual em detrimento da proteção coletiva, seguidos das sugestões quanto às medidas de competência institucional e dos trabalhadores para o manejo seguro dos resíduos químicos perigosos. Esses dados permitiram recomendar propostas para o manejo adequado dos resíduos químicos perigosos pela enfermagem.

Organization and management of design

International Nuclear Information System (INIS)

Danelli, I.G.

1987-01-01

The steps for implementation of designs, the organization and the management of PROMON are presented. The Design of Angra-1 reactor and the Design of Angra-2 Pipes, are presented as examples. (M.C.K.) [pt

A Teoria dos Conjuntos de Cantor

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Antônio Acra Freiria

1992-07-01

Full Text Available No final dos anos 50 e começo doe anos 60, houve uma reformulação significativa da Matemática no Brasil. Sob a bandeira do modernismo, seus defensores buscaram inovações no ensino da Matemática. Dessa forma, os reformistas se concentraram essencialmente na linguagem abusiva e no formalismo da Teoria dos Conjuntos, o que trouxe mais danos do que benefícios do ensino da Matemática de 1º e 2ºgraus. A linguagem formal da Teoria dos Conjuntos é porém sua parte menos importante. A teoria criada por Cantor tão logo revelou-se como o fundamento de toda a Matemática, possibilitando o desenvolvimento de novas disciplinas, como a Topologia, a Algebra Abstrata, a Teoria da Medida e Integração, a Teoria da Probabilidade e a Análise Funcional. O objetivo deste trabalho é um relato sucinto de como surgiu essa teoria, apresentando o "Conjunto de Cantor" como um dos mais ricos exemplos de "Conjunto perfeito" encontrados na literatura matemática.

O EQUIVALENTE EM CARBONATO DE CÁLCIO DOS CORRETIVOS DA ACIDEZ DOS SOLOS

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J.C. ALCARDE

1996-05-01

Full Text Available Os corretivos da acidez dos solos podem ter dois equivalentes em carbonato de cálcio: um, calculado pelos teores de cálcio e magnésio utilizando a expressão: % CaO x 1,79 + % MgO x 2,48 = %ECaCO3; outro, determinado analiticamente pelo poder ou valor de neutralização. Para uma mesma amostra ambos os valores deveriam coincidir, o que raramente acontece. Diversas hipóteses foram levantadas para justificar essa diferença. Os resultados deste trabalho permitiram inferir que nem todo o cálcio e magnésio dos corretivos devem estar associados às bases quimicamente efetivas mas também a fosfato, sulfato ou outras bases de forças inexpressivas; também os constituintes neutralizantes podem estar aprisionados em cristais de outros componentes dos corretivos, como sílica por exemplo, que só são atingidos por um ataque mais enérgico da amostra. Como conclusão, a avaliação química atual dos corretivos da acidez dos solos pode não estar se compatibilizando com o comportamento agrícola desses produtos.Agricultural liming materials can have two calcium carbonate equivalents: one calculated in function of calcium and magnesium oxide percentages, by the expression: % CaO x 1,79 + % MgO x 2,48 = %ECaCO3; and the other determined analytically by the neutralization power or value. For one sample, both values should be similar, however, this rarely occurs. Several hypoteses were raised to justify the difference. Results of this research permit to infer that not all calcium and magnesium should be associated to the chemically effective bases, but they are also associated to phosphate, sulphate or other bases of inexpressive strength. It is also possible that, the neutralizing components could be captured inside cristals, like silica for example, which react only after a strong solubilization of the sample. It is concluded that the chemical evaluation of agricultural liming materials at the present time cannot explain the agronomical behaviour of

Tratamento descentralizado de esgotos de empreendimentos comercial e residencial empregando a ecotecnologia dos wetlandsconstruídos

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Camila Maria Trein

Full Text Available ResumoO objetivo deste trabalho é apresentar o desempenho dos wetlandsconstruídos de fluxo vertical (WCFV submetidos a diferentes carregamentos orgânicos e hidráulicos, a fim de incorporar esta tecnologia como opção no tratamento descentralizado de esgotos em empreendimentos comercial e residencial. Avaliou-se ao longo de dois anos dois sistemas de tratamento: (i sistema 1 - empreendimento comercial: composto por um Reator Aneróbio Compartimentado (RAC seguido de WCFV (área superficial total de 189 m2; (ii sistema 2 - condomínio residencial: composto pela sequência RAC e WCFV com fundo saturado (área superficial total de 3.141 m2. Com o monitoramento operacional e analítico junto aos wetlands, determinaram-se taxas hidráulicas aplicadas variando de 130 a 12 mm.d-1 e carregamentos médios aplicados variando de 87 a 1,9 gDQO m-2.d-1 para os sistemas 1 e 2, respectivamente. Os distintos carregamentos foram resultantes da demanda atual dos empreendimentos, sendo que os sistemas 1 e 2 apresentaram eficiências médias globais de remoção em termos de concentração de 75% e 93% para DQO, de 88% e 97% para DBO e de 83% e 94% para SS, respectivamente. A partir dos resultados obtidos, recomenda-se a utilização dos WCFV como alternativa tecnológica de tratamento de esgoto sob o contexto da descentralização.

O Cabimento dos Embargos de Divergência

OpenAIRE

LOURENCO, S. R.

2012-01-01

A presente pesquisa objetiva demonstrar os embargos de divergência com enfoque nos elementos processuais do cabimento de tal modalidade recursal em nosso ordenamento jurídico. Para tanto, investigaremos os aspectos gerais dos embargos de divergência, a partir da análise dos elementos históricos enquanto a criação do instituto, como também sua finalidade e classificação no ordenamento jurídico brasileiro. Após, analisaremos o requisito de admissibilidade do cabimento dos embargo...

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)

Teaching Bibliometric Analysis and MS/DOS Commands.

Science.gov (United States)

Dou, Henri; And Others

1988-01-01

Outlines the steps involved in bibliometric studies, and demonstrates the ability to execute simple studies on microcomputers by downloading files using only the capability of MS/DOS. Detailed illustrations of the MS/DOS commands used are provided. (eight references) (CLB)

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

Models of signal validation using artificial intelligence techniques applied to a nuclear reactor

International Nuclear Information System (INIS)

Oliveira, Mauro V.; Schirru, Roberto

2000-01-01

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

O ecologismo dos pobres

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Juan Martinez ALIER

1997-12-01

Full Text Available O ecologísmo tem colocado em cheque as leis capitalistas de mercado, principalmente na sua fase globalizada, devido à apropriação e exploração inconsequente dos recursos naturais. Ao mesmo tempo tem apontado que o meio ambiente não se reduz ao tratamento somente cientifico da natureza. O presente artigo ressalta aspectos importantes do ecologísmo como a participação das mulheres, o marxismo, o neo-narodnismo, etc. e é rico em exemplos de problemas ambientais decorrentes das relações de produção. O ecologísmo dos pobres é apontado como uma perspectiva necessária às lutas ambientais no Terceiro Mundo.

Negro é o inferno! Um ensaio sobre as cores dos homens, dos demônios e dos deuses

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Walker Douglas Pincerati

2016-10-01

Full Text Available http://dx.doi.org/10.5007/1984-8420.2016v17n2p46 Problematiza-se o par negro.branco na formação social brasileira, trabalhando a hipótese de que ‘negro’ não é cor, mas a metáfora do corpo do ser infernal. Estatísticas oficiais, a história da formação do Brasil, um enunciado de um Deputado Federal Pastor, o quadro A libertação dos Escravos de Pedro Américo (1889 e a história da construção das catedrais góticas medievais são evocadas para analisá-lo, desde o ponto de vista linguístico-discursivo. Nota-se, destarte, uma longa história do alinhamento dos significantes branco-luz-deuses-céu-liberdade... e negro-escuridão-demônios-inferno-escravidão... atuando ainda no nosso país.

COMPARAÇÃO DOS MÉTODOS OFICIAIS DE ANÁLISE E CROMATOGRÁFICOS PARA A DETERMINAÇÃO DOS TEORES DE ALDEÍDOS E ÁCIDOS EM BEBIDAS ALCOÓLICAS

OpenAIRE

NASCIMENTO,Ronaldo F.; CERRONI,Jefferson L.; CARDOSO,Daniel R.; LIMA NETO,Benedito Santos; FRANCO,Douglas W.

1998-01-01

É apresentado um estudo comparativo entre os métodos oficiais e cromatográficos para a análise de aldeídos e de ácidos em bebidas alcoólicas. Foram analisadas trinta e cinco amostras de destilados alcoólicos. Com respeito a determinação dos teores totais de aldeídos e de ácidos. Os métodos oficiais e cromatográficos apresentam similar exatidão e reprodutibilidade. Entretanto, apenas os métodos cromatográficos permitem identificar e quantificar os componentes de cada série homologa. As metodol...

¿DOS CULTURAS O DOS PREJUICIOS? UN APORTE PARA LA COMPRENSION

Directory of Open Access Journals (Sweden)

Edelmira Ochoa Camacho

2015-12-01

Full Text Available Uno de los propósitos explícitos en el proceso de educar debería ser el favorecer la comprensión de la mirada interdisciplinar del conocimiento, que aporte a la formación de personas integrales, curiosas, críticas e imaginativas (Mendoza, Callejas, Porras y Moralejo 2011, y la universidad juega un papel importante en este aspecto. Por lo que esta investigación busca contribuir al acercamiento de las dos culturas, la humanística y la  científico-tecnológica,  separadas  tradicionalmente  por  los  prejuicios  que  han propiciado la incomprensión y el rechazo hacia los otros.  Esta investigación forma parte del Proyecto de Enseñanza y Aprendizaje sobre la Naturaleza de la Ciencia y la Tecnología (EANCYT. En este trabajo se presentan los resultados globales obtenidos en un curso de Electiva interdisciplinar titulado “Consolidación de la cultura científica” de nivel universitario, donde se aplicó una Secuencia de Enseñanza y Aprendizaje (SEA  denominada “¿Dos culturas o dos prejuicios?”, diseñada por Mendoza et al (2011, que tuvo como uno de los objetivos que los estudiantes interpreten las relaciones entre las ciencias y las humanidades con base en la lectura de textos y la discusión con pares. Antes  y  después  de  la  aplicación  de  la  SEA,  se  aplicó  un  test  a  los  estudiantes estructurado  por    6 cuestiones  pertenecientes  al  Cuestionario  de Opiniones  sobre Ciencia-Tecnología-Sociedad, COCTS (Manassero, Vázquez y Acevedo, 2003. Luego de la aplicación de la SEA se obtuvieron mayores índices (que significan opiniones más adecuadas en las cuestiones referidas a unión de dos culturas, valores y estándares, decisiones sociales, ética e instituciones educativas.

