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Sample records for angra ii nuclear

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

    International Nuclear Information System (INIS)

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

  2. 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)

  3. 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)

  4. 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

  5. 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)

  6. 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)

  7. 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.)

  8. 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)

  9. 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)

  10. 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)

  11. 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)

  12. 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)

  13. 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.

  14. 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)

  15. 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

  16. 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

  17. 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)

  18. 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)

  19. 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.

  20. 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)

  1. 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)

  2. 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

  3. 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)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2001-07-01

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

  5. 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.

  6. 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)

  7. 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)

  8. 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.

  9. 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)

  10. 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)

  11. 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)

  12. 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)

  13. On the applicability of a correlation of critical heat flux prediction for advanced nuclear fuel from Angra-1; Confirmando a aplicabilidade de uma correlacao de previsao do fluxo de calor critico para o combustivel nuclear avancado de Angra-1

    Energy Technology Data Exchange (ETDEWEB)

    Palheiros, Franklin L.; Gomes, Sydney [Industrias Nucleares do Brasil SA, Rio de Janeiro, RJ (Brazil). Gerencia de Analise Tecnica do Combustivel]. E-mail: franklin@inb.gov.br; sydney@inb.gov.br

    2005-07-01

    To establish the nuclear core operation limits it is requested that the safe condition of heat transfer between the fuel rod and the primary system coolant shall be well known. Those limits are set based on the critical heat flux marking the upper limit of nucleate boiling where the interaction of the coolant causes a departure from nucleate boiling - DNB [1]. For the new fuel type (16NGF) to be used at the Angra-1, the Kori-2, and the Krsko sites, the Critical Heat Flux must be characterized as well. Compared to the 16x16STD fuel (a 25+ year old Westinghouse design), the 16NGF design has many new features, including: three Intermediate Flow Mixers (IFM's) were added in the grid spans 4, 5 and 6 to improve the mixing behavior and consequently the thermal margin; an optimized vane pattern was used as well as an improved vane design (RFA Mod-1 vane). Others important thermal characteristics are the use of an optimized fuel rod diameter- from the U/H ratio point of view (0.360'' instead of 0.374'') and others features (Reference 2).Therefore, to demonstrate the applicability of an existing CHF correlation for the 16NGF design, two tests were performed in the Columbia University's Heat Transfer Research Facility, New York City (HTRF). Denominated Tests number 112 and number 113, they employed a 5x5 bundle array with a heated length of 12 ft. and cosine axial power shape. The purpose of this paper is then to present the data analysis from the 16NGF CHF tests and demonstrate, through a statistical evaluation, that the resulting data when evaluated is 'poolable' (combinable) with the WRB-2 database. In so doing, it can be thus stated that the WRB-2 correlation is applicable to 16 NGF Fuel Assemblies. (author)

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

    Directory of Open Access Journals (Sweden)

    Diego Santos Vieira de JESUS

    2011-11-01

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

  15. Neutrinos ANGRA: new simulation results and status of the detector construction

    Energy Technology Data Exchange (ETDEWEB)

    Anjos, J.C.; Azzi, G.L.; Gama, R.; Lima Junio, H.P.; Schiappacassa, A.; Silva, R.M.; Souza, M.N. [Centro Brasileiro de Pesquisas Fisicas (CBPF), Rio de janeiro, RJ (Brazil); Gonzalez, L.F.G.; Kemp, E.; Lima, L.B. [Universidade Estadual de Campinas (UNICAMP), SP (Brazil); Alvarenga, T.A.; Andrade, L.M.; Cerqueira, A.S.; Dornelas, T.I.; Nobrega, R.A. [Universidade Federal de Juiz de Fora (UFJF), MG (Brazil); Chimenti, P. [Universidade Federal do ABC (UFABC), SP (Brazil); Farias, P.C.; Pepe, I.M.; Rodowanski, I.J.; Simas, E.F. [Universidade Federal da Bahia (UFBA), BA (Brazil); Nunokawa, H. [Pontificia Universidade Catolica do Rio de Janeiro (PUC-Rio), RJ (Brazil); Guedes, G.P. [Universidade Estadual de Feira de Santana, BA (Brazil); Valdiviesso, G.A. [Universidade Federal de Alfenas (UNIFAL), MG (Brazil)

    2013-07-01

    Full text: The Neutrinos Angra experiment is aimed at developing an antineutrino detector for monitoring nuclear reactors. The experiment will use the Angra II nuclear reactor, with 4 GW of thermal power as source of antineutrinos and a 1 ton water Cherenkov detector, placed at 30 m of the reactor core, to look for inverse beta decay interactions. With this configuration a few thousand antineutrino interactions per day are foreseen. As the antineutrino flux is proportional to the thermal power we expect to be able to monitor the reactor activity by measuring the antineutrino rate at our detector. The main difficulty however is to overcome the very intense cosmic ray background at sea level. We will present new results obtained with a full GEANT4 simulation of the main sources of background and of the antineutrino signal and the analysis strategy to allow signal/ background separation. The Angra detector will consist of a target tank surrounded by 3 other water tanks instrumented with photomultipliers and that will serve as cosmic neutron shield and muon veto. We will show the status of the detector construction and the results obtained at CBPF where the tanks are now deployed for preliminary tests and calibration. The full detector system is expected to be deployed in Angra dos Reis by the end of 2013. (author)

  16. 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)

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

    Energy Technology Data Exchange (ETDEWEB)

    Azevedo, Carlos Vicente Goulart de; Palmieri, Elcio Tadeu; Aronne, Ivan Dionysio [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)], e-mail: cvga@cdtn.br, e-mail: etp@cdtn.br, e-mail: aroneid@cdtn.br

    2009-07-01

    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)

  18. 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)

  19. 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.)

  20. 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

  1. 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

  2. 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)

  3. 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)

  4. 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

  5. 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)

  6. 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)

  7. 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)

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

    Directory of Open Access Journals (Sweden)

    Diego Santos Vieira de JESUS

    2011-11-01

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

  9. 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)

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

    Energy Technology Data Exchange (ETDEWEB)

    Silva, Corbiniano

    2013-07-01

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

  11. 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

  12. 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...

  13. 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)

  14. 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)

  15. 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

  16. 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.

  17. 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)

  18. 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)

  19. 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.)

  20. 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}.

  1. 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

  2. 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

  3. 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.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2013-07-01

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

  5. 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)

  6. 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.)

  7. 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.

  8. 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

  9. 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)

  10. 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)

  11. 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)

  12. 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)

  13. 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)

  14. 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.

  15. 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.)

  16. Axial blanket for 16NGF Angra 1 fuel type

    Energy Technology Data Exchange (ETDEWEB)

    Sadde, Luciano Martins; Faria, Eduardo Fernandes [Industrias Nucleares do Brasil (INB), Resende, RJ (Brazil)]. E-mails: sadde@inb.gov.br; faria@inb.gov.br; Sang-Keun You [Korea Nuclear Fuel Co. Ltd. (KNFC), Taejon (Korea, Republic of)]. E-mail: skyou@knfc.co.kr

    2007-07-01

    Angra-1, Kori-2 and Krsko are nuclear power plants with the same design. However, the fuel assemblies have some differences in design due to the countries strategies and the differences in the fabrication process. The 16NGF (16x16 Next Generation Fuel) was developed by INB, KNFC and Westinghouse in order to be used in these three nuclear power plants and the 'Axial Blanket' is one of the new features for the 16NGF design. The main purpose of the Axial Blanket Optimization study is to determine which axial blanket enrichment and length would provide the better fuel cycle cost benefit. All of the calculations were performed using Gadolinium as Burnable Absorber and solid pellets type for Axial Blanket. The results indicate 1.8 w/o U235 enrichment and 8 inches length as the best option of Axial Blanket from the fuel cycle cost benefit standpoint. The economy is about 1.8%. The difference in the reload cost in the range between 1.5 and 2.6 w/o U235 enrichment and for the 6 and 8 inches length is not so significant. Due that, from the Fq limit standpoint and also for longer cycle length requirements, a higher axial blanket enrichment (2.6 w/o) and shorter length (6 inches) is recommended. (author)

  17. 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)

  18. 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.)

  19. 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)

  20. 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...

  1. 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)

  2. 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)

  3. 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)

  4. 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)

  5. 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

  6. 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)

  7. 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)

  8. 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)

  9. 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)

  10. 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

  11. 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...

  12. 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.)

  13. 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.

  14. 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

  15. Nuclear instrumentation system operating experience and nuclear instrument testing in the EBR-II

    Energy Technology Data Exchange (ETDEWEB)

    Yingling, G. E.; Curran, R. N.

    1980-01-01

    In March of 1972 three wide range nuclear channels were purchased from Gulf Atomics Corporation and installed in EBR-II as a test. The three channels were operated as a test until April 1975 when they became a permanent part of the reactor shutdown system. Also described are the activities involved in evaluating and qualifying neutron detectors for LMFBR applications. Included are descriptions of the ANL Components Technology Division Test Program and the EBR-II Nuclear Instrument Test Facilities (NITF) used for the in-reactor testing and a summary of program test results from EBR-II.

  16. 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

  17. Databases and tools for nuclear astrophysics applications. BRUSsels Nuclear LIBrary (BRUSLIB), Nuclear Astrophysics Compilation of REactions II (NACRE II) and Nuclear NETwork GENerator (NETGEN)

    Science.gov (United States)

    Xu, Y.; Goriely, S.; Jorissen, A.; Chen, G. L.; Arnould, M.

    2013-01-01

    An update of a previous description of the BRUSLIB + NACRE package of nuclear data for astrophysics and of the web-based nuclear network generator NETGEN is presented. The new version of BRUSLIB contains the latest predictions of a wide variety of nuclear data based on the most recent version of the Brussels-Montreal Skyrme-Hartree-Fock-Bogoliubov model. The nuclear masses, radii, spin/parities, deformations, single-particle schemes, matter densities, nuclear level densities, E1 strength functions, fission properties, and partition functions are provided for all nuclei lying between the proton and neutron drip lines over the 8 ≤ Z ≤ 110 range, whose evaluation is based on a unique microscopic model that ensures a good compromise between accuracy, reliability, and feasibility. In addition, these various ingredients are used to calculate about 100 000 Hauser-Feshbach neutron-, proton-, α-, and γ-induced reaction rates based on the reaction code TALYS. NACRE is superseded by the NACRE II compilation for 15 charged-particle transfer reactions and 19 charged-particle radiative captures on stable targets with mass numbers A < 16. NACRE II features the inclusion of experimental data made available after the publication of NACRE in 1999 and up to 2011. In addition, the extrapolation of the available data to the very low energies of astrophysical relevance is improved through the systematic use of phenomenological potential models. Uncertainties in the rates are also evaluated on this basis. Finally, the latest release v10.0 of the web-based tool NETGEN is presented. In addition to the data already used in the previous NETGEN package, it contains in a fully documented form the new BRUSLIB and NACRE II data, as well as new experiment-based radiative neutron capture cross sections. The full new versions of BRUSLIB, NACRE II, and NETGEN are available electronically from the nuclear database at http://www.astro.ulb.ac.be/NuclearData. The nuclear material is presented in

  18. 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

  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. 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

  1. Databases and tools for nuclear astrophysics applications BRUSsels Nuclear LIBrary (BRUSLIB), Nuclear Astrophysics Compilation of REactions II (NACRE II) and Nuclear NETwork GENerator (NETGEN)

    CERN Document Server

    Xu, Yi; Jorissen, Alain; Chen, Guangling; Arnould, Marcel; 10.1051/0004-6361/201220537

    2012-01-01

    An update of a previous description of the BRUSLIB+NACRE package of nuclear data for astrophysics and of the web-based nuclear network generator NETGEN is presented. The new version of BRUSLIB contains the latest predictions of a wide variety of nuclear data based on the most recent version of the Brussels-Montreal Skyrme-HFB model. The nuclear masses, radii, spin/parities, deformations, single-particle schemes, matter densities, nuclear level densities, E1 strength functions, fission properties, and partition functions are provided for all nuclei lying between the proton and neutron drip lines over the 8<=Z<=110 range, whose evaluation is based on a unique microscopic model that ensures a good compromise between accuracy, reliability, and feasibility. In addition, these various ingredients are used to calculate about 100000 Hauser-Feshbach n-, p-, a-, and gamma-induced reaction rates based on the reaction code TALYS. NACRE is superseded by the NACRE II compilation for 15 charged-particle transfer react...

  2. 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

  3. 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

  4. 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

  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. 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)

  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. 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)

  10. 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.)

  11. 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)

  12. Radionuclides determination in the Sargassum algae located in the Saco de Piraquara de Fora - Angra dos Reis - Rio de Janeiro - Brazil; Determinacao de radionuclideos na alga marinha bentonica localizada no Saco de Piraquara de Fora, Angra dos Reis/RJ

    Energy Technology Data Exchange (ETDEWEB)

    Arantes, Patricia V.S.; Cardoso, Sergio N.M. [ELETRONUCLEAR S.A., Angra dos Reis, RJ (Brazil). Lab. de Monitoracao Ambiental

    1999-11-01

    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 {sup 58} Co, {sup 60} Co and {sup 54} Mn, which are activated corrosion products from structural materials of the primary system and {sup 134} Cs and {sup 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 {sup 58} Co, {sup 60} Co, {sup 54} Mn, {sup 134} Cs and {sup 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

  13. 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)

  14. 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)

  15. 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…

  16. 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

  17. 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.)

  18. 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.)

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

    Directory of Open Access Journals (Sweden)

    Leandro Cardoso PEDERNEIRAS

    2012-06-01

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

  20. 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.)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2011-10-26

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

  2. Toward higher nuclearity: tetranuclear cobalt(II) metallogrid exhibiting spin crossover.

    Science.gov (United States)

    Wu, Shu-Qi; Wang, Yi-Tong; Cui, Ai-Li; Kou, Hui-Zhong

    2014-03-01

    Supramolecular strategy was employed to achieve the highest nuclearity Co(II) cluster exhibiting spin-crossover (SCO) behavior. Magnetic susceptibility characterization of the Co4(II) complex shows that two different spin-transition processes occur. The SCO behavior is directed by the partially deprotonated polydentate ligand, which favors the structural distortion required by the spin transition. PMID:24555696

  3. 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

  4. 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

  5. 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)

  6. 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.

  7. 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

  8. 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)

  9. 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)

  10. 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...

  11. 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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1978-10-10

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

  16. 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.)

  17. 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

  18. 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

  19. 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

  20. 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)

  1. 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

  2. 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

  3. 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)

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

    Science.gov (United States)

    Lugmair, G. W.; Marti, K.

    1977-01-01

    Isotope ratios and age estimations are presented for the ultramafic pyroxenite Angra dos Reis meteorite. A pyroxene-phosphate internal isochron age of 4.55 plus or minus 0.04 eons was obtained, in agreement with reported Pb-Pb ages. It is suggested that Sm-146 decay led to an increase in the ratio of Nd-142 to Nd-144 in pyroxene, which is greater than the ratio of the Nd isotopes in phosphates. The effect of Pu-244 on the fission xenon components in pyroxene and phosphate is examined. The ratios of Pu-244 to Nd, U-238, and Th-232 are compared for pyroxene and phosphate separates. The exposure age of the meteorite, as obtained by the Kr-81 to Kr-83 method, was found to be 55.5 plus or minus 1.2 million years.

  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. Angra 1 high burnup fuel behaviour under reactivity initiated accident conditions

    Energy Technology Data Exchange (ETDEWEB)

    Gomes, Daniel de Souza; Silva, Antonio Teixeira e, E-mail: dsgomes@ipen.b, E-mail: teixeira@ipen.b [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

    2011-07-01

    The 16x16 NGF (Next Generation Fuel) fuel assembly, comprising of highly corrosive-resistant ZIRLO clad fuel rods, been replacing the current 16x16 Standard (16STD) fuel assembly in the Angra 1, a pressurized water reactor, with a net output of 626 MWe. The 16x16 NGF fuel assemblies are designed for a peak rod average burnup of up to 75 GWd/MTU, thus improving fuel utilization and reducing spent fuel storage issues. A design basis accident, the Reactivity Initiated Accident (RIA), became a concern for a further increase in burnup as the simulated RIA tests revealed a lower enthalpy threshold for fuel failure. Two fuel performance codes, FRAPCON and FRAPTRAN, were used to predict high burnup behavior of Angra 1, during an RIA. The maximum average linear fuel rating used was 17.62 KW/m. The FRAPCON 3.4 code was applied to simulate the steady-state performance of the 16 NGF fuel rods up to a burnup of 55 GWd/MTU. With FRAPTRAN-1.4 the fuel behavior was simulated for an RIA power pulse of 4.5 ms (FHWH), and enthalpy peak of 130 Cal/g. With FRAPCON-3.4, the corrosion and hydrogen pickup characteristics of the advanced ZIRLO clad fuel rods were added to the code by modifying the actual corrosion model for Zircaloy-4 through the multiplication of empirical factors, which were appropriate to each alloy, and by means of reducing the current hydrogen pickup fraction. (author)

  7. 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)

  8. 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

  9. 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...

  10. 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

  11. 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)

  12. 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 ...

  13. 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)

  14. Pol II-directed short RNAs suppress the nuclear export of mRNA.

    Science.gov (United States)

    Komarova, Tatiana V; Schwartz, Anton M; Frolova, Olga Y; Zvereva, Anna S; Gleba, Yuri Y; Citovsky, Vitaly; Dorokhov, Yuri L

    2010-12-01

    The synthesis and subsequent nuclear export of non-coding RNA (ncRNA) directed by RNA polymerase (Pol) II is very sensitive to abiotic and biotic external stimuli including pathogen challenges. To assess whether stress-induced ncRNAs may suppress the nuclear export of mRNA, we exploited the ability of Agrobacterium tumefaciens to co-deliver Pol I, II and III promoter-based vectors for the transcription of short (s) ncRNAs, GFP mRNA or genomic RNA of plant viruses (Tobacco mosaic virus, TMV; or Potato virus X, PVX) into the nucleus of Nicotiana benthamiana cells. We showed that, in contrast to Pol I- and Pol III-derived sncRNAs, all tested Pol II-derived sncRNAs (U6 RNA, tRNA or artificial RNAs) resulted in decreased expression of GFP and host mRNA. The level of this inhibitory effect depended on the non-coding transcript length and promoter strength. Short coding RNA (scRNA) can also compete with mRNA for nuclear export. We showed that scRNA, an artificial 117-nt short sequence encoding Elastin-Like peptide element tandems with FLAG sequence (ELF) and the 318-nt N. benthamiana antimicrobial peptide thionin (defensin) gene efficiently decreased GFP expression. The stress-induced export of Pol II-derived sncRNA and scRNA into the cytoplasm via the mRNA export pathway may block nucleocytoplasmic traffic including the export of mRNA responsible for antivirus protection. Consistent with this model, we observed that Pol II-derived sncRNAs as well as scRNA, thionin and ELF strongly enhanced the cytoplasmic reproduction of TMV and PVX RNA. PMID:20953971

  15. 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.)

  16. 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

  17. 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...

  18. 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

  19. 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.

  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. 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

  2. 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

  3. 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 ...

  4. 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)

  5. 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.

  6. 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)

  7. Localization of a bacterial group II intron-encoded protein in eukaryotic nuclear splicing-related cell compartments.

    Directory of Open Access Journals (Sweden)

    Rafael Nisa-Martínez

    Full Text Available Some bacterial group II introns are widely used for genetic engineering in bacteria, because they can be reprogrammed to insert into the desired DNA target sites. There is considerable interest in developing this group II intron gene targeting technology for use in eukaryotes, but nuclear genomes present several obstacles to the use of this approach. The nuclear genomes of eukaryotes do not contain group II introns, but these introns are thought to have been the progenitors of nuclear spliceosomal introns. We investigated the expression and subcellular localization of the bacterial RmInt1 group II intron-encoded protein (IEP in Arabidopsis thaliana protoplasts. Following the expression of translational fusions of the wild-type protein and several mutant variants with EGFP, the full-length IEP was found exclusively in the nucleolus, whereas the maturase domain alone targeted EGFP to nuclear speckles. The distribution of the bacterial RmInt1 IEP in plant cell protoplasts suggests that the compartmentalization of eukaryotic cells into nucleus and cytoplasm does not prevent group II introns from invading the host genome. Furthermore, the trafficking of the IEP between the nucleolus and the speckles upon maturase inactivation is consistent with the hypothesis that the spliceosomal machinery evolved from group II introns.

  8. 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.

  9. 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

  10. 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)

  11. 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)

  12. 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)

  13. 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

  14. 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

  15. 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...

  16. 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

  17. 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.

  18. 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

  19. Modeling the Nuclear Infrared Spectral Energy Distribution of Type II Active Galactic Nuclei

    CERN Document Server

    Lira, Paulina; Wu, Yanling; Alonso-Herrero, Almudena; Alexander, David M; Ward, Martin

    2013-01-01

    We present results from model fitting to the Spectral Energy Distribution (SED) of a homogeneous sample of Seyfert II galaxies drawn from the $12\\mu$m Galaxy Sample. Imaging and nuclear flux measurements are presented in an accompanying paper (Videla et al., 2013). Here we add IRS Spitzer observations to further constrain the SEDs after careful subtraction of a starburst component. We use the library of CLUMPY torus models from Nenkova et al.~(2008ab) and also test the two-phase models recently produced by Stalevski et al.~(2012). We find that photometric and spectroscopic observations in the mid-IR (>5mu) are crucial to properly constrain the best-fit torus models. About half of our sources show clear near-IR excess of their SEDs above the best fit models. This problem can be less severe when using the Stalevski et al.~(2012) models. It is not clear what is the nature of this emission since best fitted black body temperatures are very high (~1700-2500 K) and the Type II classification of our sources would co...

  20. 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.

  1. 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.

  2. 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.

  3. 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.

  4. 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

  5. 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.

  6. 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

  7. 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...

  8. 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

  9. 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

  10. 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

  11. 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.

  12. 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)

  13. 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.)

  14. 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...

  15. 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)

  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. 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)

  18. 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...

  19. 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.)

  20. 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)

  1. Flow regimes and heat transfer modes identification in ANGRA 2 core, during small break in the primary loop with area of 100 cm{sup 2}, simulated with RELAP5 code

    Energy Technology Data Exchange (ETDEWEB)

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

    2015-07-01

    Identifying the flow regimes and the heat transfer modes is important for the analysis of accidents such as the Loss-of-Coolant Accident (LOCA). The aim of this paper is to identify the flow regimes, the heat transfer modes, and the correlations used in the RELAP5/MOD3.2.gama code in ANGRA 2 during the Small-Break Loss-of-Coolant Accident (SBLOCA) with a 100cm{sup 2}-rupture area in the cold leg of primary loop. The Chapter 15 of the Final Safety Analysis Report of ANGRA 2 (FSAR - A2) reports this specific kind of accident. The results from this work demonstrated the several flow regimes and heat transfer modes that can be present in the core of ANGRA 2 during the postulated accident. (author)

  2. 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.

  3. 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.

  4. 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.)

  5. Cleavage of the angiotensin II type 1 receptor and nuclear accumulation of the cytoplasmic carboxy-terminal fragment.

    Science.gov (United States)

    Cook, Julia L; Mills, Sarah J; Naquin, Ryan T; Alam, Jawed; Re, Richard N

    2007-04-01

    Our published studies show that the distribution of the ANG II type 1 (AT(1)) receptor (AT(1)R), expressed as a enhanced yellow fluorescent fusion (YFP) protein (AT(1)R/EYFP), is altered upon cellular treatment with ANG II or coexpression with intracellular ANG II. AT(1)R accumulates in nuclei of cells only in the presence of ANG II. Several transmembrane receptors are known to accumulate in nuclei, some as holoreceptors and others as cleaved receptor products. The present study was designed to determine whether the AT(1)R is cleaved before nuclear transport. A plasmid encoding a rat AT(1)R labeled at the amino terminus with enhanced cyan fluorescent protein (CFP) and at the carboxy terminus with EYFP was employed. Image analyses of this protein in COS-7 cells, CCF-STTG1 glial cells, and A10 vascular smooth muscle cells show the two fluorescent moieties to be largely spatially colocalized in untreated cells. ANG II treatment, however, leads to a separation of the fluorescent moieties with yellow fluorescence accumulating in more than 30% of cellular nuclei. Immunoblot analyses of extracts and conditioned media from transfected cells indicate that the CFP domain fused to the extracellular amino-terminal AT(1)R domain is cleaved from the membrane and that the YFP domain, together with the intracellular cytoplasmic carboxy terminus of the AT(1)R, is also cleaved from the membrane-bound receptor. The carboxy terminus of the AT(1)R is essential for cleavage; cleavage does not occur in protein deleted with respect to this region. Overexpressed native AT(1)R (nonfusion) is also cleaved; the intracellular 6-kDa cytoplasmic domain product accumulates to a significantly higher level with ANG II treatment.

  6. 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

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

    DEFF Research Database (Denmark)

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

    2011-01-01

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

  8. Nuclear reactors and fuel cycle

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2014-07-01

    The Nuclear Fuel Center (CCN) of IPEN produces nuclear fuel for the continuous operation of the IEA-R1 research reactor of IPEN. The serial production started in 1988, when the first nuclear fuel element was delivered for IEA-R1. In 2011, CCN proudly presents the 100{sup th} nuclear fuel element produced. Besides routine production, development of new technologies is also a permanent concern at CCN. In 2005, U{sub 3}O{sub 8} were replaced by U{sub 3}Si{sub 2}-based fuels, and the research of U Mo is currently under investigation. Additionally, the Brazilian Multipurpose Research Reactor (RMB), whose project will rely on the CCN for supplying fuel and uranium targets. Evolving from an annual production from 10 to 70 nuclear fuel elements, plus a thousand uranium targets, is a huge and challenging task. To accomplish it, a new and modern Nuclear Fuel Factory is being concluded, and it will provide not only structure for scaling up, but also a safer and greener production. The Nuclear Engineering Center has shown, along several years, expertise in the field of nuclear, energy systems and correlated areas. Due to the experience obtained during decades in research and technological development at Brazilian Nuclear Program, personnel has been trained and started to actively participate in design of the main system that will compose the Brazilian Multipurpose Reactor (RMB) which will make Brazil self-sufficient in production of radiopharmaceuticals. The institution has participated in the monitoring and technical support concerning the safety, licensing and modernization of the research reactors IPEN/MB-01 and IEA-R1. Along the last two decades, numerous specialized services of engineering for the Brazilian nuclear power plants Angra 1 and Angra 2 have been carried out. The contribution in service, research, training, and teaching in addition to the development of many related technologies applied to nuclear engineering and correlated areas enable the institution to

  9. 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

  10. 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)

  11. 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

  12. 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

  13. Neutron measurements in the Vandellòs II nuclear power plant with a Bonner sphere system.

    Science.gov (United States)

    Fernández, F; Bakali, M; Tomás, M; Muller, H; Pochat, J L

    2004-01-01

    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 Vandellòs 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.

