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Sample records for brazilian nuclear installations

  1. Development of a quality management system for Brazilian nuclear installations

    International Nuclear Information System (INIS)

    The present work is a proposal for developing a quality management system for Brazilian nuclear installations, based on applicable standards. The standard ISO 9001:2000 [4] establishes general requirements for the implementation of a quality management system in all kinds of organizations. The standard IAEA 50-C/SG-Q [1] establishes general requirements for the implementation of a quality assurance system in nuclear installations. The standard CNEN-NN- 1.16 [5] establishes the regulating requirements for the quality assurance systems and programs of nuclear installations, for licensing and authorization for operation of these installations in Brazil. The revision of standard IAEA 50-C/SG-Q [1], to be replaced by IAEA DS 338 [2] and IAEA DPP 349 [3], introduces the concept of 'Integrated Management System' for the nuclear area, in preference to the concept of 'Quality Assurance'. This approach is incorporated with the current tendency, because it guides the system to manage, in an integrated way, the requirements of quality, safety, health, environment, security and economics of the installation. The results of the characterization of the quality management systems established in the applicable standards are presented, with the determination of the common and conflicting points among them. Referring data to quality assurance program/quality management system in some nuclear installations of IAEA Member States are also presented. (author)

  2. 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

  3. Study of a brazilian cask and its installation for PWR spent nuclear fuel dry storage

    International Nuclear Information System (INIS)

    Spent nuclear fuel (SNF) is removed from the nuclear reactor after the depletion on efficiency in generating energy. After the withdrawal from the reactor core, the SNF is temporarily stored in pools at the same site of the reactor. At this time, the generated heat and the short and medium lived radioactive elements decay to levels that allow removing SNF from the pool and sending it to temporary dry storage. In that phase, the fuel needs to be safely and efficiently stored, and then, it can be retrieved in a future, or can be disposed as radioactive waste. The amount of spent fuel increases annually and, in the next years, will still increase more, because of the construction of new nuclear plants. Today, the number of new facilities back up to levels of the 1970's, since it is greater than the amount of decommissioning in old installations. As no final decision on the back-end of the nuclear fuel cycle is foreseen in the near future in Brazil, either to recover the SNF or to consider it as radioactive waste, this material has to be isolated in some type of storage model existing around the world. In the present study it is shown that dry SNF storage is the best option. A national cask model for SNF as well these casks storage installation are proposed. It is a multidisciplinary study in which the engineering conceptual task was developed and may be applied to national SNF removed from the Brazilian power reactors, to be safely stored for a long time until the Brazilian authorities will decide about the site for final disposal. (author)

  4. Analysis of normative requirements for the development and implementation of a quality management system in Brazilian nuclear installations and activities

    International Nuclear Information System (INIS)

    The present work identifies, characterizes and analyses the normative requirements for the development and implementation of quality management systems in Brazilian nuclear installations and activities. The requirements established in standards IAEA GS-R-3, IAEA GS-G-3.1, IAEA DS 349, NBR ISO 9001:2000 e CNEN-NN-1.16 are critically analyzed. A correlation matrix of the applicable standards is presented and the related topics among them are identified. The standards IAEA GS-R-3, IAEA GS-G-3.1 and IAEA DS 349 define general requirements for establishing, implementing, assessing and continually improving an integrated management system in nuclear installations and activities, in IAEA member countries. The standard NBR ISO 9001:2000 establishes general requirements for the implementation of a quality management system in all kinds of organizations. The standard CNEN NN-1.16 establishes the regulating requirements for the quality assurance systems and programs of nuclear installations, for licensing and authorization for operation of these installations in Brazil. The standard IAEA GS-R-3 that replaces the code IAEA 50-C-Q introduces the concept of 'Integrated Management System' for the nuclear area, in preference to the concepts of 'Quality Assurance' and 'Quality Management'. This new approach is aligned with the current tendency incorporating requirements of quality, safety, health, environment, security, economics and other in a unique management system. Examples of quality management systems implemented by Brazilian nuclear organizations and by nuclear organizations outside Brazil are analyzed and considered in the discussion of results. (author)

  5. Nuclear Installations Act 1965

    International Nuclear Information System (INIS)

    This Act governs all activities related to nuclear installations in the United Kingdom. It provides for the licensing procedure for nuclear installations, the duties of licensees, the competent authorities and carriers of nuclear material in respect of nuclear occurrences, as well as for the system of third party liability and compensation for nuclear damage. The Act repeals the Nuclear Installations (Licensing and Insurance) Act 1959 and the Nuclear Installations (Amendment Act) 1965 except for its Section 17(2). (NEA)

  6. Computer systems for nuclear installation data control

    International Nuclear Information System (INIS)

    The computer programs developed by Divisao de Instalacoes Nucleares (DIN) from Brazilian CNEN for data control on nuclear installations in Brazil are presented. The following computer programs are described: control of registered companies, control of industrial sources, irradiators and monitors; control of liable person; control of industry irregularities; for elaborating credence tests; for shielding analysis; control of waste refuge

  7. The Brazilian Nuclear Energy Program

    International Nuclear Information System (INIS)

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

  8. The insurance of nuclear installations

    International Nuclear Information System (INIS)

    A brief account is given of the development of nuclear insurance. The subject is dealt with under the following headings: the need for nuclear insurance, nuclear insurance pools, international co-operation, nuclear installations which may be insured, international conventions relating to the liability of operators of nuclear installations, classes of nuclear insurance, nuclear reactor hazards and their assessment, future developments. (U.K.)

  9. Legal bases for the installation of nuclear power plants

    International Nuclear Information System (INIS)

    The process of installation of nuclear power plants in the context of the Brazilian legal system is analysed. The structure of the political and administrative system related to the matter and the correspondent legislation are discussed. (A.L.)

  10. Nuclear installations sites safety

    International Nuclear Information System (INIS)

    This report is divided into ten parts bearing: 1 Safety analysis procedures for Basis Nuclear Installations sites (BNI) in France 2 Site safety for BNI in France 3 Industrial and transport activities risks for BNI in France 4 Demographic characteristics near BNI sites in France 5 Meteorologic characteristics of BNI sites in France 6 Geological aspects near the BNI sites in France 7 Seismic studies for BNI sites in France 8 Hydrogeological aspects near BNI sites in France 9 Hydrological aspects near BNI sites in France 10 Ecological and radioecological studies of BNI sites in France

  11. Experimental sodium loops at brazilian Institute of Nuclear Engineering (IEN)

    International Nuclear Information System (INIS)

    Thermal circuits and sodium installations proceeding from Italy to be assembled at brazilian Nuclear Engineering Institute (IEN) are presented. Also some information are provided on the sodium experimental facilities presently existent. (L.C.J.A.)

  12. The new Brazilian nuclear policy

    International Nuclear Information System (INIS)

    Since March 15, 1990, when Fernando Collor's Government was inaugurated, the Brazilian President has been pursuing a nuclear policy aimed at ensuring compliance with the constitutional principles and rules that determine the utilization of nuclear energy solely for peaceful uses and purposes. The development of Brazilian nuclear policy has followed several stages, which are reported in this paper from a legal and institutional point of view. (author)

  13. Nuclear-energetic installations

    International Nuclear Information System (INIS)

    This book contains some selected chapters of nuclear physics. It contains the following chapters: (1) Introduction; (2) Fundamentals of nuclear physics; (3) Fission of nuclei; (4) Neutrons in fission process; (5) Nuclear reactors; (6) Characteristics of basic types of energetic reactors; (7) Perspective types of nuclear reactors; (8) Fuel cycle; (9) Nuclei fusion, reactor ITER; (10) Accelerators; (11) Perspective use of accelerators in nuclear energetics

  14. The Brazilian nuclear power programme

    International Nuclear Information System (INIS)

    The booklet contains survey articles on the nuclear power problems of Brazil, the German-Brazilian nuclear power agreement, the application of international safety measures, and 'Brazil and the non-proliferation of nuclear weapons'. The agreement is given in full wording. (HP)

  15. Offshore nuclear installations

    International Nuclear Information System (INIS)

    It is possible now to foresee the creation of nuclear power plants on floating or fixed islands although from the safety viewpoint, floating islands are preferable. The definition of the legal nature of artificial islands raises a first problem insofar as artificial islands are neither islands nor ships. Furthermore, their statute would differ according to whether they were sited in territorial seas or in the new 'economic zones'. This leads to consideration of the applicability of Italian maritime legislation to nuclear power plants on floating islands without setting aside that of international regulations on radioactive maritime pollution. (N.E.A.)

  16. The safety of nuclear installations

    International Nuclear Information System (INIS)

    This Safety Fundamental publication sets out basic objectives, concepts and principles for ensuring safety that can be used both by the IAEA in its international assistance operations and by Member States in their national nuclear programmes. These Safety Fundamentals apply primarily to those nuclear installations in which the stored energy developed in certain situations could potentially results in the release of radioactive material from its designated location with the consequent risk of radiation exposure of people. These principles are applicable to a broad range of nuclear installations, but their detailed application will depend on the particular technology and the risks posed by it. In addition to nuclear power plants, such installations may include: research reactors and facilities, fuel enrichment, manufacturing and reprocessing plants; and certain facilities for radioactive waste treatment and storage

  17. The function of specialized organization in work safety engineering for nuclear installations

    International Nuclear Information System (INIS)

    The attributions of Brazilian CNEN in the licensing procedures of any nuclear installation are discussed. It is shown that the work safety engineering and industrial safety constitute important functions for nuclear safety. (M.C.K.)

  18. Leukaemia near british nuclear installations

    International Nuclear Information System (INIS)

    An excess of childhood leukaemia has been seen near some British nuclear installations, especially near the Sellafield reprocessing plant. The same result was found in a more general study including a large number of nuclear sites. Similar studies made in USA, Canada and France have been negative. Moreover, epidemiological studies made in England have discovered other childhood leukaemia clusters in areas far from nuclear facilities, and especially near potential sites of nuclear installations. Several explanations are suggested but no definite conclusion is yet possible. Doses from radioactive releases seem to be too low to account for the additional deaths from leukaemia by environmental contamination. A virus activation, which might be associated with population influx into rural isolated areas, has been considered. The hypothesis of genetic mutation induced by ionising radiation in the fathers of children with leukaemia has been made because a higher risk of leukaemia was observed for children of fathers employed at Sellafield. No firm conclusion is possible considering the small number of observed cases and the lack of excess leukaemias in the offspring of Hiroshima and Nagasaki survivors. The possibility of internal contamination, chemicals or even radon is discussed as other causes. Studies in progress might allow to find an answer to the problem of leukaemia in the vicinity of British nuclear installations

  19. Quality assurance in nuclear installations

    International Nuclear Information System (INIS)

    It has been proven that the bad quality of products, equipment, installations, and services is not due to the lack of tests, experiments and verifications. The main causes are associated with insufficient organization of the activities that have influence on the quality. The garantee of quality is conceptualized as an appropriate instrument composed of normalized criteria initially in advanced technologies. Such as nuclear science and aerospace technology. However, with the appropriate modifications it can be applied to conventional technologies

  20. 36th Brazilian Workshop on Nuclear Physics

    CERN Document Server

    Brandão de Oliveira, José Roberto; Barbosa Shorto, Julian Marco; Higa, Renato

    2014-01-01

    The Brazilian Workshop on Nuclear Physics (RTFNB, acronym in Portuguese) is organized annually by the Brazilian Physics Society since 1978, in order to: promote Nuclear Physics research in the country; stimulate and reinforce collaborations among nuclear physicists from around the country; disseminate advances in nuclear physics research and its applications; disseminate, disclose and evaluate the scientific production in this field.

  1. The dismantling of nuclear installations

    International Nuclear Information System (INIS)

    for nuclear installations, the dismantling is an important part of their exploitation. The technology of dismantling is existing and to get a benefit from the radioactive decay, it seems more easy for operating company such E.D.F. to wait for fifty years before dismantling. But in order to get the knowledge of this operation, the Safety Authority wanted to devote this issue of 'Controle'to the dismantling method. This issue includes: the legal aspects, the risks assessment, the dismantling policy at E.D.F., the site of Brennilis (first French experience of dismantling), the dismantling techniques, the first dismantling of a fuel reprocessing plant, comparison with classical installations, economic aspect, some German experiences, the cleansing of the american site of Handford. (N.C.)

  2. Analysis of normative requirements for the development and implementation of a quality management system in Brazilian nuclear installations and activities; Analise de requisitos normativos para o desenvolvimento e a implementacao de um sistema de gestao da qualidade em instalacoes e atividades nucleares brasileiras

    Energy Technology Data Exchange (ETDEWEB)

    Kibrit, Eduardo

    2008-07-01

    The present work identifies, characterizes and analyses the normative requirements for the development and implementation of quality management systems in Brazilian nuclear installations and activities. The requirements established in standards IAEA GS-R-3, IAEA GS-G-3.1, IAEA DS 349, NBR ISO 9001:2000 e CNEN-NN-1.16 are critically analyzed. A correlation matrix of the applicable standards is presented and the related topics among them are identified. The standards IAEA GS-R-3, IAEA GS-G-3.1 and IAEA DS 349 define general requirements for establishing, implementing, assessing and continually improving an integrated management system in nuclear installations and activities, in IAEA member countries. The standard NBR ISO 9001:2000 establishes general requirements for the implementation of a quality management system in all kinds of organizations. The standard CNEN NN-1.16 establishes the regulating requirements for the quality assurance systems and programs of nuclear installations, for licensing and authorization for operation of these installations in Brazil. The standard IAEA GS-R-3 that replaces the code IAEA 50-C-Q introduces the concept of 'Integrated Management System' for the nuclear area, in preference to the concepts of 'Quality Assurance' and 'Quality Management'. This new approach is aligned with the current tendency incorporating requirements of quality, safety, health, environment, security, economics and other in a unique management system. Examples of quality management systems implemented by Brazilian nuclear organizations and by nuclear organizations outside Brazil are analyzed and considered in the discussion of results. (author)

  3. Brazilian experience on qualification of radiation protection officers for industry installations

    International Nuclear Information System (INIS)

    This work presents a brief description of the process used by the brazilian regulatory authority . National Commission of Nuclear Energy (CNEN) . to qualify radiation protection officers especially to work at industry practices. A Committee for Certification of Qualification was created in order to be responsible for the elaboration and organization of the rules for the examinations. From 1999 to 2002 more than 400 radiation protection officers were qualified according to this process. The main industrial practices involved were industrial radiography, industrial irradiators, industrial accelerators, well logging petroleum and nuclear gauge. An overview is also given about the national regulatory infrastructure responsible for radiation safety controls, including the Brazilian regulation infrastructure and the national inventory of industrial installations. (author)

  4. Public perception of nuclear installations

    International Nuclear Information System (INIS)

    The key for nuclear renaissance is public acceptance. Facing energetic needs that occur around the world and lack of resources, the work of characterizing and proposing new models to represent public opinion is extremely important to all stakeholders. Even though public opinion's study on risks is relatively recent, may approaches of this subject have been suggested and presented, especially for the topic of perceptions on nuclear installations. Actual definitions on risk exist between objective and subjective models, that reflect opinions of lay public and experts. Strategies on communications with the public may be evaluated from many developed models, and its results may be registered. The use of structural models may present an exploratory character as well as confirmatory theories, as an adequate tool for the development of studies on public perception. In this work, a structural model is presented from data obtained in a previous report, and added to data collected before and after the Fukushima nuclear accident, in Japan. The effects developed from this accident offered a unique opportunity to study public opinion through the effects of a serious nuclear accident and its effects on risk communications. Aside, this work attempted to check the structural model according with obtained results, in order to sustain a constant improvement of the working tools. Yet, a comparison between data according to experts' respondents and lay public ones as well as a comparison among different students before and after a visit to nuclear station is considered. Obtained data for the structural models has been applied for on a structural model and analyzed by structural correlation matrix, latent variable structural coefficients and R2 values. Results indicate that public opinion maintains its rejection on nuclear energy and the perception of benefits, facing perceived risks before the accident, has diminished. A new model that included a latent variable for corresponding

  5. Brazilian nuclear programme - energy in Brazil

    International Nuclear Information System (INIS)

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

  6. The new Brazilian legislation on nuclear protection

    International Nuclear Information System (INIS)

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

  7. Nuclear law: institutions. Nuclear installations; Droit nucleaire: institutions. Installations nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-07-15

    The object of this work is since its first edition in 1983 under the title 'Collection of nuclear activities legislation and regulation ' to realize an ordered collection of texts constituting the juridical and institutional frame of nuclear activities, gathering the legislative, regulatory and technical texts; the international, European and national texts. Aiming to include the whole of the atom applications, this collection tackles various themes in ten chapters spread on five volumes. The volume number one includes the following chapters: Institutions, nuclear facilities. (N.C.)

  8. The year 2000 passage on nuclear installations

    International Nuclear Information System (INIS)

    The year 2000 impact on the nuclear installations must be carefully treated. Since 1998 the operating have been examine by the safety authorities and all seem ready to prevent the year 2000 risk. The three following examples are described: the EDF (Electricite De France) reactors, the fuel cycle installations, the experimental and research reactors laboratories and other installations of the Cea. (A.L.B.)

  9. Demographic characteristics of nuclear installations sites

    International Nuclear Information System (INIS)

    The selection of a nuclear installations sites can not be conceived without a deep analysis of demographic context. This analysis permits to define the critical populations around the installation and is an essential element of emergency plans. 1 tab., 2 refs. (F.M.)

  10. The Swiss nuclear installations annual report 1992

    International Nuclear Information System (INIS)

    This report concerns the safety of the Swiss nuclear installations in the period of 1992. Surveillance of these installations with regard to nuclear safety, including radiation protection, is among the tasks of the Swiss Federal Nuclear Safety Inspectorate (HSK). In Switzerland five nuclear power plants are operational: Beznau I and II, Muehleberg, Goesgen and Leibstadt. Research reactors of thermal capacities below 10 MWth are operational at the Paul Scherrer Institute (PSI), at the Swiss Federal Institute of Technology Lausanne and at the University of Basle. Further subject to HSK's supervision are all activities at PSI involving nuclear fuel or ionizing radiation, the shut down experimental reactor of Lucens, the exploration in Switzerland of final disposal facilities for radwaste and the interim radwaste storage facilities. The present report first deals with the nuclear power plants and covers, in individual sections, the aspects of installation safety, radiation protection as well as personnel and organization, and the resulting overall impression from the point of view of HSK (chapters 1-4). In chapter 5, the corresponding information is given for the research installations. Chapter 6 on radwaste disposal is dedicated to the waste treatment, waste from reprocessing, interim storage and exploration by the NAGRA. In chapter 7, the status of emergency planning in the nuclear power plants' vicinity is reported. Certificates issued for the transport of radioactive materials are dealt with in chapter 8. Finally chapter 9 goes into some general questions relating to the safety of nuclear installations, and in particular covers important events in nuclear installations abroad. In all, the operation of the Swiss nuclear installations in the period of 1992 is rated safe by HSK. (author) 7 figs., 13 tabs

  11. Mortality around French nuclear installations

    International Nuclear Information System (INIS)

    The electricity production from nuclear origin is, in France, old and very important. So, it was essential to study the observed mortality between 0 and 24 years in cities that are situated around the main french nuclear plants. Results are separately presented for each of main facilities in operation before 1975: Chinon, Chooz, La Hague, Marcoule, Saint-Laurent and Bugey

  12. Statement of nuclear incidents at nuclear installations

    International Nuclear Information System (INIS)

    The Health and Safety Executive (HSE) presents the statement of nuclear incidents at nuclear installations published under the Health and Safety Commission's powers derived from section 11 of the Health and Safety at Work, etc. Act 1974. INCIDENT 02/4/1. Harwell (United Kingdom Atomic Energy Authority) On 6 November 2002 during operations in a glove box in B220, the over pressure alarm sounded. The operators evacuated and shortly afterwards the airborne activity monitors also sounded. The building emergency arrangements for airborne activity alarms was initiated to ascertain the source and to manage the operations. An investigation by UKAEA confirmed that a release of Americium 241 into the working area had occurred at a quantity in excess of Schedule 8 column 4 of the Ionising Radiations Regulations 1999 (IRRs). A number of personnel have received intakes including the two operators and the health physics personnel who attended the event. The highest dose (up to 6 mSv.) was received by the Health Physics charge hand. UKAEA placed an embargo on the use of similar systems and have completed their own management investigation and produced an internal report. It concludes that the likely cause of the event was over-pressurisation of the vacuum equipment used in the process. The report also highlights improvements required to the ventilation system in the laboratory and adjoining areas. An action plan has been developed for this work and progress is being made. NIl has followed the UKAEA investigation and carried out its own study including a visit by a ventilation specialist. This has confirmed the problems with the ventilation system. It is a complex issue that may have a wider impact across the building. A letter has been sent to UKAEA detailing a series of short-term requirements and the need to review implications and produce a longer-term action plan. UKAEA is cooperating fully with these requirements. INCIDENT 02/4/2. Dounreay (United Kingdom Atomic Energy

  13. Culture safety in the nuclear installation

    International Nuclear Information System (INIS)

    Culture safety is aimed to empower all the personnel to contribute and responsible to the installation safety where they work in. Culture safety is important as there were so many accidents happened due to the little attention given to the safety, take as examples of what happened in Three Mille Island installation (1979) and Chernobyl (1986). These remind us that human factor gives a significant contribution to the failure of operational system which influences the safety. Therefore, as one of institutions which has nuclear installation. National Nuclear Energy Agency must apply the culture safety to guarantee the safety operation of nuclear installation to protect the personnel, community and environment from the hazard of radioactive radiation. Culture safety has two main components. The first component under the management responsibility is a framework needed in an organisation. The second component is the personnel attitude in al/ levels to respond and optimize those framework. (author)

  14. CNEN activities and brazilian nuclear power policy

    International Nuclear Information System (INIS)

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

  15. Meteorological instrumentation for nuclear installations

    International Nuclear Information System (INIS)

    The main requirements of regulatory agencies, concerning the meteorological instrumentation needed for the licensing of nuclear facilities are discussed. A description is made of the operational principles of sensors for the various meteorological parameters and associated electronic systems. Finally, it is presented an analysis of the problems associated with grounding of a typical meteorological station. (Author)

  16. Construction for Nuclear Installations. Specific Safety Guide

    International Nuclear Information System (INIS)

    This Safety Guide provides recommendations and guidance based on international good practices in the construction of nuclear installations, which will enable construction to proceed with high quality. It can be applied to support the development, implementation and assessment of construction methods and procedures and the identification of good practices for ensuring the quality of the construction to meet the design intent and ensure safety. It will be a useful tool for regulatory bodies, licensees and new entrant countries for nuclear power plants and other nuclear installations

  17. File: the releases from nuclear installations

    International Nuclear Information System (INIS)

    This file presents the policy of the Nuclear Safety Authority and notably its will to reduce the authorized release limits as low as technically and economically possible. This file presents the point of view of others government services intervening in the procedures of releases authorization for nuclear installations, installations classified for environmental protection and secret nuclear installations. Several articles allow to give the nuclear operators actions in order to control the release and the future policy. An english article relative to the reprocessing plant of Sellafield allows an international comparison. To hand over to an ecological association and to a local elected representative bring their advice and evidence on the releases in environment and their impact on man. Even, if the health is not put in motion by the authorized releases, there is no reason to authorize and practice such releases if one can limit them to a reasonable economical cost. (N.C.)

  18. Cancer risks near nuclear installations?

    International Nuclear Information System (INIS)

    The descriptive studies actually at disposal bring to the fore some children leukemia aggregates around some nuclear sites. (Sellafield, and Dounreay in the United kingdom, Kruemmel in Germany). Nevertheless, the studies grouping several sites do not find any global excess. The analytical studies have not brought any answer until now, but have allowed to eliminate some hypothesis such the Gardner genetic hypothesis. (N.C.)

  19. Conception of nuclear ventilation installations

    International Nuclear Information System (INIS)

    Main purposes of ventilation are recalled and two type of room classification in nuclear facilities. The old classification said in accordance to regulations based on the division in containment area (1 to 4) and radioprotection area. A new classification by families, recommended for reprocessing plants, is based on contamination risks. It is shown in particular the structure of ventilation in this last type of classification. Basic principles and recommendations applied in each containment area are given (depression, air renewal rate, temperature hierarchy, etc.)

  20. The Swiss nuclear installations. Annual report 1994

    International Nuclear Information System (INIS)

    Surveillance of the Swiss nuclear installations with regard to nuclear safety, including radiation protection, is among the tasks of the Swiss Federal Nuclear Safety Inspectorate (HSK). Five nuclear power plants are operational in Switzerland: the three units Beznau I and II and Muehleberg with electrical capacities in the range of 300 to 400 MWe, and the two units Goesgen and Leibstadt with capacities between 900 and 1200 MWe. These are light water reactors; at Beznau and Goesgen of the PWR type, and at Muehleberg and Leibstadt of the BWR type. Research reactors of thermal capacities below 10 MWth are operational at the Paul Scherrer Institute (PSI), at the Swiss Federal Institute of Technology Lausanne and at the University of Basel. Further subject to HSK's supervision are all activities at PSI involving nuclear fuel or ionizing radiation, the shut-down experimental reactor of Lucens, the exploration, in Switzerland, of final disposal facilities for radwaste and the interim radwaste storage facilities. The report first deals with the nuclear power and covers, in individual sections, the aspects of installation safety, radiation protection as well as personnel and organization, and the resulting overall impression from the point of view of HSK. In chapter 5, the corresponding information is given for research installations. Chapter 6, on radwaste disposal, is dedicated to the treatment of waste, waste from reprocessing, interim storage and exploration by NAGRA. In chapter 7, the status of emergency planning in the nuclear power plants' proximity is reported. Certificates issued for the transport of radioactive materials are dealt with in chapter 8. Finally chapter 9 goes into general questions relating to the safety of nuclear installations. All in all, the safety of operation of the Swiss nuclear installations, in the period of 1994, is judged as good by HSK. (author) 11 figs., 13 tabs

  1. The Swiss nuclear installations. Annual report 1993

    International Nuclear Information System (INIS)

    Surveillance of the Swiss nuclear installations with regard to nuclear safety, including radiation protection, is among the tasks of the Swiss Federal Nuclear Safety Inspectorate (HSK). Five nuclear power plants are operational in Switzerland: the three units Beznau I and II and Muehleberg with electrical capacities in the range of 300 to 400 MWe, and the two units Goesgen and Leibstadt with capacities between 900 and 1200 MWe. These are light water reactors; at Beznau and Goesgen of the PWR type, and at Muehleberg and Leibstadt of the BWR type. Research reactors of thermal capacities below 10 MWth are operational at the Paul Scherrer Institute (PSI), at the Swiss Federal Institute of Technology Lausanne and at the University of Basel. Further subject to HSK's supervision are all activities at PSI involving nuclear fuel or ionizing radiation, the shut-down experimental reactor of Lucens, the exploration of final disposal facilities for radwaste and the interim radwaste storage facilities in Switzerland. The report first deals with the nuclear power and covers, in individual sections, the aspects of installation safety, radiation protection as well as personnel and organization, and the resulting overall impression from the point of view of HSK. In chapter 5, the corresponding information is given for research installations. Chapter 6, on radwaste disposal, is dedicated to the treatment of waste, waste from reprocessing, interim storage and exploration by NAGRA. In chapter 7, the status of emergency planning in the nuclear power plants' proximity is reported. Certificates issued for the transport of radioactive materials are dealt with in chapter 8. Finally chapter 9 goes into general questions relating to the safety of nuclear installations. All in all, the safety of operation of the Swiss nuclear installations, in the period of 1993, is judged as good by HSK. (author) 10 figs., 11 tabs

  2. Actualization of the Brazilian nuclear regulations

    International Nuclear Information System (INIS)

    The present work has the objective of making public the methodological approach adopted by the Brazilian Nuclear Energy Commission (CNEN) to create a nuclear normative structure up-dated and coherent. According to the Law 4118/62, 6189/74 and 7781/89, is the attribution the CNEN to establish specific guidelines for nuclear safety and radiological protection, and also do dictate safety norms through the emission of Resolutions

  3. Childhood cancer and nuclear installations: a review

    International Nuclear Information System (INIS)

    Many epidemiological studies of childhood cancer around nuclear installations have been conducted in recent years. This article reviews results from Great Britain and elsewhere. Geographical studies have indicated raised risks of childhood leukaemia around some British nuclear installations. However, environmental assessments suggest that the findings are unlikely to be due to radioactive releases from the sites. Case-control studies have allowed more detailed investigation of putative risk factors than is possible from geographical studies. In particular, a recent national study in Britain does not support the hypothesis raised by an earlier study in West Cumbria that paternal radiation exposure prior to conception may increase the risk of leukaemia and non-Hodgkin's lymphoma in offspring. Other studies suggest that childhood leukaemia may have an infective basis, although there is still uncertainty about whether this would explain the findings around nuclear installations. The UK Childhood Cancer Study may provide more information on the causes of these diseases. (author)

  4. Radioactive releases from nuclear installations

    International Nuclear Information System (INIS)

    This paper considers the various stages in the pathway from irradiated nuclear fuel to man as separate modules, in each of which mathematical models are derived to represent the transfer of radioactivity. It begins with the generation of the radioactive inventories within fuel, both fission products and the build-up of transuranic elements; the release from fuel is then considered for metal and oxide fuels, following which the effects of plate-out in the reactor circuit are discussed. There is then a detailed treatment of the behaviour of the effluent in the atmosphere including effective height of release, building entrainment, meteorological dispersion, mechanisms for ground deposition and the effects of the duration of release. Having specified the radioactive environment, its interaction with man is described including external exposures from γ-emitting plumes of activity and the estimation of depth doses, as well as the internal organ doses resulting from inhalation or ingestion of radioactivity. Finally, applications of the methods are described in reanalysing the 1957 Windscale accident and in the planning of procedures for reactor accident monitoring as well as in the implications of future reactor designs to assessments of accidental releases. A brief summary of the reactor siting criteria adopted in the U.K. and in the U.S.A. has also been given as a background against which to review the predictive techniques and results from the range of studies of accident considered. (author)

  5. Iodine filters in nuclear installations

    International Nuclear Information System (INIS)

    The present report discusses the significance for environmental exposure of the iodine released with the gaseous effluents of nuclear power stations and reprocessing plants in relation to releases of other airborne radionuclides. Iodine filtration processes are described. The release pathways and the composition of airborne fission product iodine mixtures and their bearing on environmental exposure are discussed on the basis of measured fission product iodine emissions. The sorbents which can be used for iodine filtration, their removal efficiencies and range of applications are dealt with in detail. The particular conditions governing iodine removal, which are determined by the various gaseous iodine species, are illustrated on the basis of experimentally determined retention profiles. Particular attention is given to the limitations imposed by temperature, humidity, radiation and filter poisoning. The types of filter normally used are described, their advantages and drawbacks discussed, the principles underlying their design are outlined and the sources of error indicated. The methods normally applied to test the efficiency of various iodine sorbents are described and assessed. Operating experience with iodine filters, gathered from surveillance periods of many years, is supplemented by a large number of test results and the findings of extensive experiments. Possible ways of prolonging the permissible service lives of iodine filters are discussed and information is given on protective measures. The various iodine removal processes applied in reprocessing plants are described and compared with reference to efficiency and cost. The latest developments in filter technology in reprocessing plants are briefly outlined

  6. Planning the nuclear contribution to the Brazilian power programme

    International Nuclear Information System (INIS)

    Thermo-electric power in Brazil accounts for less than 20% of the total generating capacity. Brazil's power is essentially generated hydraulically, which ensures the growing development. The electric energy consumption keeps growing, with an annual average rate of 13% over the last five years. The present installed capacity is 20,000MW(e) and 185,000MW(e) are forecast for the year 2000. Most of the hydraulic resources are located in remote areas of the country very far from the consumption centres. In addition to the American-made nuclear power station under construction in Angra dos Reis with a power capacity of 626MW(e), the agreement signed in June 1975 between the Federal Republic of Germany and Brazil covers two more units, each of 1245MW(e) capacity, to be erected at the same site and planned to come into operation in 1982 and 1983. Several joint German-Brazilian companies will be established in the country for reactor and fuel manufacture. The Brazilian state holding nuclear company, Empresas Nucleares Brasileiras S A (Nuclebras), will participate in the formation of all joint companies with at least 51% of the capital investment. During the period of the agreement the Brazilian Government will encourage the development of technology and reduce the dependence on energy imports. Brazil's target is full independence in nuclear technology in about 15 years. (author)

  7. Diagnosis of the Brazilian Nuclear Regulatory body

    International Nuclear Information System (INIS)

    This work has the objective to present the diagnosis of the existing structure in the Brazilian Government to ensure the radioprotection and nuclear safety in the country, being compared the current situation with the conclusions presented in another studies, carried through in last 30 years, with special attention in the existence of the necessary available to support and independence of the national regulatory body for the development of the regulatory inspections activities in the radioprotection and nuclear safety. (author)

  8. Directions and deviations in the Brazilian nuclear policy

    International Nuclear Information System (INIS)

    The emergence of the Brazilian nuclear policy as a subject of interest to the Brazilian society, the conflicts characterizing its formulation and implementation between 1945 and 1958 and the political criteria for executing a Brazilian nuclear program are presented. (M.C.K.)

  9. HEPA filter containment systems for nuclear installations

    International Nuclear Information System (INIS)

    The Unipak filter containment system units have evolved over the last 20 - 30 years and now have many special features and facilities. Some developments have been required due to changes in filter design to allow higher air flows through each filter. Pressure drops across different systems at these increased flow rates are discussed. The filter containment system has been required for use in systems in which it must be able to withstand pressure or vacuum surges. Data indicating the ability of the system to withstand 15 kPa pressure or depression without permanent deformation is presented. Containment efficiency under these more stringent conditions is calculated from the pressure change. Isolating dampers can be fitted to the individual modules of the containment system. On installation at the required site units are tested to ensure system integrity prior to filter installation. The features of filter containment systems required for nuclear installations are summarised. (author)

  10. Statement of nuclear incidents at nuclear installations

    International Nuclear Information System (INIS)

    Three incidents were reported in April-June 1993. The first was on the British Nuclear Fuel plc (BNFL) site at Sellafield and concerned leakage of 0.5 TBq of alpha activity from plutonium contaminated waste stored in a steel drum. This was subsequently double contained and moved so it could be inspected regularly. No contamination of personnel occurred. The second concerned the leakage of thorium liquor from a pipe at the UKAEA's Thorium reprocessing plant at Dounreay. Two temporary repairs were made and no personnel were contaminated. The third was at the Sellafield site where a small quantity (5 mls) of plutonium containing liquor had leaked from a package and released alpha activity. The bags were temporary containment of engineering debris which may have had sharp edges. The bags had been piled up and one of the bags had torn. Recommendations were made following inquiries into each of the incidents to improve procedures and prevent similar incidents occurring. (UK)

  11. Drones and safety of nuclear installations

    International Nuclear Information System (INIS)

    Recent flyovers of French nuclear power plants by drones or UAVs (the owners of these drones could not be identified) has made the safety of these nuclear installations a matter of concern. These events also raised the question of balance between secret and information about these installations. The French Parliamentary Office for the Assessment of Scientific and Technological Choices (OPECST) organised two sets of hearings, a confidential one with people in charge of information related to national defence and security, and a public one opened to all stakeholders. This article briefly reports and discusses the results of these hearings. It appeared that these flyovers are not really a threat, are more a communication action than anything else. Suggestions have been made for the development of researches in the field of drone detection, and also for evolutions of French legislation on drones

  12. Safety culture in nuclear installations. Proceedings

    International Nuclear Information System (INIS)

    These proceedings of the International Topical Meeting on Safety Culture in Nuclear Installations held in Vienna, Austria from 24 to 28 April 1995 provide a wide forum of information exchange and discussions on the topic safety culture in nuclear power plants. Safety culture deals with human factors since it deals with attitudes, organization and management. It then means that it has a natural component in it which is linked to the national culture and education. There are about 95 contributions, some of them presented by title and abstract only. All of them are in the subject scope of INIS. (Botek)

  13. Site Evaluation for Nuclear Installations. Safety Requirements

    International Nuclear Information System (INIS)

    This publication establishes requirements and provides criteria for ensuring safety in site evaluation for nuclear installations. The Safety Guides on site evaluation listed in the references section provide recommendations on how to meet the requirements established in this publication. A review of Safety Requirements publications was commenced in 2011 following the accident in the Fukushima Daiichi nuclear power plant in Japan. The review revealed no significant areas of weakness and resulted in just a small set of amendments to strengthen the requirements and facilitate their implementation, which are contained in the present publication

  14. Radiation protection in Spanish nuclear installations

    International Nuclear Information System (INIS)

    Radiation Protection was born as a discipline at the same time as the use of ionizing radiation, once the potential harmful effects on living beings of this new phenomenon was recognized. The evolution of the use of the nuclear energy at an industrial scale brought about the evolution of this discipline , initially in association with responsibilities relating to hygiene and safety at work and subsequently as an independent responsibility within organizations involved in nuclear electricity production. From the very beginning, in the year 1968, the Spanish nuclear plant organizations included specific resources for the radiation protection of both the plant workers and the general public living around the installations. Since that time, however, radiation protection organizations and technology have evolved considerably. The purpose of this article is to present a general overview of the current status of the radiation protection activities carried out at Spanish nuclear power plants. (Author)

  15. Advanced Measuring (Instrumentation Methods for Nuclear Installations: A Review

    Directory of Open Access Journals (Sweden)

    Wang Qiu-kuan

    2012-01-01

    Full Text Available The nuclear technology has been widely used in the world. The research of measurement in nuclear installations involves many aspects, such as nuclear reactors, nuclear fuel cycle, safety and security, nuclear accident, after action, analysis, and environmental applications. In last decades, many advanced measuring devices and techniques have been widely applied in nuclear installations. This paper mainly introduces the development of the measuring (instrumentation methods for nuclear installations and the applications of these instruments and methods.

  16. The nuclear importation and exportation - The Brazilian situation

    International Nuclear Information System (INIS)

    The panorama of Brazilian economy emphasizing the measurements adopted by Brazilian government referring to importation and exportation policy is presented. The Brazilian Nuclear Program knows the nuclear trade gives good economic perspective. In the context of importation and exportation policy the laws concerned to nuclear trade transactions, taxes, national organizations responsible by the external trade policy and their attributions are presented. (M.C.K.)

  17. The Brazilian nuclear power manpower development programme

    International Nuclear Information System (INIS)

    Since the early stages of decision making, manpower availability has been recognized to be a key factor for the implementation of Brazil's nuclear power programme. Though care has been given to securing an industrial base and financial resources, the consequences of a lack of sufficient qualified manpower could be critical for the success of the whole programme. The broad scope of the Brazilian nuclear power programme which, as a main concept, aimed at establishing in the country a complete fuel cycle industry together with the construction of nuclear power plants, added another burden to the already complex task of providing appropriate human resources when advanced technologies are introduced in a developing country. Thus, not only the work-force required for nuclear power plant operation but also that needed for plant design, component manufacture, fuel cycle plant design and operation, had to be made available in number and qualification in accordance with the standards of the nuclear industry. The feasibility of the Brazilian programme depended on a complete transfer of technology, essentially achieved through personnel training. Again, the process of manpower preparation for an efficient know-how transfer required careful planning, and the great difficulty in its implementation was the lack of reliable experience at the time. (author)

  18. Fuel element storage pond for nuclear installations

    International Nuclear Information System (INIS)

    In a fuel element storage pond for nuclear installations, with different water levels, radioactive particles are deposited at the points of contact of the water surface with the pond wall. So that this deposition will not occur, a metal apron is provided in the area of the points of contact of the water surface with the bond wall. The metal apron consists of individual sheets of metal which are suspended by claws in wall hooks. To clean the sheets, these are moved to a position below the water level. The sheets are suspended from the wall hooks during this process. (orig.)