Priority of areas for agricultural radiovulnerability mapping

Energy Technology Data Exchange (ETDEWEB)

Rochedo, Elaine R.R.; Igreja, Eduardo, E-mail: elainerochedo@gmail.com, E-mail: eduigreja@gmail.com [Instituto Militar de Engenharia (IME), Rio de Janeiro, RJ (Brazil). Programa de Engenharia Nuclear; Wasserman, Maria Angelica V., E-mail: mwasserman@ien.gov.br [Instituto de Engenharia Nuclear (IEN/CNEN-RJ), Rio de Janeiro, RJ (Brazil); Perez, Daniel V., E-mail: chpd@cnps.embrapa.br [Empresa Brasileira de Pesquisa Agropecuaria (EMBRAPA), Rio de Janeiro, RJ (Brazil). Centro Nacional de Pesquisa de Solos; Rochedo, Pedro R.R., E-mail: rochedopedro@gmail.com [Universidade Federal do Rio de Janeiro (UFRJ), RJ (Brazil). Programa de Planejamento Energetico; Silva, Diogo N.G., E-mail: diogongs@gmail.com [Universidade Federal do Rio de Janeiro (UFRJ), RJ (Brazil). Instituto de Biofisica Carlos Chagas Filho

2013-07-01

The methodology for classifying areas according to soil properties for the vulnerability to a {sup 137}Cs contamination is of high importance to the preparedness related to nuclear and/or radiological accidents that lead to release of radionuclides to the environment with the consequent contamination of agricultural areas. The priority of research for agricultural areas should then focus on the surrounding areas of nuclear power plant that have higher probability of public exposure through the ingestion pathway. The objective of this work was to create a rank order for priority of areas to be mapped based on EMBRAPA database on soil properties. The 16 municipalities previously selected to define parameters for dose assessment simulations related to the Brazilian Nuclear Power Plants, located in the district of Angra dos Reis, Rio de Janeiro, have been investigated in order to create this rank order to direct the research on radio vulnerability mapping, considering their relevance to public exposure based on their agricultural productivity. The two aspects selected in this study account for the maximum loss of income and to the collective doses that can be averted due to the banning of agricultural products. These quantities are inputs to optimization analysis. The priority defined shall then guide research on both the adequate values for the transfer factors and on the agricultural countermeasures suitable to each area according to the cause(s) of their vulnerability and their typical agricultural crops. (author)

Priority of areas for agricultural radiovulnerability mapping

International Nuclear Information System (INIS)

Rochedo, Elaine R.R.; Igreja, Eduardo; Perez, Daniel V.; Rochedo, Pedro R.R.; Silva, Diogo N.G.

2013-01-01

The methodology for classifying areas according to soil properties for the vulnerability to a 137 Cs contamination is of high importance to the preparedness related to nuclear and/or radiological accidents that lead to release of radionuclides to the environment with the consequent contamination of agricultural areas. The priority of research for agricultural areas should then focus on the surrounding areas of nuclear power plant that have higher probability of public exposure through the ingestion pathway. The objective of this work was to create a rank order for priority of areas to be mapped based on EMBRAPA database on soil properties. The 16 municipalities previously selected to define parameters for dose assessment simulations related to the Brazilian Nuclear Power Plants, located in the district of Angra dos Reis, Rio de Janeiro, have been investigated in order to create this rank order to direct the research on radio vulnerability mapping, considering their relevance to public exposure based on their agricultural productivity. The two aspects selected in this study account for the maximum loss of income and to the collective doses that can be averted due to the banning of agricultural products. These quantities are inputs to optimization analysis. The priority defined shall then guide research on both the adequate values for the transfer factors and on the agricultural countermeasures suitable to each area according to the cause(s) of their vulnerability and their typical agricultural crops. (author)

Electrostaticspray preparation and properties of RDX/DOS composites

Directory of Open Access Journals (Sweden)

Jian Yao

2017-08-01

Full Text Available A composite explosive based on 1, 3, 5-trinitro-1, 3, 5-triazinane (RDX was prepared by electrostaticspray method with dioctyl sebacate (DOS as desensitizer. After preparation, the particle size and crystal structure were characterized and chemical features, such as chemical bonds, functional groups, thermal decomposition parameters and mechanical sensitivity were investigated as well. In terms of the morphologies of the composites, the particle sizes were in the range of 1–3 μm. Compared with RDX, the crystal types, chemical bonds and functional groups of the RDX/DOS composites were unchanged. The activation energy of the composites was lower than that of raw RDX, and the 3wt % DOS composites had the lowest activation energy. The impact sensitivity and friction sensitivity of the RDX/DOS composites were lower than those of raw RDX, and the 10wt% DOS composites had the highest H50 (125.9 cm and the lowest friction sensitivity (8%.

Contribution to the study of two-phase flow analysis considering the existence of a dynamic flow between the phases

International Nuclear Information System (INIS)

Silva, M.C. da; Silva, D.E. da

1981-01-01

The linear momentum and energy equation of the Relap 4/Mod 5 computer code were modified, permiting us to take in account the effects of slip between the phases of two phase flow. The modified computer code were used for the simulation of loss of coolant accident in Angra 1 power plant. The comparison of the results obtained by the modified version with experimental results show that the new model are more realistic. (E.G.) [pt

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.)

Percepção de valor em uma oferta: o papel dos valores dos consumidores

OpenAIRE

Xavier Júnior, Carlos Eduardo Ramos

2006-01-01

O valor percebido e os valores pessoais dos consumidores são temas que vêm sendo investigados na literatura de marketing por diversos pesquisadores há décadas. Neste sentido, o objetivo desta dissertação foi investigar as relações entre os valores pessoais (KAHLE; KENNEDY, 1989) dos consumidores e a importância atribuída por estes às diversas dimensões do valor percebido apresentadas na literatura (SWEENEY; SOUTAR, 2001). Para isto, definiu-se o público de estudantes universitá...

Abordagem teórica dos condicionantes da formação e consolidação dos parques tecnológicos

Directory of Open Access Journals (Sweden)

Alexandre Augusto Pereira Gaino

2014-03-01

Full Text Available O artigo discute as condições teóricas para a instalação e consolidação dos parques tecnológicos, mecanismos utilizados na promoção da inovação tecnológica e do desenvolvimento regional, alvo de diversas iniciativas de políticas públicas na atualidade. Para a consecução desse objetivo foi adotada uma abordagem teórica e exploratória, por meio de revisão bibliográfica, em especial de referências internacionais. O artigo apresenta e analisa diversos conceitos e definições de parque tecnológico e constata que essa diversidade decorre das diferentes realidades regionais e das variadas motivações dos stakeholders. O papel dos parques tecnológicos no desenvolvimento regional assume múltiplas feições em decorrência dos distintos interesses dos atores envolvidos em sua instalação. O artigo enfatiza e adverte que há importantes limitações da ideia de que o sucesso do parque depende fundamentalmente da capacidade de cooperação e mobilização de recursos por parte dos agentes envolvidos.

Influência dos valores laborais dos pais sobre os valores laborais dos filhos Parents work values influence on sons work values

Directory of Open Access Journals (Sweden)

Juliana Barreiros Porto

2006-01-01

Full Text Available Valores laborais são princípios ou metas, hierarquicamente organizadas, que as pessoas buscam e que guiam a sua vida no trabalho. A família, a escola e a experiência de trabalho são apontadas como as variáveis mais influentes na formação dos valores laborais. Os pais são considerados os agentes socializadores mais influentes nesse processo, pois servem como modelo de trabalhador para as crianças. O objetivo do presente trabalho é investigar a influência dos valores paterno e materno nos valores laborais de estudantes universitários. Participaram 129 estudantes universitários, de 17 cursos escolhidos aleatoriamente, seus pais (84 mães e 45 pais e 956 colegas de curso dos estudantes. Os participantes responderam à Escala de Valores Relativos ao Trabalho. Os resultados das regressões hierárquicas indicaram que os pais e os colegas exercem influência sobre os valores laborais de Realização Profissional e Estabilidade dos estudantes. São discutidas a relevância e as limitações desses resultados no artigo.Work values are principles or goals, ordered by importance, that people seek and that guide his/her life at work. Family, school and work experiences are indicated as the most important factors in the formation of work values. Parents are considered the most influential social agent in this process, since they serve as a role model to their children. The present study examines the impact of the work values of parents on the work values of college students. One hundred and twenty nine (129 students and their parents (84 mothers and 45 fathers in 17 randomly chosen undergraduate courses, as well as 956 colleagues of these students participated in this investigation. They answered the Work Values Scale. The results of the hierarchical regressions demonstrated that parents and colleagues influence the student's work values of Professional Achievement and Stability. The relevance and limitations of these results are discussed in

48 CFR 632.702-70 - DOS policy.

Science.gov (United States)

2010-10-01

... 48 Federal Acquisition Regulations System 4 2010-10-01 2010-10-01 false DOS policy. 632.702-70... REQUIREMENTS CONTRACT FINANCING Contract Funding 632.702-70 DOS policy. The Department's policy is to provide... incremental funding of cost-reimbursement contracts. Fixed-price, labor-hour, and time-and-materials contracts...

Program for analysis and evaluation of operational data in nuclear power plants - statistical of operational incident of 1984 to 1985 from Angra-1

International Nuclear Information System (INIS)

Soares, H.V.; Ambros, P.C.; Araujo, J.B.

1987-01-01

The reports of CNEN in the years of 1984 - 1985 regarding reactor accidents. These reports are divided into five classes: reactor shutdown, operator of the core emergency cooling system, power plant operating at limit conditions, radioactivity contamination and super exposition is presented. (A.C.A.S.)

