WorldWideScience

Sample records for angra ii nuclear

  1. Cognitive workload analysis of Angra II nuclear power plant operators under design basis accidents

    International Nuclear Information System (INIS)

    This article presents an application of cognitive modelling for evaluation the workload of nuclear operator crew. The task chosen for modelling was the small break LOCA accident in Angra II nuclear power plant. In this modelling the operation teamwork is composed by a reactor operator, a turbine operator and a shift supervisor. In the simulation the correct identification of the accident type by the team during the period of automatic actions carried through the plant protection systems is considered, i.e., the identification of the accident type is carried out during the first thirty minutes after the accident beginning. The ACT-R (Adaptive Control of Thought - Rules) was used for the simulation. The article also presents the description of the basic features of ACT-R model. We conclude that, despite the approaches made in the cognitive tasks, program ACT-R is a useful instrument for cognitive analysis of operator crew. (author)

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

    International Nuclear Information System (INIS)

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

  3. Monitoring Nuclear Reactors with Antineutrino Detectors: The ANGRA Project

    International Nuclear Information System (INIS)

    Nuclear reactors are intense source of antineutrinos and the thermal power released in the fission process is directly related to the emitted antineutrino flux. As antineutrinos interact very weekly with matter and escape the reactor containment without any significant change in their number, measuring the antineutrino flux can give quasi real time information on the reactor status (on/off) and thermal power. Furthermore as the amount of fissile elements change during the burn up of the nuclear fuel and each fissile isotope has a characteristic antineutrino energy spectrum, measuring the antineutrino energy spectrum escaping the reactor can give also information on the composition of the nuclear fuel. These unique features make antineutrino detectors good candidates to become in the near future a new safeguards tool for monitoring nuclear reactors through counting rates and spectral antineutrino measurements. We will present the status of the ANGRA Neutrinos project, aimed at developing an antineutrino detector for monitoring nuclear reactor activity. The Angra experiment will be deployed at the Brazilian nuclear power plant Angra II. A water Cherenkov detector of one ton target will be placed in a commercial container just outside the reactor containment, about 30 m of the reactor core. The 4 GW thermal power of the Angra II reactor will provide a few thousand antineutrino inverse beta decay interactions per day. The main challenge of the experiment will be to overcome the very high cosmic ray induced background at sea level, consisting mainly of muons, neutrons, gammas and electrons. We have estimated a muon flux of the order of 350 Hz and a neutron flux of about 4 Hz (left after the polyethylene shielding) in the target region. To overcome the background the detector will consist of three subsystems: 1) a muon veto 99% efficient placed in the outer most detector layer; 2) a neutron shield 30cm thick consisting of polyethylene sheets; 3) a central detector

  4. 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)

    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)

  5. 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)

  6. Waste treatment from Angra 2 and 3 nuclear power plants

    International Nuclear Information System (INIS)

    The radioactive elements produced in nuclear power plant like Angra 2 and 3 are treated in order to guarantee that discharge of radioactivity to environment does not result in doses higher than legal limits. In this paper is presented the project of treatment systems of radioactive wastes of Angra 2 e 3. The quantity of radioactive waste expected (base of project) as well as judgment to discharge in environment. (C.M.)

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

    Energy Technology Data Exchange (ETDEWEB)

    Selvatici, Edmundo; Castanheira, Luiz Carlos C.; Silva Junior, Nilo Garcia da, E-mail: edsel@eletronuclear.gov.br, E-mail: lccast@eletronuclear.gov.br, E-mail: nilogar@eletronuclear.gov.br [Eletrobras Termonuclear S.A. (SCO/ELETRONUCLEAR), Angra dos Reis, RJ (Brazil). Superintendencia de Coordenacao da Operacao; Zazo, Francisco Javier Lopez; Ruiz, Jose Antonio, E-mail: jlopez@tecnatom.es, E-mail: jaruiz@tecnatom.es [Tecnatom S.A., San Sebastian de los Reyes, Madrid (Spain)

    2015-07-01

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

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

    International Nuclear Information System (INIS)

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

  9. Angra nuclear plant - environmental control program

    International Nuclear Information System (INIS)

    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

  10. 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)

    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)

  11. Nuclear power plant Angra integrated enterprise management system

    International Nuclear Information System (INIS)

    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)

  12. Public participation in the environmental licensing process of the Angra II reactor

    International Nuclear Information System (INIS)

    Newly adopted environmental legislation in Brazil, coupled with the construction delays of the Angra II Nuclear Power Plant, raised questioning among the public on the applicability of fast licensing authorizations. To analyse this issue, a Special Commission was setup of society's representatives and of government agencies involved in the project construction and licensing. The commission took 1/2 years to reach consensus regarding the correctness of the current licensing process. The openness of the discussions, and the opportunity of interaction during such a long time, led the group members to build up unprejudiced understanding, thus achieving mutually acceptable results. (author). 2 refs

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

    Energy Technology Data Exchange (ETDEWEB)

    Viana, Ronaldo do Nascimento

    2006-07-01

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

  14. The nuclear safety culture approach at Angra 1 NPP

    International Nuclear Information System (INIS)

    TMI-2 and Chernobyl accidents. What did they have in common? TMI-2 was an American design Reactor, with full steel containment and several special design characteristics such as independent and separated safety and protection sets, with a hard licensing process through US NRC and even though suffered an accident that completely destroyed the primary plant, with the melting of the greatest portion of the nuclear fuel. Chernobyl 4 was a Soviet design reactor, type RBMK, with no containment, a questionable design, and exploded in 1986, aproximately seven years after TMI-2 accident. If a sound safety culture would have be presented during the design and the operation of both plants, those accidents would have never occurred. The post-accidents findings: The Kemmeny commission and the required action plants to implement the lessons learned post TMI-2 focused on design and operational problems. Safety culture in Angra 1: We translated to Portuguese the document INSAG-4 and INSAG-6 and included those topics as subjects to be tought during the annual general retraining for all personnel. We choose one area-chemistry section- to undergo a pilot program for self assessment/self checking. We developed a series of safety indicators that are collected monthly and discussed in a regular meeting with the heads of the divisions. Some examples are: number of alarms lit at MCB; number of controllers in manual; Rate of installation and removal of temporary modifications; calculated alowable time within a LCO and attendance to recommendations according to internal event reports and to QA findings. It is a continuous, on going task. Everyone in the organization must understand that and shall be part of it. We at Angra 1, are giving some important steps towards that objective. There are still room for improvements. We are aware of that. (author)

  15. Socio-environmental impacts of Angra dos Reis nuclear power plant

    International Nuclear Information System (INIS)

    Technological aspects and the social problematic inherent to implementation of nuclear power plants in Brazil are studied. it is showed the study in two levels: one of them, attacks aspects linked to nuclear energy and their risks in Brazil; the other one, treats of impacts of the Angra dos Reis nuclear power plants on the local comunity. (M.C.K.)

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

    International Nuclear Information System (INIS)

    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)

  17. Angra dos Reis nuclear power plant. Water intake. Hydraulic studies in reduced models

    International Nuclear Information System (INIS)

    This paper constitutes a summary about the first exploration stage of reduced model from refrigeration water intake in Angra dos Reis nuclear power. The results of wave measures during the analysis without protection work, joined and in the interior of water intake unities are presented. (C.G.C.)

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

    International Nuclear Information System (INIS)

    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)

  19. Investigation on and quality control of concretes for the Angra dos Reis nuclear power plant

    International Nuclear Information System (INIS)

    By the fact of being the first Nuclear Plant to be built in Brasil , the Angra dos Reis Nuclear Plant has arisen a great interest to the national engineering.As this plant is the first of a great complex which is begining in the country, the divulgation of the technical problems found during the construction fase is a very valuable subsidy for the next plants. A summary of the concrete researches for the Angra dos Reis Nuclear Power Plants performed are presented, with emphasis on the high density concrete studies, and for the crack control through the temperature control. Strain capacity tests results with a slow loading equipment and creep tests combined with modulus of rupture are used to predict the crack resistence of concrete. (Author)

  20. 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)

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

    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)

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

    International Nuclear Information System (INIS)

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

  4. Front-end Design and Characterization for the ν-Angra Nuclear Reactor Monitoring Detector

    Science.gov (United States)

    Dornelas, T. I.; Araújo, F. T. H.; Cerqueira, A. S.; Costa, J. A.; Nóbrega, R. A.

    2016-07-01

    The Neutrinos Angra (ν-Angra) Experiment aims to construct an antineutrinos detection device capable of monitoring the Angra dos Reis nuclear reactor activity. Nuclear reactors are intense sources of antineutrinos, and the thermal power released in the fission process is directly related to the flow rate of these particles. The antineutrinos energy spectrum also provides valuable information on the nuclear source isotopic composition. The proposed detector will be equipped with photomultipliers tubes (PMT) which will be readout by a custom Amplifier-Shaper-Discriminator circuit designed to condition its output signals to the acquisition modules to be digitized and processed by an FPGA. The readout circuit should be sensitive to single photoelectron signals, process fast signals, with a full-width-half-amplitude of about 5 ns, have a narrow enough output pulse width to detect both particles coming out from the inverse beta decay (bar nue+p → n + e+), and its output amplitude should be linear to the number of photoelectrons generated inside the PMT, used for energy estimation. In this work, some of the main PMT characteristics are measured and a new readout circuit is proposed, described and characterized.

  5. An experience of marine macrofouling control in Angra 1 - Almirante Alvaro Alberto nuclear power plant

    International Nuclear Information System (INIS)

    One of the greatest problems at the Power Plants that use sea water in the circulating water system, is the development of fouling in its sections. In Central Nuclear Almirante Alvaro Alberto - Angra 1, this fouling is represented by barnacles. These barnacles have contributed significantly to the damaging in the condenser tubes, resulting in the changing from cooper alloy tubes to Titanium ones. To help the understanding of the development and control of fouling, some researches and observations have been made using techniques adequated to Angra 1. The low-level continuous chlorination, the water flux variation and the continuous cleaning tubes system (AMERTAP) combined and used in circulation water sistem, showed satisfactory preliminar results in fouling control. (Author)

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

    International Nuclear Information System (INIS)

    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

  7. Flooding analysis of the safety-related buildings of Angra-II

    International Nuclear Information System (INIS)

    In the design phase and for the purpose of licensing of nuclear power plants, the consequences are analyzed as for instance the internal flooding caused by postulated failures in pipings and components, as well as consequential failures due to external events, of piping/components not designed for such event. In this paper, the basic criteria adopted in the flooding analysis of the safety-related buildings of Angra-2 NPP are presented, as well as the main results and consequences of this analysis in the plant design. (author). 3 refs., 1 fig

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

    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)

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

    International Nuclear Information System (INIS)

    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)

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

    International Nuclear Information System (INIS)

    This study evaluated the spatial distribution of two environmentally relevant radionuclides, 137Cs and 40K, 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 137Cs activities in the region with other locations in the world showed that the presence of this artificial nuclide is due to the atmospheric fallout from past nuclear tests made during the Cold War, not to the nuclear power plant activities.

  13. 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.

  14. A study on the external dose rates around of the nuclear plant of Angra I

    International Nuclear Information System (INIS)

    The Laboratory for Environmental Monitoring of Electronuclear monitors the external dose rates around Angra Nuclear Power Plant, regarding the local radiological conditions and its implication to the environment. A monitoring program has started at 1974 and goes on up to now, taking into account terrestrial gamma radiation, aquatic and terrestrial biomass, soils, sediments and air filters analysis within an effective area of more than 30 Km around the nuclear reactor under operation. Concerning external exposure, TL dosimetry, ionization chamber and gamma spectrometry were used. 42 monitoring stations, between the cities of Angra dos Reis and Paraty, are under operation by this time. Results indicate that actually exposure rates evaluated inside the monitoring area do not differ from typical external radiation data obtained from the State of Rio de Janeiro. A weak correlation was found between wind direction and angular external exposure distribution, indicating insignificant dispersion and deposition of man-made radionuclides from the power plant to its vicinity. On the other hand, large gradients of gamma exposure rates were found on sandy sites located at the 'directed area of impact of the reactor'. Nevertheless, the absence of artificial radionuclides and the large variations of natural ones suggest the sedimentary marine dynamics as the major agent. (author)

  15. Reactivity measurements during startup physics tests for the cycle 7 of Angra-1 Nuclear Power Station

    International Nuclear Information System (INIS)

    Angra Nuclear Power Station, Unit 1, in Angra dos Reis, RJ, Brazil, with a PWR - Pressurized Water Reactor - has an installed capacity of 1876 MW thermal and 657 MW electrical. The ongoing seventh operating cycle is designed for a duration of 217 Effective Full Power Days. The Physics Tests for the cycle 7 were started on 03/dec/97, following internal technical and administrative procedures and based also on the code ANSI-ANS-19.6.1-1985-Reload Startup Physics Tests for Pressurized Water Reactors. The purpose of the Physics Tests is to confirm by measurements the predicted core parameters as stated in the Nuclear Design report for each specific cycle and the adherence to Technical Specifications. As a minimum the Physics Tests program comprises the following determinations: reactivity computer checkout, reactor coolant system boron concentration for control rods inserted and withdrawn, control rod worthies; moderator and isothermal temperature coefficient; neutron flux symmetry; zero and full power boron concentration. This paper describes the Lower Physics Tests only, that is, the tests performed between zero and around 2% power, before the admission of steam to the turbine-generator, and consequently, before the synchronism of the Unit to the electrical distribution network of the region center-south. (author)

  16. Beyond design basis accident management related to Angra 2 nuclear power plant

    International Nuclear Information System (INIS)

    Emergency procedures, associated to beyond design basis accident management, are important issues to guarantee the safe operation of nuclear power plants, and they may use plant normal operation systems for controlling such situation. The simulation of accident critical scenarios should be developed with the aid of the most recent versions of advanced tools for thermalhydraulic analysis, in order to verify the effectiveness of plant systems in avoiding or minimizing core damage. This thesis presents the evaluation of the capabilities of a best estimate thermalhydraulic code, RELAP5/MOD3.2, for realistically simulating the application of an emergency procedure, and additional measures, for a total loss of feedwater scenario in Angra 2, a four-loop pressurized water reactor nuclear power plant operating in Brazil. The recently proposed procedure consists of a complete depressurization of the steam generator secondary side. This measure aims at enhancing the passive feed to the steam generator through the feedwater lines and feedwater tank to restore core cooling. An experiment performed at the LOB/MOD2 facility, built with a scale factor of approximately 1/700 relatively to a design similar to that of Angra 2, was the reference data basis for this activity. The results pointed to a large possibility for the control during, at least, six hours after the transient beginning. (author)

  17. Analysis of the regulations, emergency procedures and radioactive wastes of the nuclear power plant of Angra dos Reis

    International Nuclear Information System (INIS)

    This is a report on the technical visit to the Nuclear Power Plant of Angra dos Reis and is related to the following subjects: ocupational doses, radioactive effluents and environmental control; emmergency plan, and destination of radioactive waste. (A.C.A.S.)

  18. Periods of high intensity rainfall and the safety of the Angra dos Reis nuclear power plant

    International Nuclear Information System (INIS)

    The high precipitation rates aggravate the consequences of hypothetical accidental releases of radioactive material from the Angra dos Reis Nuclear Power Plant (NPP), as determined by probabilistic risk assessment. A 30-year rainfall series was analysed, aiming at calculating the probability of occurring a given amount q of precipitation during a certain period of n days. The nine highest precipitation amounts have also been determined. The results show there was a rainier climate in the '50 s and '60 s than in the '70 s and '80 s. The risk of catastrophic landslide has been enhanced as an environmental impact of the construction of the Rio-Santos highway and NPP which have not yet gone through an abnormal rainfall period. It has been suggested that criteria should be established to reduce the nuclear power and shut down the reactor when the precipitation accumulates to a dangerous limit. (author)

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

    International Nuclear Information System (INIS)

    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)

  20. 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)

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

    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)

  3. The behavior of ANGRA 2 nuclear power plant core for a small break LOCA simulated with RELAP5 code

    Science.gov (United States)

    Sabundjian, Gaianê; Andrade, Delvonei A.; Belchior, Antonio, Jr.; da Silva Rocha, Marcelo; Conti, Thadeu N.; Torres, Walmir M.; Macedo, Luiz A.; Umbehaun, Pedro E.; Mesquita, Roberto N.; Masotti, Paulo H. F.; de Souza Lima, Ana Cecília

    2013-05-01

    This work discusses the behavior of Angra 2 nuclear power plant core, for a postulate Loss of Coolant Accident (LOCA) in the primary circuit for Small Break Loss Of Coolant Accident (SBLOCA). A pipe break of the hot leg Emergency Core Cooling System (ECCS) was simulated with RELAP 5 code. The considered rupture area is 380 cm2, which represents 100% of the ECCS pipe flow area. Results showed that the cooling is enough to guarantee the integrity of the reactor core.

  4. 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)

    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)

  5. Vibration monitoring in Angra I nuclear power plant steam generator feedwater system

    International Nuclear Information System (INIS)

    The safety and reliability are the primary criteria in the design and operation of a nuclear power plant. However, due to the aging of the plant and its components, it is difficult to assure that what was originally built and qualified under strict standards is still guaranteed. In order to assure safety, reliability, availability and capacity, aging management through predictive maintenance techniques are being introduced in most plants around the world. In this present work, the monitoring of the vibrations signatures at the Angra I nuclear power plant steam generators feedwater systems main components such as the main feedwater pumps, pressure breaker blocks and the by pass valves, is presented. The vibration data was acquired, afterwards some major repairs were performed and during the startup commissioning procedures. Some of the major repairs performed are: changing of one pump shaft with balancing and alignment, replacement of the original bypass control valves by new disk stack type pneumatic control valves. The results show that no major vibrations anomaly is present after the maintenance indicating adequacy of the repairs made. The monitoring of the vibration in nuclear power plant components is being increasingly used as a tool for predictive maintenance. (author)

  6. Simulation of a channel blockage transient in the Angra 2 Nuclear Reactor using a RELAP5-3D model

    Energy Technology Data Exchange (ETDEWEB)

    Gonzalez-Mantecon, Javier; Costa, Antonella L.; Veloso, Maria Auxiliadora F.; Pereira, Claubia; Reis, Patricia A.L.; Scari, Maria E., E-mail: mantecon1987@gmail.com, E-mail: antonella@nuclear.ufmg.br, E-mail: dora@nuclear.ufmg.br, E-mail: claubia@nuclear.ufmg.br, E-mail: patricialire@yahoo.com.br, E-mail: melizabethscari@yahoo.com [Universidade Federal de Minas Gerais (UFMG), Belo Horizonte (Brazil). Escola de Engenharia. Departamento de Engenharia Nuclear

    2015-07-01

    The Angra 2 Nuclear Power Plant (NPP) is a Pressurized Water Reactor (PWR) type with electrical output of about 1350 MW. The RELAP5-3D code was used to develop a detailed thermal hydraulic model of such reactor using reference data from the Angra 2 Final Safety Analysis Report (FSAR). In this work, a blockage transient has been investigated at full power operation. The transient herein considered is related to total obstruction of a core cooling channel of one fuel assembly. The calculations were performed using a point kinetic model. The reactor behavior after this transient was analyzed and the time evolution of cladding and coolant temperatures mass flow and void fraction are presented. (author)

  7. Erection planning for the electrical components and systems of a 1300 M We PWR nuclear power plant such as Angra-2

    International Nuclear Information System (INIS)

    This paper aims to present the concepts used in the erection planning for the electrical components and systems of a 1300 M We PWR nuclear power plant such as Angra 2. These concepts were developed and implemented in several erection time schedules by the design company (NUCLEN) and were based on the experience gained from erection of similar German nuclear power plants. (author)

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

    International Nuclear Information System (INIS)

    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)

  9. 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.

  10. Transition core DNBR penalty determination for Angra-1 nuclear power plant mixed cores consisting of standard and advanced fuel assemblies

    International Nuclear Information System (INIS)

    When two (or more) types of Fuel Assemblies (FA) are inserted in a nuclear reactor core, a flow redistribution occurs, due to the different hydraulic resistances of these assemblies. This way, the FA's with higher hydraulic resistance will get a Departure from Nucleate Boiling Ratio (DNBR) penalty since a part of the total flow will diverge to the FA's with lower hydraulic resistance. Regarding Angra-1 Nuclear Power Plant (NPP), it is planned in a next cycle to insert a new Advanced FA that is a result from a joint-venture project of the companies INB - Industrias Nucleares do Brasil, WEC - Westinghouse Electric Company and KNF - Korean Nuclear Fuel. Therefore, the purpose of this article is to show the work done to determine the DNBR penalty to be applied to the Advanced FA's present in a mixed (or transition) core consisting of Advanced and Standard FA's. (author)

  11. Micro-meteorological dispersion parametrisation for short range radioactive contamination modelling in the Angra dos Reis Nuclear Power Plant site

    Energy Technology Data Exchange (ETDEWEB)

    Rizza, U.; Mangia, C., E-mail: u.rizza@isac.cnr.it, E-mail: c.mangia@isac.cnr.it [Istituto di Scienze dell' Atmosfera e del Clima (CNR/ISAC), Lecce (Italy); Vilhena, M.T.; Bodmann, B., E-mail: vilhena@mat.ufrgs.br, E-mail: bardo.bodmann@ufrgs.br [Universidade Federal do Rio Grande do Sul (UFRS), Porto Alegre, RS (Brazil); Degrazia, G.A., E-mail: degrazia@ccne.ufsm.br [Universidade Federal de Santa Maria (UFSM), Santa Maria, RS (Brazil)

    2011-07-01

    In the present work we use an Eulerian diffusion approach as the base for a micro-meteorological dispersion parametrisation for short range radioactive contamination modelling in the Angra dos Reis nuclear power plant site. The closure of the diffusion equation is implemented by means of eddy diffusivity (K-theory). The parametrizations for the eddy diffusivity co- efficient are determined from micro-meteorological parameters that were extracted from meso-scale Weather Research and Forecasting (WRF) simulations. The model is based on Taylors statistical theory together with a model for Eulerian turbulence spectra from a superposition of a buoyant and a shear contribution. We implement an interface between a LES model for the planetary boundary layer and orography related features of WRF and simulate four days, from February, the 1{sup st} to the 4{sup th} of 2010, for the environment around the nuclear power plant site at Angra dos Reis, Rio de Janeiro state, Brazil. After extraction of micro-meteorological data we determined the eddy diffusivities under the hypothesis of homogeneous turbulence. As the principal result we show the time dependence (for the time scale of a day) of the dimensionless vertical eddy diffusivity coefficients. (author)

  12. 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)

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

    International Nuclear Information System (INIS)

    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)

  14. Angra Neutrino Project: status and plans

    OpenAIRE

    Anjos, J. C.; Barbosa, A. F.; Funchal, R. Z.; Kemp, E.; Magnin, J.; H. Nunokawa(Departamento de Física, Pontifícia Universidade Católica do Rio de Janeiro, C.P. 38071, 22452-970, Rio de Janeiro, Brazil); Peres, O.L.G.; Reyna, D.; Shellard, R. C.

    2005-01-01

    We present the status and plans of the Angra Project, a new nuclear reactor neutrino oscillation experiment, proposed to be built in Brazil at the Angra dos Reis nuclear reactor complex. This experiment is aimed to measure theta_13, the last unknown of the three neutrino mixing angles. Combining a high luminosity design, very low background from cosmic rays and careful control of systematic errors at the 1% level, we propose a high sensitivity multi-detector experiment, able to reach a sensit...

  15. Simplified methodology for Angra 1 containment analysis

    International Nuclear Information System (INIS)

    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)

  16. 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)

    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)

  17. 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)

    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

  18. 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)

    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)

  19. Multianodic photomultiplier tube characterization at Angra Neutrinos Project

    International Nuclear Information System (INIS)

    Full text: The Angra Neutrino Project aims to perform the antineutrino flux measurement at the Angra II nuclear reactor in Angra dos Reis, and to correlate it to the nuclear fuel fission and burn-up. A veto system is essential in the detection system, because the rate of cosmic particles reaching the detector is much higher than the antineutrinos rate (signal to background ratio 105). The planned veto system for the Angra experiment is an array of the X-Y type, consisting of orthogonal scintillator plastic plates, where particles detection is provided by the coincidence of signals from two or more scintillators. The light signals are taken to a Multianodic Photomultiplier Tube (MAPMT) with 8 x 8 pixels, through wavelength shifter optical fibers. In each MAPMT pixel, light is converted to electric charge and this analog information is brought to a data acquisition system composed of preamplifiers and data processing modules (MPDs). In the MPDs the information is digitized. A control and visualization software performs data acquisition, making use of an interface to the universal serial bus (USB). In this work we present the data acquisition chain and results for the photomultiplier characterization, which involves determining the gain of each one of the pixels by two different methods: the single photoelectron spectrum, and the statistical technique. In the latter method, by varying the number of photons hitting a given pixel one may determine the gain from a relationship between the average converted charge and its variance. We also present results of characterization for the front-end electronics and for the analog-to-digital converters in the MPDs, which were required to implement the MAPMT data acquisition system. (author)

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

    OpenAIRE

    Diego Santos Vieira de JESUS

    2011-01-01

    The aim of this article is to explain the positions taken by Brazil under Lula’s administration (2003-2010) on nuclear non-proliferation, disarmament and arms control. In order to strengthen its position in dispute settlement and to expand its participation in international institutions, Brazil wished to intermediate between nuclear-weapon and non-nuclear weapon States. The country also tried to pressure the nuclear weapon States to fulfill their disarmament obligations and to reduce asymmetr...

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

    International Nuclear Information System (INIS)

    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.)

  2. Experience with diagnostics at ANGRA I

    International Nuclear Information System (INIS)

    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

  3. Comparison of the RELAP4/MOD3 and RELAP4/MOD5 results to the loss-of-coolant accident blowdown phase simulation on the Angra-1 nuclear power station

    International Nuclear Information System (INIS)

    It's very important to obtain information of certain thermalhydraulic parameters of the Angra 1 Nuclear Power Plant during a large LOCA in three different points: in the cold leg, in the hot leg and between the steam generator and the pump. In this way, these paper describes the results comparison of these accidents with the RELAP4/MOD3 and RELAP4/MOD5 codes with the results in the Final Safety Analysis Report of Angra 1. It was used a 36 control volume model, with 48 junctions between the control volumes, 25 heat exchange structures and 8 valves. The transient analysis were made just during the blowdown phase of the LOCA. (author)

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

    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)

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

    OpenAIRE

    Diego Santos Vieira de JESUS

    2011-01-01

    El objetivo de este artículo es explicar las posiciones adoptadas por Brasil bajo la administración Lula (2003-2010) sobre la no proliferación, el desarme y el control de las armas nucleares. Con el objetivo de reforzar su posición de solucionador de controversias y ampliar su participación en las instituciones internacionales, Brasil deseó intermediar entre los Estados que contaban con armas nucleares así como también aquellos que no las tenían. Además, intentó presionar a los Estados con ar...

  7. 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)

  8. Simulation with RELAP5/MOD3.3 of a postulated 10% hot leg break in Angra 2 nuclear power plant

    International Nuclear Information System (INIS)

    This paper presents the simulation results of a 10% break in the hot leg of Angra 2 nuclear power plant, which was run with the computer code RELAP5/MOD3.3. The initial steady state conditions for this simulation are in agreement with the experiment named SB-HL-02 that was conducted in the Large Scale Test Facility in the Rig of Safety Assessment-IV program (ROSA-IV/LSTF). The main boundary conditions specified for the simulation were: high pressure injection system (HPI) and auxiliary feedwater system (AFW) were assumed to be unavailable; and loss of offsite power was assumed to occur concurrently with scram. The results obtained were scaled down and compared with the ROSA-IV/LSTF test, which was performed with the same boundary conditions. This activity was executed in the scope of IAEA research project (CRP J72005) - Evaluation of Uncertainties in the Simulation of Accidents in Angra 2 using RELAP5/MOD3.3 Code Applying CIAU Methodology. (author)

  9. 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)

    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)

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

    International Nuclear Information System (INIS)

    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

  11. Angra-1: Balance of an experience

    International Nuclear Information System (INIS)

    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.)

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

    International Nuclear Information System (INIS)

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2015-07-01

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

  14. AREVA signs a contract for completing Angra 3

    International Nuclear Information System (INIS)

    AREVA has signed a contract for the completion of the Angra-3 reactor with the Eletrobas Eletronuclear Brasilian company. Angra-3 is a PWR-type reactor with an output electric power of 1405 MW and located in the Rio-de-Janeiro state. AREVA will provide engineering assistance, some components of the primary loop and the digit control and instrumentation system of the reactor. AREVA will also provide assistance for performing final commissioning tests. The contract worth amounts to 1.25 billions euros. Angra 3 will comply with the post-Fukushima standards of the Brasilian Nuclear Safety Authority. (A.C.)

  15. Simplified methodology for analysis of Angra-1 containing

    International Nuclear Information System (INIS)

    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)

  16. 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)

    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)

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

    International Nuclear Information System (INIS)

    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

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

    International Nuclear Information System (INIS)

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

  19. Nuclear physics II

    International Nuclear Information System (INIS)

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

  20. Development of a computational system for monitoring reactivity parameters and xenon oscillation of Angra nuclear power station - Unit 1

    International Nuclear Information System (INIS)

    The objectives of this work was the modernization of the reactor operational functions within the plant process computer. The computational system, as developed, provides, through a graphic interface, an efficient interaction between the user, the system data bank and the data acquisition system. As a consequence, it was noted an agilization in the data acquisition methods, data reproduction, calculations, result analysis, procedure automation and update of data bank parameters and factors affecting reactor reactivity and average core burnup. Inside of the objective of this work was the implementation of TRIAX methodology for monitoring and control of xenon oscillations in the computer process of Angra 1. Herewith it is presented the data set and results of calculations used for the validation of the method at the plant. It was obtained good result performance. (author)

  1. An alternative nuclear program

    International Nuclear Information System (INIS)

    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)

  2. 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)

    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)

  3. Determination of radionuclides produced by Angra I nuclear power plant in marine samples collected in the bay 'Saco de Piraquara de Fora', Angra dos Reis City, Rio de Janeiro

    International Nuclear Information System (INIS)

    The Environmental Monitoring Laboratory was created in 1978 to monitor all the environment around Angra I NPP. This started since preoperational time and goes on today, during normal operation. The purpose of the work is to describe the activities of the Laboratory in the collection and analysis of the marine samples: beach sand, sea water, fish, algae and sediments - which can be reached by an inadverted release, and to supply the results of the activities produced by the artificial radionuclides released by the reactor - Cesium-134 and Cesium-137, Cobalt-58 and 60, Iodine-131, Manganese-54 and Tritium - that can be found today and then compare them with the pre-operational

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

    International Nuclear Information System (INIS)

    This study had as purpose the assess the impact of a severe accident, and also analyze the dispersion of 131I 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 131I to the atmosphere. The value of the total activity in the nucleus to this radionuclide is 7.44 x 1017 Bq, that is relative on the sixth day of burning. This activity will be released through the chimney at a rate in Bq/s in the scenario of 12, 24, 48 and 72 hours of release. Applying the model in the proposed scenario, it is verified that the plume has concentrations of the order of 1020 Bq/m³ and dose of about 108 Sv whose value is beyond of the presented by Eletronuclear in your current emergency plan. (author)

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

    International Nuclear Information System (INIS)

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

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

    OpenAIRE

    Diego Santos Vieira de JESUS

    2011-01-01

    The aim of this article is to explain the positions taken by Brazil under Lula’s administration (2003-2010) on nuclear non-proliferation, disarmament and arms control. In order to strengthen its position in dispute settlement and to expand its participation in international institutions, Brazil wished to intermediate between nuclear-weapon and non-nuclear weapon States. The country also tried to pressure the nuclear weapon States to fulfill their disarmament obligations and to reduce asymmetr...

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

    Energy Technology Data Exchange (ETDEWEB)

    Oliveira, Mauro Vitor de

    1999-06-15

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

  8. 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)

    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)

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

    Directory of Open Access Journals (Sweden)

    Diego Santos Vieira de JESUS

    2011-11-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2000-07-01

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

  11. Reactor inventory monitoring system for Angra-1 reactor

    International Nuclear Information System (INIS)

    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)

  12. 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)

  13. 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)

    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)

  14. 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)

    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)

  15. GIS as a Decision Support Tool in the Area of Influence of the Nuclear Complex Angra dos Reis, Brazil

    OpenAIRE

    Corbiniano Silva; Luiz Landau; Paulo Fernando Lavalle Heilbron Filho; Luiz Claudio Gomes Pimentel

    2013-01-01

    The outlook concerning the occurrence of industrial accidents has led to the implementation of response systems based on geoprocessing tools, which are widely adopted in emergency for such ventures, since they have helped and served as a support for decision making, as well as for the preparation of guidelines aimed at managing emergencies. Nuclear power plants, because they constitute types of industrial activities that present dangerous conditions and attention regarding security are chara...