  19. Cancer near potential sites of nuclear installations

    International Nuclear Information System (INIS)

    Mortality and census data for 400 districts of England and Wales were analysed with respect to existing sites of nuclear power stations and sites where the construction of such installations had been considered or had occurred at a later date (potential sites). Excess mortality due to leukaemia and Hodgkin's disease in young people who lived near potential sites was similar to that in young people who lived near existing sites. Areas near existing and potential sites might share unrecognised risk factors other than environmental radiation pollution. (author)

  20. Nuclear Plant Analyzer: Installation manual. Volume 1

    International Nuclear Information System (INIS)

    This report contains the installation instructions for the Nuclear Plant Analyzer (NPA) System. The NPA System consists of the Computer Visual System (CVS) program, the NPA libraries, the associated utility programs. The NPA was developed at the Idaho National Engineering Laboratory under the sponsorship of the US Nuclear Regulatory Commission to provide a highly flexible graphical user interface for displaying the results of these analysis codes. The NPA also provides the user with a convenient means of interactively controlling the host program through user-defined pop-up menus. The NPA was designed to serve primarily as an analysis tool. After a brief introduction to the Computer Visual System and the NPA, an analyst can quickly create a simple picture or set of pictures to aide in the study of a particular phenomenon. These pictures can range from simple collections of square boxes and straight lines to complex representations of emergency response information displays

  1. 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

  2. Testing Iodine Filters for Nuclear Installations

    International Nuclear Information System (INIS)

    The removal efficiency of iodine filters for nuclear installations has been tested The test method in use includes laboratory tests of the adsorber material (under MCA conditions for temperature, relative humidity, pressure, loading, stay time and bed depth) and in-place tests at the site of the installation. For removal of methyl iodide under high relative humidity Kl-impregnated charcoal is widely used. Most of the data for charcoal removal efficiency available today result from experiments with tracer amounts of CH3131I mixed with CH3127I. Considering MCA conditions, the validity of those data should be confirmed for specific activities on charcoal 103 - 106 times higher. Experimental data are given for realistic loadings with CH3131I up to 10 Ci/g charcoal under 100% relative humidity. For standard laboratory adsorber tests a method is discussed for humidification and control of gas streams up to 100% relative humidity at elevated temperatures. The apparatus used is described. Experimental data are given for the removal efficiency and the adsorption of water in charcoal samples from long-time tests under 100% relative humidity. The overall test period was up to 98 h, simulating the phase of elevated pressure and, therefore, high iodine release from the reactor containment. The reproducibility of long-time tests under extremely high relative humidity is shown and discussed. A description of the hardware for in-place tests is included and results are given. (author)

  3. The protection system to Brazilian Nuclear Program

    International Nuclear Information System (INIS)

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

  4. Renewable energy sources and nuclear installations

    International Nuclear Information System (INIS)

    This comprehensive work report for the Swiss Federal Office of Energy (SFOE) made by the Paul Scherrer Institute PSI takes a look at work done in connection with the updating of the office's Energy Perspectives. In particular, the topic of electricity is reviewed in the light of pending important decisions in the area of nuclear energy and the newer renewable sources of energy. The report makes an attempt to estimate the effect on Swiss power production that the new renewables and new nuclear installations could have in the next 30-40 years and to what costs this could be done and which obstacles would have to overcome. The renewable energy sources include small hydro, wind, photovoltaics, solar thermal power plants, biogas, geothermal energy, wave-power and solar chemistry. The methods used include literature study and contacts with internal PSI experts on the various areas involved. The most important system characteristics were noted and learning curves for the various technologies were taken into account. Ecological and social factors were also considered

  5. Safety of nuclear installations in the Slovak Republic

    International Nuclear Information System (INIS)

    This report describes all nuclear installations in the Slovak Republic. It informs the public about the safety of nuclear installations. The spent fuel activities and nuclear wastes storage matters are discussed separately ((NPP Bohunice V-1, NPP Bohunice V-2, NPP Mochovce, NPP Bohunice A-1, Radioactive wastes repository Mochovce, Interim spent fuel storage Bohunice)

  6. PREFACE: XXXVII Brazilian Meeting on Nuclear Physics

    Science.gov (United States)

    2015-07-01

    The XXXVII Brazilian Meeting on Nuclear Physics (or XXXVII RTFNB 2014) gave continuity to a long sequence of workshops held in Brazil, devoted to the study of the different aspects of nuclear physics. The meeting took place in the Maresias Beach Hotel, in the town of Maresias (state of São Paulo) from 8th to 12th September 2014. Offering gentle weather, a charming piece of green land of splendid natural beauty with beach and all amenities, the place had all the conditions for very pleasant and fruitful discussions. The meeting involved 162 participants and attracted undergraduate and graduate students, Brazilian and South American physicists and invited speakers from overseas (USA, Italy, Spain, France, England, Switzerland, Germany and South Corea). In the program we had plenary morning sessions with review talks on recent developments in theory, computational techniques, experimentation and applications of the many aspects of nuclear physics. In the parallel sessions we had a total of 58 seminars. This volume contains 60 written contributions based on these talks and on the poster sessions. Evening talks and poster sessions gave still more insight and enlarged the scope of the scientific program. The contributed papers, representing mainly the scientific activity of young physicists, were exhibited as posters and are included in the present volume. Additional information about the meeting can be found at our website: http://www.sbfisica.org.br/~rtfnb/xxxvii-en Support and sponsorship came from brazilian national agencies: Conselho Nacional de Desenvolvimento Científico e Tecnoógico (CNPq); Coordenação de Aperfeiçoamento de Pessoal de Nível Superior (CAPES); Fundação de Amparo á Pesquisa do Estado de São Paulo (FAPESP); Fundação de Amparo á Pesquisa do Estado do Rio de Janeiro (FAPERJ); Sociedade Brasileira de Física (SBF) and Instituto de Física da Universidade de São Paulo (IFUSP). We honored Professor Alejandro Szanto de Toledo, who completed

  7. The nuclear contribution to the solution of Brazilian energy problem

    International Nuclear Information System (INIS)

    This report presents the justifying of Brazilian Nuclear Programme. Due to the demand increasing of electric energy in Brazil, the government decided to an alternative source. Although the brazilian electric power program continue basically hydroelectric, the nuclear power plants began to be constructed. The strategy adopted, the prospection of uranium enrichment, the project and construction of nuclear power plants, the responsibilities of Nuclebras and Nuclen and several stages of this program are described. (C.M.)

  8. Argentine-Brazilian declaration on common nuclear policy

    International Nuclear Information System (INIS)

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

  9. Industrial development - consequences about the implantation of Brazilian Nuclear Program

    International Nuclear Information System (INIS)

    The strategy to promote the growing industry participation in the Brazilian Nuclear Program, the difficulties, the measurements adopted for overcoming and the results obtained in terms of industrial development, are presented. (M.C.K.)

  10. Management report 2006 CNEN - Brazilian Nuclear Energy Commission

    International Nuclear Information System (INIS)

    This document reports the results of the activity management of the Comissao Nacional de Energia Nuclear - CNEN - Brazil during the year of 2005, involving the Brazilian program of nuclear activities in the areas of nuclear safety, research and development, radiopharmaceutical production, institutional management, teaching, administration in general and miscellaneous

  11. Management report 2005 CNEN - Brazilian Nuclear Energy Commission

    International Nuclear Information System (INIS)

    This document reports the results of the activity management of the Comissao Nacional de Energia Nuclear - CNEN - Brazil during the year of 2005, involving the Brazilian program of nuclear activities in the areas of nuclear safety, research and development, radiopharmaceutical production, institutional management, teaching, administration in general and miscellaneous

  12. Management report 2007 CNEN - Brazilian Nuclear Energy Commission

    International Nuclear Information System (INIS)

    This document reports the general activity management of the Comissao Nacional de Energia Nuclear - CNEN - Brazil during the year of 2007, involving the CNEN role in the public policy execution, the Brazilian program of nuclear activities in the areas of nuclear safety, research and development, radiopharmaceutical production, teaching, administration in general and miscellaneous

  13. Brazilian nuclear legislation. Revision n.1/2002

    International Nuclear Information System (INIS)

    This work intends to facilitate the access to the Brazilian nuclear legislation and other legal instruments, foreseeing the use of nuclear energy and ionizing radiation in health, work and environment areas up to 2002. Legislation on the civil liability of nuclear damage, the law of licensing taxes, controlling and inspection are also included

  14. Management report 2004 CNEN - Brazilian Nuclear Energy Commission

    International Nuclear Information System (INIS)

    This document reports the results of the activity management of the Comissao Nacional de Energia Nuclear - CNEN - Brazil during the year of 2004, involving the Brazilian program of nuclear activities in the areas of nuclear safety, research and development, radiopharmaceutical production, institutional management, teaching, administration in general and miscellaneous

  15. Code on the safety of civilian nuclear fuel cycle installations

    International Nuclear Information System (INIS)

    The 'Code' was promulgated by the National Nuclear Safety Administration (NSSA) on June 17, 1993, which is applicable to civilian nuclear fuel fabrication, processing, storage and reprocessing installations, not including the safety requirements for the use of nuclear fuel in reactors. The contents of the 'Code' involve siting, design, construction, commissioning, operation and decommissioning of fuel cycle installation. The NNSA shall be responsible for the interpretation of this 'Code'

  16. Nuclear installations abroad the accident risks and their potential consequences

    International Nuclear Information System (INIS)

    This paper endeavors to assess the threat to Ireland from severe accidents at civil nuclear installations. Among the various types of nuclear installations worldwide, reactors and reprocessing plants are considered to be the most threatening and so the paper focuses on these. The threat is assumed to be a function of the risk of severe accidents at the above types of installations and the probability of unfavourable weather conditions carrying the radioactive releases to Ireland. Although nuclear installations designed in eastern Europe and Asia are less safe than others, the greatest threat to Ireland arises from nearby installations in the UK. The difficulty of measuring the probabilities and consequences of severe nuclear accidents at nuclear installations in general is explained. In the case of the UK installations, this difficulty is overcome to some degree by using values of 'tolerable' risk adopted by the national nuclear regulator to define the radiotoxic releases from nuclear accidents. These are used as input to atmospheric dispersion models in which unfavourable weather conditions for Ireland are assumed and radiation doses are calculated to members of the Irish public. No countermeasures, such as sheltering, are assumed. In the worst cast scenario no deaths would be expected in Ireland in the immediate aftermath of the accident however, an increase in cancers over a period of 25 years or so would be expected assuming present-day models for the effect of low level radiation are valid

  17. Nuclear knowledge portal to support licensing and control nuclear activities in the Brazilian Nuclear Energy Commission

    International Nuclear Information System (INIS)

    importance of keeping the intellectual capital in the organizations that is to work with the knowledge from the collaborators. In Brazil still have many authors that discusses this concept and we adopt for this paper the definition form Cavalcanti where is the concept 'intellectual capital' refers either to the capacity, ability or experience, as well as to the formal education that the collaborators members have and add to the Organization. The 'intellectual capital' is an intangible asset, which belongs to the individual himself, thus it might be utilized by the organizations in order to generate value. The development and preservation of this intellectual capital is made through the implementation of forums of discussion, workshops or knowledge portals where the organization's collaborators share their experiences. Nevertheless, to assimilate and to develop the 'intellectual capital' does not add value to the organization: It is necessary to keep it. And one way to do so is to create desirable and encouraging work environments, to promote a sharing management and to offer programs of profits sharing. The objective of this paper is to describe how Brazilian Nuclear Energy Commission - CNEN has been developing a nuclear knowledge portal, focused in the Radiation and Safety Nuclear area. The Brazilian Nuclear Energy Commission (CNEN) is a federal autarchy created in October 10 of 1956, as a superior agency of planning, guiding, supervision and inspection in nuclear area being also the body entitled to establish standards and regulations on radiological protection, to issue licenses (permissions) and to survey and control the nuclear activities in Brazil. CNEN also develops researches related to the use of nuclear techniques in benefit of the society. The Radiation and Safety Nuclear directorate of CNEN acts, mainly, in the licensing of nuclear and radioactive installations. The people who work at this area recognize the importance of management and sharing the accumulated

  18. Enhancing the safety culture in nuclear installations through efficient regulation

    International Nuclear Information System (INIS)

    The safety culture of a nuclear installation is greatly influenced by the external regulatory agencies with which it relates or interacts. These external regulatory agencies create demands for compliance with national industry or governmental regulatory standards and requirements imposed to provide for the public health and safety. While these national regulations can influence nuclear safety, no amount of regulation can ensure safety if those who operate the nuclear installations do not or cannot take it upon themselves to operate as safely as possible. It is not possible, nor is it desirable, for a regulatory agency to have the ultimate responsibility for the safety of nuclear installations. Good judgement and safe operating philosophy cannot be legislated. There must exist a safety culture in nuclear installations which recognizes the primary and ultimate responsibility for nuclear safety lies with those who manage and operate the installation. Thus, effective regulation must exist which promotes an environment that provides the nuclear installation the latitude it needs to apply innovative solutions to improve maintenance, operations, and training, and fosters a quest for excellence. (author)

  19. Plutonium recycle in PWR reactors (Brazilian Nuclear Program)

    International Nuclear Information System (INIS)

    An evaluation is made of the material requirements of the nuclear fuel cycle with plutonium recycle. It starts from the calculation of a reference reactor and allows the evaluation of demand under two alternatives of nuclear fuel cycle for Pressurized Water Reactors (PWR): without plutonium recycle; and with plutonium recycle. Calculations of the reference reactor have been carried out with the CELL-CORE codes. For plutonium recycle, the concept of uranium and plutonium homogeneous mixture has been adopted, using self-produced plutonium at equilibrium, in order to get minimum neutronic perturbations in the reactor core. The refueling model studied in the reference reactor was the 'out-in' scheme with a constant number of changed fuel elements (approximately 1/3 of the core). Variations in the material requirements were studied considering changes in the installed nuclear capacity of PWR reactors, the capacity factor of these reactors, and the introduction of fast breeders. Recycling plutonium produced inside the system can reach economies of about 5%U3O8 and 6% separative work units if recycle is assumed only after the 5th operation cycle of the thermal reactors. The cumulative amount of fissile plutonium obtained by the Brazilian Nuclear Program of PWR reactors by 1991 should be sufficient for a fast breeder with the same capacity as Angra 2. For the proposed fast breeder programs, the fissile plutonium produced by thermal reactors is sufficient to supply fast breeder initial necessities. Howewer, U3O8 and SWU economy with recycle is not significant when the proposed fast breeder program is considered. (Author)

  20. Genesis of the Brazilian nuclear power plants program

    International Nuclear Information System (INIS)

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

  1. Economical and strategical aspects of Brazilian-Germany nuclear agreement

    International Nuclear Information System (INIS)

    The strategical and economical aspects of Brazilian-Germany nuclear agreement are analyzed in three aspects: 1) The nuclear agreement in the context of the Brazilian economic - and social development process, considering the availability of energetic resouces of the country. Political implications. Considerations about creation and transfer of technology. 2) The economy aspects involved in the agreement. Comparison costs of electrical energy generated in a nuclear power plants and hydroelectric plant in Brazil. Impacts on the industrial development. 3) Strategical aspects. (E.G.)

  2. Safety of nuclear installations: Future direction

    International Nuclear Information System (INIS)

    The Workshop presentations were divided into sessions devoted to the following topics: Environmental impact of fossil fuel energy technologies (5 papers), Future needs for nuclear power (7 papers), Safety objectives (10 papers), Safety aspects of the next generation of current-type nuclear power plants (8 papers), Safety aspects of new designs and concepts for nuclear power plants (6 papers), Special safety issues: Safety aspects of new designs and concepts for nuclear power plants (5 papers), Safety aspects of new designs and processes for the nuclear fuel cycle (5 papers), Closing panel (3 papers), 12 poster presentations and a Summary of the Workshop. A separate abstract was prepared for each of these papers. Refs, figs and tabs

  3. Nuclear installations in Belarus: Implications of political and technical issues

    International Nuclear Information System (INIS)

    The report deals with some aspects of past and present supervisory activities at nuclear installations in Belarus. It briefly describes an existing supervisory system for nuclear installations in the Republic of Belarus, its legislative basis and functions of the supervisory body. Consideration is given to further development and improvement of the supervision in such fields as revision and elaboration of normative documents on nuclear safety, training of inspectors, co-operation with other governmental bodies while examining the nuclear option in the Republic of Belarus. (author)

  4. Contribution to Brazilian laws in nuclear energy sector

    International Nuclear Information System (INIS)

    This work, in a detailed analysis of Brazilian nuclear laws will show connection net and interconnections where it is inserted, by comparing national laws to those international ones, supported in International Atomic Energy Agency (IAEA), proposing to it recommendations, norms and regulations, related to the pacific use of nuclear energy among member countries. (author)

  5. The Brazilian participation in the nuclear power plant construction

    International Nuclear Information System (INIS)

    A brief review about the origin of the brazilian nuclear power program and the strategy adopted for its implementation in Brazil is presented. The creation of the Nuclebras Engineering S/A, the Germany technology transfer and the personell job-training in Brasil are discussed. Some management models used for nuclear power plant construction in the world are still presented. (E.G.)

  6. The nuclear energy in the context of Brazilian law

    International Nuclear Information System (INIS)

    The present work has as its objective the study of nuclear activity within the context of Brazilian Law. It focuses on the organizational structure in which, as part of the Directives of the National Nuclear Energy Policy, this activity is being developed through specific legal norms. (Author)

  7. General fire protection guidelines for Egyptian nuclear installations

    International Nuclear Information System (INIS)

    The purpose of this paper is to establish the regulatory requirements that will provide and ensure fire protection of Egyptian nuclear installations. Two or more classes of occupancy are considered to occur in the same building or structure. Fire protection measures and systems were reviewed for four of the Egyptian nuclear installations. These are Egypt's first research reactor (ET-RR-1) building and systems, hot laboratories buildings and facilities, the building including the AECL type JS-6500 industrial cobalt-60 gamma irradiator ''Egypt's Mega Gamma I'' and Egypt's second research multi-purpose reactor (MPR). A brief review is given about fire incidents in Egypt, and descriptions of the only fire reported at one of the Egyptian nuclear installations over more than 35 years of operating these installations. The study outlines the various aspects of fire protection with a view to define the relevant highlights and scope of an Egyptian guidelines. (author)

  8. Performances of nuclear installations in the world

    International Nuclear Information System (INIS)

    During the last years the operators of nuclear power plants in the world, have realized numerous improvements. This success is imputable to several factors, especially an important data exchange. The Chernobyl accident, in 1986, provoked the creation of the World Association of Nuclear Operators (W.A.N.O.). It allowed to exchange information and to develop cooperation in order to go beyond cultural barriers, linguistics and policies. Then, operators in the world have brought important improvements in matter of safety, reliability. (N.C.)

  9. Nuclebras' installations for performance tests of nuclear power plants components

    International Nuclear Information System (INIS)

    The reasons for Nuclebras' Nuclear Technology Development Center to implement a laboratory for supporting Brazilian manufactures, giving to them the means for performing functional tests of industrial products, are presented. A brief description of facilities under construction: the components Test Loop and Facility for Testing N.P.P. components under Accident conditions, and other already in operation, as well as its objectives and main technical characteristics. Some test results had already obtained are also presented. (Author)

  10. NUCLEBRAS' installations for tests of nuclear power plants components

    International Nuclear Information System (INIS)

    The reasons for NUCLEBRAS' Nuclear Technology Development Center to implement a laboratory for supporting Brazilian manufacturers, giving to them the means for performing functional tests of industrial products, are presented. A brief description of the facilities under construction: the Components Test Loop and the Facility for Testing N.P.P. Components under Accident Conditions, and of other already in operation, is given, as well as its objectives and main technical characteristics. Some test results already obtained are also presented. (Author)

  11. Recycling of metals from nuclear installations

    International Nuclear Information System (INIS)

    A task group was established in 1992, by the OECD Nuclear Energy Agency's Co-operative Programme on Decommissioning, to study the recycling and reuse of material from nuclear facilities. The objective of the group was to compare recycling/reuse of material to the alternative approach of disposal as radioactive waste with subsequent replacement by newly produced material. Starting with a survey over material currently being released, the study went on to review the proposals put forward by various international organisations for activity levels at which material could be ''cleared'' from regulatory control. The task group also surveyed the status of the technologies necessary for recycling. The work of the task group was summarized in a recently published OECD Nuclear Energy Agency report. This paper gives an overview of some of the findings and conclusions of the task group. In addition, it makes some comparisons between the management of very low level radioactivity in the nuclear industry and the management of similar material in some other industries. (author)

  12. Annual report 1996 concerning the nuclear safety and radiological protection in the Swiss nuclear installations

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-05-01

    The report presents detailed information about the nuclear safety and radiological protection in the Swiss nuclear power plants, the central interim storage at Wuerenlingen, the Paul Scherrer Institute (PSI) and other nuclear installations in Switzerland. figs., tabs., refs.

  13. Annual report 1996 concerning the nuclear safety and radiological protection in the Swiss nuclear installations

    International Nuclear Information System (INIS)

    The report presents detailed information about the nuclear safety and radiological protection in the Swiss nuclear power plants, the central interim storage at Wuerenlingen, the Paul Scherrer Institute (PSI) and other nuclear installations in Switzerland. figs., tabs., refs

  14. Annual Report 1998 concerning the nuclear safety and radiological protection in the Swiss nuclear installations

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-05-01

    The report presents detailed information about the nuclear safety and radiological protection in the Swiss nuclear power plants, the central interim storage at Wuerenlingen, the Paul Scherrer Institute (PSI) and other nuclear installations in Switzerland.

  15. Annual Report 1999 concerning the nuclear safety and radiological protection in the Swiss nuclear installations

    International Nuclear Information System (INIS)

    The report presents detailed information about the nuclear safety and radiological protection in the Swiss nuclear power plants, the central interim storage at Wuerenlingen, the Paul Scherrer Institute (PSI) and other nuclear installations in Switzerland

  16. Annual Report 1998 concerning the nuclear safety and radiological protection in the Swiss nuclear installations

    International Nuclear Information System (INIS)

    The report presents detailed information about the nuclear safety and radiological protection in the Swiss nuclear power plants, the central interim storage at Wuerenlingen, the Paul Scherrer Institute (PSI) and other nuclear installations in Switzerland

  17. Annual Report 1999 concerning the nuclear safety and radiological protection in the Swiss nuclear installations

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-08-15

    The report presents detailed information about the nuclear safety and radiological protection in the Swiss nuclear power plants, the central interim storage at Wuerenlingen, the Paul Scherrer Institute (PSI) and other nuclear installations in Switzerland.

  18. Organization and development of the Brazilian nuclear program

    International Nuclear Information System (INIS)

    The paper presents the Brazilian Nuclear Energy Program: its development until the present stage, as well as the organizations and the distribution of responsibilities involved in its execution at the present time. The nuclear power policy is established at the Presidency of the Republic and is planned, executed and controlled through the Ministry of Mines and Energy. Directly subject to the Ministry is the Brazilian Nuclear Energy Commission (CNEN), which has regulatory, standardization, licensing, planning and surveillance functions. The nuclear fundamental research and manpower formation are also under CNEN responsibility. Also subject to the Ministry are two companies responsible for the execution of the Programme: the Centrais Eletricas Brasileiras S.A. - ELETROBRAS, which advises on the granting of permits for the construction and operation of nuclear power plants, and the Empresas Nucleares Brasileiras S.A. - NUCLEBRAS, which holds the monopoly of the nuclear fuel cycle in the country, designs and builds nuclear power plants and provides assistance to the electric utilities as well as promotes the participation of the Brazilian industry in the nuclear field. Besides describing the new distribution of regulatory functions given by law to the CNEN, this paper gives special emphasis to the large industrial complex which is in the process of being established with the setting-up of the many NUCLEBRAS subsidiaries in joint-venture with German firms in the nuclear field, as a consequence of the Industrial Cooperation between Brazil and the Federal Republic of Germany in the Field of the Peaceful Uses of Nuclear Energy signed between the two countries on June 27, 1975. The programs for these subsidiaries are presented and their participation in the Brazilian Nuclear Energy Programme is discussed. The technology transfer aspects of the industrial activities are also discussed, based on the Government's policy on the subject

  19. Law no. 9.765 of 17th December, 1998 on nuclear and radioactive material and installations licensing, control and fiscalization tax

    International Nuclear Information System (INIS)

    This Act was published on December 17, 2001 and set forth taxes on licensing, control and inspection of nuclear and radioactive materials and installations, and all activities related, to be enforced by the Brazilian National Nuclear Energy Commission - CNEN. This Act prescribes exemption for the research and development institutes components of the Brazilian nuclear technology development program, military organizations, public hospitals integrating the health unified system, public research institutes using nuclear techniques and philanthropic organizations as legally considered, using radioactive materials for this specific purpose

  20. Codetermination at plant level in nuclear installations

    International Nuclear Information System (INIS)

    Starting out from the protective purposes of the Atomic Energy Act, the author emphasizes the competence of the executive to concretize existing legal norms. Given in the form of an administrative act creating a legally binding obligation, governmental action has the effect of a provision of law within the meaning of section 87 BetrVG and thus excludes the right of codetermination of the works council. If there remains a margin for arrangements between employer and employees, the employer is given the final competence to decide, irrespective of the works council's right to obtain and discuss information. Official participation of the works council in the nuclear licensing procedure, as laid down in the draft version of a bill on nuclear power phase-out, cannot be accepted as it is inconsistent with the existing law concerning employees' representation and codetermination, and as it blurs the limits of responsibility of the state and the operator. (RST)

  1. The nuclear technology and the normalization in Brazil - The actuation of COBREN (Brazilian Committee of Nuclear Energy)

    International Nuclear Information System (INIS)

    The actuation fields and the organization of work groups of Brazilian Committee of Nuclear Energy (COBREN) are described. COBREN is the Brazilian Organization which co-ordinates implantation of technical norms in nuclear field aiming to avoid conflicts between interpretation of Brazilian norms and norms which have been imported together with nuclear reactor technology. (M.C.K.)

  2. The Management System for Nuclear Installations Safety Guide

    International Nuclear Information System (INIS)

    This Safety Guide is applicable throughout the lifetime of a nuclear installation, including any subsequent period of institutional control, until there is no significant residual radiation hazard. For a nuclear installation, the lifetime includes site evaluation, design, construction, commissioning, operation and decommissioning. These stages in the lifetime of a nuclear installation may overlap. This Safety Guide may be applied to nuclear installations in the following ways: (a)To support the development, implementation, assessment and improvement of the management system of those organizations responsible for research, site evaluation, design, construction, commissioning, operation and decommissioning of a nuclear installation; (b)As an aid in the assessment by the regulatory body of the adequacy of the management system of a nuclear installation; (c)To assist an organization in specifying to a supplier, via contractual documentation, any specific element that should be included within the supplier's management system for the supply of products. This Safety Guide follows the structure of the Safety Requirements publication on The Management System for Facilities and Activities, whereby: (a)Section 2 provides recommendations on implementing the management system, including recommendations relating to safety culture, grading and documentation. (b)Section 3 provides recommendations on the responsibilities of senior management for the development and implementation of an effective management system. (c)Section 4 provides recommendations on resource management, including guidance on human resources, infrastructure and the working environment. (d)Section 5 provides recommendations on how the processes of the installation can be specified and developed, including recommendations on some generic processes of the management system. (e)Section 6 provides recommendations on the measurement, assessment and improvement of the management system of a nuclear installation. (f

  3. The Management System for Nuclear Installations (Russian Edition)

    International Nuclear Information System (INIS)

    This Safety Guide is applicable throughout the lifetime of a nuclear installation, including any subsequent period of institutional control, until there is no significant residual radiation hazard. For a nuclear installation, the lifetime includes site evaluation, design, construction, commissioning, operation and decommissioning. These stages in the lifetime of a nuclear installation may overlap. This Safety Guide may be applied to nuclear installations in the following ways: (a)To support the development, implementation, assessment and improvement of the management system of those organizations responsible for research, site evaluation, design, construction, commissioning, operation and decommissioning of a nuclear installation; (b)As an aid in the assessment by the regulatory body of the adequacy of the management system of a nuclear installation; (c)To assist an organization in specifying to a supplier, via contractual documentation, any specific element that should be included within the supplier's management system for the supply of products. This Safety Guide follows the structure of the Safety Requirements publication on The Management System for Facilities and Activities, whereby: (a)Section 2 provides recommendations on implementing the management system, including recommendations relating to safety culture, grading and documentation. (b)Section 3 provides recommendations on the responsibilities of senior management for the development and implementation of an effective management system. (c)Section 4 provides recommendations on resource management, including guidance on human resources, infrastructure and the working environment. (d)Section 5 provides recommendations on how the processes of the installation can be specified and developed, including recommendations on some generic processes of the management system. (e)Section 6 provides recommendations on the measurement, assessment and improvement of the management system of a nuclear installation. (f

  4. The Brazilian Nuclear Energy Commission and the health

    International Nuclear Information System (INIS)

    The Program of Health Section / Brazilian Cnen, which was elaborated to promote the use of ionizing radiations (nuclear and x-ray techniques) in benefit of Brazilian health, with safety assurance of patients, personnels, population and environment, is presented. The Ministry of Health, industries, Medical and Physicist Associations, Universities and Research Centers are participants of this program. The activities involved in the program are: production of isotopes and radiopharmaceuticals; radiation detectors and nuclear instrumentation; radiation protection and dosimetry; education and training of human resources; applied research and new technologies. The guiding and actions that the section will adopt to attend the growing necessities of Brazilian society, considering technological powers, management, available substructure and associated difficulties are defined. (M.C.K.)

  5. Leukaemia near british nuclear installations. Leucemies autour des installations nucleaires anglaises

    Energy Technology Data Exchange (ETDEWEB)

    Hubert, D. (Electricite de France (EDF), 75 - Paris (FR))

    1991-01-01

    An excess of childhood leukaemia has been seen near some British nuclear installations, especially near the Sellafield reprocessing plant. The same result was found in a more general study including a large number of nuclear sites. Similar studies made in USA, Canada and France have been negative. Moreover, epidemiological studies made in England have discovered other childhood leukaemia clusters in areas far from nuclear facilities, and especially near potential sites of nuclear installations. Several explanations are suggested but no definite conclusion is yet possible. Doses from radioactive releases seem to be too low to account for the additional deaths from leukaemia by environmental contamination. A virus activation, which might be associated with population influx into rural isolated areas, has been considered. The hypothesis of genetic mutation induced by ionising radiation in the fathers of children with leukaemia has been made because a higher risk of leukaemia was observed for children of fathers employed at Sellafield. No firm conclusion is possible considering the small number of observed cases and the lack of excess leukaemias in the offspring of Hiroshima and Nagasaki survivors. The possibility of internal contamination, chemicals or even radon is discussed as other causes. Studies in progress might allow to find an answer to the problem of leukaemia in the vicinity of British nuclear installations.

  6. Nuclear steam supply system and method of installation

    International Nuclear Information System (INIS)

    This patent describes a method of providing a nuclear reactor power plant at a predetermined use site accessible by predetermined navigable waterways. The method is practiced with apparatus including a nuclear reactor system. The system has a nuclear steam-supply section. The method consists of: constructing a nuclear reactor system at a manufacturing site remote from the predetermined use site but accessible to the predetermined waterways for transportation from the manufacturing site to the predetermined use site, the nuclear reactor system including a barge with the nuclear steam supply section constructed integrally with the barge. Simultaneously with the construction of the nuclear reactor system, constructing facilities at the use site to be integrated with the nuclear reactor system to form the nuclear-reactor power plant; transporting the nuclear reactor system along the waterways to the predetermined use site; at the use site joining the removal parts of the altered nuclear reactor system to the remainder of the altered nuclear reactor system to complete the nuclear reactor system; and installing the nuclear reactor system at the predetermined use site and integrating the nuclear reactor system to interact with the facilities constructed at the predetermined use site to form the nuclear-reactor power plant

  7. Assessment of safety of the nuclear installations of the world

    International Nuclear Information System (INIS)

    Incidents and accidents periodically remind us that preventive measures at nuclear installations are not fully reliable. Although sound design is widely recognized to be prerequisite for safe operation, it is not sufficient. An active management that compensates for the weak aspects of the installations design by redundant operational provisions, is the key factor to ensure safe operation. Safety of nuclear installations cannot be assessed on an emotional basis. Since 1986, accurate safety assessment techniques based on an integrated approach to operational safety have been made available by the ASSET services and are applicable to any industrial process dealing with nuclear materials. The ASSET methodology enables to eliminate in advance the Root Causes of the future accidents by introducing practical safety culture principles in the current managerial practices

  8. Licensing Process for Nuclear Installations. Specific Safety Guide

    International Nuclear Information System (INIS)

    This Safety Guide describes how the licensing process should be applied at the various stages of the lifetime of a nuclear installation, with discussion of topics and required documents to be considered at each stage. Recommendations on the application by a regulatory body of a graded approach in the licensing process are also provided. It also describes the processes that should be undertaken to meet the regulatory and legal requirements in a Member State to authorize the establishment of a nuclear installation and/or initiation of its activities. While this Safety Guide focuses on safety at nuclear installations, it is noted that integration of safety and security aspects should be considered and evaluated by the regulatory body in the licensing process. Contents: 1. Introduction; 2. General recommendations for the licensing process; 3. Steps of the licensing process; Appendix I: Examples of documents to be submitted to the regulatory body.

  9. Methodology for radiological safety assessment in a Brazilian Norm/tenorm installation

    International Nuclear Information System (INIS)

    Handling, storage or any other operations involving materials containing elevated levels of natural radionuclides always causes some excess exposure to the worker and to the environment. C.N.E.N. is the regulatory authority to assess the magnitude of the potential environmental and occupational exposure. In the last year year the draft of the standard to establish safety and radiological protection requirements to ensure an adequate control level of the exposure of workers and environmental in the T.E.N.O.R.M. industries was published. The extent of exposure varies considerably in different operations, depending on the concentration of the radioactive material, chemical and physical processing, occupation times, dusting conditions etc... Exposure cannot, therefore, be assessed solely on basis of material activity concentrations. In order to determine the different ways by which the radionuclides can contaminate the environment, wastes and streams, a mass balance at the entire installation has been performed and main ways of workers exposition were characterized. During the last years the Brazilian Regulatory Body has been performing the characterization, monitoring and inspection of this kind of installation, and a methodology of work was implemented, including mass balance, radiological survey, area dust control, personal dust monitoring and internal contamination evaluation. This paper presents the methodology, including the description of a mass balance, typical results for the radiological survey, dust measurement (area and personal) and internal contamination in a typical N.O.R.M./T.E.N.O.R.M. installation. It is described, in detail, the dust monitoring related to excreta collection; the results for the radionuclide concentration in dust. The internal contamination evaluation will be reported in terms of radioactive contamination of the workers. (author)

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

    International Nuclear Information System (INIS)

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

  11. Importance of the licensing process on the safety culture in the Brazilian nuclear fuel cycle facilities

    International Nuclear Information System (INIS)

    The main objective of the Nuclear Fuel Cycle Facilities licensing processes is to ensure the safety of these installations in their entire life cycle (in the installation site selection, designing, construction, pre-operational tests, operational and decommissioning phases). The Brazilian licensing process requires from the operator, among others, before the operating license: (I) a Site Report and a Final Safety Analysis Report, ensuring that all safety related issues are adequately analyzed and understood; (II) a formal structured Management System focused on the installation safety; and (III) dissemination of safety related information to all involved operator employees and subcontractors. Therefore, these requirements reflect in an adequate operator actions and practices, ensuring a working environment with a high level of safety culture. (author)

  12. Statutory Instrument No. 121, The Nuclear Installations (Bahamas) Order 1972

    International Nuclear Information System (INIS)

    This Order extends to the Bahamas, with the exceptions, adaptations and modifications specified in the Schedule to the Order, certain provisions of the Nuclear Installations Act 1965, as amended. It is the 1965 Act which implements the provisions of the Paris Convention and the Brussels Supplementary Convention in the United Kingdom. The provisons so extended impose a duty on the nuclear operator to secure that no nuclear occurrence taking place within the territorial limits of the Bahamas causes nuclear injury or damage, and relate to the right to compensation for breach of that duty, the bringing and satisfaction of claims and other matters. (NEA)

  13. Statutory Instrument No. 1116, The Nuclear Installations (Gibraltar) Order 1970

    International Nuclear Information System (INIS)

    This Order extends to Gibraltar, with the exceptions, adaptations and modifications specified in the Schedule to the Order, certain provisions of the Nuclear Installations Act 1965, as amended. It is the 1965 Act which implements the provisions of the Paris Convention and the Brussels Supplementary Convention in the United Kingdom. The provisions so extended impose a duty on the nuclear operator to secure that no nuclear occurrence taking place within the territorial limits of Gibraltar causes nuclear injury or damage, and relate to the right to compensation for breach of that duty, the bringing and satisfaction of claims and other matters. (NEA)

  14. Statutory Instrument No. 127, The Nuclear Installations (Montserrat) Order 1972

    International Nuclear Information System (INIS)

    This Order extends to Monserrat, with the exceptions, adaptations and modifications specified in the Schedule to the Order, certain provisions of the Nuclear Installations Act 1965, as amended. It is the 1965 Act which implements the provisions of the Paris Convention and the Brussels Supplementary Convention in the United Kingdom. The provisions so extended impose a duty on the nuclear operator to secure that no nuclear occurrence taking place within the territorial limits of Monserrat causes nuclear injury or damage, and relate to the right to compensation for breach of that duty, the bringing and satisfaction of claims and other matters. (NEA)

  15. Complex organizations: the case of the Brazilian nuclear sector

    International Nuclear Information System (INIS)

    The resumption of the Brazilian Nuclear Program (BNP), in the proposed size and after 20 years of paralysis, requires profound changes in the current organizational modeling of the national nuclear industry. The effectiveness of any process of organizational change is limited to three factors. The theoretical bottleneck happens when you do not know enough about a phenomenon in order to effect the desired changes. The resource bottleneck occurs when knowledge may be available to change people's behavior but the funds necessary for implementation may be lacking. The organizational bottleneck emerges when there are knowledge and resources to solve a problem, but may not able to organize the resources in order to carry out the problem-solving effort. In the case of resumption of BNP seems clear that there is the knowledge of what is needed to make policy and the intention to allocate the necessary resources. But the question is the following: the current organizational model of the Brazilian nuclear sector is consistent with the goals laid down in the scenario of resumption of BNP? That is, is there organizational ability to leverage a program of the size proposed for the nuclear area? Find answers to these questions is crucial, because the organizational model of the Brazilian nuclear sector consists of elements involving a complex interorganizational system. Thus, this article is to examine the appropriateness of the current organizational modeling of the Brazilian nuclear sector to current demands of society. As a result, the article aims to propose recommendations for a remodeling of the nuclear sector, taking into account the current national and international scenarios of nuclear energy. (author)

  16. Complex organizations: the case of the Brazilian nuclear sector

    Energy Technology Data Exchange (ETDEWEB)

    Xavier, Roberto Salles [Comissao Nacional de Energia Nuclear (CNEN), Rio de Janeiro, RJ (Brazil). Coordenacao-Geral de Planejamento e Avaliacao], e-mail: xavier@cnen.gov.br

    2009-07-01

    The resumption of the Brazilian Nuclear Program (BNP), in the proposed size and after 20 years of paralysis, requires profound changes in the current organizational modeling of the national nuclear industry. The effectiveness of any process of organizational change is limited to three factors. The theoretical bottleneck happens when you do not know enough about a phenomenon in order to effect the desired changes. The resource bottleneck occurs when knowledge may be available to change people's behavior but the funds necessary for implementation may be lacking. The organizational bottleneck emerges when there are knowledge and resources to solve a problem, but may not able to organize the resources in order to carry out the problem-solving effort. In the case of resumption of BNP seems clear that there is the knowledge of what is needed to make policy and the intention to allocate the necessary resources. But the question is the following: the current organizational model of the Brazilian nuclear sector is consistent with the goals laid down in the scenario of resumption of BNP? That is, is there organizational ability to leverage a program of the size proposed for the nuclear area? Find answers to these questions is crucial, because the organizational model of the Brazilian nuclear sector consists of elements involving a complex interorganizational system. Thus, this article is to examine the appropriateness of the current organizational modeling of the Brazilian nuclear sector to current demands of society. As a result, the article aims to propose recommendations for a remodeling of the nuclear sector, taking into account the current national and international scenarios of nuclear energy. (author)

  17. Radiation protection in Swiss nuclear installations; Strahlenschutz in Schweizer Kernanlagen

    Energy Technology Data Exchange (ETDEWEB)

    Hammer, J.; Brunell, M. [Eidgenoessisches Nuklearsicherheitsinspektorat ENSI, Brugg (Switzerland)

    2015-07-01

    Well developed measures on operational radiation protection within Swiss nuclear installations will be presented. The focus lays on competent authority actions. Results of the last ten years, including events on radiation issues, will be discussed. Finally a view on challenges for radiation protection personnel with respect to a renewed Swiss radiation protection legislation based on recent ICRP recommendations will be given.