Rendimiento de dos variedades mejoradas de frijol, sembrados al voleo y al espeque, en Moss Pam, Waspam, rio Coco

Directory of Open Access Journals (Sweden)

Sankara Narvaez Ismael

2012-10-01

Full Text Available           Este articulo presenta el comportamiento agronómico del frijol (Phaseolus vulgaris L. en dos variedades:(DOR-364 y H-46, establecidos a través del análisis de dos métodos de siembra (al voleo y al espeque,  para medir la variable rendimiento. El experimento se realizó en la finca académica SNAKY/URACCAN, ubicada en la comunidad Moss Pam, en el municipio de Waspam río Coco, Región Autónoma Atlántico Norte (RAAN. El cultivo de frijol es de gran relevancia en la vida de las comunidades indígenas, ya que constituye al igual que el arroz, el grano de mayor importancia en la dieta familiar. Es de mencionar que las comunidades indígenas de la RAAN utilizan básicamente dos métodos de siembra (al voleo y al espeque; no obstante, siempre los rendimientos son bajos, por lo que se hace necesario el estudio con las condiciones descritas.    Se utilizó un diseño bifactorial en bloques completos al azar, en donde el factor A: equivale a las dos variedades de frijol (DOR-364 y H-46, y el factor B: dos métodos de siembra (al voleo y al espeque. La evaluación se hizo sobre las características morfométricas presentadas en la fase vegetativa y reproductiva del cultivo. El procesamiento de la información se hizo con el programa estadístico InfoStat, indagando desde el análisis del ANAVA y la prueba Kruskal-Wallis. Los resultados mostraron una alta viabilidad germinativa (95%, con diferencias estadísticas entre tratamientos en las variables altura y diámetro en la etapa vegetativa. En la etapa reproductiva las variables: número de vainas/plantas y granos/vainas/plantas, fueron las que presentaron diferencias estadísticas entre tratamientos, contrario a las variables número de flores/plantas y longitud de vainas/plantas que no mostraron diferencias. Finalmente el ANAVA con un 95 por ciento de confiabilidad encontró diferencias de medias en la variable rendimiento.Se recomienda el establecimiento de la variedad H-46

Comparison of computational performance of GA and PSO optimization techniques when designing similar systems - Typical PWR core case

International Nuclear Information System (INIS)

Souza Lima, Carlos A.; Lapa, Celso Marcelo F.; Pereira, Claudio Marcio do N.A.; Cunha, Joao J. da; Alvim, Antonio Carlos M.

2011-01-01

Research highlights: → Performance of PSO and GA techniques applied to similar system design. → This work uses ANGRA1 (two loop PWR) core as a prototype. → Results indicate that PSO technique is more adequate than GA to solve this kind of problem. - Abstract: This paper compares the performance of two optimization techniques, particle swarm optimization (PSO) and genetic algorithm (GA) applied to the design a typical reduced scale two loop Pressurized Water Reactor (PWR) core, at full power in single phase forced circulation flow. This comparison aims at analyzing the performance in reaching the global optimum, considering that both heuristics are based on population search methods, that is, methods whose population (candidate solution set) evolve from one generation to the next using a combination of deterministic and probabilistic rules. The simulated PWR, similar to ANGRA 1 power plant, was used as a case example to compare the performance of PSO and GA. Results from simulations indicated that PSO is more adequate to solve this kind of problem.

The protection system to Brazilian Nuclear Program

International Nuclear Information System (INIS)

Andreuzza, Mario Giussepp Santezzi Bertottelli

1997-01-01

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

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

Energy Technology Data Exchange (ETDEWEB)

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

1997-12-31

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

Computer-aided event tree analysis by the impact vector method

International Nuclear Information System (INIS)

Lima, J.E.P.

1984-01-01

In the development of the Probabilistic Risk Analysis of Angra I, the ' large event tree/small fault tree' approach was adopted for the analysis of the plant behavior in an emergency situation. In this work, the event tree methodology is presented along with the adaptations which had to be made in order to attain a correct description of the safety system performances according to the selected analysis method. The problems appearing in the application of the methodology and their respective solutions are presented and discussed, with special emphasis to the impact vector technique. A description of the ETAP code ('Event Tree Analysis Program') developed for constructing and quantifying event trees is also given in this work. A preliminary version of the small-break LOCA analysis for Angra 1 is presented as an example of application of the methodology and of the code. It is shown that the use of the ETAP code sigmnificantly contributes to decreasing the time spent in event tree analyses, making it viable the practical application of the analysis approach referred above. (author) [pt

Analysis of variance of primary data on plant growth analysis Análise de variância dos dados primários na análise de crescimento vegetal

Directory of Open Access Journals (Sweden)

Adelson Paulo Araújo

2003-01-01

Full Text Available Plant growth analysis presents difficulties related to statistical comparison of growth rates, and the analysis of variance of primary data could guide the interpretation of results. The objective of this work was to evaluate the analysis of variance of data from distinct harvests of an experiment, focusing especially on the homogeneity of variances and the choice of an adequate ANOVA model. Data from five experiments covering different crops and growth conditions were used. From the total number of variables, 19% were originally homoscedastic, 60% became homoscedastic after logarithmic transformation, and 21% remained heteroscedastic after transformation. Data transformation did not affect the F test in one experiment, whereas in the other experiments transformation modified the F test usually reducing the number of significant effects. Even when transformation has not altered the F test, mean comparisons led to divergent interpretations. The mixed ANOVA model, considering harvest as a random effect, reduced the number of significant effects of every factor which had the F test modified by this model. Examples illustrated that analysis of variance of primary variables provides a tool for identifying significant differences in growth rates. The analysis of variance imposes restrictions to experimental design thereby eliminating some advantages of the functional growth analysis.A análise de crescimento vegetal apresenta dificuldades relacionadas à comparação estatística das curvas de crescimento, e a análise de variância dos dados primários pode orientar a interpretação dos resultados. Este trabalho objetivou avaliar a análise de variância de dados de distintas coletas de um experimento, abordando particularmente a homogeneidade das variâncias e a escolha do modelo adequado de ANOVA. Foram utilizados dados de cinco experimentos com diferentes culturas e condições de crescimento. Do total de variáveis, 19% foram originalmente

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

Nuclear installations

International Nuclear Information System (INIS)

2001-01-01

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

Considerações gerais sôbre os órgãos odoríferos sexuais dos machos dos Lepidópteros

Directory of Open Access Journals (Sweden)

Rudolf Barth

1953-12-01

Full Text Available São determinadas as seguintes regras sôbre a função dos órgãos odoríferos dos machos dos Lepidópteros: l.ª regra: A secreção das glândulas age em forma de gás sobre a fêmea diminuindo a reação normal de fuga e provocando a disposição e preparação para a copulação. 2.ª regra: Os órgãos odoríferos nos machos de um grupo de espécies parentes encontram-se constantemente nos mesmos órgãos possuindo o mesmo tipo de estrutura (constância orgânica . 3.ª regra: As partes quitinosas (escamas odoríferas, cerdas distribuidoras, inserções etc. são especificadas para cada espécie (constância de forma. 4.ª regra: O grau de desenvolvimento e com isto o grau de eficiência dos órgãos odoríferos dos Lepidópteros noturnos é sempre mais elevado do que os dos diurnos.

Reactor building 3D-model for evaluating the pressures on concrete regularization and foundation waterproofing membrane

Energy Technology Data Exchange (ETDEWEB)

Mello Junior, Glauco J.T.; Cardoso, Tarcisio de F.; Prates, Carlos L.M. [Eletrobras Termonuclear S.A. - ELETRONUCLEAR, Rio de Janeiro, RJ (Brazil). Gerencia de Analise de Tensoes GAN.T], e-mail: glauco@eletronuclear.gov.br, e-mail: tarci@eletronuclear.gov.br, e-mail: prates@eletronuclear.gov.br

2009-07-01

Angra dos Reis site in Brazil has already 2 operating PWR NPPs. Unit 3, with identical design to Unit 2, also a 1350 MW PWR, is expected to have its construction started in 2009. This new plant shall be founded directly on sound rock. The first step is to prepare this rock surface with a concrete regularization and a foundation waterproofing membrane. This study presents a 3D model approach of the corresponding reactor building to verify the maximum pressure acting on this surface. The 3D model permits to show a more realistic pressure distribution at every foundation specific detail. A static analysis is performed using ANSYS Mechanical Release 11.1. Dead weight, permanent and live loads, Safe Shutdown Earthquake (SSE) combined with Burst Pressure Wave (BPW) from the Feedwater Tank (SSB=SSE+BPW) and differences of temperature are taken into account. Considering all foundation nodes , the pressure distribution on the waterproofing membrane for each load case is obtained for vertical and horizontal directions, which corresponds to compression and tangential reaction loads. The maximum values occur in distinct positions for each load case. The maximum results are obtained according to DIN 25449 (2008) load combination criteria. The results are compared to a simplified analysis performed before, showing a good agreement in global values. (author)

Modeling the dynamics of radionuclide concentration in animal derived products after an accident in tropical areas

International Nuclear Information System (INIS)

Vinhas, Denise M.; Rochedo, Elaine R.R.; Wasserman, Maria A.V.; Conti, Luiz F.C.

2005-01-01

Following an accidental release of radionuclides to the atmosphere with the contamination of large areas, a detailed and fast methodology to assess the prognosis of public exposure is needed to estimate radiological consequences and optimize decisions to the protection of the public. The German model ECOSYS has been chosen to integrate the SIEM - Integrated Emergency System, developed by IRD/CNEN to assess the doses to the public after an accidental contamination of rural areas. The use the model demands a considerable effort in adapting scenarios to fit the specific conditions of a location, considering the differences related to climate, environmental characteristics, agricultural calendar and practices, along with population diet. The area selected to start this adaptation considers the characteristics of the 50 km radius area surrounding the nuclear power plants at Angra dos Reis, Rio de Janeiro. At a first stage, the concentration on vegetal food products has been studied. This work describes the methodology used to select scenarios and presents results of the dynamics of the predicted concentration of radionuclides in different kinds of animal derived food products. The work provides guidance to the need of radioecological research needed to improve the adequacy of the estimates to actual Brazilian scenarios. (author)

Radiological emergency response for community agencies with cognitive task analysis, risk analysis, and decision support framework.

Science.gov (United States)

Meyer, Travis S; Muething, Joseph Z; Lima, Gustavo Amoras Souza; Torres, Breno Raemy Rangel; del Rosario, Trystyn Keia; Gomes, José Orlando; Lambert, James H

2012-01-01

Radiological nuclear emergency responders must be able to coordinate evacuation and relief efforts following the release of radioactive material into populated areas. In order to respond quickly and effectively to a nuclear emergency, high-level coordination is needed between a number of large, independent organizations, including police, military, hazmat, and transportation authorities. Given the complexity, scale, time-pressure, and potential negative consequences inherent in radiological emergency responses, tracking and communicating information that will assist decision makers during a crisis is crucial. The emergency response team at the Angra dos Reis nuclear power facility, located outside of Rio de Janeiro, Brazil, presently conducts emergency response simulations once every two years to prepare organizational leaders for real-life emergency situations. However, current exercises are conducted without the aid of electronic or software tools, resulting in possible cognitive overload and delays in decision-making. This paper describes the development of a decision support system employing systems methodologies, including cognitive task analysis and human-machine interface design. The decision support system can aid the coordination team by automating cognitive functions and improving information sharing. A prototype of the design will be evaluated by plant officials in Brazil and incorporated to a future trial run of a response simulation.