  14. 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

  15. 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)

  16. HDACs class II-selective inhibition alters nuclear receptor-dependent differentiation

    DEFF Research Database (Denmark)

    Nebbioso, Angela; Dell'Aversana, Carmela; Bugge, Anne Skovsø;

    2010-01-01

    , we show that the novel class II-selective inhibitor MC1568 interferes with the RAR- and peroxisome proliferator-activated receptor γ (PPARγ)-mediated differentiation-inducing signaling pathways. In F9 cells, this inhibitor specifically blocks endodermal differentiation despite not affecting retinoic...

  17. 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.

  18. 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

  19. 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.

  20. 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 ...

  1. 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)

  2. Description of induced nuclear fission with Skyrme energy functionals. II. Finite temperature effects

    Science.gov (United States)

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

    2015-03-01

    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 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 239Pu(n ,f ) reaction. 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 the outer fission barriers as a function of the excitation energy of the compound nucleus. We show that the coupling to the continuum induced by the finite temperature is negligible in the range of neutron energies relevant for many applications of neutron-induced fission. We prove that the concept of quantum localization introduced recently can be extended to T >0 , and we apply the method to study the interaction energy and total kinetic energy of fission fragments as a function of the temperature for the most probable fission. While large uncertainties in theoretical modeling remain, we conclude that a finite temperature nuclear density functional may provide a useful framework to obtain accurate predictions of fission fragment properties.

  3. 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 ...

  4. 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.

  5. 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)

  6. 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)

  7. 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.

  8. 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)

  9. 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)

  10. 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...

  11. 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

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

    OpenAIRE

    Tarpani José R.; Braz Maria H.P.; Bose Filho Waldek W.; Spinelli Dirceu

    2002-01-01

    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-pl...

  13. 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

  14. 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

  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. 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.

  17. 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)

  18. 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

  19. 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.

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

    Energy Technology Data Exchange (ETDEWEB)

    Mattos, Joao Roberto L. de; Dias, Marcio S. [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)], e-mail: jrmattos@cdtn.br, e-mail: marciod@cdtn.br

    2009-07-01

    The National Energy Plan 2030, issued by the Energy Research Company of the Brazilian Ministry of Mines and Energy (EPE, 2007), formalized a reference scenario for the renaissance of the nuclear option in Brazil. This scenario includes the completion of Angra 3 Nuclear Power Plant up to 2014 and the construction of four additional nuclear power plants of 1000 MWe: a fourth unit by 2020, a fifth unit by 2025 and the sixth and seventh plants by 2030. Worldwide, the energy demand and the renaissance of nuclear energy as a primary source for electric power generation are leading the industry toward new constructions as well as uprates and operational life extensions. In this new scenario the decommissioning is pushed further into the future and Brazil is not an exception, considering that Angra 1 NPP is under a process of uprating and certainly will apply for and will receive license renewals allowing its operation for 20 or more years beyond its original project. Thus, why to focus on decommissioning in the present? What is the importance of decommissioning for the development of the Brazilian nuclear industry considering the existing reactors? Should the decommissioning be considered in the design of the new nuclear power plants? What would be the decommissioning plan for the Brazilian Nuclear Power Plants? The present paper is intended to contextualize the decommissioning in the present scenarios as well as to try to answer the above questions. (author)

  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. 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

  3. 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

  4. 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)

  5. 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)

  6. 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)

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

    Science.gov (United States)

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

    2011-01-01

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

  8. 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)

  9. 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...

  10. 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.

  11. 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

  12. 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

  13. 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...

  14. 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.

  15. 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.

  16. 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.

  17. Study on the establishment of retrospective dosimetry system for nuclear radiation accident(II)

    Energy Technology Data Exchange (ETDEWEB)

    Jun, Jae Shik; Chai, Ha Seok; Lee, Jong Ok [Chungnam National Univ., Taejon (Korea, Republic of)

    1999-03-15

    This study was driven forward centering around physical techniques in retrospective dosimetry system for encountering nuclear radiation accident. The results obtained through this study are summarized as follow : the minimal facilities based on physical techniques should be assured at KINS for appropriate operation and establishment of retrospective accident dosimetry system, the necessary apparatus and man power for retrospective dose assessment by physical techniques might be operated flexibly, however, CL and TL/OSL readers should be equipped with the highest priority, a series of comparative examination of several physical techniques for retrospective dose assessment revealed that most of the irradiated materials around accident sites are usable for the dose assessment, if a priori study on the dosimetrical characteristics of those materials is preceded in accordance with the species of the collectable samples, the results of the study on the CL-dose response and radiation energy dependence of sugar and sorbitol, showed the nonlinearity in CL-dose relationship at the range of low dose(less than 5 Gy), and it led us to perform a study on the correction of the nonlinearity, and in the later study, CL output showed heavy dependence on radiation energy in the energy below around 100 keV and accordingly, a study on the correction for the energy dependence was also carried out, ve were able to obtain good results as a first attempt to carry out such corrections.

  18. 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...

  19. 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.

  20. 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.

  1. 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)

  2. Novel homo- and hetero-nuclear copper(II) complexes of tetradentate Schiff bases: Synthesis, characterization, solvent-extraction and catalase-like activity studies

    Energy Technology Data Exchange (ETDEWEB)

    Dede, Buelent [Sueleyman Demirel University, Department of Chemistry, Isparta, 32260 (Turkey)], E-mail: dbulent@fef.sdu.edu.tr; Karipcin, Fatma; Cengiz, Mustafa [Sueleyman Demirel University, Department of Chemistry, Isparta, 32260 (Turkey)

    2009-04-30

    Twelve homo- and hetero-nuclear copper(II) complexes of tetradentate Schiff base ligands containing N{sub 4} donor sets have been prepared by employing several steps. The characterization and nature of bonding of the complexes have been deduced from elemental analysis, FT-IR, molar conductivity, magnetic moment measurements and thermal analysis. The three Schiff base ligands were further identified using {sup 1}H and {sup 13}C NMR spectra. All copper(II) complexes are 1:2 electrolytes as shown by their molar conductivities ({lambda}{sub M}) in DMF and paramagnetic. The subnormal magnetic moment values of the di- and tri-nuclear complexes explained by a very strong anti-ferromagnetic interaction. The extraction ability of the ligands has been examined by the liquid-liquid extraction of selected transition metal (Mn{sup 2+}, Co{sup 2+}, Ni{sup 2+}, Cu{sup 2+}, Zn{sup 2+}, Pb{sup 2+}, Cd{sup 2+}, Hg{sup 2+}) cations. The ligands show strong binding ability toward copper(II) ion. Furthermore the homo- and hetero-nuclear copper(II) complexes were each tested for their ability to catalyse the disproportionation of hydrogen peroxide in the presence of the added base imidazole.

  3. 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

  4. 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)

  5. 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...

  6. 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.

  7. 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).

  8. 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

  9. 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)

  10. 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)

  11. 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

  12. 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

  13. 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.

  14. 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}.

  15. A Conserved Nuclear Cyclophilin Is Required for Both RNA Polymerase II Elongation and Co-transcriptional Splicing in Caenorhabditis elegans.

    Directory of Open Access Journals (Sweden)

    Jeong H Ahn

    2016-08-01

    Full Text Available The elongation phase of transcription by RNA Polymerase II (Pol II involves numerous events that are tightly coordinated, including RNA processing, histone modification, and chromatin remodeling. RNA splicing factors are associated with elongating Pol II, and the interdependent coupling of splicing and elongation has been documented in several systems. Here we identify a conserved, multi-domain cyclophilin family member, SIG-7, as an essential factor for both normal transcription elongation and co-transcriptional splicing. In embryos depleted for SIG-7, RNA levels for over a thousand zygotically expressed genes are substantially reduced, Pol II becomes significantly reduced at the 3' end of genes, marks of transcription elongation are reduced, and unspliced mRNAs accumulate. Our findings suggest that SIG-7 plays a central role in both Pol II elongation and co-transcriptional splicing and may provide an important link for their coordination and regulation.

  16. A Conserved Nuclear Cyclophilin Is Required for Both RNA Polymerase II Elongation and Co-transcriptional Splicing in Caenorhabditis elegans

    Science.gov (United States)

    Ahn, Jeong H.; Rechsteiner, Andreas; Strome, Susan; Kelly, William G.

    2016-01-01

    The elongation phase of transcription by RNA Polymerase II (Pol II) involves numerous events that are tightly coordinated, including RNA processing, histone modification, and chromatin remodeling. RNA splicing factors are associated with elongating Pol II, and the interdependent coupling of splicing and elongation has been documented in several systems. Here we identify a conserved, multi-domain cyclophilin family member, SIG-7, as an essential factor for both normal transcription elongation and co-transcriptional splicing. In embryos depleted for SIG-7, RNA levels for over a thousand zygotically expressed genes are substantially reduced, Pol II becomes significantly reduced at the 3’ end of genes, marks of transcription elongation are reduced, and unspliced mRNAs accumulate. Our findings suggest that SIG-7 plays a central role in both Pol II elongation and co-transcriptional splicing and may provide an important link for their coordination and regulation. PMID:27541139

  17. Organization and management of maintenance in the NPP's Asco and Vandellos II; Organizacion y gestion del mantenimiento en las centrales nucleares Asco y Vandellos II

    Energy Technology Data Exchange (ETDEWEB)

    Folguera, M.; Corral, A.

    2014-04-01

    The article starts with a description of the international framework that, using technical instructions, guides and guidelines, regulates the maintenance of nuclear power plants. It also outlines the characteristics of the organization and management of maintenance in the NPP's operated by ANAV. Such management is supported in a variety of processes and programs among which are: work management, training and qualification, operational experience, supervision, foreign material exclusion, work management in RP areas and outage preparation. (Author)

  18. Analysis of heavy metals from water, sediment, and tissues of Labeo angra (Hamilton, 1822), from an Ox-box lake- an wetland site from Assam, India.

    Science.gov (United States)

    Das, Suchismita; Choudhury, Shamim Sultana

    2016-01-01

    The aim of this study was to assess the regional impacts of heavy metals (Mn, Fe, Mg, Ca, Cu, Zn, Cd, Cr, Pb and Ni) on water, sediment and a native, teleost fish species, Labeo angra, inhabiting a flood plain wetland of Barak River in Assam, India. Heavy metal concentrations in the water, sediments and fish were measured; bioaccumulation factor, metal pollution index as well as condition indices were calculated, to assess the pollution load and health status of the fish. Multivariate statistical analysis was used on wetland water and sediment heavy metals to ascertain the possible sources and seasonal variations of the pollutants. Results showed that most heavy metals in the wetland water and sediments exceeded the water (drinking and irrigation) and sediment quality guidelines, respectively. Seasonal variations were observed for geogenic heavy metals, Mn, Fe, Mg and Ca while no seasonal variations were observed for anthropogenic heavy metals, Cu, Cd, Cr, Pb and Ni. Multivariate statistical analysis showed that there was strong correlation between geogenic and anthropogenic heavy metals in water and sediment, both originating from the common anthropogenic sources. Accumulation of most of the metals in all the tissues was above the safe limits as recommended by the Food and Agriculture Organization. High bioaccumulation factors and metal pollution index for these metals in the different tissues revealed that metals were extensively bio-accumulated and bioconcentrated. Condition indices in fish from the wetland suggested metabolic abnormalities. PMID:26422176

  19. Analysis of heavy metals from water, sediment, and tissues of Labeo angra (Hamilton, 1822), from an Ox-box lake- an wetland site from Assam, India.

    Science.gov (United States)

    Das, Suchismita; Choudhury, Shamim Sultana

    2016-01-01

    The aim of this study was to assess the regional impacts of heavy metals (Mn, Fe, Mg, Ca, Cu, Zn, Cd, Cr, Pb and Ni) on water, sediment and a native, teleost fish species, Labeo angra, inhabiting a flood plain wetland of Barak River in Assam, India. Heavy metal concentrations in the water, sediments and fish were measured; bioaccumulation factor, metal pollution index as well as condition indices were calculated, to assess the pollution load and health status of the fish. Multivariate statistical analysis was used on wetland water and sediment heavy metals to ascertain the possible sources and seasonal variations of the pollutants. Results showed that most heavy metals in the wetland water and sediments exceeded the water (drinking and irrigation) and sediment quality guidelines, respectively. Seasonal variations were observed for geogenic heavy metals, Mn, Fe, Mg and Ca while no seasonal variations were observed for anthropogenic heavy metals, Cu, Cd, Cr, Pb and Ni. Multivariate statistical analysis showed that there was strong correlation between geogenic and anthropogenic heavy metals in water and sediment, both originating from the common anthropogenic sources. Accumulation of most of the metals in all the tissues was above the safe limits as recommended by the Food and Agriculture Organization. High bioaccumulation factors and metal pollution index for these metals in the different tissues revealed that metals were extensively bio-accumulated and bioconcentrated. Condition indices in fish from the wetland suggested metabolic abnormalities.

  20. A GIS based methodology for nuclear reactor spent fuel disposal

    International Nuclear Information System (INIS)

    This article aims at studying the use of Geographical Information Systems for selecting a site for radioactive waste disposal of spent fuel generated by operation of Angra 1 and 2 nuclear power stations, in order to provide additional means for solving this problem in Brazil. This spent fuel continues to generate decay heat and radiation after its use in power stations. The disposal should be done in such a way as to isolate the nuclear spent fuel from people and the environment, protecting them from the heat and radioactivity for a long period of time. After elaboration of a database containing geological, hydrological, tectonic, weather, transport, conservation unit, amongst other information, one intends to combine these information, and make comparisons using preset criteria, in order to indicate the most adequate sites for disposal. (author)

  1. 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

  2. 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

  3. Considerations about the licensing process of special nuclear industrial facilities

    Energy Technology Data Exchange (ETDEWEB)

    Talarico, M.A., E-mail: talaricomarco@hotmail.com [Marinha do Brasil, Rio de Janeiro, RJ (Brazil). Coordenacao do Porgrama de Submarino com Propulsao Nuclear; Melo, P.F. Frutuoso e [Coordenacao dos Programas de Pos-Graduacao em Engenharia (COPPE/UFRJ), Rio de Janeiro, RJ (Brazil). Programa de Engenharia Nuclear

    2015-07-01

    This paper brings a discussion about the challenges involved in the development of a new kind of nuclear facility in Brazil, a naval base for nuclear submarines, with attention to the licensing process and considerations about the risk-informed decision making application to the licensing process. Initially, a model of such a naval base, called in this work, special industrial facility, is proposed, with its systems and respective sets of basic requirements, in order to make it possible the accomplishment of the special industrial facility support function to the nuclear submarine. A discussion about current challenges to overcome in this project is presented: the challenges due to the new characteristics of this type of nuclear facility; existence of several interfaces between the special industrial facilities systems and nuclear submarine systems in design activities; lack of specific regulation in Brazil to allow the licensing process of special industrial facilities by the nuclear safety authority; and comments about the lack of information from reference nuclear facilities, as is the case with nuclear power reactors (for example, the German Grafenrheinfeld nuclear plant is the reference plant for the Brazilian Angra 2 nuclear plant). Finally, in view of these challenges, an analysis method of special industrial facility operational scenarios to assist the licensing process is proposed. Also, considerations about the application of risk-informed decision making to the special industrial facility activity and licensing process in Brazil are presented. (author)

  4. 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

  5. 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

  6. 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)

  7. 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...

  8. 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.

  9. 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

  10. 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)

  11. A HST Census of Nuclear Star Clusters in Late-Type Spiral Galaxies: II. Cluster Sizes and Structural Parameter Correlations

    CERN Document Server

    Böker, T; McLaughlin, D E; Van der Marel, R P; Rix, H W; Ho, L C; Shields, J C

    2003-01-01

    We investigate the structural properties of nuclear star clusters in late-type spiral galaxies. More specifically, we fit analytical models to HST images of 39 nuclear clusters in order to determine their effective radii after correction for the instrumental point spread function. We use the results of this analysis to compare the luminosities and sizes of nuclear star clusters to those of other ellipsoidal stellar systems, in particular the Milky Way globular clusters. Our nuclear clusters have a median effective radius of r_e = 3.5 pc, with 50% of the sample falling between 2.4 pc < r_e < 5.0 pc. This narrow size distribution is statistically indistinguishable from that of Galactic globular clusters, even though the nuclear clusters are on average 4 magnitudes brighter than the old globulars. We discuss some possible interpretations of this result. From a comparison of nuclear cluster luminosities with various properties of their host galaxies, we confirm that more luminous galaxies harbor more lumino...

  12. 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)

  13. 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

  14. 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

  15. 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.

  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. Nuclear Technology. Course 32: Nondestructive Examination (NDE) Techniques II. Module 32-4, Operation of Magnetic Particle Test Equipment.

    Science.gov (United States)

    Groseclose, Richard

    This fourth in a series of six modules for a course titled Nondestructive Examination (NDE) Techniques II describes the specific technique variables and options which are available to the test technician, provides instructions for selecting and operating the appropriate test equipment, describes physical criteria for detectable discontinuities,…

  18. Nuclear Technology. Course 32: Nondestructive Examination (NDE) II. Module 32-3, Fundamentals of Magnetic Particle Testing.

    Science.gov (United States)

    Groseclose, Richard

    This third in a series of six modules for a course titled Nondestructive Examination (NDE) Techniques II explains the principles of magnets and magnetic fields and how they are applied in magnetic particle testing, describes the theory and methods of magnetizing test specimens, describes the test equipment used, discusses the principles and…

  19. 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…

  20. Non-Destructive Testing in Nuclear Technology Vol. II. Proceedings of a Symposium on Non-Destructive Testing in Nuclear Technology

    International Nuclear Information System (INIS)

    The Symposium on Non-Destructive Testing in Nuclear Technology was convened by the International Atomic Energy Agency and held, at the invitation of the Romanian People's Republic, in Bucharest from 17 to 21 May 1965. This was the first large IAEA symposium on this topic and was arranged with the help of the Romanian Institute of Atomic Physics. Over 100 participants from 20 countries and two international organizations presented 46 papers. The development of non-destructive testing techniques has increased considerably in recent years, particularly in the nuclear field. Nondestructive testing methods such as ultrasonic and radiographic testing are proving increasingly useful for ensuring that reactor materials and components will stand up to prolonged and rigorous use. Such methods are used to test for flaws, to check dimensions such as tube-wall thickness, and to determine the location and distribution of uranium fuel in a fuel element. Speakers stressed that these methods were invaluable for providing extensive and detailed data on the physical structure and condition of materials and the effects of fabrication processes. Among aspects of non-destructive testing that were discussed were the use of automation; assistance at the design stage for attaining higher strength-to-weight ratios; the testing of welds in reactor containment vessels; and the testing of sintered materials. The important information presented at the Symposium and the extensive discussions among scientists demonstrated the desire to accelerate solutions to various problems connected with non-destructive testing techniques

  1. Contribution to the study of the evolution of nuclear fuel composition in PWR type reactors. Reactor cores in three and four regions of enrichment

    International Nuclear Information System (INIS)

    The main methods for calculations of fuel depletion are studied and some approaches to do it are mentioned; the LEOPARD Code is described and full details are given for each subroutine, flow charts are included; the method given by the code for calculation of fuel depletion is described; some imperfections from the IPR's version are listed, and corrected, for instance: the method for burn-up calculation of heavy isotopes; the results of calculations for a reference reactor based on data of the Preliminary Safety Analysis Report (PSAR) for Angra I Nuclear Plant are presented and discussed. (author)

  2. Neutron beam experiments using nuclear research reactors: honoring the retirement of professor Bernard W. Wehring -II. 6. Nuclear Analytical Applications in a Semiconductor Materials Characterization Laboratory

    International Nuclear Information System (INIS)

    A typical semiconductor materials characterization laboratory is heavily loaded with surface analytical tools such as SEM, TEM, TXRF, secondary ion mass spectrometry (SIMS), AFM, and XPS. However, there are analytical needs that cannot be addressed by the aforementioned methods and often require a bulk analysis technique such as ICP/MS. Nuclear analytical methods can play a very important complementary role and provide advantages over nonnuclear techniques because of higher sensitivity, simplicity of sample preparation, and highly quantitative answers. An overwhelming majority of the semiconductor industry uses silicon as the base material for the integrated circuit (IC) manufacturing, and silicon, incidentally, has very favorable nuclear parameters. Silicon, for example, does not have a high neutron capture cross section; thus, matrix activity induced during a neutron irradiation is not very high, and more importantly, the half-life of the major radioisotope 31Si is only 2.6 h. This short half-life provides a good opportunity to study induced radioactivities of other impurities such as iron, zinc, and nickel. So, neutron activation analysis (NAA) can achieve a very high sensitivity with most transition metals and other important impurities such as copper, gold, and tungsten. NAA is very complementary to other methods of analysis in providing trace-level metals analysis of both silicon wafer and non-wafer samples such as quartz parts used in the diffusion furnaces. Data from NAA of quartz materials used in the diffusion furnaces will be described. In addition, the NAA techniques such as prompt gamma activation analysis are especially useful for the analysis of bulk hydrogen. Another nuclear method, nuclear reaction analysis (NRA), has also been widely used for this purpose. With NRA, a depth profile similar to the ones obtained by SIMS can be achieved. An important nuclear analysis in the semiconductor industry is the depth profiling of boron by neutron depth

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2011-07-01

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

  4. Chemical Effects of Nuclear Transformations. Vol. II. Proceedings of the Symposium on Chemical Effects Associated with Nuclear Reactions and Radioactive Transformations

    International Nuclear Information System (INIS)

    The study of the chemical changes consequent upon the nuclear transformation of an atom that is linked with other atoms in a molecule and surrounded by other similar or dissimilar molecules has intrigued chemists for a number of years. This interest is certainly not static but if anything is increasing. The main theme of this meeting was a discussion of the suggestions and theories that have been advanced to explain the wealth of experimental observations on the behaviour of atoms at energies and in situations not normally accessible in the laboratory. Though the subject has some practical implications in the preparation of radioisotopes, this was not an important consideration at this Symposium. The first Symposium on hot-atom chemistry organized by the Agency was held in Prague in October 1960. Comparison of the past and the present state of the subject shows that a greater variety and sophistication of techniques are now being applied as the simpler approaches used in the past have been shown to be inadequate. Progress has been made in the understanding of the simpler gas system, but in liquids and solids there is still much to clarify. It is also of interest that for the majority of the work reported in these Proceedings a reactor was the radiation source, and in this field much experimental work still remains to be done. The Symposium on Chemical Effects Associated with Nuclear Reactions and Radioactive Transformations was held from 7 to 11 December 1964 in Vienna, and was attended by 136 participants from 29 countries and 4 international organizations. It was organized by the International Atomic Energy Agency in co-operation with the Joint Commission on Applied Radioactivity. The publication of these Proceedings makes the content of the papers and discussion available to a wider audience than was possible at the meeting in Vienna

  5. The Politics of Forgetting: Otto Hahn and the German Nuclear-Fission Project in World War II

    Science.gov (United States)

    Sime, Ruth Lewin

    2012-03-01

    As the co-discoverer of nuclear fission and director of the Kaiser Wilhelm Institute for Chemistry, Otto Hahn (1879-1968) took part in Germany`s nuclear-fission project throughout the Second World War. I outline Hahn's efforts to mobilize his institute for military-related research; his inclusion in high-level scientific structures of the military and the state; and his institute's research programs in neutron physics, isotope separation, transuranium elements, and fission products, all of potential military importance for a bomb or a reactor and almost all of it secret. These activities are contrasted with Hahn's deliberate misrepresentations after the war, when he claimed that his wartime work had been nothing but "purely scientific" fundamental research that was openly published and of no military relevance.

  6. 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.

  7. A study on nuclear heat load tolerable for NET/TF coils cooled by internal flow of helium II

    International Nuclear Information System (INIS)

    NbTi cables cooled by internal flow of superfluid helium are considered an option for the design of NET/TF coils with about 11 T peak fields. Starting from an available winding cross section of 0.61x0.61 m2 for a 8 MA turns coil made of a 16 kA conductor it is shown that sufficient hydraulic cross section can be provided within such cables to remove the expected thermal load resulting from nuclear heating with exponential decay from inboard to outboard side of the winding. The concept is a pancake type coil with 1.8 K helium fed-in the high field region of each pancake. The temperature distribution within such coils is calculated, and the local safety margin is determined from temperature and field. The calculation takes account of nuclear and a.c. heating, and of thermal conductance between the individual layers and the coil casing. It is shown that operation with 1.8 K inlet and about 3 K outlet temperature is possible. The electrical insulation with about 0.5 mm thickness proves to provide sufficient thermal insulation. No additional thermal shield is required between the coil casing and the winding package. Two different types of conductors are being considered: a) POLO type cable with quadratic cross section and a central circular coolant duct, and b) an LCT type cable with two conductors wound in hand. Both concepts with about 500 m length of the cooland channels are shown to meet the requirements resulting from a peak nuclear heat load of 0.3 mW/cm3 in the inboard turns. The hydraulic diameters are sufficient to operate each coils with self-sustained fountain effect pumps. Even appreciably higher heat loads with up to 3 mW/cm3 of nuclear heating can be tolerated for the POLO type cable when the hydraulic diameter is enlarged to its maximum of 17 mm. (orig.)