  18. Brazilian nuclear renaissance in a sustainable development scenario - 097

    International Nuclear Information System (INIS)

    Brazil generated 326 TWh of hydroelectric power in 2005, accounting for ∼81% of the electricity production for that year. The 2005 to 2030 projections for the Brazilian development indicate growths from 2,020 kWh to 4,380 kWh in the per capita electricity consumption and from US$4,300 to US$8,950 in the per capita GDP (in market exchange rate and 2005 US$). The consumption of electricity is to grow from 375 TWh in 2005 to 1,030 TWh in 2030. In simple view and without considerations of aspects related with energy efficiency, this growth means 1.8 times the generation capacity of the 20. century should be built along of 25 years of the 21. century. The Brazilian electricity generation will demand all primary sources to meet the foreseen growth of the electricity consumption. As economical, safe and clean primary energy source for electricity generation, the nuclear energy is one option capable of large-scale and short-term deployment in the Brazilian growth of the electricity consumption. The contribution of nuclear generation in the electricity consumption should evolve from the current 2.6% for amounts over 5% in 2030. The perspective of the Brazilian nuclear sector is evolving to be resumed and present an opportunity for pooling and rationalizing the available skills - technical, cultural and human. The role of business opportunities and the future demands in the value chain of nuclear activities are summarized in this document. Institutions of R and D and Brazilian universities play an important role for the formation of new demanded knowledge and human resources. (authors)

  19. Decommissioning programs and strategies of basic nuclear installations at COGEMA

    International Nuclear Information System (INIS)

    In France, a lot of decommissioning projects were initiated over the last past decades permitting the French nuclear industry to acquire a great experience and knowledge in the field of dismantling. It started in the 1970's when the French Atomic Energy Agency (CEA) began to dismantle research and pilot reactors, laboratories and pilot facilities such as AT1, a pilot reprocessing plant for fast breeder spent fuels located in La Hague. The COGEMA group which is world-leader in the nuclear fuel cycle from uranium prospecting to spent fuel reprocessing and recycling (including refining, conversion, enrichment of natural uranium, manufacturing of nuclear fuels and waste conditioning), has already been involved in several nuclear clean-up and decommissioning programs. This presentation is illustrating the main decommissioning programs of COGEMA Basic Nuclear Installations within the nuclear fuel cycle, the associated initial feed back and chosen strategies

  20. 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)

  1. Financing of nuclear trade. The brazilian experience

    International Nuclear Information System (INIS)

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

  2. Fire protection and fire fighting in nuclear installations

    International Nuclear Information System (INIS)

    Fires are a threat to all technical installations. While fire protection has long been a well established conventional discipline, its application to nuclear facilities requires special considerations. Nevertheless, for a long time fire engineering has been somewhat neglected in the design and operation of nuclear installations. In the nuclear industry, the Browns Ferry fire in 1975 brought about an essential change in the attention paid to fire problems. Designers and plant operators, as well as insurance companies and regulators, increased their efforts to develop concepts and methods for reducing fire risks, not only to protect the capital investment in nuclear plants but also to consider the potential secondary effects which could lead to nuclear accidents. Although the number of fires in nuclear installations is still relatively large, their overall importance to the safety of nuclear power plants was not considered to be very high. Only more recently have probabilistic analyses changed this picture. The results may well have to be taken into account more carefully. Various aspects of fire fighting and fire protection were discussed during the Symposium, the first of its kind to be organized by the IAEA. It was convened in co-operation with several organizations working in the nuclear or fire protection fields. The intention was to gather experts from nuclear engineering areas and the conventional fire protection field at one meeting with a view to enhancing the exchange of information and experience and to presenting current knowledge on the various disciplines involved. The presentations at the meeting were subdivided into eight sessions: standards and licensing (6 papers); national fire safety practices (7 papers); fire safety by design (11 papers); fire fighting (2 papers); computer fire modeling (7 papers); fire safety in fuel center facilities (7 papers); fire testing of materials (3 papers); fire risk assessment (5 papers). A separate abstract was

  3. Assessment and statistics of Brazilian hydroelectric power plants: Dam areas versus installed and firm power

    International Nuclear Information System (INIS)

    The Brazilian relief, predominantly composed by small mountains and plateaus, contributed to formation of rivers with high amount of falls. With exception to North-eastern Brazil, the climate of this country are rainy, which contributes to maintain water flows high. These elements are essential to a high hydroelectric potential, contributing to the choice of hydroelectric power plants as the main technology of electricity generation in Brazil. Though this is a renewable source, whose utilized resource is free, dams must to be established which generates a high environmental and social impact. The objective of this study is to evaluate the impact caused by these dams through the use of environmental indexes. These indexes are ratio formed by installed power with dam area of a hydro power plant, and ratio formed by firm power with this dam area. In this study, the greatest media values were found in South, Southeast, and Northeast regions respectively, and the smallest media values were found in North and Mid-West regions, respectively. The greatest encountered media indexes were also found in dams established in the 1950s. In the last six decades, the smallest indexes were registered by dams established in the 1980s. These indexes could be utilized as important instruments for environmental impact assessments, and could enable a dam to be established that depletes an ecosystem as less as possible. (author)

  4. Public information and licensing procedures for nuclear installations. European experience

    International Nuclear Information System (INIS)

    This paper reviews the licensing procedures for nuclear installations in various European countries and examines the form, content and methods selected for information and consultation of the public. The author stresses the importance of this stage in the procedure, both for the nuclear operator and the public authorities, given the population's concern about the environment. He concludes that, irrespective of its complexity, the nuclear field cannot remain the concern of a few initiates competent to take decisions and that, consequently, this implies creation of new information systems to meet the public's desire to participate more directly in the process. (NEA)

  5. Safeguards Strategy in Physical Protection System for Nuclear Installation

    International Nuclear Information System (INIS)

    Safeguards strategy is directed at efforts of eliminating theft of nuclear materials and sabotage of nuclear installation. For achieving the above objective, it is necessary to set up safeguards strategy in physical protection of nuclear materials and installation. The safeguards strategy starts from anticipated security condition, list of thefts, planning referred to as safeguards planning. Safeguards planning are implemented in safeguards implementation, followed up then by evaluation. Results of evaluation are equipped with results of safeguards survey already developed. Safeguards' planning is made from these results and serve as guidelines for next safeguards implementation and is repeated to form a safeguard cycle. One safeguard cycle is made on a periodical basis, at least annually. (author)

  6. Conflict management in the planning of nuclear installations

    International Nuclear Information System (INIS)

    Subsequent to the decision of the Bavarian Higher Administrative Court, which after judicial review declared the development plan for the Wackersdorf site and the reprocessing facility there to be void, the author analyses the situation with regard to the tasks to be accomplished by an installation-specific planning management for coping with arising conflicts - and nuclear hazards in particular -, and for coming to a reconciliation of interests. The author agrees with the decision of the Lueneburg Higher Administrative Court which stated that, in view of the subsequent licensing procedure provided by the law, the development plans need not specify any regulations concerning the specific nuclear hazards or radiological consequences of installations of this type, so that development plans within the meaning of sec. 1, sub-sec. (3) BauGB do not necessarily have to consider nuclear risks or dose limits. (orig./HP)

  7. Remote installation of risers on underground nuclear waste storage tanks

    International Nuclear Information System (INIS)

    The West Valley Demonstration Project was established to solidify 2120 m3 (560,000) gallons of high-level nuclear waste generated during six years of commercial nuclear fuel reprocessing. This liquid will be processed to remove radioactive elements which, with the remaining sludge, will be combined with glass formers and be converted into borosilicate glass. Risers were installed on the high-level tank for installation of pumps which will be used to remove the liquid and sludge. The extensive use of remote technology was required to install the risers and to minimize operator exposure to high levels of radiation and contamination. The riser installation required remotely: drilling through two feet of concrete shielding; installing pump access pipes which are welded to the tank top; and cutting holes in tanks located 3658 mm (12) feet below ground. These operations were successfully completed 13 times without exposing personnel to high-level radiation or contamination. Specially designed remote equipment was developed for each step of this operation. Extensive operator training in the use of this equipment was performed on a tank with low radiation prior to work on the high-level tank. This paper discusses the application of remote technology that assured a quality job was safely accomplished. 3 refs., 18 figs., 2 tabs

  8. Financing of Liabilities Beyond the Service Life of Nuclear Installations

    Directory of Open Access Journals (Sweden)

    L. Havlíček

    2006-01-01

    Full Text Available Operation of a nuclear installation is connected with the creation of long-term liabilities for spent fuel management and disposal, and also decommissioning of the installation (power plant, storages. This means that the operator will have to expend considerable amount of financial resources over a long period after the closure of installation. These financial resources will have to be created during operation of the installation. Related costs to be expended in future must be fully included in the price of electricity, in order to ensure fair competition among different operators. Financial resources for future coverage of liabilities must be continuously invested in order to compensate for inflation and to gain some real interest.Any failure by the operator to comply with its liabilities poses an economic and potentially an environmental hazard for operator’s country. Due attention must therefore be paid to assessing connected costs, defining liabilities and ensuring appropriate regulatory oversight. Appropriate measures must be well defined and firmly anchored in the legislation of countries operating nuclear installations. This paper reviews the basic principles that should ensure operator’s compliance their liabilities, and maps the current situation in the Czech Republic. 

  9. Installation for accident localization at a nuclear power plant

    International Nuclear Information System (INIS)

    The installation for accident localization at a nuclear power plant with multiloop structure of the first circuit is described. The installation represents a pressurized shell inside which the reactor with the first circuit equipment are located. The whole volume under the shell is divided into autonomous boxes for one or several circulation loops. In case of accident as capacity for condensate discharge not the whole volume under pressurized shell is used, but only one of the autonomous boxes. This circumstance decreases the accident effect zone and expenditures related to the liquidation of accident consequences

  10. Institutional support to the nuclear power based on transportable installations

    International Nuclear Information System (INIS)

    Existing nuclear power uses large-power nuclear plants (more than 1,000 MWe) and enriched uranium fuel (235U). Each plant is treated as an exclusive costly project. As a result, large NPPs are operated predominantly in highly developed big countries. In many countries, construction of large power units is not reasonable because of the economic conditions and national specifics. This calls for the use of small- and medium-power nuclear plants (SMPNP), especially transportable nuclear installations (TNI). TNI feature small power (up to 100 MWe); serial production, and transportability. Small- and medium-power nuclear plants could serve to produce electricity and heat; perform water desalination; provide temporary and emergency energy supply. The authors discuss some findings of the studies carried out on the various aspects of the TNI life, as well as the legal and institutional support to their development, construction and operation. The studies have been performed in the framework of the INPRO Action Plan

  11. Licensing of nuclear and radioactive installations in Peru

    International Nuclear Information System (INIS)

    In Peru, the Regulation for Ionizing Radiation Sources is applied, which establishes the norms and procedures to follow in the nuclear and radioactive installations of the country in order to assure their correct operation as concerns to the nuclear safety and radiological protection, allowing the emission of the respective licenses. As for the nuclear facilities, this authorization includes the Previous License, the Construction License and the Operation License (provisional and definitive) and for radioactive facilities and equipment generating ionizing radiations: the Construction License and the Operation License. The personnel also require a license that can be an operator license (as for nuclear reactors) or a supervisor license (for nuclear and radioactive facilities). In spite of the above mentioned regulation and its long enforcement period, less than 10% of radioactive facilities in this country are licensed, due to different problems which will be solved in the medium term. (Author)

  12. Experience with HEPA filters at United States nuclear installations

    International Nuclear Information System (INIS)

    Part 50 of Title 10 of the United States Code of Federal Regulations requires that a number of atmosphere cleanup systems be included in the design of commercial nuclear power plants to be licensed in the United States. These filtering systems are to contain high efficiency particulate air (HEPA) filters for removal of radioactive particulate matter generated during normal and accident conditions. Recommendations for the design, testing and maintenance of the filtering systems and HEPA filter components are contained in a number of United States Nuclear Regulatory Commission documents and industry standards. This paper will discuss this published guidance available to designers of filtering systems and the plant operators of U.S. commercial nuclear power plants. The paper will also present a survey of published reports of experience with HEPA filters, failures and possible causes for the failures, and other abnormal occurrences pertaining to HEPA filters installed in U.S. nuclear power installations. A discussion will be included of U.S. practices for qualification of HEPA filters before installation, and verification of continued performance capability at scheduled intervals during operation

  13. Contribution to the Brazilian legislation in nuclear energy field

    International Nuclear Information System (INIS)

    Nuclear technology: to keep its domain is actually considered a differential for a country in relation to other ones, being able to represent an international threat to be contained or an aspect on technological and political valorization for those ones with recognized international credibility. Face to a raising use of new technologies in the field and the requirement asking for regulation in accordance with international safety standards, in order to assure its employment, the objective of this study was to demonstrate whether occupational and environmental radioprotection performed in our country is within radiological and nuclear safety international standards, and so it was updated and revised the Brazilian law in nuclear energy area, by comparing it with European Union, contextualized strong and weak points from national law, indicating criticisms and suggestions, in order that modifications will be able to be accomplished, aiming to its adequacy to international standards. The considered hypothesis showed that are required changes in the regulation structure in Brazilian nuclear area, aiming to the creation of a regulator agency of nuclear activities, with the purpose of assuring that the state of art and of technology, in terms of nuclear safety, to be the basis of the exercise related to their normative, control and safety assessment activities, on environment preservation, public and workers health, face to nuclear energy applications. (author)

  14. Brazilian nuclear politics in the context of contemporary international relations

    International Nuclear Information System (INIS)

    The present dissertation analyses the retaking of the debate over Brazilian nuclear Program's recovery by Luis Inacio Lula da Silva government, based on the defense of the utilization of an already acquired technology of its own to enrich uranium. In spite of the intrinsic duality on this subject and having in mind the pacific ends concerning the utilization of such technology by Brazil, the hypothesis sustained in this work is that the Program's defense is considered a strategy of sovereign international insertion with relative autonomy and an instrument of national valorization against other powers. In order to verify the hypothesis outlined above, we will analyse the actual government, comparing it to, two other moments in Brazilian History in which the nuclear issue also acquired preponderance on the national agenda, namely, Geisel and Sarney governments. Although these three moments differ in relation to their internal political regime, our goal is to identify their similarities. (author)

  15. Technicians for the Brazilian nuclear power programme

    International Nuclear Information System (INIS)

    The technician has a responsible role to fulfil in nuclear industry, acting as a bridge between the engineer and the skilled worker. Technicians must have sufficient theoretical knowledge to communicate with engineers, and a thorough understanding of technological practice; the nuclear industry demands both theory and practice of a high standard. In Brazil the essential role of the technician in industry is in general recognized. However, the lack of a nationally recognized Nuclear Technician and Nuclear Technologist qualification, as well as a desire of the best technicians to quality as engineers and, in some areas, inadequate salaries has resulted in a shortage of well-trained technicians. A first step to ensure availability of these technicians is to improve their career prospects and status through definition of appropriate career standards and salaries. Practical training by the industry can only be given in factories, plants and construction sites where nuclear work is done. It is proposed to extend apprentice training centres at three sites, to give the most promising students after two years of apprentice training two further years of instruction and practice to qualify as Nuclear Technicians. The training centres are chosen to cover the three sectors of nuclear industry where special training of technicians is important: manufacture and construction; operation and maintenance; and testing and analysis for process control and safety. (author)

  16. Some basic considerations about the brazilian nuclear program

    International Nuclear Information System (INIS)

    In order to assure the continued utilization of fission energy development of fast breeder reactors is a necessity. Binary fueled LMFBRs are proposed as the best type for future Brazilian nuclear systems. The inherent safety characteristics are superior to current fast breeder reactors and an efficient utilization of thorium can be realized. A possible strategy for the development of the reactor and related technologies are discussed. (Author)

  17. Safety aspects of spent nuclear fuel interim storage installations

    International Nuclear Information System (INIS)

    Nowadays safety and security of spent nuclear fuel (SNF) interim storage installations are very important, due to a great concentration of fission products, actinides and activation products. In this kind of storage it is necessary to consider the physical security. Nuclear installations have become more vulnerable. New types of accidents must be considered in the design of these installations, which in the early days were not considered like: fissile material stolen, terrorists' acts and war conflicts, and traditional accidents concerning the transport of the spent fuel from the reactor to the storage location, earthquakes occurrence, airplanes crash, etc. Studies related to airplane falling had showed that a collision of big commercials airplanes at velocity of 800 km/h against SNF storage and specially designed concrete casks, do not result in serious structural injury to the casks, and not even radionuclides liberation to the environment. However, it was demonstrated that attacks with modern military ammunitions, against metallic casks, are calamitous. The casks could not support a direct impact of this ammo and the released radioactive materials can expose the workers and public as well the local environment to harmful radiation. This paper deals about the main basic aspects of a dry SNF storage installation, that must be physically well protected, getting barriers that difficult the access of unauthorized persons or vehicles, as well as, must structurally resist to incidents or accidents caused by unauthorized intrusion. (author)

  18. Nuclear exportation and importation - the Brazilian situation

    International Nuclear Information System (INIS)

    The author proposes to set up a working group which should be responsible for the compilation of laws, procedures, and national policies for the nuclear importation and exportation in the supplying and receiving countries. Shared international views would simplify the flow of imports and exports between the countries. The author describes the different phases of exportation and importation of nuclear material are processed in her country, Brazil. (CW)

  19. Seismic qualification of existing nuclear installations in India - a proposal

    International Nuclear Information System (INIS)

    In India, the work toward seismic qualification of existing nuclear facilities has been started. Preliminary work is being undertaken with respect to identifying the facilities which would be taken up for seismic qualification, approach and methodology for re-evaluation for seismic safety, acceptance criteria, etc. Work has also been started for framing up the criteria and methodology of the seismic qualification of these facilities. Present paper contains the proposal in this respect. This proposal is on similar lines of the present practice of seismic qualification of NPP, as summarized in the Appendix, but has been modified to suit the special requirements of Indian nuclear installations. (author)

  20. State supervision of nuclear power technology installation safety

    International Nuclear Information System (INIS)

    State technical supervision of labour safety and technical installations and surveillance of working conditions follows up on the work of the former Institute of Technical Supervision. The work and problems tackled by the two institutions are described in the construction and commissioning of the A-1 nuclear power plant in Bohunice, in designing and construction of the V-1 Bohunice plant and in designing, assembly and commissioning of the active sodium loop at the Power Research Institute at Bohunice. The State Technical Supervision is represented on the Council for Nuclear Safety of the Czechoslovak Atomic Energy Commission. (J.B.)

  1. Nuclear Installations (Jersey) Order 1980 SI No. 1527

    International Nuclear Information System (INIS)

    This Order extends to the Bailiwick of Jersey with the exceptions, adaptations and modifications specified in the Schedule to the Order, certain provisions of the Nuclear Installations Act 1965, as amended. It is the 1965 Act which implements the provisions of the Paris Convention and the Brussels Supplementary Convention in the United Kingdom. These provisions relate to the duty in respect of the carriage of nuclear matter, to the right to compensation for breach of that duty and to the bringing and satisfaction of claims and other matters. This Order came into operation on 3 November 1980. (NEA)

  2. The review of safety at Magnox nuclear installations

    International Nuclear Information System (INIS)

    A number of papers reviewing safety at Magnox Nuclear Power Stations in the United Kingdom are presented. The topics covered include: a description of the scope and requirements of long term reviews carried out by the Nuclear Installations Inspectorate; the safety of pressure circuits and graphite cores; the integrity of concrete structures in the long term where reinforcement corrosion may be a problem and of biological shielding under overpressurization due to a severe reactor accident; and the safety assessment of cranes. The application of modern safety standards and methods to Magnox reactors in general is discussed and the safety review of the reactors at Chapelcross, Calder Hall and Oldbury specifically described. (UK)

  3. Gas turbine installations in nuclear power plants in Sweden

    International Nuclear Information System (INIS)

    At each of the four nuclear power stations in Sweden (Ringhals, Forsmark, Oskarshamn, Barsebaeck) gas turbine generating sets have been installed. These units are normally used for peak load operation dictated of grid and System requirements but they are also connected to supply the electrical auxiliary load of the nuclear plant as reserve power sources. The gas turbines have automatic start capability under certain abnormal conditions (such as reactor trips, low frequency grid etc) but they can also be started manually from several different locations. Starting time is approximately 2- 3 minutes from start up to full load. (author)

  4. The situation of the personnel working in nuclear installations

    International Nuclear Information System (INIS)

    It is shown in this paper that the staff committee practically has no say in deliberations and decisions concerning the physical protection system of a nuclear installation. The author explains the strict and detailed system of regulations and other provisions set by the law, which also govern the working conditions in nuclear facilities. The criteria applied in the selection of personnel are discussed, such as educational, physical and psychological qualifications; other items include personnel organisation, security screening of staff, health and safety at work, technical procedures and processes and the working environment, rights of staff to participate in the management. (HSCH)

  5. Standardization of Nuclear Instrumentation Applied in the NPP and in other nuclear installations

    International Nuclear Information System (INIS)

    Nuclear power plant (NPP) and other nuclear installations have been recognized as applications needing very sophisticated technologies. One of technologies used in this all nuclear facilities is nuclear instrumentation. In order that NPP and other nuclear installations be operated safely, nuclear instrumentation requires standardization from design to its operation. Internationally, standardizations of nuclear instrumentation have been issued by IEC (International Electrotechnical Commission). Formulation of standard in nuclear instrumentation in IEC is carried out by Technical Committee (TC) 45. This paper describes briefly the standardization of nuclear instrumentation applied in Indonesia as Indonesian National Standard (SNI, Standard National Indonesia), standardization of nuclear instrumentation developed by TC 45, SC 45A, and SC 45B, as well as the possibility to adopt and apply those IEC standard in Indonesia

  6. Nuclear liability amounts on the rise for nuclear installations

    International Nuclear Information System (INIS)

    The NEA Table on Nuclear Operator Liability Amounts and Financial Security Limits (NEA 'Liability Table'), which covers 71 countries, aims to provide one of the most comprehensive listings of nuclear liability amounts and financial security limits. The current and revised Paris and Brussels Supplementary Conventions ('Paris-Brussels regime'), the original and revised Vienna Conventions ('Vienna regime') and the Convention on Supplementary Compensation for Nuclear Damage, newly entered into force in April 2015, provide for the minimum amounts to be transposed in the national legislation of states parties to the conventions, and have served as guidelines for non-convention states. This article examine in more detail increases in the liability amounts provided for under these conventions, as well as examples of non-convention states (China, India and Korea)

  7. Nuclear medicine installations supervisors interactive course (CD-ROM)

    International Nuclear Information System (INIS)

    The professionals who work as Nuclear Medicine Installations Supervisors need a suitable training. This training must be based on the guidelines of the C.S.N. (the Spanish Agency for Nuclear Safety). The traditional training courses must comply with a set of requirements, that not always is possible to get: They are given in a settled place. They are developed during a time, more or less lengthy. This time is pre-established. However, the persons willing to follow these courses have some difficulties with the place and the time. Many of them do not live near the places where the courses are given, in general in big cities, while there are Nuclear Medicine Installations scattered through all Spain. Moreover in some occasions they have not available time to attend the courses. Many times, faced with so many obstacles, the option is not to do the suitable training course. In order to solve this kind of problems we offer an Interactive Training Course (supported by CD-ROM). The course contents are based on Spanish Regulations and on the Safety Guide, established by C.S.N., for approval Radioactive Installations Supervisors Training Courses. This guide includes General Topics for Radioactive Installations and Specific Subjects for Nuclear Medicine. (General topics) Basic knowledge on the fundamental concepts on the action and nature of Ionizing Radiations, their risks and preventions. The ionizing radiations. Biological effects of ionizing radiations. Radiological protection. Legislation on radioactive installations. (Specific Subjects) Knowledge on the radiological risks associated to the proper techniques in the specific field of application. In our case the specific field is Nuclear Medicine Installations, where the radioactive sources are used for diagnostic or for therapy. Specific legal and administrative aspects. Non-encapsulated radioactive sources. Associated radiological risks to the use of non-encapsulated sources. Installations design. Operative procedures

  8. Effective corrective actions to enhance operational safety of nuclear installations

    International Nuclear Information System (INIS)

    The safe operation of nuclear power plants around the world and the prevention of incidents in these installations remain key concerns for the nuclear community. In this connection the feedback of operating experience plays a major role: every nuclear plant operator needs to have a system in place to identify and feed back the lessons learned from operating experience and to implement effective corrective actions to prevent safety events from reoccurring. An effective operating experience programme also includes a proactive approach that is aimed at preventing the first-time occurrence of safety events. In April 2003, the IAEA issued the PROSPER guidelines for nuclear installations to strengthen and enhance their own operating experience process and for self-assessment on the effectiveness of the feedback process. Subsequently, in the course of the Operational Safety Review Teams missions conducted by the IAEA that focused on the operational safety practices of nuclear power plants, the IAEA enhanced the review of the operating experience in nuclear power plants by implementing a new module that is derived from these guidelines. In order to highlight the effective implementation of the operating experience programme and to provide practical assistance in this area, the IAEA organized workshops and conferences to discuss recent trends in operating experience. The IAEA also performed assistance and review missions at plants and corporate organizations. The IAEA is further developing advice and assistance on operating experience feedback programmes and is reporting on good practices. The present publication is the outcome of two years of coordinated effort involving the participation of experts of nuclear organizations in several Member States. It provides information and good practices for successfully establishing an effective corrective actions programme. This publication forms part of a series that develops the principles set forth in these guidelines

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

    International Nuclear Information System (INIS)

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

  10. Problems concerning the installation of pipings for nuclear power generation

    International Nuclear Information System (INIS)

    The nuclear power stations in the world in operation at the end of 1975 were 173 plants, and those in planning or construction stage were 505 plants. The total power output amounted to 530 x 103 MW. Light water reactors occupy nearly 90% of commercial nuclear power stations. The pipings in a 1100 MW BWR nuclear power station exceeds 5000 tons, and the man-hours for the construction of the pipings are enormous. High degree of safety and reliability are required for these pipings, and it is the difference and the feature that the manufacture and installation of these pipings are carried out under the strict quality assurance system, as compared with other plants. The pipings in a nuclear power plant are diverse and complex, and laid in very restricted spaces. Therefore they interfere with each other, and construction schedule is disturbed. The problems in the planning of the pipings, the reliability of the pipings, the enormous amount of the pipings, the management of working procedures, the storage, piping works and the state of installation, the consideration about the design and layout, the pipings in a containment vessel and the models of machinery and equipments, and the tendency of design method for the future are explained. (Kako, I.)

  11. Management of procurement activities in a nuclear installation

    International Nuclear Information System (INIS)

    Discussions held within the framework of IAEA regional technical co-operation projects implemented in the Latin America, Asia-Pacific and eastern Europe regions revealed an area of frequent difficulties related to the proper control, by the management of nuclear utilities, of the effective fulfilment of contractual quality and safety requirements. Evaluation of the results of a number of OSART missions has also pointed to a need for improving the control that some utilities exercise on their suppliers. The IAEA was thus prompted to initiate the development of a technical document providing guidance on these subjects. In October 1995, a consultants meeting was convened to determine the target users of the technical document and to develop the scope, contents, structure and the reference material. A first draft was then prepared. An Advisory Group meeting consisting of experts from 17 Members States was held in Vienna in May 1996 to review and complete the draft. The technical document is intended to provide practical guidance on controlling procurement, with supporting information for senior management, line managers and line supervisors in a nuclear installation. Although the guidance is structured to address the needs during the operating stage of a nuclear power plant, much of the material is also applicable to the construction and decommissioning stages and to other nuclear installations. 1 fig

  12. Statement of nuclear incidents at nuclear installations: first quarter 1993

    International Nuclear Information System (INIS)

    This press statement by the Health and Safety Executive covers nuclear incidents in the United Kingdom in the period 1st January to 31st March 1993. Of the six incidents reported, four occurred at the Windscale and Calder Works of British Nuclear Fuels (BNFL, Sellafield). Two of these were classified as level 2 on the International Nuclear Event Scale. They were a leakage of plutonium-bearing solvent liquor onto the plant floor which did not involve contamination of personnel nor release of airbourne radioactivity, and a contamination wound received by a Quality Assurance Inspector inspecting a weld on a plutonium nitrate transfer line. The other two Sellafield incidents involved short term increases in radioactive discharges from stacks; in both cases no on-site personnel were affected and the maximum potential dose to the general public was assessed at less than 0.02% of the annual permitted dose. During the transfer of stocks of protactinium 231 between two laboratories in the same building at AEA Technology Harwell, alpha contamination of the floor of one of the laboratories was detected and staff received minor skin doses well below defined dose limits; there was no release of radioactivity to the environment. At Dungeness B power station, an irradiated fuel stringer which had become immobilised in a fuelling machine was recovered without release of radioactive contamination. The investigation of each incident and the procedures adopted to avoid repetition are outlined. (UK)

  13. Assessment of safety culture in the Iranian nuclear installations

    International Nuclear Information System (INIS)

    The deficient safety culture (S.C) is the center of safety issues of nuclear industry. To benefit from the advantages of nuclear technology and considering the fact of potential hazards of accidents in nuclear installations it is essential to view safety as the highest priority. S.C is an amalgamation of values, standards, morals and norms of acceptable behavior. Organizations having effective S.C show constant commitment to safety as a top level priority. Furthermore, the personnel of a nuclear facility shall recognize the safety significance of their tasks. Many people even those who work in the field of safety do not have a correct understanding of what S.C looks like in practical sense. In this study, by conducting a survey according to IAEA-TECDOC-1329 in some nuclear facilities, the S.C within the Iranian nuclear facilities is assessed. The human and organizational factors in Tehran Research Reactor are evaluated using a questionnaire method with active participation of the reactor operators. The results sho w that the operators are pretty aware of the subject. Also it has been identified some areas of improvement. (authors)

  14. Establishment of the nuclear regulatory framework for the process of decommissioning of nuclear installations in Mexico

    International Nuclear Information System (INIS)

    Today has not managed any process of decommissioning of nuclear installations in the country; however because of the importance of the subject and the actions to be taken to long term, the Comision Nacional de Seguridad Nuclear y Salvaguardias (CNSNS) in Mexico, accordance with its objectives is developing a National Nuclear Regulatory Framework and defined requirements to ensure the implementation of appropriate safety standards when such activities are performed. In this regard, the national nuclear regulatory framework for nuclear installations and the particular case of nuclear power reactors is presented, as well as a proposed licensing process for the nuclear power plant of Laguna Verde based on international regulations and origin country regulations of the existing reactors in nuclear facilities in accordance with the license conditions of operation to allow to define and incorporate such regulation. (Author)

  15. Regulations on the safety regulation for civilian nuclear installations of the People's Republic of China

    International Nuclear Information System (INIS)

    The 'Regulations on the Safety Regulation for Cirilian Nuclear Installations of the People's Republic of China' were promulgated by the State Council on October 29, 1986. The Regulations are applicable to safety regulation of the following civilian nuclear installations: 1. Nuclear power plant; 2. Other reactors apart from that of nuclear power plant; 3. Installations for nuclear fuel production, processing, storage and reprocessing; 4. Installations for radioactive waste treatment and disposal; 5. Other nuclear installations requiring shrift regulation. The present Regulations are enacted to ensure safety for civilian nuclear installations in construction and operation to protect the site personnel, the public and the environment from possible adverse effects arising from nuclear installations and to facilitate the development of nuclear undertakings

  16. A package for environmental impact assessment of nuclear installations (NGLAR)

    International Nuclear Information System (INIS)

    The main contents, designing strategies and properties of the microcomputer-based software package NGLAR are described for environmental impact assessment of nuclear installations. The package consists of the following components: NGAS and NACC, the codes for routine and accidental airborne releases respectively; NLIQ, the code for both routine and accidental liquid releases; and NRED, environmental database system of nuclear installations. NGAS and NACC are used for evaluating atmosphere dispersion and doses to public of radioactive materials released from nuclear facilities, giving the concentrations around the facilities of radionuclides in air, on ground surface, and in varieties of animal foods and farm produces, and further estimating collective doses and doses to critical group around the facilities. NLIQ is suitable for liquid effluence released to non-tide rivers, and is modelled to calculate firstly the concentration of radionuclides concerned in the polluted rivers, and then to estimate the resulting doses to public. Under routine releases, the doses obtained from NGAS and NLIQ can be appropriately categorized and summed up together. NRED can be run independently, also used to provide some input data for above programs and save data permanently for them. Having both English and Chinese versions, the package, which was fabricated of multiple functions can be run on IBM 386 or higher and its compatible microcomputers. (3 figs., 1 tabs)

  17. Protection of nuclear installations and nuclear material against malevolent actions

    International Nuclear Information System (INIS)

    The paper presents the process used in France to cope with sabotage of nuclear material or facilities. Design basis threats are associated with the risk of aggression and the means used. Implementation of regulations uses a performance-based approach which gives the operators flexibility to choose the means and measures to be taken. The physical protection system is based upon the principle of 'defence in depth'. This concept is applied to the design and operation of the physical protection system. Sensitivity is defined by the level of radiological consequences resulting from malevolent action determined by using safety analyses to identify potential accident sequences. Vulnerability is assessed by estimating the resources required to destroy a system or function, and the paths which lead to sensitive zones or systems. Acceptable consequences are defined as levels of release which are equal to, or less than, the levels defined in the facility safety case. (author)

  18. Chapter 4. Assessment and inspection of safety at nuclear installations

    International Nuclear Information System (INIS)

    Supervisory activity of the Nuclear Regulatory Authority of the Slovak Republic (UJD) over the safety of nuclear installations in compliance with the 'Atomic Act' and other regulations includes also inspection and assessment activities of UJD. In 1999 the assessment activity were focused on newly constructed nuclear installations or their parts - Unit 2 of NPP Mochovce, National Repository of rad-waste in Mochovce, and the first phase of technology for treatment and conditioning of rad-waste in Jaslovske Bohunice. Inspection activity specified in the 'Atomic Act' is governed by internal guideline, an important part of which is an annual inspection plan that considers the routine inspections, special inspections, team inspections, and extraordinary inspections - there they are briefly described. Assessment as well as inspection activities in the NPP V-1 Bohunice, NPP V-2 Bohunice, NPP Mochovce, as well as NPP A-1 Bohunice (under decommissioning) are reviewed in detail. Assessment and inspection activities of UJD in the Interim spent fuel storage Bohunice, and in the nuclear facility 'Technology for treatment and conditioning of radioactive waste' Bohunice are described in detail, too. National radioactive waste repository Mochovce is determined for disposal low and intermediate radioactive waste. UJD issued a resolution on approval for commissioning of this nuclear facility in October 1999. VUJE bituminization facility was out of operation in 1999, The incinerator treated the burnable waste from NPP V-1 Bohunice. The technology of cementing sludge from NPP V-2 Bohunice was verified on cementing equipment. Assessment and inspection activities of UJD in 1999, which were completed by issuing UJD decisions are presented in the table form

  19. Practical decommissioning experience with nuclear installations in the European Community

    International Nuclear Information System (INIS)

    Initiated by the Commission of the European Communities (CEC), this seminar was jointly organized by Kernkraftwerke RWE Bayernwerk GmbH (KRB) and the CEC at Gundremmingen-Guenzburg (D), where the former KRB-A BWR is presently being dismantled. The meeting aimed at gathering a limited number of European experts for the presentation and discussion of operations, the results and conclusions on techniques and procedures presently applied in the dismantling of large-scale nuclear installations in the European Community. Besides the four pilot dismantling projects of the presently running third R and D programme (1989-93) of the European Community on decommissioning of nuclear installations (WAGR, BR-3 PWR, KRB-A BWR and AT-1 FBR fuel reprocessing), the organizers selected the presentation of topics on the following facilities which have a significant scale and/or representative features and are presently being dismantled: the Magnox reprocessing pilot plant at Sellafield, the HWGCR EL4 at Monts d'Arree, the operation of an on-site melting furnace for G2/G3 GCR dismantling waste at Marcoule, an EdF confinement conception of shut-down LWRs for deferred dismantling, and the technical aspects of the Greifswald WWER type NPPs decommissioning. This was completed by a presentation on the decommissioning of material testing reactors in the United Kingdom and by an overview on the conception and implementation of two EC databases on tools, costs and job doses. The seminar concluded with a guided visit of the KRB-A dismantling site. This meeting was attended by managers concerned by the decommissioning of nuclear installations within the European Community, either by practical dismantling work or by decision-making functions. Thereby, the organizers expect to have contributed to the achievement of decommissioning tasks under optimal conditions - with respect to safety and economics - by making available a complete and updated insight into on-going dismantling projects and by

  20. Practical decommissioning experience with nuclear installations in the European Community

    International Nuclear Information System (INIS)

    Initiated by the Commission of the European Communities (CEC), this seminar was jointly organized by the AEA, BNFL and the CEC at Windermere and the sites of Windscale/Sellafield, where the former Windscale advanced gas-cooled reactor and the Windscale piles are currently being dismantled. The meeting aimed at gathering a limited number of European experts for the presentation and discussion of operations, results and conclusions on techniques and procedures currently applied in the dismantling of large scale nuclear installations in the European Community

  1. Safety aspects of geological studies around nuclear installations sites

    International Nuclear Information System (INIS)

    The experience of geological studies of about forty french nuclear sites allows to set out the objectives, the phases and the geographic extensions of workings to be realized for confirming a site. The data to be collected for the safety analysis are specified; they concern the local and regional geology, the geotechnical characteristics and the essential elements for evaluating the hazards related to the soil liquefaction, the surface fracturing and in some cases the volcanic risks. It is necessary to follow up the geology during the installation construction and life. 8 refs. (F.M.)

  2. Actualization of the Brazilian nuclear regulations; Atualizacao das normas nucleares brasileiras

    Energy Technology Data Exchange (ETDEWEB)

    Wieland, Patricia; Soares, Abner Duarte; Nogueira, Tindyua de Moraes; Monteiro, Iara Arraes; Pitta, Maria Adelia Rocha; Bruno, Natanael Carvalho; Pereira, Enneite Souza; Pinto, Marvio dos S.; Lidington, Regina Marcia Rocha; Rocha, Marco Aurelio Toledo, E-mail: pwieland@cnen.gov.b, E-mail: asoares@cnen.gov.b, E-mail: tnogueira@cnen.gov.b, E-mail: iara@cnen.gov.b, E-mail: mpitta@cnen.gov.b, E-mail: nbruno@cnen.gov.b, E-mail: espereira@cnen.gov.b, E-mail: marvio@cnen.gov.b, E-mail: , E-mail: rmliding@cnen.gov.b, E-mail: mtoledo@cnen.gov.b [Comissao Nacional de Energia Nuclear (CNEN), Rio de Janeiro, RJ (Brazil). Div. de Normas

    2011-10-26

    The present work has the objective of making public the methodological approach adopted by the Brazilian Nuclear Energy Commission (CNEN) to create a nuclear normative structure up-dated and coherent. According to the Law 4118/62, 6189/74 and 7781/89, is the attribution the CNEN to establish specific guidelines for nuclear safety and radiological protection, and also do dictate safety norms through the emission of Resolutions

  3. The brazilian nuclear policy with respect to the public opinion

    International Nuclear Information System (INIS)

    Four decades of the Brazilian nuclear history have been analysed with special emphasis placed on government policy and its repercussion on public opinion. The implications of the new constitutional regulations which rule the issue are discussed. it is also studied the change in the nuclear program structure, enforced in August 1988. At different times, the government decisions on nuclear energy could be classified as miser, extravagant, dissimulated and frank, successively. Their aftermaths, which show little consistency with the expectations laid on them, have led to discredit by part of the society, which is controlled by a scientific - intellectual elite. However, recent successes are likely to reverse this trend, if the government explores them properly. (author)

  4. Quality and safety of nuclear installations: the role of administration, and, nuclear safety and regulatory procedures

    International Nuclear Information System (INIS)

    In the first paper the author defines the concepts of safety and quality and describes the means of intervention by the Public Authorities in safety matters of nuclear installations. These include individual authorisations, definition and application of technical rules and surveillance of installations. In the second paper he defines the distinction between radiation protection and safety and presents the legislative and regulatory plan for nuclear safety in France. A central safety service for nuclear installations was created in March 1973 within the Ministry of Industrial and Scientific Development, where, amongst other tasks, it draws up regulatory procedures and organizes inspections of the installations. The main American regulations for light water reactors are outlined and the French regulatory system for different types of reactors discussed

  5. Safety review and assessment on nuclear fuel cycle installations and nuclear materials control

    International Nuclear Information System (INIS)

    The NNSA conducted a review and assessment, and supervision on the large-sized fuel manufacture line of YNFP and spent fuel storage pool of LNFC and the pilot plant of Spent Fuel Reprocessing. The physical protection of newly constructed nuclear installations were reviewed and assessed and an regulatory inspection was conducted on the units that being granted with a license for nuclear materials

  6. Virtual instrumentation on mobile devices for deployment in nuclear installations

    International Nuclear Information System (INIS)

    The virtual instrumentation can be defined as a layer of software and hardware, added to a general purpose computer, so that users can interact with the computer in the same way that they interacted with traditional electronic instruments such as oscilloscopes, multi-meters and signal generators, and may add other functions defined by software. The virtual instrumentation gets a new integration environment, little explored yet, with the great growth that occurred in the mobile devices area. Nowadays it is possible to take measurements in more places by combining mobile devices with data acquisition hardware to create extremely portable and interconnected measurement systems. This paper shows the development of software and hardware that make possible the use of instrumentation on mobile devices for monitoring nuclear installations. It's presented the hardware and the application software for data acquisition of radiation monitors, developed to iOS devices. It's also shown the possibilities of hardware and software to develop near real-time data transfer to and from the field in nuclear installations, with benefits in efficiency, safety and productivity. (author)

  7. Conclusions and theses relating to the decommissioning of nuclear installations

    International Nuclear Information System (INIS)

    Most of the problems encountered in decommissioning are due to deficiencies on the side of the laws. Items of controversy revealed at the meeting are: -content covered by the term decommissioning; - definition of decommissioning stages and their hierarchy in schedule; - subject matter of decommissioning; -interfaces between operation and decommissioning processes; - substantive requirements to be met; - formal requirements to be met. The meaning of the term 'nuclear installation' used in paragraph 7 sub-sec. (3), 1st sentence Atomic Energy Act corresponds to the meaning of the term used in paragraph 7 sub-sec. 1 Atomic Energy Act. However, the licensee is free to proceed with the decommissioning of individual components of an installation that can be disconnected from the safety programme of decommissioning activities. Those measures in the post-shutdown phase under regulatory control under the operating licence or the surveillance programme do not require to be licensed anew. All other measures require a licence for decommissioning ('as far as'). Decommissioning cannot be 'directed' by orders under the surveillance programme. The (unlawful) nuclear power phaseout cannot be imposed on the basis of paragraph 7 sub-sec. 3 Atomic Energy Act. (orig./HSCH)

  8. Virtual instrumentation on mobile devices for deployment in nuclear installations

    Energy Technology Data Exchange (ETDEWEB)

    Farias, Marcos Santana; Santos, Isaac Jose A. Luquetti dos; Jesus, Miller F. de; Sant' Anna, Claudio Reis de; Szabo, Andre Pedro; Carvalho, Paulo Victor R. de, E-mail: msantana@ien.gov.br, E-mail: luquetti@ien.gov.br, E-mail: mil-far@hotmail.com, E-mail: santanna@ien.gov.br, E-mail: szabo@ien.gov.br, E-mail: paulov@ien.gov.br [Instituto de Engenharia Nuclea (IEN/CNEN-RJ), Rio de Janeiro, RJ (Brazil). Div. de Engenharia Nuclear

    2013-07-01

    The virtual instrumentation can be defined as a layer of software and hardware, added to a general purpose computer, so that users can interact with the computer in the same way that they interacted with traditional electronic instruments such as oscilloscopes, multi-meters and signal generators, and may add other functions defined by software. The virtual instrumentation gets a new integration environment, little explored yet, with the great growth that occurred in the mobile devices area. Nowadays it is possible to take measurements in more places by combining mobile devices with data acquisition hardware to create extremely portable and interconnected measurement systems. This paper shows the development of software and hardware that make possible the use of instrumentation on mobile devices for monitoring nuclear installations. It's presented the hardware and the application software for data acquisition of radiation monitors, developed to iOS devices. It's also shown the possibilities of hardware and software to develop near real-time data transfer to and from the field in nuclear installations, with benefits in efficiency, safety and productivity. (author)

  9. Fuel for the next Brazilian nuclear power plants

    International Nuclear Information System (INIS)

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

  10. Environmental assessment of nuclear installations using accumulated litterfall cycling

    International Nuclear Information System (INIS)

    For 25 years the Nuclear and Energy Research Institute - IPEN/SP processed uranium oxide to produce the fuel element. Even with major care in the handling of uranium hexafluoride and uranium compounds, there is the probability of small fractions are dispersed into the atmosphere. Due to this fact, it was proposed a study of these compounds in the environment, aiming at the bio monitoring of toxic substances originating from the fabrications process of fuel element, as well toxic metals. The litterfall it's consisted of fragments of organic vegetable, including leaves, flowers, fruits, branches, twigs and animal waste. The objective of this study was to determine the production and seasonality of litterfall in the gardens of IPEN, establish a correlation between the compartment leaves, wood and reproductive parts and evaluate the chemical composition of leaves originated of litterfall through chemical analysis. Was installed 10 litterfall collectors to determinate the production . The determination of chemical elements was realized by X-ray fluorescence for dispersion of wavelength (WDXRF). The production of dry litterfall during the period was 5.86 Kg m2 -1. The elements analyzed were Na, Mg, Al, Si, P, S, Cl, K, Ca, Ti, Mn, Fe, Ni, Cu, Br, Rb, Sr, Zr, Th and U. The major constituents of the composition of leaf Ca, Si, and K (1.8%, 0.5% and 0.6% respectively). The results allowed to conclude that the installations used in the nuclear fuel cycle earlier, as well as the installations in operation, actually didn't affect the biogeochemical cycle of plants. (author)

  11. Rules for the implementation of regulations on the safety regulation for civilian nuclear installations of the People's Republic of China. Pt.2: Safety surveillance of nuclear installations

    International Nuclear Information System (INIS)

    This Rules were promulgated by the National Nuclear Safety Administration on June 14, 1995, which are applicable to the nuclear safety surveillance of all safety-related items and activities during all stages of siting, design, construction, commissioning, operation and decommissioning of nuclear installations. The purpose of the nuclear safety surveillance is to inspect the implementation of the nuclear safety control requirements and the licence conditions, to inspect and urge the correction of items that do not conform with the nuclear safety control requirements and the licence conditions and to take enforcement measures if necessary, in order to ensure the safety of nuclear installations

  12. Use of ports, bays and waters under national Brazilian jurisdiction by nuclear ships

    International Nuclear Information System (INIS)

    This norm establishes the requirements of nuclear safety and radioprotection for the entrance and utilization of ports, bays and waters under Brazilian national jurisdiction, by nuclear ships, aiming the obtention of governmental authorization and further control from the proper authorities

  13. Consequences of bilateral and multilateral restrictions in the Brazilian Nuclear Program

    International Nuclear Information System (INIS)

    A brief historical aspects on research activities for the nuclear energy development, the historical antecedents related to restrictions in the international cooperation agreements and, the Brazilian relationship with the international nuclear policy, are presented. (M.C.K.)