Reactor building 3D-model for evaluating the pressures on concrete regularization and foundation waterproofing membrane

International Nuclear Information System (INIS)

Mello Junior, Glauco J.T.; Cardoso, Tarcisio de F.; Prates, Carlos L.M.

2009-01-01

Angra dos Reis site in Brazil has already 2 operating PWR NPPs. Unit 3, with identical design to Unit 2, also a 1350 MW PWR, is expected to have its construction started in 2009. This new plant shall be founded directly on sound rock. The first step is to prepare this rock surface with a concrete regularization and a foundation waterproofing membrane. This study presents a 3D model approach of the corresponding reactor building to verify the maximum pressure acting on this surface. The 3D model permits to show a more realistic pressure distribution at every foundation specific detail. A static analysis is performed using ANSYS Mechanical Release 11.1. Dead weight, permanent and live loads, Safe Shutdown Earthquake (SSE) combined with Burst Pressure Wave (BPW) from the Feedwater Tank (SSB=SSE+BPW) and differences of temperature are taken into account. Considering all foundation nodes , the pressure distribution on the waterproofing membrane for each load case is obtained for vertical and horizontal directions, which corresponds to compression and tangential reaction loads. The maximum values occur in distinct positions for each load case. The maximum results are obtained according to DIN 25449 (2008) load combination criteria. The results are compared to a simplified analysis performed before, showing a good agreement in global values. (author)

OptaDOS - a new tool for EELS calculations

Science.gov (United States)

Nicholls, R. J.; Morris, A. J.; Pickard, C. J.; Yates, J. R.

2012-07-01

Many modern (Scanning) Transmission Electron Microscopes ((S)TEMs) are equipped with an energy loss spectrometer. The Electron Energy Loss (EEL) spectra collected provide an experimental method of probing the bonding within a material. With the extra addition of monochromators, the energy resolution obtainable means that even more information is revealed within the fine structure of the spectra. Interpreting the fine structure can often be aided by simulation. Density-functional theory (DFT) is one method of simulating EEL spectra. DFT allows us to simulate DOS and EEL spectra from different structures. This comparison between simulation and experiment enables us to explore how changes in the spectrum are related to changes within the sample. CASTEP is a pseudopotential DFT code which can simulate both low-loss and core-loss EEL spectra. Recent developments have resulted in a separate analysis tool, OptaDOS. This package computes various spectral properties including DOS, projected DOS, joint DOS, core-loss and low-loss EEL spectra and optical spectra. One of the important aspects of the code is the way in which the DOS is calculated. This is done via linear extrapolation or adaptive smearing, methods which are not currently available within CASTEP (or indeed any other code) and which allow detailed analysis of spectral properties. This paper summarises these developments and what they mean for the interpretation of EEL spectra.

Pre-treatment of bituminized NPP wastes for disposal in near-surface repository

Energy Technology Data Exchange (ETDEWEB)

Vieira, Vanessa Mota; Tello, Clédola Cássia Oliveira de, E-mail: vanessamotavieira@gmail.com, E-mail: tellocc@cdtn.br [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)

2017-07-01

The implementation of the national repository is an important technical requirement, and a legal requirement for the entry into operation of the nuclear power plant Angra 3. The Brazilian repository is being planned to be a near-surface one. In Brazil the low and intermediate level radioactive wastes are immobilized using cement and bitumen for Angra 1 and Angra 2 NPP, respectively. The main problems due to the disposal of bituminized wastes in repositories are swelling of the waste products and their degradation in the long term. To accommodate the swelling of the bituminized wastes, the drums are filled up to 70 - 90% of their volume, which reduces the structural the repository stability and the disposal availability. Countries, which use bitumen in the solidification of NPP's radioactive waste and have near-surface repositories, need to immobilize this bituminized waste within other drums containing cement pastes or mortars to disposal them. This study aims to find solutions for the storage in surface repository of bituminized radioactive waste products, making them compatible with the acceptance criteria of cemented waste products. It was also performed a modeling with the results obtained in the leaching test using the ALT program and defined the transport model of the cesium leachate element and it was verified that in the early times the leaching was governed by the diffusion model and later by the partition model. The results obtained in this study can be used in the evaluation of performance of repositories. (author)

Pre-treatment of bituminized NPP wastes for disposal in near-surface repository

International Nuclear Information System (INIS)

Vieira, Vanessa Mota; Tello, Clédola Cássia Oliveira de

2017-01-01

The implementation of the national repository is an important technical requirement, and a legal requirement for the entry into operation of the nuclear power plant Angra 3. The Brazilian repository is being planned to be a near-surface one. In Brazil the low and intermediate level radioactive wastes are immobilized using cement and bitumen for Angra 1 and Angra 2 NPP, respectively. The main problems due to the disposal of bituminized wastes in repositories are swelling of the waste products and their degradation in the long term. To accommodate the swelling of the bituminized wastes, the drums are filled up to 70 - 90% of their volume, which reduces the structural the repository stability and the disposal availability. Countries, which use bitumen in the solidification of NPP's radioactive waste and have near-surface repositories, need to immobilize this bituminized waste within other drums containing cement pastes or mortars to disposal them. This study aims to find solutions for the storage in surface repository of bituminized radioactive waste products, making them compatible with the acceptance criteria of cemented waste products. It was also performed a modeling with the results obtained in the leaching test using the ALT program and defined the transport model of the cesium leachate element and it was verified that in the early times the leaching was governed by the diffusion model and later by the partition model. The results obtained in this study can be used in the evaluation of performance of repositories. (author)

CRISE E NOVAS EXPRESSÕES DOS MOVIMENTOS POPULARES E SINDICALCRISE E NOVAS EXPRESSÕES DOS MOVIMENTOS POPULARES E SINDICALCRISE E NOVAS EXPRESSÕES DOS MOVIMENTOS POPULARES E SINDICAL

OpenAIRE

Ivo Lesbaupin

1995-01-01

O Brasil tem visto nos últimos tempos o surgimento e desenvolvimento de inúmeros movimentos: movimentos de bairro, movimentos de mulheres, movimento negro, movimento dos atingidos pelas barragens, movimento dos sem-terra, movimento ecológico, e outros. Porque se formam tais movimentos? Qual o alcance, a capacidade de mudança social que têm estes movimentos? Quais as condições para que u m movimento seja bem sucedido?

Disk Operating System--DOS. Teacher Packet. Learning Activity Packets.

Science.gov (United States)

Oklahoma State Dept. of Vocational and Technical Education, Stillwater. Curriculum and Instructional Materials Center.

The Learning Activity Packets (LAPs) contained in this manual are designed to assist the beginning user in understanding DOS (Disk Operating System). LAPs will not work with any version below DOS Version 3.0 and do not address the enhanced features of versions 4.0 or higher. These elementary activities cover only the DOS commands necessary to…

Inter-relações entre a anatomia vegetal e a produção vegetal Interrelations between plant anatomy and plant production

Directory of Open Access Journals (Sweden)

Lenir Maristela Silva

2005-03-01

Full Text Available É realizada uma revisão de literatura que procura aproximar a anatomia vegetal do contexto da produção vegetal. O principal objetivo é o de contribuir para que o professor de Botânica possa proporcionar aos alunos dos cursos de Agronomia compreensão da diversidade da organização estrutural do vegetal.A literature revision is accomplished to approach the plant anatomy within the context of the plant production. The main objective is to contribute so that the Botany teacher will be able to make it provide for the students of the Agronomy courses to understand the diversity of behaviors in the structural organization of the plant.

Evidências Empíricas sobre a Rentabilidade dos Ativos dos Bancos no Brasil antes da Crise Americana do Subprime

Directory of Open Access Journals (Sweden)

Fernando da Silva Vinhado

2014-12-01

Full Text Available Segundo a visão pós-keynesiana, defendida por Tobin (1982, os ativos dos bancos são divididos basicamente entre aqueles de natureza defensiva, representados fundamentalmente por títulos financeiros, com característica de maior liquidez e menor rentabilidade, e as operações de crédito, que são ativos não defensivos com perfil de oferecer menor liquidez e maior rentabilidade. Com base nessa visão e a partir de dados organizados em painel, contemplando 71 instituições financeiras que atuaram no Brasil entre 2000 e 2008, no presente artigo foi utilizada a técnica econométrica do método dos momentos generalizados em sistema (GMM-SYS a fim de analisar empiricamente a influência de variáveis macro e microeconômicas sobre a rentabilidade de ativos dos bancos no país, tanto em títulos financeiros quanto em operações de crédito. Os exercícios econométricos propostos, que objetivaram melhorar a compreensão em relação à formação da rentabilidade dos ativos dos bancos no mercado bancário brasileiro, permitiram identificar aspectos como a persistência nos níveis de rentabilidade, a nacionalidade e personalidade jurídica dos bancos mais rentáveis por tipo de ativo, a influência do tamanho da instituição e do nível de capitalização sobre a rentabilidade dessas aplicações, além das evidências contrárias à hipótese de estrutura-conduta-performance (HCP no mercado bancário brasileiro. As estimativas envolvendo as variáveis macroeconômicas revelaram influência positiva da taxa básica de juros e característica pró-cíclica da rentabilidade dos ativos bancários. Assim, os achados permitem melhor decifrar o comportamento do desempenho dos ativos das instituições financeiras no Brasil, o que pode, inclusive, vir a orientar esforços de gestão e supervisão no sistema financeiro.

Evidências Empíricas sobre a Rentabilidade dos Ativos dos Bancos no Brasil antes da Crise Americana do Subprime

Directory of Open Access Journals (Sweden)

Fernando da Silva Vinhado

2014-11-01

Full Text Available Segundo a visão pós-keynesiana, defendida por Tobin (1982, os ativos dos bancos são divididos basicamente entre aqueles de natureza defensiva, representados fundamentalmente por títulos financeiros, com característica de maior liquidez e menor rentabilidade, e as operações de crédito, que são ativos não defensivos com perfil de oferecer menor liquidez e maior rentabilidade. Com base nessa visão e a partir de dados organizados em painel, contemplando 71 instituições financeiras que atuaram no Brasil entre 2000 e 2008, no presente artigo foi utilizada a técnica econométrica do método dos momentos generalizados em sistema (GMM-SYS a fim de analisar empiricamente a influência de variáveis macro e microeconômicas sobre a rentabilidade de ativos dos bancos no país, tanto em títulos financeiros quanto em operações de crédito. Os exercícios econométricos propostos, que objetivaram melhorar a compreensão em relação à formação da rentabilidade dos ativos dos bancos no mercado bancário brasileiro, permitiram identificar aspectos como a persistência nos níveis de rentabilidade, a nacionalidade e personalidade jurídica dos bancos mais rentáveis por tipo de ativo, a influência do tamanho da instituição e do nível de capitalização sobre a rentabilidade dessas aplicações, além das evidências contrárias à hipótese de estrutura-conduta-performance (HCP no mercado bancário brasileiro. As estimativas envolvendo as variáveis macroeconômicas revelaram influência positiva da taxa básica de juros e característica pró-cíclica da rentabilidade dos ativos bancários.  Assim, os achados permitem melhor decifrar o comportamento do desempenho dos ativos das instituições financeiras no Brasil, o que pode, inclusive, vir a orientar esforços de gestão e supervisão no sistema financeiro.