  8. Radiation protection of nuclear medicine workers in the Czech Republic in 2003 -some results of SONS and questionnaire survey II

    International Nuclear Information System (INIS)

    Our paper presents the most. important data concerning an equipment of 45 nuclear medicine departments (depts.) with radiation protection facilities and aids. The results of the questionnaire survey mentioned in our previous paper are briefly summarized here. A relatively low radiation burden of nuclear medicine staff suggests the standard of radiation protection measures to be relatively good in our country. However, our survey shows some shortcomings, especially the following ones: (1) some depts. need equipment for the preparation and dispensing of radiopharmaceuticals; (2) syringe shields for injection of beta-emitters such as 90Y are missing Iargely; (3) at some depts. shielding of staff from the patient containing a radiopharmaceutical is either missing or insufficient. Some deficiencies, including those not mentioned here, cannot be considered too significant. If syringe shields for beta-emitters are not available, Pb shields can be provisionally used. It would be desirable to replace the Pb shields by tungsten ones having the same effectiveness as Pb shields but smaller dimensions enabling a more comfortable injections (of course, tungsten syringe shields were available at four depts. which administered 18F-FDG in 2003). An acquaintance of depts. with the results of our survey is believed to stimulate nuclear medicine workers to improve further radiation protection in compliance with legislative requirements. (authors)

  9. Specification and verification of nuclear-power-plant training-simulator response characteristics. Part II. Conclusions and recommendations

    International Nuclear Information System (INIS)

    The nuclear industry should adopt and NRC regulatory and research actions should support the systems approach to training as a structured framework for development and validation of personnel training systems. Potential exists for improving the ability to assess simulator fidelity. Systems Identification Technology offers a potential framework for model validation. Installation of the data collection/recording equipment required by NUREG-0696 could provide a vastly improved source of data for simulator fidelity assessment. The NRC needs to continue its post-TMI actions to involve itself more rigorously and more formally in the entire process of NPP personnel training system development. However, this involvement should be a participative one with industry. The existing similator standards and guidelines should be reorganized to support the use of systems approach to training. The standards should require and support a holistic approach to training system development that recognizes simulators and simulator training as only parts of the complete training program and full-scope, high-fidelity, site-specific simulators as only one useful training device. Some recommendations for adapting the SAT/ISD process to the nuclear industry are: The formation of an NRC/industry planning/coordination group, a program planning study to develop a programmatic plan, development of a user's guide and NRC/industry workshops to establish common terminology and practice, and a pilot study applying the adopted SAT/ISD methodology to an actual nuclear industry training program

  10. Thermodynamics. Vol. II. Proceedings of the Symposium on Thermodynamics with Emphasis on Nuclear Materials and Atomic Transport in Solids

    International Nuclear Information System (INIS)

    Knowledge of the thermodynamics of nuclear materials is vital to the design of reactor fuels and moderating and cooling systems, in fact all facets of nuclear plant operation that involve mixtures of, or contact between, two or more elements in single- or multi-phase systems. The steep thermal gradients and the high temperatures involved in nuclear technology pose special problems for engineers and thermodynamicists, who have found that extrapolation of low-temperature data to high temperatures very often proves invalid. For this reason, standard thermodynamic techniques such as calorimetry and EMF-methods have been extended into high-temperature regions. Since the Agency's last conference on this subject, also held in Vienna (Thermodynamics of Nuclear Materials, 1962), there have been notable advances in calorimetry performed at temperatures greater than 1000°C, and in the use of EMF cells with solid electrolytes operated at similar temperatures. Significant advances have also been made in measuring diffusion parameters at the higher temperatures. An important field covered in this Symposium was the correlation of such atomic transport data with thermodynamic data, a prerequisite if the nuclear engineer is to incorporate diffusion results into his normal process- assessment techniques. Finally the Symposium suggested the requirements for good critical tables. The mere compiling of such data is no longer sufficient; the compiler must have free access to all the data of a particular experiment, he must have an intimate knowledge of experimental work in this field and he must weight every figure quoted in the light of his experience. As a step in this direction, the Agency has called on the services of many well-known experts and is preparing a number of monographs giving critical assessments of thermodynamic data and phase-diagrams for many of the elements of interest in reactor design. Most of the countries engaged in research in thermodynamics were represented at

  11. NOVA: a computer-aided system to monitor proper behaviour of plant components in the Gundremmingen nuclear power plant (KRB II)

    International Nuclear Information System (INIS)

    In the Gundremmingen nuclear power plant (KRB II), a computer-aided evaluation system for signal messages of the process computer has been developed to application maturity and installed. The self-acting system checks sequences of automatic operations for their proper function. Results are available only minutes after an action has happened. The high level of detail permits to detect faults before they result in system failure or loss. Since all short-time safety functions are performed automatically, these consistent and detailed checks increase the safety substantially. In addition, the NOVA-system makes it possible to search all over the signal message report for certain signals as well as to produce an overview protocol of the current (or a past) status of the plant. (orig.)

  12. Comparison between dispersed nuclear power plants and a nuclear energy center at a hypothetical site on Kentucky Lake, Tennessee. Volume II. Transmission of power

    International Nuclear Information System (INIS)

    A comparison is made among power transmission systems required to serve a single set of load center demands from four modes of siting the generating facilities: a single generation site with an ultimate generation capacity of 48,000 MW; four generation sites each with a generation capacity of 12,000 MW; 10 generation sites each with a generation capacity of 4,800 MW; and a system that resulted when the existing utility plan for future generation was logically expanded. The time period for the study is from the year 1985 to the year 2020, when the full 48,000 MW of new capacity from the single large nuclear energy center is on-line. The load centers served are Huntsville, Alabama; Evansville, Indiana; Paducah, Kentucky; and Chattanooga, Nashville, and Memphis, Tennessee. Generation sites are real locations but are hypothetical in terms of miles of transmission lines, the product of the amount of power transmitted and the distance transmitted (GW-miles), and cost

  13. Suggestion from young researchers in symposium II conducted by Japan health physics society about Fukushima Daiichi Nuclear Power Plant accident. Focusing on internal exposure management to relate to Fukushima Daiichi Nuclear Power Plant accident

    International Nuclear Information System (INIS)

    Fukushima Daiichi Nuclear Power Plants (NPPs) affected by the Great East Japan Earthquake suffered reactor core meltdown and discharged a large amount of radioactive nuclides to the air, which brought about a disorder among the public for internal exposure. Internal exposure management at the accident so as to evaluate internal exposure dose rate of personnel or the public in a quick and optimum way should be standardized with reflecting lessons learned at Fukushima Daiichi NPP accident. Three themes on internal exposure management; (1) thyroid gland screening test, (2) whole-body counters and (3) bioassay, were discussed from young researchers in symposium II conducted by Japan Health Physics Society about Fukushima Daiichi NPP accident. Progression of response to the accident and problems and proposals for each respective theme were presented in the article. (T. Tanaka)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2000-07-01

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

  15. Public perception of the nuclear area in Brazil

    Energy Technology Data Exchange (ETDEWEB)

    Imeida, R.A. de [PEN/COPPE/UFRJ, Avenida Horacio Macedo, 2030 Bloco G sala 206, Cidade Universitaria, Ilha do Fundao, Rio de Janeiro RJ (Brazil); Lourdes Moreira, M. de [Instituto de Engenharia Nuclear, Comissao Nacional de Energia Nuclear, Rua Helio de Almeida, 75 - Cidade Universitaria, Ilha do Fundao, Rio de Janeiro RJ (Brazil)

    2013-07-01

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

  16. Plasma Physics and Controlled Nuclear Fusion Research. Vol. II. Proceedings of a Conference on Plasma Physics and Controlled Physics Research

    International Nuclear Information System (INIS)

    Research on controlled nuclear fusion was first disclosed at the Second United Nations Conference on the Peaceful Uses of Atomic Energy, held at Geneva in 1958. From the information given, it was evident that a better understanding of the behaviour of hot dense plasmas was needed before the goal of economic energy release from nuclear fusion could be reached. The fact that research since then has been most complex and costly has enhanced the desirability of international co-operation and exchange of information and experience. Having organized its First Conference on Plasma Physics and Controlled Nuclear Fusion Research at Salzburg in 1961, the International Atomic Energy Agency again provided the means for such cooperation in organizing its Second Conference on this subject on 6-10 September, 1965, at Culham, Abingdon, Berks, England. The meeting was arranged with the generous help of the United Kingdom Atomic Energy Authority at their Culham Laboratory, where the facilities and assistance of the staff were greatly appreciated. At the meeting, which was attended by 268 participants from 26 member states and three international organizations, significant results from many experiments, including those from the new and larger machines, became available. It has now become feasible to intercorrelate data obtained from a number of similar machines; this has led to a more complete understanding of plasma behaviour. No breakthrough was reported nor had been expected towards the economical release of the energy from fusion, but there was increased understanding of the problems of production, control and containment of high-density and high-temperature plasmas

  17. Hydro-climatic conditions and thermoelectric electricity generation – Part II: Model application to 17 nuclear power plants in Germany

    International Nuclear Information System (INIS)

    In highly developed countries electricity generation is one of the largest water users. Water is mainly used in the cooling processes of thermal power plants. In as yet less developed countries, electricity requirements are also increasing in step with increasing production and standard of living. Renewable electricity generation is gaining more attention in both highly and less developed economies. However, many types of renewable electricity generation, e.g. wind or solar, are still unreliable due to their dependence on weather conditions. This is why electricity generation by thermal power plants will remain a substantial component of the overall energy system for the next decades. An approach is applied here for analysing links between water availability and water temperature, air temperature and electricity generation by power plants. A highly disaggregated level is used combining a power plant model and hydrological models. It is applied to analyse effects of climate change on 17 nuclear power plants in Germany. Although even under baseline conditions reduced electricity generation can be observed, any further increase in air temperatures reduces electricity output of almost all nuclear power plants. The different technological and environmental conditions of each plant site mean that specific models are necessary for the simulations. - Highlights: • Effect of climate change on 17 nuclear power plants in Germany is presented. • Main reason for reduced production is the maximum discharge water temperature. • In some regions the withdrawal is restricted due to water temperature at intake point. • Site specific models (power plants, water temperature and discharge) are necessary

  18. Construction of a bibliographic information database and development of retrieval system for research reports in nuclear science and technology (II)

    Energy Technology Data Exchange (ETDEWEB)

    Han, Duk Haeng; Kim, Tae Whan; Choi, Kwang; Yoo, An Na; Keum, Jong Yong; Kim, In Kwon [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1996-05-01

    The major goal of this project is to construct a bibliographic information database in nuclear engineering and to develop a prototype retrieval system. To give an easy access to microfiche research report, this project has accomplished the construction of microfiche research reports database and the development of retrieval system. The results of the project are as follows; 1. Microfiche research reports database was constructed by downloading from DOE Energy, NTIS, INIS. 2. The retrieval system was developed in host and web version using access point such as title, abstracts, keyword, report number. 6 tabs., 8 figs., 11 refs. (Author) .new.

  19. I. Nuclear Production Reaction and Chemical Isolation Procedure for Americium-240 II. New Superheavy Element Isotopes: Plutonium-242(Calcium-48,5n)(285)114

    Science.gov (United States)

    Ellison, Paul Andrew

    2011-12-01

    Part I discusses the study of a new nuclear reaction and chemical separation procedure for the production of 240Am. Thin 242Pu, natTi, and natNi targets were coincidently activated with protons from the 88-Inch Cyclotron, producing 240Am, 48V, and 57Ni, respectively. The radioactive decay of these isotopes was monitored using high-purity Ge gamma ray detectors in the weeks following irradiation. The excitation function for the 242 Pu(p, 3n)240Am nuclear reaction was measured to be lower than theoretical predictions, but high enough to be the most viable nuclear reaction for the large-scale production of 240 Am. Details of the development of a chemical separation procedure for isolating 240Am from proton-irradiated 242Pu are discussed. The separation procedure, which includes two anion exchange columns and two extraction chromatography columns, was experimentally investi- gated using tracer-level 241Am, 239Pu, and model proton-induced fission products 95Zr, 95Nb, 125Sb, and 152Eu. The separation procedure was shown to have an Am/Pu separation factor of >2x10 7 and an Am yield of ˜70%. The separation procedure was found to purify the Am sample from >99.9% of Eu, Zr, Nb, and Sb. The procedure is well suited for the processing of ˜1 gram of proton-irradiated 242Pu to produce a neutron-induced fission target consisting of tens of nanograms of 240Am. Part II describes the use of the Berkeley Gas-filled Separator at the Lawrence Berkeley National Laboratory 88-Inch Cyclotron for the study of the 242Pu(48Ca,5n)285114 nuclear re- action. The new, neutron-deficient, superheavy element isotope 285114 was produced in 48Ca irradiations of 242Pu targets at a center-of-target beam energy of 256 MeV ( E* = 50 MeV). The alpha decay of 285114 was followed by the sequential alpha decay of four daughter nuclides, 281Cn, 277Ds, 273Hs, and 269 Sg. 265Rf was observed to decay by spontaneous fission. The measured alpha-decay Q-values were compared with those from a macroscopic

  20. Measurements of miniature ionization chamber currents in the JSI TRIGA Mark II reactor demonstrate the importance of the delayed contribution to the photon field in nuclear reactors

    Science.gov (United States)

    Radulović, Vladimir; Fourmentel, Damien; Barbot, Loïc; Villard, Jean-François; Kaiba, Tanja; Gašper, Žerovnik; Snoj, Luka

    2015-12-01

    The characterization of experimental locations of a research nuclear reactor implies the determination of neutron and photon flux levels within, with the best achievable accuracy. In nuclear reactors, photon fluxes are commonly calculated by Monte Carlo simulations but rarely measured on-line. In this context, experiments were conducted with a miniature gas ionization chamber (MIC) based on miniature fission chamber mechanical parts, recently developed by the CEA (French Atomic Energy and Alternative Energies Commission) irradiated in the core of the Jožef Stefan Institute TRIGA Mark II reactor in Ljubljana, Slovenia. The aim of the study was to compare the measured MIC currents with calculated currents based on simulations with the MCNP6 code. A discrepancy of around 50% was observed between the measured and the calculated currents; in the latter taking into consideration only the prompt photon field. Further experimental measurements of MIC currents following reactor SCRAMs (reactor shutdown with rapid insertions of control rods) provide evidence that over 30% of the total measured signal is due to the delayed photon field, originating from fission and activation products, which are untreated in the calculations. In the comparison between the measured and calculated values, these findings imply an overall discrepancy of less than 20% of the total signal which is still unexplained.

  1. Ca2+/calmodulin-dependent kinase II contributes to inhibitor of nuclear factor-kappa B kinase complex activation in Helicobacter pylori infection.

    Science.gov (United States)

    Maubach, Gunter; Sokolova, Olga; Wolfien, Markus; Rothkötter, Hermann-Josef; Naumann, Michael

    2013-09-15

    Helicobacter pylori, a class I carcinogen, induces a proinflammatory response by activating the transcription factor nuclear factor-kappa B (NF-κB) in gastric epithelial cells. This inflammatory condition could lead to chronic gastritis, which is epidemiologically and biologically linked to the development of gastric cancer. So far, there exists no clear knowledge on how H. pylori induces the NF-κB-mediated inflammatory response. In our study, we investigated the role of Ca(2+) /calmodulin-dependent kinase II (CAMKII), calmodulin, protein kinases C (PKCs) and the CARMA3-Bcl10-MALT1 (CBM) complex in conjunction with H. pylori-induced activation of NF-κB via the inhibitor of nuclear factor-kappa B kinase (IKK) complex. We use specific inhibitors and/or RNA interference to assess the contribution of these components. Our results show that CAMKII and calmodulin contribute to IKK complex activation and thus to the induction of NF-κB in response to H. pylori infection, but not in response to TNF-α. Thus, our findings are specific for H. pylori infected cells. Neither the PKCs α, δ, θ, nor the CBM complex itself is involved in the activation of NF-κB by H. pylori. The contribution of CAMKII and calmodulin, but not PKCs/CBM to the induction of an inflammatory response by H. pylori infection augment the understanding of the molecular mechanism involved and provide potential new disease markers for the diagnosis of gastric inflammatory diseases including gastric cancer.

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

    International Nuclear Information System (INIS)

    This study has the aim to assess the impact of accidental release of radionuclides postulate from a nuclear power reactor through environmental modeling of aquatic resources. In order to do that it was used computational models of hydrodynamic circulation and transport for the simulation of tritium dispersion caused by an accidental release in Ilha Grande Bay from the site of the future third plant in two circulation scenarios. The main difference between the scenarios is based on the enhancement of dilution of the highest concentrations in the last one. This dilution enhancement resulting in decreasing concentrations was observed only during the first two weeks, when they ranged from 1 x 109 to 5 x 105 Bq/m³ close to the Itaorna beach spreading just to Sandri Island. After 180 days, the plume could not be detected anymore in the bay, because their activities would be lower than the minimum detectable value (< 11 kBq/m³). (author)

  3. Methods and Model Development for Coupled RELAP5/PARCS Analysis of the Atucha-II Nuclear Power Plant

    Directory of Open Access Journals (Sweden)

    Andrew M. Ward

    2011-01-01

    Full Text Available In order to analyze the steady state and transient behavior of CNA-II, several tasks were required. Methods and models were developed in several areas. HELIOS lattice models were developed and benchmarked against WIMS/MCNP5 results generated by NA-SA. Cross-sections for the coupled RELAP5/PARCS calculation were extracted from HELIOS within the GenPMAXS framework. The validation of both HELIOS and PARCS was performed primarily by comparisons to WIMS/PUMA and MCNP for idealized models. Special methods were developed to model the control rods and boron injection systems of CNA-II. The insertion of the rods is oblique, and a special routine was added to PARCS to treat this effect. CFD results combined with specialized mapping routines were used to model the boron injection system. In all cases there was good agreement in the results which provided confidence in the neutronics methods and modeling. A coupled code benchmark between U of M and U of Pisa is ongoing and results are still preliminary. Under a LOCA transient, the best estimate behavior of the core appears to be acceptable.

  4. Biologically relevant mono- and di-nuclear manganese II/III/IV complexes of mononegative pentadentate ligands

    DEFF Research Database (Denmark)

    Baffert, Carole; Collomb, Marie-Nöelle; Deronzier, Alain;

    2003-01-01

    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...... are the highest oxidation state products detected, and these are formed via shorter-lived intermediate mu-oxo-dimanganese(III) compounds. The rate of formation of the various oxidized products is slower in the case of the bzgbpen(-) systems which contains a bulkier non-coordinating arm. The oxidised complexes...... were characterised by UV-visible spectroscopy, ESI mass spectrometry and cyclic voltammetry. In addition, III-IV and II-III species were electrochemically generated. Thus the new mononegative pentadentate ligand systems display significant flexibility in the range of Mn oxidation states and species...

  5. Future Industrialization of the World and the Necessity of Nuclear Power, Part II: How Limited are Resources?

    International Nuclear Information System (INIS)

    Will the future world be forever divided into an industrial, developed and 'rich' on one side, and the primitive, undeveloped, and poor on the other? Is an industrial, affluent and sustainable world of 10-15 billion people owning 5-10 billion cars physically possible to exist? Can the world have enough food, minerals and energy to support such a widespread affluence in a sustainable manner? In previous papers I have argued that even without any major breakthroughs in science and technology, an industrialized, sustainable and affluent world can be created within the next half a century to a century, but only if breeder nuclear power is widely used throughout the world. In this paper I elaborate on the question of future availability of some basic natural resources. (author)

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

    International Nuclear Information System (INIS)

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

  7. U.S. Department Of Energy's nuclear engineering education research: highlights of recent and current research-II. 5. Automation of Nuclear Fuel Pellet Quality Control

    International Nuclear Information System (INIS)

    At the present time, nuclear fuel pellet inspection is performed by humans using the naked eye for judgment and decision making as to whether to accept or reject the pellet. Unnecessary re-fabrication of pellets will be costly, and having too many low-quality pellets in a fuel assembly is unacceptable. The current practice of pellet inspection by humans is tedious and subject to inconsistencies and error. In addition, manual inspection is cumbersome since the inspector must keep the pellet at arm's length and must wear glasses to protect the lenses of his or her eyes. The pellets are taken from a pellet sizing machine, dumped onto a rack, and shaken into rows; they are then viewed as a group. The entire group is rotated 90 deg four times to provide the inspector with a 360-deg view of each pellet. The pellets are examined for certain types of cracks, chips, and unusual markings, i.e., water stains and machine banding. These defects appear at any location on the pellet surface image with different intensity, size, shape, and background noise. Figure 1 shows typical defective fuel pellets with chip, banded, and end defects. The goal of this work is to automate the pellet inspection process. A prototype of such an inspection system is developed. The system examines photographic images of pellets using various artificial intelligence techniques for image analysis and defect classification. Figure 2 shows the user interface of this inspection system, which is built using Java programming language. A total of 252 pellets with various defects was available for this research. Each pellet was photographed four times at rotations of 90 deg. The resultant black-and-white negatives were scanned into the computer in 256 gray scale mode. The inspection of a fuel pellet by image analysis involves several steps, as described in Fig. 3 and as follows: Step 1-On-line image conversion: This process involves on-line digitization of the input image. Step 2-Reference model: The second

  8. An analysis of thermionic space nuclear reactor power system: II. Merits of using safety drums for backup control

    Science.gov (United States)

    El-Genk, Mahomed S.; Xue, Huimin

    1993-01-01

    An analysis is performed to investigate the merits of using the TOPAZ-II safety drums for a backup control to prevent a reactivity excursion, stabilize the reactor, and achieve steady-state power operation, following a severe hypothetical reactivity initiated accident (RIA). Such an RIA is assumed to occur during the system start-up in orbit due to a malfunction of the drive mechanism of the control drums, causing the nine drums to accidentally rotate the full 180° outward. Results show that an immediate, inward rotation of the three safety drums to an angle of 80° will shutdown the reactor, however, a delay time of 10 s will not only prevents a reactivity excursion, but also enables operating the reactor at a steady-state thermal power of about 33.3 kW (0.9 kW per TFE). Conversely, when the immediate rotation of the safety drums is to a larger angle of 100°, a steady-state operation at about 37 kW can be achieved, but a delay of 10 s causes a reactivity excursion and overheating of the TFEs. It is therefor concluded that, should the drive mechanism be modified to enable rotating the safety drums for TOPAZ-II reactor at variable speeds of and below 22.5°/s, the three safety drums could be used successfully for a backup control, following an RIA. However, since the reactivity worth of the three safety drums is only 2.0, the maximum steady-state electric power achievable for the system is limited to approximately 0.25 kW, at which the fission power is about 37 kW and the emitter temperature is approximaely 1500 K. To alleviate such a limitation and enable operation at nominal design conditions (fission power of about 107 kW or a system's total electric power of 5.6 kW), the reactivity worth of the safety drums would have to be increased by at least 0.24. An additional increase in the safety drums' worth will also be necessary to maintain steady-state operation of the system at nominal conditions throughout the mission lifetime, with all nine control drums fully

  9. NKS-B NordRisk II: Nuclear risk from atmospheric dispersion in Northern Europe - Summary report

    International Nuclear Information System (INIS)

    The objective of the NordRisk II project has been to derive practical means for assessing the risks from long-range atmospheric dispersion of radioactive materials. An atlas over different atmospheric dispersion and deposition scenarios has been developed using historical numerical weather prediction (NWP) model data. The NWP model data covers three years spanning the climate variability associated with the North Atlantic Oscillation, and the atlas considers radioactive releases from 16 release sites in and near the Nordic countries. A statistical analysis of the long-range dispersion and deposition patterns is undertaken to quantify the mean dispersion and deposition as well as the variability. Preliminary analyses show that the large-scale atmospheric dispersion and deposition is near-isotropic, irrespective of the release site and detailed climatology, and allows for a simple parameterization of the global dispersion and deposition patterns. The atlas and the underlying data are made available in a format compatible with the ARGOS decision support system, and have been implemented in ARGOS. (Author)

  10. Galaxy gas as obscurer: II. Separating the galaxy-scale and nuclear obscurers of Active Galactic Nuclei

    CERN Document Server

    Buchner, Johannes

    2016-01-01

    The "torus" obscurer of Active Galactic Nuclei (AGN) is poorly understood in terms of its density, substructure and physical mechanisms. Large X-ray surveys provide model boundary constraints, for both Compton-thin and Compton-thick levels of obscuration, as obscured fractions are mean covering factors $f_{\\text{cov}}$. However, a major remaining uncertainty is host galaxy obscuration. In Paper I we discovered a relation of $N_H \\propto M_{\\star}^{1/3}$ for the obscuration of galaxy-scale gas. Here we apply this observational relation to the AGN population, and find that galaxy-scale gas is responsible for a luminosity-independent fraction of Compton-thin AGN, but does not produce Compton-thick columns. With the host galaxy obscuration understood, we present a model of the remaining, nuclear obscurer which is consistent with a range of observations. Our radiation-lifted torus model consists of a Compton-thick component ($f_{\\text{cov}}\\sim35\\%$) and a Compton-thin component ($f_{\\text{cov}}\\sim40\\%$), which d...

  11. Identification of hazards in non-nuclear power plants. Volume 1. Summary report. Phase I and Phase II. Consultant report

    Energy Technology Data Exchange (ETDEWEB)

    1979-08-01

    This report summarizes the first step in an evaluation of the public health and safety hazards associated with non-nuclear plants. The study was limited to hazards that could affect the general public outside the plant boundaries. Public health and safety hazards are identified for seven types of power plants: coal-fired conventional boiler, atmospheric fluidized bed boiler, pressurized fluidized bed-combined cycle, oil-fired, oil-fired steam turbine, combined cycle, combustion (gas) turbine, and geothermal. Major plant systems associated with specific hazards are identified and described. Potentially hazardous conditions and events are identified for normal and abnormal plant operating conditions and for accidents at the plant. A classification of each hazard identifies the initiating event, the hazard source, equipment, or conditions that increase, monitor, or mitigate the hazard. An event tree developed for each plant relates the effect on the general public for each hazard and initiating event. A semi-quantitative hazard ranking provides a method of comparing the hazards and events at different types of plants. Consideration is given to the sensitivity of the hazard ranking to population density, changes in operating mode, and technology changes.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2011-07-01

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

  13. The Chloroplast Function Database II: a comprehensive collection of homozygous mutants and their phenotypic/genotypic traits for nuclear-encoded chloroplast proteins.

    Science.gov (United States)

    Myouga, Fumiyoshi; Akiyama, Kenji; Tomonaga, Yumi; Kato, Aya; Sato, Yuka; Kobayashi, Megumi; Nagata, Noriko; Sakurai, Tetsuya; Shinozaki, Kazuo

    2013-02-01

    The Chloroplast Function Database has so far offered phenotype information on mutants of the nuclear-encoded chloroplast proteins in Arabidopsis that pertains to >200 phenotypic data sets that were obtained from 1,722 transposon- or T-DNA-tagged lines. Here, we present the development of the second version of the database, which is named the Chloroplast Function Database II and was redesigned to increase the number of mutant characters and new user-friendly tools for data mining and integration. The upgraded database offers information on genome-wide mutant screens for any visible phenotype against 2,495 tagged lines to create a comprehensive homozygous mutant collection. The collection consists of 147 lines with seedling phenotypes and 185 lines for which we could not obtain homozygotes, as well as 1,740 homozygotes with wild-type phenotypes. Besides providing basic information about primer lists that were used for the PCR genotyping of T-DNA-tagged lines and explanations about the preparation of homozygous mutants and phenotype screening, the database includes access to a link between the gene locus and existing publicly available databases. This gives users access to a combined pool of data, enabling them to gain valuable insights into biological processes. In addition, high-resolution images of plastid morphologies of mutants with seedling-specific chloroplast defects as observed with transmission electron microscopy (TEM) are available in the current database. This database is used to compare the phenotypes of visually identifiable mutants with their plastid ultrastructures and to evaluate their potential significance from characteristic patterns of plastid morphology in vivo. Thus, the Chloroplast Function Database II is a useful and comprehensive information resource that can help researchers to connect individual Arabidopsis genes to plastid functions on the basis of phenotype analysis of our tagged mutant collection. It can be freely accessed at http://rarge.psc.riken.jp/chloroplast/.