  14. Installation technology and innovation about nuclear instrument system used in CPR1000 nuclear power plant

    International Nuclear Information System (INIS)

    Based on the nuclear instrument system erection installed in Lingao Phase Ⅱ, the erection technology characteristic, erection process, problems and optimized solutions found during site erection are detailed introduced in this paper. And the optimizations of erection technology are also analyzed and summarized. It is an important reference for nuclear instrument system erection of Hongyanhe, Ningde, Yangjiang NPP, and it is also a profitably attempt for optimization of nuclear instrument system erection and improvement of independent erection ability. (authors)

  15. Centro Regional de Ciencias Nucleares (a Brazilian regional center for nuclear sciences) - activities report - 1999

    International Nuclear Information System (INIS)

    The annual activities report of 1999 of nuclear sciences regional center - Brazilian organization - introduces the next main topics: institutional relations; sectorial actions - logistic support and training, laboratory of radiation protection and dosimetry, laboratory of metrology, laboratory of chemical characterization; technical and scientific events; and financial resources and perspectives for 2000

  16. Regulatory oversight report 2008 concerning nuclear safety in Swiss nuclear installations

    International Nuclear Information System (INIS)

    This annual report issued by the Swiss Federal Nuclear Inspectorate (ENSI) reports on the work carried out by the Inspectorate in 2008. This report reviews the regulatory activities in the four Swiss nuclear power stations and in four further nuclear installations in various Swiss research facilities. It deals with topics such as operational details, technologies in use, radiation protection, radioactive wastes, emergency dispositions, personnel and provides an assessment of operations from the safety point of view. Also, the transportation of nuclear materials - both nuclear fuels and nuclear wastes - is reported on. General topics discussed include probabilistic safety analyses and accident management, earthquake damage analysis and agreements on nuclear safety. The underground disposal of highly-radioactive nuclear wastes and work done in the rock laboratories are discussed, as are proposals for additional nuclear power stations

  17. Extent of inspections for lifting appliances in nuclear installations

    International Nuclear Information System (INIS)

    During in-service inspections of lifting appliances, the test specifications, principles, and guidelines included in the technical rules are to be applied for the inspection of elevators and cranes. In annex 1 these specifications, principles, and guidelines are compiled. For lifting appliances in nuclear installations, which according to KTA rule 3902, edition 11/75, have to meet additional and more rigorous requirements, no. 10.3 is relevant. In nos. 2 and 3 of this direction, those in-service inspections are listed in detail which go beyond the general requirements according to no. 10.3.3 rule KTA 3902, edition 11/75. The extent of the inspections has to be set up between licensee and inspecting expert in a program for in-service inspections. (orig./HP)

  18. Earthquake design response spectra for nuclear installations in Switzerland

    International Nuclear Information System (INIS)

    A statistical evaluation of strong motion records typical for the seismotectonic conditions existing in Switzerland was made to develop guidelines for establishing and reviewing earthquake design spectra for nuclear installations in Switzerland. Selection criteria, such as focal parameters of the earthquake, distance from epicenter to recording station, local conditions at recording station, and quality of the strong motion data were determined to select a final data set of 19 records on rock and 22 records on stiff alluvium out of more than 200 records predominantly from Southern Europe. A statistical analysis of these data was made to determine the 84 percentile piecewise linear design response spectra. The comparison with the horizontal US NRC spectra showed a considerable reduction in response for frequencies lower than 3.5 Hz for rock sites and 2.5 Hz for soil sites. The vertical design spectra could be established as 2/3 of the corresponding horizontal spectra over the entire frequency range. (orig.)

  19. The nuclear agreement with Germany in the context of Brazilian 'model' and the crisis

    International Nuclear Information System (INIS)

    The Brazilian Nuclear Program is discussed in the context of the so-called Brazilian 'model' which conditions the industrial and technological structure of Brazil. The relations between the Brazilian private industry, the Brazilian state industry and the foreign multinational industry in the nuclear agreement Brazil - Germany are indicated. The economic crisis, the 'energy crisis', the mistakes of the nuclear program, the political fight for the revision of the agreement, the present situation and the problems of technological transfer are also discussed. Some alternatives are suggested for NUCLEBRAS. In an annex, comments are made on the question of Brazilian reactors safety. The so-called system of Protection to the Nucleare Program is also mentioned. (I. de C.R.)

  20. Instituto de Engenharia Nuclear ( a Brazilian nuclear engineering institute) - activities report - 1997

    International Nuclear Information System (INIS)

    The annual activities report of 1997 of nuclear engineering institute - Brazilian organization - introduces the next main topics: work program; main achievements - nuclear energy social and environmental applications, radioisotopes production, research reactors operation and maintenance and adaptation, reactors technology development and nuclear fuel; technical and scientific production - articles published in periodicals, participation in scientific events, thesis and dissertations, nuclear engineering institute publications, technical communications, collaboration in jobs of others institutions; mutual cooperation and contracts activities; human resources - training and courses; products and offered services; and implemented goals in 1997

  1. Nuclear law and environmental law in the licensing of nuclear installations

    International Nuclear Information System (INIS)

    Large nuclear installations can have a considerable impact on the environment, both in actual terms, due to the construction and operation of the plant and in potential terms, related to the risk of an accident. A considerable part of the multiple authorisation processes required to develop a large nuclear project is devoted to addressing the possible impact on the environment. Accordingly, environmental protection is not only warranted by requirements and processes arising out of what is generally considered 'environmental law', but also by laws governing the design, siting, construction and operation of nuclear installations. By ensuring prevention and control of radiation releases to the environment, the aspects of nuclear law governing the design, construction, operation and decommissioning of nuclear facilities pertain to the field of environmental protection just like other fields of environmental law. The perception of the public that nuclear energy is 'anti-environmental' and the generally antinuclear stance of environmental non-governmental organisations (NGOs) should not deflect attention from the fact that protection of the environment is one of the main functions of the body of nuclear law. In this article, the general relationship between the law governing civil nuclear installations and environmental law will be analysed. The subsequent chapters will deal with environmental requirements and procedures as part of the authorisation process for a nuclear installation. The role of public participation and the involvement of neighbouring states in the licensing process will also be investigated, as they are today mainly based on environmental law. Some other aspects which may also have some relation to environmental protection, such as waste management, emergency planning, multinational early notification and assistance in the case of an accident and nuclear liability, have been omitted from discussion as they lie outside the focus of this article

  2. Generation of aerosols for filter efficiency testing in nuclear installations

    International Nuclear Information System (INIS)

    The purpose of the Research Contract No. 1815 was to develop a new method of sodium chloride aerosol generation for filter efficiency testing in nuclear installations. The first phase of the study was devoted to the development of a suitable aerosol generator. The first NaCl aerosol generator enabled determination of the influence various parameters like nozzle diameter, air flow rate, NaCl concentration in solution, solution temperature, etc., on the generation capacity and aerosol characteristics. The drawbacks of this generator were removed by modifying the design. Sodium chloride aerosol concentration was measured by means of a portable sodium flame photometer, and the particle size distribution was determined by a six-stage Andersen cascade impactor. For particle shape analysis electron microscopy was used. By using the aerosols generated the efficiency of air filters was tested. The results showed that the optimum parameters for atomization of 24NaCl solution are: Nozzle diameter 0.5x10-3m; compressed air pressure 196.132kPa; air flow rate 6.1x10-5m3/s. Under these conditions test aerosols of 0.335x10-6m mass median diameter were obtained with a geometrical standard deviation, sigma=2.04. Preliminary high efficiency particulate air filter tests with the above 24NaCl aerosols showed the minimum filter penetration of the order of 5x10-5% with a relative standard deviation not exceeding 15%. This showed that the 24NaCl aerosol generated from liquid phase can be successfully used for filter testing in nuclear installations

  3. Indonesian policies regulations and the safety criteria for decommissioning of nuclear installations

    International Nuclear Information System (INIS)

    Currently, Indonesia operates several nuclear installations such as: three research reactors, two fuel fabrication facilities, one radioactive waste facility, several irradiators, one radioisotope production facility, and other facilities utilizing radioactive materials and sources. From these installations, there is no nuclear installation which has been decommissioned to date. However, there is one nuclear installation which is not operated any more by the operator, therefore this installation has to be decommissioned. Based on this it is necessary to determine a policy, regulation and safety criteria for nuclear installation decommissioning. In this paper the policy, regulation and safety criteria for decommissioning of nuclear installations in Indonesia will be presented. The responsibility of regulatory body and licensee will also be presented. (author)

  4. Chapter No.3. Assessment and inspection of nuclear installations

    International Nuclear Information System (INIS)

    The assessment activity of UJD in relation to nuclear installation lies in assessment of safety documentation for constructions realised as nuclear installations, or construction through which changes on nuclear installations are realised. The assessment activity of UJD in 2001 was focused on National Repository of Radwaste in Mochovce, on Radwaste conditioning and treatment technology in Jaslovske Bohunice and on the assessment of documentation for the project of modernisation of Bohunice V-2 NPPs which is under preparation. The assessment of the technical condition of equipment, important in terms of nuclear safety, primarily based on results of in-service inspections and surveillance testing of safety related components and systems, is also a part of the safety assessment of nuclear installation operation. The inspectors take part in training courses and participate in other technical meetings and workshops organised by the IAEA and also take part in special training courses organised by the Nuclear Authorities of European countries, USA and Japan. Bohunice V-1 NPP is equipped with two reactors of WWER 440 type V-230 and was put into operation in 1978-1980 as one of the last nuclear power plants with this type of reactor. Both units of NPP V-1 Bohunice operated in 2001 according to the requirements of energy dispatching at nominal power, or in a regime of tertiary regulation. November 2000, a mission of experts invited by UJD and delegated by IAEA took place at the Bohunice NPPs. The mission members together with experts of the plant operator assessed the safety of the units of WWER-440/V-230 of Bohunice V-1 NPP after the reconstruction. The members of the mission prepared the report on the current status of safety of these units for the IAEA. In 2001, UJD by its decision, issued the approval for further operation of both reactor units of Bohunice V-1 NPP. In sense of the relevant decree on operational events, 20 events have been recorded, at Bohunice V-1 NPP in

  5. International guidelines for fire protection at nuclear installations including nuclear fuel plants, nuclear fuel stores, teaching reactors, research establishments

    International Nuclear Information System (INIS)

    The guidelines are recommended to designers, constructors, operators and insurers of nuclear fuel plants and other facilities using significant quantities of radioactive materials including research and teaching reactor installations where the reactors generally operate at less than approximately 10 MW(th). Recommendations for elementary precautions against fire risk at nuclear installations are followed by appendices on more specific topics. These cover: fire protection management and organization; precautions against loss during construction alterations and maintenance; basic fire protection for nuclear fuel plants; storage and nuclear fuel; and basic fire protection for research and training establishments. There are numerous illustrations of facilities referred to in the text. (U.K.)

  6. Regulatory oversight report 2007 concerning nuclear safety in Swiss nuclear installations

    International Nuclear Information System (INIS)

    This annual report issued by the Swiss Federal Nuclear Inspectorate (HSK) reports on the work carried out by the Inspectorate in 2007. This report reviews the regulatory activities in the four Swiss nuclear power stations and in four further nuclear installations in various Swiss research facilities. It deals with topics such as operational details, technologies in use, radiation protection, radioactive wastes, emergency dispositions and personnel and provides an assessment of operations from the point of view of safety. Also, the transportation of nuclear materials - both nuclear fuels and nuclear wastes - is reported on. General topics discussed include probabilistic safety analyses and accident management. Finally, the disposal of nuclear wastes and work done in the rock laboratories in Switzerland is commented on

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

    International Nuclear Information System (INIS)

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

  8. Intercomparison of 131I and 99mTc activity measurements in Brazilian nuclear medicine services

    International Nuclear Information System (INIS)

    This work outlines the quality assurance program for the activity measurements of the most used radionuclides at Brazilian Nuclear Medicine Services (NMS). The program aims to guarantee that the patient is given the correct prescribed amount of activity in diagnostic or therapeutic applications. This accurate administration depends upon proper use and calibration of the activity meters by the NMS. Underestimation of administered activity in diagnostic practices could delay correct diagnosis disturbing the value of the investigation. On the other hand, the overestimation would be worse, mainly in therapeutic applications, because an unnecessarily high absorbed dose would be delivered to the patient. The preliminary results of intercomparison for 131I and 99mTc showed that many activity meters used at NMS's present problems giving results up to 41% greater than the reference values determined at the National Metrology Laboratory for Ionizing Radiation (LNMRI) which is recognized as the Brazilian authorized metrology laboratory for ionizing radiation. These results have demonstrated that the NMS should improve the accuracy of the activity measurements of the radionuclides administered to the patients and establish the traceability to the national standards of measurements. These standards are based on a pressurized well-type ionization chamber installed at LNMRI and calibrated with reference sources standardized by absolute methods. The protocol of the intercomparison and recommendations made in order to minimize errors in measuring procedures are described and results are discussed

  9. Survey on product properties of bituminized waste concentrates from reprocessing, nuclear installations and nuclear power plants

    International Nuclear Information System (INIS)

    This report contains a brief survey on the product properties after solidification with bitumen of waste concentrates from reprocessing plants, nuclear research installations and nuclear power plants. The leach behaviour of bitumen products in water and saturated salt solutions is described as well as the radiolytic and thermal stability of the products. The reports also contain some data on sedimentation of salts fixed in bitumen. (orig.)

  10. Regulatory Oversight of Safety Culture in Nuclear Installations

    International Nuclear Information System (INIS)

    . Accordingly, this publication provides practical guidance on developing and implementing strategies and processes for regulators to employ to monitor a licensee's safety culture in nuclear installations and in related activities. It is based on a compilation of state of the art international and national efforts.

  11. S.I. 1987 No.688, The Nuclear Installations (Isle of Man) (Variation) Order 1987

    International Nuclear Information System (INIS)

    This Order, which amends the Nuclear Installations (Isle of Man) Order 1977, came into force on 7 May 1987. The Nuclear Installations (Isle of Man) Order 1977 extends certain provisions of the Nuclear Installations Act 1965 as appropriate, to the Isle of Man. This Order extends amendments made to that Act by the Energy Act 1983 and the Congenital Disabilities (Civil Liability) Act 1976, as appropriate, to the Isle of Man. (NEA)

  12. Aspects of the Brazilian law on civil liability for nuclear damage

    International Nuclear Information System (INIS)

    The civil liability for nuclear damage in the Brazilian law is analysed. The innovations introduced by the 6.453 act of October 17 th, 1977 are emphasized. The influence of international conventions on the Brazilian law are also mentioned. (A.L.)

  13. The plutonium recycle for PWR reactors from brazilian nuclear program

    International Nuclear Information System (INIS)

    The purpose of this thesis is to evaluate the material requirements of the nuclear fuel cycle with plutonium recycle. The study starts with the calculation of a reference reactor and has flexibility to evaluate the demand under two alternatives of nuclear fuel cycle for Pressurized Water Reactors (PWR): Without plutonium recycle; and with plutonium recycle. Calculations of the reference reactor have been carried out with the CELL-CORE codes. Variations in the material requirements were studied considering changes in the installed nuclear capacity of PWR reactors, the capacity factor of these reactors, and the introduction of fast breeders. Recycling plutonium produced inside the system can reach economies of about 5% U3 O8 and 6% separative work units if recycle is assumed only after the fifth operation cycle of the thermal reactors. (author)

  14. State fund of decommissioning of nuclear installations and handling of spent nuclear fuels and nuclear wastes (Slovak Republic)

    International Nuclear Information System (INIS)

    State Fund for Decommissioning of Nuclear Installations and Handling of Spent Nuclear Fuels and Nuclear Wastes was established by the Act 254/1994 of the National Council of the Slovak Republic as a special-purpose fund which concentrates financial resources intended for decommissioning of nuclear installations and for handling of spent nuclear fuels and radioactive wastes. The Act was amended in 2000, 2001 and 2002. The Fund is legal entity and independent from operator of nuclear installations Slovak Power Facilities Inc. The Fund is headed by Director, who is appointed and recalled by Minister of Economy of the Slovak Republic. Sources of the Fund are generated from: a) contributions by nuclear installation operators; b) penalties imposed by Nuclear Regulatory Authority of the Slovak Republic upon natural persons and legal entities pursuant to separate regulation; c) bank credits; d) interest on Fund deposits in banks; e) grants from State Budget; f) other sources as provided by special regulation. Fund resources may be used for the following purposes: a) decommissioning of nuclear installations; b) handling of spent nuclear fuels and radioactive wastes after the termination of nuclear installation operation; c) handling of radioactive wastes whose originator is not known, including occasionally seized radioactive wastes and radioactive materials stemming from criminal activities whose originator is not known, as confirmed by Police Corps investigator or Ministry of Health of the Slovak Republic; d) purchase of land for the establishment of nuclear fuel and nuclear waste repositories; e) research and development in the areas of decommissioning of nuclear installations and handling of nuclear fuels and radioactive wastes after the termination of the operation of nuclear installations; f) selection of localities, geological survey, preparation, design, construction, commissioning, operation and closure of repositories of spent nuclear fuels and radioactive wastes

  15. Design aspects of safety critical instrumentation of nuclear installations

    International Nuclear Information System (INIS)

    Safety critical instrumentation systems ensure safe shutdown/configuration of the nuclear installation when process status exceeds the safety threshold limits. Design requirements for safety critical instrumentation such as functional and electrical independence, fail-safe design, and architecture to ensure the specified unsafe failure rate and safe failure rate, human machine interface (HMI), etc., are explained with examples. Different fault tolerant architectures like 1/2, 2/2, 2/3 hot stand-by are compared for safety critical instrumentation. For embedded systems, software quality assurance is detailed both during design phase and O and M phase. Different software development models such as waterfall model and spiral model are explained with examples. The error distribution in embedded system is detailed. The usage of formal method is outlined to reduce the specification error. The guidelines for coding of application software are outlined. The interface problems of safety critical instrumentation with sensors, actuators, other computer systems, etc., are detailed with examples. Testability and maintainability shall be taken into account during design phase. Online diagnostics for safety critical instrumentation is detailed with examples. Salient details of design guides from Atomic Energy Regulatory Board, International Atomic Energy Agency and standards from IEEE, BIS are given towards the design of safety critical instrumentation systems. (author)

  16. Strengthening the culture of safety and performance in nuclear installations

    International Nuclear Information System (INIS)

    In mid-1995, the International Atomic Energy Agency (IAEA) in Vienna brought together a group of safety culture experts from around the world to explore and summarize those practices they viewed as important in establishing sound safety cultures in nuclear installations. This paper will summarize key findings of the Vienna team and also expand those ideas based on related work in which the authors are engaged. The paper includes a definition of safety culture, a description of three stages of safety culture, and five key practices essential to establishing and maintaining a sound safety culture. Additionally, the authors contradicts the conventional view of safety and production as trade-offs, supporting the Vienna team's conclusion that the principles, attitudes, and practices which bring about sustained levels of high performance are the same as those which enhance safety. Based on input from colleagues in several countries, this appears to hold true across geographical and ethnic boundaries. The authors also discuss how this information can be put to practical use to obtain an objective, measurable, and repeated assessment of the current state of the safety culture within a company, plant or work unit. With that information, leaders are then in the position to act on any of the several parameters which affect both safety and performance effectiveness. (author)

  17. Improvement of piping installation work in nuclear power plant

    International Nuclear Information System (INIS)

    The shortening of the construction period for nuclear power plants has become a national problem, but because of the increase of plant power output and the improvement of safety, the design process tends to extend, consequently, the construction works at a site are forced to bear burden. Especially, piping works handle innumerable parts, and require complex management, accordingly the large difference in the construction period may occur owing to the method of carrying them out. Piping works are roughly divided into carrying parts into buildings and assembling and welding. In order to improve the complexity of carrying-in works and time loss, parts should be carried into buildings vertically before the ceilings are constructed, namely under blue sky. When parts are carried in this way, the unit to be carried in can be made large, therefore, the welding work at a site can be reduced. The merits brought about by this new construction method are the shortening of piping installation period, the rationalization of process management, the improvement of work safety, and the strengthening of quality control. In this new construction method, the design and manufacture of piping parts must be finished earlier. (Kako, I.)

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

    International Nuclear Information System (INIS)

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

  19. The protection and the preservation of the environment the Brazilian nuclear law

    International Nuclear Information System (INIS)

    A set of Brazilian rules governing the protection and the preservation of the environment in relation to nuclear activities is presented. The role of CNEN, as an institution that defends the environment is also mentioned. (A.L.)

  20. Evaluation of the nuclear installations safety of the CEA in 1998

    International Nuclear Information System (INIS)

    Michel Laverie, Director of the nuclear safety and quality at the Cea, took stoke of the CEA nuclear installations in 1998. After a recall of the nuclear safety policy and organization, the author presents the risks factors bound to the CEA activities as the dismantling, the wastes and the human factors. A last part is devoted to the list of the accidents occurred during 1998 in the nuclear installations. Tables and statistics illustrate this analysis. (A.L.B.)

  1. Nuclear option: analysis of the actual status and future perspectives for Brazilian case

    International Nuclear Information System (INIS)

    This report presents a global view of actual status and future perspectives of Brazilian nuclear option. By diversity of subjects treated in it, the difficulties are appointed at each chapter, when necessary. The strategies are focused in details in chapters 7 and 8. In chapter 10 they are emphasized in its main aspects for Brazilian case. To give an overview of the state-of-the-art related to nuclear energy, many figures and references are presented in the Annex

  2. Memorandum of Understanding on cooperation and consultation on nuclear installations near borders

    International Nuclear Information System (INIS)

    This Agreement signed on 27 September 1977 lays down that the Contracting Parties will inform each other about all nuclear installations constructed along the common border. Nuclear installations within the meaning of the Agreement are installations for the production, processing, reprocessing, manufacture or fission of nuclear fuels and radioactive waste storage. The information to be communicated includes plans and decisions on siting, construction and operation of such installations and relevant documents. The Agreement provides for consultation between the Parties on safety aspects and lays down in detail all the conditions for communication of information. (NEA)

  3. The assistance and recording of radiological emergencies and nuclear accidents of Brazilian National Nuclear Energy Commission

    International Nuclear Information System (INIS)

    The Brazilian National Nuclear Energy Commission with the aim of obtain the prompt notification and of assisting in potential or real radiological emergency situations and nuclear accidents, has organized an integrated system, in prevention regimen, working 24 hours a day. All notifications related to events that could result in an emergency situation, coming from any part of the national territory, are immediately sent to the system. This system was implemented in July 1990 and has received 107 notifications of which 10% were classified as potential emergency situations. The system organization is described. (B.C.A.). 08 refs, 04 figs

  4. 75 FR 60147 - Calvert Cliffs Nuclear Power Plant, LLC; Independent Spent Fuel Storage Installation; Notice of...

    Science.gov (United States)

    2010-09-29

    ... COMMISSION Calvert Cliffs Nuclear Power Plant, LLC; Independent Spent Fuel Storage Installation; Notice of... Branch, Division of Spent Fuel Storage and Transportation, Office of Nuclear Material Safety and... Independent Spent Fuel Storage Installation (ISFSI) Technical Specifications (TS) be revised as follows: 1....

  5. Seismic Hazards in Site Evaluation for Nuclear Installations. Specific Safety Guide

    International Nuclear Information System (INIS)

    This Safety Guide was prepared under the IAEA programme for safety standards for nuclear installations. It supplements the Safety Requirements publication on Site Evaluation for Nuclear Installations. The present publication provides guidance and recommends procedures for the evaluation of seismic hazards for nuclear power plants and other nuclear installations. It supersedes Evaluation of Seismic Hazards for Nuclear Power Plants, IAEA Safety Standards Series No. NS-G-3.3 (2002). In this publication, the following was taken into account: the need for seismic hazard curves and ground motion spectra for the probabilistic safety assessment of external events for new and existing nuclear installations; feedback of information from IAEA reviews of seismic safety studies for nuclear installations performed over the previous decade; collective knowledge gained from recent significant earthquakes; and new approaches in methods of analysis, particularly in the areas of probabilistic seismic hazard analysis and strong motion simulation. In the evaluation of a site for a nuclear installation, engineering solutions will generally be available to mitigate, by means of certain design features, the potential vibratory effects of earthquakes. However, such solutions cannot always be demonstrated to be adequate for mitigating the effects of phenomena of significant permanent ground displacement such as surface faulting, subsidence, ground collapse or fault creep. The objective of this Safety Guide is to provide recommendations and guidance on evaluating seismic hazards at a nuclear installation site and, in particular, on how to determine: (a) the vibratory ground motion hazards, in order to establish the design basis ground motions and other relevant parameters for both new and existing nuclear installations; and (b) the potential for fault displacement and the rate of fault displacement that could affect the feasibility of the site or the safe operation of the installation at

  6. Progress report 2011-2013 - Brazilian Energy and Nuclear Research Institute - IPEN

    International Nuclear Information System (INIS)

    This progress report presents the results of the R&D center of IPEN in accordance with the main programs: Lasers Technology, Applications of Ionizing Radiations, Biotechnology, Renewable Energies, Radiopharmacy, Nuclear Science and Technology, Environmental Science and Technology, Nuclear Reactors and Fuel Cycle, Materials and Nanotechnology, Nuclear Safety, Education, Brazilian Multipurpose Reactor and Scientific and Technical Production

  7. Power Installations based on Activated Nuclear Reactions of Fission and Synthesis

    CERN Document Server

    Grigoriev, Yuriy

    2016-01-01

    The general scheme of power installations based on nuclear reactions of fission and synthesis activated by external sources is analyzed. The external activation makes possible to support nuclear reactions at temperatures and pressures lower than needed for chain reactions, so simplifies considerably practical realization of power installations. The possibility of operation on subcritical masses allows making installations compact and safe at emergency situations. Installations are suitable for transmutation of radioactive nuclides, what solves the problem of utilization of nuclear waste products. It is proposed and considered schemes of power installations based on nuclear reactions of fission and fusion, activated by external sources, different from ADS systems. Variants of activation of nuclear reactions of fission (U-235, 238, Pu-239) and fusion (Li-6,7, B-10,11) are considered.

  8. Plutonium: resuspension of aerosols in nuclear installations: bibliographic survey

    International Nuclear Information System (INIS)

    This document presents an analysis and a bibliographical synthesis of the studies on resuspension factors for plutonium. It aims at helping the engineers of safety to specify the scenarios of accidents which relate to their activities and to bring elements justified for the definition of their term-source 'installation' in the safety reports of the installations. (authors)

  9. Management report 2004 CNEN - Brazilian Nuclear Energy Commission; Relatorio de gestao 2004 CNEN - Comissao Nacional de Energia Nuclear

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-03-15

    This document reports the results of the activity management of the Comissao Nacional de Energia Nuclear - CNEN - Brazil during the year of 2004, involving the Brazilian program of nuclear activities in the areas of nuclear safety, research and development, radiopharmaceutical production, institutional management, teaching, administration in general and miscellaneous.

  10. Management report 2007 CNEN - Brazilian Nuclear Energy Commission; Relatorio de gestao 2007 CNEN - Comissao Nacional de Energia Nuclear

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2007-07-01

    This document reports the general activity management of the Comissao Nacional de Energia Nuclear - CNEN - Brazil during the year of 2007, involving the CNEN role in the public policy execution, the Brazilian program of nuclear activities in the areas of nuclear safety, research and development, radiopharmaceutical production, teaching, administration in general and miscellaneous.

  11. Management report 2006 CNEN - Brazilian Nuclear Energy Commission; Relatorio de gestao 2006 CNEN - Comissao Nacional de Energia Nuclear

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2007-03-15

    This document reports the results of the activity management of the Comissao Nacional de Energia Nuclear - CNEN - Brazil during the year of 2005, involving the Brazilian program of nuclear activities in the areas of nuclear safety, research and development, radiopharmaceutical production, institutional management, teaching, administration in general and miscellaneous.

  12. Management report 2005 CNEN - Brazilian Nuclear Energy Commission; Relatorio de gestao 2005 CNEN - Comissao Nacional de Energia Nuclear

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-03-15

    This document reports the results of the activity management of the Comissao Nacional de Energia Nuclear - CNEN - Brazil during the year of 2005, involving the Brazilian program of nuclear activities in the areas of nuclear safety, research and development, radiopharmaceutical production, institutional management, teaching, administration in general and miscellaneous.

  13. Training of nuclear medicine technical staff by the Brazilian Society of Nuclear Medicine and Biology

    International Nuclear Information System (INIS)

    Full text: Nuclear medicine was introduced in Brazil in 1949, at the University of Sao Paulo. Despite being a pioneer in South America and the existence of about 280 clinics of this medical specialty in the whole country serving around 185 million inhabitants, there is not any dedicated course forming its technical staff. Another shortcoming lies in the fact that there are not any basic requirements established for these professionals by an official medical or nuclear entity. As result, one can find persons ranging from university graduates (biomedics, radiology technologists, biologists, pharmacists, chemists, physicists, etc.) to secondary school graduates or radiology technicians working in nuclear medicine centres, preparing patients, labelling and injecting radiopharmaceuticals, obtaining images and processing studies. Due to the high heterogeneity of the technical staff and lack of a formal preparation, the Brazilian Society of Nuclear Medicine and Biology (SBBMN) organized during 2004 and 2005 short courses conducted in different regions of Brazil in order to supply organized basic knowledge and practice on: 1. Quality control of 99Mo-99mTc eluates and labelling and checking of dose calibrators 2. Fundamentals of radiation protection, area monitoring and decontamination 3. Quality control of scintillation cameras. Six courses were given during these two years in four cities in the South Eastern region and two in the North Eastern region. The first two topics were delivered during one weekend and the participants were presented with a lecture in the morning and, in the afternoon, a hands-on practice on the same subject. As QC of eluates and labelling and checking of dose calibrators were less practised in most clinics, this was the first time that the majority of the participants performed these activities. In one course, offered during a national congress, all three topics were included and the practical part was replaced by many examples from routine

  14. Construction and operation of nuclear installations in the light of public international law

    International Nuclear Information System (INIS)

    The operation of nuclear installations carries potential dangers and risks which may lead to transfrontier damage. This fact directly concerns public international law and gives rise to the question of the legality of nuclear installations. It would seem that construction and operation of nuclear installations are permissible activities under public international law, provided that the international standards of reactor safety and radiation protection have been met and that there exists an adequate system of civil liability law. This applies in principle also to nuclear power plants located near a border. In this case a mutual obligation of consultation of the States concerned may derive from the principle of good neighbourliness. (Auth)

  15. Application of nuclear power station design criteria to non-nuclear installations

    International Nuclear Information System (INIS)

    The nuclear industry is multi faceted, in that it includes large and complex chemical plants, a large number of different types of nuclear power stations, and on shore ship maintenance facilities, each with its own unique problems. Since the early days the industry has been aware of the additional problem which is superimposed on what may be classed as traditional fire risks, that is, the risk of an uncontrolled release of radioactivity. This has led to the development of sophisticated fire prevention and control techniques which are applied to new plants, and to the backfitting of older plants. The techniques of analysis, design and operation can be applied to both nuclear and non-nuclear installations. Passive protection is preferred backed up by active techniques. Segregation of essential plant to increase the probability of sufficient surviving to ensure safety systems operate and the provision of smoke free, protected escape routes are important aspects of layout and design. Reliability assessments, venting of smoke and hot gases, fire severity analysis, application of mathematical models contribute to the final design to protect against fires. Experiences built up in the fire fighting profession is integrated into the numerical approach by frequent involvement of the local Fire Officers at each stage of the design and layout of installations. (author)

  16. Protection of nuclear installations and materials against malevolent actions

    International Nuclear Information System (INIS)

    parts: an estimate of the resources required to destroy or sufficiently damage a system or function (for example, the quantity of explosives necessary); qualification of the paths leading to zones or systems deemed sensitive. 3) If need be, counter-measures are taken to protect zones for which the consequences would be unacceptable compared to the force of the aggression. Counter-measures are intended both to minimise sensitivity and make it more difficult to carry out the aggression envisaged. Several types of threats have been identified for the purposes of these studies: Internal threats involving actions taken by insiders acting alone or not; External threats involving actions by small group of attackers. Two assumptions are made when testing the ability of protection systems to counter aggressions of this type. The first involves a small team of attackers with limited resources, and the second takes into account a larger team with more sophisticated resources. Assumptions are also made as to the types of action which could be taken by malevolent workers in sensitive zones and the aggravating factors to be considered. As an example the loss of the offsite power supply could be taken into account. Acceptable consequences are taken as being those leading to levels of radioactive releases less than, or equal to, those taken into account in the facility safety case. This implies that vital zone vulnerability be reduced to a minimum so that an excellent level of protection can be provided for these areas. In the case of critical zones, the level of protection is considered on a case-by-case basis, depending on the consequences of malevolent actions. Finally, the paper will describe the concrete case of a nuclear installation. Emphasis will be paid on the defence in depth approach organized around prevention, management and mitigation measures. (author)

  17. Safety related events at nuclear installations in 1995

    DEFF Research Database (Denmark)

    Korsbech, Uffe C C

    1996-01-01

    Nuclear safety related events of significance at least corresponding to level 2 of the International Nuclear Event Scale are described. In 1995 only two events occured at nuclear power plants, and four events occured at plants using ionizing radiation for processing or research.......Nuclear safety related events of significance at least corresponding to level 2 of the International Nuclear Event Scale are described. In 1995 only two events occured at nuclear power plants, and four events occured at plants using ionizing radiation for processing or research....

  18. New experience on construction and installation work in Qinshan PHWR nuclear power plant

    International Nuclear Information System (INIS)

    The article provides a summary of the new experience on construction management and construction technology in the field of civil construction and installation work in Qinshan PHWR nuclear power plant, with focus on innovation in project management mode, new technology application and computerized management of construction and installation work. Management innovation, technical innovation and information technology are the key contributors to overall success of Qinshan PHWR nuclear power plant in construction and installation work. The new experience derived in these fields will be of great significance to promote independent construction of the new-round nuclear power projects in China. (author)

  19. Policies of industrial market and science and technology: the case of Brazilian nuclear program

    International Nuclear Information System (INIS)

    The relationship between policies and the definition of a national program of nuclear energy, is considered. The case under study is the Brazilian one. It is shown that an overall evaluation of market, industry and science and technology is mandatory for the definition of a nuclear energy program, and serious fault and hesitation, leading to contradiction and failure, have their roots in a basic lack of definition in policies. The evolution of the Brazilian Nuclear Energy Program will probably remain at a mediocre level until a definition at the level of policy-making in marketing, industry and science and technology is firmly pursued and maintained. (Author)

  20. Evaluation of the nuclear installations safety of the CEA in 1998; Le bilan de la surete des installations nucleaires du CEA en 1998

    Energy Technology Data Exchange (ETDEWEB)

    Laverie, M. [CEA, Dir. de la Surete Nucleaire et de la Qualite, 75 - Paris (France)

    1999-09-01

    Michel Laverie, Director of the nuclear safety and quality at the Cea, took stoke of the CEA nuclear installations in 1998. After a recall of the nuclear safety policy and organization, the author presents the risks factors bound to the CEA activities as the dismantling, the wastes and the human factors. A last part is devoted to the list of the accidents occurred during 1998 in the nuclear installations. Tables and statistics illustrate this analysis. (A.L.B.)

  1. Legal aspects of search and mining of nuclear ores under Brazilian law

    International Nuclear Information System (INIS)

    The legal aspects of mining in the Brazilian law its general principles, the basic concepts and rules established in the constitution of Brazil, in the mining code and in special laws are analysed. The rules for mining and usage of nuclear ores and other ores of interest to the nuclear field are emphasized. (A.L.)

  2. Annual Report 2007 - ABACC - Brazilian-Argentine Agency for Accounting and Control of Nuclear Materials

    International Nuclear Information System (INIS)

    This document reports activities during the year 2007 related to: technical activities as application of safeguards; management of the Quadripartite Agreement and the SCCC - Common System for Accounting and Control of Nuclear Materials; training; technical cooperation; outlook for 2008 and; institutional, administrative and financial activities; technical glossary; list of brazilian facilities; list of argentine facilities and a list of institution of nuclear area

  3. Training in radioprotection in INB - Brazilian Nuclear Industries

    International Nuclear Information System (INIS)

    This work describes the ideas that guided the training in radiation protection and the first results obtained in the first half of 2004. The training took place in the Uranium Concentrate Unit URA, in Caetite, BA, in the Ore Treatment Unit - UTM, in Caldas, MG, and in the Heavy Mineral Unit - UMP, in San Francisco de Itabapuana, RJ, Brazil. In URA it was spent 9 days. 79 students were trained in 6 classes (average 13 pupils per class). Each group spent 9 hour of training, for a total of 54 hours of training given. There was no disapproval, and the grade average of the students was 9.2, with the lowest grade 7.5 and the highest 10.0. In UTM, it was spent 9 days. 200 students were trained in 9 classes (an average of 22 students per class). Each class spent 9h of training, totaling 81 hours. There were 18 deprecations, due to the the lack of education of the students. The overall average of the grades was 8.8, with lower note zero and higher 10.0. In UTM 158 people were trained in 5 classes, with an average of 31 students per class.It is concluded that in classes with few students (7 to 12) there were few parallel discussions. In classes with many students (over thirty) there was a scattering of ideas, which interfered in the progress of training. As proposal for upcoming classes can be suggested an average 20 people per class. The division of classes in groups working together was beneficial, giving a unit, which allowed greater freedom in questions, increasing parallel content taught. The classes have evaluated positively the initiative of the work done, which will be extended to other units of DRM, and subsequently all of the INB - Brazilian Nuclear Industries

  4. Acquisition, installation and operation of nuclear magnetic resonance equipments

    International Nuclear Information System (INIS)

    The criteria used by CENPES/PETROBRAS (Research Center of PETROBRAS) to acquire NMR spectrometer are presented. The installation and operations of equipments are described. The NMR spectrometer was acquired for carrying out researches on: characterization of petroleum; analysis of catalysts; characterization of polymers; analysis of fossil fuels and observation of chemical reactions. (M.C.K.)

  5. International Co-operation in providing insurance cover for nuclear damage to third parties and for damage to nuclear installations

    International Nuclear Information System (INIS)

    This article in three parts analyses cover for damage to third parties by fixed nuclear installations, cover for damage to third parties during transport of nuclear substances and finally, cover for damage to nuclear installations. Part I reviews the principles of nuclear third party liability and describes nuclear insurance pools, the coverage and contracts provided. Part II describes inter alia the role of pools in transport operations as well as the type of contracts available, while Part III discusses material damage, the pools' capacities and the vast sums involved in indemnifying such damage. (NEA)

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

    International Nuclear Information System (INIS)

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

  7. Safety management at nuclear installations with research reactors. A comparison of five European installations

    International Nuclear Information System (INIS)

    Five European institutions with nuclear research reactors were visited to compare safety management among institutions similar to Risoe. Risoe is a National Laboratory and the main activities are research and development. In 1996 it was decided to look into safety management at Risoe again; the last revision was in 1972. The purpose was to make it more efficient and to emphasise, that the responsibility lies in the operating organisation. Information such as nuclear facilities at the institutions, the safety management organisation, emergency preparedness, and lists of radiation doses to the employees from the years 1995 and 1996 is given in the report. Also international requirements and recommendations are given in short. Furthermore the report contains some reflections on the development in safety management organisations in resent years and the conclusions drawn from the information gathered

  8. 78 FR 61401 - Entergy Nuclear Operations, Inc.; Big Rock Point; Independent Spent Fuel Storage Installation

    Science.gov (United States)

    2013-10-03

    ... COMMISSION Entergy Nuclear Operations, Inc.; Big Rock Point; Independent Spent Fuel Storage Installation..., Inc. (ENO) on June 20, 2012, for the Big Rock Point (BRP) Independent Spent Fuel Storage Installation... Regulatory Evaluation In the Final Rule for Storage of Spent Fuel in NRC-Approved Storage Casks at...

  9. Decree 2869/1972 of 21 July approving the Regulations on nuclear and radioactive installations

    International Nuclear Information System (INIS)

    This Decree determines nuclear and radioactive installations and establishes their licensing system which is carried out in several stages and differs according to the category concerned. The procedures cover in particular prior authorization, construction licence and operating licence. Provision is also made for inspections. The Annex to the Decree classifies the radionuclides for determining the category of the installation. (NEA)

  10. Cancer risks near nuclear installations?; Risque de cancer a proximite d'installations nucleaires?

    Energy Technology Data Exchange (ETDEWEB)

    Hubert, D. [Electricite de France (EDF), 75 - Paris (France). Service General de Radioprotection

    1999-07-01

    The descriptive studies actually at disposal bring to the fore some children leukemia aggregates around some nuclear sites. (Sellafield, and Dounreay in the United kingdom, Kruemmel in Germany). Nevertheless, the studies grouping several sites do not find any global excess. The analytical studies have not brought any answer until now, but have allowed to eliminate some hypothesis such the Gardner genetic hypothesis. (N.C.)

  11. Statutory Instrument No. 2056, The Nuclear Installations Act 1965 etc. (Repeals and Modifications) Regulations 1974

    International Nuclear Information System (INIS)

    These Regulations contain repeals and modifications of provisions of the Nuclear Installations Act 1965 and a modification of the Nuclear Installations (Dangerous Occurrences) Regulations 1965. They are made in consequence of the establishment on 1st January 1975 of the Health and Safety Executive and the coming into operation on that date of provisions of the Health and Safety at Work etc. Act 1974 which supersede or affect provisions of the 1965 Act and the 1965 Regulations. (NEA)

  12. Liability for injury to the unborn - Recent amendments to the United Kingdom Nuclear Installations Act

    International Nuclear Information System (INIS)

    The adoption in the United Kingdom in 1976 of an Act to determine liability for injury to the unborn (foetus) has provided the opportunity to amend the Nuclear Installations Act which governs the liability of nuclear operators, which is now extended to such injury. Any 'injury' attributable to a nuclear operator which so affects a mother that her child is born disabled involves the liability of that operator within the meaning of the Nuclear Installations Act whether or not either parent has suffered an injury on that occasion. (NEA)

  13. Control of the safety and security of nuclear installations

    International Nuclear Information System (INIS)

    This work has two parts: the first one, composed by these two volumes is prospective; it is an analysis of scientific stacks of safety and economy of the French-German nuclear pressurized type reactor project (E.P.R.) and destined to replace the actual nuclear power plants from 2010. The second part, that will take two volumes, will take stock of the 118 recommends presented in the seven previous reports in the field of safety of nuclear facilities. It will allow to identify the areas that are in evolution and the areas that stagnate. (N.C.)