Análise da lucratividade dos clientes

OpenAIRE

Madeira, Paulo

2000-01-01

Um bom sistema de Análise da lucratividade de Clientes pode ajudar a melhorar a rendibilidade global do negócio, selecionando os clientes de qualidade, e a indicar o principal caminho a segui rpara atingir uma maior lucartividade, indicando o impacto financeiro actual e potencial dos movimentos estratégicos dos clientes.

Incidente com Jornalistas portugueses no Iraque. Imprudência ou espírito missionário? A batalha dos argumentos nas colunas dos jornais

OpenAIRE

Oliveira, Madalena

2007-01-01

O chamado jornalismo de guerra é, desde o desenvolvimento de tecnologias que permitiram o relato de conflitos em directo, um dos tópicos mais estimulantes do debate em torno dos escolhos e dos desafios do ofício daqueles que têm por missão informar. Os riscos associados às movimentações dos jornalistas em campos de bata-lha são, com frequência, o fermento de notícias que enchem secções especializadas nos media. O baleamento de uma jornalista da SIC e o sequestro de um repórter da TSF, no Iraq...

Zumbi dos Palmares: a afroresiliencia

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Josué Petrônio Quirino de Oliveira

2017-10-01

Full Text Available O artigo buscou fazer uma releitura de Zumbi dos Palmares sob o prisma da resiliência, demonstrando uma visão singular ao olhar para os escravos nos quilombos e suas histórias de superação e transformação perante as adversidades, levando não só a reconstruir o imaginário afrodescendente brasileiro com o caleidoscópio da resiliência, mas revelar que a resiliência sempre foi inerente a história dos negros no Brasil. Para tanto se caracterizou como uma pesquisa exploratória com abordagem qualitativa e procedimentos bibliográficos que foram essenciais para a construção do artigo, amadurecendo e ampliando os conhecimentos envolvidos na temática. Nesta abordagem o quilombo dos Palmares foi um conjunto complexo de condições, atitudes e ações que apesar das adversidades tiveram resultados positivos, os fatos demonstraram que os negros nos quilombos foram uma prova que a resiliência negra não foi apenas um fator individual, mas uma característica comunitária que desencadeou um processo de ruptura e recuperação social, um grito de liberdade em defesa da consciência de uma raça, e de um povo. Zumbi não foi apenas um líder de um movimento libertário que marcou a história dos negros oriundos de Pernambuco e Alagoas, mas a história de uma raça por gerações no país, que se tornou sinônimo de resiliência.

Angra II pipelines and supports data base sources (GPT)

International Nuclear Information System (INIS)

Abud, Paulo Roberto; Grand Court, Eduardo Souza de

1995-01-01

The analysis of the needs related to the management of assembly of pipelines and support system in a nuclear power plant presents a great deal of data. Such situation leaded to the development of a data base named Erection Management System, EMS, which enables not only the assembly of the equipment, but also the management of the project in addition to monitoring all the activities related to assembly. This work discusses the above mentioned issues

Terrestrial gamma tracking: estimation of population exposition to radioactivity in urban areas; Rastreamento gama terrestre: estimativa da exposição da população à radioatividade em areas urbanas

Energy Technology Data Exchange (ETDEWEB)

Souza, Elder Magalhães de

2017-07-01

In this work, measurements of Ambient Dose Equivalent, H⁎(10) in urban and rural areas is proposed to assess and estimate the dose and external dose in cases of radiological or nuclear accidents. These measurements will enable the calculation and estimation of population exposure to environmental and urban radioactivity to be performed within the parameters proposed by the IAEA and UNSCEAR. To take into account the influence of background gamma radiation on radiometric measurements, all the detectors used, AT6101C, SPARCS A1 and SPARCS M1 systems, were calibrated using IRD's extensive set of planar sources. Also, a methodology for the gamma radiation terrestrial survey is proposed to use the gamma in situ spectrometry systems in H⁎(10) measurements. Shielding effects due to the use of detection systems inside vehicles were evaluated and the corresponding corrections factors calculated are 1.45 for the AT6101C detector, 1.77 for SPARCS A1 and 1.82 for SPARCS M1. The terrestrial survey to determine the value of Ambient Dose Equivalent was performed in areas not subject to intense radioactive anomalies. Among these areas are included the cities: Angra dos Reis and Paraty (State of Rio de Janeiro), Abadia de Goiás, Goiânia, Cristalina and Itumbiara (State of Goiás), Ribeirão Preto and Campinas (State of São Paulo), Brasília-DF (Federal District), Belo Horizonte, Ubá and cities of Zona da Mata (State of Minas Gerais) and Manaus (State of Amazonas). The average altitude of the cities ranged from the sea level in the cities of Angra dos Reis and Paraty to 1100 meters in Brasilia. The number of inhabitants ranged from 3,000 in Divinésia to 3 million in Brasília-DF. The mean values of H⁎(10) ranged from 63 nSv/h in Itumbiara to 170 nSv/h in Ubá. The minimum and maximum values found ranged from 25 nSv/h in Manaus to 347 nSv/h in Belo Horizonte. The average altitude of the cities ranged from the sea level in the cities of Angra dos Reis and Paraty to 1100

Terrestrial gamma tracking: estimation of population exposition to radioactivity in urban areas

International Nuclear Information System (INIS)

Souza, Elder Magalhães de

2017-01-01

In this work, measurements of Ambient Dose Equivalent, H⁎(10) in urban and rural areas is proposed to assess and estimate the dose and external dose in cases of radiological or nuclear accidents. These measurements will enable the calculation and estimation of population exposure to environmental and urban radioactivity to be performed within the parameters proposed by the IAEA and UNSCEAR. To take into account the influence of background gamma radiation on radiometric measurements, all the detectors used, AT6101C, SPARCS A1 and SPARCS M1 systems, were calibrated using IRD's extensive set of planar sources. Also, a methodology for the gamma radiation terrestrial survey is proposed to use the gamma in situ spectrometry systems in H⁎(10) measurements. Shielding effects due to the use of detection systems inside vehicles were evaluated and the corresponding corrections factors calculated are 1.45 for the AT6101C detector, 1.77 for SPARCS A1 and 1.82 for SPARCS M1. The terrestrial survey to determine the value of Ambient Dose Equivalent was performed in areas not subject to intense radioactive anomalies. Among these areas are included the cities: Angra dos Reis and Paraty (State of Rio de Janeiro), Abadia de Goiás, Goiânia, Cristalina and Itumbiara (State of Goiás), Ribeirão Preto and Campinas (State of São Paulo), Brasília-DF (Federal District), Belo Horizonte, Ubá and cities of Zona da Mata (State of Minas Gerais) and Manaus (State of Amazonas). The average altitude of the cities ranged from the sea level in the cities of Angra dos Reis and Paraty to 1100 meters in Brasilia. The number of inhabitants ranged from 3,000 in Divinésia to 3 million in Brasília-DF. The mean values of H⁎(10) ranged from 63 nSv/h in Itumbiara to 170 nSv/h in Ubá. The minimum and maximum values found ranged from 25 nSv/h in Manaus to 347 nSv/h in Belo Horizonte. The average altitude of the cities ranged from the sea level in the cities of Angra dos Reis and Paraty to 1100

Atividades Física, Educativa e de Dança: Um Estudo dos Valores Pessoais dos Consumidores Idosos

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Luciana Torres Souza Kelly

2012-02-01

Full Text Available Este artigo apresenta como objetivo principal identificar os valores pessoais dos consumidores idosos dos serviços de atividades física, educativa e de dança, sob o aspecto motivacional hedônico e utilitário. Adotou-se o modelo de cadeia meios-fim de Gutman (1982, o qual sugere que a pesquisa deve utilizar uma abordagem qualitativa através da entrevista em profundidade no levantamento dos dados e da análise de conteúdo. Uma fase da metodologia é quantitativa, decorrente da tabulação das conseqüências e valores em tabelas, visando construir os mapas hierárquicos, os quais se constituem em diagramas de freqüência. Por meio dos resultados indicados nos mapas hierárquicos de valor foi possível observar que os valores e benefícios associados à participação em cada atividade são tanto de interesse individual quanto coletivo, e tanto de natureza hedônica quanto utilitária. Constatou-se através dos resultados, a identificação de valores convergentes e divergentes apontando o perfil heterogêneo do consumidor idoso indicando que a cultura, as vivências, as experiências e as realidades atuais corroboram para a manifestação de um valor pessoal característico na sua vida. E nas situações de compra e utilização de serviços, apresentam como meta a aquisição de novas amizades e a experimentação de momentos variados (com novidades na vida diária. DOI: 10.5585/remark.v10i3.2251

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

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

Energy Technology Data Exchange (ETDEWEB)

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

2000-07-01

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

Evaluation of the ICRU operational magnitudes implantation for the photon radiation at the Angra I and Angra II nuclear power plants

International Nuclear Information System (INIS)

Viana, Ronaldo do Nascimento

2006-01-01

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 * (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 * (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 * (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 * (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 * (10)'s implementation on installations that perform measurements with radiation rate meters on the practice of radiation protection, in order to adopt the H * (10) quantity in our country. (author)

Separation and radiometric determination of {sup 59}Ni, {sup 63}Ni, {sup 55}Fe, {sup 99}Tc and {sup 94}Nb in radioactive wastes of low and intermediate activities from PWR nuclear power plants; Separacao e determinacao radiometrica dos radionuclideos {sup 59}Ni, {sup 63}Ni, {sup 55}Fe, {sup 99}Tc e {sup 94}Nb em rejeitos radioativos de baixa e media atividades provenientes de centrais nucleares do tipo PWR

Energy Technology Data Exchange (ETDEWEB)