  14. Ultraviolet-B responses of nuclear genes encoding light-harvesting complex II proteins in pea (Pisum sativum) are altered by norflurazon- and photobleaching-induced chloroplast changes

    International Nuclear Information System (INIS)

    The role of functional and intact chloroplasts in mediating the ultraviolet-B (UV-B, 290–320 nm) regulation of two nuclear genes encoding light-harvesting complex II proteins in pea (Pisum sativum L. cv. Extra Early Alaska) was studied. Plants with chloroplasts lacking or containing carotenoids and functional photosystem II were obtained by growth under dim red light (0.2 µmol m−2 s−1) in the presence or absence of norflurazon (NF), an inhibitor of carotenoid biosynthesis. The NF-treatment resulted in an increase in AB80 (lhcb1*2) mRNA but no substantial change in Cab-8 (lhcb1*4) mRNA, indicating that the mRNA accumulations for AB80 and Cab-8 were differently correlated with the presence and absence of carotenoids. The mRNA levels for both Cab-8 and AB80 in the NF-treated plants were reduced to the same extent by partially photobleaching the chloroplasts with 3 h of higher intensity white light (W, 110 µmol m−2 s−1), suggesting that chloroplast integrity was equally important for transcript accumulation of both genes. The mRNAs of both Cab-8 and AB80 in non-NF-treated control plants were decreased by UV-B irradiation, with the level of AB80 mRNA reduced to a greater extent. The UV-B-induced mRNA reduction of both genes was inhibited by NF. The difference between the UV-B responses of the two genes was unaffected by NF, but was abolished by photobleaching the NF-treated plants prior to the UV-B irradiation. Therefore, the presence of carotenoids enhanced rather than prevented the UV-B down-regulation, and the difference in UV-B responses of the two genes may be dependent on chloroplast integrity. (author)

  15. Enhanced thermal conductivity oxide nuclear fuels by co-sintering with BeO: II. Fuel performance and neutronics

    Science.gov (United States)

    McCoy, Kevin; Mays, Claude

    2008-04-01

    The fuel rod performance and neutronics of enhanced thermal conductivity oxide (ECO) nuclear fuel with BeO have been compared to those of standard UO 2 fuel. The standards of comparison were that the ECO fuel should have the same infinite neutron-multiplication factor kinf at end of life and provide the same energy extraction per fuel assembly over its lifetime. The BeO displaces some uranium, so equivalence with standard UO 2 fuel was obtained by increasing the burnup and slightly increasing the enrichment. The COPERNIC fuel rod performance code was adapted to account for the effect of BeO on thermal properties. The materials considered were standard UO 2, UO 2 with 4.0 vol.% BeO, and UO 2 with 9.6 vol.% BeO. The smaller amount of BeO was assumed to provide increases in thermal conductivity of 0, 5, or 10%, whereas the larger amount was assumed to provide an increase of 50%. A significant improvement in performance was seen, as evidenced by reduced temperatures, internal rod pressures, and fission gas release, even with modest (5-10%) increases in thermal conductivity. The benefits increased monotonically with increasing thermal conductivity. Improvements in LOCA initialization performance were also seen. A neutronic calculation considered a transition from standard UO 2 fuel to ECO fuel. The calculation indicated that only a small increase in enrichment is required to maintain the kinf at end of life. The smallness of the change was attributed to the neutron-multiplication reaction of Be with fast neutrons and the moderating effect of BeO. Adoption of ECO fuel was predicted to provide a net reduction in uranium cost. Requirements for industrial hygiene were found to be comparable to those for processing of UO 2.

  16. Deep repository for spent nuclear fuel. SR-97-Post-closure safety. Main Report. Volume I and II

    International Nuclear Information System (INIS)

    In preparation for coming site investigations for siting of a deep repository for spent nuclear fuel, the Swedish Government and nuclear regulatory authorities have requested an assessment of the repository's long-term safety. The purpose is to demonstrate whether the risk of harmful effects in individuals in the vicinity of the repository complies with the acceptance criterion formulated by the Swedish regulatory authorities, i.e. that the risk may not exceed 10-6 per year. Geological data are taken from three sites in Sweden to shed light on different conditions in Swedish granitic bedrock. The future evolution of the repository system is analyzed in the form of five scenarios. The first is a base scenario where the repository is postulated to be built entirely according to specifications and where present-day conditions in the surroundings are postulated to persist. The four other scenarios show how the evolution of the repository differs from that in the base scenario if the repository contains a few initially defective canisters, in the event of climate change, earthquakes, and future inadvertent human intrusion. The time horizon for the analyses is at most one million years, in accordance with preliminary regulations. By means of model studies and calculations, the base scenario analyzes how the radioactivity of the fuel declines with time, the repository's thermal evolution as a result of the decay heat in the fuel, the hydraulic evolution in buffer and backfill when they become saturated with water, and the long-term groundwater flow in the geosphere on the three sites. The overall conclusion of the analyses in the base scenario is that the copper canisters isolating capacity is not threatened by either the mechanical or chemical stresses to which it is subjected. The safety margins are great even in a million-year perspective. The internal evolution in initially defective canisters and the possible resultant migration of radionuclides in buffer, geosphere

  17. Deep repository for spent nuclear fuel. SR 97 - Safety after closure. Main Report. Volume I and II

    International Nuclear Information System (INIS)

    In preparation for coming site investigations for siting of a deep repository for spent nuclear fuel, the Swedish Government and nuclear regulatory authorities have requested an assessment of the repository's long-term safety. The purpose is to demonstrate whether the risk of harmful effects in individuals in the vicinity of the repository complies with the acceptance criterion formulated by the Swedish regulatory authorities, i.e. that the risk may not exceed 10-6 per year. Geological data are taken from three sites in Sweden to shed light on different conditions in Swedish granitic bedrock. The future evolution of the repository system is analyzed in the form of five scenarios. The first is a base scenario where the repository is postulated to be built entirely according to specifications and where present-day conditions in the surroundings are postulated to persist. The four other scenarios show how the evolution of the repository differs from that in the base scenario if the repository contains a few initially defective canisters, in the event of climate change, earthquakes, and future inadvertent human intrusion. The time horizon for the analyses is at most one million years, in accordance with preliminary regulations. By means of model studies and calculations, the base scenario analyzes how the radioactivity of the fuel declines with time, the repository's thermal evolution as a result of the decay heat in the fuel, the hydraulic evolution in buffer and backfill when they become saturated with water, and the long-term groundwater flow in the geosphere on the three sites. The overall conclusion of the analyses in the base scenario is that the copper canisters isolating capacity is not threatened by either the mechanical or chemical stresses to which it is subjected. The safety margins are great even in a million-year perspective. The internal evolution in initially defective canisters and the possible resultant migration of radionuclides in buffer, geosphere

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

  20. The importance of environmental education in the process of nuclear and environmental licensing of nuclear facilities

    International Nuclear Information System (INIS)

    Today, there is a thread with regard to the global environment. To reduce the environmental impact due to spending supplies to meet the basic needs of the global population. Can be considered as the power of these needs and in this context, the environmental impact occurs by the use of fossil fuels and loss of land for use of water resources. To minimize these impacts, governments are establishing appropriate laws towards the use of renewable energy. However it appears that there is still a great distance between the established law and implementation in practice. In this context nuclear energy is an attractive option, both economic and environmental. The facilities that are somehow associated with nuclear power plants are classified as radioactive or nuclear. These facilities are subject to two licensing procedures: Environmental (by IBAMA) and Nuclear (by CNEN). Nuclear installations such as nuclear power plants Angra 1 and 2, deposits and tailings facilities of the nuclear fuel cycle in Rezende that are more the attention of the population. As part of these processes are reports of analysis of safety and environmental impacts and socio-economic (EIA/RIMA RFAS), which are available to the public and then discussed at public hearings, where there is the opportunity for questions on these reports. These questions are mainly related with the social-environmental and economic due to construction and operation of these facilities. This work is a research, discussing the law, identifying the difficulties in the licensing process and presents a discussion on the importance of environmental education at all school levels, for adult audiences and is a connection between the environmental education and process of environmental licensing and nuclear, showing how the popular consciousness more informed can better discuss issues associated with these licenses, understand the advantages and disadvantages and obtain benefits. (author)

  1. Deep repository for spent nuclear fuel. SR-97-Post-closure safety. Main Report. Volume I and II

    Energy Technology Data Exchange (ETDEWEB)

    Hedin, A. [ed.

    1999-11-01

    In preparation for coming site investigations for siting of a deep repository for spent nuclear fuel, the Swedish Government and nuclear regulatory authorities have requested an assessment of the repository's long-term safety. The purpose is to demonstrate whether the risk of harmful effects in individuals in the vicinity of the repository complies with the acceptance criterion formulated by the Swedish regulatory authorities, i.e. that the risk may not exceed 10{sup -6} per year. Geological data are taken from three sites in Sweden to shed light on different conditions in Swedish granitic bedrock. The future evolution of the repository system is analyzed in the form of five scenarios. The first is a base scenario where the repository is postulated to be built entirely according to specifications and where present-day conditions in the surroundings are postulated to persist. The four other scenarios show how the evolution of the repository differs from that in the base scenario if the repository contains a few initially defective canisters, in the event of climate change, earthquakes, and future inadvertent human intrusion. The time horizon for the analyses is at most one million years, in accordance with preliminary regulations. By means of model studies and calculations, the base scenario analyzes how the radioactivity of the fuel declines with time, the repository's thermal evolution as a result of the decay heat in the fuel, the hydraulic evolution in buffer and backfill when they become saturated with water, and the long-term groundwater flow in the geosphere on the three sites. The overall conclusion of the analyses in the base scenario is that the copper canisters isolating capacity is not threatened by either the mechanical or chemical stresses to which it is subjected. The safety margins are great even in a million-year perspective. The internal evolution in initially defective canisters and the possible resultant migration of radionuclides in

  2. Deep repository for spent nuclear fuel. SR-97-Post-closure safety. Main Report. Volume I and II

    Energy Technology Data Exchange (ETDEWEB)

    Hedin, A. [ed.

    1999-11-01

    In preparation for coming site investigations for siting of a deep repository for spent nuclear fuel, the Swedish Government and nuclear regulatory authorities have requested an assessment of the repository's long-term safety. The purpose is to demonstrate whether the risk of harmful effects in individuals in the vicinity of the repository complies with the acceptance criterion formulated by the Swedish regulatory authorities, i.e. that the risk may not exceed 10{sup -6} per year. Geological data are taken from three sites in Sweden to shed light on different conditions in Swedish granitic bedrock. The future evolution of the repository system is analyzed in the form of five scenarios. The first is a base scenario where the repository is postulated to be built entirely according to specifications and where present-day conditions in the surroundings are postulated to persist. The four other scenarios show how the evolution of the repository differs from that in the base scenario if the repository contains a few initially defective canisters, in the event of climate change, earthquakes, and future inadvertent human intrusion. The time horizon for the analyses is at most one million years, in accordance with preliminary regulations. By means of model studies and calculations, the base scenario analyzes how the radioactivity of the fuel declines with time, the repository's thermal evolution as a result of the decay heat in the fuel, the hydraulic evolution in buffer and backfill when they become saturated with water, and the long-term groundwater flow in the geosphere on the three sites. The overall conclusion of the analyses in the base scenario is that the copper canisters isolating capacity is not threatened by either the mechanical or chemical stresses to which it is subjected. The safety margins are great even in a million-year perspective. The internal evolution in initially defective canisters and the possible resultant migration of radionuclides in

  3. Development of a standard data base for FBR core nuclear design. 10. Reevaluation of atomic number density of JOYO Mk-II core

    Energy Technology Data Exchange (ETDEWEB)

    Numata, Kazuyuki; Sato, Wakaei [Japan Nuclear Cycle Development Inst., Oarai, Ibaraki (Japan). Oarai Engineering Center; Ishikawa, Makoto; Arii, Yoshio [Nuclear Energy System Incorporation, Tokyo (Japan)

    1999-07-01

    The material composition of JOYO Mk-II core components in its initial core was reevaluated as a part of the effort for developing a standard data base for FBR core nuclear design. The special feature of the reevaluation is to treat the decay of Pu-241 isotope, so that the atomic number densities of Pu-241 and Am-241 in fuel assemblies can be exactly evaluated on the initial critical date, Nov. 22nd, 1982. Further, the atomic number densities of other core components were also evaluated to improve the analytical accuracy. Those include the control rods which were not so strictly evaluated in the past, and the dummy fuels and the neutron sources which were not treated in the analytical model so far. The results of the present reevaluation were as follows: (1) The changes of atomic number densities of the major nuclides such as Pu-239, U-235 and U-238 were about {+-}0.2 to 0.3%. On the other hand, the number density of Pu-241, which was the motivation of the present work, was reduced by 12%. From the fact, the number densities in the past analysis might be based on the isotope measurement of the manufacturing point of time without considering the decay of Pu-241. (2) As the other core components, the number densities of control rods and outer reflector-type A were largely improved. (author)

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

    Science.gov (United States)

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

    2015-01-01

    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 familial clustering of three or more individuals with cancer through construction of a three-generation pedigree and revisited by an itinerant group of medical geneticists. Genetic counseling was carried out with the intent of selecting potential families at risk for hereditary familial cancers. In the first phase of the study, 1,581 families were interviewed by the CHA at their homes. A positive history for cancer was present in 42.3 % of families, comprising 22.3 % with only one case per family, 11.2 % with two cases, and 8.6 % with three or more cases in the family. The informant reported that 15 % of the cases were from the father lineage, 12 % from the mother lineage, and 12.1 % within siblings. In the remaining 60.9 % families, cancer was present in both sides of the family. The types of cancer reported were uterus 8.7 % (n = 137), stomach 7.7 % (n = 122), breast 6.9 % (n = 109), throat 6.8 % (n = 99), prostate 5.4 % (n = 85), lung 5.6 % (n = 88), bowel 3.7 % (n = 59), and unspecified sites in 6.8 % (n = 108) of families. No statistical differences were noted between the data collected on each primary care unit. In the second phase of the study, 136 families (2.9 %) from the total of families interviewed in phase 1 were selected due to the presence of three or more individuals with cancer in the family. Among those, only 73 families attended genetic counseling. Comparison between the data obtained by the CHA and the medical

  5. The Brazilian status on ADS R and D: Preliminary road map to a program on accelerator utilization on basic and applied nuclear physics, products and services and to drive an experimental neutron source sub critical facility

    International Nuclear Information System (INIS)

    Brazil, still a developing country, has an Industrial Nuclear Program, that although small has already achieved a good standard: two NPPs in operation, i.e., ANGRA I and II with 2 GW installed electric capacity are generating approximately 2% of the total installed electricity, a third unit under construction, a fuel cycle industry, INB, with the capability to provide fuel elements for the NPPs. The Brazilian Navy pursues a nuclear program for nuclear propulsion which includes all the front end of the fuel cycle, including the enrichment by ultracentrifuge that is being transferred also to the industrial sector (INB). Research and development is conducted by the various Research Institutes of the Brazilian Nuclear Energy Commission (CNEN): IPEN, CDTN, and IEN which have appropriate technical capability and facilities (research reactors and accelerators) to support the industrial nuclear program, provide products and services for the Brazilian society (e.g., radioisotopes), as well as to develop new technologies. It is fair to say, however, that the Brazilian research institutions do need some new challenges, mainly to motivate and to stimulate a new generation of young engineers and scientists to pursue careers in nuclear energy R and D. The Brazilian Nuclear Physics research, being pursued mainly by the Universities, has an outstanding standard. This is documented by the number of publications in international journals, scientific citations, the number and quality of scientists, and by its capability to form human resources (Ph.D. students). However, it is felt that this scientific potential, a few exceptions apart, still needs to transfer the benefits of the scientific knowledge to the Brazilian society. These boundary conditions call for a R and D program which identifies synergies, society needs, is in agreement with the international developments in science and technology, meets sustainability criteria, matches the Brazilian reality, provides an umbrella for

  6. Development of a multi-objective PBIL evolutionary algorithm applied to a nuclear reactor core reload optimization problem

    International Nuclear Information System (INIS)

    The nuclear reactor core reload optimization problem consists in finding a pattern of partially burned-up and fresh fuels that optimizes the plant's next operation cycle. This optimization problem has been traditionally solved using an expert's knowledge, but recently artificial intelligence techniques have also been applied successfully. The artificial intelligence optimization techniques generally have a single objective. However, most real-world engineering problems, including nuclear core reload optimization, have more than one objective (multi-objective) and these objectives are usually conflicting. The aim of this work is to develop a tool to solve multi-objective problems based on the Population-Based Incremental Learning (PBIL) algorithm. The new tool is applied to solve the Angra 1 PWR core reload optimization problem with the purpose of creating a Pareto surface, so that a pattern selected from this surface can be applied for the plant's next operation cycle. (author)

  7. The retaking of the nuclear power generation option and her expansion in the South Cone; A retomada da opcao nucleoeletrica e os seus desdobramentos no Cone Sul

    Energy Technology Data Exchange (ETDEWEB)

    Mattos, Joao Roberto Loureiro de; Dias, Marcio Soares [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)]. E-mails: jrmattos@cdtn.br; marciod@cdtn.br

    2008-07-01

    From the year 2004 on, members of the brazilian nuclear sector have already indicated this retaking that from the 2008, assumed as an concrete option at the governmental ambient and now is also disseminated in the brazilian society. The 2030 Energy National Plan, recently issued by the Energy Research Enterprise makes official an reference scenery for the nuclear option retaking in the country. That scenery includes the completion of Angra 3 until the 2014, and the construction of four other 1000 MW e power plants, as follows: a fourth plant until 2020; a fifth plant until 2025, and a sixth and seventh plants until 2030. As a complement to that modifications. on February 2008 the Brazil and Argentine presidents signed a joint proclamation for the nuclear cooperation between the two countries, including the study for a power reactor that can attend the electric power of both countries. That retaking brings important unfolding for the industrial sector.

  8. 4. International Conference on Current Problems in Nuclear Physics and Atomic Energy (NPAE-Kyiv2012). Proceedings. Part I and Part II

    International Nuclear Information System (INIS)

    Such wide area of topics, discussed during the Conference, is closely connected with the interests of our country to develop the fundamental research in the field of nuclear physics, which is the base of nuclear energy. The purpose of the Conference was to bring together scientists to share their knowledge in the current problems in nuclear physics and atomic energy. consideration of the spherical ground-state proton emitters, while nuclear deformations are supposed to be further included by standard way

  9. Structure for Transparency in Nuclear Waste Management. Comparative Review of the Structures for Nuclear Waste Management in France, Sweden and the UK. A Report from the RISCOM II Project

    Energy Technology Data Exchange (ETDEWEB)

    Espejo, Raul [Syncho Ltd., Lincoln (United Kingdom)

    2002-11-01

    This report presents a comparison of the structures for nuclear waste management in France, Sweden and the UK. The source materials for this comparison are studies carried out in each of these countries by Syncho Ltd. over the past 5 years. The Swedish structural review was sponsored by SKI and SSI, and carried out as a pilot study during the years 1996 and 1997 as part of the RISCOM Pilot Project. The structural reviews of the British and French nuclear waste management systems have been in progress for the past two years (2001-2002) within the framework of RISCOM II, sponsored by the European Union. This report offers preliminary comparative views of the three systems. As with each of the individual studies more work and information are necessary to confirm and strengthen the findings. To set the context for this report it is important to remind the reader that the study in Sweden was undertaken 5 years ago, that the French case took place at the same time of significant structural changes in the country's nuclear waste management system and that the British case was undertaken at the same time of a far-reaching Government consultation process. In all cases the number of people interviewed was small. In summary, comparing the structures for transparency suggests that once existing channels for transparency are diagnosed, it should be possible to use benchmarks of good practice in one country to design methods to improve participation and communications in others. The framework used in this report allows making comparisons beyond factual reports of similarities or differences. An important conclusion of this report is that the democratic deficits that we experience today as citizens in all societies can be ameliorated if sufficient attention is paid to producing requisite organisations, with adequate communications, capable of bridging the gaps between the silent majorities and those experts and politicians responsible for policy decisions. It is the wisdom

  10. The Relationship between Nuclear Disarmament and Nuclear Nonproliferation

    Institute of Scientific and Technical Information of China (English)

    Sun; Xiangli

    2015-01-01

    The history of nuclear weapons development since the end of World War II is also one of nuclear arms control.There are two major aspects that represent the global efforts of nuclear arms control,which include limiting on nuclear weapon development in quantities and qualities,and limiting on the proliferation of nuclear weapons and the relevant research and development technologies.The limitation on the nuclear weapons development constitute

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

    Energy Technology Data Exchange (ETDEWEB)

    Silva, Diogo Neves Gomes da

    2011-07-01

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

  12. Using neural networks for prediction of nuclear parameters

    International Nuclear Information System (INIS)

    Dating from 1943, the earliest work on artificial neural networks (ANN), when Warren Mc Cullock and Walter Pitts developed a study on the behavior of the biological neuron, with the goal of creating a mathematical model. Some other work was done until after the 80 witnessed an explosion of interest in ANNs, mainly due to advances in technology, especially microelectronics. Because ANNs are able to solve many problems such as approximation, classification, categorization, prediction and others, they have numerous applications in various areas, including nuclear. Nodal method is adopted as a tool for analyzing core parameters such as boron concentration and pin power peaks for pressurized water reactors. However, this method is extremely slow when it is necessary to perform various core evaluations, for example core reloading optimization. To overcome this difficulty, in this paper a model of Multi-layer Perceptron (MLP) artificial neural network type backpropagation will be trained to predict these values. The main objective of this work is the development of Multi-layer Perceptron (MLP) artificial neural network capable to predict, in very short time, with good accuracy, two important parameters used in the core reloading problem - Boron Concentration and Power Peaking Factor. For the training of the neural networks are provided loading patterns and nuclear data used in cycle 19 of Angra 1 nuclear power plant. Three models of networks are constructed using the same input data and providing the following outputs: 1- Boron Concentration and Power Peaking Factor, 2 - Boron Concentration and 3 - Power Peaking Factor. (author)

  13. Using neural networks for prediction of nuclear parameters

    Energy Technology Data Exchange (ETDEWEB)

    Pereira Filho, Leonidas; Souto, Kelling Cabral, E-mail: leonidasmilenium@hotmail.com, E-mail: kcsouto@bol.com.br [Instituto Federal de Educacao, Ciencia e Tecnologia do Rio de Janeiro (IFRJ), Rio de Janeiro, RJ (Brazil); Machado, Marcelo Dornellas, E-mail: dornemd@eletronuclear.gov.br [Eletrobras Termonuclear S.A. (GCN.T/ELETRONUCLEAR), Rio de Janeiro, RJ (Brazil). Gerencia de Combustivel Nuclear

    2013-07-01

    Dating from 1943, the earliest work on artificial neural networks (ANN), when Warren Mc Cullock and Walter Pitts developed a study on the behavior of the biological neuron, with the goal of creating a mathematical model. Some other work was done until after the 80 witnessed an explosion of interest in ANNs, mainly due to advances in technology, especially microelectronics. Because ANNs are able to solve many problems such as approximation, classification, categorization, prediction and others, they have numerous applications in various areas, including nuclear. Nodal method is adopted as a tool for analyzing core parameters such as boron concentration and pin power peaks for pressurized water reactors. However, this method is extremely slow when it is necessary to perform various core evaluations, for example core reloading optimization. To overcome this difficulty, in this paper a model of Multi-layer Perceptron (MLP) artificial neural network type backpropagation will be trained to predict these values. The main objective of this work is the development of Multi-layer Perceptron (MLP) artificial neural network capable to predict, in very short time, with good accuracy, two important parameters used in the core reloading problem - Boron Concentration and Power Peaking Factor. For the training of the neural networks are provided loading patterns and nuclear data used in cycle 19 of Angra 1 nuclear power plant. Three models of networks are constructed using the same input data and providing the following outputs: 1- Boron Concentration and Power Peaking Factor, 2 - Boron Concentration and 3 - Power Peaking Factor. (author)

  14. Proceedings of the Sixth Arab Conference on the Peaceful Uses of Atomic Energy, Vol.II. Scientific Presentation (Reactors, Materials, Fuel Cycles and Nuclear Safety)

    International Nuclear Information System (INIS)

    The publication has been set up as a textbook for researching dealing with health protection during work with Human needs of Nuclear Science and applications. The book consists of the following chapters: Personnel and working environment monitoring; analytical techniques; radiation protection harmonized and integrated policy for the arab country; Nuclear safety; fuel cycles; nuclear medicine; accelerators; medical applications; radiation chemistry; hydrology; environmental studies; biological effects of ionizing radiation on agriculture; radiation accidents

  15. Computational analysis of neutronic parameters for TRIGA Mark-II research reactor using evaluated nuclear data libraries ENDF/B-VII.0 and JENDL-3.3

    International Nuclear Information System (INIS)

    Highlights: • SRAC-PIJ code and SRAC-CITATION have been utilized to model the core. • Most of the simulated results show no significant differences with references. • Thermal peak flux varies a bit due to up condition of TRIGA. • ENDF/B-VII.0 and JENDL-3.3 libraries perform well for neutronics analysis of TRIGA. - Abstract: Important kinetic parameters such as effective multiplication factor, keff, excess reactivity, neutron flux and power distribution, and power peaking factors of TRIGA Mark II research reactor in Bangladesh have been calculated using the comprehensive neutronics calculation code system SRAC 2006 with the evaluated nuclear data libraries ENDF/B-VII.0 and JENDL-3.3. In the code system, PIJ code was employed to obtain cross section of the core cells, followed by the integral calculation of neutronic parameters of the reactor conducted by CITATION code. All the analyses were performed using the 7-group macroscopic cross section library. Results were compared to the experimental data, the safety analysis report (SAR) of the reactor provided by General Atomic as well as to the simulated values by numerically benchmarked MCNP4C, WIMS-CITATION and SRAC-CITATION codes. The maximum power densities at the hot spot were found to be 169.7 W/cc and 170.1 W/cc for data libraries ENDF/B-VII.0 and JENDL-3.3, respectively. Similarly, the total peaking factors based on ENDF/B-VII.0 and JENDL-3.3 were calculated as 5.68 and 5.70, respectively, which were compared to the original SAR value of 5.63, as well as to MCNP4C, WIMS-CITATION and SRAC-CITATION results. It was found in most cases that the calculated results demonstrate a good agreement with our experiments and published works. Therefore, this analysis benchmarks the code system and will be helpful to enhance further neutronics and thermal hydraulics study of the reactor

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

    Energy Technology Data Exchange (ETDEWEB)

    Soares, Abner Duarte

    2010-07-01

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

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

    Directory of Open Access Journals (Sweden)

    Marcelo Neto Galvão

    2009-03-01

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

  18. PREDITORES DA INTENÇÃO DE RETORNO ÀS FEIRAS DE NEGÓCIOS: UM ESTUDO COM O PÚBLICO VISITANTE DA VI COSTA VERDE NEGÓCIOS DE ANGRA DOS REIS-RJ

    Directory of Open Access Journals (Sweden)

    Márcio Moutinho Abdalla

    2012-12-01

    Full Text Available The main objective of this paper is to identify the variables that predict the intentions of the visitors comeback to a business fair held in Angra dos Reis, Rio de Janeiro. The evaluation was conducted through a binary logistic regression model, applied to a cross-sectional sample composed by 277 visitors. As result, it was found that, of eight hypotheses, only three were accepted. Two of them are associated to the impact of the effort and commitment perception, from the visiting public, in the prediction of the comeback intention, and the third is associated to the effect of the perceived benefits from the event to the local economy, also in the prediction of the comeback intention. Considering these results, one can conclude that the study confirms the assumptions of Grönroos (2004, which postulate that the main factors that contribute to the perceived value are associated to the minimization of the customer effort and commitment, and not only to the increasing of the benefits offered.