  14. The Perspective of Small and Medium Size Nuclear Power Reactors in the Brazilian Isolated Electricity Grids

    International Nuclear Information System (INIS)

    As a consequence of the international crisis that has shaken the nuclear industry almost all over the world during the late 1980s, new academic contributions, which could settle a new basis for the nuclear energy in Brazil, have been scarce. This paper aims to partially fulfill this gap. We discuss some perspectives for the nuclear option to regain some prominence in the Brazilian energy matrix. Recent developments in the nuclear industry, including advances in plant design, have been opening interesting markets for small and medium nuclear power reactors (SMNPRs). We access the suitability and feasibility of such new technology in the Brazilian isolated electricity grids. We conclude by saying that, although the difficulties are still huge, SMNPRs may be a good strategy for Brazil to revitalize its nuclear policy. (author)

  15. Planned reliability in the transport and installation of large nuclear components

    International Nuclear Information System (INIS)

    The transport and installation of heavy and bulky large components require detailed planning of all jobs and activities, trained and experienced personnel and corresponding technical equipment for reliable and quality-assured implementation. The correct approach to the planning and implementation of such transports and installations has been confirmed by years of successful performance of these jobs e.g. in reactor pressure vessels and steam generators for nuclear power plants. Large components for nuclear power plants are truly extreme examples but will be all the better suited for demonstrating the problems inherent in transport and installation. (orig.)

  16. An installation for detecting the position of the control rods in a nuclear reactor

    International Nuclear Information System (INIS)

    Description is given of a digitally controlled installation for detecting the position of the control rods of a nuclear reactor. The installation is characterized in that it comprises a magnetic element providing a portion of a driving rod, a plurality of spaced Hall effect transducers distributed in pairs along an axis parallel with the axis of the casing of the driving rods, in the vicinity of the casing outer periphery, and means adapted to receive the output signals of the various transducers for providing an indication of the position of each control rod in the reactor vessel. That installation can be applied to pressurized water nuclear reactors

  17. What about risk associated with chemical releases of nuclear installations?

    International Nuclear Information System (INIS)

    The French authority for nuclear safety requests the French institute of radiation protection (IRSN) to perform impacts assessment for the chemical discharges from nuclear facilities in the context of licensing operator. To carry out its mission, IRSN developed assessment methods and a computer tool named CALIES (CALcul d'Impact Environnemental et Sanitaire des rejets d'effluents chimiques liquides et gazeux - Risk assessment for environment and population). (author)

  18. Site release in the decommissioning of nuclear installations

    International Nuclear Information System (INIS)

    Spanish regulatory framework for the decommissioning process of a nuclear facility ends up with a decommission statement, which releases the licence-holder of the facility from its responsibilities as an operator. It also establishes -where a restricted site release applies- the appropriate future use restrictions, and the responsible of both maintaining such restrictions and ensuring their compliance. Releasing a site implies eliminating all radiological monitoring. The Regulations, however, did not specify either the radiological conditions to be met for the site to be released, or the possibility of a partial release -with or without restrictions-. In case of restricted site release, the Regulations did not specify either the required criteria for such a release. This paper presents the main features of the Safety Instruction IS-13 'Radiological criteria for the release of nuclear facilities sites' issued recently by the Spanish Nuclear Safety Council as a new specific regulation. This Safety Instruction establishes the requirements and conditions for the release of nuclear facility sites, that is, radiological criteria on the effective dose to the public, partial release of nuclear facility sites and restricted release of nuclear facility sites. (author).

  19. Site release in the decommissioning of nuclear installations

    International Nuclear Information System (INIS)

    Spanish regulatory framework for the decommissioning process of a nuclear facility ends up with a decommission statement, which releases the licence-holder of the facility from its responsibilities as an operator. It also establishes -where a restricted site release applies- the appropriate future use restrictions, and the responsible of both maintaining such restrictions and ensuring their compliance. Releasing a site implies eliminating all radiological monitoring. The Regulations, however, did not specify either the radiological conditions to be met for the site to be released, or the possibility of a partial release -with or without restrictions-. In case of restricted site release, the Regulations did not specify either the required criteria for such a release. This paper presents the main features of the Safety Instruction IS-13 'Radiological criteria for the release of Nuclear Facilities Sites' issued recently by the Spanish Nuclear Safety Council as a new specific regulation. This Safety Instruction establishes the requirements and conditions for the release of nuclear facility sites, that is, radiological criteria on the effective dose to the public, partial release of nuclear facility sites and restricted release of nuclear facility sites. (author)

  20. Peculiarities of physical protection assurance of the nuclear materials at nuclear installation decommissioning stage

    International Nuclear Information System (INIS)

    On December 15, 2000 Unit 3 of Chernobyl NPP, which is the last one in Ukraine having RBMK-type reactor, was permanently shutdown before the end of its lifetime. A number of projects related to establishing infrastructure for the plant decommissioning are being implemented in compliance with the Ukraine's commitments. Decommissioning stage includes activities on fuel unloading from the cores of Unit I and Unit 3, fuel cooling in the ponds followed by the fuel transportation to the spent fuel dry storage facility (currently under construction) for its safe long-term storage. Special facilities are being created for liquid and solid radioactive waste treatment. Besides, it is planned to implement a number of projects to convert Shelter Object in environmentally safe structure. Physical protection work being an essential part of the nuclear material management is organized in line with the recommendations of the IAEA, and the Laws of Ukraine 'On Nuclear Energy Utilization and Radiation Safety', 'On Physical Protection of Nuclear Installations and Materials', 'Regulations on Physical Protection of Nuclear Materials and Installations', other codes and standards. While organizing physical protection on ChNPP decommissioning stage we have to deal with some specific features, namely: Significant amount of fuel assemblies, which are continuously transferred between various storage and operation facilities; Big amount of odd nuclear material at Shelter Object; 'Theft of new fuel fragments from the central hall of the Shelter Object in 1995 with the intention of their further sale. The thieves were detained and sentenced. The stolen material was withdrawn, that prevented its possible proliferation and illicit trafficking. At present physical protection of ChNPP does not fully satisfy the needs of the decommissioning stage and Ukraine's commitments on non-admission of illicit trafficking. Work is carried out, aimed to improve nuclear material physical protection, whose main

  1. Nuclear Reactor RA Safety Report, Vol. 3, Building and installations

    International Nuclear Information System (INIS)

    RA reactor building is built of concrete and bricks as an enclosed building with limited number of controlled openings, and limited number of doors and windows. It is made of three parts: central; circular annex in the central part; sanitary corridor. The largest part of the RA reactor building is the reactor hall. This volume includes detailed description, figure and diagrams showing building characteristics, power supply systems, water supply systems, ventilation and heating systems, gas and compressed air installation as well as fire prevention system

  2. Handling installation for a fast neutron nuclear reactor

    International Nuclear Information System (INIS)

    The installation comprises inside the reactor vessel, a beam able to rotate unscotch about the vertical axis of the reactor core, a movable trolley on the beam carrying a guide tube. A fixed beam is placed in a handling room above the reactor closure head and fuel causes with another trolley carrying another guide tube. The transfer of an assembly between the core to one of the causes is made by a gripper suspended from a cable wound on a winch placed at the end of the handling room

  3. Politics and engineering in nuclear-energy installations

    International Nuclear Information System (INIS)

    The author gives a summarising report on the 1977 Reactor Conference where the review lectures gave information on the present social-political and polito-economic questions at issue on nuclear energy, such as the attitude of politicians in the democracy; the effects of zero growth and subdivision; indpendence of energy supply due to a national waste-disposal centre, and adaption of the economy to the changing requirements of the people. By statements on leasing and export finance, the necessity for state promotion and international cooperation in building up a reactor industry, as well as transfer of nuclear technology, he demonstrates the interlinking between political economy and the nuclear industry. He also reports on the state of the work in Germany on studying risks from nuclear power stations having pressure-water reactors; ensuring reliability of output and of the system; the tightening of high-temperature reactor development; the competitive position of nuclear energy, and the energy research programme in the Federal Republic of Germany. (orig.)

  4. Decommissioning Licensing Process of Nuclear Installations in Spain

    International Nuclear Information System (INIS)

    The Enresa experience related to the decommissioning of nuclear facilities includes the decommissioning of the Vandellos I and Jose Cabrera NPPs. The Vandellos I gas-graphite reactor was decommissioned in about five years (from 1998 to 2003) to what is known as level 2. In February 2010, the decommissioning of Jose Cabrera power plant has been initiated and it is scheduled to be finished by 2018. The decommissioning of a nuclear power plant is a complex administrative process, the procedure for changing from operation to decommissioning is established in the Spanish law. This paper summarizes the legal framework defining the strategies, the main activities and the basic roles of the various agents involved in the decommissioning of nuclear facilities in Spain. It also describes briefly the Licensing documents required to obtain the decommissioning authorization and the Enresa point of view, as licensee, on the licensing decommissioning process. (author)

  5. Current emergency programs for nuclear installations in Japan

    International Nuclear Information System (INIS)

    Large effort has been taken for nuclear emergency programs in Japan especially after the JCO accident. A special law for nuclear emergency was established after the accident. The law extended the scope of emergency preparedness to fuel cycle facilities, research reactors, etc. and clarified the roles and responsibilities of the national government, local governments and license holders. For initial responses, the action levels and action procedures are defined based on environmental doses and specific initial events of NPPs. A senior specialist was dispatched to each site for nuclear emergency and a facility 'Off-site center' to be used as the local emergency headquator was designated at each site. This paper describes the structure of emergency program, responsibility of related organizations and the definition of unusual events for notification and emergency. Emergency preparedness, emergency radiation monitoring and computer-based prediction of on- and off-site situation are also addressed. (author)

  6. Social and economic aspects of the decommissioning of nuclear installations

    International Nuclear Information System (INIS)

    Many countries are facing the task of decommissioning and dismantling their commercial nuclear power plants. The three major components of a decommissioning project are the: regulatory framework, including safety regulations; technological developments and the environmental implications; and socioeconomic aspects.The first two have global, national, regional and local dimensions, but the socioeconomic impact is restricted to local environment, affecting mainly the local communities living around a nuclear power plant.These plants contribute, during their construction and operation, to the social and economic development of the region around the sites; the shut down of the reactor and decommissioning of the nuclear power plant facilities will have negative consequences on the life and economy of the local communities. The type of socioeconomic impact varies according to the phase of the dismantling project: (a) the transition period; (b) preparation for safe enclosure; (c) safe enclosure; and (d) final dismantling. Among the issues of concern are: (1) the negative impact on the local demography, resulting in a decrease in the population; (2) decrease of economic activity in the area; (3) loss of jobs (unemployment, anticipated retirement); and (4) reduction in local incomes. Additionally, success in decommissioning nuclear facilities is linked to the ability to demonstrate that the actions taken, both by the licensee and the nuclear regulatory authority, are protective of public health and the environment. Therefore, it is important to stress the need to build public confidence as a key component of the decommissioning effort. The paper analyses the socioeconomic impacts on the local communities around the site and proposes some practical recommendations to mitigate the negative socioeconomic consequences of a decommissioning project from a generic perspective. It also offers conclusions and recommendations based on the experience and information gathered on the

  7. A new environmental measuring programme for the Hanau nuclear installations

    International Nuclear Information System (INIS)

    Since 1980, the site of the Hanau nuclear enterprises has been subject to a radiological monitoring programme. The measured results and the experience gained so far have been taken as a basis for a revision of this programme. The revision was intended to finally yield a programme which satisfies the principle requirements of the currently applicable directive for radiological monitoring and which in terms of procedure and formal aspects is as close as possible to the pattern applied to nuclear power plants. The measured results are listed in detail. (orig./DG)

  8. Fatigue damage of nuclear facilities; Endommagement par fatigue des installations nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-07-01

    The conference on the fatigue damage of nuclear facilities, organized by the SFEN (french society of nuclear energy), took place at Paris the 23. of november 2000. Eleven papers were presented, showing the state of the art and the research programs in the domain of the sizing rules, safety, installations damage, examination and maintenance. (A.L.B.)

  9. Strategic Considerations for the Sustainable Remediation of Nuclear Installations

    International Nuclear Information System (INIS)

    Nuclear sites around the world are being decommissioned and remedial actions are being undertaken to enable sites, or parts of sites, to be reused. Although such activities are relatively straightforward for most sites, experience has suggested that preventative action is needed to minimise the impact of remediation activities on the environment and the potential burden to future generations. Removing all contamination in order to make a site suitable for any use generates waste and has associated environmental, social and economic drawbacks and benefits. Site remediation should thus be sustainable and result in an overall net benefit. This report draws on recent experience of NEA member countries in nuclear site remediation during decommissioning in order to identify strategic considerations for the sustainable remediation of subsurface contamination - predominantly contaminated soil and groundwater - to describe good practice, and to make recommendations for further research and development. It provides insights for the decision makers, regulators, implementers and stakeholders involved in nuclear site decommissioning so as to ensure the sustainable remediation of nuclear sites, now and in the future. (authors)

  10. Off-site emergency plan for nuclear installations

    International Nuclear Information System (INIS)

    This safety manual lays down the regulatory requirements on behalf of the site management for establishment and implementation of their response to radiological emergencies in Indian nuclear power plants and toxicity related emergencies in Indian heavy water production plants, where such emergencies have potential for affecting safety of the population near the site. (original). 5 appendices, tabs., 4 figs

  11. Licensing systems and inspection of nuclear installations 1991

    International Nuclear Information System (INIS)

    This revised and updated study provides a description of the nuclear licensing regulations and practices applied in OECD countries with specific provisions in that field. The national systems have been described according to a standard format to facilitate comparisons and research. In most cases, the descriptions are supplemented by flow charts illustrating the procedures and specifying the different authorities involved

  12. Reliability of fossil-fuel and nuclear power installations

    International Nuclear Information System (INIS)

    The conference heard a total of 37 papers of which 24 were inputted in INIS. The subject area was mainly the use of reliability information systems and the production of data banks for these systems, the application of the reliability theory and the reliability analysis of equipment and systems of nuclear power plants. (J.P.)

  13. Regulatory Oversight for Ageing Management of Nuclear Research Installations in the Russian Federation

    International Nuclear Information System (INIS)

    Rostechnadzor reviews reports of the operating organizations on notifiable events and their annual reports on the status of nuclear and radiation safety at nuclear research installations, which contain data on the conditions of the SSCs important to safety. The evaluation of outcomes is being used by Rostechnadzor for methodical oversight of nuclear research installation safety, including control of efficiency of ageing management programmes in operating organizations. The results of the evaluation of notifiable events in 2010 regarding ageing are given in the paper. The events were classified in terms of type of ageing and item of concern. (author)

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

    International Nuclear Information System (INIS)

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

  15. Nuclear installations in Slovakia accords to the convention definition

    International Nuclear Information System (INIS)

    In this part the nuclear power plants Bohunice - Units V-1 and V-2 and NPP Mochovce (description of units, safety reports and safety improvement programs) are described. Description of Bohunice A-1, history and current status of the NPP A-1 and NPP decommissioning program are included. In next parts interim spent fuel storage, technologies of Raw processing and treatment, and treated and solid Raw storage sites are described

  16. The protection of nuclear installations from outside aggressions

    International Nuclear Information System (INIS)

    When selecting a site for a nuclear power station, the possibility of outside natural aggressions from atmospheric, hydrologic or seismic origin should be carefully considered. The site being chosen, outside natural or non-natural aggressions which are linked to it, such as plane crashes, projectiles, fires, bursting of dams, deliberate human aggressions... should be thoroughly appraised to take them into account when designing the future plant

  17. Seismic risk and safety of nuclear installations. A look at the Cadarache Centre; Risque sismique et surete des installations nucleaires. Regards sur le Centre de Cadarache

    Energy Technology Data Exchange (ETDEWEB)

    Verrhiest-Leblanc, G.; Chevallier, A. [Autorite de Surete Nucleaire 75 - Paris (France)

    2010-11-15

    After a brief recall of some important seismic events which occurred in the past in the south-eastern part of France, the authors indicate the nuclear installations present in this region. They outline the difference between requirements for a usual building and for basic nuclear installations. They indicate laws and regulations which are to be applied to these installations like to any hazardous industrial installation. They describe the seismic risk as it has been determined for the Cadarache area, and evoke the para-seismic design of new nuclear installations which are to be built in Cadarache and actions for a para-seismic reinforcement of existing constructions. Finally, they evoke organisational aspects (emergency plans) and the approach for a better information and transparency about the seismic risk

  18. Comparison of the activity measurements in nuclear medicine services in the Brazilian northeast region

    International Nuclear Information System (INIS)

    The Northeastern Regional Centre for Nuclear Sciences (CRCN-NE), National Nuclear Energy Commission, has organized for the first time in nuclear medicine services (NMSs) in the Brazilian northeast region a comparison of activity measurements for 99mTc, 131I, 67Ga, 201Tl and 57Co. This tool is widely utilized to evaluate not only the accuracy of radionuclide calibrators, but also the competence of NMSs to measure the activity of the radiopharmaceuticals and the performance of the personnel involved in these measurements. The comparison results showed that 90% of the results received from participants are within the ±10% limit established by the Brazilian Norm. - Highlights: • Establishing a comparison program of activity measurements was an important tool to guarantee the satisfactory performance of radionuclide calibrators in the Brazilian northeast region. • In this program 121 measurements performed in the nuclear medicine services of Alagoas, Paraíba, Pernambuco, Piauí, Rio Grande do Norte and Sergipe States were obtained. • The analysis of the results demonstrated that 90% of the results received from participants are within the ±10% limit established by the Brazilian Norm. • The services whose results were outside the recommended limits can be supported the Reference Laboratory in order to identify and to correct eventual unacceptable results

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

    International Nuclear Information System (INIS)

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

  20. Internationally Standardized Cost Item Definitions for Decommissioning of Nuclear Installations

    International Nuclear Information System (INIS)

    The European Commission (EC), the International Atomic Energy Agency (IAEA), and the Organization for Economic Cooperation and Development/Nuclear Energy Agency (OECD/NEA) have agreed to jointly prepare and publish a standardized list of cost items and related definitions for decommissioning projects. Such a standardized list would facilitate communication, promote uniformity, and avoid inconsistency or contradiction of results or conclusions of cost evaluations for decommissioning projects carried out for specific purposes by different groups. Additionally, a standardized structure would also be a useful tool for more effective cost management. This paper describes actual work and result thus far

  1. Installation method for the steel container and vessel of the nuclear heating reactor

    International Nuclear Information System (INIS)

    The Nuclear Heating Reactor (NHR) has the advantages of inherent safety and better economics, integrated arrangement, full power natural circulation and dual vessel structure. However, the large thin container presents a new and difficult problem. The characteristics of the dual vessel installation method are analyzed with system engineering theory. Since there is no foreign or domestic experience, a new method was developed for the dual vessel installation for the 5 MW NHR. The result shows that the installation method is safe and reliable. The research on the dual vessel installation method has important significance for the design, manufacture and installation of the NHR dual vessel, as well as the industrialization and standardization of the NHR

  2. Portfolio of patents after the Brazilian Innovation Act: the case of the Comissao Nacional de Energia Nuclear - CNEN (Brazilian National Nuclear Energy Commission)

    Energy Technology Data Exchange (ETDEWEB)

    Pereira, Gustavo Jose; Guimaraes, Regia Ruth Ramirez; Perry, Katia da Silva Peixoto, E-mail: pereira@cdtn.br, E-mail: rrrg@cdtn.br, E-mail: kspp@cdtn.br [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil); Teruya, Dirceu Yoshikazu, E-mail: teruya@inpi.gov.br [Instituto Nacional da Propriedade Industrial (INPI), Rio de Janeiro, RJ (Brazil)

    2013-07-01

    The process of technological development is due to the need to promote a solution to a particular problem of agents, compete with products and/or processes on the international market and to promote scientific advancement. Thus, the patent system is a repository of knowledge for protection, for promotion of diffusion through licensing agreements and an indicator of technological development. In 2004, the Brazilian Government enacted the Brazilian Innovation Act and the mechanisms were improved for cooperation between firms and public education, science and technology organisations and also promoted the commercialisation of technology produced by public education, science and technology organisations and the mandatory establishment of Technology Transfer Offices. The Comissao Nacional de Energia Nuclear (CNEN) is a federal agency responsible for basic and applied research in the field of nuclear technology and has used the patent system since the 1980s to protect its knowledge. With the advent of the Innovation Act in 2004, there was a significant boost in requests for patents in CNEN which also established an internal set of normative acts and created a System of Innovation Management and Technology Innovation Offices in its research institutes to support management and dissemination of knowledge. The aim of this case study is to present the profile of the requests for patents by CNEN before and after the enactment of the Brazilian Innovation Act covering the period of time between 1980 and 2010. (author)

  3. Portfolio of patents after the Brazilian Innovation Act: the case of the Comissao Nacional de Energia Nuclear - CNEN (Brazilian National Nuclear Energy Commission)

    International Nuclear Information System (INIS)

    The process of technological development is due to the need to promote a solution to a particular problem of agents, compete with products and/or processes on the international market and to promote scientific advancement. Thus, the patent system is a repository of knowledge for protection, for promotion of diffusion through licensing agreements and an indicator of technological development. In 2004, the Brazilian Government enacted the Brazilian Innovation Act and the mechanisms were improved for cooperation between firms and public education, science and technology organisations and also promoted the commercialisation of technology produced by public education, science and technology organisations and the mandatory establishment of Technology Transfer Offices. The Comissao Nacional de Energia Nuclear (CNEN) is a federal agency responsible for basic and applied research in the field of nuclear technology and has used the patent system since the 1980s to protect its knowledge. With the advent of the Innovation Act in 2004, there was a significant boost in requests for patents in CNEN which also established an internal set of normative acts and created a System of Innovation Management and Technology Innovation Offices in its research institutes to support management and dissemination of knowledge. The aim of this case study is to present the profile of the requests for patents by CNEN before and after the enactment of the Brazilian Innovation Act covering the period of time between 1980 and 2010. (author)

  4. The directive establishing a community framework for the nuclear safety of nuclear installations: the European Union approach to nuclear safety

    International Nuclear Information System (INIS)

    This article aims at explaining the evolution leading to the adoption of the recent Council Directive 2009/71/EURATOM establishing a Community framework for the nuclear safety of nuclear installations adopted with the consent of all 27 members states following the overwhelming support of the European Parliament, that creates for the first time, a binding legal framework that brings legal certainty to European Union citizens and reinforces the role and independence of national regulators. The paper is divided into three sections. The first section addresses the competence of the European Atomic energy Community to legislate in the area of nuclear safety. It focuses on the 2002 landmark ruling of the European Court of justice that confirmed this competence by recognizing the intrinsic link between radiation protection and nuclear safety. The second part describes the history of the Nuclear safety directive from the initial 2003 European Commission proposal to today 's text in force. The third part is dedicated to a description of the content of the Directive and its implications on the further development of nuclear safety in the European Union. (N.C.)

  5. Experience of a Brazilian A/E in seismic analysis of nuclear structures components

    International Nuclear Information System (INIS)

    The experience of Promon Engenharia S.A., a Brazilian A/E which participated in the civil and mechanical engineering projects of the first Nuclear Power Plant in Brazil, is presented. In these projects the aspects of input for seismic analysis, seismic analysis in nuclear structures founded on piles, dynamic analysis for airplane crash, and piping analysis had to be faced for the first time in the country. The solution of these problems and some case examples are presented. (Author)

  6. Research on artificial intelligence systems for nuclear installations

    International Nuclear Information System (INIS)

    The development and utilization of atomic energy in Japan has be advanced in conformity with the long term plan of atomic energy development and utilization decided in 1987. As one of the basic targets, the upbringing of creative and innovative science and technology is put up. Artificial intelligence technology has been positioned as one of the important basic technologies for promoting future atomic energy development. The research and development of artificial intelligence technology have been advanced aiming at making nuclear power stations autonomous, by the guidance of Science and Technology Agency and the cooperation of several research institutes. The upbringing of creative science and technology, the preponderant development of basic technology, the concept of developing the basic technology for atomic energy, the concept of autonomous plants, the standard for autonomy, the approach to autonomous plants, the present state of the researches in respective research institutes on autonomous operation and autonomous maintenance are described. (K.I.)

  7. Chavir: Virtual reality simulation for interventions in nuclear installations

    International Nuclear Information System (INIS)

    Companies involved in the nuclear industry have to prepare for interventions by precisely analyzing the radiological risks and rapidly evaluating the consequences of their operational choices. They also need to consolidate the experiences gained in the field with greater responsiveness and lower costs. This paper brings out the advantages of using virtual reality technology to meet the demands in the industry. The CHAVIR software allows the operators to prepare (and repeat) all the operations they would have to do in a safe virtual world, before performing the actual work inside the facilities. Since the decommissioning or maintenance work is carried out in an environment where there is radiation, the amount of radiation that the operator would be exposed to is calculated and integrated into the simulator. (authors)

  8. International conference on safety culture in nuclear installations. Contributed papers

    International Nuclear Information System (INIS)

    Safety culture is that assembly of characteristics and attitudes in organisation and individuals which establishes that as an overriding priority nuclear plant safety issues receives the attention warranted by their significance. This definition of safety culture brings out two major components in its manifestation. The framework within which individuals within the organisation works.The attitude and response of individual towards the safety issues over productivity and economics in the organisational work practices. The industry literature provides a great deal of insight at the artefact and espoused value levels, although as yet it remains somewhat disorganized. There is, however, an overall lack of understanding of the assumption level of safety culture. The IAEA has organised the conference on safety culture for better understanding of the safety culture issues on the international level

  9. Improvement of radioiodine filters installed in nuclear power plants

    International Nuclear Information System (INIS)

    A method had to be developed allowing to extend the authorized service life of iodine sorption filters. After the qualitative and quantitative assessment of filter pollutants in the exhaust air of a PWR safety containment the investigations concentrated on the adsorption of the poltutants through additional activated carbon, if applicable provided as a guard bed, and on the possibility of pollutant desorption with hot air as the sweeping gas. Only pollutant absorption proved to be a method to be applied with success in nuclear power stations. Due to the difficulties arising in the storage or disposal of contaminated activated carbon, the consumption of activated carbon is of decisive importance for the safe adherence to a given minimum removal efficiency. A special filter type was developed with a view to reduce the consumption af activated carbon and the removal efficiency obtained was compared with that of a conventional deep bed filter on the basis of similar carbon consumption (tests with model filters). (orig.)

  10. Legal requirements concerning the technical safety of nuclear installations

    International Nuclear Information System (INIS)

    A short survey on nuclear risks and the nuclear safety conception is followed by the attempted clear definition of the semantic import of section 7, sub-section (2), No. 3 of the Atomic Energy Act. There are first beginnings of a concretization of the state-of-the-art in science and technology, i.e. all kinds of sub-legislative regulations such as the regulations of the Radiation Protection Ordinance which show scientific substance, guidelines issued by the Ministers, as well as codes for practice set up by various technical bodies and standardization associations, all of which are designed to compensate for this loop hole in the legislation. This study goes to examine to what extent administration and jurisdiction may take into account such codes of practice for the concretization of the legal requirements, and whether they are even binding on those executing the law. Only the respective regulations of the Radiation Protection Ordinance have a binding effect. All other guidelines and codes of practice are not legally binding per se, nor are they capable of being legally permitted by being referred to in terms of legal norms or by the self-commitment of those executing the law. Any attempt of using them, as the basis of a prime facie evidence or as an anticipating expertise, at least evidentarily for the concretization will have to fail owing to their evaluating character and to the fact that they may interfere in sociological conflict. An exception may be a case where a clear distinction can be made as to what extent the contents of such codes of practice is related to scientific and technological findings or to decisions based on evaluations. In such a case, a prima facil evicdence for the conformity of the regulation in question with the state-of-the-art in science and technology may be considered, which would easy the concretization of Art. 7 II Section 3 of the Atomic Law. (orig./HSCH)

  11. Safety culture in nuclear installations. A society-driven issue

    International Nuclear Information System (INIS)

    Ever since safety culture was first named by INSAG as an assembly of characteristics and attitudes in organisations and individuals that establish an overriding priority of nuclearpowerplant safety issues, there has been a continuous process of elaborating the terminology, its meaningfulness and applicability in different cases. There have been a number of attempts to analyse the etymology of the expression safety culture but the one offered here gives the possibility to make several very interesting conclusions. In most of the important dictionaries' safety has been described as a state of being free from danger or as a condition of being safe from causing or suffering hurt injury or loss. There are different approaches in determining culture, but two of them may be very useful for this case: culture can be looked upon as the expression of the intellectual development in the society or the socially transmitted pattern of human behaviour that includes thought, speech, action, institutions and man-made objects. If we try to apply this type of approach when assesing the operation of the nuclear power plants in Eastern Europe and former Soviet Union, many interesting conclusions can be drawn, which may somewhat differ from the initially made statements, as they started to appear in 1991 and later on, after caring out the first safety review missions by IAEA and others. On the other hand one can also find a reasonable explanation of the deterioration of safety again applying this type of approach. In the paper, these problems are discussed on the example of the Kozloduy nuclear power plant and the situation in Bulgaria. (author)

  12. Inventory of chemical releases of nuclear installations in the North-Cotentin

    International Nuclear Information System (INIS)

    The nuclear installations concerned by this study are Cogema La Hague, the Flamanville nuclear power plant, the Manche plant and the National Navy of Cherbourg.The objective followed by the ' source term ' work group has consisted in counting and examining the whole of existing measures relative to the releases of chemical substances in the liquid and gaseous effluents. Then because of the lack of measures for the operation first years of installations, the work group has estimated the order of magnitude of these chemical releases (essentially for Cogema La Hague). This report presents a review of the literature looking at the background levels of chemicals in different environmental compartments: air, soil, plants and animals products. these values have been summarized here to be available for comparisons with concentrations input by the North Cotentin nuclear installations, calculated by the G.R.N.C. (radioecology group of Nord Cotentin)

  13. The Nuclear Installations Act 1965 etc. (Repeals and Modifications) Regulations 1974, Statutory Instrument 1974 No. 2056

    International Nuclear Information System (INIS)

    Regulations which came into force on 1st January 1975 repeal and modify certain of the provisions of the 1965 Act and of the Nuclear Installations (Dangerous Occurrences) Regulations 1965; they follow from the establishment of the Health and Safety Executive and the entry into force of provisions of the Health and Safety at Work etc. Act 1974 which affect or supersede provisions of the 1965 Act and the 1965 Regulations. The purpose of this amendment is to transfer the functions under the 1965 Act, connected with the licensing of nuclear installations, from the Secretary of State for Energy to the Health and Safety Executive, and to transfer the functions of inspectors of nuclear installations appointed by the Secretary of State under the 1965 Act to inspectors henceforth appointed by the Health and Safety Executive. (NEA)

  14. Accountability and non-proliferation nuclear regime: a review of the mutual surveillance Brazilian-Argentine model for nuclear safeguards

    International Nuclear Information System (INIS)

    The regimes of accountability, the organizations of global governance and institutional arrangements of global governance of nuclear non-proliferation and of Mutual Vigilance Brazilian-Argentine of Nuclear Safeguards are the subject of research. The starting point is the importance of the institutional model of global governance for the effective control of non-proliferation of nuclear weapons. In this context, the research investigates how to structure the current arrangements of the international nuclear non-proliferation and what is the performance of model Mutual Vigilance Brazilian-Argentine of Nuclear Safeguards in relation to accountability regimes of global governance. For that, was searched the current literature of three theoretical dimensions: accountability, global governance and global governance organizations. In relation to the research method was used the case study and the treatment technique of data the analysis of content. The results allowed: to establish an evaluation model based on accountability mechanisms; to assess how behaves the model Mutual Vigilance Brazilian-Argentine Nuclear Safeguards front of the proposed accountability regime; and to measure the degree to which regional arrangements that work with systems of global governance can strengthen these international systems. (author)

  15. The Role of BAPETEN in Fostering Safety Culture Implementation at Nuclear Installations

    International Nuclear Information System (INIS)

    BAPETEN is the Regulatory Body in the field of nuclear energy in Indonesia to perform regulatory function through regulation, licensing, inspection and enforcement. In discussing the role of BAPETEN in fostering safety culture implementation, we must keep in mind that the operator has the prime responsibility for safely operating the nuclear facility, the regulator has the responsibility for independently assuring that nuclear plants are operated safely. In order to fulfill the commitment in fostering nuclear safety culture implementation in nuclear installation, BAPETEN strives for strict nuclear regulations through the development of clear safety regulatory practices. Some nuclear safety regulation and technical document has already put the safety culture consideration. BAPETEN performs several activities regarding to encourage and improve the awareness among the users of nuclear energy in implementing safety culture. In promoting safety culture, BAPETEN set a good example in its own performance and regulatory principles base on BAPETEN Management System. (author)

  16. Verification Problems of Nuclear Installations Safety Software of Strength Analysis (NISS SA)

    International Nuclear Information System (INIS)

    The use of software in Ukraine for strength analysis of nuclear installation systems end elements is nowadays rather limited in connection to the absence of a uniform concept of their verification and application and complexity of methodological guides. Creation of a methodology of certification is given large importance with numerical researches allowing to establish estimation reliability criterions, common for all nuclear installation safety software for strength analysis (NISS SA). Two examples of such researches are given: dependence convergence of FEM-decision on number of freedom degrees of discrete models; influence of the creation of FEM equation methods on character of decisions convergence

  17. Childhood leukaemia incidence around French nuclear installations using geographic zoning based on gaseous discharge dose estimates.

    OpenAIRE

    Evrard, Anne-Sophie; Hémon, Denis; Morin, Aline; Laurier, Dominique; Tirmarche, Margot; Backe, Jean-Claude; Chartier, Michel; Clavel, Jacqueline

    2006-01-01

    The present study investigated for the first time the incidence of childhood leukaemia (1990–2001) around French nuclear installations using a geographic zoning based on estimated doses to the red bone marrow due to gaseous radioactive discharges. The observed number of cases of acute leukaemia (O=750) in 40 km2 centred on 23 French nuclear installations between 1990 and 2001 was lower than expected (E=795.01), although not significantly so (standardised incidence ratio SIR=0.94, 95% confiden...

  18. MODELING ATMOSPHERIC RELEASES OF TRITIUM FROM NUCLEAR INSTALLATIONS

    Energy Technology Data Exchange (ETDEWEB)

    Okula, K

    2007-01-17

    Tritium source term analysis and the subsequent dispersion and consequence analyses supporting the safety documentation of Department of Energy nuclear facilities are especially sensitive to the applied software analysis methodology, input data and user assumptions. Three sequential areas in tritium accident analysis are examined in this study to illustrate where the analyst should exercise caution. Included are: (1) the development of a tritium oxide source term; (2) use of a full tritium dispersion model based on site-specific information to determine an appropriate deposition scaling factor for use in more simplified, broader modeling, and (3) derivation of a special tritium compound (STC) dose conversion factor for consequence analysis, consistent with the nature of the originating source material. It is recommended that unless supporting, defensible evidence is available to the contrary, the tritium release analyses should assume tritium oxide as the species released (or chemically transformed under accident's environment). Important exceptions include STC situations and laboratory-scale releases of hydrogen gas. In the modeling of the environmental transport, a full phenomenology model suggests that a deposition velocity of 0.5 cm/s is an appropriate value for environmental features of the Savannah River Site. This value is bounding for certain situations but non-conservative compared to the full model in others. Care should be exercised in choosing other factors such as the exposure time and the resuspension factor.

  19. Radiation protection and safety of nuclear installations - Interface problems

    International Nuclear Information System (INIS)

    The paper discusses the application of the limitation of risk involved in 'criterion curves', safety goals and reliability criteria as one of the main interfaces between radiation protection and quantitative nuclear safety. Several problems of trade-off are also important areas of interface. Maintenance and inspection are planned with the aim of reducing accidental risk, but can involve increased occupational exposures to radiation. The paper discusses the problem as a case involving exposures and potential exposures, occupational risk and public risk. Other typical trade-offs involve shifting exposures between occupational groups or between workers and the public. These problems of interface are particular cases of decision making, which in radiation protection is typified by the optimization requirement of the system of dose limitation. Difficult conceptual problems are involved in extending the use of optimization to the case of probabilistic exposures. The paper examines these difficulties which become increasingly complicated for low probability-high consequence situations. The use of expectation values becomes invalid in such situations and also the possibility of high doses (beyond the range of stochastic linearity) requires special consideration. Different tools of decision analysis theory are mentioned as possible aids for the application of the optimization requirement. 10 refs

  20. Can Nuclear Installations and Research Centres Adopt Cloud Computing Platform-

    International Nuclear Information System (INIS)

    Cloud Computing is arguably one of the recent and highly significant advances in information technology today. It produces transformative changes in the history of computing and presents many promising technological and economic opportunities. The pay-per-use model, the computing power, abundance of storage, skilled resources, fault tolerance and the economy of scale it offers, provides significant advantages to enterprises to adopt cloud platform for their business needs. However, customers especially those dealing with national security, high end scientific research institutions, critical national infrastructure service providers (like power, water) remain very much reluctant to move their business system to the cloud. One of the main concerns is the question of information security in the cloud and the threat of the unknown. Cloud Service Providers (CSP) indirectly encourages this perception by not letting their customers see what is behind their virtual curtain. Jurisdiction (information assets being stored elsewhere), data duplication, multi-tenancy, virtualisation and decentralized nature of data processing are the default characteristics of cloud computing. Therefore traditional approach of enforcing and implementing security controls remains a big challenge and largely depends upon the service provider. The other biggest challenge and open issue is the ability to perform digital forensic investigations in the cloud in case of security breaches. Traditional approaches to evidence collection and recovery are no longer practical as they rely on unrestricted access to the relevant systems and user data, something that is not available in the cloud model. This continues to fuel high insecurity for the cloud customers. In this paper we analyze the cyber security and digital forensics challenges, issues and opportunities for nuclear facilities to adopt cloud computing. We also discuss the due diligence process and applicable industry best practices which shall be

  1. A diagnostic of the strategy employed for communicating nuclear related information to Brazilian communities around uranium mining areas

    International Nuclear Information System (INIS)

    This paper presents a diagnostic of the strategy used by the Brazilian uranium mining industry to communicate nuclear related information to communities around a mining area. The uranium mining industry in Brazil, which is run by the government, has been concerned with communication issues for quite some time. The need to communicate became more apparent after new mining operations started in the Northern region of Brazil. The fact that the government does not have a clear communication guideline made the operators of the uranium mining industry aware of the increasing demand for establishment of a good relationship with several types of Stake holders as well as employment of personnel with experience in dealing with them. A diagnostic of the current communication situation in Brazil and an analysis of the approaches over the past years was done through interviews with employees of the mining industry and review of institutional communication materials. The results were discussed during a Consultant's Meeting organized by the IAEA 's Seibersdorf Laboratory in October 2007. The output of the meeting included an overview of modern communication strategies used by different countries and a suggestion for new uranium mining operations in developing or under developed countries. The strategy for communicating nuclear related information to Brazilian communities varied according to the influence of different Stake holder groups. One initiative worth mentioning was the creation of a Mobile Nuclear Information Thematic Room, which was installed in several locations. This project was seen as one of the main tools to relate to community. Many Stake holders were identified during the diagnostic phase in preparation for the IAEA 's meeting on communication strategy: children, NGOs (Non Government Organizations), local churches, media and internal Stake holders, among others. An initial evaluation showed that the perception of a neighbouring community regarding an uranium

  2. A diagnostic of the strategy employed for communicating nuclear related information to Brazilian communities around uranium mining areas

    International Nuclear Information System (INIS)

    This paper presents a diagnostic of the strategy used by the Brazilian uranium mining industry to communicate nuclear related information to communities around a mining area. The uranium mining industry in Brazil, which is run by the government, has been concerned with communication issues for quite some time. The need to communicate became more apparent after new mining operations started in the Northern region of Brazil. The fact that the government does not have a clear communication guideline made the operators of the uranium mining industry aware of the increasing demand for establishment of a good relationship with several types of Stakeholders as well as employment of personnel with experience in dealing with them. A diagnostic of the current communication situation in Brazil and an analysis of the approaches over the past years was done through interviews with employees of the mining industry and review of institutional communication materials. The results were discussed during a Consultant's Meeting organized by the IAEA's Seibersdorf Laboratory in October 2007. The output of the meeting included an overview of modern communication strategies used by different countries and a suggestion for new uranium mining operations in developing or under developed countries. The strategy for communicating nuclear related information to Brazilian communities varied according to the influence of different Stakeholder groups. One initiative worth mentioning was the creation of a 'Mobile Nuclear Information Thematic Room', which was installed in several locations. This project was seen as one of the main tools to relate to community. Many Stakeholders were identified during the diagnostic phase in preparation for the IAEA's meeting on communication strategy: children, NGOs (Non Government Organizations), local churches, media, and internal Stakeholders, among others. An initial evaluation showed that the perception of a neighbouring community regarding an uranium mining

  3. Statutory Instrument No. 125, The Nuclear Installations (Falkland Islands and Dependencies) Order 1972

    International Nuclear Information System (INIS)

    This Order extends to the Falkland Islands, with the exceptions, adaptations and modifications specified in the Schedule to the Order, certain provisions of the Nuclear Installations Act 1965, as amended. It is the 1965 Act which implements the provisions of the Paris Convention and the Brussels Supplementary Convention in the United Kingdom. The provisions so extended impose a duty on the nuclear operator to secure that no nuclear occurrence taking place within the territorial limits of the Falkland Islands causes nuclear injury or damage, and relate to the right to compensation for breach of that duty, the bringing and satisfaction of claims and other matters. (NEA)

  4. Statutory Instrument No. 122, The Nuclear Installations (British Solomon Islands Protectorate) Order 1972

    International Nuclear Information System (INIS)

    This Order extends to the British Solomon Islands Protectorate, with the exceptions, adaptations and modificatons specified in the Schedule to the Order, certain provisions of the Nuclear Installations Act 1965, as amended. It is the 1965 Act which implements the provisions of the Paris Convention and the Brussels Supplementary Convention in the United Kingdom. The provisions so extended impose a duty on the nuclear operator to secure that no nuclear occurrence taking place within the territorial limits of the British Solomon Islands Protectorate causes nuclear injury or damage, and relate to the right to compensation for breach of that duty, the bringing and satisfaction of claims and other matters. (NEA)

  5. Statutory Instrument No. 126, The Nuclear Installations (Hong Kong) Order 1972

    International Nuclear Information System (INIS)

    This Order extends to Hong Kong, with the exceptions, adaptations and modifications specified in the Schedule to the Order, certain provisions of the Nuclear Installations Act 1965, as amended. It is the 1965 Act which implements the provisions of the Paris Convention and the Brussels Supplementary Convention in the United Kingdom. The provisions so extended impose a duty on the nuclear operator to secure that no nuclear occurrence taking place within the territorial limits of Hong Kong causes nuclear injury or damage, and relate to the right to compensation for breach of that duty, the bringing and satisfaction of claims and other matters. (NEA)

  6. Statutory Instrument No. 125, The Nuclear Installations (Gilbert and Ellice Islands) Order 1972

    International Nuclear Information System (INIS)

    This Order extends to the Gilbert and Ellice Islands, with the exceptions, adaptations and modifications specified in the Schedule to the Order, certain provisions of the Nuclear Installations Act 1965, as amended. It is the 1965 Act which implements the provisions of the Paris Convention and the Brussels Supplementary Convention in the United Kingdom. The provisions so extended impose a duty on the nuclear operator to secure that no nuclear occurrence taking place within the territorial limits of the Gilbert and Ellice Islands causes nuclear injury or damage, and relate to the right to compensation for breach of that duty, the bringing and satisfaction of claims and other matters. (NEA)

  7. Statutory Instrument No. 123, The Nuclear Installations (Cayman Islands) Order 1972

    International Nuclear Information System (INIS)

    This Order extends to the Cayman Islands, with the exceptions, adaptations and modifications specified in the Schedule to the Order, certain provisions of the Nuclear Installations Act 1965, as amended. It is the 1965 Act which implements the provisions of the Paris Convention and the Brussels Supplementary Convention in the United Kingdom. The provisions so extended impose a duty on the nuclear operator to secure that no nuclear occurrence taking place within the territorial limits of the Cayman Islands causes nuclear injury or damage, and relate to the right to compensation for breach of that duty, the bringing and satisfaction of claims and other matters. (NEA)

  8. The Nuclear Installations (Guernsey) Order 1978 (Statutory Instrument 1528, 24 October 1978)

    International Nuclear Information System (INIS)

    This Order extends to Guernsey, with the exceptions, adaptations and modifications specified in the Schedule to the Order, certain provisions of the Nuclear Installations Act 1965, as amended. It is the 1965 Act which implements the provisions of the Paris Convention and the Brussels Supplementary Convention in the United Kingdom. The provisions so extended impose a duty on the nuclear operator to secure that no nuclear occurrence taking place within the territorial limits of Guernsey causes nuclear injury or damage, and relate to the right to compensation for breach of that duty, the bringing and satisfaction of claims and other matters. (NEA)

  9. Statutory Instrument No. 128, The Nuclear Installations (St. Helena) Order 1972

    International Nuclear Information System (INIS)

    This Order extends to St. Helena with the exceptions, adaptations and modifications specified in the Schedule to the Order, certain provisions of the Nuclear Installations Act 1965, as amended. It is the 1965 Act which implements the provisions of the Paris Convention and the Brussels Supplementary Convention in the United Kingdom. The provisions so extended impose a duty on the nuclear operator to secure that no nuclear occurrence taking place within the territorial limits of St. Helena causes nuclear injury or damage, and relate to the right to compensation for breach of that duty, the bringing and satisfaction of claims and other matters. (NEA)

  10. Management report 2003 CNEN - Brazilian Nuclear Energy Commission

    International Nuclear Information System (INIS)

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

  11. Special safety requirements applied to Brazilian nuclear power plant

    International Nuclear Information System (INIS)

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

  12. Study of energetic balance in uranium cycle and in the nuclear Brazilian program

    International Nuclear Information System (INIS)

    The direct and indirect energetic investments for the construction and maintenance of nuclear power plants as well as for the fuel cycle, were analysed. The existing data in the literature was applied to the brazilian nuclear programme with a special attention to those peculiar aspects, particularly the enrichment process and mining. The energetic investments required by the various systems, using the 626 MW nuclear power stations or the 1240 MW, were determined in function of the brazilian ore with 0.108% of U3O8 and of a mine with a stripping ratio (the ratio of tons of overburden to tons of ore) of 28/1. About the enrichment, two hypothesis were considered for the concentration of 235U in the enrichment plant tails - the tails assay (0.25 and 0.35% of 235U) and for the specific energy consumption per unit of separative work (3.60 and 4.40 MWh/UTS). The fuel cycles with and without recycling of uranium and plutonium were taken in consideration. During the lifetime of the plants and for the various cases considered there is a self-consumption between 10 and 16 percent of the produced energy. The cumulative energy requirements as a function of time, was made for individual plants and for the brazilian nuclear programme as a whole in its actual form (9 nuclear power plants). (E.G.)