Temba, Eliane Silvia Codo

2016-10-01

The objective of this work was the development and establishment of a specific analytical protocol for the determination of the {sup 59}Ni, {sup 63}Ni, {sup 55}Fe, {sup 99}Tc and {sup 94}Nb radionuclides in low and intermediate radioactive waste samples of Almirante Alvaro Alberto Nuclear Power Plant, CNAAA, located in the city of Angra dos Reis, RJ. The separation and purification techniques used have taken into account the particularities of each radionuclide studied. Chemical separation methods were used, as well as carriers and radioisotope tracers, and ion-exchange and extraction chromatography involving specific resins. The main techniques used for the analysis and determination of the radionuclides were Liquid Scintillation Counting (LSC) and Gamma Spectrometry. Also used were Atomic Emission Spectroscopy with Inductively Coupled Plasma (ICP-AES) and Neutron Activation Analysis (NAA) for the chemical yield determination. Concerning to the {sup 59}Ni, {sup 63}Ni, {sup 55}Fe radionuclides, the methodology of sequential separation proved to be very appropriate for their separation and determination, as could be observed by the results obtained. Chemical yields in the range from 39 to 100%, and LSC counting efficiencies in the range of 37.8% for {sup 55}Fe, and 71.5% for {sup 63}Ni, are in accordance with the results found in the literature. The spectra of LSC showed that the methodology used to separation and purification of these radionuclides was very successful. The results for {sup 59}Ni have shown that the use of a {sup 55}Fe certified standard for calibration of the equipment was a viable alternative. In the case of the {sup 99}Tc radionuclide the use of rhenium as carrier and chemical yield monitor, resulted in high chemical yields. Use of Gamma Spectrometry analysis made it possible to check that the main interfering agents were actually removed with the combined use of anion exchange chromatography and TEVA resin. The chemical yield of {sup 94}Nb was

ESCRITORAS BAIANAS DOS OITOCENTOS ENFRENTANDO PRECONCEITOS

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Helena Parente Cunha

2017-05-01

Full Text Available Tem sido a conquista dos últimos anos o reconhecimento das autoras brasileiras dos séculos passados, mias numerosas do que se supunha e que foram esquecidas devido aos preconceitos do canone Literário. A partir da segunda metade do século XIX, com o levantamento dos períodos em todo o país, dirigidos e editados por mulheres e para mulheres, veiculavam as ideias avançadas e, ao mesmo tempo, concepções do sistema patriarcado. O medo do corpo e do erotismo se transmite à produção literária feminina que, ao se inspirar no amor, quase sempre usa linguagem pudica, procuando santificar o sentimento. Mas não raro surgem passagens de uma audácia inesperada, num desafio ostensivo aos convencionalizmos do cânone comportamental. Estudam-se como as escritoreas Ana Ribeiro, Ildefonsa Laura César e Adelio Fonseca, dentro deste contexto

Estudio de inmunogenicidad para dos vacunas recombinantes contra hepatitis B

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O. Juliao

1991-12-01

Full Text Available Este estudio compara la inmunogenicidad (seroconversión, seroprotección e Hiperrespuesta, producida por dos vacunas recombinantes contra la hepatitis B (Engerix-B de Bélgica y Cubana, en dos esquemas (012 y 016 meses, empleando los métodos de cuantificación para Anti-HBsAg (Abbott y Organón, los cuales fueron también comparados. En el estudio participaron 257 voluntarios,  divididos al azar en 4 grupos (dos vacunas, dos esquemas. Resultados: los dos métodos de Abbon y Organon, no presentan diferencias estadísticas significativas. La vacuna cubana muestra una mayor respuesta inmunogénica para dos dosis de vacuna y para el esquema 012. No hay diferencia entre los esquemas 012 y 016 y en el esquema 016 no se ven diferencias estadísticamente significativas con la vacuna Engerix-B. En esta Última el esquema 016 muestra mejores resultados que el 012.

PADRONIZAÇÃO DA SÍNTESE DOS PRINCIPAIS CONSTITUINTES FEROMONAIS DE INSETOS DOS GÊNEROS METAMASIUS E RHYNCHOPHORUS

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JOHNNATAN DUARTE DE FREITAS

2011-05-01

Full Text Available Os curculionídeos são insetos que causam grandes problemas econômicos aos agricultores e atingem culturas, como coco, dendê, cana-de-açúcar, milho, banana, algodão, etc. O controle de pragas agrícolas, ainda hoje, utiliza grandes quantidades de inseticidas, que são prejudiciais à saúde dos animais, do homem e do meio ambiente. Uma alternativa ao uso desses inseticidas é o uso de feromônios, por serem mais seletivos e menos tóxicos. Nesse trabalho, descrevemos a síntese, em escala preparativa, dos compostos (±-5-Nonanol, (±-2-Metil-4-octanol, (±-2-Metil-4-heptanol, (±-3-Metil-4-octanol, (±-5-Metil-4-octanol, (±-4-Metil-5-nonanol, (±-6-Metil-2-hepten-4-ol, 2-Metil-4-octanona, 2-Metil-4-heptanona e (±-4-Metil-5-nonanona, principais constituintes feromonais de alguns insetos dos gêneros Metamasius e Rhynchophoruseas. A síntese consistiu na reação de Grignard entre um aldeído e um brometo de alquilmagnésio. As oxidações dos álcoois para obtenção das cetonas foram realizadas com hipoclorito de sódio.

Números primos: os átomos dos números

OpenAIRE

Rigoti, Marcio Dominicali

2015-01-01

Este trabalho apresenta um estudo sobre os Números Primos que passa por resultados básicos, como a infinitude dos números primos e o Teorema Fundamental da Aritmética, e resultados mais sofisticados, como o Teorema de Wilson e a consequente função geradora de primos. Além dos resultados teóricos apresenta-se uma interpretação geométrica para os números primos. Essa interpretação e aplicada na ilustração de alguns dos resultados relacionados a primos abordados no ensino básico. Atividades envo...

Efeitos deleterios dos cloretos em reservatorios de concreto

OpenAIRE

Matoski, Adalberto

1998-01-01

Dissertação (mestrado) - Universidade Federal de Santa Catarina, Centro Tecnologico Caracterização dos reservatórios de água potável das regiões de Curitiba e Florianópolis, quanto às patologias apresentadas. Utilização do ensaio de potencial de eletrodo para a definição das linhas equipotenciais sobre a laje de concreto dos reservatórios. Análise dos efeitos do cloro adicionado à água, para sua desinfecção, sobre o concreto. Comparaçao entre os ensaios químico e de espectrometria de raio...

O legado dos desenhadores da guerra

OpenAIRE

Almeida, Reginaldo Rodrigues de

2017-01-01

O comportamento que causa dano ou prejuízo moral é um comportamento violento, logo temido. Porém, não se foge dele, antes se procura.Verifica-se uma avidez global em busca de imagens,sejam fotografias ou vídeos, tendo a fotografia do interior da casa de espectáculos parisiense Le Bataclan, com os cadáveres dos reféns,ainda que pouco perceptível, sido vista até à exaustão, na sequência dos ataque terroristas dodia 13 de Novembro de 2015 em Paris.

Repercussões da aceleração dos ritmos de trabalho na saúde dos servidores de um juizado especial

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Daiane Dal Pai

2014-09-01

Full Text Available Os recentes incrementos tecnológicos promovidos junto ao serviço judiciário federal trouxeram avanços importantes para a melhoria dos atendimentos prestados à população, contudo originaram novas demandas organizacionais aos trabalhadores do setor. Objetivo Conhecer as repercussões da organização do trabalho no cotidiano laboral e na saúde dos servidores do Juizado Especial Federal de Porto Alegre (RS.Procedimentos metodológicos Desenvolveu-se uma pesquisa de abordagem qualitativa, por meio de entrevistas semiestruturadas com 17 servidores de um juizado especial federal. As falas foram gravadas em áudio, transcritas e submetidas à análise de conteúdo. O referencial teórico da psicodinâmica do trabalho fundamentou a interpretação dos achados.Resultados Foram identificadas duas categorias de análise: (1 Mudanças na organização do trabalho: de processos judiciais físicos à aceleração virtual e (2 Adaptação dos profissionais às mudanças e suas repercussões sobre a saúde. Na primeira categoria foram discutidas as transformações vivenciadas pelos trabalhadores a partir da implantação dos sistemas informatizados de recebimento e análise dos processos judiciais. Na segunda categoria revelaram-se as exigências psíquicas e físicas que os trabalhadores associaram ao contexto laboral.Conclusão Concluiu-se que os trabalhadores se percebem diante de um ritmo acelerado e elevado volume de trabalho, convivendo com sintomas que sugerem o adoecimento e sentindo-se desassistidos quanto às mudanças estabelecidas ao processo de trabalho.

ESTUDO DOS PRINCÍPIOS APLICADOS À UTILIZAÇÃO DOS AGENTES QUÍMICOS DESINFETANTES HOSPITALARES

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Vanda M. Galvão Jouclas

Full Text Available As autoras realizaram um levantamento bibliográfico coletando dados atualizados sobre a utilização dos agentes químicos desinfetantes hospitalares, levando-se em consideração suas possibilidades e suas limitações. São abordados na fundamentação científica o conceito de desinfecção e esterilização, as condições necessárias para a ação efetiva de um agente químico, os critérios de escolha do agente químico, e a classificação dos agentes químicos utilizados em equipamentos e materiais médico-cirúrgicos.

Análise e Mapeamento sobre a Avaliação da Evidenciação dos Atos Públicos dos Entes Governamentais

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Lucas dos Santos Matos

2015-08-01

Full Text Available O aumento da demanda da população e dos órgãos fiscalizadores por informações relacionadas à gestão governamental ocasionou a necessidade de melhorar a evidenciação dos relatórios públicos, tanto na abrangência e qualidade da informação quanto na sua transparência. Surge então a necessidade de desenvolver modelos de avaliação da transparência dos atos públicos que contemplem a necessidade dos usuários. Assim, esta pesquisa, de natureza exploratório-descritiva, com abordagem qualitativa e quantitativa, objetiva realizar um mapeamento sobre o tema avaliação da evidenciação dos atos públicos dos entes governamentais a partir da seleção de um rol de artigos internacionais reconhecidos cientificamente e, a partir deste portfólio, realizar uma análise de conteúdo destes artigos, visando à identificação de oportunidades de pesquisas. Dessa forma, foi selecionado o Knowledge Development Process – Constructivist (ProKnow-C como instrumento de intervenção do processo. O resultado foi um conjunto de 14 artigos científicos, publicados entre 2000 e 2013, com reconhecimento e, para estes artigos, evidenciou-se os principais artigos, periódicos, autores e palavras-chave acerca do tema de estudo. A análise de conteúdo possibilitou encontrar destaques e oportunidades para pesquisas futuras. Verificou-se que a literatura trata apenas de modelos de avaliação da transparência pública conforme os critérios definidos por normas e legislações, mas é necessário considerar as necessidades dos usuários.