  16. The relevance of PSA during shutdown conditions for the Angra-1 NPP

    International Nuclear Information System (INIS)

    In view of the issuance of the Authorization for Permanent Operation of the Angra-1 Nuclear Power Plant, the Brazilian Regulatory Body (CNEN) is requiring a Probabilistic Safety Assessment (PSA) level 1 to be performed by the Utility (FURNAS), which should consider shutdown conditions within its scope. Angra-1 PSA is part of a Safety Improvement Programme under implementation. An analysis of Angra-1 power history, covering the last eight years of operation, has shown that 56.7% of this period corresponds to shutdown operational modes. Regarding the same period, an Analysis of Angra-1 operational experience was performed to select potential initiating events during shutdown conditions. Within the Safety Improvement Programme, a complete review of Angra-1 Technical Specifications should be carried out making use of the PSA results. The inclusion of Limiting Conditions for Operation during shutdown modes is expected to be recommended. The objective of this article is to point out, based on an analysis of Angra-1 operational experience and power history, covering the last three cycles, the relevance of requiring shutdown conditions to be included in the Angra-1 PSA scope. (author). 15 refs

  17. CNEN activities and brazilian nuclear power policy

    International Nuclear Information System (INIS)

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

  18. Design and tests of a data acquisition system for the Angra anti-neutrinos detector

    International Nuclear Information System (INIS)

    Full text: We describe the design of a Data Acquisition System (DAQ) for the Angra antineutrino project, aimed at developing an antineutrino detector to monitor nuclear reactors through the detection of antineutrino counting rates and spectral measurements. The experiment, presently under construction, will take place at the Brazilian nuclear power plant Angra II and will detect antineutrinos generated in the fusion process of the nuclear reactor fuel. The DAQ system is designed to be able to digitize and to store all the analog signals coming from the photomultiplier tubes (PMT), after going through the front-end electronics. It is composed of VME standard electronic modules. We focus here on the design of a new VME data acquisition card (NDAQ), which will be part of the Angra DAQ. This card is composed of eight analog-to-digital channels (ADC), each one featuring 10 bits of vertical resolution and 125 MHz of sampling rate. In order to measure time between events, or between PMT pulses, an 82 ps resolution time-to-digital converter (TDC) is also included in the card. Other NDAQ features are: one 512K x 8 bits Static RAM for on-board data storage, reprogrammable data processing circuit (through the use of a Field Programmable Gate Array - FPGA), standalone operation (connecting to any computer via USB port) and a 512K x 32 bits output buffer, used to reduce dead time in the data flow. The card allows VME block read cycles, reaching the usual bandwidth of more than 20 MB/s. Considering the worst-case estimated event rate of 1kHz, comprising neutrino and muons events, the Angra project must be able to deal with 10 MB/s event rate, which is safely below the card bandwidth. The design uses off-the-shelf devices from worldwide semiconductor companies. A software framework for the DAQ is developed for Linux platforms by using standard scientific tools and languages like ROOT and C++. The NDAQ design is currently under tests. The design and preliminary results, using

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

    OpenAIRE

    Orlando Gibelli, Sonia M.; e Melo, P. F. Frutuoso; Bogado Leite, Sérgio Q.

    2012-01-01

    In this work, Probabilistic Safety Assessment (PSA) is used to evaluate Allowed Outage Times (AOT) and Surveillance Test Intervals (STI) extensions for three Angra 1 nuclear power plant safety systems. The interest in such an analysis lies on the fact that PSA comprises a risk-based tool for safety evaluation and has been increasingly applied to support both the regulatory and the operational decision-making processes. Regarding Angra 1, among other applications, PSA is meant to be an additio...

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

    International Nuclear Information System (INIS)

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

  1. Simulation results for light propagation in the central detector for the Angra anti-neutrinos experiment

    International Nuclear Information System (INIS)

    Full text: An antineutrino detector to be installed in the surrounding area of the Angra II nuclear reactor in Angra dos Reis is currently under development. The related experiment is intended to create a new tool capable of measuring the antineutrino flux coming from the reactor, making use of detection system placed near the reactor dome, and correlate it to the nuclear fuel fission and burn-up. The proposed detector is a box- shaped volume filled with water doped with 0.2% Gadolinium. The photons generated by the passage of particles are collected by 40 photomultiplier tubes (PMT). Aiming to evaluate the importance of reflecting inner surfaces and to provide directives concerning the best positioning of the PMTs inside the detector, a simulation of light propagation in its active volume has been done. Photons are supposed to be point-like entities traveling in straight lines. In the simulation, we investigate the overall photon counting efficiency by analyzing the number of reflections and the length travelled by the photons before being collected or absorbed, as well as the distribution of these photons in different configurations of the PMTs. Different light reflecting structures around the PMTs are also simulated, in order to find those that reduce the probability for a photon to be bounced back to the direction from which it was emitted. We show that a configuration in which the photon emission direction is preserved may be used as VETO for cosmic events. (author)

  2. Fuel for the next Brazilian nuclear power plants

    International Nuclear Information System (INIS)

    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)

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

    International Nuclear Information System (INIS)

    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)

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

    International Nuclear Information System (INIS)

    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)

  5. 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)

  6. Cost-effectiveness of risk-reduction measures from a national viewpoint: a case study of the Angra nuclear plant in Brazil.

    Science.gov (United States)

    de Oliveira, L F; Barros, E B; Fleming, P V; Rosa, L P

    1987-09-01

    In this paper a systemic or national approach to cost-effectiveness analysis of risk-reduction measures is reviewed, and its advantages and limitations are discussed. The method is applied to the problem of the cost-effectiveness of increasing the Angra 3 NPP containment wall thickness from the present 60 cm to 180 cm thick in order to prevent damage to the reactor core in case of a direct commercial aircraft crash on it. It is concluded that this measure is not cost-effective if the referred approach is considered. PMID:3120260

  7. 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.

  8. 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)

  9. Angra 2 - qualification of the bitumen waste product

    International Nuclear Information System (INIS)

    In Angra Nuclear Power Plant, Unit 2, the concentrates from the liquid waste processing system and spent resins from the reactor coolant purification system, represent the low and intermediate level radioactive waste to be incorporate into a bitumen matrix. In order to attempt the Process Control Program aimed to obtain a waste product qualified to an intermediate and a final store, a program to qualify a Brazilian supplier bitumen manufacture, simulated tests in pilot scale in Centro de Desenvolvimento da Tecnologia Nuclear CDTN and tests in industrial scale, in Angra 2 during the commissioning and licensing phase was performed. The paper presents the team experience gained since the bitumen selection up to the bitumen characterization simulated waste product. (author)

  10. Tritium (3H) as a tracer for monitoring the dispersion of conservative radionuclides discharged by the Angra dos Reis nuclear power plants in the Piraquara de Fora Bay, Brazil

    International Nuclear Information System (INIS)

    Presently, two nuclear power plants operate in Brazil. Both are located at Itaorna beach, Angra dos Reis, approximately 133 km from Rio de Janeiro city. The reactor cooling circuits require the input of seawater, which is later discharged through a pipeline into the adjacent Piraquara de Fora Cove. The radioactive effluents undergo ion-exchange treatment prior to their release in batches, causing the enrichment of 3H relative to other radionuclides in the discharged waters. Under steady state conditions, the 3H gradient in the Piraquara de Fora waters can be used to determine the dependence of the dilution factor on the distance from the discharge point. The present work describes experiments carried out at the reactor site during batch release episodes, including time series sampling at the discharge point and surface seawater sampling every 250 m to a distance of 1250 m, after a double distillation, the 3H concentration was measured by liquid scintillation counting applying a Quantulus liquid scintillation spectrometer. The obtained results showed a linear relationship between the 3H concentration and distance from the discharge point. At 1250 m from the discharge point a dilution index of 1:15 was measured which fits the expected value based on modeling. - Highlights: • The present work describes experiments carried out at the Angra dos Reis reactor site during batch release episodes. • Time series sampling of surface seawater were performed every 250 m to a distance of 1250 m. • It was observed a linear relationship between the 3H concentration and distance from the discharge point

  11. Anticipated simulation of Angra-1 start-up physical tests

    International Nuclear Information System (INIS)

    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.)

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

    International Nuclear Information System (INIS)

    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)

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

    International Nuclear Information System (INIS)

    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.)

  14. ANGRA-1 probabilistic safety study

    International Nuclear Information System (INIS)

    For the establishment of interim safety goals a methodology for calculating consequences and risks associated with the Angra-1 operation was developed. The most important contributors to the core melt frequency are two occurrences. The first is loss of main feedwater whose contributions correspond to 66.4% of the total core melt frequency calculated for two years of data collection. The second major contributor is a loss of offsite power case which contributes 33.2% of the total. The development of emergency procedures for addressing severe accidents consist of proposals to help in delaying and minimizing the release of radioactive products to the environment. The Angra-1 PSS calculated the less reliable lines as being the hot legs suction lines. The interface LOCAs contribution to the consequences can be reduced by the improvement of the reliability of the hot legs suction lines through the installation of extra isolation valves. Refs, figs and tabs

  15. 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}.

  16. Angra 1-Conditioning of radioactive waste and related problems

    International Nuclear Information System (INIS)

    The problems presented during the the commissioning of the solid waste processing system of Angra 1, are discussed. Based on the obtained results, some modifications have been introduced in order to get a better final product quality. Such modifications are described and the results compared with those originally obtained. The items related to the preliminary acceptance criteria for radioactive wastes, established by the Brazilian National Nuclear Energy Commission, are discussed, taking into account the final disposal and transportation problems. Considering the final product quality generated in Angra 1, the utility (FURNAS - Centrais Eletricas S.A.) has taken the necessary measures for acquiring a new waste immobilization unit, in order to be in accordance with the acceptance criteria. The paper still presents the method for interim storage on site, the handling procedures for the encapsulated radwastes, as well as , data about the radioactive wastes volume generated, according to their characteristics. (Author)

  17. Critérios de estabilidade atmosférica para a região da Central Nuclear Almirante Álvaro Alberto, Angra dos Reis - RJ Criteria of atmospheric stability for the region around the nuclear power plant Almirante Álvaro Alberto, Angra dos Reis - RJ

    Directory of Open Access Journals (Sweden)

    José Francisco De Oliveira Júnior

    2010-06-01

    Full Text Available Realizaram-se avaliações climatológicas, sazonais e diárias, da estabilidade atmosférica na região da Central Nuclear Almirante Álvaro Alberto (CNAAA, Angra dos Reis - RJ. A climatológica foi baseada no critério de Pasquill-Gifford (P-G para um período de 26 anos (1980-2006 e a sazonal-diária pelos números de Richardson Global (RiB e de Froude (Fr - estudo de caso (2002-05. O Fr foi usado na caracterização do escoamento da região. O critério de P-G mostrou que as classes predominantes foram D, E e F (no período noturno e diurno. Avaliaram-se as classes predominantes com a direção e velocidade do vento, os setores mais freqüentes foram S, SSW, SSE no período diurno e N, NNE, NNW e E no noturno. Quanto à velocidade verificou-se que a classe D foi mais veloz, e as classes E e F menos velozes, em qualquer período. As maiores velocidades foram coincidentes com a brisa marítima. Baseado no RiB, a condição estaticamente estável prevaleceu em comparação às demais, sendo de 79%, seguida da instável (17% e neutra (4%. O Fr indicou que o escoamento na CNAAA foi caracterizado por regime de vento fraco, com forte estabilidade e ar estagnado. A maior parte das ocorrências (63% foi para Fr inferior a 0,1, seguida de poucas ocorrências nas categorias Fr igual a 1,0 (8% e superior a 1,7 (12%. Os critérios utilizados na caracterização da estabilidade na região e na análise do regime de escoamento indicaram a baixa capacidade da atmosfera para a dispersão de poluentes, devido à predominância da condição estável e do regime de bloqueio.The atmospheric stability over the nuclear power plant Almirante Álvaro Alberto (CNAAA, Angra dos Reis - RJ, Brazil, was analyzed at climatological, seasonal, and daily scales. The climatologic analysis was based on the Pasquill-Gifford (P-G for a long-term series of 26 years (1980 - 2006, while the seasonal/daily was performed using the Global Richardson number, RiB, and the Froude number

  18. Tritium ((3)H) as a tracer for monitoring the dispersion of conservative radionuclides discharged by the Angra dos Reis nuclear power plants in the Piraquara de Fora Bay, Brazil.

    Science.gov (United States)

    de Carvalho Gomes, Franciane; Godoy, José Marcus; de Carvalho, Zenildo Lara; de Souza, Elder Magalhães; Rodrigues Silva, José Ivan; Tadeu Lopes, Ricardo

    2014-10-01

    Presently, two nuclear power plants operate in Brazil. Both are located at Itaorna beach, Angra dos Reis, approximately 133 km from Rio de Janeiro city. The reactor cooling circuits require the input of seawater, which is later discharged through a pipeline into the adjacent Piraquara de Fora Cove. The radioactive effluents undergo ion-exchange treatment prior to their release in batches, causing the enrichment of (3)H relative to other radionuclides in the discharged waters. Under steady state conditions, the (3)H gradient in the Piraquara de Fora waters can be used to determine the dependence of the dilution factor on the distance from the discharge point. The present work describes experiments carried out at the reactor site during batch release episodes, including time series sampling at the discharge point and surface seawater sampling every 250 m to a distance of 1250 m, after a double distillation, the (3)H concentration was measured by liquid scintillation counting applying a Quantulus liquid scintillation spectrometer. The obtained results showed a linear relationship between the (3)H concentration and distance from the discharge point. At 1250 m from the discharge point a dilution index of 1:15 was measured which fits the expected value based on modeling. PMID:24959753

  19. 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)

    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)

  20. Variações na estrutura da comunidade zooplanctônica próxima a usina I da Central Nuclear Almirante Álvaro Alberto (C.N.A.A.A.) - (Angra Dos Reis-R.J.-Brasil) - Ciclo 1980/81 E 1991/93

    OpenAIRE

    Cristina de Oliveira Dias; Sérgio L.C Bonecker; Catarina R. Nogueira

    1999-01-01

    During the years of 1980/80 was performed a ecological study in Ribeira Bay (Angra dos Reis-R.J.-Brazil) in order to provide informations about of the planktonic community in pre-operational conditions, in the region of the Admiral Álvaro Aberto Nuclear Power Plant (C.N.A.A.A.). After 10 years of activities of the Nuclear Power Plant the zooplankton material was obtained in vertical hauls with a net of 150 μm at two fixed points (Piraquara de Fora Cove and Itaorna Beach) in order to stud...

  1. 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)

    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). 137Cs-60Co - and 125I 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 101 for Cs, to 103 for I and 103-104 for Co. Higher B.F. for Co and I were found for P. vickersiae (up to 1,4 X 104) an A. spicifera (up to 7 X 103) 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.)

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

    Science.gov (United States)

    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.

    2016-09-01

    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.

  3. Nuclear installations

    International Nuclear Information System (INIS)

    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

  4. Nuclear structure. Volume II. Nuclear deformations

    International Nuclear Information System (INIS)

    Volume II, together with Volume I, contains a systematic treatment of the basis that has been gradually established during the last decades for understanding the vast body of data on nuclear properties and reactions. The presentation involves partly a development of the theoretical concepts and mathematical tools and partly a critical analysis of experimental results in terms of these concepts. While the first volume is concerned with single-particle motion and the formulation of symmetries, the second volume deals with collective rotational and vibrational motion as well as with the coupling of single-particle motion to the collective degrees of freedom. The discussion exploits several different levels of presentation, and this has motivated the division of the material into text, illustrative examples, and appendices. The text represents an attempt at a systematic development of the subject, in which each section is based on the concepts explained in previous sections. The comparison of theoretical concepts with the experimental evidence is contained in the illustrative examples; these examples are worked out in considerable detail and involve the full arsenal of available theoretical tools. The appendices are devoted to the development of general tools of quantal theory and to the analysis of idealized models that provide useful insight into various aspects of nuclear structure. This division of material contributes to making the book self-contained and at the same time provides the opportunity to elucidate the problems from several different points of view without destroying the unity of the concept. The presentation reflects the authors' view of nuclear physics as part of the broad development of concepts describing quantal many-body systems ranging from atoms and condensed matter to the structure of elementary particles

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

    International Nuclear Information System (INIS)

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

  6. Input data for simulating Angra I using the TRAC/PF1 code

    International Nuclear Information System (INIS)

    This report described the modeling, the input data preparation and the steady state operational conditions results for Angra 1 Nuclear Power Plant obtained with TRAC/PFL Code, aiming the simulation of accidents and operational transients further on. Suggestions are presented to minimize the difficulties met in this study. (author)

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

    International Nuclear Information System (INIS)

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2001-07-01

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

  9. Preoperational environmental monitoring of the Angra reactor site

    International Nuclear Information System (INIS)

    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)

  10. Angra 1 - conditioning of radioactive wastes and related problems

    International Nuclear Information System (INIS)

    This paper deals with the problems presented during the comminnioning of the solid waste processing system of Angra 1. Based on the obtained results, some modifications have been introduced in order to get a better final product quality. Such modifications are described and the results compared with those originally obtained. The items related to the preliminary acceptance criteria for radioactive wastes, established by the Brazilian National Nuclear Energy Commission, are discussed, taking into account the final disposal and transportation problems. Considering the final product quality generated in Angra 1, the utility (FURNAS - Centrais Eletricas S.A.) has taken the necessary measures for acquiring a new waste immobilization unit, in order to be in accordance with the mentioned acceptance criteria. The paper still presents the method for interim storage on site, the handling procedures for the encapsulated radwastes, as well as, data about the radioactive wastes volume generated, according to their characteristics. As results of the adopted measures, the implementation of wich has being closely followed by the Competent Authority, reasonable confidence is provided that the system should be able to generated a product with satisfactory properties. (Author)

  11. 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)

    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)

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

    International Nuclear Information System (INIS)

    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)

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

    International Nuclear Information System (INIS)

    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)

  14. The neutrino oscillation experiment in the reactor of Angra dos Reis

    International Nuclear Information System (INIS)

    The ANGRA project plans and status is presented, a new neutrino oscillation experiment in reactors, proposed to be assembled in Angra dos Reis nuclear complex. This experiment is intended to measure the angle θ13, the last of the three mixing angles in the neutrino sector even without a positive measure. This project proposes a multi-experiment with high sensitivity, able to achieve a sensitivity to detect anti-neutrinos disappearance of sin2 2θ13 = 0.006 in three years of operation, combining a high-brightness, low noise in cosmic rays and a careful control of systematic errors. It is planned to also explore the possibility of using the detection of neutrinos for the purpose of safeguards and non-proliferation of nuclear weapons.(author)

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

    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.)

  17. Analysis of Angra-1 fuel rod during the large break loss-of-coolant accident

    International Nuclear Information System (INIS)

    The main objective of this work is to study the fuel element behavior of the Angra 1 Nuclear Reactor, during a large loss of coolant accident caused by as rupture of the cold leg. Only the blowdown phase was considered. For this study the steps discribed below were done: - analysis of the blowdown phase was performed with the computational code RELAP4/MOD5 (option EM); analysis of the hot channel during the blowdown was made using the computational code RELAP/MOD5 (option EM); analysis of the fuel element performance during the accident with the computational code FRAP-T6. The results obtained in the steps above were compared with data presented in the Angra 1 Final Safety Analysis Report. (author)

  18. Nuclear medicine and thyroid disease - part II

    International Nuclear Information System (INIS)

    Part 1 of this article discussed the anatomy, physiology and basic pathology of the thyroid gland. Techniques of thyroid scanning and a few clinical examples are shown part II Copyright (2005) The Australian and New Zealand Society Of Nuclear Medicine Inc

  19. Quality assurance requirements for dedication process in Angra 1

    International Nuclear Information System (INIS)

    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)

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

    Directory of Open Access Journals (Sweden)

    Sonia M. Orlando Gibelli

    2012-01-01

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

  1. Probabilistic risk analysis of Angra-1 reactor

    International Nuclear Information System (INIS)

    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.)

  2. Moisture gauge determination of the steam of Angra 1 reactor using Na-24 as radioactive tracer

    International Nuclear Information System (INIS)

    Hereby it is presented the chronology and the results of the moisture carryover test, performed as part of the commissioning of the Angra Nuclear Power Station - Unit 1. It was used the Na-24 as radioactive tracer. The source of Na 2 CO 3 was produced in the Reactor IPR-R1 of the Nuclear Technology Development Center in Belo Horizonte-MG. The results obtained were 0.172% with steam probe and 0.222% with samples taken from the Plant process sampling systems. Both results were smaller than 0.25%, assumed in the scope of supply of the plant equipment. (author). 2 refs., 5 tabs

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

    International Nuclear Information System (INIS)

    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.)

  4. 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)

    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)

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

    International Nuclear Information System (INIS)

    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.)

  6. European Nuclear Decommissioning Training Facility II

    International Nuclear Information System (INIS)

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

  7. Country nuclear fuel cycle profile: Brazil

    International Nuclear Information System (INIS)

    Brazil has two operating nuclear power plants: Angra 1, a 657 MW(e) Westinghouse PWR and Angra 2, a 1350 MW(e) Siemens KWU PWR. Both units are owned and operated by ELETRONUCLEAR. Angra 1 started operation in March 1982 (commercial operation since December 1984) and Angra 2 started commercial operation in February 2001. In 2002 the two plants produced about 4% of the country's electricity supply, of which more than 88% comes from hydroelectric plants. Brazil has not yet decided about its nuclear fuel cycle policy. The Pocos de Caldas CIPC mining and ore processing plant was closed in 1997. The Lagoa Real area Caetite unit started operation in 2000 with an initial capacity of 340 t U/a. As part of the Brazilian Navy's nuclear propulsion programme, a UF6 pilot plant with a nominal production capacity of 40 t U/a is under construction at the Navy Research Institute (CTMSP) at Ipero, 100 km from Sao Paulo. There are no plans to install a commercial plant in the near future. As part of its nuclear propulsion programme the Brazilian Navy has installed a demonstration enrichment centrifuge pilot plant at Ipero. Recently the Brazilian Government decided to start the industrial implementation of the ultracentrifuge process developed by the CTMSP in the Resende industrial plant in the State of Rio de Janeiro. The complete set of units is intended to be operating in 8 years to meet the needs of Angra 1 and partially those of Angra 2 and 3 (∼300 t SWU/a). A future increase in this capacity will depend on technical evaluation and resource availability. The two unit fuel fabrication plant of INB is located at Resende, Rio de Janeiro State, and has a production capacity of 280 t U/a. The fuel fabrication plant has been refurbished and produces the fuel rods and fuel elements for Brazilian nuclear reactors at its unit I. Unit II, which is responsible for pellet fabrication, has been operating since June 1999 with a capacity of 120 tonnes of UO2 pellets/a. The UO2 powder

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

    International Nuclear Information System (INIS)

    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.)

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

    International Nuclear Information System (INIS)

    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.)

  10. Startup control of the TOPAZ-II space nuclear reactor

    OpenAIRE

    Astrin, Cal D.

    1996-01-01

    Approved for public release; distribution isunlimited. The Russian designed and manufactured TOPAZ-II Thermionic Nuclear Space Reactor has been supplied to the Ballistic Missile Defense Organization for study as part of the TOPAZ International Program. A Preliminary Nuclear Safety Assessment investigated the readiness to use the TOPAZ-II in support of a Nuclear Electric Propulsion Space Test Mission (NEPSTP). Among the anticipated system modifications required for launching the TOPAZ-II sy...

  11. Annex II: The global nuclear power picture

    International Nuclear Information System (INIS)

    Worldwide there were 439 nuclear power plants (NPPs) operating as of 31 December 2003. Nuclear power supplied 16% of global electricity generation in 2002, down slightly from 16.2% in 2001.12 Table II.1 summarizes world nuclear experience as of 31 December 2003. The global energy availability factor for NPPs rose to approximately 84% in 2003, continuing its steady climb from 74.2% in 1991. Two new NPPs were connected to the grid in 2003. This follows six new connections in 2002 and three in 2001. There were six retirements in 2003, the four 50 MW(e) units at Calder Hall in the UK, the 640 MW(e) unit at Stade in Germany and the Fugen ATR 148 MW(e) unit in Japan. There had been four retirements in 2002 (Kozloduy- 1 and -2 in Bulgaria and Bradwell units A and B in the UK) and no retirements in 2001. In 2003, construction started on just one new NPP, a 202 MW(e) PHWR in India. Current expansion, as well as near-term and long-term growth prospects, are centred in Asia. Of 31 reactors under construction worldwide at the end of 2003, 18 are located either in China, the Republic of Korea, the Democratic People's Republic of Korea, Japan or India. Twenty-one of the last 30 reactors to have been connected to the grid are in the Far East and South Asia. In Western Europe, with the retirement of four units in the UK and one in Germany, there are now 141 operating reactors. The last new connection to the grid was France's Civaux-2 in 1999. With upratings and licence extensions, overall capacity is likely to remain near existing levels, despite decisions to phase out nuclear power in Belgium (which passed its phase-out law in January 2003), Germany and Sweden

  12. Experiments with radioactive nuclear beams II

    International Nuclear Information System (INIS)

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

  13. History of nuclear power in Brazil

    Energy Technology Data Exchange (ETDEWEB)

    Rosa, L.P.

    2006-07-15

    The 1973 energy crisis prompted the United States to suspend supplies of enriched uranium to the reactor being built in Brazil, Angra I. In 1975, the Brazil-Germany Nuclear Agreement was announced. The Programme was a failure. Today the Angra II nuclear reactor has been completed, the only reactor completed under the agreement with Germany. Brazil's last military President implemented the Parallel Nuclear Programme, which included uranium enrichment with the justification of developing the technology that had not been transferred through the Nuclear Agreement with Germany. In 1986, the existence of a deep shaft drilled by the Air Force was revealed. A Technical Report concluded that it had all the characteristics and dimensions required to test a nuclear bomb. Some years later, the Civilian Government acknowledged the existence of an underground nuclear explosion facility and symbolically sealed this shaft. The situation in Brazil has improved recently. Brazil ratified the Treaty of Tlatelolco on the denuclearisation of Latin America and established ABACC, an agency handling mutual inspections of nuclear facilities in Brazil and Argentina. Brazil also signed the Nuclear Weapons Non-Proliferation Treaty. The uranium enrichment activities are being transferred to a civilian industry. More importantly, I do not believe that the uranium enrichment project is intended to endow Brazil with the capacity to produce nuclear weapons. (author)

  14. Analysis of the rod drop accident for Angra-1

    International Nuclear Information System (INIS)

    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, FNAH, will be at least 6% higher than the allowable FNAH-values. Therefore, the DNBR design margin will be preserved at the event of rod drop. (author)

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

    International Nuclear Information System (INIS)

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

  16. Angra-1 probabilistic safety study-phase B

    International Nuclear Information System (INIS)

    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)

  17. Photomultiplier tubes characterization at the Angra Neutrinos Project

    International Nuclear Information System (INIS)

    Full text: A large number of Photomultiplier Tubes (PMTs) are going to be used in the Angra Neutrinos Project, which will be implemented to detect anti-neutrinos produced in a nuclear reactor by observing Cherenkov light in a water tank. At the current stage of the project, 40 PMTs are expected to be used. These should be characterized and have their performance parameters periodically evaluated. The electronic system for data acquisition used in the measurements of the PMT gain was developed from a Data Processing Module (MPD), composed by analogue to digital converters that are controlled by a high speed Field Programmable Gate Array (FPGA) and transmits data to a computer using an interface designed to communicate via the Universal Serial Bus (USB). A preamplifier circuit with waveform shaping capability is necessary to capture the voltage pulse generated by particle detection. Both the PMT characterization and the neutrino detection require the observation of single photoelectron, as a signal with amplitude of few millivolt and duration shorter than 50 nanosecond, with electrical charge around 1.6 picocoulomb. In this work we present the whole data acquisition chain, with particular emphasis on the design of the preamplifier circuit and on the measurement of the single photoelectron spectrum from which the PMT gain is estimated. Results for 4 PMTs are presented and discussed, along with a description of the software - developed under the Linux operational system, using C++ language on the ROOT/CERN [http://root.cern.ch] platform - used to implement the data acquisition and analysis. (author)

  18. Determination of the stability classes in Angra dos Reis

    International Nuclear Information System (INIS)

    The applicability of the methods for the calculation of atmospheric dispersion used in Angra dos Reis, (site of Angra I - reactor) is discussed. A review is made of the main meteorological parameters indicating turbulence, as well as of the methods presently em ployed for doing dispersion estimates. The turbulence indicator measured in Angra dos Reis and their utilization in the categorization of the stability conditions are discussed. The methods of the rate of vertical temperature variation and the fluctuation of the wind direction to calculate the concentration in the air, are used. The correlations existing between these two methods and their temporal and spacial variation are analysed. The analysis of one-year data allows the conclusion, that, due to the low wind velocity; in Angra dos Reis the fluctuation method is a good indicator of horizontal dispersion, but it does not allow the Knowledge of vertical stability which is better determined by the vertical gradient of temperature. Due to the local condition between the mountains and the sea, only experiments on atmospheric diffusion may indicate the better method for the calculation of local dispersion. (E.G.)

  19. Brazil: Angra 2 NPP. Project control. Annex 2

    International Nuclear Information System (INIS)

    This annex deals with project control. Construction of Angra 2 has had strong decrease of investment from 1984 to 1994. Storage programme has been implemented and inspections are being planned. Personnel has been maintained to advance engineering work and to maintain site structures. Construction has been resumed with full co-operation of the foreign supplier plant is 94% complete (October 1998). (author)

  20. Experiments with the initial erections of the Angra-2 reactor

    International Nuclear Information System (INIS)

    The main erection services for Angra 2 will be contracted 11/95; the actual services will start in 02/96. FURNAS and NUCLEN decided to anticipate some services related to the main erection; the present paper presents the situation of these initial erection services, as well as the experience gained so far. (author)

  1. Brazil: Angra 2 NPP. Manpower and documentation. Annex 2B

    International Nuclear Information System (INIS)

    This annex deals with manpower and documentation. Several initiatives were implemented during the suspension period to preserve manpower and documentation at Angra 2 NPP. They have paid off and construction of the NPP was resumed with relatively little unexpected difficulties. This annex outlines the essentials of these initiatives. (author)

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

    International Nuclear Information System (INIS)

    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.)

  3. Qinshan II nuclear safety supervision and management system and method

    International Nuclear Information System (INIS)

    The peaceful use of nuclear energy is along with the potential risk of radioactive release, so its safety is particularly important. Nuclear safety supervision and management is a dynamic process. It has out quite stable mandatory regulations, but also has technological advances and continuous improvement with time. The article discusses the organization, procedures and scope of the Qinshan II nuclear safety supervision and management, and simultaneity comments to the methods in this respect. (author)

  4. Nuclear emergency buildings of Asco and Vandellos II nuclear power plants; Centros alternativos de emergencias de las centrales nucleares de Asco y Vandellos II

    Energy Technology Data Exchange (ETDEWEB)

    Massuet, J.; Sabater, J.; Mirallas Esteban, S.

    2016-08-01

    The Nuclear Emergency Buildings sited at Asco and Vandellos II Nuclear Power Plants (NPP) are designed to safety manage emergencies in extreme situations, beyond the design basis of the Nuclear Power Plants. Designed in accordance with the requirements of the Spanish Nuclear Regulator (Consejo de Seguridad Nuclear-CSN) these buildings are ready to operate over a period of 72 hours without external assistance and ensure habitability for crews of 120 and 70 people respectively. This article describes the architectural conception, features and major systems of the Nuclear Emergency Buildings sited at Asco and Vandellos II. (Author)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2001-12-15

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

  6. Special safety requirements applied to Brazilian nuclear power plant

    International Nuclear Information System (INIS)

    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.)

  7. Manhattan project II: Abolishing nuclear weapons

    International Nuclear Information System (INIS)

    Most people seem to think that the era of nuclear danger is over, that it ended along with the Cold War. Whatever residual problems remain in terms of proliferation or possible terrorism, they believe, are being dealt urgently and adequately by their national leaders. Unfortunately, they are wrong on both counts. Although the risk of nuclear war between the NATO and former Warsaw Pact powers has virtually vanished, the chance that some nuclear weapons will kill many people, may be higher than before. The elimination of nuclear weapons, meaning rejection of terrorism, must be accomplished by multilateral collaboration. To recover fundamental moral bearings, as well as to preserve life and civilization, the USA, Russia, Great Britain, France, China, India and Pakistan must cease to be terrorist states

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

    International Nuclear Information System (INIS)

    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)

  9. European Trilateral Track II Nuclear Dialogues

    OpenAIRE

    Center on Contemporary Conflict

    2013-01-01

    FY 2013-2014. Project Lead: Clark Murdock & Franklin Miller NATO nuclear policy faces a variety of external challenges including the increased complexity of deterrence relationships, WMD proliferation to new actors capable of disrupting stability, and the increasing strategic significance of Asia. The three nuclear members of NATO, the United States, United Kingdom, and France (P-3), will drive the burden-sharing strategy and consensus necessary to weather a NATO drawdown while maintaining...

  10. Probabilistic analysis of the loss of external eletric power in Angra-1 considering uncertainty propagation

    International Nuclear Information System (INIS)

    To fullfill the needs of the probabilistic safety assessment for the Angra 1 nuclear power plant, a computer code for performing event tree analyses ETAP2, has developed in PASCAL language for the Burroughs B-6700 computer. The code employs the impact vector method. A dependency matrix is defined which allows for proper consideration of all relevant intersystem dependencies. The analyses are carried out to the subsystem (train or channel) level. The uncertainty analysis is performance on the dominant accident sequences lumped in two different groups: one for assessing the core-degradation-class frequencies and another for obtaining the core-degradation frequency concerning the initiator under analysis. For this purpose we use a discrete Monte Carlo algorithm which is faster than others available besides furnishing reliable results. The Loss-Of-Offsite power initiator analysis is presented for illustration purposes. The ETAP2 current version is implemented in the VAX 11/780 computer. (author)

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

    International Nuclear Information System (INIS)

    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)

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

    International Nuclear Information System (INIS)

    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)

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

    International Nuclear Information System (INIS)

    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)

  14. An economical analysis of stretch-out for Angra 1

    International Nuclear Information System (INIS)

    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)

  15. Brazil: Angra 2 NPP. Upgrades. Modifications and improvements. Annex 2A

    International Nuclear Information System (INIS)

    This annex deals with upgrades - modifications and improvements. With decision to resume construction of Angra 2, a study was conducted to select modifications and improvements required to bring Angra 2 to the standard of the reference plant. This annex summarizes decisions reached. (author)

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

    International Nuclear Information System (INIS)

    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.)