  13. 1990 No. 1918. The Nuclear Installations Act 1965 (Repeal and Modifications) Regulations 1990

    International Nuclear Information System (INIS)

    These Regulations entered into force on 31 October 1990. They repeal part of Section (1) of the Nuclear Installations Act 1965 to remove the exemption of the United Kingdom Atomic Energy Authority (UKAEA) from licensing under the Act. The Regulations also amend the 1965 Act to ensure that the UKAEA's duties in respect of the safety of premises it occupies will continue to apply whether or not a nuclear site licence has been granted. (NEA)

  14. Analysis of Leukemia incidence (1997-2007) in vicinity area of a nuclear installation

    International Nuclear Information System (INIS)

    Objective: To investigate the leukemia incidence among residents in the vicinity area of a nuclear installation. Methods: The data were collected by the retrospective survey. Diagnosis is based on the medical records in all the relevant hospitals. The study area was those residential areas within 10 km of radium surrounding the installation. All residents who had lived in the study area for six months and over were recruited into the study group. Results: The survey ascertained 643 newly diagnosed leukemia cases in the study area during 1997 to 2007. The crude rate was 2.51/100000, and its standardized rate to national population structure was 2.53/100000. The incidence rate in the study area was slightly lower than that in the whole city. No increase trend was detected during the period. Conclusions: No significant difference of the leukemia incidence rate was found between the vicinity area of the nuclear installation and the whole city. (authors)

  15. Radiation accidents on human in the nuclear installations and their medical emergency procedures, (1)

    International Nuclear Information System (INIS)

    Present nuclear installations are one of the safest installations among industrial facilities, being equipped with various safety instruments. Since X-ray was discovered in 1895, however, many radiation injuries of various degrees and kinds occurred. Among dangerous nuclides often observed as radioactivity pollutions in nuclear installations, the exposure to β-ray such as 90Sr, 106Ru, 95Zr, 131I, 144Ce, etc, is considered to be serious problems. When they affect wounds or are inhaled into lungs, only symptomatic treatment is practicable at present, and usually nothing can be depended upon, but spontaneous eliminating ability. As the mass inhalation of α nuclides, especially transuranium nuclides, is quite dangerous, the treatment by lung-irrigation now under development is most effective as the emergency treatment. When trans-uranium nuclides were accidentally observed from wounds, they should be eliminated by the injection of chelating agent. (Kobatake, H.)

  16. Safety regulation on emergency response and radiation protection in civilian nuclear installations

    International Nuclear Information System (INIS)

    The NNSA organized continuously a review on the emergency planning of the nuclear installations for the operating organizations GNPS, INET/TU and NPIC, and the regulatory inspection on site emergency response and radiation protection for YNFP, INET/TU: Especially a site inspection on site emergency preparedness including an exercise for the Mingjiang Experimental Reactor of NPIC were implemented in 1996

  17. The Role Of Quality Assurance Program For Safety Operation Of Nuclear Installations

    International Nuclear Information System (INIS)

    Nuclear installations expose potential hazard of radiation, therefore in their construction, operation and maintenance, it is necessary to consider safety aspect, in which the safety requirements which has been determined must be met. One of the requirements that is absolutely needed is quality assurance, which covers arrangement of quality assurance program, organization and administration of the implementation of quality assurance, and supervision. Quality Assurance program is a guideline containing quality policies and basic determination on the realization of activities that effect the quality of equipment's and items used in the operation of nuclear installations in order that the operation of nuclear installation can run safety and in accordance with their design aims and operation limits. Quality Assurance Program includes document control, design control, supply control, control of equipment s and items, operation/process control, inspection and control of equipment test, and control of nonconformance and corrections. General system of nuclear installation operation is equipped with safety and supporting systems. These systems must apply the quality assurance program that cover control of activities in the systems. In the implementation of the quality assurance program, it is necessary to establish procedures, work guidelines/instructions, and quality recording that constitutes documents of quality system 2nd, 3th, and 4th level after the quality assurance program. To ensure the effectivity and to prove whether the realization of the program has been pursuant to the determined requirements, an internal audit must be conducted accordingly

  18. 76 FR 22935 - Calvert Cliffs Nuclear Power Plant, LLC Independent Spent Fuel Storage Installation; Notice of...

    Science.gov (United States)

    2011-04-25

    ... Class C (GTCC) waste and other radioactive materials associated with spent fuel storage at the CCNPP... granted, the renewed license will authorize the applicant to continue to store spent fuel in a dry cask... COMMISSION Calvert Cliffs Nuclear Power Plant, LLC Independent Spent Fuel Storage Installation; Notice...

  19. Installation and evaluation of a nuclear power plant operator advisor based on artificial intelligence technology

    International Nuclear Information System (INIS)

    This report discusses the following topics on a Nuclear Power Plant operator advisor based on artificial Intelligence Technology; Workstation conversion; Software Conversion; V ampersand V Program Development Development; Simulator Interface Development; Knowledge Base Expansion; Dynamic Testing; Database Conversion; Installation at the Perry Simulator; Evaluation of Operator Interaction; Design of Man-Machine Interface; and Design of Maintenance Facility

  20. Adaptation of high pressure water jets with abrasives for nuclear installations dismantling

    International Nuclear Information System (INIS)

    This report presents the work realized for adjust the cutting technology with high pressure water jet with abrasives for nuclear installation dismantling. It has necessited the conception and the adjustement of a remote tool and the realization of cutting tests with waste produce analysis. This technic can be ameliorated with better viewing systems and better fog suction systems

  1. Development of ringed-blast-cutter and its application in decommission of nuclear installation

    International Nuclear Information System (INIS)

    The characteristic of blast-cut technique is presented, and the summary of the development and testing of ringed-blast-cutter is given. The application foreground of ringed-blast-cutter in decommissions of nuclear installation, and some researches for improving blast-cut technique in the future are also described

  2. A model for evaluating robotics and remote tooling in nuclear installations

    International Nuclear Information System (INIS)

    A model designed to evaluate the cost-effectiveness of the use of robotics and remote tooling in achieving reduction of occupational exposure at nuclear installations is presented. The operational cost saving of implementing dose reduction action is introduced as a key parameter. Through specific example, a partial demonstration of the model is given. (author)

  3. Study of the Brazilian scientific production in the nuclear field from 1970 to 1979

    International Nuclear Information System (INIS)

    The study of some patterns of the Brazilian scientific literature production - e.g., generated and/or published in Brazil - in the nuclear field included in CIN (Nuclear Information Center) / INIS (International Nuclear Information System) data base from 1970 to 1979 is presented. The purpose is to research: - the growth of the production; - the main subject areas; - the language of the publication; - the literature presentation form; - the author's characterization; - the most productive institutions, their geographical distribution and countries where the literature is published. (E.G.)

  4. IAEA Assistance in Helping Member States Develop Effectively Independent and Robust Regulators for Nuclear Installation Safety

    International Nuclear Information System (INIS)

    Full text: The International Conference on Topical Issues in Nuclear Installation Safety will be focused on the exchange of information on the latest thinking and advances in the implementation of the concept of Defence-in-Depth (DID) in nuclear installations, and the associated challenges. The focus will be on operating nuclear installations, including nuclear power plants, research reactors and fuel cycle facilities, and on how lessons learned from operating experience and recent events (e.g. the Fukushima Daiichi accident) are used to enhance safety. The implementation of DID covers a number of elements that are directly related to the different states and phases of a nuclear facility. This presentation will discuss the importance of the regulatory body in its oversight role as a cross-cutting element of DID in helping to assure the safety of nuclear installations. Taking note of the numerous challenges in developing an effectively independent and robust regulatory body, the presentation will describe how the IAEA assists Member States in their development of the appropriate regulatory infrastructure and necessary capacity to carry out their regulatory responsibilities – consistent with the IAEA Safety Standards. The presentation will describe the importance of the self-assessment process which serves as a starting point for helping Member States gain an understanding of what support they need and when the support should be provided as they develop into a competent regulatory authority. The presentation will discuss recent improvements in the self-assessment process and related IAEA services in this regard. Once regulatory bodies are established, it is essential that they seek continuous improvement. In this regard, the presentation will describe the IAEA’s assistance provided through the Integrated Regulatory Review Service (IRRS) and recent activities to improve the IRRS, consistent with the IAEA’s Action Plan on Nuclear Safety. (author)

  5. A legislative framework for the safety of nuclear installations in the European Union

    International Nuclear Information System (INIS)

    For the first time since the inception of the European Community in 1957 and after two previously unsuccessful attempts, on 25 June 2009 the Council of the European Union adopted European-wide, binding requirements on nuclear safety. The goal of the 'Council Directive establishing a Community framework for the nuclear safety of nuclear installations' ('the Directive') is to maintain and to promote the continuous improvement of nuclear safety and to ensure that a high level of nuclear safety is provided by EU member states to protect workers and the general public against the dangers arising from nuclear installations. The Directive is based on the IAEA Safety Fundamentals and the Convention on Nuclear Safety. The 27 member states of the Community are required to bring into force the laws, regulations and administrative provisions necessary to comply with the Directive by 22 July 2011. The Directive applies to a range of nuclear installations that is wider than the one adopted in the Convention on Nuclear Safety.9 The Directive applies to any civilian nuclear installation, defined as: a) an enrichment plant, nuclear fuel fabrication plant, nuclear power plant, reprocessing plant, research reactor facility, spent fuel storage facility; and b) storage facilities for radioactive waste that are on the same site and are directly related to nuclear installations listed under point a). The Directive is without doubt a milestone in international and regional law making in the field of nuclear law, not so much because of its content but because of the supranational nature of European law and the powers of EU institutions. Member states have long resisted the Directive because of the powers which it delegates to the European Commission, and more importantly, to the European Court of Justice. The Commission, as the guardian of the treaties and the measures taken by the institutions, ensures that EU legislation is applied correctly by the member states. It can start

  6. Post-installed concrete anchors in nuclear power plants: Performance and qualification

    International Nuclear Information System (INIS)

    Graphical abstract: - Highlights: • Review of qualification and design regulations for anchors in nuclear power plants. • First complete set of nuclear anchor load–displacement data and its evaluation ever. • Demonstration of robust test behavior of a qualified post-installed anchor product. - Abstract: In nuclear power plants (NPPs), post-installed anchors are widely used for structural and non-structural connections to concrete. In many countries, anchor products employed for safety relevant applications have to be approved by the authorities. For the high safety standards in force for NPPs, special requirements have to be met to allow for extreme design situations. This paper presents an experimental test program conducted to evaluate the performance of anchors according to the German Guideline for Anchorages in Nuclear Power Plants and Nuclear Technology Installations (DIBt KKW Leitfaden, 2010). After a brief introduction to anchor behavior and the regulative context, the results of tension and shear tests carried out on undercut anchors are discussed. Robust load capacities and relatively small displacements determined for demanding load and crack cycling tests demonstrated the suitability of anchors qualified according to a state-of-the-art qualification guideline

  7. Risk of childhood leukaemia in the vicinity of nuclear installations: Findings and recent controversies

    International Nuclear Information System (INIS)

    The identification of a local excess of cancer cases, possibly associated with ionizing radiation, always receives substantial media coverage and communication about clusters is difficult. We reviewed studies that examined the risk of leukaemia among young people near nuclear installations. An excess of leukaemia exists near some nuclear installations, at least for the reprocessing plants at Sellafield and Dounreay and the nuclear power plant Kruemmel. Nonetheless, the results of multi-site studies invalidate the hypothesis of an increased risk of leukaemia related to nuclear discharge. Up until now, analytic studies have not found an explanation for the leukaemia clusters observed near certain nuclear installations. The hypothesis of an infectious aetiology associated with population mixing has been proposed, but needs to be investigated further. The review illustrates two recent examples in France (La Hague reprocessing plant) and in Germany (Kruemmel power plant), where controversies developed after reports of increased leukaemia risks. These examples show the importance of recalling the current epidemiological knowledge and of using systematic recording of cases to replace the alleged excesses in a more general framework. Some elements should also be suggested from the recent French and German experiences to reinforce credibility in the results

  8. Environmental Impact Assessment for the Decommissioning of Nuclear Installations. Vol. 1-3

    International Nuclear Information System (INIS)

    This Report presents the results of a study concerned with Environmental Impact Assessment (EIA) for the decommissioning of nuclear installations in European Union Member States and in the Applicant Countries in Central and Eastern Europe. The study, undertaken for the Environment Directorate General of the European Commission, took place between January 2000 and March 2001 under contract number B4-3040/99/136035/MAR/C2 entitled Environmental Impact Assessment for the Decommissioning of nuclear Installations. The study presents an analysis of the current situation in the European Union and in the Applicant Countries, and develops guidance for applying the relevant Directives for EIA to the specific issue of decommissioning nuclear installations although there is also scope for application to other large or controversial projects. The first part of the report (Volume 1) describes the current situation in the EU Member States and Applicant Countries. On the basis of this status, the guidance presented in Volume 2 was developed. Draft versions of these volumes were reviewed by an independent review panel and were then subjected to detailed discussion and debate at a Workshop held in Brussels in January 2001. The Workshop was attended by more than 60 representatives of the nuclear industry, nuclear regulators, public interest groups and EIA experts. Some minor changes were made following the Workshop, a record of which can be found in Volume 3. (author)

  9. Radioactive environmental background studies at possible sites for nuclear installations in the Republic of Cuba

    International Nuclear Information System (INIS)

    To evaluate and consider possible Cuban nuclear installations, environmental studies were carried out at three sites: Quebrada nuclear research centre; Juragua nuclear power plant and Holguin north zone. Based on the results, it was concluded that the gamma radiation level is normal, the natural radionuclides in soil, vegetation, superficial waters and foodstuffs are at the same level as the ones reported in the current literature and the total effective dose rate does not exceed one tenth mSv/year. (B.C.A.). 12 refs, 08 tabs, 02 figs

  10. The new approach of the radiological emergency response team at the Brazilian National Nuclear Energy Commission's Institute of Radiation Protection and Dosimetry after the Goiania accident

    International Nuclear Information System (INIS)

    The evaluation of the emergency actions taken during the Goiania accident caused a complete revision of the Brazilian Nuclear Energy Commission's Institute of Radiation Protection and Dosimetry Emergency Response Team. The changes were in both the scope of the emergency responsibilities and in the organization of the emergency team. This new organization permits an emergency response to accidents in nuclear installations such as nuclear reactors or fuel cycle facilities, or accidents involving radiation sources in hospitals, industry, etc. The organization takes into account all the emergency phases, with emphasis on a quick response in the initial phase. Of a total emergency team of one hundred and four people, there are twenty-six members on call twenty-four hours a day. (author). 1 fig

  11. Conflict management in the planning of nuclear installations. Konfliktbewaeltigung bei der Planung kerntechnischer Anlagen

    Energy Technology Data Exchange (ETDEWEB)

    Pfeifer, M. (Muenster Univ. (Germany, F.R.). Zentralinstitut fuer Raumplanung)

    1989-07-01

    Subsequent to the decision of the Bavarian Higher Administrative Court, which after judicial review declared the development plan for the Wackersdorf site and the reprocessing facility there to be void, the author analyses the situation with regard to the tasks to be accomplished by an installation-specific planning management for coping with arising conflicts - and nuclear hazards in particular -, and for coming to a reconciliation of interests. The author agrees with the decision of the Lueneburg Higher Administrative Court which stated that, in view of the subsequent licensing procedure provided by the law, the development plans need not specify any regulations concerning the specific nuclear hazards or radiological consequences of installations of this type, so that development plans within the meaning of sec. 1, sub-sec. (3) BauGB do not necessarily have to consider nuclear risks or dose limits. (orig./HP).

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

    International Nuclear Information System (INIS)

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

  13. Forecasting of the radioactive material transport demand for the Brazilian Nuclear Program and the security aspects

    International Nuclear Information System (INIS)

    In the nuclear fuel cycle, a lot of radioactive materials are produced. These radioactive materials must be transported in order to promote the integration of the fuel cycle units. Considerations about the transport characteristics of radioactive material were made for each section of the fuel cycle. These considerations were based on the experience of several countries and in accordance with the International Atomic Energy Agency regulations. A prediction of transport demands for the Brazilian Nuclear Program until year 2.010 was made. The prediction refers mainly to the quantity of radioactive material produced in each section of the cycle the quantity of vehicles needed for the transport of these materials. Several safety aspects were considered specially, the accidents predictions for years 2.000 and 2.010. The accident probability in Brazilian railroads and highways was compared with that of the USA. (author)

  14. Genetic variability in mitochondrial and nuclear genes of Larus dominicanus (Charadriiformes, Laridae) from the Brazilian coast

    OpenAIRE

    Gisele Pires de Mendonça Dantas; Diogo Meyer; Raquel Godinho; Nuno Ferrand; João Stenghel Morgante

    2012-01-01

    Several phylogeographic studies of seabirds have documented low genetic diversity that has been attributed to bottleneck events or individual capacity for dispersal. Few studies have been done in seabirds on the Brazilian coast and all have shown low genetic differentiation on a wide geographic scale. The Kelp Gull is a common species with a wide distribution in the Southern Hemisphere. In this study, we used mitochondrial and nuclear markers to examine the genetic variability of Kelp Gull po...

  15. 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)

  16. Political dynamics of the creation of the Brazilian National Commission for Nuclear Energy, 1956-1960

    OpenAIRE

    Tatiane Lopes dos Santos; Ana Maria Ribeiro de Andrade

    2013-01-01

    The article analyzes the political dynamics of the process that founded the Brazilian National Nuclear Energy Commission (CNEN), concluded in October 1956, during Juscelino Kubitschek's government. It argues that the President Kubitschek yielded to military interests, especially from the Army and Navy, ignoring the bill on the same matter that was in discussion at Brazil's House of Representatives. This strategy helped to reduce the disagreement between the Conselho Nacional de Pesquisas (CNP...

  17. Improving the turbine district heating installations of single-circuit nuclear power plants

    Science.gov (United States)

    Kondurov, E. P.; Kruglikov, P. A.; Smolkin, Yu. V.

    2015-10-01

    Ways for improving the turbine district heating installations of single-circuit nuclear power plants are considered as a possible approach to improving the nuclear power plant energy efficiency. The results of thermal tests carried out at one of single-circuit NPPs in Russia with a view to reveal the possibilities of improving the existing heat-transfer equipment of the turbine district heating installation without making significant investments in it were taken as a basis for the analysis. The tests have shown that there is certain energy saving potential in some individual units and elements in the turbine district heating installation's process circuit. A significant amount of thermal energy can be obtained only by decreasing the intermediate circuit temperature at the inlet to the heater of the first district-heating extraction. The taking of this measure will also lead to an additional amount of generated electricity because during operation with the partially loaded first heater, the necessary amount of heat has to be obtained from the peaking heater by reducing live steam. An additional amount of thermal energy can also be obtained by eliminating leaks through the bypass control valves. The possibility of achieving smaller consumption of electric energy for power plant auxiliaries by taking measures on reducing the available head in the intermediate circuit installation's pump unit is demonstrated. Partial cutting of pump impellers and dismantling of control valves are regarded to be the most efficient methods. The latter is attributed to qualitative control of the turbine district heating installation's thermal load. Adjustment of the noncondensable gas removal system will make it possible to improve the performance of the turbine district heating installation's heat-transfer equipment owing to bringing the heat-transfer coefficients in the heaters to the design level. The obtained results can be used for estimating the energy saving potential at other

  18. Main crane type selection and arrangement for nuclear power plant construction and installation

    International Nuclear Information System (INIS)

    Large-scaled cranes are needed to hoist assemblies in civil works and installation of nuclear plants. Different cranes are required in CPR1000, EPR and AP1000 to match different site layout. Before construction, the type of cranes, the working area, as well as the transmitting path should be chosen according to the layout characters to make civil works and installation can be carried out smoothly. This article will give precept on type-choosing and layout of large-scaled cranes by analyzing the hoisting requirements in CPR1000, EPR and AP1000. (authors)

  19. Organisation arrangements of nuclear medicine services. Planning of installations. Laboratory monitoring

    International Nuclear Information System (INIS)

    Apart from safety and quality requirements, the organisation of nuclear medicine services, or more generally of installations where nonsealed radioactive sources are used, is governed by profitability and efficiency criteria. In view of the high price of products and apparatus, the equipment must be based on a rationalisation of options guiding the organisation arrangements as a whole. The following items are dealt with in succession: various categories of installations; general planning of equipment; equipment regulations based on a major requirement, the confinement of contamination sources; practical observations concerning administrative and technical questions

  20. Design, fabrication and installation of irradiation facilities -Advanced nuclear material development-

    International Nuclear Information System (INIS)

    The objective of this study is to design and construct the steady state fuel test loop and non-instrumented capsules to be installed in KMRR. The principle contents of this project are to design, fabricate the steady-state fuel test loop and non-instrumented capsule to be installed in KMRR for nuclear technology development. This project will be completed in 1996, so preparation of design criteria for fuel test loop have been performed in 1993 as the first year of the first phase in implementing this project. Also design and pressure drop test of non-instrumented capsule have been performed in 1993

  1. Proceedings of the 6.Brazilian Meeting on Nuclear Medicine

    International Nuclear Information System (INIS)

    Several subjects on nuclear medicine are presented. The use of scintiscanning in heart diseases, neoplasms, etc. is emphasized. Radioisotope preparation techniques and labelling of compounds used in radioassays are described. (M.A.C.)

  2. Proceedings of the 7. Brazilian Meeting on Nuclear Medicine

    International Nuclear Information System (INIS)

    Subjects about nuclear medicine are discussed. Researchs concerning the use of radioisotopes as tracers in several diseases are presented. The use of radioisotopes in diagnosis are emphasized. (M.A.C.)

  3. Proceedings of the 3. Brazilian Meeting on Nuclear Applications

    International Nuclear Information System (INIS)

    Researches in nuclear applications have been developed in Brazil, and were presented in this Meeting. Over 230 papers were presented in the areas of dosimetry, instrumentation, medicine, biology, agriculture, industry, radiochemistry, radiological protection, hydrology, environment and waste management

  4. Inventory of chemical releases of nuclear installations in the North-Cotentin; Inventaire des rejets chimiques des installations nucleaires du Nord-Cotentin

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2002-05-15

    The nuclear installations concerned by this study are Cogema La Hague, the Flamanville nuclear power plant, the Manche plant and the National Navy of Cherbourg.The objective followed by the ' source term ' work group has consisted in counting and examining the whole of existing measures relative to the releases of chemical substances in the liquid and gaseous effluents. Then because of the lack of measures for the operation first years of installations, the work group has estimated the order of magnitude of these chemical releases (essentially for Cogema La Hague). This report presents a review of the literature looking at the background levels of chemicals in different environmental compartments: air, soil, plants and animals products. these values have been summarized here to be available for comparisons with concentrations input by the North Cotentin nuclear installations, calculated by the G.R.N.C. (radioecology group of Nord Cotentin)

  5. Security of a nuclear material in an installation is determined by how far the installation is to assure that nuclear material remains at a predetermined location

    International Nuclear Information System (INIS)

    This paper observed a preliminary design on nuclear material tracking system in the installation for decision making support based on multi sensor fusion that is reliable and accurate to ensure that the nuclear material remains inside the control area. Capability on decision making in the Management Information System is represented by an understanding of perception in the third level of abstraction. The second level will be achieved with the support of image analysis and organizing data. The first level of abstraction is constructed by merger between several CCD camera sensors distributed in a building in a data fusion representation. Data fusion is processed based on Wavelett approach. Simulation utilizing Matlab programming shows that Wavelett fuses multi information from sensors as well. Hope that when the nuclear material out of control regions which have been predetermined before, there will arise a warning alarm and a message in the Management Information System display. Thus the nuclear material movement time event can be obtained and tracked as well. (author)

  6. Advanced LP turbine installation at 1300 MW nuclear power station Unterweser

    International Nuclear Information System (INIS)

    This paper reports on Preussen Elektra AG's Unterweser power plant. The steam turbine-generator features a disk-type LP turbine rotor design developed in the late 1960's to early 1970's. This rotor design has been installed in 19 nuclear power plants. The 47 rotors in these plants have been in operation for an average of almost 10 years. The design of the 1970 vintage nuclear LP turbine rotors was based on extensive experience gained with disk-type rotors of fossil turbines built in the 1950's. When EPRI reported about corrosion cracking in nuclear LP turbines, a program was initiated by Siemens/KWU as original steam turbine supplier to ultrasonically inspect all their disk-type rotors in nuclear power plats. Indications on one rotor disk in the Unterweser plant was found. This single event was the only one found out of 310 disks inspected in nuclear power plants

  7. Protocol between the Nuclear Protection and Safety Bureau of Portugal and the Nuclear Energy Commission of Spain on Technical Information concerning Nuclear Installations in Border Areas

    International Nuclear Information System (INIS)

    This Protocol was concluded under the Agreement of the same date on the safety of nuclear installations in border areas. Its purpose is to prescribe the type of information referred to in the Agreement. It lays down in detail all the documents to be supplied concerning the siting, construction, operation and decommissioning of nuclear installations, including the geological, seismological, meteorological, hydrological and ecological aspects of the sites concerned, for purposes of environmental protection; the characteristics of the projected installations and emergency plans must also be provided. Similarly to the Agreement, this Protocol will remain in force for a period of ten years. (NEA)

  8. International conference on the operational safety performance in nuclear installations. Contributed papers

    International Nuclear Information System (INIS)

    In 2001, the IAEA organized an 'International Conference on Topical Issues in Nuclear Safety'. The issues discussed during the conference were: (1) risk- informed decision-making; (2) influence of external factors on safety; (3) safety of fuel cycle facilities; (4) safety of research reactors; and (5) safety performance indicators. Senior nuclear safety decision makers reviewed the issues and formulated recommendations for future actions by national and international organizations. In 2004, the IAEA organized an 'International Conference on Topical Issues in Nuclear Safety' in Beijing China. The issues discussed during the conference were: (1) changing environment - coping with diversity and globalization; (2) operating experience - managing changes effectively; (3) regulatory management systems - adapting to changes in the environment; and (4) long term operations - maintaining safety margins while extending plant lifetimes. The results of this conference confirmed the importance of operators and regulators of nuclear facilities meeting periodically to share experience and opinion on emerging issues and future challenges of the nuclear industry. Substantial progress has been made, and continues to be made by Member States in enhancing the safety of nuclear installations worldwide. At the same time, more attention is being given to other areas of nuclear safety. The safety standards for research reactors are being updated and new standards are planned on the safety of other facilities in the nuclear fuel cycle. The Agency has taken a lead role in this effort and is receiving much support from its Member States to gain international consensus in these areas. The objective of the conference is to foster the exchange of information on operational safety performance and operating experience in nuclear installations, with the aim of consolidating an international consensus on: - the present status of these issues; - emerging issues with international implications

  9. The social construction of risk and the controversial Brazilian Nuclear Program: among scientific, political and public

    International Nuclear Information System (INIS)

    This research aims to investigate the Brazilian Nuclear Program (PNB) stating as reference the Fukushima nuclear accident. Its main purpose is to analyze how the Japanese accident impacted the PNB. Therefore, the program will be analyzed within 10-years (2004-2014) in order to answer this question. The discussion launched in this thesis is based on the framework of the Social Studies of Science and Technology, which enables the understanding of socio-technical controversies beyond the social or technological determinism. Through the discussion of the concepts of framing, socio-technical imaginary, risk and governance of science and technology, the research shows how the controversy in focus has resulted in the opportunity to consider not only economic, technological, environmental issues about nuclear energy, but also its political dimensions and challenges. Among these challenges, and from very different perspectives, arise questions about the role nuclear energy plays in the Brazilian context, the future of the program and the decision making process on these issues. Despite the central purpose of this study is essentially on risks, PNB and on the Brazilian context, it should be pointed that it is impossible to consider it in isolation of what is happening internationally (considering interests, tensions, relations between actors, etc.) The research thereby identifies key implications of Fukushima in the international context, but focuses on the disputes regarding possible review of the PNB. It also highlights how the socio-technical controversies, such as the nuclear energy, demand or impose a discussion on the governance of science and technology, risk and on the engagement of different sectors and actors in decision-making on issues, that are at the same time about energy, technology and nationality relevance. All this reflection is made from multi-sited analysis, which allowed following the controversy surrounding nuclear energy, reheated by the Fukushima

  10. The Brazilian Nuclear Program and the consequences for medical physics; O Programa Nuclear Brasileiro e a fisica medica no Brasil

    Energy Technology Data Exchange (ETDEWEB)

    Goncalves, Odair Dias [Comissao Nacional de Energia Nuclear (CNEN), Rio de Janeiro, RJ (Brazil)], e-mail: odairdg@cnen.gov.br

    2009-10-15

    The use of radioactive materials or nuclear phenomena in medicine begun before the Second World War; since then, the knowledge about nuclear power has been through a huge development. Impelled by the development of nuclear power plants, the application of nuclear techniques and processes in medicine also had a similar progress, as the same happened in Brazil. On the other hand, the parallel evolution did not happen in developing ways to guarantee the safe and secure use of such knowledge, which grew in the energy field faster and earlier than in medicine. This paper attempts to make a brief analysis of the progress in both fields throughout time, emphasizing the Brazilian Nuclear Program and its consequences on the field of medical physics. (author)

  11. Outline of a future security system to provide physical protection of nuclear installations

    International Nuclear Information System (INIS)

    Nuclear energy, within three or four decades, may become a main pillar of the world's energy supply. The author discusses the problems entailed by the necessity to protect nuclear facilities against assaults, and whether this can be ensured without interference with civic rights. The method applied by the author to show the significance of the problems is to explain the current situation, and to compare it with a plausible outline of the developments to be expected over the next 50 years. He shows the hazards to be taken into account due to criminal actions by persons from outside, or by persons working in nuclear facilities. A main problem is the fact that the security system to be set up has to encompass not only the nuclear installation itself, but also the surrounding area, and the measures to be taken will have an impact on the society, which necessarily will curtail personal freedom. The author presumes that the necessity to guarantee physical protection of nuclear facilities will lead to a modification of the meaning of basic rights, and states his anxiety that security for nuclear installations might affect our concept of freedom. (HSCH)

  12. Heat-electricity convertion systems for a Brazilian space micro nuclear reactor

    International Nuclear Information System (INIS)

    This contribution will discuss the evolution work in the development of thermal cycles to allow the development of heat-electricity conversion for the Brazilian space micro nuclear Reactor. Namely, innovative core and nuclear fuel elements, Brayton cycle, Stirling engine, heat pipes, passive multi-fluid turbine, among others. This work is basically to set up the experimental labs that will allow the specification and design of the space equipment. Also, some discussion of the cost so far, and possible other applications will be presented. (author)

  13. Heat-electricity convertion systems for a Brazilian space micro nuclear reactor

    Energy Technology Data Exchange (ETDEWEB)

    Guimaraes, Lamartine N.F.; Marcelino, Natalia B.; Placco, Guilherme M.; Nascimento, Jamil A.; Borges, Eduardo M., E-mail: guimarae@ieav.cta.br, E-mail: lamartine.guimaraes@pq.cnpq.br, E-mail: jamil@ieav.cta.br, E-mail: jalnsgf@outlook.com, E-mail: borges.em@hotmail.com, E-mail: ecorborges@hotmail.com, E-mail: ivayolini@gmail.com, E-mail: guilherme_placco@ig.com.br [Instituto de Estudos Avancados (IEAv/DCTA), Sao Jose dos Campos, SP (Brazil); Barrios Junior, Ary Garcia, E-mail: arygarcia89@yahoo.com [Faculdade de Tecnologia Sao Francisco (FATESF), Jacarei, SP (Brazil)

    2013-07-01

    This contribution will discuss the evolution work in the development of thermal cycles to allow the development of heat-electricity conversion for the Brazilian space micro nuclear Reactor. Namely, innovative core and nuclear fuel elements, Brayton cycle, Stirling engine, heat pipes, passive multi-fluid turbine, among others. This work is basically to set up the experimental labs that will allow the specification and design of the space equipment. Also, some discussion of the cost so far, and possible other applications will be presented. (author)

  14. Effects of the Brazilian Regulatory Inspection Programme on Nuclear Medicine Facilities

    International Nuclear Information System (INIS)

    This work aims to demonstrate the importance of the regulatory inspections carried out by Brazilian regulatory body in the area of nuclear medicine field. The main aspects observed during the inspections are presented as well as the time evolution of the non-compliances, according to their occurrence by type. The results point out the importance of continuous coercion actions to improve the radiological protection level in nuclear medicine facilities in compliance with the standards established by the national regulatory authority and international recommendations. (author)

  15. Proceedings of the 2. Brazilian Meeting on Nuclear Applications

    International Nuclear Information System (INIS)

    Researches in nuclear applications have been developed in Brazil, and were presented in this Meeting. Over 130 papers were presented in the areas of dosimetry, instrumentation, medicine, biology, agriculture , industry, radiochemistry, radiological protection, hydrology and environment. (L.C.J.A.)

  16. 20. Brazilian congress on biology and nuclear medicine. Abstracts

    International Nuclear Information System (INIS)

    Several aspects concerning the use of nuclear medicine in cardiology, oncology, neurology, endocrinology among other areas are studied. Various topics related to diagnosis and treatment of diseases are presented, e.g. radiotracers use, radiopharmaceuticals (mainly associated with technetium 99), development and standardization of radionuclides, structural chemical analysis, metabolism, biological functions. The scintiscanning is the most reported diagnostic technique

  17. Centro Regional de Ciencias Nucleares (a Brazilian regional center for nuclear sciences) - activities report - 1999; Centro Regional de Ciencias Nucleares - relatorio de atividades - 1999

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-12-01

    The annual activities report of 1999 of nuclear sciences regional center - Brazilian organization - introduces the next main topics: institutional relations; sectorial actions - logistic support and training, laboratory of radiation protection and dosimetry, laboratory of metrology, laboratory of chemical characterization; technical and scientific events; and financial resources and perspectives for 2000.