A proteção dos deslocados ambientais no regime internacional dos refugiados

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Andrea Pacheco Pacífico

Full Text Available O deslocamento de pessoas por causas ambientais gera discussões pela ausência de reconhecimento legal e proteção jurídica específica para essa categoria de pessoas. Assim, este artigo examina o Regime Internacional dos Refugiados (RIR, conceitua deslocados ambientais (DA e reflete sobre a ausência de proteção pelo RIR. Em seguida, examina as causas e as consequências dos deslocamentos e as formas de proteção aos DA, concluindo que os regimes vigentes não lhes oferecem proteção efetiva. Uma solução, segundo Betts (2009, seria cooperação para proteção por persuasão via cruzamento de assuntos de interesse estatal, persuadindo Estados a cooperarem em seus interesses, como saída eficaz para a ausência de proteção efetiva aos DA.

EDITORIAL: Plágio e ineditismo dos artigos

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Fernando Castro Amoras

2016-06-01

Full Text Available EDITORIAL: Plágio e ineditismo dos artigos A partir deste ano de 2016, a revista Estação Científica (UNIFAP passou a adotar, como instrumento auxiliar da seleção dos artigos que serão publicados, a checagem de plágio nos conteúdos dos trabalhos que recebemos. Consta no site da revista a informação de que todos os trabalhos passarão por verificação de plágio, e desta forma alerta-se que sejam apresentados à Estação Científica (UNIFAP apenas os trabalhos que tenham autenticidade de autoria.

Application of perturbation methods for sensitivity analysis for nuclear power plant steam generators; Aplicacao da teoria de perturbacao a analise de sensibilidade em geradores de vapor de usinas nucleares

Energy Technology Data Exchange (ETDEWEB)

Gurjao, Emir Candeia

1996-02-01

The differential and GPT (Generalized Perturbation Theory) formalisms of the Perturbation Theory were applied in this work to a simplified U-tubes steam generator model to perform sensitivity analysis. The adjoint and importance equations, with the corresponding expressions for the sensitivity coefficients, were derived for this steam generator model. The system was numerically was numerically solved in a Fortran program, called GEVADJ, in order to calculate the sensitivity coefficients. A transient loss of forced primary coolant in the nuclear power plant Angra-1 was used as example case. The average and final values of functionals: secondary pressure and enthalpy were studied in relation to changes in the secondary feedwater flow, enthalpy and total volume in secondary circuit. Absolute variations in the above functionals were calculated using the perturbative methods, considering the variations in the feedwater flow and total secondary volume. Comparison with the same variations obtained via direct model showed in general good agreement, demonstrating the potentiality of perturbative methods for sensitivity analysis of nuclear systems. (author) 22 refs., 7 figs., 8 tabs.

Taxonomia de Coffea arabica L. VI: caracteres morfológicos dos haplóides

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A. Carvalho

1952-06-01

Full Text Available No decorrer dos trabalhos de melhoramento do café em execução no Instituto Agronômico de Campinas, plantas haplóides foram encontradas nas variedades typica, bourbon, maragogipe, semperflorens, laurina, erecta, caturra e San Ramon, da espécie Coffea arabica. Todos os haplóides apresentam porte menor e fôlhas mais estreitas e mais finas do que as variedades que lhes deram origem. Apesar de as flores serem completas, nota-se esterilidade muito acentuada. Raramente se formam alguns frutos, e êstes são providos de uma única semente, motivo pelo qual as plantas haplóides são denominadas "monosperma". Os fatôres genéticos dominantes maragogipe (Mg, erecta (Er, caturra (Ct e San Ramon, bem como os gens recessivos semperflorens (sf, e laurina (lr, das variedades estudadas, manifestam-se nas plantas haplóides, de modo semelhante ao que ocorre nas plantas diplóides correspondentes. O fator para coloração bronze dos brotos novos tem dominância incompleta e, na condição heterozigota (Brbr, mostra intensidade intermediária de côr. Nas plantas haplóides contendo um só alelo Br, a côr dos brotos novos é bronze-clara. Uma única dose do fator Na, que também apresenta dominância incompleta, dando, na forma heterozigota (Nana e na presença de tt, o fenótipo conhecido por murta, manifesta-se, na forma haplóide, dando plantas semelhantes às homozigotas ttNaNa, apenas com fôlhas mais estreitas e mais finas. Chamou-se atenção para as linhas puras de café obtidas pela duplicação do número de cromosômios dos haplóides e sua aplicação nos ensaios de linhagens e na determinação das taxas de mutação. As observações realizadas na meiose da espécie C. arabica, bem como os dados das análises genéticas e as observações feitas nesses haplóides parecem indicar que, se essa espécie fôr alotetraplóide, tal origem deve ser bem antiga, comportando-se hoje a espécie C. arábica, como um diplóide normal. As plantas

Diâmetro dos grãos de pólen e tamanho dos estômatos em acessos diplóides e tetraplóides de Hemarthria altissima (Poiret Stapf & Hubbard (Gramineae Pollen grain diameter and stomatal size in diploid and tetraploid accessions of Hemarthria altissima (Poiret Stapf & Hubbard (Gramineae

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Solange Bosio Tedesco

1999-06-01

Full Text Available Sete acessos da gramínea forrageira Hemarthria altissima, diplóides e tetraplóides africanos e tetraplóides brasileiros, foram analisados com fins de caracterizar, nos diferentes níveis de ploidia, os parâmetros diâmetro dos grãos de pólen e tamanho dos estômatos, com o objetivo de utilizar esses critérios para inferência de níveis de ploidia nessa espécie. As medidas foram feitas com o auxílio de um microscópio com ocular micrométrica. Os resultados demostraram que o diâmetro dos grãos de pólen podem ser utilizados para caracterizar diferentes níveis de ploidia, enquanto que o tamanho dos estômatos não é um critério seguro nessa espécie.Seven accessions of african diploid and tetraploid and brazilian tetraploid plants of Hemarthria altissima were studied to distinguish, in each ploidy level, the characters of pollen grain diameter and stomatal size. Measurements were performed with ocular micrometer microscope. Results demonstrated that pollen grain diameter can be used to characterize different ploidy levels, but the stomatal size is not a reliable criterion in this species.

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

Energy Technology Data Exchange (ETDEWEB)

NONE

2000-07-01

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

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

Energy Technology Data Exchange (ETDEWEB)

NONE

2000-07-01

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

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

Storage and uses alternatives of depleted UF6

International Nuclear Information System (INIS)

Marques, S.; Dotto, R.M.

1988-01-01

The U-enrichment of the Angra-1 pellets (Brazil) have generated about 792 ton of depleted-U, which is nowadays beeing stored by URENCO. The possible sending of this compound to Brazil, added to the fact that in the future, NUCLEI (Nuclebras Enriquecimento Isotopico) itself will generate it, reopens the discussion of the destination of this compound. In this context, the necessity, interest and viability aspects of a reconvertion plant of UF 6 in Brazil are getting important and are, in what follows, breafly discussed. (author) [pt

AVALIAÇÃO DA EFICIÊNCIA DA APLICAÇÃO DOS ROYALTIES DA MINERAÇÃO NO DESENVOLVIMENTO SOCIAL DOS MUNICÍPIOS MINEIROS

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Alexandre de Cássio Rodrigues

2016-12-01

Full Text Available Tendo os royalites da mineração como origens de recursos públicos dos municípios nos quais a atividade mineral ocorre, essa pesquisa tem como objetivo analisar, por meio de indicadores sociais, se a aplicação dos royalties da mineração tem impactado positivamente no desenvolvimento dos municípios mineiros. Para tanto, utilizou-se na pesquisa documental a prestação de contas anual das prefeituras e câmaras municipais, informações sobre população municipal no site do IBGE e obtido o Índice Firjan de Desenvolvimento Municipal, sendo posteriormente utilizadas técnicas de regressão linear e análise de clusters. Os resultados indicam que o aumento da dependência dos royalties da mineração implica na redução do desenvolvimento humano dos municípios de base mineral. Além disso, não foram encontradas evidências de que a atividade mineral proporcione altos níveis de geração de emprego e distribuição de renda. Portanto, é necessário que esses recursos sejam geridos de forma mais eficiente, priorizando-se projetos que estimulem a diversificação econômica dos municípios.

Das bruxas, dos índios, dos negros e dos jovens da Febem

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Sylvia Leser de Mello

2001-01-01

Full Text Available Este artigo visa discutir os temas Pesquisa e Direitos Humanos, partindo da definição do que pretende a Ciência, suas limitações e momentos seus a serviço de condenações de bruxas e ateus. Trata-se de levantar a questão da 'parcialidade' da Ciência e das formas de exclusão que ela ajudou a gerar e manter face aos criminosos, aos loucos, aos negros e, sem dúvida, aos jovens das camadas populares que são institucionalizados na FEBEM. E, na tentativa de resistência a se deixar levar pelo que de nefasto existe na mercantilização da Ciência hoje, buscar radicalizar a exigência de defesa dos Direitos Humanos.