  17. Nuclear spectroscopy with direct relations II. Proceedings

    Energy Technology Data Exchange (ETDEWEB)

    Throw, F. E. [ed.

    1964-03-01

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

  18. Nuclear spectroscopy with direct relations II. Proceedings

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

    To follow the bioaccumulation and tissue distribution of 137Cs and 60Co 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. 137Cs concentration factors (CFs) were 3 and 5 in whole fish and muscle, respectively. The highest concentration of 137Cs was found in the muscle which accounted for 66% of the total body burden. In contrast, the highest concentration and greatest fraction (19%) of 60Co was located in the liver. Whole body and muscle CFs for 60Co, 0.2 and 0.08 respectively, were much lower than those for 137Cs. 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 137Cs 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 60Co 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 60Co was approximately 2.5 times more available for uptake by grouper than the cationic forms initially present. It is concluded that the uptake of 60Co by fish exposed to radioactive effluents would be a function of the different forms of 60Co present. 20 refs, 2 figs, 2 tabs

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

    International Nuclear Information System (INIS)

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

  1. 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)

  2. Application of CAESAR II in nuclear pipelines stress analysis

    International Nuclear Information System (INIS)

    Pipelines system is the important component of nuclear power plant. Its disposal and support decide force state and may influence the safety of the whole equipment. The stress analysis model is set up by CAESAR II and used to analyze the pipelines system of No.1 unit in Daya Bay nuclear power plant. The invalid cause of part bellows type expansion joint is found by this means. The calculation of this model is corresponded with actual measurement. The disposal and support project of pipelines system are regulated based on the calculations. It is shown that the appropriate model set up by CAESAR II can be used in pipelines stress analysis of nuclear power plant. (authors)

  3. The self assessment at ANGRA 1 NPP in Brazil

    International Nuclear Information System (INIS)

    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

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

    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)

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

    International Nuclear Information System (INIS)

    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.)

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

    International Nuclear Information System (INIS)

    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)

  8. Farewell to the nuclear energy program

    International Nuclear Information System (INIS)

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

  9. Brazilian safety standard for fire protection in nuclear power plants

    International Nuclear Information System (INIS)

    During licensing and surveillance of nuclear power plants the Comissao Nacional de Energia Nuclear of Brazil adopted IAEA Safety Series No. 50-SG-D2 as the basic regulatory document for fire protection. In the Angra I nuclear power plant, which was designed in the United States of America, the BTP 9.5-1 guidelines (revision 2, including Appendix R to 10 CFR, Part 50) were used in support, and in Angra II, which was designed in the Federal Republic of Germany, several Federal German standards were adopted. Because these guidelines, and some of the requirements therein, do not always agree with Brazilian law and site characteristics, it was decided to produce Safety Standard NE-2.03. It is based on Safety Series No. 50-SG-D2 and BTP 9.5-1, since they contain specific approaches to fire protection in nuclear power plants. Where any disagreement with Federal German and Brazilian standards occurred, a comprehensive engineering analysis was made in order to solve these problems without compromising plant safety. All the relevant aspects of the Brazilian Safety Standard are outlined. Also discussed are the modifications which had to be made to the guidelines and their requirements so that they are in accordance with Brazilian law and the site characteristics. (author). 3 refs

  10. Nuclear Electronics II. Proceedings of the Conference on Nuclear Electronics. V. II

    International Nuclear Information System (INIS)

    Nuclear instruments are used in almost every phase of atomic energy work, from assessing health hazards and prospecting for nuclear materials to plant control and nuclear physics experiments. The demands on nucleonic instrumentation are growing steadily. High-energy particle physics need such instruments for measuring extremely short times; in various research experiments most advanced electronic systems are required; and routine applications of radioisotopes call for more reliable instruments for automated counting facilities. In order to give designers and users of nuclear instrumentation an opportunity to discuss the research results and to exchange information on recent developments and new designs, the International Atomic Energy Agency, in co-operation with the Federal Nuclear Energy Commission of Yugoslavia, organized a Conference on Nuclear Electronics which was held in Belgrade from 15-20 May 1961. It was attended by more than 300 scientists from nearly 30 countries and five international organizations. Over 150 papers were read and discussed. As the field of nuclear electronics has expanded considerably, it was impossible to discuss all aspects of nuclear electronics in one series of meetings. Included in the main topics were radiation detectors, electronic circuitry in conventional and fast-pulse techniques and advanced electronic systems used in nuclear research. The Proceedings presented in these volumes contain the full records of the Conference, including discussions. The present state of technique, together with current trends and developments, are outlined. Of particular value should be the world-wide survey on progress recently made in such fields as those connected with semiconductor detectors, spark counters, luminescence chambers and fast electronic facilities for nuclear physics research. Together with the Proceedings of the Symposium on the same subject held in Paris and also published by the International Atomic Energy Agency, these volumes

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

    International Nuclear Information System (INIS)

    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

  12. 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)

    14C is a is a long-lived beta-emitting nuclide (T1/2 = 5730 years) produced naturally in the upper atmosphere as a result of reactions between neutrons and stable 14N(14N(n,p)14C). Although in a lesser extent, nuclear power plants produce 14C as well during their routine operation. Since it is converted in 14CO2 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 14C 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 14C 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 14C 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 14C can be emitted as hydrocarbons, CO or CO2, 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 CO2 and hydrocarbon fractions but in Angra II, all hydrocarbons are converted to CO2 by using a Pd/Al2O3 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 five different wind

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

    International Nuclear Information System (INIS)

    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)

  14. Parametric study of the TANDEM cycle fuel material balance between Angra-1 and Embalse

    International Nuclear Information System (INIS)

    The TANDEM cycle fuel material balance between the Angra-I PWR in Brazil and Embalse CANDU reactor in Argentina is estimated. The analysis considers the discharge burnup of Angra-I and a dilution ratio (decontaminated uranium dioxide from the PWR: natural uranium dioxide) of 1.9:1.0 for the fuel of the Embalse CANDU reactor. Parametric studies involving the MOX fuel have been carried out for different dilution ratios and different PWR discharge burnups. (author)

  15. 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

  16. Persistency of atmospheric diffusion conditions in Angra dos Reis - Brazil

    International Nuclear Information System (INIS)

    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)

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

    International Nuclear Information System (INIS)

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

  18. 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)

    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)

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

    International Nuclear Information System (INIS)

    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)

  20. 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)

  1. Station Blackout in unit 1 and analysis of the wind field in the region of Angra dos Reis

    International Nuclear Information System (INIS)

    Highlights: • Severe accident is one that exceeds the design basis (set of information that identifies the specific functions to be performed by an item from a nuclear facility or specific values chosen for controlling parameters as fundamental reference data for the project). • A Station Blackout occurs through loss of external energy and internal energy, consecutively. The external loss by event in the transmission lines. The internal loss by problems in diesel generators. • With a Station Blackout, the Plant begins to present problems at your core, due to failure in the cooling and in the residual heat removal. Without the removal of heat from the fuel rods, the temperature in the core increases abruptly and thus arises a series of events. - Abstract: Since the Fukushima accident a lot wondered on if a nuclear reactor is really safe and, specifically, if the Plants of Angra are trusted to a severe accident as occurred in Japan. The initiator event in Fukushima was a tsunami which in turn affected the external power system and then the internal power system, through failure of the diesel generators. In the case of Angra dos Reis the initiator event would be by sliding slope, the event most likely to occur, which affect the external network, common fault for all three units and later the internal network in this case, the plant most likely fault on your internal network is the unit 1, due the generators GD1 and GD2 have higher probabilities failure of departure and failure to continue to operate 2.86 × 10−2 and 2.4 × 10−3, in comparison with the generators GD3 and CD4, respectively 1.74 × 10−4 and 9.06 × 10−4. With relationship to the dispersibilidade of the pollutant in an eventual liberation for atmosphere, it is inferred by the results of the analysis of the winds of the area that the area presents low capacity dispersive

  2. Role of nuclear hexokinase II in DNA repair

    International Nuclear Information System (INIS)

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

  3. Nuclear material inventory estimation in solvent extraction contractors II

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

    It was postulated in the cooling system, a LOCA where was lost 431 m3 of coolant. The inventory was 1.87 x 1010 Bq/m3 of tritium, 2.22 x 107 Bp/m3 of cobalt and 3.48 x 108 Bq/m3 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

  5. 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)

    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

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

    International Nuclear Information System (INIS)

    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

  7. Design of nuclear power plants

    International Nuclear Information System (INIS)

    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.)

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

    International Nuclear Information System (INIS)

    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)

  9. Activities related to ''nuclear model parameter testing for nuclear data evaluation'' (Reference Input Parameter Library: Phase II) at CNDC

    International Nuclear Information System (INIS)

    The objectives of the RIPL CRP Phase II are to test thoroughly all segments of the Starter File of the Reference Input Parameter Library, focusing on optical model parameters and nuclear level density parameters. The nuclear level density calculations for 303 nuclei with the two recommended parameter sets have been performed. 88 sets of optical potential parameters are prepared for RIPL-2. A nuclear model code UNF is being prepared at CNDC for the physical testing of RIPL. (author)

  10. 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)

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

    Science.gov (United States)

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

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

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

    International Nuclear Information System (INIS)

    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.)

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

    International Nuclear Information System (INIS)

    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)

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

  16. Aseismic design of the Heysham II Nuclear Power Station

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

    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)

  18. Review of tube support plate analysis for steam generators of Millstone Unit II Nuclear Power Plant

    International Nuclear Information System (INIS)

    Magnetite growth in steam generator tube support plates was observed in the Millstone Unit II Nuclear Power Plant. If growth is allowed to continue, the tube may eventually fail resulting from plate shifting and the squeezing action of the growing magnetite. The corrective actions undertaken by the Northeast Nuclear Energy Company (NNECO) for this effect have been summarized in a report submitted to the U.S. Nuclear Regulatory Commission (NRC) entitled, Millstone Unit No. II Steam Generator Repairs and Corrective Actions, Docket No. 50-336. The analytical study part of this report is reviewed here, and conclusions and recommendations for further research are given

  19. Modelling of radionuclides dispersion in coastal waters. A study case on the dispersion of radionuclides released with the liquid effluents of Angra dos Reis NPP - Brazil

    International Nuclear Information System (INIS)

    The problem of the dispersion of radionuclides at coastal areas is discussed. The study focused on the dispersion of 3H and 137Cs released at Ribeira Bay, Rio de Janeiro, Brazil, with the liquid effluents of the Angra dos Reis nuclear power plant. It has been demonstrated that due to the site specific hydrodynamics the exportation of radionuclides to the open ocean would be a rather fast process. The study also examined the best strategy for accidental releases. It could be evaluated that in terms of the radionuclide inventory in the boxes the release at Itaorna Inlet would be a better option than the release at Piraquara de Fora Inlet. However, this option should be examined after a detailed dose assessment study. (author)

  20. 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)

    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)

  1. Reliability study of the Angra-I component coolant system considering uncertainty in the fault tree analysis by a fuzzy model

    International Nuclear Information System (INIS)

    The probabilistic safety analysis (PSA) has been used in industrial plant risk studies since 1960. In nuclear regulatory and the PSA are a non-dispensable methodology. The estimation of the system top event using fault tree/minimal cut set approach is the higher traditional PSA technique applied. However, the credible results is strongly linked to basic event precision. Recently, some researchers have developed mathematical approaches to estimate the dispersion in failure data. The fuzzy set theory is a good option to be applied in order to characterize the derivation of a basic event. This paper presented the bases of a fuzzy methodology commonly applied in fault tree studies, and, finally, it showed a realistic case study involving Angra I component coolant system. (author)

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

    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)

  4. Nuclear proliferation and civilian nuclear power: report of the Nonproliferation Alternative Systems Assessment Program. Volume II. Proliferation resistance

    Energy Technology Data Exchange (ETDEWEB)

    1979-12-01

    Volume II assesses proliferation resistance. Chapters are devoted to: assessment of civilian nuclear systems (once-through fuel-cycle systems, closed fuel cycle systems, research reactors and critical facilities); assessment of associated sensitive materials and facilities (enrichment, problems with storage of spent fuel and plutonium content, and reprocessing and refabrication facilities); and safeguards for alternative fuel cycles.

  5. Nuclear proliferation and civilian nuclear power: report of the Nonproliferation Alternative Systems Assessment Program. Volume II. Proliferation resistance

    International Nuclear Information System (INIS)

    Volume II assesses proliferation resistance. Chapters are devoted to: assessment of civilian nuclear systems (once-through fuel-cycle systems, closed fuel cycle systems, research reactors and critical facilities); assessment of associated sensitive materials and facilities (enrichment, problems with storage of spent fuel and plutonium content, and reprocessing and refabrication facilities); and safeguards for alternative fuel cycles

  6. Sm-Nd-Pu timepieces in the Angra dos Reis meteorite

    International Nuclear Information System (INIS)

    Sm-Nd systematics in pyroxene and phosphate mineral separates of Angra dos Reis have been studied. A pyroxene-phosphate internal isochron age of T2=4.55+-0.04 AE is obtained, in excellent agreement with reported Pb-Pb ages. 142Nd/144Nd ratios in pyroxene samples are systematically larger than those in phosphates by 6 parts in 105. This variation is tentatively assigned to a radiogenic contribution from extinct 146Sm. Fission xenon components in pyroxene and phosphate separates are characterized by discrete ratios of fission/spallation and evidence is presented for a third ratio in celsian. It is shown that this characteristic is due to a close association of 244Pu with the light REE. Computed ratios 244Pu/Nd are the same in pyroxene and phosphate separates, but 244Pu/238U and 244Pu/232Th ratios are not. Taking the fission xenon retention age to be 4.55 AE, an abundance ratio 244Pu/Nd=1.5x10-4 (or an atomic ratio 244Pu/150Nd=1.6x10-3) is obtained at this time and in the region of the solar system where the Angra dos Reis parent body formed. The exposure age of Angra dos Reis, as obtained by the 81Kr-83Kr method is 55.5+-1.2 m.y. Neutron capture during the 55.5-m.y. exposure to cosmic rays increased the ratio 150Sm/149Sm in Angra dos Reis by 6 parts in 104. (Auth.)

  7. Reliability analysis of the Angra-1 safety electric bus bar, considering the new Diesel generators configuration

    International Nuclear Information System (INIS)

    Aiming the electrical system reliability improvement, the Angra-1 energy electric system has been modified. The two original Diesel generators were replaced by two new ones, and the former were configured as standby generators. The purpose of this work is to quantify the electric system reliability improvement under the mentioned modifications by using Markovian analysis. It was found that the new configuration for the emergency Diesel system improves significantly the power supply to the safety buses. (author). 8 refs., 3 figs., 5 tabs

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

    International Nuclear Information System (INIS)

    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.)

  9. Transient analysis models for nuclear power plants

    International Nuclear Information System (INIS)

    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.)

  10. Safety analysis of nuclear power plants

    International Nuclear Information System (INIS)

    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.)

  11. Development of methods for measuring materials nuclear characteristics, Phases, I, II, II and IV

    International Nuclear Information System (INIS)

    This report contains the following phases of the project 'measurement of nuclear characteristics of reactor materials': nuclear performances of the neutron chopper; method for measuring total effective cross sections by transmission method on the chopper; review of methods for measuring activation cross sections; measurement of neutron spectra of the RA reactor and measurement of total effective cross section of gold by using the chopper

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

    Science.gov (United States)

    Shore, Ferdinand J.

    1974-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1977-12-14

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

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

    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)

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

    International Nuclear Information System (INIS)

    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.)

  17. JALTES-II: a systems analysis model for long-term strategy on nuclear power development

    International Nuclear Information System (INIS)

    JALTES-II has been developed as a systems analysis model for long-term strategy on nuclear power development. The model optimizes future reactor systems by using a linear-programming technique, and also calculates in detail the demand for nuclear fuel cycle activities. JALTES-II has been utilized so far in the analyses on the role of the Advanced Thermal Reactor, the effective utilization of plutonium, and so on. This report describes the outline of the model, mathematical formulations, computer programs, and input and output data items. A set of examples of input and output data are attached in the appendix. (author)

  18. Monte Carlo simulation of nuclear energy study (II). Annual report on Nuclear Code Evaluation Committee

    International Nuclear Information System (INIS)

    In the report, research results discussed in 1999 fiscal year at Nuclear Code Evaluation Committee of Nuclear Code Research Committee were summarized. Present status of Monte Carlo simulation on nuclear energy study was described. Especially, besides of criticality, shielding and core analyses, present status of applications to risk and radiation damage analyses, high energy transport and nuclear theory calculations of Monte Carlo Method was described. The 18 papers are indexed individually. (J.P.N.)

  19. 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

  20. Country Report Summary: Brazil [Project Management in Nuclear Power Plant Construction: Guidelines and Experience

    International Nuclear Information System (INIS)

    In 1975, Brazil and Germany signed a Cooperation Agreement to develop in Brazil a complete nuclear fuel cycle. It included the development of a heavy equipment industry, a nuclear fuel factory and a protocol for purchasing eight NPPs of the PWR type. The two first 1300 MW units were ordered in 1975. In 1976, at the beginning of the Project, a twelve month time gap between the completions of the two plants was planned. Later these time gaps were changed to 18 months and, then, to 24 months, until the investments were substantially reduced from 1984 to 1994. Engineers, technical and administrative personnel were kept employed to continue the engineering, to set up a component preservation and inspection programme, and to proceed at a very slow speed construction of the site structures. In 1976, during the construction of Angra 2 concrete analysis of the containment foundations carried out in cooperation with the Licensing Authority led to a recalculation of this structure. This caused a severe schedule delay and the foundations were completed only in 1982. From 1984 onwards the slow economic conditions in Brazil had a serious effect on the implementation of the nuclear power program and the construction of Angra 2 and Angra 3. This situation led the utility to proceed with the construction of Angra 2 and the rock excavation of Angra 3, according to the annual budget authorized by the Brazilian government, until 1986 when the whole project was stopped. In March, 1996 the mechanical, electric and I and C erections were re-started and all the systems, whose erection was a pre-condition for core loading, were installed and ready for operation in March, 2000. Angra 2 was declared operational in December 2000. Angra 3 received a Construction License from the Brazilian Authorities in June 2010 and the first concrete of the Reactor building was poured June 1st, 2010. According to the Time Schedule, Commercial Operation should start in December 2015.

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

    International Nuclear Information System (INIS)

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

  2. Beam-to-beam joints with bolted end-plate connections concerning steel platforms Angra 2 NPP

    International Nuclear Information System (INIS)

    The paper presents adopted end-plates connections as structural solution for joints in steel platforms subjected to seismic loads as well as exceptional loads due to postulated piping ruptures. The beam-to-beam bolted end-plate connections designed for Angra 2 NPP were based in allowable stresses design. Also, usual assumptions and methods in the engineering practice, concerning steel platforms for german power plants in the 80's, were considered. The adopted method is compared with the proceedings according to Eurocode 3 - Part 1-8 to verify safety margins between old and new concept. The target of this comparison is to be sure that the adopted design is enough conservative to be adopted for the next NPP - Angra 3 (similar to Angra 2), whose construction will start in 2009. (author)

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

    International Nuclear Information System (INIS)

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

  4. The startup tests for TRIGA Mark II at the Institute for Nuclear Energy

    International Nuclear Information System (INIS)

    This paper briefly describes the start-up tests for TRIGA Mark-II at the Institute for Nuclear Energy and some of the problems during the construction. This Report consists of three parts: 1. Shield Construction and Installation of ITU-TRR Components. 2. Start-up Experiments. 3. Experience Gained in Operation and Maintenance

  5. 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)

    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)

  6. On the future of nuclear power in Brazil

    International Nuclear Information System (INIS)

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

  7. On the future of nuclear power in Brazil

    Energy Technology Data Exchange (ETDEWEB)

    Lameiras, Fernando Soares [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN), Belo Horizonte, MG (Brazil)]. E-mail: fsl@cdtn.br

    2002-07-01

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

  8. Titanium-II: an evaluated nuclear data file

    International Nuclear Information System (INIS)

    A comprehensive evaluated nuclear data file for elemental titanium is outlined including definition of the data base, the evaluation procedures and judgments, and the final evaluated results. The file describes all significant neutron-induced reactions with elemental titanium and the associated photon-production processes to incident neutron energies of 20.0 MeV. In addition, isotopic-reaction files, consistent with the elemental file, are separately defined for those processes which are important to applied considerations of material-damage and neutron-dosimetry. The file is formulated in the ENDF format. This report formally documents the evaluation and, together with the numerical file, is submitted for consideration as a part of the ENDF/B-V evaluated file system. 20 figures, 9 tables

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

    International Nuclear Information System (INIS)

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

  10. Maintenance rates optimization of nuclear and conventional thermal power plants

    International Nuclear Information System (INIS)

    This work presents results of simulations carried out aiming to verify the best periods for the programmed maintenances of the nuclear power plants Angra 1 and Angra 2. It was taken in consideration other thermal and hydro power plants relevant for the operation of the region's electrical power system. The modeling of this geoelectrical area was made for the program MAINT, developed by EDP-Electricity of Portugal, as a function of the load curves, the monthly consumption rates and the hydrological conditions of the hydro power plants. (author)

  11. Broadening of axial neutron flux difference operating band in Angra I

    International Nuclear Information System (INIS)

    ANGRA I Technical Specifications requires the axial flux difference to remain within ± 5 percent band, relative to a reference value, for any power level. The reference value is the axial flux difference at a 100% power, all rods (almost) out and equilibrium Xenon distribution. This paper presents the results of several Simulations, performed by FURNAS staff aiming the validation of calculation results against the reload designer's ones. It was also proved that the Axial Flux Difference Operating band can be broadened to ''Ref. +- 6.9% ) without exce eding the limit imposed by the ''envelope-curve''. (author)

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

    International Nuclear Information System (INIS)

    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

  13. Angra do Heroísmo no quadro das "cidades de paisagem” Portuguesas medievo-renascentistas

    OpenAIRE

    Fernandes, José Manuel

    2007-01-01

    Revista do IHA, N.4 (2007), pp.212-231 Procura-se fazer a integração da cidade de Angra do Heroísmo, com as suas características urbano-arquitectónicas, no conjunto mais amplo das cidades de expressão ou influencia portuguesa nas diversas áreas transatlânticas. Enumeram-se as urbes de Portugal Continental com maior valor e dimensão como “Cidades de Paisagem”, conceito que se pretende realçar e tornar operativo, nas cidades litorais, fluviais e interiores. Referem-se, procurando uma cara...

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2005-12-15

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

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

    International Nuclear Information System (INIS)

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

  18. Independent Qualification of the CIAU Tool Based on the Uncertainty Estimate in the Prediction of Angra 1 NPP Inadvertent Load Rejection Transient

    International Nuclear Information System (INIS)

    The Code with - the capability of - Internal Assessment of Uncertainty (CIAU) is a tool proposed by the 'Dipartimento di Ingegneria Meccanica, Nucleare e della Produzione (DIMNP)' of the University of Pisa. Other Institutions including the nuclear regulatory body from Brazil, 'Comissao Nacional de Energia Nuclear', contributed to the development of the tool. The CIAU aims at providing the currently available Relap5/Mod3.2 system code with the integrated capability of performing not only relevant transient calculations but also the related estimates of uncertainty bands. The Uncertainty Methodology based on Accuracy Extrapolation (UMAE) is used to characterize the uncertainty in the prediction of system code calculations for light water reactors and is internally coupled with the above system code. Following an overview of the CIAU development, the present paper deals with the independent qualification of the tool. The qualification test is performed by estimating the uncertainty bands that should envelope the prediction of the Angra 1 NPP transient RES-11. 99 originated by an inadvertent complete load rejection that caused the reactor scram when the unit was operating at 99% of nominal power. The current limitation of the 'error' database, implemented into the CIAU prevented a final demonstration of the qualification. However, all the steps for the qualification process are demonstrated. (authors)

  19. Nuclear Structure and the Fate of Core Collapse (Type II) Supernova

    OpenAIRE

    Gai, Moshe

    2014-01-01

    For a long time Gerry Brown and his collaborator Hans Bethe considered the question of the final fate of a core collapse (Type II) supernova. Recalling ideas from nuclear structure on Kaon condensate and a soft equation of state of the dense nuclear matter they concluded that progenitor stars with mass as low a 17-18M$_\\odot$ (including supernova 1987A) could collapse to a small mass black hole with a mass just beyond 1.5M$_\\odot$, the upper bound they derive for a neutron star. We discuss an...

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

    International Nuclear Information System (INIS)

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2013-12-15

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

  2. 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)

    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

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

    International Nuclear Information System (INIS)

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

  4. Design of relief tank for Qinshan phase II nuclear power project

    International Nuclear Information System (INIS)

    The relief tank is the special equipment of the reactor coolant system. The purpose of this equipment is to collect, condensate and cool steam of the high temperature and the high pressure from the pressurizer safety valve or the relief valve and collect drain water from various systems. The author briefly introduces the design of the relief tank for the Qinshan Phase II nuclear power project. The design features of equipment are following: the material is selected reasonably, the steam is condensed completely, both condensing and cooling are done inside the equipment, the bursting disc device nozzle have the function of the man hole. The design of this equipment is rational, which is examined by the experts. The proprietor has a greed to use this equipment for the Qinshan Phase II nuclear power project

  5. Summary report of the 1st research coordination meeting on nuclear model parameter testing for nuclear data evaluation (Reference Input Parameter Library: Phase II)

    International Nuclear Information System (INIS)

    The report describes findings and conclusions of the 1st Research Coordination Meeting on Nuclear Model Parameter Testing for Nuclear Data Evaluation (Reference Input Parameter Library: Phase II). In particular, a critical review of the RIPL Starter File was performed, and a detailed scope and workplan of the RIPL-II project were prepared. In an appendix are included the extended abstracts of four technical papers presented at the meeting. A separate abstract was prepared for each paper

  6. Vascular oxidative stress upregulates angiotensin II type I receptors via mechanisms involving nuclear factor kappa B

    OpenAIRE

    Bhatt, Siddhartha R.; Lokhandwala, Mustafa F.; Banday, Anees Ahmad

    2014-01-01

    The association of oxidative stress with hypertension is well known. However, a causal role of oxidative stress in hypertension is unclear. Vascular angiotensin II type 1 receptor (AT1R) upregulation is a prominent contributor to pathogenesis of hypertension. However, the mechanisms causing this upregulation are unknown. Oxidative stress is an important regulator of protein expression via activation of transcription factors such as nuclear factor kappa B (NFκB). The present study was carried ...

  7. Analysis and control of welding deformation in Qinshan nuclear power phase II extension project

    International Nuclear Information System (INIS)

    The paper analyzes the severe deformation in the welding of core barrel in Qinshan Nuclear Power Phase II Extension Project Reactor No. 3 unit, which nearly induces the loss of the function of the core barrel. Measures such as improving the welding fixture,process and parameter, and loading the counterweight is taken for the No. 4 unit to minimize the deformation, and the result shows that the weld of the No. 4 core barrel satisfies the design requirements. (authors)

  8. Preliminary nuclear safety assessment of the NEPST (Topaz II) space reactor program

    International Nuclear Information System (INIS)

    The United States (US) Strategic Defense Initiative Organization (SDIO) decided to investigate the possibility of launching a Russian Topaz II space nuclear power system. A preliminary nuclear safety assessment was conducted to determine whether or not a space mission could be conducted safely and within budget constraints. As part of this assessment, a safety policy and safety functional requirements were developed to guide both the safety assessment and future Topaz II activities. A review of the Russian flight safety program was conducted and documented. Our preliminary nuclear safety assessment included a number of deterministic analyses, such as; neutronic analysis of normal and accident configurations, an evaluation of temperature coefficients of reactivity, a reentry and disposal analysis, an analysis of postulated launch abort impact accidents, and an analysis of postulated propellant fire and explosion accidents. Based on the assessment to date, it appears that it will be possible to safely launch the Topaz II system in the US with a modification to preclude water flooded criticality. A full scale safety program is now underway

  9. 14N nuclear quadrupole interaction in Cu(II) doped L-alanine

    International Nuclear Information System (INIS)

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

  10. Heterometallic Cu(II)-Dy(III) Clusters of Different Nuclearities with Slow Magnetic Relaxation.

    Science.gov (United States)

    Modak, Ritwik; Sikdar, Yeasin; Cosquer, Goulven; Chatterjee, Sudipta; Yamashita, Masahiro; Goswami, Sanchita

    2016-01-19

    The synthesis, structures, and magnetic properties of two heterometallic Cu(II)-Dy(III) clusters are reported. The first structural motif displays a pentanuclear Cu(II)4Dy(III) core, while the second one reveals a nonanuclear Cu(II)6Dy(III)3 core. We employed o-vanillin-based Schiff base ligands combining o-vanillin with 3-amino-1-propanol, H2vap, (2-[(3-hydroxy-propylimino)-methyl]-6-methoxy-phenol), and 2-aminoethanol, H2vae, (2-[(3-hydroxy-ethylimino)-methyl]-6-methoxy-phenol). The differing nuclearities of the two clusters stem from the choice of imino alcohol arm in the Schiff bases, H2vap and H2vae. This work is aimed at broadening the diversity of Cu(II)-Dy(III) clusters and to perceive the consequence of changing the length of the alcohol arm on the nuclearity of the cluster, providing valuable insight into promising future synthetic directions. The underlying topological entity of the pentanuclear Cu4Dy cluster is reported for the first time. The investigation of magnetic behaviors of 1 and 2 below 2 K reveals slow magnetic relaxation with a significant influence coming from the variation of the alcohol arm affecting the nature of magnetic interactions. PMID:26702645

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

  13. Nuclear structure and the fate of core collapse (Type II) supernova

    International Nuclear Information System (INIS)

    For a long time Gerry Brown and his collaborator Hans Bethe considered the question of the final fate of a core collapse (Type II) supernova. Recalling ideas from nuclear structure on Kaon condensate and a soft equation of state of the dense nuclear matter they concluded that progenitor stars with mass as low as 17–18M⊙ (including supernova 1987A) could collapse to a small mass black hole with a mass just beyond 1.5M⊙, the upper bound they derive for a neutron star. We discuss another nuclear structure effect that determines the carbon to oxygen ratio (C/O) at the end of helium burning. This ratio also determines the fate of a Type II supernova with a carbon rich progenitor star producing a neutron star and oxygen rich collapsing to a black hole. While the C/O ratio is one of the most important nuclear inputs to stellar evolution it is still not known with sufficient accuracy. We discuss future efforts to measure with gamma-beam and TPC detector of the 12C(α,γ)16O reaction that determines the C/O ratio in stellar helium burning

  14. Nuclear Structure and the Fate of Core Collapse (Type II) Supernova

    CERN Document Server

    Gai, Moshe

    2014-01-01

    For a long time Gerry Brown and his collaborator Hans Bethe considered the question of the final fate of a core collapse (Type II) supernova. Recalling ideas from nuclear structure on Kaon condensate and a soft equation of state of the dense nuclear matter they concluded that progenitor stars with mass as low a 17-18M$_\\odot$ (including supernova 1987A) could collapse to a small mass black hole with a mass just beyond 1.5M$_\\odot$, the upper bound they derive for a neutron star. We discuss another nuclear structure effect that determines the carbon to oxygen ratio (C/O) at the end of helium burning. This ratio also determines the fate of a Type II supernova with a carbon rich progenitor star producing a neutron star and oxygen rich collapsing to a black hole. While the C/O ratio is one of the most important nuclear input to stellar evolution it is still not known with sufficient accuracy. We discuss future efforts to measure with gamma-beam and TPC detector the 12C(a,g)16O reaction that determines the C/O rat...

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

    Science.gov (United States)

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

    1951-05-01

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

  16. Zooplankton as an environmental monitoring tool in the area under Almirante Alvaro Alberto nuclear power plant influence

    International Nuclear Information System (INIS)

    Available as short communication only. Angra nuclear power plant refrigeration systems uses sea water collected in Itaorna and discharged in Piraquara de Fora, with an increase in temperature. Besides this, chlorine is added to avoid fouling in the circulation system. Zooplankton, small and generally microscope organism is very sensible to environmental changes. This work describes the methodology to evaluate the influence of Angra nuclear power plant liquid effluents in zooplankton organisms describing results and verifying impacts in this area. (author). 4 refs, 4 figs

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

    International Nuclear Information System (INIS)

    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.)