  19. Deployment of a three-dimensional array of Micro-Pocket Fission Detector triads (MPFD3) for real-time, in-core neutron flux measurements in the Kansas State University TRIGA Mark-II Nuclear Reactor

    Science.gov (United States)

    Ohmes, Martin Francis

    A Micro-Pocket Fission Detector (MPFD) is a miniaturized type of fission chamber developed for use inside a nuclear reactor. Their unique design allows them to be located between or even inside fuel pins while being built from materials which give them an operational lifetime comparable to or exceeding the life of the fuel. While other types of neutron detectors have been made for use inside a nuclear reactor, the MPFD is the first neutron detector which can survive sustained use inside a nuclear reactor while providing a real-time measurement of the neutron flux. This dissertation covers the deployment of MPFDs as a large three-dimensional array inside the Kansas State University TRIGA Mark-II Nuclear Reactor for real-time neutron flux measurements. This entails advancements in the design, construction, and packaging of the Micro-Pocket Fission Detector Triads with incorporated Thermocouple, or MPFD3-T. Specialized electronics and software also had to be designed and built in order to make a functional system capable of collecting real-time data from up to 60 MPFD3-Ts, or 180 individual MPFDs and 60 thermocouples. Design of the electronics required the development of detailed simulations and analysis for determining the theoretical response of the detectors and determination of their size. The results of this research shows that MPFDs can operate for extended times inside a nuclear reactor and can be utilized toward the use as distributed neutron detector arrays for advanced reactor control systems and power mapping. These functions are critical for continued gains in efficiency of nuclear power reactors while also improving safety through relatively inexpensive redundancy.

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

    International Nuclear Information System (INIS)

    This study has the aim to assess the impact of accidental release of tritium postulate from a nuclear power reactor through environmental modeling of aquatic resources. In order to do that it was used computational models of hydrodynamics and transport for the simulation of tritium dispersion caused by an accident in a CANDU reactor located in the ongoing Angra 3 site. This exercise was accomplished with the aid of a code system (SisBAHIA) developed in the Rio de Janeiro Federal University (COPPE/UFRJ). The CANDU reactor is one that uses heavy water (D2O) as moderator and coolant of the core. It was postulated, then, the LOCA (Loss of Coolant Accident) accident in the emergency cooling system of the nucleus (without fusion), where was lost 66 m3 of soda almost instantaneously. This inventory contained 35 PBq and was released a load of 9.7 TBq/s in liquid form near the Itaorna beach, Angra dos Reis - RJ. The models mentioned above were applied in two scenarios (plant stopped and operating) and showed a tritium plume with specific activities larger than the reference level for seawater (1.1 MBq/m3 ) during the first 14 days after the accident. The main difference between the scenario without and with seawater recirculation (pumping and discharge) is based on the enhancement of dilution of the highest concentrations in the last one. This dilution enhancement resulting in decreasing concentrations was observed only during the first two weeks, when they ranged from 1x109 to 5x105 Bq/m3 close to the Itaorna beach spreading just to Sandri Island. After 180 days, the plume could not be detected anymore in the bay, because their activities would be lower than the minimum detectable value (3). (author)

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

    International Nuclear Information System (INIS)

    This study has the aim to assess the impact of accidental release of tritium postulate from a nuclear power reactor through environmental modeling of aquatic resources. In order to do that it was used computational models of hydrodynamics and transport for the simulation of tritium dispersion caused by an accident in a CANDU reactor located in the ongoing Angra 3 site. It was postulated, then, the LOCA - Loss of Coolant Accident -, accident in the emergency cooling system of the nucleus ( without fusion), where was lost 66m3 of soda almost instantaneously. This inventory contained 35 PBq and was released a load of 9.7 TBq/s in liquid form near the Itaorna beach, Angra dos Reis - RJ. The models mentioned above were applied in two scenarios ( plant stopped or operating) and showed a tritium plume with specific activities larger than the reference level for seawater (1.1MBq/m3), during the first 14 days after the accident. The main difference between the scenario without and with seawater recirculation (pumping and discharge) is based on the enhancement of dilution of the highest concentrations in the last one. This dilution enhancement resulting in decreasing concentrations was observed only during the first two weeks, when they ranged from 1x109 to 5x105 Bq/m3 close to the Itaorna beach spreading just to Sandri Island. After 180 days, the plume could not be detected anymore in the bay, because their activities would be lower than the minimum detectable value (3). (author)

  2. The LLNL Heavy Element Facility -- Facility Management, Authorization Basis, and Readiness Assessment Lessons Learned in the Heavy Element Facility (B251) Transition from Category II Nuclear Facility to Radiological Facility

    Energy Technology Data Exchange (ETDEWEB)

    Mitchell, M; Anderson, B; Brown, E; Gray, L

    2006-04-10

    This paper presents Facility Management, Readiness Assessment, and Authorization Basis experience gained and lessons learned during the Heavy Element Facility Risk Reduction Program (RRP). The RRP was tasked with removing contaminated glove boxes, radioactive inventory, and contaminated ventilation systems from the Heavy Element Facility (B251) at Lawrence Livermore National Laboratory (LLNL). The RRP was successful in its goal in April 2005 with the successful downgrade of B251 from a Category II Nuclear Facility to a Radiological Facility. The expertise gained and the lessons learned during the planning and conduct of the RRP included development of unique approaches in work planning/work control (''Expect the unexpected and confirm the expected'') and facility management. These approaches minimized worker dose and resulted in significant safety improvements and operational efficiencies. These lessons learned can help similar operational and management activities at other sites, including facilities restarting operations or new facility startup. B251 was constructed at LLNL to provide research areas for conducting experiments in radiochemistry using transuranic elements. Activities at B251 once included the preparation of tracer sets associated with the underground testing of nuclear devices and basic research devoted to a better understanding of the chemical and nuclear behavior of the transuranic elements. Due to the age of the facility, even with preventative maintenance, facility safety and experimental systems were deteriorating. A variety of seismic standards were used in the facility design and construction, which encompassed eight building increments constructed over a period of 26 years. The cost to bring the facility into compliance with the current seismic and other requirements was prohibitive, and simply maintaining B251 as a Category II nuclear facility posed serious cost considerations under a changing regulatory environment

  3. Aquatic macro algae of a region under Almirante Alvaro Alberto nuclear power plant influence. I. Taxonomic composition; Macroalgas marinhas da regiao sob influencia da Central Nuclear Almirante Alvaro Alberto, Angra dos Reis, RJ, Brasil. I. Composicao taxonomica

    Energy Technology Data Exchange (ETDEWEB)

    Pedrini, A.G. [Instituto de Radioprotecao e Dosimetria (IRD), Rio de Janeiro, RJ (Brazil)]|[Universidade Santa Ursula, Rio de Janeiro, RJ (Brazil). Centro de Ciencias Biologicas; Cassano, V.; Coelho, L.G.; Labronici, G.J. [Universidade do Estado, Rio de Janeiro, RJ (Brazil). Inst. de Biologia

    1994-12-31

    A total of 134 taxa were found: 32 Chlorophyta, 29 Phaeophyta and 74 Rhodophyta. The Caulerpales (Chlorophyta) had the highest number of taxa (37,5%) followed by the Dictyotales (Phaeophyta - 43%) and Ceramiales (Rhodophyta - 53%). The benthic flora shows some affinity to that of Ilha Grande (part), Sepetiba Bay and Paraty (Sorensen`s Index - 0,62, 0,61 and 0,58 respectively. (author). 22 refs, 1 fig, 1 tab.

  4. Nuclear power data 2016; Kernenergie in Zahlen 2016

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2016-04-15

    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.

  5. Heat shock protein 70 protects against seizure-induced neuronal cell death in the hippocampus following experimental status epilepticus via inhibition of nuclear factor-κB activation-induced nitric oxide synthase II expression.

    Science.gov (United States)

    Chang, Chiung-Chih; Chen, Shang-Der; Lin, Tsu-Kung; Chang, Wen-Neng; Liou, Chia-Wei; Chang, Alice Y W; Chan, Samuel H H; Chuang, Yao-Chung

    2014-02-01

    Status epilepticus induces subcellular changes that may eventually lead to neuronal cell death in the hippocampus. Based on an animal model of status epilepticus, our laboratory showed previously that sustained hippocampal seizure activity activates nuclear factor-κB (NF-κB) and upregulates nitric oxide synthase (NOS) II gene expression, leading to apoptotic neuronal cell death in the hippocampus. The present study examined the potential modulatory role of heat shock protein 70 (HSP70) on NF-κB signaling in the hippocampus following experimental status epilepticus. In Sprague-Dawley rats, kainic acid (KA) was microinjected unilaterally into the hippocampal CA3 subfield to induce prolonged bilateral seizure activity. Expression of HSP70 was elevated as early as 1h after the elicitation of sustained seizure activity, followed by a progressive elevation that peaked at 24h. Pretreatment with an antisense oligonucleotide against hsp70 decreased the HSP70 expression, and significantly augmented IκB kinase (IKK) activity and phosphorylation of IκBα, alongside enhanced nuclear translocation and DNA binding activity of NF-κB in the hippocampal CA3 neurons and glial cells. These cellular events were followed by enhanced upregulation of NOS II and peroxynitrite expression 3h after sustained seizure activity that led to an increase of caspase-3 and DNA fragmentation in the hippocampal CA3 neurons 7days after experimental status epilepticus. We concluded that HSP70 protects against apoptotic cell death induced by NF-κB activation and NOS II-peroxynitrite signaling cascade in the hippocampal CA3 and glial cells following experimental status epilepticus via suppression of IKK activity and deactivation of IκBα.

  6. Nuclear Capacity Auctions

    OpenAIRE

    Fridolfsson, Sven-Olof; Tangerås, Thomas

    2011-01-01

    We propose nuclear capacity auctions as a means to improve the incentives for investing in nuclear power. A properly designed auction would (i) allocate the license to the most efficient bidder; (ii) sell the license if and only if new nuclear power was socially optimal. In particular, capacity auctions open the market for large-scale entry by outside firms. Requiring licensees to sell a share of capacity as virtual power plant contracts increases auction efficiency by softening incumbent pro...

  7. I. Nuclear Production Reaction and Chemical Isolation Procedure for 240Am II. New Superheavy Element Isotopes: 242Pu(48Ca,5n)285-114

    OpenAIRE

    Ellison, Paul Andrew

    2011-01-01

    Part I discusses the study of a new nuclear reaction and chemical separation procedure for the production of 240Am. Thin 242Pu, natTi, and natNi targets were coincidently activated with protons from the 88-Inch Cyclotron, producing 240Am, 48V, and 57Ni, respectively. The radioactive decay of these isotopes was monitored using high-purity Ge gamma ray detectors in the weeks following irradiation. The excitation function for the 242Pu(p, 3n)240Am nuclear reaction was measured to be lower than t...

  8. DECOVALEX - Mathematical models of coupled T-H-M processes for nuclear waste repositories. Executive summary for Phases I,II and III

    International Nuclear Information System (INIS)

    This executive summary presents the motivation, structure, objectives, methodologies and results of the first stage of the international DECOVALEX project - DECOVALEX I (1992-1995). The acronym stands for Development of Coupled Models and their Validation against Experiment in Nuclear Waste Isolation, and the project is an international effort to develop mathematical models, numerical methods and computer codes for coupled thermo-hydro-mechanical processes in fractured rocks and buffer materials for geological isolation of spent nuclear fuel and other radioactive wastes, and validate them against laboratory and field experiments. 24 refs

  9. Presentation of safety after closure of the repository for spent nuclear fuel. Main report of the project SR-Site. Part II; Redovisning av saekerhet efter foerslutning av slutfoervaret foer anvaent kaernbraensle. Huvudrapport fraan projekt SR-Site. Del II

    Energy Technology Data Exchange (ETDEWEB)

    2011-07-01

    The purpose of the safety assessment SR-Site is to investigate whether a safe repository for spent nuclear fuel by KBS-3 type can be constructed at Forsmark in Oesthammar in Sweden. The location of the Forsmark has been selected based on results of several surveys from surface conditions at depth in Forsmark and in Laxemar in Oskarshamn. The choice of location is not justified in SR-Site Report, but in other attachments to SKB's permit applications. SR-Site Report is an important part of SKB's permit applications to construct and operate a repository for spent nuclear fuel at Forsmark in Oesthammar. The purpose of the report in the applications is to show that a repository at Forsmark is safe after closure

  10. Study of different fitness functions with safety restriction for nuclear reactor reload problem using QDPSO

    Energy Technology Data Exchange (ETDEWEB)

    Oliveira, Paulo C. de, E-mail: paulocaixeta@poli.ufrj.br [Universidade Federal do Rio de Janeiro (UFRJ), Rio de Janeiro, RJ (Brazil). Departamento de Engenharia Nuclear; Lima, Alan M.M. de; Schirru, Roberto, E-mail: alan@lmp.ufrj.br, E-mail: schirru@lmp.ufrj.br [Coordenacao dos Programas de Pos-Graduacao em Engenharia (COPPE/UFRJ), Rio de Janeiro, RJ (Brazil)

    2015-07-01

    Nuclear Reactor Reload Problem (NRRP) is a classical problem in Nuclear Engineering that has been studied for more than 40 years, which focuses on the economics and safety of the Nuclear Power Plant (NPP). This problem consists in searching for the best loading pattern of fuel assemblies (FA) in the core, aiming to determine the permutation of fuel assemblies that optimizes the uranium utilization, with fitness function evaluated according to specific criteria and methods of nuclear reactor physics, such as the maximum mean power peak and the boron concentration. In this article will be presented different methodologies to obtain a representative fitness function for NRRP, where Quantum particle Swarm optimization (QPSO) was used to determine which one gives the best array of fuel assemblies that will make the maximum EFPD (Effective Full Power Days) with the least computational effort. In this approach, as well as others in literature, was not used Burnable Poison in the simulations and the results will be compared in relation of the maximization of the cycle length considering the boron concentration yield by the reactor physics code, to make sure that the configuration is valid from a safety point of view. This paper was based on Angra 1's seventh reload cycle. (author)

  11. DIFFUSION IN THE VICINITY OF STANDARD-DESIGN NUCLEAR POWER PLANTS--II: WIND-TUNNEL EVALUATION OF BUILDING-WAKE CHARACTERISTICS

    Science.gov (United States)

    Laboratory experiments were conducted to simulate radiopollutant effluents released to the atmosphere from two standard-design nuclear power plants. The main objective of the study was to compare the dispersion in the wakes of the plants with that in a simulated atmospheric bound...

  12. High Resolution Nuclear Magnetic Resonance Studies of the Active Site of Chymotrypsin. II. Polarization of Histidine 57 by Substrate Analogues and Competitive Inhibitors

    NARCIS (Netherlands)

    Robillard, G.; Shulman, R.G.

    1974-01-01

    The proton nuclear magnetic resonance signal of the His57-Asp102 hydrogen bonded proton in the charge relay system of chymotrypsinogen A and chymotrypsin Aδ has been monitored to determine the influence of substrate analogues and competitive inhibitors on the electronic state of the active site regi

  13. Validation of WIMS-SNAP code systems for calculations in TRIGA-MARK II type reactors; Validacion del sistema de codigos WIMS-SNAP para calculos en reactores nucleares tipo TRIGA-MARK II

    Energy Technology Data Exchange (ETDEWEB)

    Hernandez Valle, S.; Lopez Aldama, D. [Centro de Investigaciones Nucleares, Tecnologicas y Ambientales, La Habana (Cuba). E-mail: svalle@ctn.isctn.edu.cu

    2000-07-01

    The following paper contributes to validate the Nuclear Engineering Department methods to carry out calculations in TRIGA reactors solving a Benchmark. The benchmark is analyzed with the WIMS-D/4-SNAP/3D code system and using the cross section library WIMS-TRIGA. A brief description of the DSN method is presented used in WIMS/d{sup 4} code and also the SNAP-3d code is shortly explained. The results are presented and compared with the experimental values. In other hand the possible error sources are analyzed. (author)

  14. Analyses of promoter-proximal pausing by RNA polymerase II on the hsp70 heat shock gene promoter in a Drosophila nuclear extract.

    OpenAIRE

    Li, B.; Weber, J. A.; Chen, Y; Greenleaf, A L; Gilmour, D S

    1996-01-01

    Analyses of Drosophila cells have revealed that RNA polymerase II is paused in a region 20 to 40 nucleotides downstream from the transcription start site of the hsp70 heat shock gene when the gene is not transcriptionally active. We have developed a cell-free system that reconstitutes this promoter-proximal pausing. The paused polymerase has been detected by monitoring the hyperreactivity of thymines in the transcription bubble toward potassium permanganate. The pattern of permanganate reacti...

  15. Material control in nuclear fuel fabrication facilities. Part II. Accountability, instrumntation, and measurement techniques in fuel fabrication facilities, P.O.1236909. Final report

    International Nuclear Information System (INIS)

    This report describes the measurement techniques, the instrumentation, and the procedures used in accountability and control of nuclear materials, as they apply to fuel fabrication facilities. Some of the material included has appeared elswhere and it has been summarized. An extensive bibliography is included. A spcific example of application of the accountability methods to a model fuel fabrication facility which is based on the Westinghouse Anderson design

  16. Health effects model for nuclear power plant accident consequence analysis. Part I. Introduction, integration, and summary. Part II. Scientific basis for health effects models

    Energy Technology Data Exchange (ETDEWEB)

    Evans, J.S.; Moeller, D.W.; Cooper, D.W.

    1985-07-01

    Analysis of the radiological health effects of nuclear power plant accidents requires models for predicting early health effects, cancers and benign thyroid nodules, and genetic effects. Since the publication of the Reactor Safety Study, additional information on radiological health effects has become available. This report summarizes the efforts of a program designed to provide revised health effects models for nuclear power plant accident consequence modeling. The new models for early effects address four causes of mortality and nine categories of morbidity. The models for early effects are based upon two parameter Weibull functions. They permit evaluation of the influence of dose protraction and address the issue of variation in radiosensitivity among the population. The piecewise-linear dose-response models used in the Reactor Safety Study to predict cancers and thyroid nodules have been replaced by linear and linear-quadratic models. The new models reflect the most recently reported results of the follow-up of the survivors of the bombings of Hiroshima and Nagasaki and permit analysis of both morbidity and mortality. The new models for genetic effects allow prediction of genetic risks in each of the first five generations after an accident and include information on the relative severity of various classes of genetic effects. The uncertainty in modeloling radiological health risks is addressed by providing central, upper, and lower estimates of risks. An approach is outlined for summarizing the health consequences of nuclear power plant accidents. 298 refs., 9 figs., 49 tabs.

  17. Test-system for the control and selection of tests applicable to a weldment and its documentation for assembling the Angra - 2 pipelines

    International Nuclear Information System (INIS)

    Due to quality assurance characteristics applicable to the construction of a Nuclear Power Plant, the welding inspection for the piping erection becomes a very well controlled and documented activity. By means of informatic support, a system was developed for the control and selection of testes applicable to a weldment according to the suitable specification. As a result, it is obtained: cost reduction during the project phase, expedition of modifications due to isometric revision, better control and follow-up of inspections activities and piping erection, and the guarantee of the correct interpretation for the applicable specification. (author)

  18. Estudio termodinámico y estructural de un escenario transitorio de Blackout en la planta nuclear de Ascó II con el código RELAP5/SCDAP

    OpenAIRE

    Weill , Vincent

    2005-01-01

    Esta memoria incluye una primera parte descriptiva del modelo de planta de Ascó II, modelo híbrido realizado utilizando el código de cálculo RELAP5/SCDAP. El término híbrido significa que se trata de dos aspectos del diseño de la planta nuclear: la descripción de la vasija con su nodalización específica SCDAP y la descripción de la parte hidrodinámica, es decir de todos los otros componentes, con una nodalización RELAP. Una vez el modelo descrito, se introducirá el escenario es...

  19. Expert system with fuzzy logic for the calculation of performance and security indicators in monitoring and strategic planning of nuclear power plants; Sistema especialista com logica nebulosa para o calculo de indicadores de desempenho e seguranca na monitoracao e planejamento estrategico de usinas nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Souto, Kelling C.; Schirru, Roberto [Universidade Federal, Rio de Janeiro, RJ (Brazil). Coordenacao dos Programas de Pos-graduacao de Engenharia. Lab. de Monitoracao de Processos]. E-mail: kelling@lmp.ufrj.br; schirru@lmp.ufrj.br

    2005-07-01

    This work develops the start to an expert system, which is able to infer about a generic structure of indicators, in order to monitor, measure and evaluate questions related to project, security operation and human performance according to politics, objectives and goals of the nuclear power plant Angra 2. This structure, organized in graphics, inserted in the context of orientation towards objects, represents the knowledge about the expert system and is mapped out in a fuzzy context. The engine of inference is of backward chaining type associated to a process of search in depths, in such a way that it establishes the representative status of the plant, making possible to analyze and manage the mission of its situation. (author)

  20. Coordination Nature of 4-Mercaptoaniline to Sn(II Ion: Formation of a One Dimensional Coordination Polymer and Its Decomposition to a Mono Nuclear Sn(IV Complex

    Directory of Open Access Journals (Sweden)

    Eon S. Burkett

    2014-12-01

    Full Text Available The coordination of the bifunctional ligand 4-mercaptoaniline with aqueo us tin(II metal ion was studied. A coordination polymer was synthesized when an aqueous solution of SnCl2 was treated with 4-MA. The crystalline material is stable under atmospheric conditions retaining its oxidation state. However, when submerged in a solution saturated with oxygen, the compound oxidizes to a mononuclear tin(IV complex. Both the compounds were characterized by single crystal X-ray diffraction studies. Although the structure of the tin(IV complex was previously reported, crystal structure of this compound was redetermined.

  1. The thermal column. A new irradiation position for fission-track dating in the University of Pavia Triga Mark II nuclear reactor

    International Nuclear Information System (INIS)

    In the present paper a new irradiation position arranged for fission-track dating in the Triga Mark II reactor of the University of Pavia is described. Fluence values determined using the NIST glass standard SRM 962a for fission-track dating and the traditional metal foils are compared. Relatively high neutron thermalization (cadmium ratio of 85.3 for gold and 643 for cobalt) and lack of significant fluence spatial gradients are very favorable factors for fission-track dating. Finally, international age standards (or putative age standards) irradiated in this new position yielded results consistent with independent reference ages. (author). 9 refs., 2 figs., 4 tabs

  2. I. Excluded Volume Effects in Ising Cluster Distributions and Nuclear Multifragmentation II. Multiple-Chance Effects in α-Particle Evaporation

    Energy Technology Data Exchange (ETDEWEB)

    Breus, Dimitry Eugene [Univ. of California, Berkeley, CA (United States)

    2005-05-16

    In Part 1, geometric clusters of the Ising model are studied as possible model clusters for nuclear multifragmentation. These clusters may not be considered as non-interacting (ideal gas) due to excluded volume effect which predominantly is the artifact of the cluster's finite size. Interaction significantly complicates the use of clusters in the analysis of thermodynamic systems. Stillinger's theory is used as a basis for the analysis, which within the RFL (Reiss, Frisch, Lebowitz) fluid-of-spheres approximation produces a prediction for cluster concentrations well obeyed by geometric clusters of the Ising model. If thermodynamic condition of phase coexistence is met, these concentrations can be incorporated into a differential equation procedure of moderate complexity to elucidate the liquid-vapor phase diagram of the system with cluster interaction included. The drawback of increased complexity is outweighted by the reward of greater accuracy of the phase diagram, as it is demonstrated by the Ising model. A novel nuclear-cluster analysis procedure is developed by modifying Fisher's model to contain cluster interaction and employing the differential equation procedure to obtain thermodynamic variables. With this procedure applied to geometric clusters, the guidelines are developed to look for excluded volume effect in nuclear multifragmentation. In part 2, an explanation is offered for the recently observed oscillations in the energy spectra of α-particles emitted from hot compound nuclei. Contrary to what was previously expected, the oscillations are assumed to be caused by the multiple-chance nature of α-evaporation. In a semi-empirical fashion this assumption is successfully confirmed by a technique of two-spectra decomposition which treats experimental α-spectra has having contributions from at least two independent emitters. Building upon the success of the multiple-chance explanation of the oscillations, Moretto's single

  3. Insights of probabilistic risk analysis on the development of severe accident management guidance: a case study for a plant similar to ANGRA I

    International Nuclear Information System (INIS)

    Probabilistic Risk Analysis (PRA) surges as a way to evaluate the risk of Nuclear Power Plants (NPPs) and to quantify it. Its objective was to track sequences of accidents and define mitigate actions to prevent core damage. But when the core is damaged the question is how to avoid releases of radionuclides to the environment. PRA evaluates this scenario too and is input to the Severe Accident Management Guidance (SAMG). This paper aims in the interaction between PRA and SAMG, both under development for the Brazilian NPPs, focusing in one specific Plant Damage State (PDS). The objective is to develop an Accident Progression Event Tree (APET) proposing the mitigate actions for the event, helping to understand the phenomena.(author)

  4. Nuclear Medicine

    Science.gov (United States)

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

  5. I. A comparative study of ribo-, deoxyribo-, and hybrid oligonucleotide helices by nuclear magnetic resonance. II. Optical studies of ethidium binding to oligonucleotides

    Energy Technology Data Exchange (ETDEWEB)

    Pardi, A.