  18. Brazilian nuclear power plants decommissioning plan for a multiple reactor site

    International Nuclear Information System (INIS)

    Actually, Brazil has two operating Nuclear Power Plants and a third one under construction, all at Central Nuclear Almirante Alvaro Alberto - CNAAA. To comply with regulatory aspects the power plants operator, Eletronuclear, must present to Brazilian Nuclear Regulatory Agency, CNEN, a decommissioning plan. Brazilian experience with decommissioning is limited because none of any nuclear reactor at the country was decommissioned. In literature, decommissioning process is well described despite few nuclear power reactors have been decommissioned around the world. Some different approach is desirable for multiple reactors sites, case of CNAAA site. During the decommissioning, a great amount of wastes will be produced and have to be properly managed. Particularly, the construction of Auxiliary Services on the site could be a good choice due to the possibility of reducing costs. The present work intends to present to the Eletronuclear some aspects of the decommissioning concept and decommissioning management, storage and disposal de wastes, based on the available literature, regulatory standards of CNEN and international experience as well as to suggest some solutions to be implemented at CNAAA site before starts the decommissioning project in order to maximize the benefits. (author)

  19. Seismic Hazard Assessment in Site Evaluation for Nuclear Installations: Ground Motion Prediction Equations and Site Response

    International Nuclear Information System (INIS)

    The objective of this publication is to provide the state-of-the-art practice and detailed technical elements related to ground motion evaluation by ground motion prediction equations (GMPEs) and site response in the context of seismic hazard assessments as recommended in IAEA Safety Standards Series No. SSG-9, Seismic Hazards in Site Evaluation for Nuclear Installations. The publication includes the basics of GMPEs, ground motion simulation, selection and adjustment of GMPEs, site characterization, and modelling of site response in order to improve seismic hazard assessment. The text aims at delineating the most important aspects of these topics (including current practices, criticalities and open problems) within a coherent framework. In particular, attention has been devoted to filling conceptual gaps. It is written as a reference text for trained users who are responsible for planning preparatory seismic hazard analyses for siting of all nuclear installations and/or providing constraints for anti-seismic design and retrofitting of existing structures

  20. Stakeholder involvement in the management of effluent discharges from nuclear installations in France

    International Nuclear Information System (INIS)

    The involvement of local stakeholders in the decision-making process regarding health, safety and environmental issues is developing in many countries. As far as the management of effluent discharges from nuclear installations in France is concerned, members of Local Commission of Information, including elected people and NGOs, are playing an increasing role in that respect. To deepen the understanding of these risk governance processes, a working group of experts from different institutions was set up in 2000 by the Institute of Radiation Protection and Nuclear Safety (IRSN). The aim of this working group was to 1) analyse the stakeholder involvement processes already in place in France around nuclear and non-nuclear installations; 2) perform case studies of few national and international experiences around nuclear installations (notably concerning the revision of creation authorisation decree of COGEMA La Hague reprocessing plant, the environmental policy of BNFL Sellafield reprocessing plant, the discharges surveillance of EDF Fessenheim nuclear power plant); 3) study the evolution of the regulatory context for the stakeholder involvement. Four main elements, contributing to the social trust emerge from this analysis: 1) the social dynamics of the consultation process, notably with the emergence of 'new' stakeholders such as elected people and NGOs; 2) the readability of the plant follow-up from the point of view of local stakeholders and their involvement in the decision process (the relay role of these 'new' stakeholders); 3) the contribution of the institutional and pluralist expertise to the social trust (broadening of the range of values taken into account); 4) the issue of the local justification of the plant in the prospect of the sustainable development (no risk being acceptable without counter-parts). This paper will address these different issues on the basis of the case studies in the perspective of examining the radiological risk governance process

  1. Installation of a new type of nuclear reactor in Mexico: advantages and disadvantages

    International Nuclear Information System (INIS)

    In this work the main advantages and disadvantages of the installation of a new type of nuclear reactor different to the BWR type reactor in Mexico are presented. A revision of the advanced reactors is made that are at the moment in operation and of the advanced reactors that are in construction or one has already planned its construction in the short term. Specifically the A BWR and EPR reactors are analyzed. (Author)

  2. The Community's research and development programme on decommissioning of nuclear installations. Third annual progress report 1987

    International Nuclear Information System (INIS)

    This is the third annual progress report of the European Community's programme (1984-88) of research on the decommissioning of nuclear installations. It shows the status of the programme on 31 December 1987. The third progress report describes the objectives, scope and work programme of the 69 research contracts concluded, as well as the progress of work achieved and the results obtained in 1987

  3. HM Nuclear Installations Inspectorate: a bibliography of published work, 1962-1987

    International Nuclear Information System (INIS)

    This bibliography contains references to published reports, conference papers and journal articles produced by individual members of the Nuclear Installations Inspectorate and the Inspectorate as a whole. The bibliography has been compiled from records held by the Health and Safety Executive Library and Information Service. All items have been indexed in HSELINE, HSE's publicly available database. The bibliography is arranged in 2 parts: by author(s) and by subject. (author)

  4. The community's research and development programme on decommissioning of nuclear installations. Fourth annual progress report 1988

    International Nuclear Information System (INIS)

    This is the fourth annual progress report on the European Community's programme (1984-88) of research on the decommissioning of nuclear installations. It shows the status of the programme at 31 December 1988. The fourth progress report describes the objectives, scope and work programme of the 72 research contracts concluded, as well as the progress of work achieved and the results obtained in 1988

  5. The Creation of a French Basic Nuclear Installation - Description of the Regulatory Process - 13293

    International Nuclear Information System (INIS)

    CEA is a French government-funded technological research organization. It has to build a medium-level waste interim storage facility because the geological repository will not be available until 2025. This interim storage facility, called DIADEM, has to be available in 2017. These wastes are coming from the research facilities for spent fuel reprocessing and the dismantling of the most radioactive parts of nuclear facilities. The CEA handles the waste management by inventorying the needs and updating them regularly. The conception of the facility is mainly based on this inventory. It provides quantity and characteristics of wastes and it gives the production schedule until 2035. Beyond mass and volume, main characteristics of these radioactive wastes are chemical nature, radioisotopes, radioactivity, radiation dose, the heat emitted, corrosive or explosive gas production, etc. These characteristics provide information to study the repository safety. DIADEM mainly consists of a concrete cell, isolated from the outside, wherein stainless steel welded containers are stored, stacked in a vertical position in the racks. DIADEM is scheduled to store three types of 8 mm-thick, stainless steel cylindrical containers with an outside diameter 498 mm and height from 620 to 2120 mm. DIADEM will be a basic nuclear installation (INB in French) because of overall activity of radioactive substances stored. The creation of a French basic nuclear installation is subject to authorization according to the French law No. 2006-686 of 13 June 2006 on Transparency and Security in the Nuclear Field. The authorization takes into account the technical and financial capacities of the licensee which must allow him to conduct his project in compliance with these interests, especially to cover the costs of decommissioning the installation and conduct remediation work, and to monitor and maintain its location site or, for radioactive waste disposal installations, to cover the definitive shut

  6. The Creation of a French Basic Nuclear Installation - Description of the Regulatory Process - 13293

    Energy Technology Data Exchange (ETDEWEB)

    Mahe, Carole [CEA Marcoule - BP17171 - 30207 Bagnols-Sur-Ceze (France); Leroy, Christine [CEA Cadarache - 13108 Saint Paul-Lez-Durance (France)

    2013-07-01

    CEA is a French government-funded technological research organization. It has to build a medium-level waste interim storage facility because the geological repository will not be available until 2025. This interim storage facility, called DIADEM, has to be available in 2017. These wastes are coming from the research facilities for spent fuel reprocessing and the dismantling of the most radioactive parts of nuclear facilities. The CEA handles the waste management by inventorying the needs and updating them regularly. The conception of the facility is mainly based on this inventory. It provides quantity and characteristics of wastes and it gives the production schedule until 2035. Beyond mass and volume, main characteristics of these radioactive wastes are chemical nature, radioisotopes, radioactivity, radiation dose, the heat emitted, corrosive or explosive gas production, etc. These characteristics provide information to study the repository safety. DIADEM mainly consists of a concrete cell, isolated from the outside, wherein stainless steel welded containers are stored, stacked in a vertical position in the racks. DIADEM is scheduled to store three types of 8 mm-thick, stainless steel cylindrical containers with an outside diameter 498 mm and height from 620 to 2120 mm. DIADEM will be a basic nuclear installation (INB in French) because of overall activity of radioactive substances stored. The creation of a French basic nuclear installation is subject to authorization according to the French law No. 2006-686 of 13 June 2006 on Transparency and Security in the Nuclear Field. The authorization takes into account the technical and financial capacities of the licensee which must allow him to conduct his project in compliance with these interests, especially to cover the costs of decommissioning the installation and conduct remediation work, and to monitor and maintain its location site or, for radioactive waste disposal installations, to cover the definitive shut

  7. COMARE statement: investigation of the incidence of cancer around Wylfa and Trawsfyndd nuclear installations

    Energy Technology Data Exchange (ETDEWEB)

    Redwood, J.A.

    1994-06-16

    In answer to a House of Commons question, this piece from Hansard for 16th June 1994 looks at the incidence of cancer around the Trawsfynydd and Wylfa nuclear installations in Wales. A study undertaken between 1974 and 1986 followed groupings of many cancers, especially leukaemias, lymphoid leukaemia, lymphomas, Hodgkin's disease, multiple myeloma, brain and thyroid cancers. These were chosen because of their suggested links with radiation in the medical literature. No statistically significant links were found between the incidence of cancers studied and residence near the nuclear stations. (UK).

  8. Acquired experience resulting from transforming a chemical installation into a nuclear one

    Energy Technology Data Exchange (ETDEWEB)

    Zamfirache, M.; Stefan, L.; Bornea, A.; Stefanescu, I. [National Research and Development Institute for Cryogenics and Isotopic Technologies - ICIT, Uzinei (Romania)

    2015-03-15

    ICIT-Valcea has developed an experimental pilot-scale installation for tritium and deuterium separation. The main objective of this pilot was to demonstrate the water detritiation technology and to transfer this technology to the CANDU reactors of the Cernavoda nuclear power plant. The pilot-scale installation was initiated in 1992. The initial design and construction were performed similarly to chemical plants as the separation of isotopes was focused on only hydrogen and deuterium to assess feasibility. In a second phase we have begun to transform it into a nuclear facility with the aim of separating tritium. Moving to tritium separation has imposed a lot of changes. Changes consisted mainly of: -) re-design of the technological systems for nuclear material processing, applying specific codes and standards (ASME, Romanian nuclear specific pressure boundary prescriptions for code classification); -) design and implementation of new systems, classified as safety systems; -) re-design and implementation of command and control systems, complying with the requirements of reliability and maintenance required for the project promoted; -) revaluation of auxiliary systems (utilities, power supply); -) implementing radiation protection systems, including secondary barriers; -) implementing and maintaining environment operational program specific to the new nuclear plant; -) developing and conducting safety analyzes; and -) the production of specific documentation to obtain the necessary permits for construction, commissioning and operation of the plant.

  9. The regulator as an influence on safety culture in a nuclear installation

    International Nuclear Information System (INIS)

    In the United Kingdom, many external bodies have an effect on the safety culture within a nuclear installation. Such bodies include anti-nuclear groups, local councils, the general public and, most importantly of all, the general publics nuclear watchdog - the nuclear installations inspectorate or NII. This paper explores some of those influences, from the experience at BNFLs Sellafield complex. The NII influence is so significant because of their frequency and level of actual and potential interaction with the nuclear operators. As a division of the UK health and safety executive, the NII annually devote about 20 man years of inspection and assessment effort to Sellafield plants and projects and carry out over 700 visits. They visit people at all levels (not just senior management) and are regularly seen on plant. Inspectors are normally allocated to an operational area for 1-2 years before moving on. They also carry out site wide team inspections on specific issues or topics. Inspectors have statutory powers of inspection, they can order plant improvements, shutdown operations, and can bring prosecution for unsafe practices. (author)

  10. Installation and commissioning of operation nuclear power plant reactor protection system modernization project

    International Nuclear Information System (INIS)

    Qinshan Nuclear Power Plant is the first nuclear power plant in mainland China; it is also the first one which realizes the modernization of analog technology based Reactor Protection System in the operation nuclear power plant of China. The implementation schedule is the shortest one which use same digital technology platform (TELEPERM XS of AREVA NP) to modifying the safety class I and C system in the world, the whole project spent 28 months from equipment contract signed to putting system into operation. It open up a era for operation nuclear power plant using mature digital technology to make safety class I and C system modernization in China. The important practical significance of this successful project is very obvious. This article focus on two important project stage--equipment installation and system commissioning, it is based on a large number of engineering implementation fact, it covers the problems and solutions happened during the installation and commission. The purpose of the article is to share the experience and lessons of safety I and C system modernization for other operation nuclear power plant. (authors)

  11. Acquired experience resulting from transforming a chemical installation into a nuclear one

    International Nuclear Information System (INIS)

    ICIT-Valcea has developed an experimental pilot-scale installation for tritium and deuterium separation. The main objective of this pilot was to demonstrate the water detritiation technology and to transfer this technology to the CANDU reactors of the Cernavoda nuclear power plant. The pilot-scale installation was initiated in 1992. The initial design and construction were performed similarly to chemical plants as the separation of isotopes was focused on only hydrogen and deuterium to assess feasibility. In a second phase we have begun to transform it into a nuclear facility with the aim of separating tritium. Moving to tritium separation has imposed a lot of changes. Changes consisted mainly of: -) re-design of the technological systems for nuclear material processing, applying specific codes and standards (ASME, Romanian nuclear specific pressure boundary prescriptions for code classification); -) design and implementation of new systems, classified as safety systems; -) re-design and implementation of command and control systems, complying with the requirements of reliability and maintenance required for the project promoted; -) revaluation of auxiliary systems (utilities, power supply); -) implementing radiation protection systems, including secondary barriers; -) implementing and maintaining environment operational program specific to the new nuclear plant; -) developing and conducting safety analyzes; and -) the production of specific documentation to obtain the necessary permits for construction, commissioning and operation of the plant

  12. fire safety review at nuclear installations case study : Egypt's second research reactor

    International Nuclear Information System (INIS)

    the importance of fire safety in the safe operation of nuclear installations is recognized worldwide. lessons learned from past experience indicate that fire poses a real threat to nuclear safety and that its significance extends far beyond the scope of a conventional fire hazard. A methodology provided by the IAEA is used (after simplified ) to assess the adequacy and effectiveness of the overall fire safety arrangements provided in operating large nuclear installations. three primary methods are used to acquire the information needed to assess the effectiveness of reactor fire safety and to propose specific recommendations for improvement. these are document review, personnel interviews, and direct observation. effective fire protection includes a number of distinct elements that must be integrated into the overall fire safety arrangements of the reactor. As a minimum , these elements cover organization, a fire prevention program including a comprehensive fire hazard analysis, provision for passive fire protection measures, installation of reliable and effective fire detection and extinguishing systems and equipment, periodic inspection, maintenance and testing of all fire protection measures (passive and active); a quality assurance program, and the manual fire fighting capability. A simplified method is proposed to assess the fire protection safety of egypt;s second research reactor. fire hazard analysis and experimental fire growth model for the reactor electrical board room is developed, simplified fire safety inspection checklist has been prepared for professional fire safety specialists to evaluate the adequacy and effectiveness of reactor fire safety . also a simplified fire incident reporting system is proposed

  13. Environmental Radiological Monitoring Programme around nuclear installations during the decommissioning process

    International Nuclear Information System (INIS)

    Spanish Regulations require that an Environmental Radiological Monitoring Programme (PVRA) should be carried out during the different life stages of the plants: preoperational, operation, termination of the operation, dismantling and decommissioning. The Spanish Nuclear Safety Council published a Regulatory Guide to provide guidance on the design and development of this programmes around nuclear power installations during the operation of the plant in routine situations and this Guide specifies that PVRA should be adapted to the different life plant situations in order to evaluate the radiological impact of the plant due to the activities performed in each of them. In Spain at the moment two nuclear power installations are undergoing the decommissioning process: Vandellos 1 NPP and the Centro de Investigaciones Energeticas Medioambientales y Tecnologicas (CIEMAT). Jose Cabrera NPP is in the situation of termination of the operation. This paper presents the changes made in the PVRA carried out around these installations in order to know the potential radiological impact due to radionuclide discharges to the environment as a result of the decommissioning process. (author)

  14. Childhood leukaemia risks: from unexplained findings near nuclear installations to recommendations for future research

    International Nuclear Information System (INIS)

    Recent findings related to childhood leukaemia incidence near nuclear installations have raised questions which can be answered neither by current knowledge on radiation risk nor by other established risk factors. In 2012, a workshop was organised on this topic with two objectives: (a) review of results and discussion of methodological limitations of studies near nuclear installations; (b) identification of directions for future research into the causes and pathogenesis of childhood leukaemia. The workshop gathered 42 participants from different disciplines, extending widely outside of the radiation protection field. Regarding the proximity of nuclear installations, the need for continuous surveillance of childhood leukaemia incidence was highlighted, including a better characterisation of the local population. The creation of collaborative working groups was recommended for consistency in methodologies and the possibility of combining data for future analyses. Regarding the causes of childhood leukaemia, major fields of research were discussed (environmental risk factors, genetics, infections, immunity, stem cells, experimental research). The need for multidisciplinary collaboration in developing research activities was underlined, including the prevalence of potential predisposition markers and investigating further the infectious aetiology hypothesis. Animal studies and genetic/epigenetic approaches appear of great interest. Routes for future research were pointed out. (review)

  15. Regulation of the life cycle of nuclear installations. Peer discussions on regulatory practices

    International Nuclear Information System (INIS)

    This report arises from the sixth series of peer discussions on regulatory practices entitled 'Regulation of Life Cycle of Nuclear Installations'. Senior regulators from 18 Member States participated in three peer group discussions during 1997-1998. This report presents the outcome of these meetings and recommendations of good practices identified by senior regulators, which do not necessarily reflect those of the governments of the nominating Member States, the nominating organizations, or the IAEA. The purpose of this report is to disseminate the views which the senior regulators presented at the meetings relating to the policies, principles and requirements imposed by regulatory bodies for the safe management of the life cycle of a nuclear installation. The intention of doing this is to assist Member States in the formulation and enhancement of their regulatory control over PLCM by identifying commonly accepted good practices. This report is structured to cover the subject matter under the following main headings: Policies and Principles for the Life Cycle Management of Nuclear Installations; Responsibilities of the Regulatory Body and the Operating Organization; Requirements and Criteria Imposed by the Regulatory Body; Licensing and Regulatory Assessment for Plant Life Cycle Management; and Good Practices

  16. Nuclear knowledge portal for supporting licensing and controlling nuclear activities in the Brazilian Nuclear Energy Commission

    International Nuclear Information System (INIS)

    The knowledge economy is pivotal for moving the wealth and development of traditional industrial sectors - abundant in manual labour, raw materials and capital - to areas whose products, processes and services are rich in technology and knowledge. Even in research areas such as nuclear energy, where goods are based on high technology, the ability to transform information into knowledge, and knowledge into decisions and actions, is extremely important. Therefore, the value of products from these areas depends more and more on the degree of innovation, technology and intelligence incorporated by them. Thus, it has become increasingly important and relevant to acquire strategic knowledge and make it available to the organisation. Therefore, the objective of this paper is to present the construction of a Nuclear Knowledge Portal for aiding and streamlining the Licensing and Management activities of the CNEN. (author)

  17. Nuclear knowledge portal to support licensing and control nuclear activities in the Brazilian Nuclear Energy Commission

    International Nuclear Information System (INIS)

    The Knowledge Economy is pivotal for moving the wealth and development of traditional industrial sectors - abundant in manual labor, raw materials and capital - to areas whose products, processes and services are rich in technology and knowledge. Even in research areas such as nuclear energy, where goods are based on high technology, the ability to transform information into knowledge, and knowledge into decisions and actions, is extremely important. Therefore, the value of products from these areas depends more and more on the degree of innovation, technology and intelligence incorporated by them. Thus, it has become increasingly important and relevant to acquire strategic knowledge and make it available to the organization. Therefore, the objective of this article is to present the construction of a Nuclear Knowledge Portal for aiding and streamlining the Licensing and Management activities of the CNEN. (author)

  18. Report on Activities of the Nuclear Regulatory Authority of the Slovak Republic and on Safety of Nuclear Installations in the Slovak Republic in 2005. Annual report 2005

    International Nuclear Information System (INIS)

    A brief account of activities carried out by the Nuclear Regulatory Authority of the Slovak Republic in 2005 is presented. These activities are reported under the headings: Foreword; (1) Vision, Mission and Principles of Activities; (2) Legislation; (3) Issuance of Authorisations, Safety Assessment and Enforcement; (4) Nuclear Safety of Nuclear Installations in the Slovak Republic; (4.1) Nuclear installations in operation in the Slovak Republic; (4.2) Nuclear Installations under construction in the Slovak Republic; (4.3) Decommissioning of nuclear installations in the Slovak Republic; (5) Spent Fuel and Radioactive Waste Management and Safety of other Nuclear Installations in the Slovak Republic; (5.1) Generation and minimisation of radioactive waste; (5.2) Management of radioactive waste; (5.3) Pre-disposal management of radioactive waste; (5.4) Disposal of radioactive waste; (5.5) Shipment of radioactive waste; (5.6) Safety of other nuclear installations in the Slovak Republic; (6) Personnel Qualification and Training; (7) Nuclear Materials and Physical Protection of Nuclear installations; (8) Emergency Preparedness; (9) International Co-operation; (10) Public Communication; (11) UJD SR; (11.1) UJD SR organizational chart; (11.2) UJD SR organizational chart; (11.3) Human resources and training; (11.4) Internal system of quality assurance; (11.5) Development of UJD SR regulatory activities; Appendix: Abbreviations; Development of UJD SR regulatory activities

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

    International Nuclear Information System (INIS)

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

  20. Report on activities of Nuclear Regulatory Authority of the Slovak Republic and safety of nuclear installations in the Slovak Republic in 2009. Annual report

    International Nuclear Information System (INIS)

    A brief account of activities carried out by the Nuclear Regulatory Authority of the Slovak Republic (UJD SR) in 2009 is presented. These activities are reported under the headings: (1) Foreword; (2) Legislation; (3) Issuance of authorizations, assessment, supervisory activities and enforcement; (4) Nuclear safety of nuclear installations in the Slovak Republic; (5) Safety of other nuclear installations; (6) Management of radioactive waste; (7) Nuclear materials and physical protection of nuclear materials; (8) Emergency planning and preparedness; (9) International activities; (10) Public communication; (11) Nuclear Regulatory Authority of the Slovak Republic; (12) UJD SR organization chart; (13) Abbreviations.

  1. Report on activities of Nuclear Regulatory Authority of the Slovak Republic and safety of nuclear installations in the Slovak Republic in 2008. Annual report

    International Nuclear Information System (INIS)

    A brief account of activities carried out by the Nuclear Regulatory Authority of the Slovak Republic (UJD SR) in 2008 is presented. These activities are reported under the headings: (1) Foreword; (2) Legislation; (3) Issuance of authorizations, assessment, supervisory activities and enforcement; (4) Nuclear safety of nuclear installations in the Slovak Republic; (5) Safety of other nuclear installations; (6) Management of radioactive waste; (7) Nuclear materials and physical protection of nuclear materials; (8) Activity of Building Office; (9) Emergency planning and preparedness; (10) International activities; (11) Public communication; (11) Nuclear Regulatory Authority of the Slovak Republic; (12) UJD SR organization chart; (13) Abbreviations

  2. Safety review, assessment and regulatory inspection on nuclear fuel cycle installations and nuclear material control

    International Nuclear Information System (INIS)

    The NNSA conducted surveillance in 1999 on the Yibin Nuclear Fuel Plant (YNFP) and the laboratory for the Qinghua HTR elements. A CP was granted for the Pilot Plant of Spent Fuel Reprocessing in NNFP and a review and assessment on nuclear safety for the construction application of product line with the fuel elements of HWR in the Baotou No. 202 plant and a review and assessment was performed. The NNSA approved the nuclear material license at QNPP and performed surveillance on the nuclear material control for the 6 licensees of nuclear material such as the INET/Tu, QNPJVC etc

  3. Environmental monitoring program at CDTN - Brazilian Nuclear Technology Development Centre

    International Nuclear Information System (INIS)

    An environmental monitoring programme was established in 1985 at CDTN'S with the aim to register continuously the level of the environmental radioactivity, to demonstrate that the adopted procedures are in accordance with the national nuclear energy commission requirements, to evaluate the real or potential radiation dose rate for critical groups as well as for the population in the vicinity, to detect eventual failures in effluent liberation control and to take the proper measures, to give information to the population. The paper describes the experimental procedures and the results obtained. (B.C.A.). 12 refs, 02 tabs, 01 fig

  4. Role of prototype ground-test stands in developing transportable nuclear power installations

    International Nuclear Information System (INIS)

    Naval and shipborne (transportable) nuclear power installations (NPI) must incorporate the main constituents of the power installations of nuclear power plants (NPP) and meet some distinguishing specifications. Firstly as a direct consequence of the higher power-to-weight ratio of the installation (due to severe restrictions on its weight and size parameters), the power intensity of the core of the transportable NPI is higher than that of the cores used in NPP. Secondly, in view of the space constraints, a close arrangement of the equipment is necessary. Thirdly, the highly autonomous nature of the transportable NPI increases the stringency of the specifications with respect to the reliability and the service life of NPI that are realized, as a rule, by ensuring high reliability of the individual components and by reserving the extremely important elements (spares) of the systems of the installations. Furthermore, the required overall reliability of the installation and minimization of the number of operators calls for a high degree of automatic control. The prototype stand is a powerful facility for solving the problems related to the development and the assimilation of the newly designed transportable NPI. Its efficiency would be maximum if it is put into operation 2-3 years before completing the construction of the prototype NPI of a given type. In order to ensure efficient operation, it must satisfy certain conditions among which the most important ones are ensuring maximum identity of NPI tested using the stand and the newly created series-produced NPI, availability of powerful facilities for collecting, possessing and storing the obtained information, inclusion of a modeling complex based on the modern computer technology, and the presence of a well developed scientific infrastructure and a structure of the maintenance and engineering services

  5. A program for occupational radiological protection in a nuclear installation linked to a NORM/TENORM phosphate

    International Nuclear Information System (INIS)

    Mining that has natural radionuclides associated with the ore is known as NORM mining. The Santa Quiteria Unit (USQ) is included in this category. It is a NORM phosphate mine that belongs to the Nuclear Industries of Brazil. This unit is divided into two areas: the phosphate mining and production (conventional mining facility, CMF-USQ) and a production of uranium diuranate (nuclear facility, NF-USQ). The NF-USQ must follow the Brazilian legislation for nuclear installation (NF). This legislation is under the responsibility of the Nuclear Energy National Commission - CNEN, the nuclear regulatory agency in Brazil. Brazilian law on NF requires the facility to have a system of radioprotection and also requires the existence of a radiation protection service (RPS), composed of trained professionals and coordinated by a radioprotection supervisor (RS), accredited by CNEN, which manages the implementation of the occupational radiation protection program (ORPP). This work reports on the design of the ORPP for the NF-USQ associated with CMF-USQ, and on the minimum requirements for a RPS and the kinds of monitoring to be carried out. It also aims to classify the areas as for radioprotection aspects, and to indicate the number and qualifications of the radioprotection staff. Moreover, the work also informs the equipment necessary to the operation of the RPS and other relevant parameters. Finally, it explains the models used in estimating doses for occupationally exposed individuals (OEI) and for individuals of the public (IP), and also the derived limits proposed by the operator for the NFUSQ. The NF-USQ will have 51 OEI, of which 11 belonging to the RS, one being the RPS accredited by CNEN. The NF will be composed of 12 areas, 10 being free areas, one will be supervised and one will be a controlled area. Individual and area monitoring will be carried out. The derived limits proposed by the operator are shown in table 1. These derived limits are calculated based on the limit

  6. A program for occupational radiological protection in a nuclear installation linked to a NORM/TENORM phosphate

    Energy Technology Data Exchange (ETDEWEB)

    Pereira, Wagner de S.; Py Junior, Delcy de A. [Industrias Nucleares do Brasil (INB), Pocos de Caldas, MG (Brazil). Unidade de Tratamento de Minerios. Coordenacao de Protecao Radiologica], e-mail: wspereira@inb.gov.br, e-mail: delcy@inb.gov.br; Kelecom, Alphonse [Universidade Federal Fluminense (UFF), Niteroi, RJ (Brazil). Inst. de Biologia. Curso de Pos-Graduacao em Biologia Marinha], e-mail: kelecom@uol.com.br; Mortagua, Valter [Industrias Nucleares do Brasil (INB), Jurubatuba, SP (Brazil). Usina de Interlagos (USIN). Coordenacao da Unidade de Sao Paulo], e-mail: valtermortagua@inb.gov.br

    2009-07-01

    Mining that has natural radionuclides associated with the ore is known as NORM mining. The Santa Quiteria Unit (USQ) is included in this category. It is a NORM phosphate mine that belongs to the Nuclear Industries of Brazil. This unit is divided into two areas: the phosphate mining and production (conventional mining facility, CMF-USQ) and a production of uranium diuranate (nuclear facility, NF-USQ). The NF-USQ must follow the Brazilian legislation for nuclear installation (NF). This legislation is under the responsibility of the Nuclear Energy National Commission - CNEN, the nuclear regulatory agency in Brazil. Brazilian law on NF requires the facility to have a system of radioprotection and also requires the existence of a radiation protection service (RPS), composed of trained professionals and coordinated by a radioprotection supervisor (RS), accredited by CNEN, which manages the implementation of the occupational radiation protection program (ORPP). This work reports on the design of the ORPP for the NF-USQ associated with CMF-USQ, and on the minimum requirements for a RPS and the kinds of monitoring to be carried out. It also aims to classify the areas as for radioprotection aspects, and to indicate the number and qualifications of the radioprotection staff. Moreover, the work also informs the equipment necessary to the operation of the RPS and other relevant parameters. Finally, it explains the models used in estimating doses for occupationally exposed individuals (OEI) and for individuals of the public (IP), and also the derived limits proposed by the operator for the NFUSQ. The NF-USQ will have 51 OEI, of which 11 belonging to the RS, one being the RPS accredited by CNEN. The NF will be composed of 12 areas, 10 being free areas, one will be supervised and one will be a controlled area. Individual and area monitoring will be carried out. The derived limits proposed by the operator are shown in table 1. These derived limits are calculated based on the limit

  7. Assessing and improving the safety culture of non-power nuclear installations

    International Nuclear Information System (INIS)

    The development and application of safety culture principles has understandably focused on nuclear power plant and fuel cycle facilities and has been based on studies in Europe, North America, Japan and Korea. However, most radiation injuries and deaths have resulted from the mishandling of radioactive sources, inadvertent over-exposure to X-rays and critically incidents, unrelated to nuclear power plant. Within the Forum on Nuclear Cooperation in Asia (FNCA), Australia has been promoting initiatives to apply safety culture principles across all nuclear and radiation application activities and in a manner that is culturally appropriate for Asian countries. ANSTO initiated a Safety Culture Project in 1996 to develop methods for assessing and improving safety culture at nuclear and radiation installations other than power reactors and to trial these at ANSTO and in the Asian region. The project has sensibly drawn on experience from the nuclear power industry, particularly in Japan and Korea. There has been a positive response in the participating countries to addressing safety culture issues in non-power nuclear facilities. This paper reports on the main achievements of the project. Further goals of the project are also identified. (author)

  8. Report on Activities of the Nuclear Regulatory Authority of the Slovak Republic and on Safety of Nuclear Installations in the Slovak Republic in 2006. Annual Report 2006

    International Nuclear Information System (INIS)

    A brief account of activities carried out by the Nuclear Regulatory Authority of the Slovak Republic in 2006 is presented. These activities are reported under the headings: Foreword; (1) Vision, Mission and Principles of Activities; (2) Legislation; (3) Issuance of Authorisations, Safety Assessment and Enforcement; (3.1) Issuance of Authorizations/Permissions; (3.2) Assessment and Inspections Activities; (3.3) Safety Assessment and Enforcement; (4) Nuclear Safety of Nuclear Installations in the Slovak Republic; (4.1) Nuclear installations in operation in the Slovak Republic; (4.2) Nuclear Installations under construction in the Slovak Republic; (4.3) Decommissioning of nuclear installations in the Slovak Republic; (5) Safety of Other Nuclear Installations; (5.1) Other Nuclear Installations in Operation; (5.2) Other Nuclear Installations under Construction; (5.3) Other Nuclear Installations under Decommissioning; (6) Management of Radioactive Waste; (6.1) Generation and minimisation of radioactive waste; (6.2) Management of radioactive waste; (6.3) Pre-disposal management of radioactive waste; (6.4) Disposal of radioactive waste; (6.5) Shipment of radioactive waste; (7) Nuclear Materials; (7.1) Accounting for and Control of Nuclear Materials; (7.2) Shipment of Nuclear Materials; (7.3) Illicit Trafficking of Nuclear Materials and Other Radioactive Material; (8) Emergency Planning and Preparedness; (9) International Activities; (9.1) European Affairs; (9.2) Membership in International Organisations; (9.3) Fulfilment of Obligations under International Contractual Instruments; (9.4) Bilateral Co-operation; (10) Public Communication; (11) UJD SR; (11.1) Economy Data; (11.2) Human resources and training; (11.3) Internal Management Quality System; (11.4) Development of UJD SR Regulatory Activities; (12) Abbreviations

  9. Safety review and assessment on nuclear fuel cycle installations and nuclear material control

    International Nuclear Information System (INIS)

    The NNSA conducted regulation on the manufacture line of fuel element for NPP at the Yibin Nuclear Fuel Plant, (YNFP) and the storage pool for spent fuel at the Lanzhou Nuclear Fuel Complex (LNFC), and accepted the construction application of Pilot Plant of Spent Fuel Reprocessing at LNFC and started the review and assessment. Besides, the surveillance and inspection were conducted also for units that had licenses for nuclear materials

  10. Installation and operational approaches for a nuclear steam generator corrosion monitor

    International Nuclear Information System (INIS)

    This paper addresses some of the significant issues regarding the plant installation and operational philosophies of a dedicated corrosion monitor for nuclear steam generators. Proper installation requires: (1) provision for representative introduction of the secondary feedwater, (2) design of the monitors' feedline to prevent settling of suspended solids, (3) proper isolation for inspection and maintenance, and (4) compliance with relevent safety statutes. Various options regarding feedline installation are discussed. Plant interface requirements for the installation are also identified. Since the operational modes for a corrosion monitor can be either ''real time'' (i.e., following plant load conditions including transients) or accelerated (operational conditions which would accelerate deposition of contaminants and hence corrosion), development of a long term test plan is necessary so that a mode can be selected which best meets the utilities specific test goals. Accelerated operation implies that the monitor's test specimen will be exposed to a more adverse corrosion environment than that which exists in the actual operating steam generators. The impact of the operational mode on potential ancillary equipment is presented and control options related to the accelerated mode of operation are discussed

  11. Assessment of the radiological consequences in case of an emergency on a nuclear installation

    International Nuclear Information System (INIS)

    The French Institute for Health Physics and Nuclear Safety (IPSN) has, for emergency cases on nuclear installations, an Emergency Technical Centre (Centre Technique de Crise - CTC) to provide the public authorities with the technical analysis of the events and with information concerning possible developments in terms of potential releases and radiological consequences to the environment. The CTC is connected, by a special line, to the French Meteorological Office so as to have access to meteorological parameters and local forecasts on the nuclear site at all times. For atmospheric dispersion and radiological consequences, three methods have been developed: a set of operational graphs (for first aid), a gaussian plume model and a gaussian puff model (SIROCCO); the latter two models are implanted on a VAX 8530 computer (with graphical monitors) reserved for that purpose

  12. Basic principles and guidelines governing services of the police for the protection of nuclear installations

    International Nuclear Information System (INIS)

    Services of the police can be ordered for physical protection of nuclear installations of any kind and of nuclear materials transports in cases where there is danger that those first responsible cannot cope with the situation. The contribution discusses physical protection measures as a licensing requirement, the duties of the police forces within the given scope, the measures that can and may be taken by the police, the establishment of special commissions, as well as the particular provisions for nuclear materials transports. The provisions governing police services for physical protection have led to an efficient and well furnished system in terms of organisation, personnel, and materials, which guarantees protection to a great extent. (orig./HSCH)

  13. A compact radiation monitoring data acquisition system for space critical nuclear installations

    International Nuclear Information System (INIS)

    With the increased public concern for the harmful effects of nuclear radiation, it has become a mandatory requirement for all the nuclear installations to maintain the radiation levels within the permissible limits during the normal plant operation and also to initiate appropriate actions to prevent the spread of radioactivity during abnormal incidents. This paper describes the details of a compact radiation monitoring system being developed by using an industrial PC/386 computer for a nuclear reactor. The system is designed by adopting a modular I/O architecture for easy maintenance and system upgradation and provides easy to use menu-driven user interactions. This paper highlights the details of system architecture, user interface and the diagnostic features built in to the system in order to improve the system usage and reliability. 2 refs., 2 figs

  14. Experience in conducting regional training courses (RTC) on security of nuclear installations

    International Nuclear Information System (INIS)

    Two regional training courses on nuclear security were organized in India, one in the year 2003 (May, 2003) and the last one in 2004 (October, 2004). Both the training courses were organized in Mumbai, India with participation from 7 regional countries. In the first course, 7 faculties out of 13 were drawn from abroad while in the second course most of the faculties (4 out 14) were from India. Total 46 (23 from India and 23 from regional countries) professionals have been trained in these two training courses, many of them attending such training courses for the first time. The focus of the first course was security of nuclear installations with special emphasis on security and control of radioactive sources. Security culture was dealt for the first time in such a course. Second course, primarily was on physical protection of nuclear installation and material. In both the training courses, besides theoretical lectures and workgroup exercise sessions, a field trip to a nuclear power station demonstrating actual physical protection system were arranged for the benefit of the participants. The participants of both the courses have provided very positive feed back on different aspects of the courses. This paper discusses, the two training courses on nuclear security organized jointly by IAEA and India for the regional countries and discusses the feed back received. It also brings out the plan of action for the courses to be held in immediate future and greater role India can play in the nuclear security initiatives particularly in the area of training and education on physical protection. (author)

  15. Comparison of activity measurements of the 67Ga and 123I at Brazilian nuclear medicine services

    International Nuclear Information System (INIS)

    Since 1998, the National Laboratory for Ionizing Radiations (LNMRI), of Institute for Radioprotection and Dosimetry, belonging to the Brazilian Commission for Nuclear Energy (IRD/CNEN), is conducting a comparison program for the measurements of radiopharmaceutical activities applied to to patients at the nuclear medicine sector, viewing to assessment the quality of that measurements. This work presents the results of three comparison rounds using the 67Ga and 123I, establishing the metrological tracking of the calibrators used by the participants. The results were analysed under the the viewpoint of the conformal with the regulatory authority and show that those comparisons are necessary to improve the quality of radiopharmaceutical measurement activities, identify failures on the equipment and technical procedures used by the nuclear medicine services all over the country

  16. International Conference on Topical Issues in Nuclear Installation Safety: Defence in Depth — Advances and Challenges for Nuclear Installation Safety. Proceedings of an International Conference held in Vienna, Austria, 21-24 October 2013

    International Nuclear Information System (INIS)

    The fifth International Conference on Topical Issues in Nuclear Installation Safety was dedicated to the defence in depth (DID) concept which is fundamental to the safety of nuclear installations. The main focus of the conference was to foster the exchange of information on the implementation of DID and the associated challenges. This CD-ROM contains the papers presented at the conference as well as the summary and conclusions, including recommendations for further actions to strengthen DID and its implementation

  17. Decision process regarding nuclear generation: the Brazilian case

    International Nuclear Information System (INIS)

    Countries face a constant need to expand their electricity generation capacities. Electricity sources in a country and the respective generation technologies have different technical, economic, environmental, social and political characteristics. The evaluation criteria of the generating sources and their technologies must not be restricted to the supply of the increased demand at the lowest cost. Compliance with other public policies must be considered in the decision process of the expansion, for instance, maximize local acquisition and minimize foreign fuel purchase. Countries have different energy resources, as well as different levels of technology and development in their industrial parks. Brazil has many mineral reserves, besides the hydraulic potential, for supporting the expansion. The decision process in this sector, which includes nuclear energy as a sub-sector, requires analyzing and evaluating various information and data. In this stage, a quantitative model providing a first approach for the decision may be applied. The new institutional structure adopted in the sector during the 1990s and 2000s brought about new conditions into an already complex decision process. In such context of methodology complexity, political aspects gain relevance, becoming of increased importance. The political environment is described and the players are identified. One conclusion and a few recommendations are provided. (author)

  18. Genetic variability in mitochondrial and nuclear genes of Larus dominicanus (Charadriiformes, Laridae) from the Brazilian coast.

    Science.gov (United States)

    de Mendonça Dantas, Gisele Pires; Meyer, Diogo; Godinho, Raquel; Ferrand, Nuno; Morgante, João Stenghel

    2012-12-01

    Several phylogeographic studies of seabirds have documented low genetic diversity that has been attributed to bottleneck events or individual capacity for dispersal. Few studies have been done in seabirds on the Brazilian coast and all have shown low genetic differentiation on a wide geographic scale. The Kelp Gull is a common species with a wide distribution in the Southern Hemisphere. In this study, we used mitochondrial and nuclear markers to examine the genetic variability of Kelp Gull populations on the Brazilian coast and compared this variability with that of sub-Antarctic island populations of this species. Kelp Gulls showed extremely low genetic variability for mitochondrial markers (cytb and ATPase) and high diversity for a nuclear locus (intron 7 of the β-fibrinogen). The intraspecific evolutionary history of Kelp Gulls showed that the variability found in intron 7 of the β-fibrinogen gene was compatible with the variability expected under neutral evolution but suggested an increase in population size during the last 10,000 years. However, none of the markers revealed evidence of a bottleneck population. These findings indicate that the recent origin of Kelp Gulls is the main explanation for their nuclear diversity, although selective pressure on the mtDNA of this species cannot be discarded. PMID:23271950

  19. Genetic variability in mitochondrial and nuclear genes of Larus dominicanus (Charadriiformes, Laridae from the Brazilian coast

    Directory of Open Access Journals (Sweden)

    Gisele Pires de Mendonça Dantas

    2012-01-01

    Full Text Available Several phylogeographic studies of seabirds have documented low genetic diversity that has been attributed to bottleneck events or individual capacity for dispersal. Few studies have been done in seabirds on the Brazilian coast and all have shown low genetic differentiation on a wide geographic scale. The Kelp Gull is a common species with a wide distribution in the Southern Hemisphere. In this study, we used mitochondrial and nuclear markers to examine the genetic variability of Kelp Gull populations on the Brazilian coast and compared this variability with that of sub-Antarctic island populations of this species. Kelp Gulls showed extremely low genetic variability for mitochondrial markers (cytb and ATPase and high diversity for a nuclear locus (intron 7 of the β-fibrinogen. The intraspecific evolutionary history of Kelp Gulls showed that the variability found in intron 7 of the β-fibrinogen gene was compatible with the variability expected under neutral evolution but suggested an increase in population size during the last 10,000 years. However, none of the markers revealed evidence of a bottleneck population. These findings indicate that the recent origin of Kelp Gulls is the main explanation for their nuclear diversity, although selective pressure on the mtDNA of this species cannot be discarded.