  18. Regulatory experience since 1995 in the field of instrumentation and control and support Systems of Nuclear Power Plants in Brazil

    Energy Technology Data Exchange (ETDEWEB)

    Furieri, Eusterio B.; Saldanha, Pedro L.C.; Silva, Paulo A. da; Nascimento, Joao M.L. do [Comissao Nacional de Energia Nuclear (CNEN), Rio de Janeiro, RJ (Brazil). Coordenacao de Reatores (CODRE)]. E-mails: eusterio@cnen.gov.br; saldanha@cnen.gov.br; pasilva@cnen.gov.br; jnascim@cnen.gov.br

    2007-07-01

    This paper presents licensing and regulatory control experiences in the field of instrumentation and control (I and C), electrical and computer-based support systems of the Brazilian nuclear power plants (NPP), since the issuance of Authorization for Permanent Operation (AOP) of ANGRA 1 NPP, in December 1994, covering licensing activities of ANGRA 2 from 1996 to 2006. The reports of the first PSR are under discussion and evaluation by CNEN, since 2005, including an evaluation of AOP's Improvement Programs closer related to electrical and I and C systems discussed in this report. ANGRA 1 is also implemented major modifications, as the steam generators replacement, the use of advanced nuclear fuel and the plant power uprate, which will required many design changes and/or modernization of I and C and related support systems. With respect to the Construction License of ANGRA 3, it is briefly presented the licensing status and preparation activities for the review and assessment of digital I and C systems, which will have similar functions of the analog I and C systems in operation at ANGRA 2 NPP. (author)

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

    International Nuclear Information System (INIS)

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

  20. Physics with gamma-beams and charged particle detectors: I) Nuclear structure II) Nuclear astrophysics

    Energy Technology Data Exchange (ETDEWEB)

    Gai, Moshe [LNS at Avery Point, University of Connecticut, Groton, CT 06340-6097, USA and Wright Lab, Dept. of Physics, Yale University, New Haven, CT 06520-8124 and the Charged Particle Working Group (CPWG) of the Technical Design Report (TDR) (United States)

    2015-02-24

    The Charged Particle Working Group (CPWG) is proposing to construct large area Silicon Strip Detector (SSD), a gas Time Projection Chamber detector read by an electronic readout system (eTPC) and a Bubble Chamber (BC) containing superheated high purity water to be used in measurements utilizing intense gamma-ray beams from the newly constructed ELI-NP facility at Magurele, Bucharest in Romania. We intend to use the SSD and eTPC detectors to address essential problems in nuclear structure physics, such as clustering and the many alpha-decay of light nuclei such as {sup 12}C and {sup 16}O. All three detectors (SSD, eTPC and BC) will be used to address central problems in nuclear astrophysics such as the astrophysical cross section factor of the {sup 12}C(α,γ) reaction and other processes central to stellar evolution. The CPWG intends to submit to the ELI-NP facility a Technical Design Report (TDR) for the proposed detectors.

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

    International Nuclear Information System (INIS)

    The worldwide development of nuclear power will lead to increasing demands for uranium. To meet its customers' growing requirements, AREVA has chosen to invest in COMURHEX II to renew and modernize its industrial conversion tool. An entirely new plant is to be built on the Tricastin site to the north of the existing COMURHEX plant. The plant, together with other large-scale investment projects such as the future Georges Besse II enrichment plant - also located on the Tricastin site - and the modernization of the FBFC fuel fabrication facilities in the south of France, will enable AREVA to strengthen its position as a long-standing and fully integrated player at the Front End of the nuclear fuel cycle. These major investments confirm the group's strong commitment to the global development of nuclear power. Converting uranium ore into uranium hexafluoride (UF6) is a key stage before the enrichment and fabrication of nuclear fuel. AREVA is gearing up for market changes, increasing its uranium production from 15,000 tons per year to 21,000 tons per year to match market needs. Today the conversion units of the different industrial operators are showing their age. They will need replacing in the medium term to increase production capacity and keep abreast of the economic, regulatory and environmental conditions of tomorrow's market. Its euros 610 million investment in the Narbonne and Pierrelatte sites in southern France will make AREVA the first uranium converter to overhaul its industrial tool. Thus indicating the group's intention of remaining world leader in UF6 conversion. The COMURHEX II project will involve the modernization and upgrading of our installations on the basis of tried-and-tested processes and techniques, while incorporating technological innovations that will improve the production performance, reinforce nuclear safety in the facilities, while further reducing the environmental impact of their activities. The first industrial production on the basis

  2. The research on corrosion condition and anticorrosion methods of SEP system pipelines in Qinshan Nuclear Power Plant Phase II

    International Nuclear Information System (INIS)

    SEP system in Qinshan nuclear power plant phase II provides drinking water and firefight water for nuclear island, conventional island, inner and outer of BOP structures. Many corrosion perforations in the SEP pipeline were found during operation. This article analysis the corrosion reasons and presents some reasonable treatment and surveillance methods. (authors)

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

    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)

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

    International Nuclear Information System (INIS)

    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)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2000-07-01

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

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

    International Nuclear Information System (INIS)

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

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

    DEFF Research Database (Denmark)

    Staresincic, Lidija; Walker, Jane; Dirac-Svejstrup, A Barbara; Mitter, Richard; Svejstrup, Jesper Q

    2011-01-01

    We identified XAB1 in a proteomic screen for factors that interact with human RNA polymerase II (RNAPII). Because XAB1 has a conserved Saccharomyces cerevisiae homologue called Npa3, yeast genetics and biochemical analysis were used to dissect the significance of the interaction. Degron-dependent......We identified XAB1 in a proteomic screen for factors that interact with human RNA polymerase II (RNAPII). Because XAB1 has a conserved Saccharomyces cerevisiae homologue called Npa3, yeast genetics and biochemical analysis were used to dissect the significance of the interaction. Degron...... in yeast extracts. Indeed, Npa3 depletion in vivo affects nuclear localization of RNAPII; the polymerase accumulates in the cytoplasm. Npa3 is a member of the GPN-LOOP family of GTPases. Npa3 mutants that either cannot bind GTP or that bind but cannot hydrolyze it are inviable and unable to support...

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

    International Nuclear Information System (INIS)

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

  10. American Physicists, Nuclear Weapons in World War II, and Social Responsibility

    Science.gov (United States)

    Badash, Lawrence

    2005-06-01

    Social responsibility in science has a centuries-long history, but it was such a minor thread that most scientists were unaware of the concept. Even toward the conclusion of the Manhattan Project, which produced the first nuclear weapons, only a handful of its participants had some reservations about use of a weapon of mass destruction. But the explosions over Hiroshima and Nagasaki not only made society more aware of the importance of science, they made scientists more aware of their responsibility to society. I describe the development of the concept of social responsibility and its appearance among American scientists both before and after the end of World War II.

  11. Direct determination of bulk etching rate for LR-115-II solid state nuclear track detectors

    Indian Academy of Sciences (India)

    T A Salama; U Seddik; T M Heggazy; A Ahmed Morsy

    2006-09-01

    The thickness of the removed layer of the LR-115-II solid state nuclear track detector during etching is measured directly with a rather precise instrument. Dependence of bulk etching rate on temperature of the etching solution is investigated. It has been found that the bulk etching rate is 3.2 m/h at 60°C in 2.5 N NaOH of water solution. It is also found that the track density in detectors exposed to soil samples increases linearly with the removed layer.

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

    CERN Multimedia

    2002-01-01

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

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

  15. Radionuclides determination in the Sargassum algae located in the Saco de Piraquara de Fora - Angra dos Reis - Rio de Janeiro - Brazil

    International Nuclear Information System (INIS)

    The main purpose of the Environmental Monitoring Laboratory, in the Mambucaba Residential Site is to control all environment around Almirante Alvaro Alberto Nuclear Power Station (AAANPS) in order to check its operational influence on the local ecosystem. Angra I Nuclear Power Plant usually discharges liquid waste from the Treatment System (waste and recycle evaporators). Before the water is discharged into the sea, it is chemically and radiochemically and analysed to verify if dissolved contaminants are in agreement with the specifications established by the Fundacao Estadual de Engenharia de Meio Ambiente (FEEMA) for the chemical parameters and by the Comissao Nacional de Energia Nuclear (CNEN) for radiochemical parameters. Such radioactive contaminants are 58 Co, 60 Co and 54 Mn, which are activated corrosion products from structural materials of the primary system and 134 Cs and 137 Cs, fission products produced by the nuclear reactor during its operation. To measure and control the possible discharge of these radionuclides into the sea and their incorporation to the marine organisms, it was created the Environmental Radiological Monitoring Special Program (ERMSP). The purpose of this program is to control the absorption of the radionuclides 58 Co, 60 Co, 54 Mn, 134 Cs and 137 Cs in algae of the genus Sargassum located in the surroundings the discharge of the liquid effluents of the genus Sargassum located in the surroundings the discharge of the liquid effluents of the Plant in Saco de Piraquara de Fora. The algae are considered excellent bioindicators because they are fixed on the rocks, being totally dependent on the water quality where they live, being being as easy target to incorporate and to detect those radionuclides. The algae are collected bimestrally and analysed by the Laboratory. This work presents the sampling process, the preparation, the sampling process, the preparation, the analysis of the radionuclides and the results obtained. (author)

  16. Calculation of Departure from Nucleate Boiling Ratio (DNBR) minimum for accident analysis of main steam line break at Angra-1

    International Nuclear Information System (INIS)

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

  17. Study on the importance and sensibility of the parameters used in the Angra-1 auxiliary feedwater system reliability analysis

    International Nuclear Information System (INIS)

    In this paper some procedures are presented in order to develop an importance and sensitivity analysis on the parameters considered in the reliability study of the Auxiliary Feedwater System of Angra-1. The importance analysis is performed to determine the events which have contribution on the top event. The results obtained from the sensitivity analysis can show the effects of variations in probability values of the dominant component failures on the probability of the top event. (author). 7 refs., 9 figs., 5 tabs

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

    International Nuclear Information System (INIS)

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

  19. Initiating events in the safety probabilistic analysis of nuclear power plants

    International Nuclear Information System (INIS)

    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.)

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

    International Nuclear Information System (INIS)

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

  1. Evaluation of nuclear safety measurements in ITU TRIGA Mark-II Reactor

    International Nuclear Information System (INIS)

    For the evaluation of the radiation measurements all the records made during over 20 years of operation of ITU TRIGA Mark-II Training and Research Reactor which has 250 kW full power are considered. In addition to the routine measurements, monitoring of the radiation levels in special places in the reactor are evaluated also which can be important for special working conditions. For the evaluation of the personnel monitoring, all the records are investigated for personnel exposed to radiation working at the ITU TRIGA Mark-II Training and Research Reactor. Determinations in air and water samples are tabulated for the reactor. Water samples have been taken from two cooling systems and the cooling tower. Air samples have been taken from the filter of ventilation system. Results of all the radiation measurements are evaluated according to the maximum permissible levels from the point of view of nuclear safety and public safety. One can conclude that ITU TRIGA Mark-II Training and Research Reactor has been operated in safe conditions since the reactor criticality date on 11 March 1979. (authors)

  2. Civilian nuclear power on the drawing board: the development of Experimental Breeder Reactor-II

    International Nuclear Information System (INIS)

    On September 28, 2001 a symposium was held at Argonne National Laboratory as part of the festivities to mark the 100th birthday of Enrico Fermi. The symposium celebrated Fermi's ''contribution to the development of nuclear power'' and focused on one particular ''line of development'' resulting from Fermi's interest in power reactors: Argonne's fast reactor program. Symposium participants made many references to the ways in which the program was linked to Fermi, who led the team which created the world's first self-sustaining nuclear chain reaction. For example, one presentation featured an April, 1944 memo that described a meeting attended by Fermi and others. The memo came from the time when research on plutonium and the nuclear chain reaction at Chicago's WWII Metallurgical Laboratory was nearing its end. Even as other parts of the Manhattan Engineering Project were building on this effort to create the bombs that would end the war, Fermi and his colleagues were taking the first steps to plan the use of nuclear energy in the postwar era. After noting that Fermi ''viewed the use of [nuclear] power for the heating of cities with sympathy,'' the group outlined several power reactor designs. In the course of discussion, Fermi and his colleagues took the first steps in conjuring the vision that would later be brought to life with Experimental Breeder Reactor I (EBR-I) and Experimental Breeder Reactor II (EBR-II), the celebrated achievements of the Argonne fast reactor program. Group members considered various schemes for a breeder reactor in which the relatively abundant U-238 would be placed near a core of fissionable material. The reactor would be a fast reactor; that is, neutrons would not be moderated, as were most wartime reactors. Thus, the large number of neutrons emitted in fast neutron fission would hit the U-238 and create ''extra'' fissionable material, that is, more than ''invested,'' and at the same time produce power. The group identified the problem of

  3. Civilian nuclear power on the drawing board: the development of Experimental Breeder Reactor-II.

    Energy Technology Data Exchange (ETDEWEB)

    Westfall, C.

    2003-02-20

    On September 28, 2001 a symposium was held at Argonne National Laboratory as part of the festivities to mark the 100th birthday of Enrico Fermi. The symposium celebrated Fermi's ''contribution to the development of nuclear power'' and focused on one particular ''line of development'' resulting from Fermi's interest in power reactors: Argonne's fast reactor program. Symposium participants made many references to the ways in which the program was linked to Fermi, who led the team which created the world's first self-sustaining nuclear chain reaction. For example, one presentation featured an April, 1944 memo that described a meeting attended by Fermi and others. The memo came from the time when research on plutonium and the nuclear chain reaction at Chicago's WWII Metallurgical Laboratory was nearing its end. Even as other parts of the Manhattan Engineering Project were building on this effort to create the bombs that would end the war, Fermi and his colleagues were taking the first steps to plan the use of nuclear energy in the postwar era. After noting that Fermi ''viewed the use of [nuclear] power for the heating of cities with sympathy,'' the group outlined several power reactor designs. In the course of discussion, Fermi and his colleagues took the first steps in conjuring the vision that would later be brought to life with Experimental Breeder Reactor I (EBR-I) and Experimental Breeder Reactor II (EBR-II), the celebrated achievements of the Argonne fast reactor program. Group members considered various schemes for a breeder reactor in which the relatively abundant U-238 would be placed near a core of fissionable material. The reactor would be a fast reactor; that is, neutrons would not be moderated, as were most wartime reactors. Thus, the large number of neutrons emitted in fast neutron fission would hit the U-238 and create ''extra'' fissionable material

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2015-10-02

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

  5. Neutron measurements in the Vandellos II nuclear power plant with a Bonner sphere system

    International Nuclear Information System (INIS)

    In some Spanish nuclear power plants of pressurised water reactor (PWR) type, albedo thermoluminescence dosemeters are used for personal dosimetry while survey meters, based on a thermal-neutron detector inside a cylindrical or spherical moderator, are used for dose rate assessment in routine monitoring. The response of both systems is highly dependent on the energy of the existing neutron fields. They are usually calibrated by means of ISO neutron sources with energy distributions quite different from those encountered at these installations. Spectrometric measurements with a Bonner sphere system (BSS) allow us to determine the reference dosimetric values. The UAB group, under request from the National Coordinated Research Action, was in charge of characterising the neutron fields and evaluating the response of personal dosemeters at several measurement points inside the containment building of the Catalan Nuclear Power Plant Vandellos II. The neutron fields were characterised at five places using the UAB-BSS and a home made unfolding code called MITOM. The results obtained confirm the presence of low-energy components in the neutron field in most of the selected points. Moreover, we have found no influence of the nuclear fuel burning on the shape of the spectrum. (authors)

  6. Erection of reactor vessel support of Angra-2 nuclear power plant reactor

    International Nuclear Information System (INIS)

    The erection of Reactor Pressure Vessel Support (RPV) on site can be divided in 3 different phases, according to the course of construction activities of the plant itself. They are, as follow: 1. Erection of the Embedded Parts in concrete. 2. Erection of Support before installation of RPV. 3. Erection of Support after installation of Reactor Pressure Vessel. The work will be restricted to part of item 2 of above mentioned phases, comprising since the lifting of the component inside of Reactor Building, until the dimensional records, after welding works of segments in their final localization, which steps can be considered as critical in the erection sequence. (author)

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

  9. Commissioning of the water demineralization plant of Atucha II Nuclear Power Plant

    International Nuclear Information System (INIS)

    In Argentina there are two operating Nuclear Power Reactors and a third one is being constructed. Embalse NPP is a 648 Mwe CANDU®-600 type pressurized heavy water reactor (PHWR), designed and built by Atomic Energy of Canada (AECL) and in commercial operation since 1984. Atucha I is a Pressurized Vessel Heavy Water Reactor (PVHWR) of 340 Mwe, in operation since 1974, and Atucha II (also PHWR) of 740 Mwe is in advanced construction state, both of them designed by SIEMENS-KWU. All of these Nuclear Power Plants are operated by Nucleoelectrica Argentina (N.A.S.A.). The Comision Nacional de Energia Atomica (C.N.E.A.) is the R and D nuclear institution in the country that, among many other topics, provides technical support to the plants. Although the Atucha II project has suffered some years of delay, pressure tests are expected to be carried out by the end of the year 2010 and in that sense, water chemistry related activities, specifications, chemistry manuals, laboratories organization and personnel training are acquiring importance. The demineralized water needed for the secondary and auxiliary systems is obtained by means of a demineralization plant, which purifies water from Parana River up to nuclear grade. This plant was designed by Degremont in 1979 and consists of a preliminary treatment by coagulation - flocculation and gravel filters, and subsequent demineralization with ion exchange resins. For the commissioning of the demineralization plant, preliminary tests in the chemical laboratory are performed. The flocculator is simulated using a Jar-Test, different coagulants and coagulation aids are tested with the objective of selecting the best product and defining its optimum dosage. The coagulated water is filtered by means of a funnel with filtration paper and sand. The clarified water thus obtained is treated by ion exchange resins, the train consisting of a cationic, an anionic and a mixed bed. The purpose of the laboratory experiments is to test the resins

  10. PWR-UO2 nuclear fuel criticality study: control rod effects on infinite neutron multiplication factor and spent fuel composition

    International Nuclear Information System (INIS)

    Highlights: • A three-dimensional model of a PWR fuel were simulated. • Results using TRITON/T6-DEPL module in SCALE 6.0 and two libraries (238 and 44 groups) were compared. • Variations in the infinite neutron multiplication factor and the nuclides concentrations, both under control rod insertion effects were analysed. • Results show very good agreement with those published by OECD. -- Abstract: Deterministic and stochastic nuclear codes are software packages used to perform reactor physics calculations, especially in PWRs, the most common type of nuclear reactor currently in operation. The NEA Expert Group on Burn-up Credit Criticality Safety has published a Benchmark with results obtained from simulations of PWR-UO2 nuclear fuel. The same simulations were performed at DEN/UFMG with SCALE 6.0, a modular nuclear system code developed by Oak Ridge National Laboratory using two different neutron energy libraries (238 and 44 groups). The results obtained using a three-dimensional model with the T6-DEPL sequence of the TRITON module in SCALE 6.0 for spent fuel inventory and infinite neutron multiplication factor calculations show very good agreement with those published by the OECD. The main goal of this work is to validate the methodology at DEN/UFMG for future use in simulations related to Angra I, II and III Nuclear Power Plants

  11. Nuclear knowledge management at the IAEA

    International Nuclear Information System (INIS)

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

  12. Iron normal mode dynamics in (nitrosyl)iron(II)tetraphenylporphyrin from X-ray nuclear resonance data.

    OpenAIRE

    Rai, Brajesh K; Durbin, Stephen M.; Prohofsky, Earl W.; Sage, J. Timothy; Wyllie, Graeme R. A.; Scheidt, W. Robert; Sturhahn, Wolfgang; Alp, E. Ercan

    2002-01-01

    The complete iron atom vibrational spectrum has been obtained by refinement of normal mode calculations to nuclear inelastic x-ray absorption data from (nitrosyl)iron(II)tetraphenylporphyrin, FeTPP(NO), a useful model for heme dynamics in myoglobin and other heme proteins. Nuclear resonance vibrational spectroscopy (NRVS) provides a direct measurement of the frequency and iron amplitude for all normal modes involving significant displacement of (57)Fe. The NRVS measurements on isotopically en...

  13. KNK II, Compact Sodium-Cooled Reactor in the Nuclear Research Center Karlsruhe

    International Nuclear Information System (INIS)

    The report gives an overview of the project of the sodium-cooled fast reactor KNK II in the nuclear research center KfK in Karlsruhe. This test reactor was the preparatory stage of the prototype plant SNR 300 and had several goals: to train operating personal, to practice the licensing procedures in Germany, to get experience with the sodium technology and to serve as a test bed for fast breeder core components. The report contains contributions of KfK as the owner and project managing organization, of INTERATOM as the design and construction company and of the KBG as the plant operating organization. Experience with and results of relevant aspects of the project are tackled: project management, reactor core and component design, safety questions and licensing, plant design and test programs

  14. Analysis of Early Severe Accident Initiated by LBLOCA for Qinshan Phase II Nuclear Power Project

    Directory of Open Access Journals (Sweden)

    Shi Xing-Wei

    2013-07-01

    Full Text Available The purpose of this study is to simulate an early Severe Accident (SA scenario more detail through transferring the thermal-hydraulic status of the plant predicted by RELAP5 computer code to SA Program (SAP. Based on the criterion of date extract time, the RELAP5 thermal-hydraulic calculation data is extracted to form a file for SAP input card at 1477K of cladding surface. Relying on the thermal-hydraulic boundary parameters calculated by RELAP5 code, analysis of early SA initiated by the Large Break Loss-of-Coolant Accident (LBLOCA without mitigation measures for Qinshan Phase II Nuclear Power Plant (QSP-II performed by SAP through finding the key events of accident sequence, estimating the amount of hydrogen generation and oxidation behavior of the cladding and evaluating the relocation order of the materials collapsed in the central region of the core. The results of this study are expected to improve the SA analysis methodology more detail through analyzing early SA scenario.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2014-12-01

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

  16. Co-Chairs’ Summary of Technical Session 3A. Nuclear Forensic Science: Signatures of Nuclear Material II

    International Nuclear Information System (INIS)

    Nuclear forensics refers to the application of science — in particular nuclear science —within the forensic science field. It is no longer a concept but a working tool, although it is still regarded by some as an emerging discipline that connects nuclear science and forensic science. Nuclear forensics is currently used effectively and reliably to prevent and respond to nuclear security events which involve nuclear and other radioactive material out of regulatory control. Its applications are critical in nuclear security systems to determine the data characteristics (i.e. signatures) of nuclear material subject to law enforcement investigations. This session was dedicated to papers on nuclear material signatures that highlighted and presented current work and developments or future expectations demonstrating the potential of nuclear forensic science

  17. Proliferating cell nuclear antigen, p53 and micro vessel density: Grade II vs. Grade III astrocytoma

    Directory of Open Access Journals (Sweden)

    Malhan Priya

    2010-01-01

    Full Text Available Histological classification and grading are prime procedures in the management of patients with astrocytoma, providing vital data for therapeutic decision making and prognostication. However, it has limitations in assessing biological tumor behavior. This can be overcome by using newer immunohistochemical techniques. This study was carried out to compare proliferative indices using proliferating cell nuclear antigen (PCNA, extent of p53 expression and micro vessel morphometric parameters in patients with low grade and anaplastic astrocytoma. Twenty-five patients, each of grade II and grade III astrocytoma were evaluated using monoclonal antibodies to PCNA, p53 protein and factor VIII related antigen. PCNA, p53-labeling indices were calculated along with micro vessel morphometric analysis using Biovis Image plus Software. Patients with grade III astrocytoma had higher PCNA and p53 labeling indices as compared with grade II astrocytoma (29.14 plus/minus 9.87% vs. 16.84 plus/minus 6.57%, p 0.001; 18.18 plus/minus 6.14% vs. 6.14 plus/minus 7.23%, p 0.001, respectively. Micro vessel percentage area of patients with grade III astrocytoma was also (4.26 plus/minus 3.70 vs. 1.05 plus/minus 0.56, p 0.001, higher along with other micro vessel morphometric parameters. Discordance between histology and one or more IHC parameters was seen in 5/25 (20% of patients with grade III astrocytoma and 9/25 (36% of patients with grade II disease. PCNA and p53 labeling indices were positively correlated with Pearson′s correlation, p less than 0.001 for both. Increased proliferative fraction, genetic alterations and neovascularization mark biological aggressiveness in astrocytoma. Immunohistochemical evaluation scores over meet the challenge of accurate prognostication of this potentially fatal malignancy.

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

    Energy Technology Data Exchange (ETDEWEB)

    Tello, Cledola C.O. de [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)], e-mail: tellocc@cdtn.br; Gomes, Nelson J.P.O. [Eletrobras Termonuclear S.A. - ELETRONUCLEAR, Rio de Janeiro, RJ (Brazil). Dept. GSR.T], e-mail: ogomes@eletronuclear.gov.br

    2009-07-01

    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)

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

    International Nuclear Information System (INIS)

    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)

  20. The nuclear-resonance-scattering station at the PETRA II undulator beamline

    Energy Technology Data Exchange (ETDEWEB)

    Franz, H.; Hukelmann, B.; Schneider, J.R. [HASYLAB at DESY (Germany)

    2000-07-15

    PETRA II, a 12 GeV accelerator at DESY, Hamburg, is used to produce synchrotron radiation (SR) for experiments in the hard X-ray regime when it is not running as injector for HERA. The beam from an undulator is split by a diamond crystal in Laue geometry to feed two experimental stations, one of which is now dedicated for nuclear resonance experiments. The X-ray energy may be chosen in the range from 5 to 55 keV covering all isotopes already observed with SR and many interesting candidates for new resonances. Tuning may be performed by optimising the magnetic gap and the storage ring energy. In particular, the opportunities for timing experiments are unique due to a very flexible filling mode of the storage ring. The flux at the sample position is comparable to undulator beams at ESRF. The second beamline covers higher energies up to some 300 keV and may also be used for nuclear resonance experiments.

  1. The nuclear-resonance-scattering station at the PETRA II undulator beamline

    Science.gov (United States)

    Franz, H.; Hukelmann, B.; Schneider, J. R.

    2000-07-01

    PETRA II, a 12 GeV accelerator at DESY, Hamburg, is used to produce synchrotron radiation (SR) for experiments in the hard X-ray regime when it is not running as injector for HERA. The beam from an undulator is split by a diamond crystal in Laue geometry to feed two experimental stations, one of which is now dedicated for nuclear resonance experiments. The X-ray energy may be chosen in the range from 5 to 55 keV covering all isotopes already observed with SR and many interesting candidates for new resonances. Tuning may be performed by optimising the magnetic gap and the storage ring energy. In particular, the opportunities for timing experiments are unique due to a very flexible filling mode of the storage ring. The flux at the sample position is comparable to undulator beams at ESRF. The second beamline covers higher energies up to some 300 keV and may also be used for nuclear resonance experiments.

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

    NARCIS (Netherlands)

    Reiling, Erwin; van Vliet-Ostaptchouk, Jana V.; van't Riet, Esther; van Haeften, Timon W.; Arp, Pascal A.; Hansen, Torben; Kremer, Dennis; Groenewoud, Marlous J.; van Hove, Els C.; Romijn, Johannes A.; Smit, Jan W. A.; Nijpels, Giel; Heine, Robert J.; Uitterlinden, Andre G.; Pedersen, Oluf; Slagboom, P. Eline; Maassen, Johannes A.; Hofker, Marten H.; 't Hart, Leen M.; Dekker, Jacqueline M.

    2009-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    1980-06-01

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

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

  7. Beznau II nuclear power plant: Expertise on NOK's request for the removal of the time limitation for the operation licence

    International Nuclear Information System (INIS)

    The Federal Agency for the Safety of Nuclear Installations (HSK) is the Swiss authority responsible for nuclear safety and protection against radioactivity in nuclear power plants. It has to examine the request of the North-East Swiss Power Corporation (NOK) concerning the removal of the operational time limitation for the Beznau-II reactor (KKB-II). In the present report HSK reviews the enterprise management and the safety of KKB-II on the basis of the results of the Periodic Safety Review. The Beznau nuclear power plant exhibits a very high degree of technical and organisational safety. During the past 10 years the plant has been operated in a safe manner. At the same time the plant has been improved and this guarantees that the mechanisms of ageing degradation are systematically identified and that measures can be taken that are possibly necessary. Under such conditions, the safety of KKB-II can be guarantied at all times. As a result of the management of quality, environmental and working safety conditions, the correct application and the continuous improvement of all processes important to safety are ensured. With these measures KKB has shown that safety is given priority over and against all other working goals. The examination by HSK of the Periodic Safety Review has shown that, in the past, KKB has applied modernisation measures independent of the licensing situation of the two reactor blocks. These modernisation measures largely contribute to the fact that the HSK examination did not reveal any significant safety deficiencies. Other improvement measures allow risk reduction or can bee seen as an adaptation to experience gained and to the state of the technological art. In conclusion, HSK states that no safety-relevant facts have been found which could prevent the removal of the time limitation on the operational licence for KKB-II. From the point of view of HSK, KKB-II fulfils the conditions for the safe continuation of operation

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

    International Nuclear Information System (INIS)

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

  9. Flebotomíneos de áreas com notificações de casos autóctones de leishmaniose visceral canina e leishmaniose tegumentar americana em Angra dos Reis, Rio de Janeiro, Brasil Phlebotomine fauna in areas of autochthonous cases of canine visceral leishmaniasis and American cutaneous leishmaniasis in Angra dos Reis, Rio de Janeiro, Brazil

    Directory of Open Access Journals (Sweden)

    Marcos Barbosa de Souza

    2009-01-01

    Full Text Available Flebótomos de áreas com notificações de casos autóctones de leishmaniose visceral canina e leishmaniose tegumentar americana em Angra dos Reis, Rio de Janeiro, Brasil. O município de Angra dos Reis apresenta casos humanos de leishmaniose tegumentar americana desde 1945. Inquéritos flebotomínicos realizados em 1978 revelaram a presença de Nyssomyia intermedia e a primeira notificação de Lutzomyia longipalpis no Rio de Janeiro, Ilha Grande, Angra dos Reis. Em agosto de 2002 foi notificado o primeiro caso canino de leishmaniose visceral na Ilha Grande, Angra dos Reis. Inquéritos flebotomínicos realizados nos peridomicílios, no período de novembro de 2002 a maio de 2003, em quatro localidades de Angra dos Reis, resultaram em 12.554 flebotomíneos e a presença de nove espécies: Brumptomyia sp.; Nyssomyia intermedia, Migonemyia migonei, Micropygomyia schreiberi, Pintomyia fischeri, Psychodopygus davisi, Psychodopygus ayrosai, Evandromyia tupinambay, Psathyromyia pelloni. foi Nyssomyia intermedia, predominante em todas as localidades, seguida por M.migonei. O principal vetor da LVA, Lutzomyia longipalpis, não foi detectado nas localidades, incluindo áreas do entorno, onde um cão infectado residia.The city of Angra dos Reis presents human cases of American cutaneous leishmaniasis since 1945. Phlebotomine surveys in 1978 had disclosed the presence of Nyssomyia intermedia and the first notification of Lutzomyia longipalpis in Rio de Janeiro, Ilha Grande, Angra dos Reis. In August of 2002 the first canine case of visceral leishmaniasis in the Ilha Grande, Angra dos Reis was notified. Surveys of phlebotomines in the peridomiciliary areas, in the period of November, 2002, through May, 2003, in four localities of Angra dos Reis, resulted in 12,554 specimens belonging to nine species: Brumptomyia sp. Nyssomyia intermedia, Migonemyia migonei, Micropygomyia schreiberi, Pintomyia fischeri, Psychodopygus davisi, Psychodopygus ayrosai

  10. Erection services of electrical, instrumentation and control and telecommunications components and systems for a 1300 MW e PWR nuclear power plant

    International Nuclear Information System (INIS)

    Erection services of Electrical, Instrumentation and Control (I and C) and Telecommunications components and systems for a 1300 MW e PWR Nuclear Power Plant are described based on the philosophy adopted for Angra 2 and 3 NPPs. These services include erection follow-up and control activities, engineering services, prefabrication, erection, technical documentation and related data processing activities. (author)

  11. Analysis of Radionuclide Releases from the Fukushima Dai-ichi Nuclear Power Plant Accident Part II

    Science.gov (United States)

    Achim, Pascal; Monfort, Marguerite; Le Petit, Gilbert; Gross, Philippe; Douysset, Guilhem; Taffary, Thomas; Blanchard, Xavier; Moulin, Christophe

    2014-03-01

    The present part of the publication (Part II) deals with long range dispersion of radionuclides emitted into the atmosphere during the Fukushima Dai-ichi accident that occurred after the March 11, 2011 tsunami. The first part (Part I) is dedicated to the accident features relying on radionuclide detections performed by monitoring stations of the Comprehensive Nuclear Test Ban Treaty Organization network. In this study, the emissions of the three fission products Cs-137, I-131 and Xe-133 are investigated. Regarding Xe-133, the total release is estimated to be of the order of 6 × 1018 Bq emitted during the explosions of units 1, 2 and 3. The total source term estimated gives a fraction of core inventory of about 8 × 1018 Bq at the time of reactors shutdown. This result suggests that at least 80 % of the core inventory has been released into the atmosphere and indicates a broad meltdown of reactor cores. Total atmospheric releases of Cs-137 and I-131 aerosols are estimated to be 1016 and 1017 Bq, respectively. By neglecting gas/particulate conversion phenomena, the total release of I-131 (gas + aerosol) could be estimated to be 4 × 1017 Bq. Atmospheric transport simulations suggest that the main air emissions have occurred during the events of March 14, 2011 (UTC) and that no major release occurred after March 23. The radioactivity emitted into the atmosphere could represent 10 % of the Chernobyl accident releases for I-131 and Cs-137.

  12. IFU spectroscopy of 10 early-type galactic nuclei - II. Nuclear emission line properties

    Science.gov (United States)

    Ricci, T. V.; Steiner, J. E.; Menezes, R. B.

    2014-05-01

    Although it is well known that massive galaxies have central black holes, most of them accreting at low Eddington ratios, many important questions still remain open. Among them are the nature of the ionizing source, the characteristics and frequencies of the broad-line region and of the dusty torus. We report observations of 10 early-type galactic nuclei, observed with the Gemini Multi Object Spectrograph in integral field unit mode, installed on the Gemini South telescope, analysed with standard techniques for spectral treatment and compared with results obtained with principal component analysis Tomography (Paper I). We performed spectral synthesis of each spaxel of the data cubes and subtracted the stellar component from the original cube, leaving a data cube with emission lines only. The emission lines were decomposed in multi-Gaussian components. We show here that, for eight galaxies previously known to have emission lines, the narrow-line region can be decomposed in two components with distinct line widths. In addition to this, broad Hα emission was detected in six galaxies. The two galaxies not previously known to have emission lines show weak Hα+[N II] lines. All 10 galaxies may be classified as low-ionization nuclear emission regions in diagnostic diagrams and seven of them have bona fide active galactic nuclei with luminosities between 1040 and 1043 erg s-1. Eddington ratios are always <10-3.