    1980-11-01

    The conformations and the helix-to-coil transitions in the following oligonucleotides: (I) a DNA duplex dCT/sub 5/G + dCA/sub 5/G; (II) an RNA duplex rCU/sub 5/G + rCA/sub 5/G; (III) a DNA-RNA hybrid duplex dCT/sub 5/G + rCA/sub 5/G; and (IV) a DNA-RNA hybrid triplex rCU/sub 5/G + dCA/sub 5/G were studied. The first three mixtures all form stable double helical structures at 5/sup 0/C, whereas IV forms a triple strand with a ratio of 2:1 rCU/sub 5/G:dCA/sub 5/G. The chemical shifts of the imino protons in the double strands indicate that I, II, and III have different conformations in solution. This implies a significant change in helical parameters. The chemical shift and sugar pucker data are consistent with helix I having B form geometry, whereas II and III have A (or A') geometry. The chemical shifts of the base protons in system I had transition midpoints of 28 to 30/sup 0/C indicating an all-or-none transition. The exchange lifetimes of the imino protons on helix I were a factor of two longer, for the interior A.T base pairs, than those on helix III. This reflects the greater stability of the DNA helix compared to the hybrid helix. The two terminal C.G base pairs in helix I were also found to have much different exchange rates, indicative of a sequence dependence for these exchange rates. The thermodynamic properties of ethidium binding to several oligonucleotides were investigated. The order of the stability for the 2:1 oligonucleotide:ethidium complexes was found to be rCpG > dCpG > rCpUpG approx. = rUpA > rGpUpG + rCpC. These complexes present models for a possible mechanism for frameshift mutagenesis by ethidium. A large positive induced circular dichroism (CD) has been observed for ethidium upon intercalation into nucleic acids. (ERB)

  6. Chromosome aberrations induced in human lymphocytes by U-235 fission neutrons: I. Irradiation of human blood samples in the "dry cell" of the TRIGA Mark II nuclear reactor.

    Science.gov (United States)

    Fajgelj, A; Lakoski, A; Horvat, D; Remec, I; Skrk, J; Stegnar, P

    1991-11-01

    A set-up for irradiation of biological samples in the TRIGA Mark II research reactor in Ljubljana is described. Threshold activation detectors were used for characterisation of the neutron flux, and the accompanying gamma dose was measured by TLDs. Human peripheral blood samples were irradiated "in vitro" and biological effects evaluated according to the unstable chromosomal aberrations induced. Biological effects of two types of cultivation of irradiated blood samples, the first immediately after irradiation and the second after 96 h storage, were studied. A significant difference in the incidence of chromosomal aberrations between these two types of samples was obtained, while our dose-response curve fitting coefficients alpha 1 = (7.71 +/- 0.09) x 10(-2) Gy-1 (immediate cultivation) and alpha 2 = (11.03 +/- 0.08) x 10(-2) Gy-1 (96 h delayed cultivation) are in both cases lower than could be found in the literature.

  7. Chromosome aberrations induced in human lymphocytes by U-235 fission neutrons: I. Irradiation of human blood samples in the "dry cell" of the TRIGA Mark II nuclear reactor.

    Science.gov (United States)

    Fajgelj, A; Lakoski, A; Horvat, D; Remec, I; Skrk, J; Stegnar, P

    1991-11-01

    A set-up for irradiation of biological samples in the TRIGA Mark II research reactor in Ljubljana is described. Threshold activation detectors were used for characterisation of the neutron flux, and the accompanying gamma dose was measured by TLDs. Human peripheral blood samples were irradiated "in vitro" and biological effects evaluated according to the unstable chromosomal aberrations induced. Biological effects of two types of cultivation of irradiated blood samples, the first immediately after irradiation and the second after 96 h storage, were studied. A significant difference in the incidence of chromosomal aberrations between these two types of samples was obtained, while our dose-response curve fitting coefficients alpha 1 = (7.71 +/- 0.09) x 10(-2) Gy-1 (immediate cultivation) and alpha 2 = (11.03 +/- 0.08) x 10(-2) Gy-1 (96 h delayed cultivation) are in both cases lower than could be found in the literature. PMID:1962281

  8. Global disturbances of the ionosphere caused by the electric field from the high-altitude nuclear explosion 'Starfish' on July 9, 1962. I, II

    Science.gov (United States)

    Tsedilina, E. E.; Shashun'kina, V. M.

    1990-10-01

    The theory of the formation of an artifical radiation belt of high-energy electrons in the magnetosphere is used to examine possible ionospheric effects from the electric field generated by the Starfish nuclear test explosion over Johnston Island on July 9, 1962. A region in the Northern Hemisphere is identified where the explosion led to a drop in electron density in the F-region maximum by about 20 percent and a lowering of the layer by 20-30 km in the course of one hour after the explosion. The F-layer gradually came back to normal in the following hour. It is suggested that, in the initial period after the explosion, this effect was associated with the western electric field, which caused the lowering of the F-layer, as well as with changes in the recombination-diffusion balance in this layer.

  9. Optimization of automation: II. Estimation method of ostracism rate based on the loss of situation awareness of human operators in nuclear power plants

    International Nuclear Information System (INIS)

    Highlights: • We analyze the relationship between Out-of-the-Loop and the loss of human operators’ situation awareness. • We propose an ostracism rate estimation method by only considering the negative effects of automation. • The ostracism rate reflects how much automation interrupts human operators to receive information. • The higher the ostracism rate is, the lower the accuracy of human operators’ SA will be. - Abstract: With the introduction of automation in various industries including the nuclear field, its side effect, referred to as the Out-of-the-Loop (OOTL) problem, has emerged as a critical issue that needs to be addressed. Many studies have been attempted to analyze and solve the OOTL problem, but this issue still needs a clear solution to provide criteria for introducing automation. Therefore, a quantitative estimation method for identifying negative effects of automation is proposed in this paper. The representative aspect of the OOTL problem in nuclear power plants (NPPs) is that human operators in automated operations are given less information than human operators in manual operations. In other words, human operators have less opportunity to obtain needed information as automation is introduced. From this point of view, the degree of difficulty in obtaining information from automated systems is defined as the Level of Ostracism (LOO). Using the LOO and information theory, we propose the ostracism rate, which is a new estimation method that expresses how much automation interrupts human operators’ situation awareness. We applied production rules to describe the human operators’ thinking processes, Bayesian inference to describe the production rules mathematically, and information theory to calculate the amount of information that human operators receive through observations. The validity of the suggested method was proven by conducting an experiment. The results show that the ostracism rate was significantly related to the accuracy

  10. Transfer of Tritium in the Environment after Accidental Releases from Nuclear Facilities. Report of Working Group 7 Tritium Accidents of EMRAS II Topical Heading Approaches for Assessing Emergency Situations. Environmental Modelling for Radiation Safety (Emras II) Programme

    International Nuclear Information System (INIS)

    Environmental assessment models are used for evaluating the radiological impact of actual and potential releases of radionuclides to the environment. They are essential tools for use in the regulatory control of routine discharges to the environment and also in planning measures to be taken in the event of accidental releases. They are also used for predicting the impact of releases which may occur far into the future, for example, from underground radioactive waste repositories. It is important to verify, to the extent possible, the reliability of the predictions of such models by a comparison with measured values in the environment or with predictions of other models. The IAEA has been organizing programmes of international model testing since the 1980s. These programmes have contributed to a general improvement in models, in the transfer of data and in the capabilities of modellers in Member States. IAEA publications on this subject over the past three decades demonstrate the comprehensive nature of the programmes and record the associated advances which have been made. From 2009 to 2011, the IAEA organized a programme entitled Environmental Modelling for RAdiation Safety (EMRAS II), which concentrated on the improvement of environmental transfer models and the development of reference approaches to estimate the radiological impacts on humans, as well as on flora and fauna, arising from radionuclides in the environment. Different aspects were addressed by nine working groups covering three themes: reference approaches for human dose assessment, reference approaches for biota dose assessment and approaches for assessing emergency situations. This publication describes the work of the Tritium Accidents Working Group

  11. Unsymmetrical Chelation of N-Thioether-Functionalized Bis(diphenylphosphino)amine-Type Ligands and Substituent Effects on the Nuclearity of Iron(II) Complexes: Structures, Magnetism, and Bonding.

    Science.gov (United States)

    Fliedel, Christophe; Rosa, Vitor; Falceto, Andrés; Rosa, Patrick; Alvarez, Santiago; Braunstein, Pierre

    2015-07-01

    Starting from the short-bite ligands N-thioether-functionalized bis(diphenylphosphino)amine-type (Ph2P)2N(CH2)3SMe (1) and (Ph2P)2N(p-C6H4)SMe (2), the Fe(II) complexes [FeCl2(1)]n (3), [FeCl2(2)]2 (4), [Fe(OAc)(1)2]PF6 (5), and [Fe(OAc)(2)2]PF6 (6) were synthesized and characterized by Fourier transform IR, mass spectrometry, elemental analysis, and also by X-ray diffraction for 3, 4, and 6. Complex 3 is a coordination polymer in which 1 acts as a P,P-pseudochelate and a (P,P),S-bridge, whereas 4 has a chlorido-bridged dinuclear structure in which 2 acts only as a P,P-pseudochelate. Since these complexes were obtained under strictly similar synthetic and crystallization conditions, these unexpected differences were ascribed to the different spacer between the nitrogen atom and the −SMe group. In both compounds, one Fe–P bond was found to be unusually long, and a theoretical analysis was performed to unravel the electronic or steric reasons for this difference. Density functional theory calculations were performed for a set of complexes of general formula [FeCl2(SR2){R21PN(R2)P′R23}] (R = H, Me; R1, R2, and R3 = H, Me, Ph), to understand the reasons for the significant deviation of the iron coordination sphere away from tetrahedral as well as from trigonal bipyramidal and the varying degree of unsymmetry of the two Fe–P bonds involving pseudochelating PN(R)P ligands. Electronic factors nicely explain the observed structures, and steric reasons were further ruled out by the structural analysis in the solid-state of the bis-chelated complex 6, which displays usual and equivalent Fe–P bond lengths. Magnetic susceptibility studies were performed to examine how the structural differences between 3 and 4 would affect the interactions between the iron centers, and it was concluded that 3 behaves as an isolated high-spin Fe(II) mononuclear complex, while significant intra- and intermolecular ferromagnetic interactions were evidenced for 4 at low temperatures

  12. Environmental Sensitivity in Nuclear Emergencies in Rural and Semi-natural Environments. Report of Working Group 8, Environmental Sensitivity of EMRAS II Topical Heading Approaches for Assessing Emergency Situations. Environmental Modelling for RAdiation Safety (EMRAS II) Programme

    International Nuclear Information System (INIS)

    Environmental assessment models are used for evaluating the radiological impact of actual and potential releases of radionuclides to the environment. They are essential tools for use in the regulatory control of routine discharges to the environment and also in planning measures to be taken in the event of accidental releases. They are also used for predicting the impact of releases which may occur far into the future, for example, from underground radioactive waste repositories. It is important to verify, to the extent possible, the reliability of the predictions of such models by comparison with measured values in the environment or by comparing them with the predictions of other models. The IAEA has been organizing programmes of international model testing since the 1980s. The programmes have contributed to a general improvement in models, in transfer data and in the capabilities of modellers in Member States. IAEA publications on this subject over the past three decades demonstrate the comprehensive nature of the programmes and record the associated advances which have been made. From 2009 to 2011, the IAEA organized a programme entitled Environmental Modelling for RAdiation Safety (EMRAS II), which concentrated on the improvement of environmental transfer models and the development of reference approaches to estimate the radiological impacts on humans, as well as on flora and fauna, arising from radionuclides in the environment. The following topics were addressed in nine working groups: Reference Approaches for Human Dose Assessment - Working Group 1: Reference Methodologies for Controlling Discharges of Routine Releases; - Working Group 2: Reference Approaches to Modelling for Management and Remediation at NORM and Legacy Sites; - Working Group 3: Reference Models for Waste Disposal Reference Approaches for Biota Dose Assessment; - Working Group 4: Biota Modelling; - Working Group 5: Wildlife Transfer Coefficient Handbook; - Working Group 6: Biota Dose

  13. Synthesis, crystal structure and magnetic properties of three unprecedented tri-nuclear and one very rare tetra-nuclear copper(II) Schiff-base complexes supported by mixed azido/phenoxo/nitrato or acetato bridges.

    Science.gov (United States)

    Biswas, Chaitali; Drew, Michael G B; Ruiz, Eliseo; Estrader, Marta; Diaz, Carmen; Ghosh, Ashutosh

    2010-08-28

    Three novel mixed bridged trinuclear and one tetranuclear copper(II) complexes of tridentate NNO donor Schiff base ligands [Cu(3)(L(1))(2)(mu(1,1)-N(3))(2)(CH(3)OH)(2)(BF(4))(2)] (1), [Cu(3)(L(1))(2)(mu(1,1)-N(3))(2)(mu-NO(3)-1kappaO:2kappaO')(2)] (2), [Cu(3)(L(2))(2)(mu(1,1)-N(3))(2)(mu-NO(3)-1kappaO:2kappaO')(2)] (3) and [Cu(4)(L(3))(2)(mu(1,1)-N(3))(4)(mu-CH(3)COO-1kappaO:2kappaO')(2)] (4) have been synthesized by reaction of the respective tridentate ligands (L(1) = 2-[1-(2-dimethylamino-ethylimino)-ethyl]-phenol, L(2) = 2-[1-(2-diethylamino-ethylimino)-ethyl]-phenol, L(3) = 2-[1-(2-dimethylamino-ethylimino)-methyl]-phenol) with the corresponding copper(ii) salts in the presence of NaN(3). The complexes are characterized by single-crystal X-ray diffraction analyses and variable-temperature magnetic measurements. Complex 1 is composed of two terminal [Cu(L(1))(mu(1,1)-N(3))] units connected by a central [Cu(BF(4))(2)] unit through nitrogen atoms of end-on azido ligands and a phenoxo oxygen atom of the tridentate ligand. The structures of 2 and 3 are very similar; the only difference is that the central unit is [Cu(NO(3))(2)] and the nitrate group forms an additional mu-NO(3)-1kappaO:2kappaO' bridge between the terminal and central copper atoms. In complex 4, the central unit is a di-mu(1,1)-N(3) bridged dicopper entity, [Cu(2)(mu(1,1)-N(3))(2)(CH(3)COO)(2)] that connects two terminal [Cu(L(3))(mu(1,1)-N(3))] units through end-on azido, phenoxo oxygen and mu-CH(3)COO-1kappaO:2kappaO' triple bridges to result in a tetranuclear unit. Analyses of variable-temperature magnetic susceptibility data indicates that there is a global weak antiferromagnetic interaction between the copper(II) ions in complexes 1-3, with the exchange parameter J of -9.86, -11.6 and -19.98 cm(-1) for 1-3, respectively. In complex 4 theoretical calculations show the presence of an antiferromagnetic coupling in the triple bridging ligands (acetato, phenoxo and azido) while the interaction

  14. Combining non-destructive nuclear techniques to study Roman leaded copper coins from Ilipa (II-I centuries B.C.)

    Energy Technology Data Exchange (ETDEWEB)

    Moreno-Suarez, A.I., E-mail: amoreno6@us.es [Centro Nacional de Aceleradores, Avd. Thomas A. Edison, 7 Isla de la Cartuja, 41092 Seville (Spain); Departamento de Fisica Aplicada I, University of Seville (Spain); Gomez-Tubio, B., E-mail: tubio@us.es [Centro Nacional de Aceleradores, Avd. Thomas A. Edison, 7 Isla de la Cartuja, 41092 Seville (Spain); Departamento de Fisica Aplicada III, University of Seville (Spain); Respaldiza, M.A., E-mail: respaldiza@us.es [Centro Nacional de Aceleradores, Avd. Thomas A. Edison, 7 Isla de la Cartuja, 41092 Seville (Spain); Departamento de Fisica Atomica, Nuclear y Molecular, University of Seville (Spain); Chaves, F., E-mail: fchaves@us.es [Departamento de Prehistoria y Arqueologia, University of Seville (Spain); Ortega-Feliu, I., E-mail: iofeliu@us.es [Centro Nacional de Aceleradores, Avd. Thomas A. Edison, 7 Isla de la Cartuja, 41092 Seville (Spain); Ontalba-Salamanca, M.A., E-mail: ontalba@unex.es [Departamento de Fisica, University of Extremadura (Spain); Ager, F.J., E-mail: fjager@us.es [Centro Nacional de Aceleradores, Avd. Thomas A. Edison, 7 Isla de la Cartuja, 41092 Seville (Spain); Departamento de Fisica Aplicada I, University of Seville (Spain)

    2011-12-15

    A set of 32 bronze coins (II-I centuries B.C.) from the Roman city of Ilipa Magna (present-day Alcala del Rio, Seville) have been analyzed by means of non-destructive techniques. These coins are classified in different series according to their numismatic characteristics. They are very interesting from the archaeological point of view because a freshwater fish is depicted on the obverse (unusual in Mediterranean Cultures) and a spike on the reverse (also unusual but frequent in the South of the Iberian Peninsula). A comparative study has been made by PIXE (Proton Induced X-ray Emission) and XRF (X-ray Fluorescence) both corrected by GRT (Gamma Ray Transmission) in order to avoid the polishing of the coins. The results show that after the correction with GRT both independent methods give compatible concentrations for all of the coins that can be assumed as the actual bulk compositions . The average concentrations of the different series have been calculated and they could help to classify the series of coins chronologically.

  15. Mechanical behaviors of the dispersion nuclear fuel plates induced by fuel particle swelling and thermal effect II: Effects of variations of the fuel particle diameters

    Science.gov (United States)

    Ding, Shurong; Wang, Qiming; Huo, Yongzhong

    2010-02-01

    In order to predict the irradiation mechanical behaviors of plate-type dispersion nuclear fuel elements, the total burnup is divided into two stages: the initial stage and the increasing stage. At the initial stage, the thermal effects induced by the high temperature differences between the operation temperatures and the room temperature are mainly considered; and at the increasing stage, the intense mechanical interactions between the fuel particles and the matrix due to the irradiation swelling of fuel particles are focused on. The large-deformation thermo-elasto-plasticity finite element analysis is performed to evaluate the effects of particle diameters on the in-pile mechanical behaviors of fuel elements. The research results indicate that: (1) the maximum Mises stresses and equivalent plastic strains at the matrix increase with the fuel particle diameters; the effects of particle diameters on the maximum first principal stresses vary with burnup, and the considered case with the largest particle diameter holds the maximum values all along; (2) at the cladding near the interface between the fuel meat and the cladding, the Mises stresses and the first principal stresses undergo major changes with increasing burnup, and different variations exist for different particle diameter cases; (3) the maximum Mises stresses at the fuel particles rise with the particle diameters.

  16. Effects of alien and intraspecies cytoplasms on manifestation of nuclear genes for wheat resistance to brown rust: II. Specificity of cytoplasm influence on different Lr genes

    Energy Technology Data Exchange (ETDEWEB)

    Voluevich, E.A.; Buloichik, A.A.; Palilova, A.N. [Institute of Genetics and Cytology, Minsk (Belarus)

    1995-04-01

    Specificity of expression of the major nuclear genes Lr to two brown rust clones in hybrids with the same maternal cytoplasm was analyzed. It was evaluated by a resistant: susceptible ratio in the F{sub 2}. Reciprocal hybrids were obtained from the cross between the progeny of homozygous susceptible plants of the cultivar Penjamo 62 and its alloplasmatic lines carrying cytoplasms of Triticum dicoccoides var. fulvovillosum, Aegilops squarrosa var. typical, Agropyron trichophorum, and isogenic lines of the cultivar Thatcher (Th) with the Lr1, Lr9, Lr15, and Lr19 genes. It was shown that the effect of the Lr1 gene in the cytoplasm of cultivar Thatcher and in eu-, and alloplasmatic forms of Penjamo 62 was less expressed than that of other Lr genes. Cytoplasm of the alloplasmatic line (dicoccoides)-Penjamo 62 was the only exception: in the F{sub 2}, hybrids with Th (Lr1) had a higher yield of resistant forms than those with Th (Lr15). In the hybrid combinations studied, expression and/or transmission of the Lr19 gene was more significant than that of other genes. This gene had no advantages over Lr15 and Lr19 only in cytoplasm of the alloplasmatic line (squarrosa)-Penjamo 62. In certain hybrid cytoplasms, the display of the Lr1, Lr15, and Lr19 genes, in contrast to Lr9, varied with the virulence of the pathogen clones. 15 refs., 5 tabs.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2011-07-01

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

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

    International Nuclear Information System (INIS)

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

  19. Options Study - Phase II

    Energy Technology Data Exchange (ETDEWEB)

    R. Wigeland; T. Taiwo; M. Todosow; W. Halsey; J. Gehin

    2010-09-01

    The Options Study has been conducted for the purpose of evaluating the potential of alternative integrated nuclear fuel cycle options to favorably address the issues associated with a continuing or expanding use of nuclear power in the United States. The study produced information that can be used to inform decisions identifying potential directions for research and development on such fuel cycle options. An integrated nuclear fuel cycle option is defined in this study as including all aspects of the entire nuclear fuel cycle, from obtaining natural resources for fuel to the ultimate disposal of used nuclear fuel (UNF) or radioactive wastes. Issues such as nuclear waste management, especially the increasing inventory of used nuclear fuel, the current uncertainty about used fuel disposal, and the risk of nuclear weapons proliferation have contributed to the reluctance to expand the use of nuclear power, even though it is recognized that nuclear power is a safe and reliable method of producing electricity. In this Options Study, current, evolutionary, and revolutionary nuclear energy options were all considered, including the use of uranium and thorium, and both once-through and recycle approaches. Available information has been collected and reviewed in order to evaluate the ability of an option to clearly address the challenges associated with the current implementation and potential expansion of commercial nuclear power in the United States. This Options Study is a comprehensive consideration and review of fuel cycle and technology options, including those for disposal, and is not constrained by any limitations that may be imposed by economics, technical maturity, past policy, or speculated future conditions. This Phase II report is intended to be used in conjunction with the Phase I report, and much information in that report is not repeated here, although some information has been updated to reflect recent developments. The focus in this Options Study was to

  20. U.S. Department Of Energy's nuclear engineering education research: highlights of recent and current research-II. 6. A Flashing Simulator for Natural Circulation Heated Systems

    International Nuclear Information System (INIS)

    By design, many of the next generation of nuclear reactors rely on 'natural circulation' either as the primary mode of heat removal or as a passive safety mechanism under off-normal conditions. Studies have shown that flashing-induced instabilities are of concern during startup of natural-circulation loops and small scale natural-circulation light water reactors. Flashing refers to the beginning of (adiabatic) boiling in the unheated riser when there is no boiling upstream. Flashing occurs because the saturation enthalpy at low pressures (under 20 bars, experienced during reactor startup conditions) decreases significantly with decreasing pressure. Hence, in systems with long risers and under low-power/low-pressure conditions (large pressure drop relative to the absolute pressure), even if there is no boiling in the heated core, it is possible that the saturation enthalpy somewhere in the riser might drop to the level of local enthalpy. This leads to local boiling in the unheated riser. (See Fig. 1.) Because of the nature of this instability -caused by a drop in saturation enthalpy with pressure- it cannot be analyzed using most current stability codes that, in general, assume constant saturation properties. Hence, experiments must be conducted and appropriate thermal-hydraulic models must be developed to analyze flashing and flashing-induced instabilities. A simulator with significantly enhanced modeling and simulation capabilities is being developed under a grant from the U.S. Department of Energy (DOE) Nuclear Engineering Education Research program to analyze flashing and flashing-induced instabilities. The model developed here allows an arbitrary number of nodes in both the heated section (allowing axially varying heat flux) and in the unheated riser section. Obviously, the saturation enthalpy in this model is a function of pressure. Pressure-dependent enthalpy leads to a modified energy equation and introduces a new dimensionless quantity, i.e., a flashing

  1. Axiology of nuclear energy

    International Nuclear Information System (INIS)

    Nuclear energy was born in World War II and it has grown within the regime of Cold War. When the Cold War came to the end around early 1990 s, we who have benefited by the development of nuclear energy must have been challenged with a new tide of civilization change. Although it has not been so much closely questioned since then, such a new movement, that was submerging, abruptly manifested on September 11, 2001. Then, many of us realized that global circumstances, especially concerned with security, must have actually changed with the reordering of the world basic structures. This paper describes on the thoughts to reveal the cause and background of the event on September 11 with the linkage to nuclear energy development, or nuclear civilization in pursuit of the future regime of nuclear in harmonization with the global society in 21st century. (author)

  2. Nuclear Confidence

    Institute of Scientific and Technical Information of China (English)

    2011-01-01

    The Fukushima nuclear accident provides valuable lessons for China national nuclear Corp.as it continues to expand its operations AS Japan’s Fukushima nuclear crisis sparks a global debate over nuclear safety,China National Nuclear Corp. (CNNC),the country’s largest nuclear plant operator, comes under the spotlight.

  3. Nuclear power and nuclear weapons

    International Nuclear Information System (INIS)

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2011-06-15

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

  5. Nuclear moments

    CERN Document Server

    Kopferman, H; Massey, H S W

    1958-01-01

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

  6. Fuel management inside the reactor. Project AZ-101 (ININ). Report of the generation of the nuclear bank 'L1PG3826' of the assemblies GE5 and GE9B 'collapsed' of the CNLV for the FCS-II program of the FMS system; Administracion de combustible dentro del reactor. Proyecto AZ-101 (ININ). Reporte de generacion del banco nuclear 'L1PG3826' de los ensambles GE5 y GE9B 'colapsados' de la CNLV para el programa FCS-II del FMS

    Energy Technology Data Exchange (ETDEWEB)

    Alonso V, G.; Torres A, C

    1991-06-15

    In order to be able to carry out studies but next to the operation of the reactor of the CNLV with the program FCS-II of the package of codes for the fuel management FMS, it was generated a 'collapsed' nuclear bank integrating the generated information with RECORD of each one of those assemblies of the initial load and of the first recharge. To generate the bank, the different ones RECORD 'cells' that compose each assemble were 'collapsed' to an alone one, representing this, to the one complete assemble in what refers to the fuel bars distribution and enrichments. The one collapsed of each assemble it is made averaging the content of UO{sub 2} and Gd{sub 2}O{sub 3} in each fuel bar by the volumetric fraction occupied by each axial section of the fuel bar where the content of UO{sub 2} and Gd{sub 2}O{sub 3} were constant, by this way the x-y fuel bars arrangement is conserved but a representative fuel cell of all the assemble is obtained. Of the five different assemblies that will be load in the reactor of the CNLV (3 of the initial load and 2 of the first recharge), only 4 were collapsed; the remaining one to be totally formed by natural uranium it was not necessary to collapse. From the collapsing process new enrichment values in U-235 and in content of Gd{sub 2}O{sub 3} for each fuel bar, for what according to the generation procedure of nuclear information it was generated the required information by RECORD for each fuel bar with Gd{sub 2}O{sub 3} with the ECLIPSE code. Once generated this information it was proceeded to generate the homogenized nuclear information, with RECORD, for the whole cell. According to the requirements of nuclear information of FCS-II, the nuclear Information generated with RECORD only was of the defined type as series 1 in the procedure of generation of nuclear banks '6F3/1/CN029/90/P1'; that which means that only it was generated nuclear information as function of the burnup of the fuel and of

  7. Theories of Low Energy Nuclear Transmutations

    OpenAIRE

    Srivastava, Y. N.; Widom, A.; Swain, J.