Optimization of reload of nuclear power plants using ACO together with the GENES reactor physics code

Energy Technology Data Exchange (ETDEWEB)

Lima, Alan M.M. de; Freire, Fernando S.; Nicolau, Andressa S.; Schirru, Roberto, E-mail: alan@lmp.ufrj.br, E-mail: andressa@lmp.ufrj.br, E-mail: schirru@lmp.ufrj.br, E-mail: ffreire@eletronuclear.gov.br [Coordenacao de Pos-Graduacao e Pesquisa de Engenharia (PEN/COPPE/UFRJ), Rio de Janeiro, RJ (Brazil); Eletrobras Termonuclear S.A. (ELETRONUCLEAR), Rio de Janeiro, RJ (Brazil)

2017-11-01

The Nuclear reload of a Pressurized Water Reactor (PWR) occurs whenever the burning of the fuel elements can no longer maintain the criticality of the reactor, that is, it cannot maintain the Nuclear power plant operates within its nominal power. Nuclear reactor reload optimization problem consists of finding a loading pattern of fuel assemblies in the reactor core in order to minimize the cost/benefit ratio, trying to obtain maximum power generation with a minimum of cost, since in all reloads an average of one third of the new fuel elements are purchased. This loading pattern must also satisfy constraints of symmetry and security. In practice, it consists of the placing 121 fuel elements in 121 core positions, in the case of the Angra 1 Brazilian Nuclear Power Plant (NPP), making this new arrangement provide the best cost/benefit ratio. It is an extremely complex problem, since it has around 1% of great places. A core of 121 fuel elements has approximately 10{sup 13} combinations and 10{sup 11} great locations. With this number of possible combinations it is impossible to test all, in order to choose the best. In this work a system called ACO-GENES is proposed in order to optimization the Nuclear Reactor Reload Problem. ACO is successfully used in combination problems, and it is expected that ACO-GENES will show a robust optimization system, since in addition to optimizing ACO, it allows important prior knowledge such as K infinite, burn, etc. After optimization by ACO-GENES, the best results will be validated by a licensed reactor physics code and will be compared with the actual results of the cycle. (author)

Optimization of reload of nuclear power plants using ACO together with the GENES reactor physics code

International Nuclear Information System (INIS)

Lima, Alan M.M. de; Freire, Fernando S.; Nicolau, Andressa S.; Schirru, Roberto

2017-01-01

The Nuclear reload of a Pressurized Water Reactor (PWR) occurs whenever the burning of the fuel elements can no longer maintain the criticality of the reactor, that is, it cannot maintain the Nuclear power plant operates within its nominal power. Nuclear reactor reload optimization problem consists of finding a loading pattern of fuel assemblies in the reactor core in order to minimize the cost/benefit ratio, trying to obtain maximum power generation with a minimum of cost, since in all reloads an average of one third of the new fuel elements are purchased. This loading pattern must also satisfy constraints of symmetry and security. In practice, it consists of the placing 121 fuel elements in 121 core positions, in the case of the Angra 1 Brazilian Nuclear Power Plant (NPP), making this new arrangement provide the best cost/benefit ratio. It is an extremely complex problem, since it has around 1% of great places. A core of 121 fuel elements has approximately 10"1"3 combinations and 10"1"1 great locations. With this number of possible combinations it is impossible to test all, in order to choose the best. In this work a system called ACO-GENES is proposed in order to optimization the Nuclear Reactor Reload Problem. ACO is successfully used in combination problems, and it is expected that ACO-GENES will show a robust optimization system, since in addition to optimizing ACO, it allows important prior knowledge such as K infinite, burn, etc. After optimization by ACO-GENES, the best results will be validated by a licensed reactor physics code and will be compared with the actual results of the cycle. (author)

Operational safety system performance alternative to the WANO's indicator

International Nuclear Information System (INIS)

Lyra, Moacir

2002-01-01

One of the operational safety performance indicators recommended by the World Association of Nuclear Operators (WANO) and adopted by Electronuclear is the reliability of the safety systems. The parameter selected to represent this indicator is the average unavailability of the trains of the concerned system. This parameter would be universally representative of the reliability for comparison purpose only if all nuclear power plants were designed within the same redundancy criteria. Considering the diversity of design criteria of the power plants in operation and based on a probabilistic approach, this paper proposes new performance indicators which are comparable regardless the redundancy criteria of the system. A case example applied to a system of the Angra 2 nuclear power plant shows that, even though with the plant in the infancy phase, the performance of the system in the period is very good. (author)

COMPARAÇÃO DOS MÉTODOS OFICIAIS DE ANÁLISE E CROMATOGRÁFICOS PARA A DETERMINAÇÃO DOS TEORES DE ALDEÍDOS E ÁCIDOS EM BEBIDAS ALCOÓLICAS

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NASCIMENTO Ronaldo F.

1998-01-01

Full Text Available É apresentado um estudo comparativo entre os métodos oficiais e cromatográficos para a análise de aldeídos e de ácidos em bebidas alcoólicas. Foram analisadas trinta e cinco amostras de destilados alcoólicos. Com respeito a determinação dos teores totais de aldeídos e de ácidos. Os métodos oficiais e cromatográficos apresentam similar exatidão e reprodutibilidade. Entretanto, apenas os métodos cromatográficos permitem identificar e quantificar os componentes de cada série homologa. As metodologias propostas utilizando as técnicas de cromatografia gasosa e cromatografia líquida são simples, rápidas e apresentam maior sensibilidade que os métodos oficiais sendo aplicáveis também a amostras coloridas.

Influência da forma dos agregados miúdos nas propriedades do concreto

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F. Fabro

Full Text Available Os agregados miúdos utilizados na produção de concretos são basicamente as areias naturais provenientes dos leitos dos rios e os agregados artificiais oriundos da britagem de rocha. A principal diferença entre estes dois agregados está no formato de seus grãos. O objetivo principal deste trabalho é avaliar o formato dos grãos de agregados miúdos por meio de diferentes parâmetros, analisando as diferenças entre as formas dos agregados, e suas conseqüências nas propriedades das argamassas e concretos confeccionadas com estes materiais. Para medição dos grãos dos agregados empregou-se a análise digital de imagens e foram calculados os seguintes parâmetros: relação de aspecto, esfericidade, indicador de lamelaridade e coeficiente de forma, sendo que os dois últimos foram os que melhor avaliaram a forma dos agregados. Observou-se que o formato dos grãos dos agregados artificiais depende do tipo de britador empregado pelas pedreiras no processo de britagem das rochas. Os agregados oriundos do britador do tipo vertical de impacto possuem grãos mais arredondados, semelhantes aos grãos da areia natural. Verificou-se que o formato dos grãos dos agregados tem influência direta sobre a consistência das argamassas e concretos, porém não apresentou influência nos resultados de resistência à compressão.

A prática de enfermagem em uma Unidade de Queimados: análise dos discursos dos enfermeiros

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Lídia Aparecida Rossi

1994-06-01

Full Text Available Este estudo teve como objetivo analisar a prática de enfermagem em uma Unidade de Queimados. Essa análise foi realizada a partir dos depoimentos de enfermeiros dessa Unidade, obtidos em um estudo anterior através de técnica de observação participante e de registro cursivo(19. Concluímos que os enfermeiros estão insatisfeitos com os salários, com a jornada de trabalho, com o relacionamento médico-enfermeiro e com as situações que envolvem o sofrimento e a agressividade dos pacientes. O cuidado direto parece consistir em uma fonte de satisfação, mas o enfermeiro está dividido entre a realização desse cuidado e os problemas que têm que resolver. O planejamento da assistência foi ajustado às rotinas do serviço e não às necessidades dos pacientes.

Relation between water chemistry and operational safety

International Nuclear Information System (INIS)

Oliveira, M.F. de.

1991-01-01

This report describes the relation between chemistry/radiochemistry and operational safety, the technics bases for chemical and radiochemical parameters and an analysis of the Annual Report of Angra I Operation and OSRAT Mission report to 1989 in this area too. Furthermore it contains the transcription of the technical Specifications related to the chemistry and radiochemistry for Angra I. (author)

Bases morfofisiológicas para maior tolerância dos híbridos modernos de milho a altas densidades de plantas Morpho-physiological bases for greater tolerance of modern maize hybrids to high plant densities

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Luís Sangoi

2002-08-01

Full Text Available O lançamento de híbridos de milho tolerantes ao aumento da densidade de plantas contribuiu para o incremento do potencial produtivo da cultura na segunda metade do século XX. Objetiva-se com esta revisão de literatura discutir características morfológicas, fisiológicas, fenológicas e alométricas que contribuíram para maior adaptação do milho a elevadas densidades de plantas. Os processos de seleção utilizados pelos melhoristas minimizaram a natureza protândrica da planta, reduzindo o tamanho do pendão. Isso propiciou desenvolvimento alométrico mais equilibrado entre as inflorescências masculina e feminina, limitou a esterilidade feminina e favoreceu a sincronia entre antese e espigamento. O ideotipo de planta compacto dos híbridos modernos, caracterizado pela presença de plantas baixas, com menor número de folhas e folhas eretas, melhorou a qualidade da luz no interior do dossel, contribuindo para reduzir a dominância apical do pendão sobre as espigas. A menor produção de fitomassa reduziu a competição intra-específica e aumentou a eficiência de uso dos fatores ambientais, disponibilizando mais carboidratos para atender às diferentes demandas da planta na fase reprodutiva. O maior equilíbrio nas relações entre fonte e dreno contribuiu para retardar a senescência foliar, resultando em maior absorção de nutrientes e maior eficiência de uso do nitrogênio. O desenvolvimento de híbridos com menor estatura e espigas mais próximas do solo reduziu a quantidade de plantas acamadas e quebradas. A compreensão das bases morfofisiológicas responsáveis pela maior tolerância do milho à competição intra-específica auxiliará melhoristas e fisiologistas a maximizar a eficiência do arranjo de plantas para alcançar altos rendimentos.The release of maize hybrids tolerant to high plant densities has contributed to enhance the potential for grain yield in this crop in the second half of last century. This review aims

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

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

Obtenção de anticorpos policlonais contra proteínas presentes em plantas afetadas pela anomalia declínio dos citros Production of antibodies against proteins expressed in plants affected by citrus blight

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Sanzio Carvalho Lima Barrios

2006-10-01

Full Text Available O declínio dos citros, uma anomalia de etiologia desconhecida, continua sendo um dos entraves para o setor citrícola, uma vez que não existem medidas de prevenção e controle para as plantas acometidas pela anomalia. Para a caracterização e estudo da anomalia, muita ênfase tem sido dada à mudança na expressão gênica de plantas afetadas, que culmina no acúmulo de proteínas. Proteínas totais extraídas dos vasos do xilema de raízes de plantas afetadas pela anomalia, quando separadas por eletroforese no sistema SDS-PAGE 12,5%, apresentam um perfil eletroforético contendo proteínas com massas moleculares de cerca de 21, 23, 31 e 42 kDa, sendo que plantas consideradas sadias apresentam proteínas de 21, 31 e 42 kDa. Com este trabalho objetivou-se obter anticorpos contra essas proteínas, bem como a titulação adequada para os mesmos. Duas inoculações subcutâneas foram realizadas em coelhos, espaçadas de 15 dias, ambas usando cerca de 120 µg de proteína isolada, sendo que cada coelho recebeu uma proteína específica, visando à produção de anticorpos. A primeira sangria foi realizada aos 21 dias após a primeira inoculação e as demais semanalmente. A técnica Western Blotting foi realizada para a confirmação da especificidade dos anticorpos, bem como para determinação das respectivas titulações. O título 1:1500 foi aquele que proporcionou maior especificidade para as proteínas de 21, 23 e 31 kDa. Para a proteína de 42 kDa a melhor titulação foi de 1:3000. Estes anticorpos poderão ser utilizados em estudos para caracterização dessas proteínas.Citrus blight, an abnormality of unknown etiology, is a major problem in citrus production, since there are no prevention and control measures to be taken. In order to characterize this abnormality, changes in genetic expression of the affected plants have exhaustedly been studied. Crude proteec extract obtained from the root xylem of the abnormal plants, when separated