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

    International Nuclear Information System (INIS)

    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)

  14. 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)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2015-07-01

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

  16. Establishment of Procedures and Techniques for Nuclear Forensic Investigations Part II - Workshop on Nuclear Forensics Instituto de Pesquisas Energeticas e Nucleares

    International Nuclear Information System (INIS)

    The principal objective of this research contract was to implement a comprehensive program of nuclear forensic science in Brazil. The work plan had the following goals: - Reviewing and upgrading procedures and methods for chemical, physical and isotopic characterization of nuclear materials; - Demonstrating the reliability of the developed procedures by analyzing reference materials; - Collecting and analyzing common nuclear material in Brazil; and - Establishing a database for the nuclear forensic signatures of nuclear material in Brazil

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

    OpenAIRE

    Reiling, Erwin; Van Vliet-Ostaptchouk, Jana V.; van't Riet, Esther; van Haeften, Timon W; Arp, Pascal A; Hansen, Torben; Kremer, Dennis; Groenewoud, Marlous J.; van Hove, Els C.; Romijn, Johannes A.; Smit, Jan W. A.; Nijpels, Giel; Heine, Robert J.; Uitterlinden, André G.; Pedersen, Oluf

    2009-01-01

    Mitochondria play an important role in many processes, like glucose metabolism, fatty acid oxidation and ATP synthesis. In this study, we aimed to identify association of common polymorphisms in nuclear-encoded genes involved in mitochondrial protein synthesis and biogenesis with type II diabetes mellitus (T2DM) using a two-stage design. In the first stage, we analyzed 62 tagging single nucleotide polymorphisms (SNPs) in the Hoorn study (n=999 participants) covering all common variation in 13...

  18. National approach to economic performance indicators for nuclear power plants: Brazil

    International Nuclear Information System (INIS)

    The Brazilian electrical system comprises a fairly large grid, covering a very large territory, with a current installed capacity of around 75 GW. The electricity generated is predominantly hydroelectric. There has been great pressure in the last years to aggregate new energy to the grid in order to meet an increase in demand, thus requiring heavy investment in the generation, transmission and distribution of electricity. Under these circumstances it will be possible for nuclear power to participate in this market and to overcome the main obstacles to its growth in the electrical matrix. There are two nuclear units in operation: Angra 1 (657 MW(e) PWR) which went into commercial operation in January 1985 and Angra 2 (1350 MW(e) PWR) which started commercial operation in February 2001. Both are located in the Angra dos Reis region, 130 km from Rio de Janeiro and 220 km from Sao Paulo. A third PWR plant, Angra 3, similar to the second unit, is under construction at the same site. Although the capacity of the two nuclear plants represents less than 3% of the total installed capacity in Brazil, they produced, in 2002, close to 14,000 GW·h, corresponding to 4% of the total national electricity production and approximately 12% of the maximum storage capacity of the equivalent water reservoir in the southeast and central-west regions. The current challenge for nuclear energy in Brazil is to compete in the new market, in which the tariffs of the four federal supplier companies in 2002 stayed around 20 $/MW·h for the generation services. The generation costs of hydroelectric plants are currently about 15 $/MW·h compared with nuclear's 27 $/MW·h. It is a question of competitiveness. In the long term, nuclear energy will be necessary in the Brazilian energy mix. It is not known how long this period will be or whether Brazil will be able to implement its nuclear power programme in the future

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

    Directory of Open Access Journals (Sweden)

    Stiening Beate

    2004-06-01

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

  20. Automatic optimization of a nuclear reactor reload using the algorithm Ant-Q

    International Nuclear Information System (INIS)

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

  1. Study of multi cycles with FCS-II code for Unit 1 of Laguna Verde Nuclear Power Plant

    International Nuclear Information System (INIS)

    A study of 20 operating cycles for the BWR type reactor of Laguna Verde Nuclear Power Plant UNIT 1 is presented. The study was performed by the optimization group of fuel reloading by means of FCS-II code which is part of a computing package of Fuel Management System; with this results, part of the information concerning to a multi cycles analysis is evaluated; the information was provided by General Electric (GE) to Comision Federal de Electricidad. This study is part of the inter-institutional project of Fuel Management inside core for Laguna Verde Nuclear Power Plant where the involved institutions are Instituto de Investigaciones Electricas and Instituto Nacional de Investigaciones Nucleares under the direction of Comision Federal de Electricidad. (Author)

  2. Nuclear future: thinking for building. Proceedings of the 5. Brazilian national meeting on nuclear applications; 8. General congress on nuclear energy; 12. Brazilian national meeting on reactor physics and thermal hydraulics

    International Nuclear Information System (INIS)

    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

  3. Integrated impact analysis of a nuclear power plant: evaluation of accident scenarios, radiological dose estimates and protective measures

    International Nuclear Information System (INIS)

    The potential environmental impact associated to hypothetical accident scenarios in nuclear power plants can be better evaluated by using an integrated analysis approach. This approach would also help the planning of protective measures to protect public and the environment. The objective of this work identification of critical areas and groups of population, in terms of protective measures, by taking a geographical information system approach in the region of Angra dos Reis, where the Brazilian nuclear power plant is located

  4. Concentration of heavy metals in benthic algae from Ribera Bay, Angra dos Reis, R. J. State, Brazil, suggesting monitor species

    Energy Technology Data Exchange (ETDEWEB)

    Guimaraes, J.R.D.; Lacerda, L.D. de; Teixeira, V.L. (Rio de Janeiro Univ. (Brazil). Inst. de Biofisica; Faculdade de Biologia e Psicologia Maria Thereza, Niteroi (Brazil). Lab. de Botanica Marinha)

    1982-08-01

    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/sup 2/ for Ni to 10/sup 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.

  5. First limits on WIMP nuclear recoil signals in ZEPLIN-II: a two phase xenon detector for dark matter detection

    CERN Document Server

    Alner, G J; Bewick, A; Bungau, C; Camanzi, B; Carson, M J; Cashmore, R J; Chagani, H; Chepel, V; Cline, D; Davidge, D; Davies, J C; Daw, E; Dawson, J; Durkin, T; Edwards, B; Gamble, T; Gao, J; Ghag, C; Howard, A S; Jones, W G; Joshi, M; Korolkova, E V; Kudryavtsev, V A; Lawson, T; Lebedenko, V N; Lewin, J D; Lightfoot, P; Lindote, A; Liubarsky, I; Lopes, M I; Lüscher, R; Majewski, P; Mavrokoridis, K; McMillan, J E; Morgan, B; Muna, D; Murphy, A S J; Neves, F; Nicklin, G G; Ooi, W; Paling, S M; Cunha, J P; Plank, S J S; Preece, R M; Quenby, J J; Robinson, M; Sergiampietri, F; Silva, C; Solovov, V N; Smith, N J T; Smith, P F; Spooner, N J C; Sumner, T J; Thorne, C; Tovey, D R; Tziaferi, E; Walker, R J; Wang, H; White, J; Wolfs, F L H

    2007-01-01

    Results are presented from the first underground data run of ZEPLIN-II, a 31 kg two phase xenon detector developed to observe nuclear recoils from hypothetical weakly interacting massive dark matter particles. Discrimination between nuclear recoils and background electron recoils is afforded by recording both the scintillation and ionisation signals generated within the liquid xenon, with the ratio of these signals being different for the two classes of event. This ratio is calibrated for different incident species using an AmBe neutron source and Co-60 gamma-ray sources. From our first 31 live days of running ZEPLIN-II, the total exposure following the application of fiducial and stability cuts was 225 kgxdays. A background population of radon progeny events was observed in this run, arising from radon emission in the gas purification getters, due to radon daughter ion decays on the surfaces of the walls of the chamber. An acceptance window, defined by the neutron calibration data, of 50% nuclear recoil acce...

  6. H II regions, infrared dark molecular clouds and the local geometry of the Milky Way's nuclear star-forming ring

    CERN Document Server

    Liszt, H S

    2009-01-01

    To interpret the galactic center H II region complexes as constituents of a barred galaxy's nuclear star-forming ring, we compare 18cm VLA radiocontinuumm, $8-22\\mu$ MSX IR and 2.6mm BTL and ARO12m CO emission in the inner few hundred pc. Galactic center H II regions are comparable in their IR appearance, luminosity and SED to M17 or N!0, but the IR light distribution is strongly modified by extinction at 8-22$\\mu$, locally and overall. In Sgr B2 at $l > 0.6$\\degr strong radio H II regions are invisible in the IR. In two favorable cases, extinction from individual galactic center molecular clouds is shown to have $\\tau \\ga 1$ at 8-22$\\mu$ independent of wavelength. The gas kinematics are mostly rotational but with systematic $\\pm 30-50$ \\kms non-circular motion. Sgr B and C both show the same shell and high-velocity cap structure. The H II regions lie in a slightly-inclined ring of radius $\\approx$ 180 pc (1.2\\degr) whose near side appears at higher latitude and lower velocity and contains Sgr B. Sgr C is on ...

  7. Abdus Salam: A Reappraisal. Part II Salam's Part in the Pakistani Nuclear Weapon Programme

    CERN Document Server

    Dombey, Norman

    2011-01-01

    Salam's biographies claim that he was opposed to Pakistan's nuclear weapon programme. This is somewhat strange given that he was the senior Science Advisor to the Pakistan government for at least some of the period between 1972 when the programme was initiated and 1998 when a successful nuclear weapon test was carried out. I look at the evidence for his participation in the programme.

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

    International Nuclear Information System (INIS)

    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)

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

    CERN Document Server

    McRae, Kenneth D

    2014-01-01

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

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

    DEFF Research Database (Denmark)

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

    2009-01-01

    Mitochondria play an important role in many processes, like glucose metabolism, fatty acid oxidation and ATP synthesis. In this study, we aimed to identify association of common polymorphisms in nuclear-encoded genes involved in mitochondrial protein synthesis and biogenesis with type II diabetes...... for correct mitochondrial protein synthesis and biogenesis: aminoacyl tRNA synthetases, translation initiation factors, tRNA modifying enzymes and mitochondrial DNA transcription and replication. SNPs showing evidence for association with T2DM were measured in second stage genotyping (n=10164......-wide association studies, this SNP was also not associated with T2DM (P=0.72). In conclusion, we did not find evidence for association of common variants in 13 nuclear-encoded mitochondrial proteins with T2DM.European Journal of Human Genetics advance online publication, 11 February 2009; doi:10.1038/ejhg.2009.4....

  11. The protection system to Brazilian Nuclear Program

    International Nuclear Information System (INIS)

    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)

  12. 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)

    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.)

  13. Identification of familial clustering for cancer through the family health strategy program in the municipality of Angra dos Reis, Rio de Janeiro, Brazil

    OpenAIRE

    Vieira, Daniela Koeller Rodrigues; Attianezi, Margareth; Esposito, Ana Carolina; Barth, Anneliese; Sequeira, Cecília; Krause, Nathália; Oliveira, Vivian; Lucidi, Alexandre; Serao, Cassio; Llerena, Juan C

    2014-01-01

    Identification of families with history of cancer in the municipality of Angra dos Reis, Rio de Janeiro (Brazil), through the Brazilian Unified Primary Health Care System was explored based in the Community Health Agents (CHA) program. This study was divided into two phases: a descriptive one with a cross-sectional epidemiological data of families with history of cancer based on CHA-collected data from home visits in four primary health care units. The second phase consisted in identifying fa...

  14. Applications of artificial intelligence and expert systems in ANGRA-I emergency preparedness - The Brazilian case

    International Nuclear Information System (INIS)

    This study describes a system to follow a nuclear accident and points the areas where the presence of artificial intelligence could be necessary: diagnostics systems, emergency classification, accident management strategies and protective actions. Logical rules could be combined with deterministic equations to provide an expert system prototype to manage a nuclear emergency preparedness for nuclear reactors (fast or thermal) in the Brazilian Nuclear Energy National Commission. (CNEN). (author)

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

    International Nuclear Information System (INIS)

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

  16. Pile foundation of nuclear power plant structures

    International Nuclear Information System (INIS)

    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)

  17. 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)

    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

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

    International Nuclear Information System (INIS)

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

  19. Description of Induced Nuclear Fission with Skyrme Energy Functionals: II. Finite Temperature Effects

    OpenAIRE

    Schunck, N.; Duke, DJ; Carr, H.

    2013-01-01

    Understanding the mechanisms of induced nuclear fission for a broad range of neutron energies could help resolve fundamental science issues, such as the formation of elements in the universe, but could have also a large impact on societal applications in energy production or nuclear waste management. The goal of this paper is to set up the foundations of a microscopic theory to study the static aspects of induced fission as a function of the excitation energy of the incident neutron, from the...

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

    Science.gov (United States)

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

    2013-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2009-11-27

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

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

    International Nuclear Information System (INIS)

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

  3. 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

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

    International Nuclear Information System (INIS)

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

  5. WASTES-II, a logistics simulation tool for assessing system performance of the commercial nuclear waste management system

    International Nuclear Information System (INIS)

    The simulation of the movement of spent nuclear fuel within the commercial waste management system is a necessary precursor to evaluating the performance of any proposed configuration of a commercial waste management system (CWMS). The waste system transport and economic simulation (WASTES) model simulates the movement and storage of spent fuel from the time it is discharged into individual reactor pools to the time it is placed in a mined geologic repository. The original development of the WASTES model was jointly sponsored by the Monitored Retrievable Storage (MRS) Program Office at Pacific Northwest Laboratory (PNL) and the Transportation Technology Center at Sandia National Laboratories. Enhancements to the WASTES model that resulted in the development of the WASTES-II model were sponsored by both the MRS program at PNL (for use in analyzing the effects of various policy decisions, waste system logistics considerations, and facility operating schedules) and the PNL Nuclear Waste Fund Analysis program [to provide transportation economics for the U.S. Department of Energy's (DOE's) Total System Life-Cycle cost (TSLCC) analysis program]. The model was designed to provide detailed analyses that were beyond the capabilities of other available models. WASTES uses discrete event simulation techniques to model the generation of commercial spent nuclear fuel, the buildup of spent-fuel inventories within the system, and the movement of spent fuel throughout the system

  6. Nuclear fuel back-end. Vol.II: Costs of electricity production

    International Nuclear Information System (INIS)

    This document is a two-volume general report concerning the issue of nuclear fuel back-end. It is intended to inform the public upon the issues of radioactive waste management as well as other key issues of great economic significance in the nuclear power field. Within the frame of three chapters the following main issues concerning the power supply are addressed and discussed in the second volume: 1. Present French nuclear power system as a power supply security and national competitiveness factor, as well as, a major factor in the future power market; 2. The classical energy accounting analyses indicate a convergence in the costs of different energy generation systems but a variety of methodological biases; 3. When the external costs of different energy generation system are taken into consideration, the nuclear power production appears as an unescapable solution for future. In conclusion, the French nuclear programme initiated in 1970 was a gaining choice from the point of view of energy independence, technological progress, importation savings and exportation reserves. It became an important pillar of the global competitiveness of the French economy. Due to a cumulated investment of FFR 450 billion, France has an electronuclear sector that generated 376 TWh in 1997 i.e. 78.2% of the electricity produced in this country. The electricity cost in France is the lowest in Europe. Thus France will develop the experience acquired in the nuclear power field and so will attain the place deserved on the world electricity market, which records at present a fast growth

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

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

    Energy Technology Data Exchange (ETDEWEB)

    1978-06-01

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

  11. Neuroradiology in the ocular motility disorders : II. nuclear and infranuclear pathway

    International Nuclear Information System (INIS)

    The nuclear and infranuclear pathway of eye movement begins from the ocular motor nuclei situated in the brain stem, where the axons originate and form three ocular motor nerves. Although each of the ocular motor nerves follows a distinct route to reach the end organ, the extraocular muscles, they also have common housings in the cavernous sinus and at the orbital apex, where part or all of them are frequently and simultaneously affected by a common disease process. Since the fine details of normal and diseased structures can frequently be seen on radiologic imaging, especially magnetic resonance (MR) imaging, a knowledge of the basic anatomy involved in nuclear and infranuclear eye movement is important. In this description, in addition to the normal nuclear and infranuclear pathway of eye movement, we have noted the radiologic findings of typical diseases involving each segment of the nuclear and infranuclear pathway, particularly as seen on magnetic resonance images. Brief comments on ocular motor pseudopalsy, which mimics ocular motor palsy, are also included

  12. On growth of spinodal instabilities in nuclear matter-II:asymmetric matter

    CERN Document Server

    Acar, F; Yilmaz, O; Gokalp, A

    2015-01-01

    As an extension of our previous work, the growth of density fluctuations in the spinodal region of charge asymmetric nuclear matter is investigated in the basis of the stochastic mean-field approach in the non-relativistic framework. A complete treatment of density correlation functions are presented by including collective modes and non-collective modes as well.

  13. Description of Induced Nuclear Fission with Skyrme Energy Functionals: II. Finite Temperature Effects

    CERN Document Server

    Schunck, N; Carr, H

    2013-01-01

    Understanding the mechanisms of induced nuclear fission for a broad range of neutron energies could help resolve fundamental science issues, such as the formation of elements in the universe, but could have also a large impact on societal applications in energy production of nuclear waste management. The goal of this paper is to set up the foundations of a microscopic model to study the static aspects of induced fission as a function of the excitation energy of the incident neutron, from thermal to fast neutrons. To account for the high excitation energy of the compound nucleus, we employ a statistical approach based on finite temperature nuclear density functional theory with Skyrme energy densities, which we benchmark on the fission of 239Pu(n,f). We compute the evolution of the least-energy fission pathway across multidimensional potential energy surfaces with up to five collective variables as a function of the nuclear temperature, and predict the evolution of both the inner and outer fission barriers as ...

  14. Application of the oxydation process with silver (II) electrogenerated in the nuclear fields

    International Nuclear Information System (INIS)

    The solubilization, in nitric medium of some of radioactive compounds handled in the reprocessing fuel cycle, requires the use of electrochemical processes. The redox couple Ag(II)/Ag(I) with a normal potential of 1,92 Volt/NHE has been used as a strong oxidative mediator for the dissolution of plutonium dioxide, decontamination of contaminated Pu bearing wastes (ashes, various materials). Otherwise the use of this couple has been considered for the destruction of organic resins and extractants. (orig.)

  15. Visual examination program of the TRIGA Mark II reactor Vienna with the nuclear underwater telescope

    International Nuclear Information System (INIS)

    The visual inspection programm carried out during a three month shut-period at the TRIGA Mark II reactor Vienna is described. Optical inspection of all welds inside the reactor tank was carried out with an underwater telescope developed by the Central Research Institute of Physics, Budapest, Hungary. It is shown that even after 23 years of reactor operation all tank internals were found to be in good condition and minor defects can be easily repaired by remote handling tools. (Author)

  16. Expression of the nuclear encoded OEE1 protein is required for oxygen evolution and stability of photosystem II particles in Chlamydomonas reinhardtii.

    OpenAIRE

    Mayfield, S P; Bennoun, P; Rochaix, J D

    1987-01-01

    In Chlamydomonas reinhardtii the oxygen evolving enhancer protein 1 (OEE1), which is part of the oxygen evolving complex of photosystem II (PS II), is coded for by a single nuclear gene (psb1). The nuclear mutant FuD44 specifically lacks the OEE1 polypeptide and is completely deficient in photosynthetic oxygen evolution. In this mutant a 5 kb DNA insertion into the 5' region of the psb1 gene results in the complete absence of OEE1 mRNA and protein. A revertant, FuD44-R 2, which is capable of ...

  17. Safety probabilistic study of Almirante Alvaro Alberto nuclear power plant-Unit I

    International Nuclear Information System (INIS)

    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.)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2000-12-01

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

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

    International Nuclear Information System (INIS)

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

  20. Nuclear medicine in diagnosis and treatment of diseases of the head and neck: II

    International Nuclear Information System (INIS)

    The advent of both improved imaging systems and new radioactive agents has increased the effectiveness of nuclear medicine in diagnosing and treating diseases of the head and neck. In this second of two articles, researchers discuss radionuclide bone imaging and the role of nuclear medicine in the management of thyroid disease. Radionuclide bone imaging is useful in the differential diagnosis of sinusitis, the early detection of head and neck fracture, the assessment of temporomandibular joint disease, and the identification of local extension of primary head and neck carcinoma. In the management of thyroid disease, radionuclide technology is uniquely helpful in the diagnostic evaluation of the thyroid nodule and radioactive iodine continues to play a major role in thyroid cancer therapy

  1. Technical improvement of ATE system of Ling'ao Nuclear Power Plant Phase II

    International Nuclear Information System (INIS)

    In order to solve the problem that the content of SO42- in Steam Generator significantly increased beyond the criteria after the use of the condensate treatment (ATE) system in Daya Bay Nuclear Power Plant and Ling'ao Nuclear Power Plant Phase I, technical improvement have been conducted on the sizes of the fore cation bed and the mixed bed, water distributing devices, ion exchange resins and separation facility. The effectiveness for the ion exchange of the mixed bed is improved, the resolved substance of cation resin is decreased; it is more impossible for fragments and powder which would lead high SO42- content in Steam Generator. Finally, the quality of the steam-water could be improved and ensured. (authors)

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

    Science.gov (United States)

    Aymard, François; Gulminelli, Francesca; Margueron, Jérôme

    2016-08-01

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

  3. 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)

    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 100cm2-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)

  4. Qinshan phase II extension nuclear power project thermal stratification and fatigue stress analysis for pressurizer surge line

    International Nuclear Information System (INIS)

    Thermal stratification of pressurizer surge line induced by the inside fluid brings on global bending moments, local thermal stresses, unexpected displacements and support loadings of the pipe system. In order to avoid a costly three-dimensional computation, a combined 1D/2D technique has been developed and implemented to analyze the thermal stratification and fatigue stress of pressurize surge line of QINSHAN Phase II Extension Nuclear Power Project in this paper, using the computer codes SYSTUS and ROCOCO. According to the mechanical analysis results of stratification, the maximum stress and cumulative usage factor, the loadings at connections of surge line to main pipe and RCP and the displacements of surge line at supports are obtained. (authors)

  5. Hydrogeological modelling of the eastern region of Areco river locally detailed on Atucha I and II nuclear power plants area

    International Nuclear Information System (INIS)

    Water flow behaviour of Pampeano aquifer was modeled using Visual Mod-flow software Package 2.8.1 with the assumption of a free aquifer, within the region of the Areco river and extending to the rivers of 'Canada Honda' and 'de la Cruz'. Steady state regime was simulated and grid refinement allows obtaining locally detailed calculation in the area of Atucha I and II Nuclear power plants, in order to compute unsteady situations as the consequence of water flow variations from and to the aquifer, enabling the model to study the movement of possible contaminant particles in the hydrogeologic system. In this work the effects of rivers action, the recharge conditions and the flow lines are analyzed, taking always into account the range of reliability of obtained results, considering the incidence of uncertainties introduced by data input system, the estimates and interpolation of parameters used. (author)

  6. II. congress of Czechoslovak Society of Nuclear Medicine and Radiation Hygiene

    International Nuclear Information System (INIS)

    The proceedings contain 165 abstracts of papers covering all areas of the application of nuclear medicine, such as osteology, cardiology, immunology, neurology, oncology, etc. The topics include the examination of the skeleton with radioisotopes, various immunology methods, scintiscanning of body organs, tumor monitoring, radiopharmacology aspects, biological radiation effects, cytogenetic changes following irradiation, and studies of radiation effects on DNA repair. Separate volumes are devoted to education of technicians, processing of radioisotope examination data, radiation protection and decontamination. (M.D.)

  7. Underwater Nuclear Fuel Disassembly and Rod Storage Process and Equipment Description. Volume II

    International Nuclear Information System (INIS)

    The process, equipment, and the demonstration of the Underwater Nuclear Fuel Disassembly and Rod Storage System are presented. The process was shown to be a viable means of increasing spent fuel pool storage density by taking apart fuel assemblies and storing the fuel rods in a denser fashion than in the original storage racks. The assembly's nonfuel-bearing waste is compacted and containerized. The report documents design criteria and analysis, fabrication, demonstration program results, and proposed enhancements to the system

  8. ICSBEP criticality benchmarking for nuclear data validations, KAMINI, PURNIMA-II and PURNIMA-I

    International Nuclear Information System (INIS)

    India has contributed three experimental benchmarks to the International handbook of the International Criticality safety Benchmark Evaluation Project (ICSBEP) of the US-DOE/NEA-DB. This presentation describes the interesting experience in creating these three Indian experimental benchmarks for nuclear data and code validation studies. The concept of definition of benchmark is also reviewed for convenience. Series of sensitivity studies are performed to assess the various uncertainties that arise in knowledge of the description of the actual system

  9. Detection of Disease Genes by Use of Family Data. II. Application to Nuclear Families

    OpenAIRE

    Tu, I-Ping; Balise, Raymond R.; Whittemore, Alice S

    2000-01-01

    Two likelihood-based score statistics are used to detect association between a disease and a single diallelic polymorphism, on the basis of data from arbitrary types of nuclear families. The first statistic, the nonfounder statistic, extends the transmission/disequilibrium test to accommodate affected and unaffected offspring and missing parental genotypes. The second statistic, the founder statistic, compares observed or inferred parental genotypes with those of some reference population. In...

  10. Merging of globular clusters within inner galactic regions. II. The Nuclear Star Cluster formation

    CERN Document Server

    Capuzzo-Dolcetta, R

    2008-01-01

    In this paper we present the results of two detailed N-body simulations of the interaction of a sample of four massive globular clusters in the inner region of a triaxial galaxy. A full merging of the clusters takes place, leading to a slowly evolving cluster which is quite similar to observed Nuclear Clusters. Actually, both the density and the velocity dispersion profiles match qualitatively, and quantitatively after scaling, with observed features of many nucleated galaxies. In the case of dense initial clusters, the merger remnant shows a density profile more concentrated than that of the progenitors, with a central density higher than the sum of the central progenitors central densities. These findings support the idea that a massive Nuclear Cluster may have formed in early phases of the mother galaxy evolution and lead to the formation of a nucleus, which, in many galaxies, has indeed a luminosity profile similar to that of an extended King model. A correlation with galactic nuclear activity is suggeste...

  11. Nuclear Energy Center study. Phase II. Site suitability analysis. Final report

    International Nuclear Information System (INIS)

    A site screening study was conducted to identify a site or sites for detailed, site-specific study as a nuclear energy center. Using technical criteria of water requirements, geotechnical constraints, and projected load center and transmission considerations as well as environmental and institutional considerations, five potential study sites in the State of South Carolina were identified, evaluated against established criteria, and ranked according to their acceptability as potential nuclear energy center study sites. Consideration of what is ''representative'' of a site as well as the ranking score was factored into site recommendations, since the site deemed easiest to license and permit may not be the most desirable site for future study of the technical and institutional feasibility and practicality of a specific site. The sites near Lake Hartwell and the Savannah River Plant (SRP) of the Department of Energy were selected as potential study sites after consideration of the above criteria. Because the Lake Hartwell site offers the opportunity to consider institutional issues which may be more representative of other possible NEC sites, it is recommended that the Lake Hartwell site be studied to establish the feasibility and practicality of the nuclear energy concept on a site-specific basis

  12. The downstream side of the nuclear fuel cycle. Tome II: Electricity generating costs

    International Nuclear Information System (INIS)

    As part of the Office's continuing work in the nuclear field, Mr. Christian Bataille and Mr. Robert Galley, Members of Parliament for the Nord and Aube departements respectively, published in June 1998 the first part of their investigation into the downstream side of the nuclear fuel cycle, focusing on the work done in application of the law of 30 December 1991 concerning research into radioactive waste management. This document supplements that initial technical approach with a technical and economic study of the costs of generating electricity. To begin with, the performance of existing nuclear generating plant is examined, in particular the past, present and future contributions of this plant to the growth and competitiveness of the French economy. Secondly, the competitiveness of the different generating systems is analysed with a view to the construction of new facilities, using the method of discounted average costs which is at present the standard approach governing investment decisions, and identifying the different ways in which the said systems are dealt with as regards the cost categories considered. The potential contributions of external factor analysis and the calculation of external costs are then reviewed in order to evaluate the advantages and drawbacks of the different electricity generating systems on a more global basis. The report includes more than a hundred tables of data and cost curves upon which the Rapporteurs base their comments, conclusions and recommendations

  13. Geological disposal of nuclear waste: II. From laboratory data to the safety analysis – Addressing societal concerns

    International Nuclear Information System (INIS)

    Highlights: • Models for repository safety can only partly be validated. • Long term risks need to be translated in the context of societal temporalities. • Social sciences need to be more strongly involved into safety assessment. - Abstract: After more than 30 years of international research and development, there is a broad technical consensus that geologic disposal of highly-radioactive waste will provide for the safety of humankind and the environment, now, and far into the future. Safety analyses have demonstrated that the risk, as measured by exposure to radiation, will be of little consequence. Still, there is not yet an operating geologic repository for highly-radioactive waste, and there remains substantial public concern about the long-term safety of geologic disposal. In these two linked papers, we argue for a stronger connection between the scientific data (paper I, Grambow et al., 2014) and the safety analysis, particularly in the context of societal expectations (paper II). In this paper (II), we assess the meaning of the technical results and derived models (paper I) for the determination of the long-term safety of a repository. We consider issues of model validity and their credibility in the context of a much broader historical, epistemological and societal context. Safety analysis is treated in its social and temporal dimensions. This perspective provides new insights into the societal dimension of scenarios and risk analysis. Surprisingly, there is certainly no direct link between increased scientific understanding and a public position for or against different strategies of nuclear waste disposal. This is not due to the public being poorly informed, but rather due to cultural cognition of expertise and historical and cultural perception of hazards to regions selected to host a geologic repository. The societal and cultural dimension does not diminish the role of science, as scientific results become even more important in distinguishing

  14. Computational analysis of neutronic parameters for TRIGA Mark-II research reactor using evaluated nuclear data libraries

    International Nuclear Information System (INIS)

    The aim of this study is to analyze the neutronic parameters of TRIGA Mark-II research reactor using the chain of NJOY-WIMS-CITATION computer codes based on evaluated nuclear data libraries CENDL-2.2 and JEFF-3.1.1. The nuclear data processing code NJOY99.0 has been employed to generate the 69 group WIMS library for the isotopes of TRIGA core. The cell code WIMSD-5B was used to generate the cross sections in CITATION format and then 3-dimensional diffusion code CITTATION was used to calculate the neutronic parameters of the TRIGA Mark-II research reactor. All the analyses were performed using the 7-group macroscopic cross section library. The CITATION test-runs using different cross section sets based on different models applied in WIMS calculations have shown a strong influence of those models on the final integral parameters. Some of the cells were specially treated with PRIZE options available in WIMSD-5B to take into account the fine structure of the flux gradient in the fuel-reflector interface region. It was observed that two basic parameters, the effective multiplication factor, keff and the thermal neutron flux, were in good agreement among the calculated results with each other as well as the measured values. The maximum power densities at the hot spot were 1.0446E02 W/cc and 1.0426E02 W/cc for the libraries CENDL-2.2 and JEFF-3.1.1 respectively. The calculated total peaking factors 5.793 and 5.745 were compared to the original SAR value of 5.6325 as well as MCNP result. Consequently, this analysis will be helpful to enhance the neutronic calculations and also be used for the further thermal-hydraulics study of the TRIGA core.

  15. Computational analysis of neutronic parameters for TRIGA Mark-II research reactor using evaluated nuclear data libraries

    Energy Technology Data Exchange (ETDEWEB)

    Uddin, M.N. [Department of Physics, Jahangirnagar University, Dhaka (Bangladesh); Sarker, M.M., E-mail: sarker_md@yahoo.co [Reactor Physics and Engineering Division, Institute of Nuclear Science and Technology, Atomic Energy Research Establishment, Ganakbari, Savar, GPO Box 3787, Dhaka-1000 (Bangladesh); Khan, M.J.H. [Reactor Physics and Engineering Division, Institute of Nuclear Science and Technology, Atomic Energy Research Establishment, Ganakbari, Savar, GPO Box 3787, Dhaka-1000 (Bangladesh); Islam, S.M.A. [Department of Physics, Jahangirnagar University, Dhaka (Bangladesh)

    2010-03-15

    The aim of this study is to analyze the neutronic parameters of TRIGA Mark-II research reactor using the chain of NJOY-WIMS-CITATION computer codes based on evaluated nuclear data libraries CENDL-2.2 and JEFF-3.1.1. The nuclear data processing code NJOY99.0 has been employed to generate the 69 group WIMS library for the isotopes of TRIGA core. The cell code WIMSD-5B was used to generate the cross sections in CITATION format and then 3-dimensional diffusion code CITTATION was used to calculate the neutronic parameters of the TRIGA Mark-II research reactor. All the analyses were performed using the 7-group macroscopic cross section library. The CITATION test-runs using different cross section sets based on different models applied in WIMS calculations have shown a strong influence of those models on the final integral parameters. Some of the cells were specially treated with PRIZE options available in WIMSD-5B to take into account the fine structure of the flux gradient in the fuel-reflector interface region. It was observed that two basic parameters, the effective multiplication factor, k{sub eff} and the thermal neutron flux, were in good agreement among the calculated results with each other as well as the measured values. The maximum power densities at the hot spot were 1.0446E02 W/cc and 1.0426E02 W/cc for the libraries CENDL-2.2 and JEFF-3.1.1 respectively. The calculated total peaking factors 5.793 and 5.745 were compared to the original SAR value of 5.6325 as well as MCNP result. Consequently, this analysis will be helpful to enhance the neutronic calculations and also be used for the further thermal-hydraulics study of the TRIGA core.