    2012-01-01

    Employing concrete examples from nuclear physics it is shown that low energy nuclear reactions can and have been induced by all of the four fundamental interactions (i) (stellar) gravitational, (ii) strong, (iii) electromagnetic and (iv) weak. Differences are highlighted through the great diversity in the rates and similarity through the nature of the nuclear reactions initiated by each.

  8. Elements from chlorine to calcium nuclear reactions

    CERN Document Server

    Kunz, Wunibald

    1968-01-01

    Nuclear Tables: Part II Nuclear Reactions, Volume 3: The Elements from Chlorine to Calcium contains tabulations of the nuclear reaction values of elements chlorine, argon, potassium, and calcium. These tabulations provide the calculated Q-values of the elements and their isotopes. This book will be of value to general chemistry researchers.

  9. Nuclear safeguards; Salvaguardias nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Zurron, O.

    2015-07-01

    Safeguards control at the Juzbado Plant is implemented through the joint IAEA/EURATOM partnership approach in force within the European Union for all nuclear facilities. this verification agreement is designed to minimize burden on the operators whilst ensuring that both inspectorate achieve the objectives related to their respective safeguards regimes. This paper outlines the safeguards approaches followed by the inspectorate and the particularities of the Juzbado Plants nuclear material accountancy and control system. (Authors)

  10. Environmental monitoring of the Angra reactor site

    International Nuclear Information System (INIS)

    The single and sumarized results obtained under the monitoring program are presented and compared with those obtained during the preoperational period. Direct radiation was measured with a solid-state dosimeter network. The concentration levels of natural and artificial radionuclides were determined in primary media like air, surface and sea water, in accumulators like soil, sand and sediments, in indicators like grass and seaweed, and in the main local foodstuff, which includes marine produce (fish, shellfish and shrimps), milk bananas, manioc and oranges. The measurements included gross alpha and beta activity measurements and gamma spectrometry. Specific techniques were used for the measurement of the activity concentration of tritium in sea water and surface water and of I-131 in air and milk. The only detectable artificial radionuclide was CS-137 whose occasional presence in milk, pasture, fish and manioc can be attributed to world-wide fallout. (orig./PW)

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

    Energy Technology Data Exchange (ETDEWEB)

    Gurjao, Emir Candeia

    1996-02-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    Almeida, Renata Araujo de

    2011-07-01

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

  13. Nuclear ventriculography

    Science.gov (United States)

    ... ventriculography (RNV); Multiple gate acquisition scan (MUGA); Nuclear cardiology; Cardiomyopathy - nuclear ventriculography ... 56. Udelson JE, Dilsizian V, Bonow RO. Nuclear cardiology. In: Bonow RO, Mann DL, Zipes DP, Libby ...

  14. Nuclear power

    OpenAIRE

    Waller, David; McDonald, Alan; Greenwald, Judith; Mobbs, Paul

    2005-01-01

    David Waller and Alan McDonald ask whether a nuclear renaissance can be predicted; Judith M. Greenwald discusses keeping the nuclear power option open; Paul Mobbs considers the availability of uranium and the future of nuclear energy.

  15. Nuclear electronics

    International Nuclear Information System (INIS)

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

  16. A simplified study of public perception in the nuclear field: suggestions for educational campaign for different segments of society

    International Nuclear Information System (INIS)

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

  17. Diagnosis of class using swarm intelligence applied to problem of identification of nuclear transient

    Energy Technology Data Exchange (ETDEWEB)

    Villas Boas Junior, Manoel; Strauss, Edilberto, E-mail: junior@lmp.ufrj.b [Instituto Federal de Educacao, Ciencia e Tecnologia do Ceara/ Universidade do Estado do Ceara, Itaperi, CE (Brazil). Mestrado Integrado em Computacao Aplicada; Nicolau, Andressa dos Santos; Schirru, Roberto, E-mail: andressa@lmp.ufrj.b [Coordenacao dos Programas de Pos-Graduacao de Engenharia (PEN/COPPE/UFRJ), Rio de Janeiro, RJ (Brazil). Programa de Engenharia Nuclear; Mello, Flavio Luis de [Universidade Federal do Rio de Janeiro (POLI/UFRJ), RJ (Brazil). Escola Politecnica. Dept. de Engenharia Eletronica e Computacao

    2011-07-01

    This article presents a computational model of the diagnostic system of transient. The model makes use of segmentation techniques applied to support decision making, based on identification of classes and optimized by Particle Swarm Optimization algorithm (PSO). The method proposed aims to classify an anomalous event in the signatures of three classes of the design basis transients postulated for the Angra 2 nuclear plant, where the PSO algorithm is used as a method of separation of classes, being responsible for finding the best centroid prototype vector of each accident/transient, ie equivalent to Voronoi vector that maximizes the number of correct classifications. To make the calculation of similarity between the set of the variables anomalous event in a given time t, and the prototype vector of variables of accident/transients, the metrics of Manhattan, Euclidean and Minkowski were used. The results obtained by the method proposed were compatible with others methods reported in the literature, allowing a solution that approximates the ideal solution, ie the Voronoi vectors. (author)

  18. Nuclear power

    International Nuclear Information System (INIS)

    The subject is covered in chapters entitled: nuclear power certainties and doubts; nuclear power in the Western World to 2000; the frequency of core meltdown accidents; hidden costs of the accident at Three Mile Island; costs of nuclear accidents - implications for reactor choice; defining the risks of nuclear power; the uncertain economics of a nuclear power program; the economics of enabling decisions (Sizewell B as an enabling decision); trade in nuclear electricity; some pointers to the future. (U.K.)

  19. Nuclear Thermodynamics of the Heaviest Elements. II

    Energy Technology Data Exchange (ETDEWEB)

    Foreman Jr., Bruce M.; Seaborg, Glenn T.

    1958-01-01

    The masses of the isotopes of the heaviest elements have been calculated from known decay data in the region, extended by means of decay energies calculated from closed decay-energy cycles and estimated from the systematics of alpha and beta decay energies. The absolute values of the masses are based on the mass-spectrometrically determined mass of Pb{sup 208} and a few measured neutron binding energies. The half-life systematics of alpha decay and spontaneous fission are also presented, and some predictions of the properties of as yet undiscovered nuclides are made.

  20. Nuclear Thermodynamics of the Heaviest Elements. II

    Energy Technology Data Exchange (ETDEWEB)

    Foreman Jr., Bruce M.; Seaborg, Glenn T.

    1957-10-01

    The masses of the isotopes of the heaviest elements have been calculated from known decay data in the region, extended by means of decay energies calculated from closed decay-energy cycles and estimated from the systematics of alpha and beta decay energies. The absolute values of the masses are based on the mass-spectrometrically determined mass of Pb{sup 208} and a few measured neutron binding energies. The half-life systematics of alpha decay and spontaneous fission are also presented, and some predictions of the properties of as yet undiscovered nuclides are made.

  1. Landscape of atomic nuclear shapes

    CERN Document Server

    Moon, Chang-Bum

    2016-01-01

    We exhibit a wide variety of the nuclear shape phases over the nuclear chart along with a shell model scheme. Various nuclear shapes are demonstrated within the framework of proton-neutron spin-orbital interactions; ferro-deformed, sub-ferro-deformed, and spherical shapes. The spherical shape is classified into the three magic-number categories in view of a large shell gap mechanism; double-magic nuclei I, double magic nuclei II, and double magic nuclei III. We discuss nuclear shape coexistence in the space Z = 76 to 84 as providing a new way to understanding the dynamical shape phases.

  2. Landscape of atomic nuclear shapes

    OpenAIRE

    Moon, Chang-Bum

    2016-01-01

    We exhibit a wide variety of the nuclear shape phases over the nuclear chart along with a shell model scheme. Various nuclear shapes are demonstrated within the framework of proton-neutron spin-orbital interactions; ferro-deformed, sub-ferro-deformed, and spherical shapes. The spherical shape is classified into the three magic-number categories in view of a large shell gap mechanism; double-magic nuclei I, double magic nuclei II, and double magic nuclei III. We discuss nuclear shape coexisten...

  3. Nuclear power policy as a differential game

    OpenAIRE

    Backlund, Kenneth

    2000-01-01

    This paper examines nuclear energy output in a differential game framework involving two countries. The countries differ regarding nuclear technology with one being relatively safe and the other less safe. Simulation of a numerical model gives the following results, (i) A cooperative agreement will imply less use of nuclear energy compared with both a noncooperative Nash equilibrium and an uncontrolled market solution, (ii) The country with relatively safe nuclear energy technology benefits m...

  4. Nuclear Theory - Nuclear Power

    Science.gov (United States)

    Svenne, J. P.; Canton, L.; Kozier, K. S.

    2008-01-01

    The results from modern nuclear theory are accurate and reliable enough to be used for practical applications, in particular for scattering that involves few-nucleon systems of importance to nuclear power. Using well-established nucleon-nucleon (NN) interactions that fit well the NN scattering data, and the AGS form of the three-body theory, we have performed precise calculations of low-energy neutron-deuteron (n+d) scattering. We show that three-nucleon force effects that have impact on the low-energy vector analyzing powers have no practical effects on the angular distribution of the n+d cross-section. There appear to be problems for this scattering in the evaluated nuclear data file (ENDF) libraries, at the incident neutron energies less than 3.2 MeV. Supporting experimental data in this energy region are rather old (>25 years), sparse and often inconsistent. Our three-body results at low energies, 50 keV to 10.0 MeV, are compared to the ENDF/B-VII.0 and JENDL (Japanese Evaluated Nuclear Data Library) -3.3 evaluated angular distributions. The impact of these results on the calculated reactivity for various critical systems involving heavy water is shown.

  5. Report on nuclear installations safety and security control

    International Nuclear Information System (INIS)

    This report of the parliamentary office for evaluation of scientific and technological choices bearing on the safety and security of nuclear installations is divided into 2 volumes bearing on: - Volume I: nuclear installations safety. - nuclear safety and international organizations. - works separation: Finland, Belgium and Federal Republic of Germany. - French organization. - Volume II: security and information. - French nuclear security. - Public information

  6. Tech Area II: A history

    Energy Technology Data Exchange (ETDEWEB)

    Ullrich, R. [Ktech Corp., Albuquerque, NM (United States)

    1998-07-01

    This report documents the history of the major buildings in Sandia National Laboratories` Technical Area II. It was prepared in support of the Department of Energy`s compliance with Section 106 of the National Historic Preservation Act. Technical Area II was designed and constructed in 1948 specifically for the final assembly of the non-nuclear components of nuclear weapons, and was the primary site conducting such assembly until 1952. Both the architecture and location of the oldest buildings in the area reflect their original purpose. Assembly activities continued in Area II from 1952 to 1957, but the major responsibility for this work shifted to other sites in the Atomic Energy Commission`s integrated contractor complex. Gradually, additional buildings were constructed and the original buildings were modified. After 1960, the Area`s primary purpose was the research and testing of high-explosive components for nuclear weapons. In 1994, Sandia constructed new facilities for work on high-explosive components outside of the original Area II diamond-shaped parcel. Most of the buildings in the area are vacant and Sandia has no plans to use them. They are proposed for decontamination and demolition as funding becomes available.

  7. TBscore II

    DEFF Research Database (Denmark)

    Rudolf, Frauke; Lemvik, Grethe; Abate, Ebba;

    2013-01-01

    Abstract Background: The TBscore, based on simple signs and symptoms, was introduced to predict unsuccessful outcome in tuberculosis patients on treatment. A recent inter-observer variation study showed profound variation in some variables. Further, some variables depend on a physician assessing...... them, making the score less applicable. The aim of the present study was to simplify the TBscore. Methods: Inter-observer variation assessment and exploratory factor analysis were combined to develop a simplified score, the TBscore II. To validate TBscore II we assessed the association between start...

  8. Nuclear control

    Energy Technology Data Exchange (ETDEWEB)

    Yoon, Wan Kee [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1995-02-01

    International cooperation in nuclear industries requires nuclear control as prerequisites. The concept of nuclear control is based on the Treaty on the Non-proliferation of Nuclear Weapon (NPT). The International Atomic Energy Agency (IAEA) plays central role in implementing nuclear control. Nuclear control consists of nuclear safeguards, physical protection, and export/import control. Each member state of NPT is subject to the IAEA`s safeguards by concluding safeguards agreements with the IAEA. IAEA recommends member states to implement physical protection on nuclear materials by `The Physical Protection of Nuclear Material` and `The Convention on the Physical Protection of Nuclear Material` of IAEA. Export/Import Control is to deter development of nuclear weapons by controlling international trade on nuclear materials, nuclear equipments and technology. Current status of domestic and foreign nuclear control implementation including recent induction of national inspection system in Korea is described and functions of recently set-up Technology Center for Nuclear Control (TCNC) under the Korea Atomic Energy Research Institute (KAERI) are also explained. 6 tabs., 11 refs. (Author).

  9. Fuel management inside the reactor. Project AZ-101 (ININ). Report of the generation of the nuclear bank 'L1PG3826' of the assemblies GE5 and GE9B 'collapsed' of the CNLV for the FCS-II program of the FMS system

    International Nuclear Information System (INIS)

    In order to be able to carry out studies but next to the operation of the reactor of the CNLV with the program FCS-II of the package of codes for the fuel management FMS, it was generated a 'collapsed' nuclear bank integrating the generated information with RECORD of each one of those assemblies of the initial load and of the first recharge. To generate the bank, the different ones RECORD 'cells' that compose each assemble were 'collapsed' to an alone one, representing this, to the one complete assemble in what refers to the fuel bars distribution and enrichments. The one collapsed of each assemble it is made averaging the content of UO2 and Gd2O3 in each fuel bar by the volumetric fraction occupied by each axial section of the fuel bar where the content of UO2 and Gd2O3 were constant, by this way the x-y fuel bars arrangement is conserved but a representative fuel cell of all the assemble is obtained. Of the five different assemblies that will be load in the reactor of the CNLV (3 of the initial load and 2 of the first recharge), only 4 were collapsed; the remaining one to be totally formed by natural uranium it was not necessary to collapse. From the collapsing process new enrichment values in U-235 and in content of Gd2O3 for each fuel bar, for what according to the generation procedure of nuclear information it was generated the required information by RECORD for each fuel bar with Gd2O3 with the ECLIPSE code. Once generated this information it was proceeded to generate the homogenized nuclear information, with RECORD, for the whole cell. According to the requirements of nuclear information of FCS-II, the nuclear Information generated with RECORD only was of the defined type as series 1 in the procedure of generation of nuclear banks '6F3/1/CN029/90/P1'; that which means that only it was generated nuclear information as function of the burnup of the fuel and of the vacuum in the fuel cell. Although the nuclear bank was generated (identified as 'L1PG3826') in

  10. Nuclear technology review 2002

    International Nuclear Information System (INIS)

    The unifying theme of the Nuclear Technology Review 2002 (NTR-2002) is the importance of innovation. Innovation makes it possible to step beyond incremental evolutionary improvements constrained by diminishing returns. For crop production and public health, for example, the sterile insect technique created a whole new path for future improvements, distinctly different from applying ever larger amounts of pesticides. Nuclear techniques offer a new and safer approach to removing the world's estimated 60,000,000 abandoned land mines. New precision techniques create the potential for ever less intrusive and more effective radiation treatments for cancer. For nuclear power continuing innovation will be a key factor in closing the projection gap between long term global energy scenarios in which nuclear power expands substantially and near term scenarios with only modest expansion or even decline. While the NTR-2002 presents a worldwide review of the state-of-the-art of nuclear science and technology, and not an annual report on IAEA activities, it notes areas where the Agency has a particularly important role to play. Part I of the NTR-2002 'Fundamentals of Nuclear Development', reviews developments in the field of nuclear, atomic and molecular data. Research reactors remain essential to progress in nuclear science and technology. Part I reviews advances in radioisotope production, the use of accelerators and neutron activation analysis relevant to applications ranging from medicine particularly the light against cancer to industry. Part I also reviews developments in nuclear instrumentation and nuclear fusion, particularly in connection with the International Thermonuclear Experimental Reactor. Part II begins with a summary of nuclear power production in 2001. At the end of 2001 there were 438 nuclear power plants (NPPs) in operation, corresponding to a total capacity of 353 GW(e), more than 10000 reactor-years of cumulative operating experience and about 16% of global

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2013-07-01

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

  12. Learning, innovation and communication: evolving dynamics of a nuclear emergency plan; Aprendizagem, inovacao e comunicacao: a dinamica evolutica de um plano de emergencia nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Quadros, Andre Luiz Lopes

    2014-07-01

    The technological development inherent to modern societies has placed human beings in situations of choice from a wide variety of possible risks. As a way to protect people and the environment, actions need to be developed in order to reduce possible consequences of the materialisation of these risks. The thermonuclear power generation demand planning in order to prepare answers to possible emergency situations, as even being considered of low probability of occurrence, when they happen have a significant impact on populations and regions of its surroundings. Considering the relevance of this issue, this thesis aimed to identify and analyze the dynamics of preparedness and response to emergency situations in a Nuclear Power Plant, trying to understand its evolution over the time and systematizing it, considering the actors involved, processes of organizational learning, innovation and risk communication, considered as crucial for the development and improvement of emergency plans. Concerning preparedness and response to possible emergency situations in this nuclear plant, it was possible not only to confirm the importance of the three processes studied, but also observe that they can be treated and evaluated in an integrated and systematic way. So, it was presented a model that aims to facilitate the understanding of this perspective and enhance the importance of participation and cooperation between all stakeholders (organizations and the local population) within a socio-participatory perspective. To this end, this exploratory research sought for evidences in documents, participation in planning meetings, direct observation of the general exercises of the CNAAA External Emergency Plan of 2013, interviews with some of the actors involved and through the application of a questionnaire among the population of the Praia Vermelha, in Angra dos Reis, Rio de Janeiro. (author)

  13. Swedish nuclear waste efforts

    Energy Technology Data Exchange (ETDEWEB)

    Rydberg, J.

    1981-09-01

    After the introduction of a law prohibiting the start-up of any new nuclear power plant until the utility had shown that the waste produced by the plant could be taken care of in an absolutely safe way, the Swedish nuclear utilities in December 1976 embarked on the Nuclear Fuel Safety Project, which in November 1977 presented a first report, Handling of Spent Nuclear Fuel and Final Storage of Vitrified Waste (KBS-I), and in November 1978 a second report, Handling and Final Storage of Unreprocessed Spent Nuclear Fuel (KBS II). These summary reports were supported by 120 technical reports prepared by 450 experts. The project engaged 70 private and governmental institutions at a total cost of US $15 million. The KBS-I and KBS-II reports are summarized in this document, as are also continued waste research efforts carried out by KBS, SKBF, PRAV, ASEA and other Swedish organizations. The KBS reports describe all steps (except reprocessing) in handling chain from removal from a reactor of spent fuel elements until their radioactive waste products are finally disposed of, in canisters, in an underground granite depository. The KBS concept relies on engineered multibarrier systems in combination with final storage in thoroughly investigated stable geologic formations. This report also briefly describes other activities carried out by the nuclear industry, namely, the construction of a central storage facility for spent fuel elements (to be in operation by 1985), a repository for reactor waste (to be in operation by 1988), and an intermediate storage facility for vitrified high-level waste (to be in operation by 1990). The R and D activities are updated to September 1981.

  14. Swedish nuclear waste efforts

    International Nuclear Information System (INIS)

    After the introduction of a law prohibiting the start-up of any new nuclear power plant until the utility had shown that the waste produced by the plant could be taken care of in an absolutely safe way, the Swedish nuclear utilities in December 1976 embarked on the Nuclear Fuel Safety Project, which in November 1977 presented a first report, Handling of Spent Nuclear Fuel and Final Storage of Vitrified Waste (KBS-I), and in November 1978 a second report, Handling and Final Storage of Unreprocessed Spent Nuclear Fuel (KBS II). These summary reports were supported by 120 technical reports prepared by 450 experts. The project engaged 70 private and governmental institutions at a total cost of US $15 million. The KBS-I and KBS-II reports are summarized in this document, as are also continued waste research efforts carried out by KBS, SKBF, PRAV, ASEA and other Swedish organizations. The KBS reports describe all steps (except reprocessing) in handling chain from removal from a reactor of spent fuel elements until their radioactive waste products are finally disposed of, in canisters, in an underground granite depository. The KBS concept relies on engineered multibarrier systems in combination with final storage in thoroughly investigated stable geologic formations. This report also briefly describes other activities carried out by the nuclear industry, namely, the construction of a central storage facility for spent fuel elements (to be in operation by 1985), a repository for reactor waste (to be in operation by 1988), and an intermediate storage facility for vitrified high-level waste (to be in operation by 1990). The R and D activities are updated to September 1981

  15. PORT II

    Science.gov (United States)

    Muniz, Beau

    2009-01-01

    One unique project that the Prototype lab worked on was PORT I (Post-landing Orion Recovery Test). PORT is designed to test and develop the system and components needed to recover the Orion capsule once it splashes down in the ocean. PORT II is designated as a follow up to PORT I that will utilize a mock up pressure vessel that is spatially compar able to the final Orion capsule.

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

    Energy Technology Data Exchange (ETDEWEB)

    Borges, Ronaldo Celem

    2001-10-15

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

  17. Nuclear Scans

    Science.gov (United States)

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

  18. Nuclear forensics

    International Nuclear Information System (INIS)

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

  19. Motor operated valve signatures events extraction module using an specialist system for the nuclear power plant MOV diagnostic system

    International Nuclear Information System (INIS)

    A predictive maintenance program for motor-operated valves is performed every year at Angra I Nuclear Power Plant in order to detect early failures of the valves and to diagnosis the valve degradation. The purpose of this maintenance program is to increase the reactor reliability and security. The main predictive maintenance activities are usually performed in the swing check-valves, gate valves and globe valves. The valves data analysis usually performed during the plant outage allows one to detect any failure and adjust the valves parameters like torque-switch and limitorque. The main purpose of this thesis is to develop a computer program to select the valve events parameter using the valve power signature during the closed-open and open-closed cycles. The results obtained by the developed algorithm are connected to a developed specialist system to perform the valves events identification. An important contribution of this thesis is that the valves signature features are obtained without changing the signal morphology. (author)

  20. Remediation strategies after nuclear or radiological accidents: part 2 - accident scenarios for assessing effectiveness of cleanup procedures

    Energy Technology Data Exchange (ETDEWEB)

    Rochedo, Elaine R.R. [Comissao Nacional de Energia Nuclear (CNEN-RJ), Rio de Janeiro, RJ (Brazil). Coordenacao de Instalacoes Nucleares], e-mail: erochedo@cnen.gov.br; Silva, Diogo N.G.; Wasserman, Maria A.V.; Conti, Luiz F.C. [Instituto de Radioprotecao e Dosimetria (IRD/CNEN-RJ), Rio de Janeiro, RJ (Brazil)], e-mail: dneves@ird.gov.br, e-mail: angelica@ird.gov.br, e-mail: lfcconti@ird.gov.br

    2009-07-01

    The selection of protective measures and remediation strategies after an accident needs to be based on previously established criteria, to minimize unnecessary stress and the exposures involved in cleanup operations that are not effective in reducing doses to the public. In a first stage, a database describing the countermeasures has been developed including their efficiency on removing contamination from surfaces. However, to assess the effectiveness of cleanup procedures in reducing doses to members of the public, it was necessary to derive specific scenarios in order to simulate the long term behavior of the material in the environment, since the contribution of different surfaces to doses changes with time after contamination. A basic release and exposure scenario was developed to assess the dose reduction due to the mostly used procedures. Exposure scenarios were selected to fit the surroundings of the Brazilian nuclear power plants in Angra dos Reis. Simulations were performed using SIEM, the integrated system for dose assessment after contamination events, developed at IRD. The contamination of urban environments was assessed for Cs-137, as this was found to be the most relevant long term radionuclide to contribute to doses to member of the public. The effects on reducing external exposures were assessed for periods up to 50 years after the contamination. For agricultural areas, the focus was on ingestion doses from contamination with I-131 for periods up to 1 year after contamination. Results will be complemented on the database in order to support multi-criteria decision making processes after accidents. (author)

  1. Qualification and application of nuclear reactor accident analysis code with the capability of internal assessment of uncertainty

    International Nuclear Information System (INIS)

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

  2. Nuclear Legislation in OECD and NEA Countries. Regulatory and Institutional Framework for Nuclear Activities - New Zealand

    International Nuclear Information System (INIS)

    This country profile provide comprehensive information on the regulatory and Institutional Framework governing nuclear activities as well as a detailed review of a full range of nuclear law topics, including: mining regime; radioactive substances; nuclear installations; trade in nuclear materials and equipment; radiation protection; radioactive waste management; non-proliferation and physical protection; transport; and nuclear third party liability. The profile is complemented by reproductions of the primary legislation regulating nuclear activities in the country. Content: I. General regulatory regime: 1. Introduction; 2. Mining regime; 3. Radioactive Substances and Equipment; 4. Nuclear installations; 5. Trade in nuclear materials and equipment; 6. Radiation protection; 7. Radioactive waste management; 8. Nuclear security; 9. Transport; 10. Nuclear third party liability; II. Institutional Framework: 1. Regulatory and supervisory authorities - National Radiation Laboratory - NRL; 2. Advisory bodies - Radiation Protection Advisory Council; 3. Public and semi-public agencies - Research institutes

  3. Nuclear energy

    International Nuclear Information System (INIS)

    An overview about the evolution of nuclear energy for the next 25 years is presented. Several types of nuclear power reactors are described and the power installed up to year 2000 are discussed. Some processes of nuclear fuel enrichment used in the world are shown. (E.G.)

  4. Nuclear Ambitions

    Institute of Scientific and Technical Information of China (English)

    2008-01-01

    China will begin to build the world’s first third-generation nuclear power plant at the Sanmen Nuclear Power Project in Sanmen City, coastal Zhejiang Province, in March 2009, accord-ing to the State Nuclear Power Technology Corp.

  5. Nuclear structure

    CERN Document Server

    Nazarewicz, W

    1999-01-01

    Current developments in nuclear structure are discussed from a theoretical perspective. The studies of the nuclear many-body system provide us with invaluable information about the nature of the nuclear interaction, nucleonic correlations at various energy-distance scales, and the modes of the nucleonic matter.

  6. Nuclear weapons, nuclear effects, nuclear war

    Energy Technology Data Exchange (ETDEWEB)

    Bing, G.F.