  16. Reliability analysis of the service water system of Angra 1 reactor

    International Nuclear Information System (INIS)

    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.)

  17. Poisson regression analysis of the mortality among a cohort of World War II nuclear industry workers

    International Nuclear Information System (INIS)

    A historical cohort mortality study was conducted among 28,008 white male employees who had worked for at least 1 month in Oak Ridge, Tennessee, during World War II. The workers were employed at two plants that were producing enriched uranium and a research and development laboratory. Vital status was ascertained through 1980 for 98.1% of the cohort members and death certificates were obtained for 96.8% of the 11,671 decedents. A modified version of the traditional standardized mortality ratio (SMR) analysis was used to compare the cause-specific mortality experience of the World War II workers with the U.S. white male population. An SMR and a trend statistic were computed for each cause-of-death category for the 30-year interval from 1950 to 1980. The SMR for all causes was 1.11, and there was a significant upward trend of 0.74% per year. The excess mortality was primarily due to lung cancer and diseases of the respiratory system. Poisson regression methods were used to evaluate the influence of duration of employment, facility of employment, socioeconomic status, birth year, period of follow-up, and radiation exposure on cause-specific mortality. Maximum likelihood estimates of the parameters in a main-effects model were obtained to describe the joint effects of these six factors on cause-specific mortality of the World War II workers. We show that these multivariate regression techniques provide a useful extension of conventional SMR analysis and illustrate their effective use in a large occupational cohort study

  18. Beznau II nuclear power plant: Expertise on NOK's request for the removal of the time limitation for the operation licence; KKW Beznau II: Gutachten zum Gesuch der NOK um Aufhebung der Befristung der Betriebsbewilligung

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2004-03-15

    The Federal Agency for the Safety of Nuclear Installations (HSK) is the Swiss authority responsible for nuclear safety and protection against radioactivity in nuclear power plants. It has to examine the request of the North-East Swiss Power Corporation (NOK) concerning the removal of the operational time limitation for the Beznau-II reactor (KKB-II). In the present report HSK reviews the enterprise management and the safety of KKB-II on the basis of the results of the Periodic Safety Review. The Beznau nuclear power plant exhibits a very high degree of technical and organisational safety. During the past 10 years the plant has been operated in a safe manner. At the same time the plant has been improved and this guarantees that the mechanisms of ageing degradation are systematically identified and that measures can be taken that are possibly necessary. Under such conditions, the safety of KKB-II can be guarantied at all times. As a result of the management of quality, environmental and working safety conditions, the correct application and the continuous improvement of all processes important to safety are ensured. With these measures KKB has shown that safety is given priority over and against all other working goals. The examination by HSK of the Periodic Safety Review has shown that, in the past, KKB has applied modernisation measures independent of the licensing situation of the two reactor blocks. These modernisation measures largely contribute to the fact that the HSK examination did not reveal any significant safety deficiencies. Other improvement measures allow risk reduction or can bee seen as an adaptation to experience gained and to the state of the technological art. In conclusion, HSK states that no safety-relevant facts have been found which could prevent the removal of the time limitation on the operational licence for KKB-II. From the point of view of HSK, KKB-II fulfils the conditions for the safe continuation of operation

  19. Communication and surrounding of Asco and Vandellos II nuclear power plants

    International Nuclear Information System (INIS)

    The Asco and Vandellos-II power plants have always been integrated into the regions where they are located, and they take an active part in the development of surrounding towns through quality employment provided by our facilities, social and cultural support and aid to development promoted by regional councils. Communication to media is a corporate priority defined in our strategic plant, to ensure openness, rigour and punctuality. We also attend to the visitors who want to learn more about our facilities in the visitor center, and we have agreements with agrarian institutions in the area so that students can de practical training in the farms we own for agricultural production. (Author)

  20. Recommended criteria for the evaluation of on-site nuclear power plant emergency plans, volume II: criteria

    International Nuclear Information System (INIS)

    A critical review of existing Canadian and international nuclear power plant (NPP) emergency plans, evaluation criteria, and approaches has been conducted to provide AECB staff with information which can be used to assess the adequacy of NPP on-site emergency response plans. The results of this work are published in two volumes. Volume I, Basis Document, provides the reasons why certain requirements are in place. It also gives comprehensive references to various standards.Volume II, Criteria, contains the criteria which relate to on-site actions and their integration with control room activities and the roles of off-site responsible organizations. The recommended criteria provide information on what is required, and not on how to accomplish the requirements. The licensees are given the latitude to decide on the methods and processes needed to meet the requirements. The documents do not address NPP off-site plans and response capability, or the control room emergency operating procedures and response capability. This report contains only Volume II: Criteria. 55 refs., 2 tabs., 1 fig

  1. Nuclear-translocated endostatin downregulates hypoxia inducible factor-1α activation through interfering with Zn(II) homeostasis.

    Science.gov (United States)

    Guo, Lifang; Chen, Yang; He, Ting; Qi, Feifei; Liu, Guanghua; Fu, Yan; Rao, Chunming; Wang, Junzhi; Luo, Yongzhang

    2015-05-01

    Hypoxia‑inducible factor‑1α (HIF‑1α) is key in tumor progression and aggressiveness as it regulates a series of genes involved in angiogenesis and anaerobic metabolism. Previous studies have shown that the transcriptional levels of HIF‑1α may be downregulated by endostatin. However, the molecular mechanism by which endostatin represses HIF‑1α expression remains unknown. The current study investigated the mechanism by which nuclear‑translocated endostatin suppresses HIF‑1α activation by disrupting Zn(II) homeostasis. Endostatin was observed to downregulate HIF‑1α expression at mRNA and protein levels. Blockage of endostatin nuclear translocation by RNA interference of importin α1/β1 or ectopic expression of NLS‑deficient mutant nucleolin in human umbilical vein endothelial cells co‑transfected with small interfering (si)‑nucleolin siRNA compromises endostatin‑reduced HIF‑1α expression. Nuclear‑translocated apo‑endostatin, but not holo‑endostatin, significantly disrupts the interaction between CBP/p300 and HIF‑1α by disturbing Zn(II) homeostasis, which leads to the transcriptional inactivation of HIF‑1α. The results reveal mechanistic insights into the method by which nuclear‑translocated endostatin downregulates HIF‑1α activation and provides a novel way to investigate the function of endostatin in endothelial cells. PMID:25607980

  2. Sequence-specific interactions of nuclear factors with conserved sequences of human class II major histocompatibility complex genes

    International Nuclear Information System (INIS)

    All class II major histocompatibility complex genes contain two highly conserved sequences, termed X and Y, with the promoter region(s), which may have a role in regulation of expression. To study trans-acting factors that interact with these sequences, sequence-specific DNA binding activity has been examined by the gel electrophoresis retardation assay using the HLA-DQ2β gene 5' flanking DNA and nuclear extracts derived from various cell types. Several specific protein-binding activities were found using a 45-base-pair (bp) HinfI/Sau96I (-142 to -98 bp) and a 38-bp Sau96I/Sau96I (-97 to -60 bp) fragment, which include conserved sequence X (-113 to -100 bp) and conserved sequence Y (-80 to -71 bp), respectively. Competition experiments, methylation interference analysis, and DNase I footprinting demonstrated that distinct proteins in a nuclear extract of Raji cells (a human B lymphoma line) bind to sequence X, to sequence Y, and to DNA 5' of the X sequence (termed sequence W). The factor binding site in the W sequence is also found to be conserved among β-chain genes and is suggested to be a γ-interferon control region

  3. AIRDOS-II computer code for estimating radiation dose to man from airborne radionuclides in areas surrouding nuclear facilities

    International Nuclear Information System (INIS)

    The AIRDOS-II computer code estimates individual and population doses resulting from the simultaneous atmospheric release of as many as 36 radionuclides from a nuclear facility. This report describes the meteorological and environmental models used is the code, their computer implementation, and the applicability of the code to assessments of radiological impact. Atmospheric dispersion and surface deposition of released radionuclides are estimated as a function of direction and distance from a nuclear power plant or fuel-cycle facility, and doses to man through inhalation, air immersion, exposure to contaminated ground, food ingestion, and water immersion are estimated in the surrounding area. Annual doses are estimated for total body, GI tract, bone, thyroid, lungs, muscle, kidneys, liver, spleen, testes, and ovaries. Either the annual population doses (man-rems/year) or the highest annual individual doses in the assessment area (rems/year), whichever are applicable, are summarized in output tables in several ways--by nuclides, modes of exposure, and organs. The location of the highest individual doses for each reference organ estimated for the area is specified in the output data

  4. Microstructural and Fractographic Characterization of a Thermally Embrittled Nuclear Grade Steel: Part II - Quenching and Tempering

    Directory of Open Access Journals (Sweden)

    José R. Tarpani

    2002-09-01

    Full Text Available A nuclear reactor pressure vessel steel was submitted to different quenching and tempering heat treatments aimed at simulating neutron irradiation damage. The obtained microstructures were mechanically tested and submitted to metallographic and fractographic survey. The relevant microstructural and fractographic aspects were employed in the interpretation of the mechanical performance of the thermally embrittled microstructures. A well defined correlation was determined between the elastic-plastic fracture toughness parameter J-integral and the Charpy impact energy, which was achieved for some of the Q&T microstructures.

  5. Theory and Implementation of Nuclear Safety System Codes - Part II: System Code Closure Relations, Validation, and Limitations

    Energy Technology Data Exchange (ETDEWEB)

    Glenn A Roth; Fatih Aydogan

    2014-09-01

    This is Part II of two articles describing the details of thermal-hydraulic sys- tem codes. In this second part of the article series, the system code closure relationships (used to model thermal and mechanical non-equilibrium and the coupling of the phases) for the governing equations are discussed and evaluated. These include several thermal and hydraulic models, such as heat transfer coefficients for various flow regimes, two phase pressure correlations, two phase friction correlations, drag coefficients and interfacial models be- tween the fields. These models are often developed from experimental data. The experiment conditions should be understood to evaluate the efficacy of the closure models. Code verification and validation, including Separate Effects Tests (SETs) and Integral effects tests (IETs) is also assessed. It can be shown from the assessments that the test cases cover a significant section of the system code capabilities, but some of the more advanced reactor designs will push the limits of validation for the codes. Lastly, the limitations of the codes are discussed by considering next generation power plants, such as Small Modular Reactors (SMRs), analyz- ing not only existing nuclear power plants, but also next generation nuclear power plants. The nuclear industry is developing new, innovative reactor designs, such as Small Modular Reactors (SMRs), High-Temperature Gas-cooled Reactors (HTGRs) and others. Sub-types of these reactor designs utilize pebbles, prismatic graphite moderators, helical steam generators, in- novative fuel types, and many other design features that may not be fully analyzed by current system codes. This second part completes the series on the comparison and evaluation of the selected reactor system codes by discussing the closure relations, val- idation and limitations. These two articles indicate areas where the models can be improved to adequately address issues with new reactor design and development.

  6. Experimental research of irradiated nuclear fuel cladding failure processes: OECD Studsvik Cladding Integrity Project II

    International Nuclear Information System (INIS)

    The following 4 partial tasks were addressed: V001: Experimental results and knowledge of the effect of the material properties of the cladding and pellet on the phenomena of mechanical fuel-cladding interaction under the effect of radiation, at different temperatures and RAMP power load; V002: Knowledge based on the analysis of experimental data concerning the effect of iodine on the development of cracks on the fuel pin cladding tubes; V003: Processing the results of experiments to determine the primary cause of delayed hydride cracking (DHC) initiation in modern cladding alloys with low hydrogen concentrations; and V004: Analysis of the result of research into the effect of hydrides and hydrogen in the solid solution on the extension of nuclear fuel pin cladding. The results corroborated the prediction capabilities of the FEMAXI-6 code. The calculations were performed both for the reactor ramp tests and for the relaxation tests of the cladding materials, where MKP SW was the dominant tool. MKP was used for calculations within the bilateral relations with Studsvik Nuclear in the preparation of a new mechanical test for investigation of DHC, and basic MKP analyses were performed for the off-reactor test with an expansion mandrel. The theoretical generalization of the unique experimental data is documented through analysis and description of the final validation phase within the Quantum Technologies MKP model. (P.A.)

  7. Reason analysis for contamination of protective clothes during the first outage of unit 1 at Qinshan Nuclear Power Plant phase II

    International Nuclear Information System (INIS)

    More contamination events of protective clothes were occurred during the first outage of Unit 1 at Qinshan Nuclear Power Plant phase II. As a result, contaminated protective clothes were accumulated. This paper describes the amount and conditions of protective clothes analyses and discussies the reason of contamination. The measures for protecting protective clothes agaist contamination were put forward. (authors)

  8. In the matter of the application of the Westinghouse Electric Corporation for the export of pressurized water reactor to Asociacion Nuclear ASCO II, Barcelona, Spain

    International Nuclear Information System (INIS)

    The paper contains the text of a decision of the US NRC that the export of the ASCO nuclear power unit II to Spain would not be inimical to the common defense and security of the United States, so that there are no objections to issue the license to Westinghouse Electric Corporation. Furthermore the paper contains the dissenting opinion of Commissioner Gilinsky. (HP)

  9. Model of automatic fuel management for the Atucha II nuclear central with the PUMA IV code

    International Nuclear Information System (INIS)

    The Atucha II central is a heavy water power station and natural uranium. For this reason and due to the first floor reactivity excess that have this type of reactors, it is necessary to carry out a continuous fuel management and with the central in power (for the case of Atucha II every 0.7 days approximately). To maintain in operation these centrals and to achieve a good fuels economy, different types of negotiate of fuels that include areas and roads where the fuels displace inside the core are proved; it is necessary to prove the great majority of these managements in long periods in order to corroborate the behavior of the power station and the burnt of extraction of the fuel elements. To carry out this work it is of great help that a program implements the approaches to continue in each replacement, using the roads and areas of each administration type to prove, and this way to obtain as results the one regulations execution in the time and the average burnt of extraction of the fuel elements, being fundamental this last data for the operator company of the power station. To carry out the previous work it is necessary that a physicist with experience in fuel management proves each one of the possible managements, even those that quickly can be discarded if its don't fulfill with the regulatory standards or its possess an average extraction burnt too much low. For this it is of fundamental help that with an automatic model the different administrations are proven and lastly the physicist analyzes the more important cases. The pattern in question not only allows to program different types of roads and areas of fuel management, but rather it also foresees the possibility to disable some of the approaches. (Author)

  10. Nuclear reactors and fuel cycle

    International Nuclear Information System (INIS)

    The Nuclear Fuel Center (CCN) of IPEN produces nuclear fuel for the continuous operation of the IEA-R1 research reactor of IPEN. The serial production started in 1988, when the first nuclear fuel element was delivered for IEA-R1. In 2011, CCN proudly presents the 100th nuclear fuel element produced. Besides routine production, development of new technologies is also a permanent concern at CCN. In 2005, U3O8 were replaced by U3Si2-based fuels, and the research of U Mo is currently under investigation. Additionally, the Brazilian Multipurpose Research Reactor (RMB), whose project will rely on the CCN for supplying fuel and uranium targets. Evolving from an annual production from 10 to 70 nuclear fuel elements, plus a thousand uranium targets, is a huge and challenging task. To accomplish it, a new and modern Nuclear Fuel Factory is being concluded, and it will provide not only structure for scaling up, but also a safer and greener production. The Nuclear Engineering Center has shown, along several years, expertise in the field of nuclear, energy systems and correlated areas. Due to the experience obtained during decades in research and technological development at Brazilian Nuclear Program, personnel has been trained and started to actively participate in design of the main system that will compose the Brazilian Multipurpose Reactor (RMB) which will make Brazil self-sufficient in production of radiopharmaceuticals. The institution has participated in the monitoring and technical support concerning the safety, licensing and modernization of the research reactors IPEN/MB-01 and IEA-R1. Along the last two decades, numerous specialized services of engineering for the Brazilian nuclear power plants Angra 1 and Angra 2 have been carried out. The contribution in service, research, training, and teaching in addition to the development of many related technologies applied to nuclear engineering and correlated areas enable the institution to fulfill its mission that is to

  11. Quantitative analysis of the radioactive wastes to be generated in the Brazilian nuclear power plants

    International Nuclear Information System (INIS)

    In the nuclear fuel cycle radioactive waste requiring special treatment (processing, transportation and disposal) is produced. For the implementation of a waste management program, parameters such as volume, specific activity, thermal power, gamma power, (alpha,η) and spontaneous fission neutron production rates are required. In this work, we have calculated: a) The specific activity, thermal power, gamma power and neutron production rate for the irradiated fuel of Angra II; b) The volumes of radioactive waste that will be produced in the nuclear fuel cycle in Brazil; c) The specific activity, thermal power, gamma power and neutron production rate for the high-level waste that will be produced during fuel reprocessing. In the short-term it is concluded that the major problems that will require solution will be the disposal of the low-level waste (volume VL) and the interim storage of the irradiated fuel elements (volume VF) generated in the nuclear power plants. For the years 1990 and 2010 these volumes are: (1990) VL = 16149 m3; VF = 1287 m3 and (2010) VL = 690506 m3, VF = 55051 m3. In the medium-term the problem of the interim storage of the high-level waste (volume VH) must be solved. The volumes of this waste we have calculated for the years 2000 and 2010 are: (2000) VH = 50 m3 and (2010) VH = 1265 m3. Long term evaluation of high-level waste disposal must be analysed to aid in initial studies of this problem. Several parameters of this waste have been calculated as a function of time after reprocessing. (author)

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

    International Nuclear Information System (INIS)

    This report supplements the GESSAR II SER (NUREG-0979), issued in April 1983, summarizing the results of the staff's safety review of the GESSAR II BWR/6 nuclear island design. The review is carried out in accordance with the procedures for demonstrating the acceptability of the design for the severe-accident concerns described in draft NUREG-1070, NRC Policy on Future Reactor Designs: Decisions on Severe Accident Issues in Nuclear Power Plant Regulation. Supplement 2 also provides more recent information regarding resolution or update of the confirmatory items and FDA-1 conditions identified in SSER 1. Subject to favorable resolution of the items discussed in this supplement, the staff concludes that the GESSAR II design satisfactorily addresses the severe-accident concerns described in draft NUREG-1070

  13. Waveform cross correlation for seismic monitoring of underground nuclear explosions. Part II: Synthetic master events

    CERN Document Server

    Bobrov, Dmitry; Rozhkov, Mikhail

    2013-01-01

    Waveform cross correlation is an efficient tool for detection and characterization of seismic signals. The efficiency critically depends on the availability of master events. For the purposes of the Comprehensive Nuclear-Test-Ban Treaty, cross correlation can globally reduce the threshold monitoring by 0.3 to 0.4 magnitude units. In seismically active regions, the optimal choice of master events is straightforward. There are two approaches to populate the global grid in aseismic areas: the replication of real masters and synthetic seismograms calculated for seismic arrays of the International Monitoring System. Synthetic templates depend on the accuracy of shape and amplitude predictions controlled by focal depth and mechanism, source function, velocity structure and attenuation along the master/station path. As in Part I, we test three focal mechanisms (explosion, thrust fault, and actual Harvard CMT solution for one of the April 11, 2012 Sumatera aftershocks) and two velocity structures (ak135 and CRUST 2.0...

  14. Reactor dynamics experiment of nuclear ship Mutsu using pseudo random signal (II). The second experiment

    International Nuclear Information System (INIS)

    In order to investigate dynamics of the reactor plant of the nuclear ship Mutsu, the second reactor noise experiment using pseudo random binary sequences (PRBS) was performed on August 30, 1991 in the third experimental navigation. The experiments using both reactivity and load disturbances were performed at 50% of reactor power and under a quiet sea condition. Each PRBS was applied by manual operation of the control rod or the main steam valve. Various signals of the plant responses and of the acceleration of ship motion were measured. Furthermore, natural reactor noise signals were measured after each PRBS experiment in order to evaluate the effects of the PRBS disturbances. This paper summarizes the planning of the experiment, the instruction for the experiment and logs, the data recording conditions, recorded signal wave forms and the results of power spectral analysis. (author)

  15. Multifragmentation of a very heavy nuclear system (II): bulk properties and spinodal decomposition

    Energy Technology Data Exchange (ETDEWEB)

    Frankland, J.D.; Rivet, M.F.; Borderie, B. [Paris-11 Univ., Inst. de Physique Nucleaire, 91 - Orsay (France)] [and others

    2000-07-01

    The properties of fragments and light charged particles emitted in multifragmentation of single sources formed in central 36 A.MeV Gd+U collisions are reviewed. Most of the products are isotropically distributed in the reaction c.m. Fragment kinetic energies reveal the onset of radial collective energy. A bulk effect is experimentally evidenced from the similarity of the charge distribution with that from the lighter 32 A.MeV Xe+Sn system. Spinodal decomposition of finite nuclear matter exhibits the same property in simulated central collisions for the two systems, and appears therefore as a possible mechanism at the origin of multifragmentation in this incident energy domain. (authors)

  16. A probabilistic seismic risk assessment procedure for nuclear power plants: (II) Application

    Science.gov (United States)

    Huang, Y.-N.; Whittaker, A.S.; Luco, N.

    2011-01-01

    This paper presents the procedures and results of intensity- and time-based seismic risk assessments of a sample nuclear power plant (NPP) to demonstrate the risk-assessment methodology proposed in its companion paper. The intensity-based assessments include three sets of sensitivity studies to identify the impact of the following factors on the seismic vulnerability of the sample NPP, namely: (1) the description of fragility curves for primary and secondary components of NPPs, (2) the number of simulations of NPP response required for risk assessment, and (3) the correlation in responses between NPP components. The time-based assessment is performed as a series of intensity-based assessments. The studies illustrate the utility of the response-based fragility curves and the inclusion of the correlation in the responses of NPP components directly in the risk computation. ?? 2011 Published by Elsevier B.V.

  17. Nuclear and extended spectra of NGC 1068 - II. Near-infrared stellar population synthesis

    Science.gov (United States)

    Martins, Lucimara P.; Riffel, Rogério; Rodríguez-Ardila, Alberto; Gruenwald, Ruth; de Souza, Ronaldo

    2010-08-01

    We performed stellar population synthesis on the nuclear and extended regions of NGC 1068 by means of near-infrared spectroscopy to disentangle their spectral energy distribution components. This is the first time that such a technique is applied to the whole 0.8-2.4 μm wavelength interval in this galaxy. NGC 1068 is one of the nearest and probably the most studied Seyfert 2 galaxy, becoming an excellent laboratory to study the interaction between black holes, the jets that they can produce and the medium in which they propagate. Our main result is that traces of young stellar population are found at ~100 pc south of the nucleus. The contribution of a power-law continuum in the centre is about 25 per cent, which is expected if the light is scattered from a Seyfert 1 nucleus. We find peaks in the contribution of the featureless continuum about 100-150 pc from the nucleus on both sides. They might be associated with regions where the jet encounters dense clouds. Further support to this scenario is given by the peaks of hot dust distribution found around these same regions and the H2 emission-line profile, leading us to propose that the peaks might be associated to regions where stars are being formed. Hot dust also has an important contribution to the nuclear region, reinforcing the idea of the presence of a dense, circumnuclear torus in this galaxy. Cold dust appears mostly in the south direction, which supports the view that the south-west emission is behind the plane of the galaxy and is extinguished very likely by dust in the plane. Intermediate-age stellar population contributes significantly to the continuum, especially in the inner 200 pc.

  18. Nuclear Energy Center Site Survey, 1975. Part II. The U.S. electric power system and the potential role of nuclear energy centers

    International Nuclear Information System (INIS)

    Information related to Nuclear Energy Centers (NEC) in the U.S. is presented concerning the U.S. electric power system today; electricity demand history and forecasts; history and forecasts of the electric utility industry; regional notes; the status, history, and forecasts of the nuclear role; power plant siting problems and practices; nuclear facilities siting problems and practices; origin and evolution of the nuclear energy center concept; conceptualized description of nuclear energy centers; potential role of nuclear energy centers; assumptions, criteria, and bases; typical evolution of a nuclear energy center; and the nuclear fuel cycle

  19. 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)

    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)

  20. Ageing management program of wires for Atucha II Nuclear Power Plant

    International Nuclear Information System (INIS)

    Electrical cables constitute one of the most important components of NPP in terms o maintenance, safety and availability of the plant. Due to their large extension (thousands of kilometers) it is impossible to fully replace them and aging management becomes essential for long term operation of NPP. Since Atucha II is under construction there was a good opportunity to establish and implement a holistic cable aging management program from the beginning according to the state of the art in this field. The scope of this program involves safety related cables, including EQ cables and non EQ cables as well. Due to the diversity of the installed cables is impossible to address an aging management program of every single specimen. However it is possible to establish 'cables families' of similar aging behavior based on insulation and jacket material, manufacture, etc Several aging management strategies were set for the different 'cables families'. These strategies include cables deposit in plant, elaboration of procedures of visual and tactile inspection, NDE techniques, etc Currently the aging management program is being implemented covering topic such as: Cable screening and grouping. Review of EQ documentation and conventional qualification information referring to the installed cables. Establishment of base line of condition monitoring techniques. Calibration and set up of test parameters for NDE techniques. Aging mechanism characterization and determination of. Design construction and installation of cable deposit in plant (author)

  1. Nuclear and Extended Spectra of NGC 1068 - II: Near-Infrared Stellar Population Synthesis

    CERN Document Server

    Martins, Lucimara; Rodríguez-Ardila, Alberto; Gruenwald, Ruth; de Souza, Ronaldo

    2010-01-01

    We performed stellar population synthesis on the nuclear and extended regions of NGC 1068 by means of near-infrared spectroscopy to disentangle their spectral energy distribution components. This is the first time that such a technique is applied to the whole 0.8 - 2.4 micron wavelength interval in this galaxy. NGC 1068 is one of the nearest and probably the most studied Seyfert 2 galaxy, becoming an excellent laboratory to study the interaction between black holes, the jets that they can produce and the medium in which they propagate. Our main result is that traces of young stellar population are found at ~ 100 south of the nucleus. The contribution of a power-law continuum in the centre is about 25%, which is expected if the light is scattered from a Seyfert 1 nucleus. We find peaks in the contribution of the featureless continuum about 100 - 150 pc from the nucleus on both sides. They might be associated with regions where the jet encounters dense clouds. Further support to this scenario is given by the pe...

  2. The European Research on Severe Accidents in Generation-II and -III Nuclear Power Plants

    Directory of Open Access Journals (Sweden)

    Jean-Pierre Van Dorsselaere

    2012-01-01

    Full Text Available Forty-three organisations from 22 countries network their capacities of research in SARNET (Severe Accident Research NETwork of excellence to resolve the most important remaining uncertainties and safety issues on severe accidents in existing and future water-cooled nuclear power plants (NPP. After a first project in the 6th Framework Programme (FP6 of the European Commission, the SARNET2 project, coordinated by IRSN, started in April 2009 for 4 years in the FP7 frame. After 2,5 years, some main outcomes of joint research (modelling and experiments by the network members on the highest priority issues are presented: in-vessel degraded core coolability, molten-corium-concrete-interaction, containment phenomena (water spray, hydrogen combustion…, source term issues (mainly iodine behaviour. The ASTEC integral computer code, jointly developed by IRSN and GRS to predict the NPP SA behaviour, capitalizes in terms of models the knowledge produced in the network: a few validation results are presented. For dissemination of knowledge, an educational 1-week course was organized for young researchers or students in January 2011, and a two-day course is planned mid-2012 for senior staff. Mobility of young researchers or students between the European partners is being promoted. The ERMSAR conference is becoming the major worldwide conference on SA research.

  3. Dynamics of asymmetric binary glass formers. II. Results from nuclear magnetic resonance spectroscopy

    Energy Technology Data Exchange (ETDEWEB)

    Bock, D.; Kahlau, R.; Pötzschner, B.; Körber, T.; Wagner, E.; Rössler, E. A., E-mail: ernst.roessler@uni-bayreuth.de [Experimentalphysik II, Universität Bayreuth, 95440 Bayreuth (Germany)

    2014-03-07

    Various {sup 2}H and {sup 31}P nuclear magnetic resonance (NMR) spectroscopy techniques are applied to probe the component dynamics of the binary glass former tripropyl phosphate (TPP)/polystyrene-d{sub 3} (PS) over the full concentration range. The results are quantitatively compared to those of a dielectric spectroscopy (DS) study on the same system previously published [R. Kahlau, D. Bock, B. Schmidtke, and E. A. Rössler, J. Chem. Phys. 140, 044509 (2014)]. While the PS dynamics does not significantly change in the mixtures compared to that of neat PS, two fractions of TPP molecules are identified, one joining the glass transition of PS in the mixture (α{sub 1}-process), the second reorienting isotropically (α{sub 2}-process) even in the rigid matrix of PS, although at low concentration resembling a secondary process regarding its manifestation in the DS spectra. Pronounced dynamical heterogeneities are found for the TPP α{sub 2}-process, showing up in extremely stretched, quasi-logarithmic stimulated echo decays. While the time window of NMR is insufficient for recording the full correlation functions, DS results, covering a larger dynamical range, provide a satisfactory interpolation of the NMR data. Two-dimensional {sup 31}P NMR spectra prove exchange within the broadly distributed α{sub 2}-process. As demonstrated by {sup 2}H NMR, the PS matrix reflects the faster α{sub 2}-process of TPP by performing a spatially highly hindered motion on the same timescale.

  4. TRIGA Mark II nuclear reactor facility. Final report, 1 July 1980--30 June 1995

    International Nuclear Information System (INIS)

    This report is a final culmination of activities funded through the Department of Energy's (DOE) University Reactor Sharing Program, Grant DE-FG02-80ER10273, during the period 1 July 1980 through 30 June 1995. Progress reports have been periodically issued to the DOE, namely the Reactor Facility Annual Reports C00-2082/2219-7 through C00-2082/10723-21, which are contained as an appendix to this report. Due to the extent of time covered by this grant, summary tables are presented. Table 1 lists the fiscal year financial obligations of the grant. As listed in the original grant proposals, the DOE grant financed 70% of project costs, namely the total amount spent of these projects minus materials costs and technical support. Thus the bulk of funds was spent directly on reactor operations. With the exception of a few years, spending was in excess of the grant amount. As shown in Tables 2 and 3, the Reactor Sharing grant funded a immense number of research projects in nuclear engineering, geology, animal science, chemistry, anthropology, veterinary medicine, and many other fields. A list of these users is provided. Out of the average 3000 visitors per year, some groups participated in classes involving the reactor such as Boy Scout Merit Badge classes, teacher's workshops, and summer internships. A large number of these projects met the requirements for the Reactor Sharing grant, but were funded by the University instead

  5. TRIGA Mark II nuclear reactor facility. Final report, 1 July 1980--30 June 1995

    Energy Technology Data Exchange (ETDEWEB)

    Ryan, B.C.

    1997-05-01

    This report is a final culmination of activities funded through the Department of Energy`s (DOE) University Reactor Sharing Program, Grant DE-FG02-80ER10273, during the period 1 July 1980 through 30 June 1995. Progress reports have been periodically issued to the DOE, namely the Reactor Facility Annual Reports C00-2082/2219-7 through C00-2082/10723-21, which are contained as an appendix to this report. Due to the extent of time covered by this grant, summary tables are presented. Table 1 lists the fiscal year financial obligations of the grant. As listed in the original grant proposals, the DOE grant financed 70% of project costs, namely the total amount spent of these projects minus materials costs and technical support. Thus the bulk of funds was spent directly on reactor operations. With the exception of a few years, spending was in excess of the grant amount. As shown in Tables 2 and 3, the Reactor Sharing grant funded a immense number of research projects in nuclear engineering, geology, animal science, chemistry, anthropology, veterinary medicine, and many other fields. A list of these users is provided. Out of the average 3000 visitors per year, some groups participated in classes involving the reactor such as Boy Scout Merit Badge classes, teacher`s workshops, and summer internships. A large number of these projects met the requirements for the Reactor Sharing grant, but were funded by the University instead.

  6. Design of sample carrier for neutron irradiation facility at TRIGA MARK II nuclear reactor

    Science.gov (United States)

    Abdullah, Y.; Hamid, N. A.; Mansor, M. A.; Ahmad, M. H. A. R. M.; Yusof, M. R.; Yazid, H.; Mohamed, A. A.

    2013-06-01

    The objective of this work is to design a sample carrier for neutron irradiation experiment at beam ports of research nuclear reactor, the Reaktor TRIGA PUSPATI (RTP). The sample carrier was designed so that irradiation experiment can be performed safely by researchers. This development will resolve the transferring of sample issues faced by the researchers at the facility when performing neutron irradiation studies. The function of sample carrier is to ensure the sample for the irradiation process can be transferred into and out from the beam port of the reactor safely and effectively. The design model used was House of Quality Method (HOQ) which is usually used for developing specifications for product and develop numerical target to work towards and determining how well we can meet up to the needs. The chosen sample carrier (product) consists of cylindrical casing shape with hydraulic cylinders transportation method. The sample placing can be done manually, locomotion was by wheel while shielding used was made of boron materials. The sample carrier design can shield thermal neutron during irradiation of sample so that only low fluencies fast neutron irradiates the sample.

  7. Design of sample carrier for neutron irradiation facility at TRIGA MARK II nuclear reactor

    International Nuclear Information System (INIS)

    The objective of this work is to design a sample carrier for neutron irradiation experiment at beam ports of research nuclear reactor, the Reaktor TRIGA PUSPATI (RTP). The sample carrier was designed so that irradiation experiment can be performed safely by researchers. This development will resolve the transferring of sample issues faced by the researchers at the facility when performing neutron irradiation studies. The function of sample carrier is to ensure the sample for the irradiation process can be transferred into and out from the beam port of the reactor safely and effectively. The design model used was House of Quality Method (HOQ) which is usually used for developing specifications for product and develop numerical target to work towards and determining how well we can meet up to the needs. The chosen sample carrier (product) consists of cylindrical casing shape with hydraulic cylinders transportation method. The sample placing can be done manually, locomotion was by wheel while shielding used was made of boron materials. The sample carrier design can shield thermal neutron during irradiation of sample so that only low fluencies fast neutron irradiates the sample.

  8. Radiation effects in concrete for nuclear power plants, Part II: Perspective from micromechanical modeling

    International Nuclear Information System (INIS)

    Highlights: • A micromechanical model for irradiated concrete is proposed. • Confrontation with literature data is successful. • Neutron radiation-induced volumetric expansion is a predominant degradation mode. • The nature of the aggregate alters the severity of damage to irradiated concrete. - Abstract: The need to understand and characterize the effects of neutron irradiation on concrete has become urgent because of the possible extension of service life of many nuclear power generating stations. Current knowledge is primarily based on a collection of data obtained in test reactors. These data are inherently difficult to interpret because materials and testing conditions are inconsistent. A micromechanical approach based on the Hashin composite sphere model is presented to derive a first-order separation of the effects of radiation on cement paste and aggregate, and, also, on their interaction. Although the scarcity of available data limits the validation of the model, it appears that, without negating a possible gamma-ray induced effect, the neutron-induced damage and swelling of aggregate plays a predominant role on the overall concrete expansion and the damage of the cement paste. The radiation-induced volumetric expansion (RIVE) effects can also be aided by temperature elevation and shrinkage in the cement paste

  9. Radiation effects in concrete for nuclear power plants, Part II: Perspective from micromechanical modeling

    Energy Technology Data Exchange (ETDEWEB)

    Le Pape, Y., E-mail: lepapeym@ornl.gov; Field, K.G.; Remec, I.

    2015-02-15

    Highlights: • A micromechanical model for irradiated concrete is proposed. • Confrontation with literature data is successful. • Neutron radiation-induced volumetric expansion is a predominant degradation mode. • The nature of the aggregate alters the severity of damage to irradiated concrete. - Abstract: The need to understand and characterize the effects of neutron irradiation on concrete has become urgent because of the possible extension of service life of many nuclear power generating stations. Current knowledge is primarily based on a collection of data obtained in test reactors. These data are inherently difficult to interpret because materials and testing conditions are inconsistent. A micromechanical approach based on the Hashin composite sphere model is presented to derive a first-order separation of the effects of radiation on cement paste and aggregate, and, also, on their interaction. Although the scarcity of available data limits the validation of the model, it appears that, without negating a possible gamma-ray induced effect, the neutron-induced damage and swelling of aggregate plays a predominant role on the overall concrete expansion and the damage of the cement paste. The radiation-induced volumetric expansion (RIVE) effects can also be aided by temperature elevation and shrinkage in the cement paste.

  10. Group, field and isolated early-type galaxies II. Global trends from nuclear data

    CERN Document Server

    Denicolo, G; Terlevich, E; Forbes, D A; Terlevich, A I; Denicolo, Glenda; Terlevich, Roberto; Terlevich, Elena; Forbes, Duncan A.; Terlevich, Alejandro

    2004-01-01

    We have derived ages, metallicities and enhanced-element ratios [alpha/Fe] for a sample of 83 early-type galaxies essentially in groups, the field or isolated objects. The stellar population properties derived for each galaxy corresponds to the nuclear r_e/8 aperture extraction. The median age found for Es is 5.8 +- 0.6 Gyr and the average metallicity is +0.37 +- 0.03 dex. For S0s, the median age is 3.0 +- 0.6 Gyr and [Z/H] = 0.53 +- 0.04 dex. We compare the distribution of our galaxies in the Hbeta-[MgFe] diagram with Fornax galaxies. Our elliptical galaxies are 3-4 Gyr younger than Es in the Fornax cluster. We find that the galaxies lie in a plane defined by [Z/H] = 0.99 log sigma_0 - 0.46 log Age - 1.60. More massive (larger sigma_0) and older galaxies present, on average, large [alpha/Fe] values, and therefore, must have undergone shorter star-formation timescales. Comparing group against field/isolated galaxies, it is not clear that environment plays an important role in determining their stellar populat...

  11. Influence of marine sediments in the distribution of the main radionuclides of the effluent from the nuclear power plant Almirante Alvaro Alberto (Unit 1)

    International Nuclear Information System (INIS)

    This study aimed to: 1) Characterize bottom sediments of the Angra dos Reis region, in the dispersion area of the effluent of the central Almirante Nuclear Alvaro Alberto, Unit 1. 2) Determining the adsorption capacity of these sediments to the long half-life and mean radionuclides to be released in the reactor effluent in a higher concentration. 3) Estimate the fraction of the different studied radionuclides that will be immobilized in sediments. 4) Identify critical radionuclides available for food chain

  12. SPLOSH II: A dynamics programme for nuclear - thermal - hydrodynamic behaviour of water-cooled reactors

    International Nuclear Information System (INIS)

    A dynamics code is described that solves the two-group neutron diffusion equations simultaneously with the thermal and the hydraulic equations for an average channel of a water-cooled reactor. Other reactor channels can be represented as 'slaves', which have no feedback to the average channel. The fission power at any axial station in a slave channel is related to that in the average by prescribed time-dependent factors, and the hydraulic flow is determined from pressure-drop requirements dictated by the performance of the average channel. A finite difference model of the fuel element and can represents the behaviour of the fuel temperatures and surface heat flux. The representation of the hydraulic circuit has been made sufficiently general that the code is applicable to B.W.R., P.W.R. and pressure tube reactor designs. The code can be used to study transients resulting from imposed time variations in coolant flow, inlet enthalpy, system pressure, electrical torque supplied to the circulating pumps, (or alternatively, the angular velocity of the pump rotors,) moderator height, frictional resistances simulating blockages and control rod and fuel element insertions. The harmonic response can be obtained by injecting sinusoidal time variations until the starting transient has been damped out. Output includes axial distributions of the neutron fluxes, heat flux, coolant density and temperature, burn-but margin, and the fuel and can temperatures in both the average and the slave channels. The code was originally written in FORTRAN II for use on the IBM 7090. Computing times vary greatly with the problem and the desired accuracy but experience has shown that a computing time which is slower than real time by a factor thirty is adequate for a wide range of cases. The code has recently been converted to S2 and EGTRAN for use on the IBM 7030 and the English Electric Leo Marconi KDF 9 computers. (author)

  13. 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)

    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/cm2/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)

  14. Acoustoelastic evaluation of welding and heat treatment stress relieving of pressure vessel steel for Angra 3

    Energy Technology Data Exchange (ETDEWEB)

    Moraes, Bruno C. de, E-mail: bruno.cesar@nuclep.gov.br [Nuclebras Equipamentos Pesados S.A (NUCLEP), Itaguai, RJ (Brazil); Bittencourt, Marcelo de S.Q., E-mail: bruno.cesar@nuclep.gov.br, E-mail: bittenc@ien.gov.br [Instituto de Engenharia Nuclear (IEN/CNEN-RJ), Rio de Janeiro, RJ (Brazil)

    2015-07-01

    Currently the knowledge of non-destructive techniques allows to evaluate the stresses on components and mechanical structures, aiming at physical security, preservation of the environment and avoid financial losses associated with the construction and operation of industrial plants. The search for new techniques, especially applied in the nuclear industry to assess status more accurately, voltage safety and to ensure structural integrity, for example, core components of the primary circuit, such as the reactor pressure vessel and steam generator has become of great importance within the community of non-destructive testing .This paper aims to contribute to the non-destructive technique development in order to ensure the structural integrity of nuclear components. One acoustoelastic evaluation of steel 20 MnMoNi 55, used in pressure vessels of nuclear power plants were performed. The acoustic birefringence technique was use to evaluate the acoustoelastic behavior of the test material in the as received condition, after welding and after the stress relief heat treatment. The constant acoustoelastic material was obtained by an uniaxial loading test. It was found a slight anisotropy in the material as received. After welding, a marked variation of acoustic birefringence in the region near the weld bead was observed. The heat treatment indicated a new change of acoustic birefringence. Obtaining the acoustoelastic constant allowed the evaluation of stress in the different conditions of the weld and treated material. (author)

  15. Acoustoelastic evaluation of welding and heat treatment stress relieving of pressure vessel steel for Angra 3

    International Nuclear Information System (INIS)

    Currently the knowledge of non-destructive techniques allows to evaluate the stresses on components and mechanical structures, aiming at physical security, preservation of the environment and avoid financial losses associated with the construction and operation of industrial plants. The search for new techniques, especially applied in the nuclear industry to assess status more accurately, voltage safety and to ensure structural integrity, for example, core components of the primary circuit, such as the reactor pressure vessel and steam generator has become of great importance within the community of non-destructive testing .This paper aims to contribute to the non-destructive technique development in order to ensure the structural integrity of nuclear components. One acoustoelastic evaluation of steel 20 MnMoNi 55, used in pressure vessels of nuclear power plants were performed. The acoustic birefringence technique was use to evaluate the acoustoelastic behavior of the test material in the as received condition, after welding and after the stress relief heat treatment. The constant acoustoelastic material was obtained by an uniaxial loading test. It was found a slight anisotropy in the material as received. After welding, a marked variation of acoustic birefringence in the region near the weld bead was observed. The heat treatment indicated a new change of acoustic birefringence. Obtaining the acoustoelastic constant allowed the evaluation of stress in the different conditions of the weld and treated material. (author)

  16. Synthesis, nuclear magnetic resonance and infrared studies of zinc(II) and cadmium(II) complexes of thiosemicarbazones derived from fluorenone and p-anisaldehyde

    International Nuclear Information System (INIS)

    Fluorenone (FTSCH) and p-anisaldehyde (ATSCH) thiosemicarbazones react with zinc(II) and cadmium(II) acetates forming M:L 1:2 complexes, characterized by IR, 1H and 13C NMR spectra and elemental analyses. The coordination mode of the ligands is discussed and four-coordinate, pseudo-tetrahedral structures are suggested. (author)

  17. Comprehensive aging assessment of circuit breakers and relays for Nuclear Plant Aging Research (NPAR) Program Phase II

    International Nuclear Information System (INIS)

    The Phase I study - NUREG/CR-4715, BNL-NUREG-52017 AN,RV, An Aging Assessment Of Relays And Circuit Breakers And System Interactions, identified relays and circuit breakers used in nuclear plants, failure mechanisms of these relays and circuit breakers, that some failure mechanisms are age related, and that failure of safety systems is possible from relays and circuit breaker failures if adequate maintenance and testing are not performed. It also proposed some potential inspection, surveillance and condition monitoring methods to detect significant aging methods prior to loss of safety function. The objectives of Phase II are to: (1) identify and characterize aging and service wear effects of circuit breakers and relays which, if unchecked, could impair plant safety; (2) identify and develop methods of inspection, surveillance, and condition monitoring, and of evaluating residual life of circuit breakers and relays, which will assure timely detection of significant aging effects prior to loss of safety function; (3) evaluate the effectiveness of storage, maintenance, repair and replacement practices in mitigating the rate and extent of degradation in circuit breakers and relays caused by aging and service wear. The research results will be utilized to identify inspection, surveillance and condition monitoring needs, define inspection intervals, provide service life parameter limits and service life prediction methodology

  18. Failure analysis of leakage on titanium tubes within heat exchangers in a nuclear power plant. Part II: Mechanical degradation

    International Nuclear Information System (INIS)

    Serious failure incidents like clogging, quick thinning, and leakage frequently occurred on lots of titanium tubes of heat exchangers in a nuclear power plant in China. In the Part I of the whole failure analysis study with totally two parts, factors mainly involving three kinds of electrochemical corrosions were investigated, including galvanic corrosion, crevice corrosion, and hydrogen-assisted corrosion. In the current Part II, through microscopically analyzing the ruptures on the leaked tubes by scanning electron microscopy (SEM) and energy dispersive spectrometry (EDS), another four causes dominantly lying in the aspect of mechanical degradation were determined - clogging, erosion, mechanical damaging, and fretting. Among them, the erosion effect was the primary one, thus the stresses it exerted on the tube wall were also supplementarily evaluated by finite element method (FEM). Based on the analysis results, the different degradation extents and morphologies by erosion on the tubes when they were clogged by different substances such as seashell, rubber debris, and sediments were compared, and relevant mechanisms were discussed. Finally, countermeasures were put forward as well. (Copyright copyright 2012 WILEY-VCH Verlag GmbH and Co. KGaA, Weinheim)

  19. Does Brazil need new nuclear power plants?

    Energy Technology Data Exchange (ETDEWEB)

    Carvalho, Joaquim F. de [Graduate Program on Energy, University of Sao Paulo, SP (Brazil)], E-mail: jfdc35@uol.com.br; Sauer, Ildo L. [Graduate Program on Energy, University of Sao Paulo, SP (Brazil); Institute of Electrotechnics and Energy, University of Sao Paulo, SP (Brazil)], E-mail: illsauer@iee.usp.br

    2009-04-15

    In October 2008, the Brazilian Government announced plans to invest US$212 billion in the construction of nuclear power plants, totaling a joint capacity of 60,000 MW. Apart from this program, officials had already announced the completion of the construction of the nuclear plant Angra III; the construction of large-scale hydroelectric plans in the Amazon and the implantation of natural gas, biomass and coal thermoelectric plants in other regions throughout the country. Each of these projects has its proponents and its opponents, who bring forth concerns and create heated debates in the specialized forums. In this article, some of these concerns are explained, especially under the perspective of the comparative analysis of costs involved. Under such merit figures, the nuclear option, when compared to hydro plants, combined with conventional thermal and biomass-fueled plants, and even wind, to expand Brazilian power-generation capacity, does not appear as a priority.

  20. Does Brazil need new nuclear power plants?

    Energy Technology Data Exchange (ETDEWEB)

    De Carvalho, Joaquim F. [Graduate Program on Energy, University of Sao Paulo, SP (Brazil); Sauer, Ildo L. [Graduate Program on Energy, University of Sao Paulo, SP (Brazil)]|[Institute of Electrotechnics and Energy, University of Sao Paulo, SP (Brazil)

    2009-04-15

    In October 2008, the Brazilian Government announced plans to invest US$212 billion in the construction of nuclear power plants, totaling a joint capacity of 60,000 MW. Apart from this program, officials had already announced the completion of the construction of the nuclear plant Angra III; the construction of large-scale hydroelectric plans in the Amazon and the implantation of natural gas, biomass and coal thermoelectric plants in other regions throughout the country. Each of these projects has its proponents and its opponents, who bring forth concerns and create heated debates in the specialized forums. In this article, some of these concerns are explained, especially under the perspective of the comparative analysis of costs involved. Under such merit figures, the nuclear option, when compared to hydro plants, combined with conventional thermal and biomass-fueled plants, and even wind, to expand Brazilian power-generation capacity, does not appear as a priority. (author)

  1. Nuclear

    International Nuclear Information System (INIS)

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

  2. The role of the decomissioning process on the development of the Brazilian nuclear program

    International Nuclear Information System (INIS)

    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)

  3. MESODIF-II: a variable trajectory plume segment model to assess ground-level air concentrations and deposition of effluent releases from nuclear power facilities

    International Nuclear Information System (INIS)

    MESODIF-II is a variable trajectory plume segment atmospheric transport model designed to predict normalized air concentrations and deposition of radioactive, but otherwise non-reactive, effluents released from one or two levels over the same position in an xy-plane. In such a model, calculated particle trajectories vary as synoptic scale wind varies. At all sampling times the particles are connected to form a segmented plume centerline; the lateral and vertical dimensions of the plume are determined by a parameterization of turbulence scale diffusion. The model development arose from the need to assess the radiological effects of routine operations of commercial nuclear power reactors. The purpose of the present document is to make MESODIF-II and its peripheral programs available to those who wish to use it directly. The theory and mathematics in the model are explained. A user's guide, which treats not only MESODIF-II descriptively, but also other programs that have to be used to generate the input wind and stability data is included. Two other peripheral programs that are used in conjunction with MESODIF-II are also described. One is Program Stagg, the other is Program RERITE. A complete test run of MESODIF-II is included, as is the complete code for the program and the control cards used on the CDC-6400. A glossary for the MESODIF-II code, and a reference list arealso provided

  4. CFD analysis of a regular sector of the ITER vacuum vessel. Part II: Thermal-hydraulic effects of the nuclear heat load

    OpenAIRE

    Zanino, Roberto; Subba, Fabio; Savoldi, Laura; Corpino, Sabrina

    2013-01-01

    The 3D Computational Fluid Dynamic (CFD) steady state analysis of the regular sector #5 of the ITER vacuum vessel (VV) is presented in these two companion papers using the commercial software ANSYS-FLUENT®. The pure hydraulic analysis, concentrating on flow field and pressure drop, is presented in Part I. This Part II focuses on the thermal-hydraulic analysis of the effects of the nuclear heat load. Being the VV classified as safety important component, an accurate thermal-hydraulic analysis ...

  5. Mortality pattern of the surrounding population of the Central Nuclear Almirante Alvaro Alberto / 1986 to 2007

    International Nuclear Information System (INIS)

    This paper aims to update two earlier epidemiological studies on the mortality profile of the resident population in the influence area of the Central Nuclear Almirante Alvaro Alberto. The main objective is analyze and compare the profile of mortality among the population classified in areas with the distance from source of exposure in three strata. Municipalities contained within a radius of 30 km of the nuclear power, neighboring municipalities, contained within a radius of 30 to 50 km, municipalities contained within 50 to 100 km, beyond Cabo Frio, which presents similar characteristics to the municipality of Angra dos Reis

  6. Nanocellulose/nanobentonite composite anchored with multi-carboxyl functional groups as an adsorbent for the effective removal of Cobalt(II) from nuclear industry wastewater samples.

    Science.gov (United States)

    Anirudhan, T S; Deepa, J R; Christa, J

    2016-04-01

    A novel adsorbent, poly(itaconic acid/methacrylic acid)-grafted-nanocellulose/nanobentonite composite [P(IA/MAA)-g-NC/NB] with multi carboxyl functional groups for the effective removal of Cobalt(II) [Co(II)] from aqueous solutions. The adsorbent was characterized using FTIR, XRD, SEM-EDS, AFM and potentiometric titrations before and after adsorption of Co(II) ions. FTIR spectra revealed that Co(II) adsorption on to the polymer may be due to the involvement of COOH groups. The surface morphological changes were observed by the SEM images. The pH was optimized as 6.0. An adsorbent dose of 2.0g/L found to be sufficient for the complete removal of Co(II) from 100mg/L at room temperature. Pseudo-first-order and pseudo-second-order models were tested to describe kinetic data and adsorption of Co(II) follows pseudo-second-order model. The equilibrium attained at 120min. Isotherm studies were conducted and data were analyzed using Langmuir, Freundlich and Sips isotherm models and best fit was Sips model. Thermodynamic study confirmed endothermic and physical nature of adsorption of the Co(II) onto the adsorbent. Desorption experiments were done with 0.1MHCl proved that without significant loss in performance adsorbent could be reused for six cycles. The practical efficacy and effectiveness of the adsorbent were tested using nuclear industrial wastewater. A double stage batch adsorption system was designed from the adsorption isotherm data of Co(II) by constructing operating lines. PMID:26844393

  7. Accumulation of radioactive corrosion products on steel surfaces of VVER-type nuclear reactors. II. 60Co

    International Nuclear Information System (INIS)

    In the case of intact fuel claddings, the predominant source of radioactivity in the primary circuits of water-cooled nuclear reactors is the activation of corrosion products in the core. The most important corrosion product radionuclides in the primary coolant of pressurized water reactors (PWRs) are 60Co, 58Co, 51Cr, 54Mn, 59Fe (as well as 110mAg in some Soviet-made VVER-type reactor). The second part of this series is focused on the complex studies of the formation and build-up of 60Co-containing species on an austenitic stainless steel type 08X18H10T (GOST 5632-61) and magnetite-covered carbon steel often to be used in Soviet-planned VVERs. The kinetics and mechanism of the cobalt accumulation were studied by a combination (coupling) of an in situ radiotracer method and voltammetry in a model solution of the primary circuit coolant. In addition, independent techniques such as X-ray photoelectron spectroscopic (XPS) and ICP-OES are also used to analyze the chemical state of Co species in the passive layer formed on stainless steel as well as the chemical composition of model solution. The experimental results have revealed that: (i) The passive behavior of the austenitic stainless steel at open-circuit conditions, the slightly alkaline pH and the reducing water chemistry can be considered to be optimal to minimize the 60Co contamination. (ii) The highly potential dependent deposition of various Co-oxides at E>1.10 V (vs. RHE) offers a unique possibility to elaborate a novel electrochemical method for the decrease or removal of cobalt traces from borate-containing coolants contaminated with 60Co and/or 58Co radionuclides

  8. Control of Angra 1' PZR by a fuzzy rule base build through genetic programming

    International Nuclear Information System (INIS)

    There is an optimum pressure for the normal operation of nuclear power plant reactors and thresholds that must be respected during transients, what make the pressurizer an important control mechanism. Inside a pressurizer there are heaters and a shower. From their actuation levels, they control the vapor pressure inside the pressurizer and, consequently, inside the primary circuit. Therefore, the control of the pressurizer consists in controlling the actuation levels of the heaters and of the shower. In the present work this function is implemented through a fuzzy controller. Besides the efficient way of exerting control, this approach presents the possibility of extracting knowledge of how this control is been made. A fuzzy controller consists basically in an inference machine and a rule base, the later been constructed with specialized knowledge. In some circumstances, however, this knowledge is not accurate, and may lead to non-efficient results. With the development of artificial intelligence techniques, there wore found methods to substitute specialists, simulating its knowledge. Genetic programming is an evolutionary algorithm particularly efficient in manipulating rule base structures. In this work genetic programming was used as a substitute for the specialist. The goal is to test if an irrational object, a computer, is capable, by it self, to find out a rule base reproducing a pre-established actuation levels profile. The result is positive, with the discovery of a fuzzy rule base presenting an insignificant error. A remarkable result that proves the efficiency of the approach. (author)

  9. Proceeding of the Scientific Meeting and Presentation on Basic Research in Nuclear of the Scientific and Technology Part II : Nuclear Chemistry; Process Technology and Radioactive Waste Management; Environment

    International Nuclear Information System (INIS)

    Scientific Meeting and Presentation on Basic Research in Nuclear Science and Technology is a routine activity was held by Yogyakarta Nuclear Research Centre, National Atomic Energy Agency (BATAN) for monitoring the research activity which achieved in BATAN. The Proceeding contains a proposal about basic which has Nuclear Chemistry, Process Technology, Radioactive Waste Management and Environment. This proceeding is the second part from two part which published in series. There are 61 articles which have separated index

  10. Proceedings of the Scientific Meeting and Presentation on Basic Researchin Nuclear Science and Technology part II: Nuclear Chemistry, Process Technology, Radioactive Waste Management and Environment

    International Nuclear Information System (INIS)

    Scientific Meeting and Presentation on Basic Research in Nuclear Scienceand Technology is an annual activity held by Centre for Research and Development of Advanced Technology, National Nuclear Energy Agency, for monitoring research activities achieved by the Agency. The papers presented in the meeting were collected into proceedings. These are the second part of the proceedings that contain 71 articles in the fields of nuclear chemistry, process technology, radioactive waste management, and environment (PPIN).

  11. Chiral Nuclear Dynamics II

    CERN Document Server

    Rho, Mannque

    2008-01-01

    This is the sequel to the first volume to treat in one effective field theory framework the physics of strongly interacting matter under extreme conditions. This is vital for understanding the high temperature phenomena taking place in relativistic heavy ion collisions and in the early Universe, as well as the high-density matter predicted to be present in compact stars. The underlying thesis is that what governs hadronic properties in a heat bath and/or a dense medium is hidden local symmetry which emerges from chiral dynamics of light quark systems and from the duality between QCD in 4D and

  12. Report of the joint seminar on heavy-ion nuclear physics and nuclear chemistry in the energy region of tandem accelerators (II)

    International Nuclear Information System (INIS)

    A meeting of the second joint seminar on Heavy-Ion Nuclear Physics and Nuclear Chemistry in the Energy Region of Tandem Accelerators was held after an interval of two years at the Tokai Research Establishment of the JAERI, for three days from January 9 to 11, 1986. In the seminar, about 70 nuclear physicists and nuclear chemists of JAERI and other Institutes participated, and 38 papers were presented. These include general reviews and topical subjects which have been developed intensively in recent years, as well as the new results obtained by using the JAERI tandem accelerator. This report is a collection of the papers presented to the seminar. (author)

  13. Proceedings of the Scientific Meeting and Presentation on Basic Research in Nuclear of the Science and Technology part II : Nuclear Chemistry and Process Technology

    International Nuclear Information System (INIS)

    The Scientific Meeting and Presentation on Basic Research in Nuclear Science and Technology is a routine activity held by Centre for Accelerator Technology and Material Process, National Nuclear Energy Agency, for monitoring the research activity which achieved in National Nuclear Energy Agency. The Meeting was held in Yogyakarta on July 10, 2007. The proceedings contains papers presented on the meeting about Nuclear Chemistry and Process Technology and there are 47 papers which have separated index. The proceedings is the second part of the three parts which published in series. (PPIN)

  14. FINESSE: study of the issues, experiments and facilities for fusion nuclear technology research and development. Interim report. Volume II

    International Nuclear Information System (INIS)

    The Nuclear Fusion Issues chapter contains a comprehensive list of engineering issues for fusion reactor nuclear components. The list explicitly defines the uncertainties associated with the engineering option of a fusion reactor and addresses the potential consequences resulting from each issue. The next chapter identifies the fusion nuclear technology testing needs up to the engineering demonstration stage

  15. FINESSE: study of the issues, experiments and facilities for fusion nuclear technology research and development. Interim report. Volume II

    Energy Technology Data Exchange (ETDEWEB)

    Abdou, M.

    1984-10-01

    The Nuclear Fusion Issues chapter contains a comprehensive list of engineering issues for fusion reactor nuclear components. The list explicitly defines the uncertainties associated with the engineering option of a fusion reactor and addresses the potential consequences resulting from each issue. The next chapter identifies the fusion nuclear technology testing needs up to the engineering demonstration stage. (MOW)

  16. Vulnerability Assessment of the nuclear power plant Vandellos II before a tornado; Evaluacion de vulnerabilidad de C.N. Vandellos II ante tornado

    Energy Technology Data Exchange (ETDEWEB)

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

    2010-07-01

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

  17. Co-Chairs’ Summary of Technical Session 3C. Data Compilation Tools for Supporting Nuclear Forensic Interpretation II

    International Nuclear Information System (INIS)

    This session continued with presentations (following Technical Session 2D) focused on the application of national nuclear forensics libraries as a data compilation tool for nuclear forensic interpretation. The experience of States that have developed a national nuclear forensics library is valuable to other States that are contemplating developing such a library as one possible means to assist in determining the origin and history of nuclear material and other radioactive material. Information relevant to a national nuclear forensics library may already exist within the States, having been collected at other times for other purposes. A national nuclear forensics library is one possible way for States to help ensure the security of nuclear material and other radioactive material for which they are responsible

  18. Proceeding of the Scientific Meeting and Presentation on Basic Research of Nuclear Science and Technology: Book II. Nuclear Chemistry, Process Technology, and Radioactive Waste Processing and Environment

    International Nuclear Information System (INIS)

    The proceeding contains papers presented on Scientific Meeting and Presentation on on Basic Research of Nuclear Science and Technology, held in Yogyakarta, 25-27 April 1995. This proceeding is second part of two books published for the meeting contains papers on nuclear chemistry, process technology, and radioactive waste management and environment. There are 62 papers indexed individually. (ID)

  19. Nuclear power data 2016

    International Nuclear Information System (INIS)

    The brochure on nuclear power data 2016 covers the following topics: (I) nuclear power in Germany: nuclear power plants in Germany; shut-down and decommissioned nuclear power plants, gross electricity generation, primary energy consumption; (II) nuclear power worldwide: nuclear electricity production, nuclear power plants.

  20. Genesis of the Brazilian nuclear power plants program

    International Nuclear Information System (INIS)

    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)

  1. 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)

    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 102 for Ni to 105 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)

  2. Análise económica das políticas municipais espelhadas nas GOP do concelho de Angra do Heroísmo

    OpenAIRE

    Toste, Vera Borges

    2016-01-01

    Com este trabalho pretende-se analisar as políticas municipais do concelho de Angra do Heroísmo, as quais são espelhadas nas Grandes Opções do Plano da Câmara Municipal. Estas definem os objetivos estratégicos para o desenvolvimento económico e social do município e compreendem uma base móvel de quatro anos. Este planeamento estratégico torna-se viável através das propostas de Orçamento da entidade. Como tal, é importante esclarecer e relacionar estes temas, bem como o seu funcionamento na CM...

  3. Comparisons between the extensive radiological measurements made during start up of units I and II of the CNAAA NPP

    International Nuclear Information System (INIS)

    Integrated tests (IT) applied to the Units I and II of the CNAAA NPP (Angra dos Reis, Rio de Janeiro) were part of the comprehensive test programme to which the plants were submitted before authorization for commercial operation is issued. The so called IT tests included operation at zero power and subsequent power levels (the power escalation) until the nominal operation power. This paper reports and compares the results of systematic neutron and gamma dose-rate measurements performed inside and outside the reactor containment of the units, during the start-up phase of the operation of the plants, for different power levels of the reactors. (author)

  4. 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

  5. Heterogeneity of nuclear estrogen-binding sites in the rat uterus: a simple method for the quantitation of type I and type II sites by [3H]estradiol exchange

    International Nuclear Information System (INIS)

    Estrogen administration to mature-ovariectomized rats causes the activation or stimulation of secondary nuclear estrogen-binding sites (type II) in the uterus which can interfere with estrogen receptor (type I) measurement. Earlier reports from our laboratory have shown that quantitation of type I sites in the presence of the type II site is very difficult and can only be achieved by graphic analysis of saturation curves which employ a wide range (0.4-40 NM) of [3H]estradiol concentrations in nuclear exchange assay. The studies presented in this manuscript describe simple methods which can be used to separately quantitate both nuclear estrogen-binding sites using a single concentration of [3H]estradiol. Since the nuclear type II site does not bind [3H]estradiol in the presence of reducing agent, type I sites can be easily quantitated by incubating nuclei (37 C for 30 min) in Tris-EDTA buffer containing 0.1-1.00 mM dithiothreitol using a single saturating concentration of [3H]estradiol. Conversely, a single concentration of [3H]estradiol (40-80 nM) can be used to quantitate the nuclear type II site by incubating nuclei in Tris-EDTA buffer under conditions (4 C for 60 min) which do not measure occupied nuclear estrogen receptor. Therefore, by using the appropriate buffer system, type I and type II sites can be easily separated in mixed binding systems. In addition, we also demonstrate that Nafoxidine does not bind to the nuclear type II site. Therefore, it can be used as a competitive inhibitor of [3H]estradiol binding to type I sites and permit the measurement of type II sites without interference from type I sites. These techniques should be applicable to autoradiographic or fluorescence studies which cannot discriminate between steroid binding to these two classes of nuclear estrogen-binding sites

  6. Cyclam Derivatives with a Bis(phosphinate) or a Phosphinato-Phosphonate Pendant Arm: Ligands for Fast and Efficient Copper(II) Complexation for Nuclear Medical Applications.

    Science.gov (United States)

    David, Tomáš; Kubíček, Vojtěch; Gutten, Ondrej; Lubal, Přemysl; Kotek, Jan; Pietzsch, Hans-Jürgen; Rulíšek, Lubomír; Hermann, Petr

    2015-12-21

    Cyclam derivatives bearing one geminal bis(phosphinic acid), -CH2PO2HCH2PO2H2 (H2L(1)), or phosphinic-phosphonic acid, -CH2PO2HCH2PO3H2 (H3L(2)), pendant arm were synthesized and studied as potential copper(II) chelators for nuclear medical applications. The ligands showed good selectivity for copper(II) over zinc(II) and nickel(II) ions (log KCuL = 25.8 and 27.7 for H2L(1) and H3L(2), respectively). Kinetic study revealed an unusual three-step complex formation mechanism. The initial equilibrium step leads to out-of-cage complexes with Cu(2+) bound by the phosphorus-containing pendant arm. These species quickly rearrange to an in-cage complex with cyclam conformation II, which isomerizes to another in-cage complex with cyclam conformation I. The first in-cage complex is quantitatively formed in seconds (pH ≈5, 25 °C, Cu:L = 1:1, cM ≈ 1 mM). At pH >12, I isomers undergo nitrogen atom inversion, leading to III isomers; the structure of the III-[Cu(HL(2))] complex in the solid state was confirmed by X-ray diffraction analysis. In an alkaline solution, interconversion of the I and III isomers is mutual, leading to the same equilibrium isomeric mixture; such behavior has been observed here for the first time for copper(II) complexes of cyclam derivatives. Quantum-chemical calculations showed small energetic differences between the isomeric complexes of H3L(2) compared with analogous data for isomeric complexes of cyclam derivatives with one or two methylphosphonic acid pendant arm(s). Acid-assisted dissociation proved the kinetic inertness of the complexes. Preliminary radiolabeling of H2L(1) and H3L(2) with (64)Cu was fast and efficient, even at room temperature, giving specific activities of around 70 GBq of (64)Cu per 1 μmol of the ligand (pH 6.2, 10 min, ca. 90 equiv of the ligand). These specific activities were much higher than those of H3nota and H4dota complexes prepared under identical conditions. The rare combination of simple ligand synthesis, very

  7. Insulin-like growth factor-II, phosphatidylinositol 3-kinase, nuclear factor-kappaB and inducible nitric-oxide synthase define a common myogenic signaling pathway.