    1991-08-20

    This paper provides a brief and mostly non-technical description of the militarily important features of nuclear weapons, of the physical phenomena associated with individual explosions, and of the expected or possible results of the use of many weapons in a nuclear war. Most emphasis is on the effects of so-called ``strategic exchanges.``

  7. Greenfield nuclear power for Finland

    Energy Technology Data Exchange (ETDEWEB)

    Saarenpaa, Tapio

    2010-09-15

    In Finland, licensing for new nuclear power is ongoing. The political approval is to be completed in 2010. Fennovoima's project is unique in various ways: (i) the company was established only in 2007, (ii) its ownership includes a mixture of local energy companies, electricity-intensive industries and international nuclear competence through E.ON, and (iii) it has two alternative greenfield sites. There are five prerequisites for a successful nuclear power project in a transparent democracy of today: (1) need for additional power capacity, (2) actor prepared to invest, (3) established competence, (4) available site, (5) open communications, and (6) favorable public opinion.

  8. Status: nuclear and radiochemistry discipline

    International Nuclear Information System (INIS)

    There is no universally accepted definition for the term 'nuclear chemistry'. We may regard nuclear chemistry as an interdisciplinary subject with roots in physics, biology, and chemistry. The basic aspects include among others (i) nuclear reactions and energy levels, (ii) the types and energetics of radioactive decay, (iii) the formation and properties of radioactive elements, (iv) the effect of individual isotopes on chemical and physical properties, and (v) the effects of nuclear radiation on matter. Research in (i) and (ii) is often indistinguishable in purpose and practice from that in nuclear physics, although for nuclear chemists, chemical techniques may play a significant role. (iii) and (iv) can be classified as radiochemistry and isotope chemistry, while (v) falls in the classification of radiation chemistry. There is an urgent need in India also to have similar mechanism. Different universities, research organizations and the education administrators should join hands to address this issue in a focused manner. This is all the more needed urgently as the nuclear power programme and other applications are expected to increase many fold in coming years

  9. Nuclear physics

    Energy Technology Data Exchange (ETDEWEB)

    Kamal, Anwar

    2014-09-01

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

  10. Nuclear physics

    International Nuclear Information System (INIS)

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

  11. Nuclear forensics

    International Nuclear Information System (INIS)

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

  12. Learning, innovation and communication: evolving dynamics of a nuclear emergency plan

    International Nuclear Information System (INIS)

    The technological development inherent to modern societies has placed human beings in situations of choice from a wide variety of possible risks. As a way to protect people and the environment, actions need to be developed in order to reduce possible consequences of the materialisation of these risks. The thermonuclear power generation demand planning in order to prepare answers to possible emergency situations, as even being considered of low probability of occurrence, when they happen have a significant impact on populations and regions of its surroundings. Considering the relevance of this issue, this thesis aimed to identify and analyze the dynamics of preparedness and response to emergency situations in a Nuclear Power Plant, trying to understand its evolution over the time and systematizing it, considering the actors involved, processes of organizational learning, innovation and risk communication, considered as crucial for the development and improvement of emergency plans. Concerning preparedness and response to possible emergency situations in this nuclear plant, it was possible not only to confirm the importance of the three processes studied, but also observe that they can be treated and evaluated in an integrated and systematic way. So, it was presented a model that aims to facilitate the understanding of this perspective and enhance the importance of participation and cooperation between all stakeholders (organizations and the local population) within a socio-participatory perspective. To this end, this exploratory research sought for evidences in documents, participation in planning meetings, direct observation of the general exercises of the CNAAA External Emergency Plan of 2013, interviews with some of the actors involved and through the application of a questionnaire among the population of the Praia Vermelha, in Angra dos Reis, Rio de Janeiro. (author)

  13. Experience in training of health personnel for response to radiological and nuclear accidents

    International Nuclear Information System (INIS)

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

  14. Nuclear physicist, arms control advocate

    CERN Multimedia

    Chang, K

    2002-01-01

    Victor F. Weisskopf, a nuclear physicist who worked on the Manhattan Project to build the first atomic bomb in World War II and later became an ardent advocate of arms control, died Monday at his home in Newton, MA, USA. He was 93 (1 page).

  15. Nuclear energy and nuclear weapons

    International Nuclear Information System (INIS)

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

  16. Nuclear Energy Center: upper St. Lawrence region. Part I. Siting. Part II. Fort Drum surrogate site, description and impact assessment. Part III. Dispersed sites impact assessment and comparison with the NEC

    Energy Technology Data Exchange (ETDEWEB)

    Merry, P.A.; Luner, C.; Hong, S.W.; Canham, H.O.; Boggs, J.F.; McCool, T.P.

    1976-12-01

    This report is one of many supporting documents used by the Nuclear Regulatory commission in the preparation of the Nuclear Energy Center Site Survey (NECSS) mandated by Congress. While the overall study focuses on the feasibility and practicability of nuclear energy centers (NECs), this report is directed towards choosing a suitable surrogate site in the upper St. Lawrence region of New York State, assessing the probable impacts associated with construction and operation of the NEC, and comparing these impacts with those associated with small dispersed nuclear power stations. The upper St. Lawrence region is surveyed to identify a specific site that might be suitable for a surrogate NEC. Several assumptions about the basic design of an NEC are delineated, and a general overview of the characteristics of the region is given. The Fort Drum Military Reservation is chosen as a suitable surrogate site. Fort Drum and the surrounding area are described in terms of land use and population patterns, terrestrial and aquatic ecology, water use and quality, meteorology, institutional framework, and socioeconomic structure. The impacts associated with NEC development are assessed. Then the impacts associated with smaller dispersed nuclear power stations located throughout New York State are assessed and compared with the impacts associated with the NEC. Finally, the impacts due to development of the transmission line networks associated with the NEC and with the dispersed power stations are assessed and compared.

  17. Nuclear Legislation in OECD and NEA Countries. Regulatory and Institutional Framework for Nuclear Activities - Finland

    International Nuclear Information System (INIS)

    This country profile provide comprehensive information on the regulatory and Institutional Framework governing nuclear activities as well as a detailed review of a full range of nuclear law topics, including: mining regime; radioactive substances; nuclear installations; trade in nuclear materials and equipment; radiation protection; radioactive waste management; non-proliferation and physical protection; transport; and nuclear third party liability. The profile is complemented by reproductions of the primary legislation regulating nuclear activities in the country. Content: I. General regulatory regime: 1. Introduction; 2. Mining regime; 3. Radioactive substances, nuclear fuel and equipment; 4. Nuclear installations; (Licensing and inspection, including nuclear safety; Emergency response); 5. Trade in nuclear materials and equipment; 6. Radiation protection; 7. Radioactive waste management; 8. Nuclear security; 9. Transport; 10. Nuclear third party liability; II. Institutional Framework: 1. Regulatory and supervisory authorities (Ministry of Trade and Industry - KTM; Ministry of Social Affairs and Health; Ministry of the Interior; Ministry of the Environment; Ministry of Foreign Affairs); 2. Advisory bodies (Advisory Committee on Nuclear Energy; Advisory Committee on Nuclear Safety); 3. Public and semi-public agencies (Finnish Radiation and Nuclear Safety Authority - STUK; State Nuclear Waste Management Fund)

  18. Nuclear power

    International Nuclear Information System (INIS)

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

  19. Nuclear APC.

    Science.gov (United States)

    Neufeld, Kristi L

    2009-01-01

    Mutational inactivation of the tumor suppressor gene APC (Adenomatous polyposis coli) is thought to be an initiating step in the progression of the vast majority ofcolorectal cancers. Attempts to understand APC function have revealed more than a dozen binding partners as well as several subcellular localizations including at cell-cell junctions, associated with microtubules at the leading edge of migrating cells, at the apical membrane, in the cytoplasm and in the nucleus. The present chapter focuses on APC localization and functions in the nucleus. APC contains two classical nuclear localization signals, with a third domain that can enhance nuclear import. Along with two sets of nuclear export signals, the nuclear localization signals enable the large APC protein to shuttle between the nucleus and cytoplasm. Nuclear APC can oppose beta-catenin-mediated transcription. This down-regulation of nuclear beta-catenin activity by APC most likely involves nuclear sequestration of beta-catenin from the transcription complex as well as interaction of APC with transcription corepressor CtBP. Additional nuclear binding partners for APC include transcription factor activator protein AP-2alpha, nuclear export factor Crm1, protein tyrosine phosphatase PTP-BL and perhaps DNA itself. Interaction of APC with polymerase beta and PCNA, suggests a role for APC in DNA repair. The observation that increases in the cytoplasmic distribution of APC correlate with colon cancer progression suggests that disruption of these nuclear functions of APC plays an important role in cancer progression. APC prevalence in the cytoplasm of quiescent cells points to a potential function for nuclear APC in control of cell proliferation. Clear definition of APC's nuclear function(s) will expand the possibilities for early colorectal cancer diagnostics and therapeutics targeted to APC. PMID:19928349

  20. Nuclear astrophysics

    International Nuclear Information System (INIS)

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

  1. NF ISO 7097-1. Nuclear fuel technology - Uranium dosimetry in solutions, in uranium hexafluoride and in solids - Part 1: reduction with iron (II) / oxidation with potassium bi-chromate / titration method

    International Nuclear Information System (INIS)

    This standard document describes the mode of operation of three different methods for the quantitative dosimetry of uranium in solutions, in UF6 and in solids: reduction by iron (II), oxidation by potassium bi-chromate and titration. (J.S.)

  2. Application of complex engineering solutions through advanced composite innovation (for repair of degraded buried pipe at Vandellos II Nuclear Power Plant); Reparacion de tuberias de un sistema de servicios no esenciales con recubrimiento interno de fibra de carbono

    Energy Technology Data Exchange (ETDEWEB)

    Bueno, J. M.; Raji, B. B.

    2011-07-01

    This technical presentation is focused on introducing an engineering solution approach and identification of sensitivity of applications of advanced carbon fiber in a pressurized wet environment: Engineering design, quality assurance of installation, inspection, and a comprehensive testing program to validate and bench mark the design data and compliance with code requirements in nuclear power plants.

  3. Marketing nuclear energy

    International Nuclear Information System (INIS)

    It is shown how the nuclear industry can present itself to the American public in a more favorable light. Two pieces of writing concerning the same event, the reactor accident at the Enrico Fermi reactor near Detroit, Michigan in 1966, is analyzed for clarity and readability. Seven principles of persuasive communication, as outlined by R.H.S. Crossman who was in charge of Allied psychological warfare in Europe during World War II, are quoted along with examples of their violation, and suggestions given how they might be improved. 10 refs

  4. Public relations policy: The Electronuclear experience

    International Nuclear Information System (INIS)

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

  5. Nuclear Legislation in OECD and NEA Countries. Regulatory and Institutional Framework for Nuclear Activities - Australia

    International Nuclear Information System (INIS)

    This country profile provide comprehensive information on the regulatory and Institutional Framework governing nuclear activities as well as a detailed review of a full range of nuclear law topics, including: mining regime; radioactive substances; nuclear installations; trade in nuclear materials and equipment; radiation protection; radioactive waste management; non-proliferation and physical protection; transport; and nuclear third party liability. The profile is complemented by reproductions of the primary legislation regulating nuclear activities in the country. Content: I) - General Regulatory Regime: 1. Introduction; 2. Mining regime; 3. Radioactive substances and equipment; 4. Nuclear installations (Licensing and inspection, including nuclear safety; Protection of the environment against radiation effects); 5. Trade in nuclear materials and equipment; 6. Radiation protection; 7. Radioactive waste management; 8. Non-proliferation and physical protection (Bilateral safeguards agreements; International Atomic Energy Agency Safeguards Agreement; The South Pacific Nuclear Free Zone Treaty Act; The Comprehensive Nuclear Test-Ban Treaty Act; The Nuclear Non-Proliferation (Safeguards) Act); 9. Transport; 10. Nuclear third party liability; II) - Institutional Framework: 1. Regulatory and supervisory authorities (Minister for Health and Ageing; Minister for Foreign Affairs; Minister for the Environment, Heritage and the Arts; Minister for, Resources, Energy and Tourism); 2. Advisory bodies (Radiation Health and Safety Advisory Council; Advisory Committees); 3. Public and semi-public agencies (Australian Radiation Protection and Nuclear Safety Agency (ARPANSA); Australian Safeguards and Non-Proliferation Office; Australian Nuclear Science and Technology Organisation (ANSTO); Supervising Scientist)

  6. Nuclear violence

    International Nuclear Information System (INIS)

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

  7. Nuclear Astrophysics

    Science.gov (United States)

    Drago, Alessandro

    2005-04-01

    The activity of the Italian nuclear physicists community in the field of Nuclear Astrophysics is reported. The researches here described have been performed within the project "Fisica teorica del nucleo e dei sistemi a multi corpi", supported by the Ministero dell'Istruzione, dell'Università e della Ricerca.

  8. Nuclear engineering introduction

    International Nuclear Information System (INIS)

    This book describes nuclear engineering introducing nuclear energy and its utilization, nuclear engineering basics, nuclear reactor and nuclear reaction, nuclear steam system, thermal output and reactor physics, transient reactor, radiation management, safety in nuclear power plant and nuclear economy. It explains the technical terms of nuclear engineering in detail.

  9. Nuclear stress test

    Science.gov (United States)

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

  10. Nuclear energy

    International Nuclear Information System (INIS)

    This book provides the man in the street with a fair presentation of nuclear energy and can help him to build his own opinion about this much debated question. The first chapter defines what is involved in the hazy term of energy. The second chapter explains how a nuclear power plant operates. The chapters 3 to 6 give a good grounding in basic physics to understand radioactivity and the different processes that occur in a nuclear reactor. The chapters 7 and 8 present the different reactor types and the complete fuel cycle from uranium ore extraction to radioactive waste storage. The last chapter is dedicated to the pros and cons of nuclear energy, this chapter includes a presentation of the organization of nuclear safety in France. (A.C.)

  11. Nuclear haematology

    International Nuclear Information System (INIS)

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

  12. Nuclear Safety

    International Nuclear Information System (INIS)

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

  13. Recent results in nuclear astrophysics

    CERN Document Server

    Coc, Alain; Kiener, Juergen

    2016-01-01

    In this review, we emphasize the interplay between astrophysical observations, modeling, and nuclear physics laboratory experiments. Several important nuclear cross sections for astrophysics have long been identified e.g. 12C(alpha,gamma)16O for stellar evolution, or 13C(alpha,n)16O and 22Ne(alpha,n)25Mg as neutron sources for the s-process. More recently, observations of lithium abundances in the oldest stars, or of nuclear gamma-ray lines from space, have required new laboratory experiments. New evaluation of thermonuclear reaction rates now includes the associated rate uncertainties that are used in astrophysical models to i) estimate final uncertainties on nucleosynthesis yields and ii) identify those reactions that require further experimental investigation. Sometimes direct cross section measurements are possible, but more generally the use of indirect methods is compulsory in view of the very low cross sections. Non-thermal processes are often overlooked but are also important for nuclear astrophysics,...

  14. Nuclear questions

    Energy Technology Data Exchange (ETDEWEB)

    Durrani, M. [Physics World (United Kingdom)

    2006-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2008-07-01

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

  16. North Korean nuclear issues and the LWR project; technical cooperation scheme in nuclear control

    International Nuclear Information System (INIS)

    Three pillars of nuclear control regime are nuclear material accountancy control, nuclear export control and physical protection in order to assure nuclear transparency of a nation. It would be prudent to have a proper understanding of the DPRK's nuclear infrastructure before a meaningful collaboration may take place. Chapter 1 introduces the history of nuclear program development in the DPRK, Chapter 2 contains the technical framework of the state system of nuclear materials accountancy control, and Chapters 3 and 4 describe the nuclear export control and physical protection infrastructure needed in preparation for the LWR plant operation. The final Chapter 5 summarizes the salient points raised at the Muju Workshop. Completion of the Monograph series I, II, III is expected to contribute towards the successful completion of the KEDO LWR construction following the satisfactory conclusion of the IAEA verification process

  17. Nuclear medicine

    International Nuclear Information System (INIS)

    The task of the Expert Committee was to review the technical development and efficacy of nuclear medicine methods and to recommend the best possible means of establishing nuclear medicine services at various levels of medical care in different countries. After reviewing the contributions which nuclear medicine can make, the various types of medical institutions and hospitals in existence, the requirements, organization and funding of nuclear medicine services, and the cost/effectiveness of nuclear medicine, a number of recommendations were made. IAEA and WHO should make information on existing methods of cost/effectiveness analysis widely available; invite governments to include a description of such analysis methods in training programmes of their health officers; assist in the acquisition of the necessary data; and encourage and eventually support actual applications of such analyses to carefully selected nuclear medicine procedures in varying medicosocial environments. They were further recommended to study possible ways of improving reliability and ease of servicing nuclear medicine equipment, and extent of possible local construction; the possibility of making available supplies of matched characterized reagents for radioimmunoassay and related techniques; and to study the advantages of establishing a network of collaborating centres on an international basis

  18. Elizabeth II uus kunstigalerii

    Index Scriptorium Estoniae

    1999-01-01

    Tähistamaks oma troonile asumise 50. aastapäeva, avab Elizabeth II 6. II 2002 Buckinghami palees uue kunstigalerii, mis ehitatakse palee tiibhoonena. Arhitekt John Simpson. Elizabeth II kunstikogust

  19. Nuclear questions

    International Nuclear Information System (INIS)

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

  20. Nuclear Scales

    OpenAIRE

    Friar, J. L.

    1998-01-01

    Nuclear scales are discussed from the nuclear physics viewpoint. The conventional nuclear potential is characterized as a black box that interpolates nucleon-nucleon (NN) data, while being constrained by the best possible theoretical input. The latter consists of the longer-range parts of the NN force (e.g., OPEP, TPEP, the $\\pi$-$\\gamma$ force), which can be calculated using chiral perturbation theory and gauged using modern phase-shift analyses. The shorter-range parts of the force are effe...

  1. Nuclear Technology Review 2007

    International Nuclear Information System (INIS)

    . Worldwide at the end of 2006, there were 435 nuclear power reactors in operation, totalling 370 GW(e). In the course of the year two new reactors were connected to the grid and eight were retired, resulting in a small net growth in global nuclear generating capacity during 2006, taking the increased rating of existing reactors into account, of 1443 MW(e). There were three construction starts plus the resumption of active construction at one plant in the Russian Federation, for a total of 23 641 MW(e) under construction at the end of the year. Driven partly by rising expectations for nuclear power, uranium spot prices continued to rise in 2006, to nine times their historic 2000 low. Annual exploration expenditures have increased more than three-fold since 2001. Brazil opened its new Resende enrichment facility, and construction started at the US National Enrichment Facility and at the Georges Besse II enrichment plant in France. Final testing for commissioning Japan's new Rokkasho reprocessing plant began in March. The world's only operating geological repository, the Waste Isolation Pilot Plant in the USA, received its first recertification from the US Environmental Protection Agency since opening in 1999. France passed new legislation setting goals to apply for a licence for a deep geological repository with the aim of opening it by 2025, and for a prototype reactor by 2020 to, among other tasks, test transmutation of long-lived radioisotopes. The Swedish nuclear fuel and waste management company SKB filed an application for an encapsulation plant in Oskarshamn, the first step towards final disposal.

  2. Institute for Nuclear Theory annual report No. 2, 1 March 1991--29 February 1992

    Energy Technology Data Exchange (ETDEWEB)

    Haxton, W.; Henley, E. M. [Washington Univ., Seattle, WA (United States). Dept. of Physics

    1992-01-01

    This report discusses research on the following topics in Nuclear physics: electromagnetic interactions and few-nucleon systems; N*'s and nucleon structure; mesons and fields in nuclei; and nuclear astrophysics of type II supernovae. (LSP).

  3. Institute for Nuclear Theory annual report No. 2, 1 March 1991--29 February 1992

    International Nuclear Information System (INIS)

    This report discusses research on the following topics in Nuclear physics: electromagnetic interactions and few-nucleon systems; N*'s and nucleon structure; mesons and fields in nuclei; and nuclear astrophysics of type II supernovae. (LSP)

  4. Nuclear physics

    International Nuclear Information System (INIS)

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

  5. [Nuclear theory

    International Nuclear Information System (INIS)

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

  6. Nuclear safety

    International Nuclear Information System (INIS)

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

  7. Nuclear reaction

    CERN Multimedia

    Penwarden, C

    2001-01-01

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

  8. The future of nuclear power

    CERN Document Server

    Mahaffey, James

    2012-01-01

    Newly conceived, safer reactor designs are being built in the United States (and around the world) to replace the 104 obsolete operating nuclear power reactors in this country alone. The designs--which once seemed exotic and futuristic--are now 40 years old, and one by one these vintage Generation II plants will reach the end of productive service in the next 30 years. The Future of Nuclear Power examines the advanced designs, practical concepts, and fully developed systems that have yet to be used. This book introduces readers to the traditional, American system of units, with some archaic te

  9. Nuclear accidents

    International Nuclear Information System (INIS)

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

  10. Nuclear Nonproliferation

    Energy Technology Data Exchange (ETDEWEB)

    Atkins-Duffin, C E

    2008-12-10

    With an explosion equivalent of about 20kT of TNT, the Trinity test was the first demonstration of a nuclear weapon. Conducted on July 16, 1945 in Alamogordo, NM this site is now a Registered National Historic Landmark. The concept and applicability of nuclear power was demonstrated on December 20, 1951 with the Experimental Breeder Reactor Number One (EBR-1) lit four light bulbs. This reactor is now a Registered National Historic Landmark, located near Arco, ID. From that moment forward it had been clearly demonstrated that nuclear energy has both peaceful and military applications and that the civilian and military fuel cycles can overlap. For the more than fifty years since the Atoms for Peace program, a key objective of nuclear policy has been to enable the wider peaceful use of nuclear energy while preventing the spread of nuclear weapons. Volumes have been written on the impact of these two actions on the world by advocates and critics; pundits and practioners; politicians and technologists. The nations of the world have woven together a delicate balance of treaties, agreements, frameworks and handshakes that are representative of the timeframe in which they were constructed and how they have evolved in time. Collectively these vehicles attempt to keep political will, nuclear materials and technology in check. This paper captures only the briefest abstract of the more significant aspects on the Nonproliferation Regime. Of particular relevance to this discussion is the special nonproliferation sensitivity associated with the uranium isotope separation and spent fuel reprocessing aspects of the nuclear fuel cycle.

  11. Nuclear education

    International Nuclear Information System (INIS)

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

  12. Seguro Nuclear

    International Nuclear Information System (INIS)

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

  13. Nuclear Data

    Energy Technology Data Exchange (ETDEWEB)

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

    2014-01-23

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

  14. Nuclear technology

    International Nuclear Information System (INIS)

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

  15. Nuclear enthalpies

    OpenAIRE

    Rozynek Jacek

    2015-01-01

    Even small departures from a nuclear equilibrium density with constant nucleon masses require an increase of a nucleon enthalpy. This process can be described as volume corrections to a nucleon rest energy, which are proportional to pressure and absent in a standard Relativistic Mean Field (RMF) with point-like nucleons. Bag model and RMF calculations show the modifications of nucleon mass, nucleon radius and a Parton Distribution Function (PDF) of Nuclear Matter (NM) above the saturation poi...

  16. Nuclear astrophysics

    Energy Technology Data Exchange (ETDEWEB)

    Arnould, M. [Institut d' Astronomie et d' Astrophysique, Universite Libre de Bruxelles, Bruxelles (Belgium); Takahashi, K. [Max-Planck-Institut fuer Astrophysik, Garching (Germany)

    1999-03-01

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

  17. Nuclear astrophysics

    Science.gov (United States)

    Arnould, M.; Takahashi, K.

    1999-03-01

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

  18. Nuclear Structure

    Science.gov (United States)

    Gargano, Angela

    2003-04-01

    An account of recent studies in the field of theoretical nuclear structure is reported. These studies concern essentially research activities performed under the Italian project "Fisica Teorica del Nucleo e dei Sistemi a Molti Corpi". Special attention is addressed to results obtained during the last two years as regards the development of new many-body techniques as well as the interpretation of new experimental aspects of nuclear structure.

  19. Nuclear fuel

    International Nuclear Information System (INIS)

    It is expected that nuclear power generation will reach 49 million kW in 1985 and 129 million kW in 1995, and the nuclear fuel having to be supplied and processed will increase in proportion to these values. The technical problems concerning nuclear fuel are presented on the basis of the balance between the benefit for human beings and the burden on the human beings. Recently, especially the downstream of nuclear fuel attracts public attention. Enriched uranium as the raw material for light water reactor fuel is almost monopolized by the U.S., and the technical information has not been published for fear of the diversion to nuclear weapons. In this paper, the present situations of uranium enrichment, fuel fabrication, transportation, reprocessing and waste disposal and the future problems are described according to the path of nuclear fuel cycle. The demand and supply of enriched uranium in Japan will be balanced up to about 1988, but afterwards, the supply must rely upon the early establishment of the domestic technology by centrifugal separation method. No problem remains in the fabrication of light water reactor fuel, but for the fabrication of mixed oxide fuel, the mechanization of the production facility and labor saving are necessary. The solution of the capital risk for the construction of the second reprocessing plant is the main problem. Japan must develop waste disposal techniques with all-out efforts. (Kako, I.)

  20. What are the communication challenges for politicians, experts and stakeholders in order to enhance transparency in nuclear waste management decisions? Report from a Team Syntegrity Meeting. The European Project RISCOM-II. Work Package 3

    Energy Technology Data Exchange (ETDEWEB)

    Andersson, Kjell [Karinta-Konsult, Taeby (Sweden); Espejo, Raul [Syncho Ltd., Birmingham (United Kingdom); Wene, Clas-Otto [Wenergy, Lund (Sweden)

    2003-09-01

    The Team Syntegrity Meeting is a special part of the project. It aims for increased awareness among key stakeholder groups in Europe about how nuclear waste decision processes should be developed in order to increase transparency and trust. Team Syntegrity is conducted with a special meeting format. The self-organisation of the meeting is a strong positive feature of the format. Instead of having a project leader setting the agenda, the participants formulate their own topics of relevance starting from an opening question. This report documents the meeting that was held in Lanaken, Belgium on 14-17 May 2002. The opening question for the meeting was: What are communication challenges for politicians, experts and stakeholders in order to enhance transparency in nuclear waste management decisions? There are different opinions about how communication on nuclear waste issues should be done. There are differences between stakeholder groups, and there are different approaches taken in various countries. Still it should be possible to reach a deeper understanding of social communications, that is, understanding the requirements to have effective communications between policy makers, experts and stakeholders. The aim was thus not to develop common views on the nuclear waste problem as such, but rather common grounds for developing procedures for effective communication. Hopefully, this meeting made some progress in this direction. The call for the Team Syntegrity (TS) Meeting resulted in 105 Statements of Importance given in Appendix 2. Following the TS format the meeting then formed its own agenda by first producing 30 Aggregated Statements of Importance (Appendix 3), which were grouped into 12 Consolidated Statements of Importance or topics. The group discussions were thus held under the twelve topics of: Consultation, communication and participation; Mutual learning; Roles and arenas; Heritage; Transparency; Wider context; Process; Risk; Institutional cultures