    Science.gov (United States)

    Kaliman, P; Canicio, J; Testar, X; Palacín, M; Zorzano, A

    1999-06-18

    Insulin-like growth factors (IGFs) are potent inducers of skeletal muscle differentiation and phosphatidylinositol (PI) 3-kinase activity is essential for this process. Here we show that IGF-II induces nuclear factor-kappaB (NF-kappaB) and nitric-oxide synthase (NOS) activities downstream from PI 3-kinase and that these events are critical for myogenesis. Differentiation of rat L6E9 myoblasts with IGF-II transiently induced NF-kappaB DNA binding activity, inducible nitric-oxide synthase (iNOS) expression, and nitric oxide (NO) production. IGF-II-induced iNOS expression and NO production were blocked by NF-kappaB inhibition. Both NF-kappaB and NOS activities were essential for IGF-II-induced terminal differentiation (myotube formation and expression of skeletal muscle proteins: myosin heavy chain, GLUT 4, and caveolin 3), which was totally blocked by NF-kappaB or NOS inhibitors in rat and human myoblasts. Moreover, the NOS substrate L-Arg induced myogenesis in the absence of IGFs in both rat and human myoblasts, and this effect was blocked by NOS inhibition. Regarding the mechanisms involved in IGF-II activation of NF-kappaB, PI 3-kinase inhibition prevented NF-kappaB activation, iNOS expression, and NO production. Moreover, IGF-II induced, through a PI 3-kinase-dependent pathway, a decrease in IkappaB-alpha protein content that correlated with a decrease in the amount of IkappaB-alpha associated with p65 NF-kappaB. PMID:10364173

  8. Communication and surrounding of Asco and Vandellos II nuclear power plants; La comunicacion y el entorno de las centrales de Asco y Vandellos II

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2004-07-01

    The Asco and Vandellos-II power plants have always been integrated into the regions where they are located, and they take an active part in the development of surrounding towns through quality employment provided by our facilities, social and cultural support and aid to development promoted by regional councils. Communication to media is a corporate priority defined in our strategic plant, to ensure openness, rigour and punctuality. We also attend to the visitors who want to learn more about our facilities in the visitor center, and we have agreements with agrarian institutions in the area so that students can de practical training in the farms we own for agricultural production. (Author)

  9. Análise da evolução da ocupação e uso do solo no Concelho de Angra do Heroismo. Influência nos movimentos de terreno e de vertente

    OpenAIRE

    Silva, Carmen Sofia Rocha

    2010-01-01

    Mestrado em Arquitectura Paisagista - Instituto Superior de Agronomia This master dissertation aims to study mass movements dynamics and its classification, as well as the identification of the factors that control and initiate them. These concepts and knowledge were applied to the district of Angra do Heroísmo in Terceira´s island of the Azores in order to elaborate a map where the areas showing susceptibility to mass movements were identified. This identification and mapping of mass move...

  10. Development and Validation of Methodology to Model Flow in Ventilation Systems Commonly Found in Nuclear Facilities - Phase II

    Energy Technology Data Exchange (ETDEWEB)

    Strons, Philip [Argonne National Lab. (ANL), Argonne, IL (United States); Bailey, James L. [Argonne National Lab. (ANL), Argonne, IL (United States); Davis, John [Argonne National Lab. (ANL), Argonne, IL (United States); Grudzinski, James [Argonne National Lab. (ANL), Argonne, IL (United States); Hlotke, John [Argonne National Lab. (ANL), Argonne, IL (United States)

    2016-03-01

    In this report we present the results of the Phase II analysis and testing of the flow patterns encountered in the Alpha Gamma Hot Cell Facility (AGHCF), as well as the results from an opportunity to expand upon field test work from Phase I by the use of a Class IIIb laser. The addition to the Phase I work is covered before proceeding to the results of the Phase II work, followed by a summary of findings.

  11. Orphan nuclear receptor small heterodimer partner inhibits angiotensin II-stimulated PAI-1 expression in vascular smooth muscle cells

    OpenAIRE

    Lee, Kyeong-Min; Seo, Hye-Young; Kim, Mi-Kyung; Min, Ae-Kyung; Ryu, Seong-Yeol; Kim, Yoon-Nyun; Park, Young Joo; Choi, Hueng-Sik; Lee, Ki-Up; Park, Wan-Ju; Park, Keun-Gyu; Lee, In-Kyu

    2009-01-01

    Angiotensin II is a major effector molecule in the development of cardiovascular disease. In vascular smooth muscle cells (VSMCs), angiotensin II promotes cellular proliferation and extracellular matrix accumulation through the upregulation of plasminogen activator inhibitor-1 (PAI-1) expression. Previously, we demonstrated that small heterodimer partner (SHP) represses PAI-1 expression in the liver through the inhibition of TGF-β signaling pathways. Here, we investigated whether SHP inhibite...

  12. CFD analysis of a regular sector of the ITER vacuum vessel. Part II: Thermal-hydraulic effects of the nuclear heat load

    International Nuclear Information System (INIS)

    The 3D Computational Fluid Dynamic (CFD) steady state analysis of the regular sector no. 5 of the ITER vacuum vessel (VV) is presented in these two companion papers using the commercial software ANSYS-FLUENT®. The pure hydraulic analysis, concentrating on flow field and pressure drop, is presented in Part I. This Part II focuses on the thermal-hydraulic analysis of the effects of the nuclear heat load. Being the VV classified as safety important component, an accurate thermal-hydraulic analysis is mandatory to assess the capability of the water coolant to adequately remove the nuclear heat load on the VV. Based on the recent re-evaluation of the nuclear heat load, the steady state conjugate heat transfer problem is solved in both the solid and fluid domains. Hot spots turn out to be located on the surface of the inter-modular keys and blanket support housings, with the computed peak temperature in the sector reaching ∼290 °C. The computed temperature of the wetted surfaces is well below the coolant saturation temperature and the temperature increase of the water coolant at the outlet of the sector is of only a few °C. In the high nuclear heat load regions the computed heat transfer coefficient typically stays above the 500 W/m2 K target

  13. Co-Chairs’ Summary of Technical Session 3F. Nuclear Forensic Science: Synergies with Other Disciplines II

    International Nuclear Information System (INIS)

    Nuclear forensic science is a relatively new discipline but may be traced to many older and established branches of science and technology. The aim of nuclear forensics is to categorize and characterize seized nuclear material and other radioactive material, to determine the origins and intended use of the materials, and to provide evidence for a potential criminal prosecution. Often existing and proven analytical techniques from other disciplines, such as radiochemistry and traditional forensics, are used to extract such information from the seized radioactive material or evidence contaminated with radionuclides. In addition, new approaches, applications and techniques may be developed to improve nuclear forensic conclusions. The session first summarized recent work using nanoscale morphology and sample impurities as nuclear forensic signatures. The session continued with a report on the use of laser ionization time of flight mass spectrometry to acquire rapid uranium isotope ratios. The session concluded with the presentation of the results and progress of two IAEA coordinated research projects, aimed at the application of nuclear forensics in combating illicit trafficking of nuclear material and other radioactive material

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

    International Nuclear Information System (INIS)

    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)

  15. Occupational exposure analysis at the unit 1 of Almirante Alvaro Alberto nuclear power plant

    International Nuclear Information System (INIS)

    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)

  16. Computational Analysis of Nuclear Safety Parameters of 3 MW TRIGA Mark-II Research Reactor Based on Evaluated Nuclear Data Libraries JENDL-3.3 and ENDF/B-VII.0

    Energy Technology Data Exchange (ETDEWEB)

    Khan, Jahirul Haque [Bangladesh Atomic Energy Commission, Dhaka (Bangladesh)

    2013-07-01

    The objective of this study is to explain the main nuclear safety parameters of 3 MW TRIGA Mark-II Research Reactor at AERE, Savar, Dhaka, Bangladesh from the viewpoint of reactor safety and also reactor operator. The most important nuclear reactor physics safety parameters are power distribution, power peaking factors, shutdown margin, control rod worth, excess reactivity and fuel temperature reactivity coefficient. These parameters are calculated using the chain of the computer codes the SRAC-PIJ for cell calculation based on neutron transport theory and the SRAC-CITATION for core calculation based on neutron diffusion equation. To achieve this objective the TRIGA model is developed by the 3-D diffusion code SRAC-CITATION based on the group constants that come from the collision probability transport code SRAC-PIJ. In this study the evaluated nuclear data libraries JENDL-3.3 and ENDF/B-VII.0 are used. The calculated most important reactor physics parameters are compared to the safety analysis report (SAR) values as well as earlier published MCNP results (numerically benchmark). It was found that the calculated results show a good agreement between the said libraries. Besides, in most cases the calculated results reveal a reasonable agreement with the SAR values (by General Atomic) as well as the MCNP results. In addition, this analysis can be used as the inputs for thermal-hydraulic calculations of the TRIGA fresh core in the steady state and pulse mode operation. Because of power peaking factors, power distributions and temperature reactivity coefficients are the most important reactor safety parameters for normal operation and transient safety analysis in research as well as in power reactors. They form the basis for technical specifications and limitations for reactor operation such as loading pattern limitations for pulse operation (in TRIGA). Therefore, this analysis will be very important to develop the nuclear safety parameters data of 3 MW TRIGA Mark-II

  17. Computational Analysis of Nuclear Safety Parameters of 3 MW TRIGA Mark-II Research Reactor Based on Evaluated Nuclear Data Libraries JENDL-3.3 and ENDF/B-VII.0

    International Nuclear Information System (INIS)

    The objective of this study is to explain the main nuclear safety parameters of 3 MW TRIGA Mark-II Research Reactor at AERE, Savar, Dhaka, Bangladesh from the viewpoint of reactor safety and also reactor operator. The most important nuclear reactor physics safety parameters are power distribution, power peaking factors, shutdown margin, control rod worth, excess reactivity and fuel temperature reactivity coefficient. These parameters are calculated using the chain of the computer codes the SRAC-PIJ for cell calculation based on neutron transport theory and the SRAC-CITATION for core calculation based on neutron diffusion equation. To achieve this objective the TRIGA model is developed by the 3-D diffusion code SRAC-CITATION based on the group constants that come from the collision probability transport code SRAC-PIJ. In this study the evaluated nuclear data libraries JENDL-3.3 and ENDF/B-VII.0 are used. The calculated most important reactor physics parameters are compared to the safety analysis report (SAR) values as well as earlier published MCNP results (numerically benchmark). It was found that the calculated results show a good agreement between the said libraries. Besides, in most cases the calculated results reveal a reasonable agreement with the SAR values (by General Atomic) as well as the MCNP results. In addition, this analysis can be used as the inputs for thermal-hydraulic calculations of the TRIGA fresh core in the steady state and pulse mode operation. Because of power peaking factors, power distributions and temperature reactivity coefficients are the most important reactor safety parameters for normal operation and transient safety analysis in research as well as in power reactors. They form the basis for technical specifications and limitations for reactor operation such as loading pattern limitations for pulse operation (in TRIGA). Therefore, this analysis will be very important to develop the nuclear safety parameters data of 3 MW TRIGA Mark-II

  18. Uncertainties in nuclear transition matrix elements for neutrinoless $\\beta \\beta $ decay II: the heavy Majorana neutrino mass mechanism

    CERN Document Server

    Rath, P K; Raina, P K; Chaturvedi, K; Hirsch, J G

    2011-01-01

    Employing four different parametrization of the pairing plus multipolar type of effective two-body interaction and three different parametrizations of Jastrow-type of short range correlations, the uncertainties in the nuclear transition matrix elements $M_{N}^{(0\

  19. Dynamic Isotope Power System (DIPS) Applications Study. Volume II. Nuclear Integrated Multimission Spacecraft (NIMS) design definition. Final report

    International Nuclear Information System (INIS)

    The design requirements for the Nuclear Integrated Multimission Spacecraft. (NIMS) are discussed in detail. The requirements are a function of mission specifications, payload, control system requirements, electric system specifications, and cost limitations

  20. Dynamic Isotope Power System (DIPS) Applications Study. Volume II. Nuclear Integrated Multimission Spacecraft (NIMS) design definition. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Prickett, W. Z.

    1979-11-01

    The design requirements for the Nuclear Integrated Multimission Spacecraft. (NIMS) are discussed in detail. The requirements are a function of mission specifications, payload, control system requirements, electric system specifications, and cost limitations. (LCL)

  1. Plasma Physics and Controlled Nuclear Fusion Research. Proceedings of the Third International Conference on Plasma Physics and Controlled Nuclear Fusion Research. Vol. II

    International Nuclear Information System (INIS)

    Proceedings of the Third Conference on this matter convened by the IAEA and held at Novosibirsk, 1-7 August 1968. The meeting was attended by more than 400 participants from 24 countries. Contents: (Vol. I) Summary of the Conference (4 papers); Shock waves (8 papers); Toroidal confinement I (Tokamak, Zeta, etc.) (11 papers); Toroidal confinement II (Multipoles, etc.) (9 papers); Toroidal confinement III (Stellarators) (9 papers); Drift waves and non-linear phenomena (15 papers); Toroidal confinement IV (Theory) , Laser-produced plasmas, Astron (9 papers). (Vol. II) Plasma focus, Confinement by neutral gas. Instabilities and waves (16 papers); Open-ended systems I (Mirrors) (11 papers); HF heating, confinement and stabilization (13 papers); Open-ended systems II (Theta pinch) (12 papers); Turbulent heating, Beam-plasma interaction (10 papers). Each paper is in its original language (80 English, 37 Russian and 10 French) and is preceded by an abstract in English with one in the original language if this is not English. The discussions are in English. (author)

  2. Report on the NOK's request for the removal of time limits on the licence for the operation of the Beznau II nuclear power plant

    International Nuclear Information System (INIS)

    The Swiss Federal Council limited the licence for the operation of the nuclear power reactor Beznau-II (KKB-II) to December 31, 2004. According to the legal requirements for the removal of the time limitation for the operational licence, the power plant operator (NOK) fulfilled a Periodic Safety Review. The Federal Agency for the Safety of Nuclear Installations (HSK) examined the request based on the documents delivered by NOK. In October 2002 the German-Swiss Commission for the Safety of Nuclear Installations (DSK) wrote a report considering three evaluation domains: a) application of the former HSK considerations; b) operational experience, especially the results of the surveillance programme on ageing and the maintenance aspects associated with it; c) for the future, retaining of the radiological consequences on German states during normal operation as well as after incidents according to the present German ordinances. HSK delivered a report giving its assessment of the operation of the Beznau nuclear power plant (KKB). According to its report, the plant exhibits a very high degree of technical and organisational safety. During the past 10 years the plant has been operated in a safe manner and the installation has been improved as a result of continuous modernisation. As no safety-relevant incidents have been noted, HSK concludes that the time limitation of the operational licence of KKB-II can be removed. On its part, DSK expects that the monitoring of ageing should become a continuous practice at the plant. The following areas are recommended for special attention: reactor thermal power; release of radioactive materials to the environment; safety report; full scope simulator; release of radioactive materials to drainage water; surveillance of leakage of the primary circuit; extension of the operational life to over 40 years; probabilistic analysis of earthquakes. As far as the radioactive exposition of the neighbouring German regions during normal operation is

  3. Cd(II) complexes with different nuclearity and dimensionality based on 3-hydrazino-4-amino-1,2,4-triazole

    Energy Technology Data Exchange (ETDEWEB)

    Xu, Cai-Xia; Zhang, Jian-Guo, E-mail: zjgbit@bit.edu.cn; Yin, Xin; Jin, Xin; Li, Tong; Zhang, Tong-Lai; Zhou, Zun-Ning

    2015-03-15

    A series of zero- to two-dimensional Cd(II) coordination compounds have been synthesized by the reaction of Cd(II) salts and 3-hydrazino-4-amino-1,2,4-triazole di-hydrochloride (HATr·2HCl). [CdCl{sub 2}(HATr){sub 2}] (1) and [Cd{sub 2}Cl{sub 4}(HATr){sub 2}(H{sub 2}O){sub 2}] (2) have discrete mononuclear and binuclear structures, respectively. [Cd(HATr){sub 2}(ClO{sub 4}){sub 2}]{sub n} (3) presents polymeric 1-D chain and [Cd{sub 2}(NO{sub 3}){sub 2}Cl{sub 2}(HATr){sub 2}]{sub n} (4) shows 2-D frameworks. All Cd(II) ions exhibit distorted octahedral configurations in 1–3, whilst both hexa and heptacoordinated Cd(II) are formed in 4. The HATr ligands adopt chelating coordinated mode in 1, while tri-dentate bridging–chelating mode in 2–4. The chloride ion is a mono-coordinated ligand in 1 and 2, but it bridges two adjacent metal ions in 4. Furthermore, thermal behaviors have been investigated and the results reveal that all complexes have good thermal stability. The impact sensitivity test indicates that complex 3 is sensitive to impact stimuli. - Graphical abstract: Four Cd(II) complexes based on 3-hydrazino-4-amino-1,2,4-triazole ligands exhibit diverse structures from mononuclear to 2D networks. - Highlights: • Cd(II) complexes containing 3-hydrazino-4-amino-1,2,4-triazole ligands. • Mononuclear, binuclear, 1-D and 2-D structures. • Good thermal stability. • Thermal decomposition kinetics.

  4. Cd(II) complexes with different nuclearity and dimensionality based on 3-hydrazino-4-amino-1,2,4-triazole

    International Nuclear Information System (INIS)

    A series of zero- to two-dimensional Cd(II) coordination compounds have been synthesized by the reaction of Cd(II) salts and 3-hydrazino-4-amino-1,2,4-triazole di-hydrochloride (HATr·2HCl). [CdCl2(HATr)2] (1) and [Cd2Cl4(HATr)2(H2O)2] (2) have discrete mononuclear and binuclear structures, respectively. [Cd(HATr)2(ClO4)2]n (3) presents polymeric 1-D chain and [Cd2(NO3)2Cl2(HATr)2]n (4) shows 2-D frameworks. All Cd(II) ions exhibit distorted octahedral configurations in 1–3, whilst both hexa and heptacoordinated Cd(II) are formed in 4. The HATr ligands adopt chelating coordinated mode in 1, while tri-dentate bridging–chelating mode in 2–4. The chloride ion is a mono-coordinated ligand in 1 and 2, but it bridges two adjacent metal ions in 4. Furthermore, thermal behaviors have been investigated and the results reveal that all complexes have good thermal stability. The impact sensitivity test indicates that complex 3 is sensitive to impact stimuli. - Graphical abstract: Four Cd(II) complexes based on 3-hydrazino-4-amino-1,2,4-triazole ligands exhibit diverse structures from mononuclear to 2D networks. - Highlights: • Cd(II) complexes containing 3-hydrazino-4-amino-1,2,4-triazole ligands. • Mononuclear, binuclear, 1-D and 2-D structures. • Good thermal stability. • Thermal decomposition kinetics

  5. Protective role of Nigella sativa against experimentally induced type-II diabetic nuclear damage in Wistar rats

    OpenAIRE

    T. J. Sheikh; D. V. Joshi; B. J. Patel

    2013-01-01

    Aim: To identify the anti-mutagenic effect of Nigella sativa on the experimentally induced chronic diabetes (type – II) in Wistar rats.Materials and Methods: The anti-mutagenic effect was evaluated in Nigella sativa treated diabetic rats against the streptozotocin - nicotinamide (STZ-NA) (at a dose rate of 45-110 i.p mg/kg b.wt for 90 days) induced type-II diabetes mellitus using bone marrow micronucleus tests. The antioxidant status was tested by estimating the serum levels of lipid peroxida...

  6. Nuclear data sensitivity and uncertainty for the Canadian supercritical water-cooled reactor II: Full core analysis

    International Nuclear Information System (INIS)

    Highlights: • H-2, Pu-239, and Th-232 make large contributions to SCWR modelling sensitivity. • H-2, Pu-239, and Th-232 make large contributions to SCWR modelling uncertainty. • Isotopes of Zr make large contributions to SCWR modelling uncertainty. - Abstract: Uncertainties in nuclear data are a fundamental source of uncertainty in reactor physics calculations. To determine their contribution to uncertainties in calculated reactor physics parameters, a nuclear data sensitivity and uncertainty study is performed on the Canadian supercritical water reactor (SCWR) concept. The nuclear data uncertainty contributions to the neutron multiplication factor keff are 6.31 mk for the SCWR at the beginning of cycle (BOC) and 6.99 mk at the end of cycle (EOC). Both of these uncertainties have a statistical uncertainty of 0.02 mk. The nuclear data uncertainty contributions to Coolant Void Reactivity (CVR) are 1.0 mk and 0.9 mk for BOC and EOC, respectively, both with statistical uncertainties of 0.1 mk. The nuclear data uncertainty contributions to other reactivity parameters range from as low as 3% of to as high as ten times the values of the reactivity coefficients. The largest contributors to the uncertainties in the reactor physics parameters are Pu-239, Th-232, H-2, and isotopes of zirconium

  7. New Nuclear Materials Including Non Metallic Fuel Elements. Vol. II. Proceedings of the Conference on New Nuclear Materials Technology, Including Non Metallic Fuel Elements

    International Nuclear Information System (INIS)

    One of the major aims of the International Atomic Energy Agency in furthering the peaceful uses of atomic energy is to encourage the development of economical nuclear power. Certainly, one of the more obvious methods of producing economical nuclear power is the development of economical fuels that can be used at high temperatures for long periods of time, and which have sufficient strength and integrity to operate under these conditions without permitting the release of fission products. In addition it is desirable that after irradiation these new fuels be economically reprocessed to reduce further the cost of the fuel cycle. As nuclear power becomes more and more competitive with conventional power the interest in new and more efficient higher-temperature fuels naturally increases rapidly. For these reasons, the Agency organized a Conference on New Nuclear Materials Technology, Including Non-Metallic Fuel Elements, which was held from 1 to 5 July 1963 at the International Hotel, Prague, with the assistance and co-operation of the Government of the Czechoslovak Socialist Republic. A total of 151 scientists attended, from 23 countries and 4 international organizations. The participants heard and discussed more than 60 scientific papers. The Agency wishes to thank the scientists who attended this Conference for their papers and for many spirited discussions that truly mark a successful meeting. The Agency wishes also to record its gratitude for the assistance and generous hospitality accorded the Conference, the participants and the Agency's staff by the Government of the Czechoslovak Socialist Republic and by the people of Prague. The scientific information contained in these Proceedings should help to quicken the pace of progress in the fabrication of new and m ore economical fuels, and it is hoped that these proceedings will be found useful to all workers in this and related fields

  8. Nuclear Technology. Course 32: Nondestructive Examination (NDE) Techniques II. Module 32-5, Fundamentals of Eddy Current Testing.

    Science.gov (United States)

    Espy, John

    This fifth in a series of six modules for a course titled Nondestructive Examination (NDE) Techniques II describes the fundamental concepts applicable to eddy current testing in general. The module follows a typical format that includes the following sections: (1) introduction, (2) module prerequisites, (3) objectives, (4) notes to…

  9. Biologically relevant mono- and di-nuclear manganese II/III/IV complexes of mononegative pentadentate ligands

    DEFF Research Database (Denmark)

    Baffert, Carole; Collomb, Marie-Nöelle; Deronzier, Alain; Kjærgaard-Knudsen, Sanne; Latour, Jean-Marc; Lund, Kirsten H.; McKenzie, Christine J.; Mortensen, Martin; Nielsen, Lars Preuss; Thorup, Niels

    Manganese(II) complexes of mononegative pentadentate N4O ligands [Mn2(mgbpen)(2)(H2O)(2)](ClO4)(2) (1), (mgbpen(-) = N-methyl-N'-glycyl-N,N'-bis(2-pyridylmethyl)ethane-1,2-diamine) and [Mn-2(bzgbpen)(2)(H2O)(2)](ClO4)(2) ( 2), (bzgbpen(-)=N-benzyl-N'-glycyl-N,N'-bis(2-pyridylmethyl)ethane-1......,2-diamine) have been prepared. The crystal structure of the Mn(II)-aqua complex of 1, shows it to be dimeric via (mu-kappaO)-bridging through one carboxylate oxygen atom of each of the two ligands. The non-coordinated carboxylate oxygen atoms are H-bonded to the water ligands on the adjacent Mn ion. The......-bridged dimanganese(III) and di-mu-oxo-dimanganese(II) complexes, depending on solvent. The [Mn(III)-OR](+), R = H or CH3 complexes are generated in water or methanol, respectively, and are potentially useful spectroscopic models for active Mn-lipoxygenases. In acetonitrile, di-mu-oxo-dimanganese(II) complexes are...

  10. Cd(II) complexes with different nuclearity and dimensionality based on 3-hydrazino-4-amino-1,2,4-triazole

    Science.gov (United States)

    Xu, Cai-Xia; Zhang, Jian-Guo; Yin, Xin; Jin, Xin; Li, Tong; Zhang, Tong-Lai; Zhou, Zun-Ning

    2015-03-01

    A series of zero- to two-dimensional Cd(II) coordination compounds have been synthesized by the reaction of Cd(II) salts and 3-hydrazino-4-amino-1,2,4-triazole di-hydrochloride (HATr·2HCl). [CdCl2(HATr)2] (1) and [Cd2Cl4(HATr)2(H2O)2] (2) have discrete mononuclear and binuclear structures, respectively. [Cd(HATr)2(ClO4)2]n (3) presents polymeric 1-D chain and [Cd2(NO3)2Cl2(HATr)2]n (4) shows 2-D frameworks. All Cd(II) ions exhibit distorted octahedral configurations in 1-3, whilst both hexa and heptacoordinated Cd(II) are formed in 4. The HATr ligands adopt chelating coordinated mode in 1, while tri-dentate bridging-chelating mode in 2-4. The chloride ion is a mono-coordinated ligand in 1 and 2, but it bridges two adjacent metal ions in 4. Furthermore, thermal behaviors have been investigated and the results reveal that all complexes have good thermal stability. The impact sensitivity test indicates that complex 3 is sensitive to impact stimuli.

  11. Nuclear Technology. Course 32: Nondestructive Examination (NDE) Techniques II. Module 32-6, Operation of Eddy Current Test Equipment.

    Science.gov (United States)

    Espy, John; Selleck, Ben

    This sixth in a series of six modules for a course titled Nondestructive Examination (NDE) Techniques II details eddy current examination of steam generator tubing. The module follows a typical format that includes the following sections: (1) introduction, (2) module prerequisites, (3) objectives, (4) notes to instructor/student, (5) subject…

  12. Transit and absorption of nuclear industry derivatives by marine biota

    International Nuclear Information System (INIS)

    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 60Co, 137Cs and 131I 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 85Sr by ''snail'' (Strombus pugilis) and by ''barnacle'' (Megabalanus tintinnabulum). The remobilization of 60Co 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)

  13. ATMS_Phase_II: a standalone code for counting non-overlapping high-density nuclear tracks

    Science.gov (United States)

    Khayat, Omid

    2014-02-01

    In this paper we focus on counting and density measurements of non-overlapping high-density nuclear track images. This paper is a continuum of another paper of the author introducing ATMS software which has been particularly developed for overlapping nuclear tracks. Here, as the second phase of the ATMS software, a hybrid algorithm is presented for counting the tracks according to user parameter initialization, template inserting and correlation estimation to initially detect nuclear track candidates, then to evaluate geometrical and contextual features of track candidates and finally a decision-making process according to the user's sensitivity considerations. The presented hybrid algorithm is verified and validated by a database containing 100 randomly selected Alpha track images captured from the surface of CR-39 polycarbonate detectors irradiated by environmental Alpha particles emitted from Rn-222 near a copper mine around Anarak city.

  14. In situ leaching of a nuclear rubblized copper ore body. Volume II. Detailed design, calculations, and procedures

    International Nuclear Information System (INIS)

    Detailed descriptions of technical and economic evaluations are presented for a feasibility study on the use of nuclear explosive technology for exploitation of deep-lying copper deposits. The approach considered involves the emplacement of nuclear explosives below the water table in a deep-lying copper deposit. The explosives are detonated to rubblize the rock, then oxygen and water are passed through the rubblized zone to leach out the copper as copper sulfate. The copper sulfate is then brought to the surface where liquid ion exchange and electrowinning is used to remove the copper. (JGB)

  15. Nuclear model parameter testing for nuclear data evaluation (Reference Input Parameter Library: Phase II). Summary report of the second research co-ordination meeting

    International Nuclear Information System (INIS)

    This report summarizes the results and recommendations of the Second Research Coordination Meeting on Testing and Improvement of the Reference Input Parameter Library: Phase II. A primary aim of this meeting was to review progress in the CRP work, to review results of testing the library, to establish the RIPL-2 format and to decide on the contents of the library. The actions were agreed with an aim to complete the project by the end of 2001. Separate abstracts were prepared for 10 individual papers

  16. Nuclear model parameter testing for nuclear data evaluation (Reference Input Parameter Library: Phase II). Summary report of the third research co-ordination meeting

    International Nuclear Information System (INIS)

    This report summarises the results and recommendations of the third Research Co-ordination Meeting on improving and testing the Reference Input Parameter Library: Phase II. A primary aim of the meeting was to review the achievements of the CRP, to assess the testing of the library and to approve the final contents. Actions were approved that will result in completion of the file and a draft report by the end of February 2002. Full release of the library is scheduled for July 2002. (author)

  17. The funding of dangerous nuclear projects. Nuclear trade and safety: the role of French private banks. What are we talking about?

    International Nuclear Information System (INIS)

    Countries which export nuclear technologies, notably France, have developed mechanisms of financial support to incite private banks to finance the sale of reactors to foreign countries, notably EPRs in the case of France. After having briefly introduced this issue, and dealing with the French case, this publication indicates the concerned banks, and outlines that some of them finance nuclear projects which have been assessed by NGOs as dangerous in terms of nuclear safety. It notably presents the Angra 3 project in Brazil: its cost, its planning, its main safety problems (obsolete technology, building authorization awarded without any actual safety analysis, situation of conflict of interest for the Brazilian regulator). It also presents the Jaitapur project in India in which Areva is as well involved: costs, funding, planning, main risks (seismic risk area, safety level much lower than the one required in France, controversy on the impact study). The document finally explains why banks must not fund nuclear projects

  18. 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}.

  19. Evolution of seismic monitoring systems of nuclear power plants. Improvements and practical applications; Evolucion de los sistemas de vigilancia sismica de las II.NN. Mejoras introducidas y aplicaciones practicas

    Energy Technology Data Exchange (ETDEWEB)

    Sanchez Cabanero, J. G.; Jimenez Juan, A.

    2010-07-01

    The II. NN. Spanish have a seismic monitoring system (SVS) covering two objectives relevant to nuclear security: determining earthquake leave operation, and specific data that serve to limit or reduce the uncertainties associated with the seismic source, the site and design. Since its construction, the major SVS II. NN. have been equipped with the best time of seismic instrumentation to record earthquakes strong, but with limited resolution for recording in the free field and appropriately moderate earthquakes.

  20. Alterations in hepatic mRNA expression of phase II enzymes and xenobiotic transporters after targeted disruption of hepatocyte nuclear factor 4 alpha.

    Science.gov (United States)

    Lu, Hong; Gonzalez, Frank J; Klaassen, Curtis

    2010-12-01

    Hepatocyte nuclear factor 4 alpha (HNF4a) is a liver-enriched master regulator of liver function. HNF4a is important in regulating hepatic expression of certain cytochrome P450s. The purpose of this study was to use mice lacking HNF4a expression in liver (HNF4a-HNull) to elucidate the role of HNF4a in regulating hepatic expression of phase II enzymes and transporters in mice. Compared with male wild-type mice, HNF4a-HNull male mouse livers had (1) markedly lower messenger RNAs (mRNAs) encoding the uptake transporters sodium taurocholate cotransporting polypeptide, organic anion transporting polypeptide (Oatp) 1a1, Oatp2b1, organic anion transporter 2, sodium phosphate cotransporter type 1, sulfate anion transporter 1, sodium-dependent vitamin C transporter 1, the phase II enzymes Uridine 5'-diphospho (UDP)-glucuronosyltransferase (Ugt) 2a3, Ugt2b1, Ugt3a1, Ugt3a2, sulfotransferase (Sult) 1a1, Sult1b1, Sult5a1, the efflux transporters multidrug resistance-associated protein (Mrp) 6, and multidrug and toxin extrusion 1; (2) moderately lower mRNAs encoding Oatp1b2, organic cation transporter (Oct) 1, Ugt1a5, Ugt1a9, glutathione S-transferase (Gst) m4, Gstm6, and breast cancer resistance protein; but (3) higher mRNAs encoding Oatp1a4, Octn2, Ugt1a1, Sult1e1, Sult2a2, Gsta4, Gstm1-m3, multidrug resistance protein (Mdr) 1a, Mrp3, and Mrp4. Hepatic signaling of nuclear factor E2-related factor 2 and pregnane X receptor appear to be activated in HNF4a-HNull mice. In conclusion, HNF4a deficiency markedly alters hepatic mRNA expression of a large number of phase II enzymes and transporters, probably because of the loss of HNF4a, which is a transactivator and a determinant of gender-specific expression and/or adaptive activation of signaling pathways important in hepatic regulation of these phase II enzymes and transporters. PMID:20935164