  20. Safety management on nuclear fuel cycle installations and nuclear material control

    International Nuclear Information System (INIS)

    In 1998, the NNSA conducted some inspections on the YIBIN Nuclear Fuel Fabrication Plant that was under normal operation and the Pilot plant of NPP spent fuel Reprocessing that was construction at the Lanzhou Nuclear Fuel Complex. The NNSA also issued the OP to Tsinghua University for its Fuel Fabrication Laboratory of HTR-10 after safety review. The NNSA conducted the safety review on the CP application for the Fabrication Facility of Fuel Element for Heavy Water Reactor (CANDU-6) at the Baotou Nuclear Fuel Plant of CNNC in Baotou. The NNSA finished the safety review on the Beilong intermediate-level and low-level Radioactive Waste Repository in Guangdong. The NNSA conducted some inspections on the nuclear material control, and completed the verification of the Nuclear Material License of China Corporation of Atomic Energy Industry and other two organizations

  1. Report on activities of Nuclear Regulatory Authority of the Slovak Republic and safety of nuclear installations in the Slovak Republic in 2007. Annual report

    International Nuclear Information System (INIS)

    A brief account of activities carried out by the Nuclear Regulatory Authority of the Slovak Republic (UJD SR) in 2007 is presented. These activities are reported under the headings: (1) Foreword; (2) Legislation; (3) Issuance of authorizations, assessment, supervisory activities and enforcement; (4) Nuclear safety of nuclear installations in the Slovak Republic; (5) Safety of other nuclear installations; (6) Management of radioactive waste; (7) Nuclear materials; (8) Emergency planning and preparedness; (9) International activities; (10) Public communication; (11) Nuclear Regulatory Authority of the Slovak Republic; (12) Abbreviations

  2. Brazilian navy nuclear propulsion program catalytic of the national technological development

    International Nuclear Information System (INIS)

    The Naval Propulsion Development Program, leading by the Brazilian Navy, is one of the greatest self-sufficient technological efforts ever undertaken in Brazil. Besides the technological spin-offs, this program served as catalyst to maintain a critical mass of human resources, mainly in the 80's and early of 90's, when the destiny of the nuclear sector was uncertain. Today the R and D perspectives in Brazil are different, but this program is still updated with this new reality. This paper presents the main characteristics and the present status of this program. (author)

  3. Safety culture in nuclear installations: Summary of an international topical meeting

    International Nuclear Information System (INIS)

    An international topical meeting, Safety Culture in Nuclear Installations, was organized by the American Nuclear Society (ANS) Austria Local Section, cosponsored by the ANS Nuclear Reactor Safety and Human Factors Divisions in cooperation with the Nuclear Energy Agency of the Organization for Economic Cooperation and Development (NEA/OECD) and held in Vienna April 24-28, 1995. Some 250 experts from 30 different countries and organizations took part in the 85 paper presentations and two workshops. The concept of safety culture was initially used in the first International Nuclear Safety Advisory Group (INSAG) report on the Chernobyl accident analysis report in 1986. Although some elements of safety culture have been used over the years in nuclear safety activities, the new phrase safety culture and the concept were found interesting as highlighting the 'soft' aspects of safety and as encompassing more than human errors. Unfortunately, for many years it was used more in the way of identifying lack of safety culture. Conscious of this application, INSAG further developed the safety culture concept in the INSAG 4 report: The report contains a definition, the universal aspects of safety culture, the two main components of safety culture management and individual behaviour, and performance indicators of a good safety culture. This report is now quite famous and adopted with some additions or complementary definitions by many institutes and organizations for their daily activities

  4. IAEA Assistance to developing countries in the regulation of nuclear installations

    International Nuclear Information System (INIS)

    The paper analyses the IAEA assistance to developing countries in the regulation of nuclear installations. The projected growth of nuclear power both in industrialised and developing IAEA Member States has led to a reassessment of the role that the Agency should play pursuant to its statutory obligation in the area of nuclear safety. Accelerated work was begun nearly 3 years ago to establish a wide range of recommendations essential in matters of nuclear power plant safety so as to provide an internationally acceptable body of basic criteria and minimum requirements. In recent years the IAEA has increasingly provided advisory services to developing countries for the elaboration of enabling legislation; also intensive training programmes covering specific nuclear safety and regularoty topics have been carried out through special training courses and conducted in co-operation with host countries with extensive nuclear experience and appropriate training facilities. Experience has shown that these services have been of practical help to national authorities in providing guidance and initiatives for speeding up the process of framing laws and regulations. (NEA)

  5. European Community (Radiological and Nuclear Medicine Installations) Regulations, 1998. Statutory Instrument S.I. No. 250 of 1998

    International Nuclear Information System (INIS)

    These regulations establish the criteria of acceptability to be met for radiological installations and nuclear medicine installations. The regulations implement the provisions of EC Directive 84/466 Euratom of 3 September 1984 laying down the basic measures for radiation protection of persons undergoing medical examinations or treatment and to provide protection for workers and the general public. (author)

  6. Topical issues in nuclear installation safety: Continuous improvement of nuclear safety in a changing world. Proceedings of an international conference

    International Nuclear Information System (INIS)

    In 1991, the IAEA organized an International Conference on the Safety of Nuclear Power: Strategy for the Future. Recommendations from that conference prompted actions in subsequent installations worldwide, and included the establishment of the Convention on Nuclear Safety, which entered into force in October 1996. In 1998, the IAEA sponsored an International Conference on Topical Issues in Nuclear, Radiation and Radioactive Waste Safety. In response to the concerns identified and the recommendations provided by the conference, actions were taken to improve the monitoring of safety by developing performance indicators; furthering the use of probabilistic safety insights to complement and help optimize the prescriptive nature of regulations; and addressing actions needed to ensure the future availability of competent professionals. In 2001, the IAEA sponsored an International Conference on Topical Issues in Nuclear Safety. The findings were again essential in providing Member States, the IAEA and the nuclear industry with insights into where future activities should be focused. Some of these areas included the need to develop international guidance on the use of probabilistic safety insights, the potential negative impacts on safety from external factors, the need for emergency preparedness guidance for fuel cycle facilities, the safety challenges associated with poor utilization programmes at research reactors, and the need to develop simple indicators of safe operating performance. Although substantial progress has been made in improving the safe operational performance of nuclear installations over the past years, numerous issues continue to be of concern. These include ensuring quality of design and operation of nuclear installations with the growing diversification and globalization of the nuclear community, obtaining, maintaining and managing knowledge, utilizing common internationally accepted safety standards, balancing the needs between safety and security

  7. The year 2000 embedded systems problem to maintain the safety of nuclear installations

    International Nuclear Information System (INIS)

    The Y2K problem may impact on nuclear installations in a number of ways because embedded systems are used in nuclear routine operation, monitoring and control system. The very simplest embedded systems are capable of performing only a single function or set of functions to meet a single predetermined purpose. In more complex systems the functioning of the embedded system is determined by an application program that enables the embedded system to be used for a particular purpose in a specific application. The simplest devices consist of a single microprocessor which may itself be packaged with other chips in a hybrid system or Application Specific Integrated Circuit (ASIC). Its input comes from a detector or sensor and its output goes to a switch or activator which may start or stop the operation of a positioning motors or, by operating a valve, may control the flow of cooling system to reactor core. Embedded systems in our organization are also be found in Batan security systems. These include systems for the security of buildings and premises, and in the communication systems on which these depend. In the enclosed paper we demonstrate the use of analytic model and reliability analysis. The subject of this reliability test is to detect the components of the embedded system with PLC's that could fail on Y2K problem in nuclear installation and safety system. (author)

  8. The high-temperature sodium coolant technology in nuclear power installations for hydrogen power engineering

    Science.gov (United States)

    Kozlov, F. A.; Sorokin, A. P.; Alekseev, V. V.; Konovalov, M. A.

    2014-05-01

    In the case of using high-temperature sodium-cooled nuclear power installations for obtaining hydrogen and for other innovative applications (gasification and fluidization of coal, deep petroleum refining, conversion of biomass into liquid fuel, in the chemical industry, metallurgy, food industry, etc.), the sources of hydrogen that enters from the reactor plant tertiary coolant circuit into its secondary coolant circuit have intensity two or three orders of magnitude higher than that of hydrogen sources at a nuclear power plant (NPP) equipped with a BN-600 reactor. Fundamentally new process solutions are proposed for such conditions. The main prerequisite for implementing them is that the hydrogen concentration in sodium coolant is a factor of 100-1000 higher than it is in modern NPPs taken in combination with removal of hydrogen from sodium by subjecting it to vacuum through membranes made of vanadium or niobium. Numerical investigations carried out using a diffusion model showed that, by varying such parameters as fuel rod cladding material, its thickness, and time of operation in developing the fuel rods for high-temperature nuclear power installations (HT NPIs) it is possible to exclude ingress of cesium into sodium through the sealed fuel rod cladding. However, if the fuel rod cladding loses its tightness, operation of the HT NPI with cesium in the sodium will be unavoidable. Under such conditions, measures must be taken for deeply purifying sodium from cesium in order to minimize the diffusion of cesium into the structural materials.

  9. Safety culture in nuclear installations: Bangladesh perspectives and key lessons learned from major events

    International Nuclear Information System (INIS)

    Steps necessary to be taken to ensure safety in nuclear installations are suggested. One of the steps suggested is enhancing the safety culture. It is necessary to gain a common understanding of the concept itself, the development stages of safety culture by way of good management practices and leadership for safety culture improvement in the long-term. International topical meetings on safety culture may serve as an important forum for exchange of experiences. From such conventions new initiatives and programmes may crop up which when implemented around the world is very likely to improve safety management and thus boost up the safety culture in nuclear installations. International co-operation and learning are to be prompted to facilitate the sharing of the achievements to face the challenges involved in the management of safety and fixing priorities for future work and identify areas of co-operations. Key lessons learned from some major events have been reported. Present status and future trend of nuclear safety culture in Bangladesh have been dealt with. (author)

  10. Radiation exposure as a result of radioactivity in the vicinity of nuclear installations

    International Nuclear Information System (INIS)

    The nuclear industry in South Africa is expected to expand dramatically and, as a result, the effects of radioactive effluent from these installations on the environment will be of great practical and scientific importance. The long-term effects of low-level radiation cannot be clinically predicted; physical determination and prediction is therefore the accepted measure of radiation exposure. This study includes a survey of all forms of natural and man-made radiation to which the general public is constantly exposed. An intensive study was made of radioactive fallout over South Africa from nuclear bomb tests. From this the general radiation exposure of the South African public could be calculated. It also led to valuable scientific information on mesometeorology and health physics. The latter includes the relationship between air concentration and deposition, the transfer of airborne iodine-131 to milk, and the accumulation of strontium-90 and cesium-137 in human beings as a result of their diets. Thorough environmental studies were conducted at existing nuclear installation sites i.e. Pelinbada which is the site of the National Nuclear Research Centre and Dynefontein which is the proposed site of South Africa's first nuclear power station. These included meso-meteorology, atmospheric dispersion by means of neutron-activable tracers, accumulation factors for important radionuclides in edible marine species by means of stable element tracers, population surveys, background radioactivity surveys etc. From these results critical exposure pathways were established for both sites and the relationship between effluent release and radiation dose to the public was determined. This has lead to the establishment of maximum permissible releases for the operation of the SAFARI-1 research reactor by the Atomic Energy Board and for the specifications of the proposed Koeberg power reactors to be operated by the Electricity Supply Commission at Dynefontein

  11. The Contribution of Palaeoseismology to Seismic Hazard Assessment in Site Evaluation for Nuclear Installations

    International Nuclear Information System (INIS)

    IAEA Safety Standards Series No. SSG-9, Seismic Hazards in Site Evaluation for Nuclear Installations, published in 2010, covers all aspects of site evaluation relating to seismic hazards and recommends the use of prehistoric, historical and instrumental earthquake data in seismic hazard assessments. Prehistoric data on earthquakes cover a much longer period than do historical and instrumental data. However, gathering such data is generally difficult in most regions of the world, owing to an absence of human records. Prehistoric data on earthquakes can be obtained through the use of palaeoseismic techniques. This publication describes the current status and practices of palaeoseismology, in order to support Member States in meeting the recommendations of SSG-9 and in establishing the necessary earthquake related database for seismic hazard assessment and reassessment. At a donors’ meeting of the International Seismic Safety Centre Extrabudgetary Project in January 2011, it was suggested to develop detailed guidelines on seismic hazards. Soon after the meeting, the disastrous Great East Japan Earthquake and Tsunami of 11 March 2011 and the consequent accident at the Fukushima Daiichi nuclear power plant occurred. The importance of palaeoseismology for seismic hazard assessment in site evaluation was highlighted by the lessons learned from the Fukushima Daiichi nuclear power plant accident. However, no methodology for performing investigations using palaeoseismic techniques has so far been available in an IAEA publication. The detailed guidelines and practical tools provided here will be of value to nuclear power plant operating organizations, regulatory bodies, vendors, technical support organizations and researchers in the area of seismic hazard assessment in site evaluation for nuclear installations, and the information will be of importance in support of hazard assessments in the future

  12. Evaluation of the accomplishment of the Brazilian regulation 'Portaria No. 453/98' in mammography X-ray sets installed in the Sergipe state, Brazil

    International Nuclear Information System (INIS)

    In this work was done an evaluation of the accomplishment of the regulation 'Portaria No. 453/98' of the Ministry of Health in mammography machine installed in the Sergipe state, Brazil. The quality control procedures were carried out in 23 equipments currently used in clinical routine. The testing methodologies are described in documents of two Brazilian institutions: ANVISA and Brazilian College of Radiology. The following results are expressed on percentage of equipments that were in conformity with minimum requirement of the regulation, considering separately the three kinds of the tests above mentioned. About mechanical parts: compression force (70%), coincidence between the radiation field and the radiographic film (80%) and distortion of the plate compression (47%). About image analysis: performance and reproducibility of the automatic exposure control (54% and 63% respectively), and image quality (84%). In the item beam radiation quality: reproducibility and linearity of the air rate kerma (100% and 84% respectively). In the automatic processors were monitored the following parameters: temperature (70%), pH (65%) and dry-to-dry processing time (25%). The unsatisfactory test results of the plate compression and automatic exposure control jeopardize the expected balance between dose distribution and image quality. This unbalance has significant effects on image nonuniformity and/or a localized dose increment. Even though the results of the tests of image quality and air Kerma rate can be considered satisfactory they are not enough for a full evaluation because they do not take into account the interaction with the object of interest: the breast. The results of the time processing suggest that the operators must change the parameters of the technique employed, attempting to maintain the image quality without resulting in an increase of the absorbed dose. (author)

  13. The interest of intervention of foreign communities in the litigation about nuclear installation authorizations

    International Nuclear Information System (INIS)

    The author comments the decision of inadmissibility taken by the French State Council about the validity of legal actions undertaken by foreign communities (for instance Swiss communities) to challenge the legality of a decision authorizing the creation of a nuclear installation located in France. The author outlines and comments the fact that, despite this decision of inadmissibility, the Council applies unprecedented criteria to judge the appeal admissibility. In a second part, the author discusses the importance of the risk factor and the way it assessed by the administrative court

  14. Nuclear installations and childhood leukaemia - testing the hypotheses, exploring the implications - a review

    International Nuclear Information System (INIS)

    The main thesis of this paper has been to demonstrate the particular phenomenology of the nuclear installations/childhood leukaemia sagas and to infer the scientific and public policy implications of the experience of investigation of these hypotheses and their confounders. If, as appears to be the case, we live in a period where science policy is more populist and thus liable to be impacted more directly and immediately by 'public concern' issues, it follows that there may also be new challenges for public information and understanding and new requirements for the operation of the process of public science policy. (author)

  15. Influence of radioactive effluents from nuclear installations on mortality of the woods

    International Nuclear Information System (INIS)

    Referring to a theory of Reichelt that also radioactive materials, effused from nuclear installations and uranium ores, can contribute to mortality of the woods, it is checked, by studying corresponding literature, to what extent this agrees with the facts. According to this study the radionuclides seem to contribute to the internal and external radiation doses of plants. However these doses are so small with respect to natural radiation doses that it is highly unprobable that this effect contributes to damage of the woods. (Auth.)

  16. Proceedings of the 2. SIPEN: Integration week from IPEN - Brazilian Institute for Energy and Nuclear Researches, CNEN/SP

    International Nuclear Information System (INIS)

    The technical-scientific activities of IPEN (Instituto de Pesquisas Energeticas e Nucleares), Brazilian CNEN, has been presented in these proceedings. It includes the following topics: management and logistics, infra-structure and support, application of nuclear techniques, fuel cycle, materials, reactor research, development of products and services, radiation protection and monitoring. Nuclear medicine and application of radiation in biological assays are studied. Environmental impacts and management of radioactive wastes are also presented

  17. Radioactivity monitoring of areas near nuclear installations in Baden-Wuerttemberg. Annual report 1997

    International Nuclear Information System (INIS)

    The report presents the results of radioactivity monitoring measurements by the Landesanstalt fuer Umweltschutz in the reporting period of 1997. The sites monitored under the monitoring programme of the Land Baden-Wuerttemberg are the Karlsruhe Research Center, the nuclear power stations at Obrigheim, Neckarwestheim and Philippsburg, and the TRIGA research reactor at Heidelberg. Foreign nuclear power stations located near the border to Baden-Wuerttemberg are those in Switzerland, namely at Beznau/Leibstadt and Villigen, and the Fessenheim nuclear power station in France. Measurements cover the local gamma dose, aerosols and precipitations in the stations' environments, and radioactivity measurements in samples of soil, vegetation, food plants, milk and milk products, surface waters, sediments, fish, and drinking water. Depending on the environmental media, samples are taken and measured throughout the year, or in particular seasons only. The measured values still reflect the presence of long-lived fallout from former nuclear weapons tests and the Chernobyl reactor accident. Traces of licensed discharges from the nuclear installations could be detected in some cases, primarily in surface waters. The values measured are within the limits defined by radiation protection regulations and are negligible within the limits for radiation exposure of the population. Measured values did not indicate any illegal discharges or radioactivity release exceeding the maximum permissible levels. (orig./CB)

  18. On alteration of reactor installation (additional installation of No.3 and No.4 plants in the Genkai Nuclear Power Station, Kyushu Electric Power Co., Inc.)

    International Nuclear Information System (INIS)

    The Nuclear Safty Commission sent the reply to the Minister of International Trade and Industry on October 4, 1984, on this matter after having received the report from the Committee on Examination of Nuclear Reactor Safety and carried out the deliberation. It was judged that the applicant has the technical capability required for installing and operating these reactor facilities. Also it was judged that on the safety after these reactor plants are installed, there is no obstacle in the prevention of disaster due to contaminated substances and reactors. The policy of the investigation and deliberation is reported. The contents of the investigation and deliberation are the condition of location such as site, geological features and ground, earthquake, weather, hydraulic problem and social environments, the safety design of reactor facilities, the evaluation of radiation exposure dose in normal operation, the analysis of abnormal transient change in operation, accident analysis and the evaluation of location. (Kako, I.)

  19. Contributions by emissions from nuclear installations to concentrations of radionuclides in milk

    CERN Document Server

    Green, N

    1983-01-01

    A year-long study has been carried out to determine whether milk produced near nuclear sites contains concentrations of radionuclides that can be attributed to discharges from the installations, and, as a consequence, whether there is enhanced exposure of those members of the public who consume this milk. Eight creameries were chosen and monthly samples of milk were taken for analysis. The concentrations of caesium-137 and strontium-90 were measured and compared with results from a national survey conducted as part of the Board's environmental radioactivity surveillance programme. No effect attributable to discharges from the nuclear establishments was identified. The activity concentrations ranged between 0.1 and 3 times the national average; the variation relates mainly to rainfall in the area, although other factors may also have an effect. However, milk contributes only a small fraction of the total dietary intake of caesium-137 and strontium-90, and so the exposure of persons consuming the milk varies on...

  20. Perspectives of application of thermoelectric generators in nonserviced nuclear power installations

    International Nuclear Information System (INIS)

    The experience in operating thermoelectrogenerators of various purpose is analyzed. The possibilities of using the thermoelectrogenerators in the nonserviced nuclear power installations are considered. The technical data on the operating and planned nuclear thermopower facilities (NTPF) are presented. The scientific-research complex Gamma-5 consisting of a water-water reactor and thermogenerator, mounted from thermoelectrical module, is described. The bench tests proved the ability of the facility to operate in the self-regulation mode. The project of the nonserviced NTPF Elena with the thermal capacity of 5 MW and electrical capacity of 100 kW is developed on the basis of the Gamma-5 complex operational results. This nonserviced NTPF is designed for the heat and electricity supply of small settlements and industrial zones

  1. Radioactivity monitoring of areas near nuclear installations in Baden-Wuerttemberg. Annual report 2004

    International Nuclear Information System (INIS)

    This report presents the results of radioactivity monitoring in the vicinity of nuclear installations in the year 2004. Monitoring activities comprise the measurement of local gamma dose rates, aerosols and precipitation in the surrounding area, as well as examinations on soil, vegetation, vegetable foods, milk and dairy products, surface waters, sediments, fish and drinking water. Samples are collected year round or seasonally, depending on the medium in question. Due consideration is given to the particular features of a region such as tobacco or wine growing. All data obtained are in the safe range and as far as public radiation exposure is concerned negligible. Newly included in the monitoring programme since 2002 are interim repositories that are required for storing spent fuel elements on the premises of the nuclear power plants in Philippsburg and Neckarwestheim. The programme as well as the monitoring results are attached to this report. Local gamma and neutron dose rates are either below or only slightly above detection threshold

  2. Study of populations living near nuclear facilities. Etude des populations habitant pres des installations nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    Hubert, D. (Electricite de France (EDF), 75 - Paris (France). Comite de Radioprotection); Hill, C. (Centre de Lutte Contre le Cancer Gustave-Roussy, 94 - Villejuif (France))

    1994-01-01

    After the observation in 1983 of a leukaemia cluster among children living near the Sellafield nuclear waste reprocessing plant (United Kingdom), numerous epidemiologic studies have been conducted on the risk of cancer or leukaemia in populations in the vicinity of nuclear installations. The methodology of these cohort and case-control studies of mortality or of incidence is reviewed. Some cohort studies have shown an excess of childhood leukaemia, but only in the UK; French, US, Canadian and German studies were negative. In 1990, a first case-control study found a relationship between the risk of leukaemia in children living around Sellafield and the professional exposure of their father to ionizing radiation before conception, but all further studies were negative. A viral infection, facilitated by large influxes of people into isolated areas, has also been suggested as a possible cause of the excess leukaemias. (authors). 26 refs., 3 tabs.

  3. A method and installation for reducing radioactive emissions in a nuclear power station

    International Nuclear Information System (INIS)

    The invention relates to an installation for reducing radioactive emissions in a nuclear power station. The radioactive emissions resulting from leakages between the primary and secondary liquids in a steam-generator of a pressurized-water nuclear power-station are reduced by placing a demineralizer in the exhaust of the draining tank and also by sending the draining tank steam towards the condenser. In case of major failures leading to the power station stoppage, an auxiliary turbine is used, the latter being designed for being actuated by the steam derived from the main steam conduit. The auxiliary turbine drives the pumps for pumping the cooling-water intended for the condenser. The steam driving the auxiliary turbine is exhausted towards the condenser, too. Condensed water is returned to the steam generator and is evacuated through the draining tank

  4. ASN guide project. Safety policy and management in INBs (base nuclear installations)

    International Nuclear Information System (INIS)

    This guide presents the recommendations of the French Nuclear Safety Authority (ASN) in the field of safety policy and management (PMS) for base nuclear installations (INBs). It gives an overview and comments of some prescriptions of the so-called INB order and PMS decision. These regulatory texts define a framework for provisions any INB operator must implement to establish his safety policy, to define and implement a system which allows the safety to be maintained, the improvement of his INB safety to be permanently looked for. The following issues are addressed: operator's safety policy, identification of elements important for safety, of activities pertaining to safety, and of associated requirements, safety management organization and system, management of activities pertaining to safety, documentation and archiving

  5. Development of processes for the utilization of Brazilian coal using nuclear process heat and/or nuclear process steam

    International Nuclear Information System (INIS)

    Status of the project: End of the project definition phase and preparation of the planned conceptual phase. Objective of the project: Development of processes for the utilization of nuclear process heat and/or nuclear process steam for the gasification of coal with high ash content, in particular coal from Brazil. Results: With the data of Brazilian coal of high ash content (mine Leao/ 43% ash in the mine-mouth quality, 20% ash after preparation) there have been worked out proposals for the mine planning and for a number of processes. On the basis of these proposals and under consideration of the main data specified by the Brazilian working group there have been choosen two processes and worked out in a conceptual design: 1) pressurized water reactor + LURGI-pressure gasifier/hydrogasification for the production of SNG and 2) high temperature reactor steam gasification for the production of town gas. The economic evaluation showed that the two processes are not substantially different in their cost efficiency and they are economical on a long-term basis. For more specific design work there has been planned the implementation of an experimental programme using the semi-technical plants 'hydrogasification' in Wesseling and 'steam gasification' in Essen as the conceptual phase. (orig.)

  6. Regulatory oversight report 2009 concerning nuclear safety in Swiss nuclear installations

    International Nuclear Information System (INIS)

    ENSI, the regulatory body of the Swiss Confederation, assesses and monitors the nuclear safety of nuclear facilities in Switzerland. These include the five nuclear power plants (NPPs), the plant-based interim storage facilities, the Central Interim Storage Facility (ZWILAG) at Wuerenlingen, as well as the nuclear facilities at the Paul Scherrer Institute (PSI) and the two universities of Basel and Lausanne (EPFL). Its regulatory obligations also include the transport of radioactive materials from and to nuclear facilities and the preparation of a deep geological repository for radioactive waste. ENSI maintains its own emergency organisation that would be activated in case of a serious incident at a nuclear facility in Switzerland. The legislative framework for ENSI's regulatory functions are the Nuclear Energy Act (KEG), the Nuclear Energy Ordinance (KEV), the Radiological Protection Act (StSG), the Radiological Protection Ordinance (StSV), as well as other ordinances and regulations related to reactor safety, the training of operating personnel, the organisation of the emergency response to increases in radioactivity, the transport of radioactive materials, and the deep geological repository. ENSI formulates and updates guidelines that stipulate the criteria by which it evaluates the activities and plans put forward by the operators of nuclear facilities. It regularly publishes reports and provides the public with information on events and findings at nuclear facilities. Chapters 1 to 4 of this Surveillance Report are devoted to the five Swiss NPPs. For each plant, the ENSI evaluation concludes with a safety ranking: high, good, satisfactory and unsatisfactory. Chapter 5 deals with ZWILAG for the processing and interim storage of radioactive waste from Swiss nuclear facilities. Chapters 6 and 7 deal with the nuclear facilities at PSI and with the research reactors at Basel and at EPFL. Chapter 8 deals with the transport of radioactive materials from and to nuclear

  7. Regulatory oversight report 2012 concerning nuclear safety in Swiss nuclear installations

    International Nuclear Information System (INIS)

    The Swiss Federal Nuclear Safety Inspectorate (ENSI) assesses and monitors nuclear facilities in Switzerland. These include the five nuclear power plants, the interim storage facilities based at each plant, the Central Interim Storage Facility (ZWILAG) and the nuclear facilities at the Paul Scherrer Institute (PSI), at the Federal Institute of Technology in Lausanne (EPFL) and at the University of Basel. Using a combination of inspections, regulatory meetings, examinations and analyses together with reports from the licensees of individual facilities, ENSI obtains the required overview of nuclear safety in the relevant facilities. It ensures that the facilities comply with the regulations and operate as required by law. Its regulatory responsibilities also include the transport of radioactive materials from and to nuclear facilities and the preparations for a deep geological repository for nuclear waste. ENSI maintains its own emergency organisation. It formulates and updates its own guidelines which stipulate the criteria for evaluating the current activities and future plans of the operators of nuclear facilities. ENSI produces regular reports on its regulatory activities and nuclear safety in Swiss nuclear facilities. It fulfils its statutory obligation to provide the public with information on particular events and findings in nuclear facilities. In 2012, the five nuclear power plants in Switzerland were all operated safely. 34 events were reported; on the international INES scale of 0 to 7, ENSI rated 33 events as Level 0 and 1 as Level 1. ENSI evaluates the safety of each nuclear power plant as part of a systematic safety evaluation taking account of both reportable events and other findings, in particular the results of more than 400 inspections conducted by ENSI during 2012. ZWILAG consists of several interim storage halls, a conditioning plant and an incineration/melting plant. At the end of 2012, the cask storage hall contained 40 transport/storage casks

  8. Root Cause Analysis Following an Event at a Nuclear Installation: Reference Manual. Companion CD

    International Nuclear Information System (INIS)

    Following an event at a nuclear installation, it is important to determine accurately its root causes so that effective corrective actions can be implemented. As stated in IAEA Safety Standards Series No. SF-1, Fundamental Safety Principles: “Processes must be put in place for the feedback and analysis of operating experience”. If this process is completed effectively, the probability of a similar event occurring is significantly reduced. Guidance on how to establish and implement such a process is given in IAEA Safety Standards Series No. NS-G-2.11, A System for the Feedback of Experience from Events in Nuclear Installations. To cater for the diverse nature of operating experience events, several different root cause analysis (RCA) methodologies and techniques have been developed for effective investigation and analysis. An event here is understood as any unanticipated sequence of occurrences that results in, or potentially results in, consequences to plant operation and safety. RCA is not a topic uniquely relevant to event investigators: knowledge of the concepts enhances the learning characteristics of the whole organization. This knowledge also makes a positive contribution to nuclear safety and helps to foster a culture of preventing event occurrence. This publication allows organizations to deepen their knowledge of these methodologies and techniques and also provides new organizations with a broad overview of the RCA process. It is the outcome of a coordinated effort involving the participation of experts from nuclear organizations, the energy industry and research centres in several Member States. This publication also complements IAEA Services Series No. 10, PROSPER Guidelines: Guidelines for Peer Review and for Plant Self- Assessment of Operational Experience Feedback Process, and is intended to form part of a suite of publications developing the principles set forth in these guidelines. In addition to the information and description of RCA

  9. Root Cause Analysis Following an Event at a Nuclear Installation: Reference Manual

    International Nuclear Information System (INIS)

    Following an event at a nuclear installation, it is important to determine accurately its root causes so that effective corrective actions can be implemented. As stated in IAEA Safety Standards Series No. SF-1, Fundamental Safety Principles: “Processes must be put in place for the feedback and analysis of operating experience”. If this process is completed effectively, the probability of a similar event occurring is significantly reduced. Guidance on how to establish and implement such a process is given in IAEA Safety Standards Series No. NS-G-2.11, A System for the Feedback of Experience from Events in Nuclear Installations. To cater for the diverse nature of operating experience events, several different root cause analysis (RCA) methodologies and techniques have been developed for effective investigation and analysis. An event here is understood as any unanticipated sequence of occurrences that results in, or potentially results in, consequences to plant operation and safety. RCA is not a topic uniquely relevant to event investigators: knowledge of the concepts enhances the learning characteristics of the whole organization. This knowledge also makes a positive contribution to nuclear safety and helps to foster a culture of preventing event occurrence. This publication allows organizations to deepen their knowledge of these methodologies and techniques and also provides new organizations with a broad overview of the RCA process. It is the outcome of a coordinated effort involving the participation of experts from nuclear organizations, the energy industry and research centres in several Member States. This publication also complements IAEA Services Series No. 10, PROSPER Guidelines: Guidelines for Peer Review and for Plant Self- Assessment of Operational Experience Feedback Process, and is intended to form part of a suite of publications developing the principles set forth in these guidelines. In addition to the information and description of RCA

  10. The manpower training and development programs of NUCLEBRAS for the Brazilian nuclear program

    International Nuclear Information System (INIS)

    As technology transfer is one of the main objectives of the Brazilian Nuclear Program, the principal aim of manpower training has been to provide the conditions for absorbing this technology. The strategy used for such a program required a quantitative and qualitative planning of manpower needs, through medium-range and long-term forecasts, with the condition of maximum utilization of the existing educational infra-structure. On-the-job training which is considered one of the most important means for technology transfer, was given highest priority. Also, management development was considered very important for the implementation of the Nuclear Program. This paper shows the results achieved from 1973 up to now by the manpower training and development programs. (Author)

  11. Regulatory oversight report 2010 concerning nuclear safety in Swiss nuclear installations

    International Nuclear Information System (INIS)

    Acting as the regulatory body of the Swiss Confederation, the Swiss Federal Nuclear Safety Inspectorate, ENSI, assesses and monitors nuclear facilities in Switzerland. This includes the five nuclear power plants (NPPs), the plant-based interim storage facilities, the Central Interim Storage Facility (ZWILAG) at Wuerenlingen, the nuclear facilities at the Paul Scherrer Institute (PSI), the two universities of Basel and Lausanne, the transport of radioactive materials from and to nuclear facilities and the preparation for a deep geologic repository for radioactive waste. Using inspections, surveillance meetings, reviews and analyses as well as reports from plant licensees, ENSI obtains the required overview of the safety of the nuclear facilities. It maintains its own emergency organisation, which is an integral part of the national emergency structure. The legislative framework at the basis of the activity of ENSI specifies the criteria by which it evaluates the activities and plans of the operators of nuclear facilities. ENSI provides the public with information on particular events and observations relating to nuclear facilities. The five nuclear power plants in Switzerland (Beznau Units 1 und 2, Muehleberg, Goesgen and Leibstadt) were all operated safely in 2010. Last year, there were 39 notifiable events in Switzerland: 4 events affected both Beznau Units, 10 events the Goesgen NPP, 6 the Leibstadt NPP and 13 the Muehleberg NPP and 6 in other facilities. Based on the International Nuclear Event Scale (INES) of 0-7, ENSI rated 38 events as Level 0, and as INES Level 2 the event on 31 August 2010 during maintenance work at the Leibstadt NPP, where a diver was exposed to radiation in excess of the maximum annual exposure rate of 20 mSv. The ZWILAG at Wuerenlingen consists of several interim storage halls, a conditioning plant and the plasma plant (incineration/melting plant). At the end of 2010, the cask storage hall contained 34 transport/storage casks with spent

  12. Equipment and piping for nuclear power plants, test and research reactors, and nuclear installations

    International Nuclear Information System (INIS)

    The standard concerns the primary and secondary circuits as well as the safety and protection equipment in nuclear power plants with PWR or LWGR type reactors. Rules for design, manufacturing, erection, operation, and maintenance of the reactors, steam generators, vessels, pumps and housings, and pressure pipes are provided

  13. Regulatory oversight report 2011 concerning nuclear safety in Swiss nuclear installations

    International Nuclear Information System (INIS)

    The Swiss Federal Nuclear Safety Inspectorate ENSI, acting as the regulatory body of the Swiss Confederation, assesses and monitors nuclear facilities in Switzerland. These include five nuclear power plants, the interim storage facilities based at each plant, the Central Interim Storage Facility (ZWILAG) at Wuerenlingen together with the nuclear facilities at the Paul Scherrer Institute (PSI) and the two universities of Basel and Lausanne. ENSI ensures that the facilities comply with regulations and operate according to the law. Its regulatory responsibilities also include the transport of radioactive materials to and from nuclear facilities and the preparations for a deep geologic repository for nuclear waste. It maintains its own emergency organisation, which is an integral part of a national emergency structure. Building on the legislative framework, ENSI also formulates and updates its own guidelines. It provides the public with information on particular events and findings in nuclear facilities. In 2011, all five nuclear power reactors in Switzerland (Beznau Units 1 and 2, Muehleberg, Goesgen and Leibstadt) were operated safely and ENSI concluded that they had complied with their approved operating conditions. There were 27 reportable events in the nuclear power plants in Switzerland: 7 at Beznau, 5 at Goesgen, 11 at Leibstadt und 4 at Muehleberg. On the international INES scale of 0 to 7, ENSI rated 26 events as Level 0. One event, at the Muehleberg nuclear power plant, was rated as INES Level 1. This related to a potential blockage of the emergency water intake system in the event of extreme flooding. The operator BKW shut down the Muehleberg plant ahead of the scheduled maintenance date and upgraded the system. ZWILAG consists of several interim storage halls, a conditioning plant and a plasma plant (incineration/melting plant). At the end of 2011, the cask storage hall contained 34 transport/storage casks with fuel assemblies and vitrified residue packages

  14. GANIL: a basic nuclear installation dedicated to research - 'ACROnic du nucleaire' nr 90, September 2010

    International Nuclear Information System (INIS)

    GANIL stands for Grand Accelerateur National d'Ions Lourds (Large National accelerator of heavy ions). It is located in Caen. A new installation for the production of radioactive ions (SPIRAL2) is planned within this research facility. This document briefly describes the use of ion beams to explore matter, and the purpose of GANIL, SPIRAL and SPIRAL2. The construction of this last equipment induces new radiation protection and safety issues which are herein discussed: matter confinement, protection of personnel, waste management (dismantling, storage and transport), and impact of releases on the environment. Annual authorization for gaseous releases and equivalent dose limitations are indicated. The document presents the action of the local information commission (CLI) which has been created in relationship with this nuclear installation, and comments the answers given by the GSIEN (Group of scientists for information on nuclear energy) to questions asked by the CLI about the need for a release authorization, about specified levels, about the waste issue, about incident or accident scenarios, about possibilities to optimize the survey system. A last part reports the CLI's opinion on the public inquiry made about the SPIRAL2 project

  15. The Optimization of Radioactive Waste Management in the Nuclear Installation Decommissioning Process

    International Nuclear Information System (INIS)

    The paper presents a basic characterization of nuclear installation decommissioning process especially in the term of radioactive materials management. A large amount of solid materials and secondary waste created after implementation of decommissioning activities have to be managed considering their physical, chemical, toxic and radiological characteristics. Radioactive materials should be, after fulfilling all the conditions defined by the authorities, released to the environment for the further use. Non-releasable materials are considered to be a radioactive waste. Their management includes various procedures starting with pre-treatment activities, continuing with storage, treatment and conditioning procedures. Finally, they are disposed in the near surface or deep geological repositories. Considering the advantages and disadvantages of all possible ways of releasing the material from nuclear installation area, optimization of the material management process should be done. Emphasis is placed on the radiological parameters of materials, availability of waste management technologies, waste repositories and on the radiological limits and conditions for materials release or waste disposal. Appropriate optimization of material flow should lead to the significant savings of money, disposal capacities or raw material resources. Using a suitable calculation code e.g. OMEGA, the evaluation of the various material management scenarios and selection of the best one, based on the multi-criterion analysis, should be done. (authors)

  16. Decommissioning of nuclear installations in the research framework programmes of the European Commission

    International Nuclear Information System (INIS)

    Decommissioning is the final phase in the life cycle of a nuclear installation and is to be considered part of a general strategy of environmental restoration after the final suspension of industrial activities. At present, over 110 nuclear facilities (nuclear power plants, fuel cycle facilities, particle accelerators and nuclear research installations) within the European Union (EU) are at various stages of the decommissioning process and it is forecast that at least a further 160 facilities will need to be decommissioned over the next 20 years (within the present 15 EU member States). Enlargement of the EU would contribute to a rapid increase in the number of nuclear facilities to be decommissioned (at least 50 facilities). Since 1979, the EC's Directorate-General for Research has conducted four successive five-year research and development programmes on the decommissioning of nuclear installations performed under cost sharing contracts with organizations within the EU. The main objective of these programmes was, and still is, to establish a scientific and technological basis for the safe, socially acceptable and economically affordable decommissioning of obsolete nuclear installations. The main objectives of these activities were to strengthen the scientific and technical knowledge in this field, with a particular view to enhancing safety and environmental protection aspects, and minimizing occupational exposures and dismantling costs as well as radioactive waste arisings. In the beginning of the 1990s, four pilot decommissioning projects were chosen to compare the differences in the approach of a: fuel processing plant (AT1 in La Hague); gas cooled reactor (WAGR in Windscale); boiling water reactor (KRB-A Gundremmingen in Germany); pressurized water reactor (BR3 in Belgium). Five years ago, a WWER type reactor (Greifswald in Germany) was added to this list of pilot decommissioning sites. Operations to remove the reactor internals were undertaken with the use of

  17. The Community's research and development programme on decommissioning of nuclear installations: First annual progress report (year 1985)

    International Nuclear Information System (INIS)

    This is the first Annual Progress Report of the European Community's 1984-88 programme of research on the decommissioning of nuclear installations. It shows the status of implementation reached on 31 December 1985. The 1984-88 programme has the following contents: A. Research and development projects concerning the following subjects: Project No 1: Long-term integrity of building and systems; Project No 2: Decontamination for decommissioning purposes; Project No 3: Dismantling techniques; Project No 4: Treatment of specific waste materials: steel, concrete and graphite; Project No 5: Large containers for radioactive waste produced in the dismantling of nuclear installations; Project No 6: Estimation of the quantities of radioactive wastes arising from the decommissioning of nuclear installations in the Community; Project No 7: Influence of installation design features on decommissioning. B. Identification of guiding principles, namely: - certain guiding principles in the design and operation of nuclear installations with a view to simplifying their subsequent decommissioning, - guiding principles in the decommissioning of nuclear installations which could form the initial elements of a Community policy in this field. C. Testing of new techniques under real conditions, within the framework of large-scale decommissioning operations undertaken in Member States. This first progress report, covering the period of putting the programme into action, describes the work to be carried out under the 27 research contracts concluded, as well as initial work performed and first results obtained

  18. Nuclear Energy Agency task group on Radiological Characterisation for Decommissioning of Nuclear Installations

    International Nuclear Information System (INIS)

    Radiological characterisation plays a significant role in the process of decommissioning of shut-down nuclear facilities in order to ensure the protection of the environment and radiation safety. At all stages of a decommissioning programme or project, adequate radiological characterisation is of crucial importance, not least from a material and waste perspective. The radiological characterisation is a key element for planning, controlling and optimising decommissioning and dismantling activities. Experience has shown that data and information from the operation of a facility can - supplemented by recently collected and analysed data and information - be of crucial importance for decisions on waste management and for characterisation of radioactive waste. Once the dismantling has been done, some information may be hard, costly or even impossible to obtain later in the waste management process. This was the reason why the Working Party on Decommissioning and Dismantling (WPDD) of the OECD Nuclear Energy Agency (NEA) decided in late 2013 to extend the mandate of the Task Group on Radiological Characterisation and Decommissioning (TGRCD) for a second phase focusing on nuclear facility characterisation from a waste and material end-state perspective whereas the first phase focused on overall strategies of radiological characterisation. This paper gives an overview of the activities and findings within both phases up to now. (authors)

  19. Liabilities identification and long-term management decommissioning of nuclear installations in Slovak Republic

    International Nuclear Information System (INIS)

    The decommissioning is defined as the safe removal of nuclear facilities from service and reduction of residual radioactivity and/or risk to a level enabling their use for the purpose of another nuclear facility or unrestricted use (site release) and termination of license. The Legal Basis for Decommissioning and Waste Management are described in 4 acts: - 1. Act 130/98 Coll. on peaceful use of nuclear energy (Atomic Act); - 2. The act No 127/1994 Coll. on environmental impact assessment (amended 2000); - 3. The act No 254/1994 Coll. on creation of state found for NPP decommissioning, spent fuel management and disposal investment (amended 2000, 2001); 4. The act No 272/1994 Coll. on protection of public health (amended 1996,2000). The licensing process for radioactive waste management installations as for all nuclear installations is running in following principal steps. The permits for siting, construction, operation including commissioning, individual steps of decommissioning and site release are issued by municipal environmental office on the basis of the Act No 50/1976 Coll. on territorial planning and construction rules and the decisions of the Nuclear regulatory Authority (UJD SR) based on the Atomic Act. The safety documentation shall be prepared by applicant and it is subject of the regulatory bodies approval, for nuclear safety is responsible UJD SR, for radiation protection Ministry of Health, for fire protection Ministry of Interior and for general safety Ministry of Labour, Social Policy and Family. UJD SR issues the permit for each decommissioning phase based on review and approval of safety documentation. Decommissioning Strategy of Slovak Republic was strongly influenced by the changes of Waste Management Strategy. During the last time UJD SR dedicated the great effort to principal improvement of legislation, to cooperation with Ministry of Economy with the aim to create rules for financial sources for decommissioning activities and to enforcement of

  20. 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

  1. Performance of HEPA Filter Medium under Accidental Conditions in Nuclear Installations

    International Nuclear Information System (INIS)

    High Efficiency Particulate Air filters (HEPA Filters) are the main components in ventilation or confinement system for the retention of radioactive particles in nuclear installations. During abnormal conditions or accidents (e.g. fire accident, criticality in a nuclear fuel cycle facility and LOCA in power reactors) the resulting heat, smoke and humidity affect to a large extent the performance of HEPA filters. As a part of a research programme aims at the evaluation and improvement of the performance of HEPA filter media during abnormal conditions, the effect of elevated temperatures up to 400 degree C on the resistance of medium to penetration of water under pressure has been investigated. The test results showed that the resistance of the medium to penetration of water decreases with increase in temperature and thermal exposure time. This could be attributed to burnout of the organic binder used to improve the resistance of the medium to the penetration of water. The results also showed that at 400 degree C the resistance of the medium to the penetration of water disappeared. This was confirmed by inspection of the filter medium samples after exposure to high temperature using a scanning electron microscope. The inspection of the medium samples showed that the organic binder in the medium was deformed and finally collapsed at 400 degree C. Also, a best estimate model for the relation of filter medium resistance to water penetration under elevated temperature has been implemented. The results of this study can help in establishing a regulatory operating limit conditions (OLCs) for HEPA filter operation at high temperatures conditions in nuclear installations

  2. Performance of HEPA Filter Medium under Accidental Conditions in Nuclear Installations

    International Nuclear Information System (INIS)

    High Efficiency Particulate Air filters (HEPA Filters) are the main components in ventilation or confinement system for the retention of radioactive particles in nuclear installations. During abnormal conditions or accidents (e.g. fire accident, criticality in a nuclear fuel cycle facility and LOCA in power reactors) the resulting heat, smoke and humidity affect to a large extent the performance of HEPA filters. As a part of a research programme aims at the evaluation and improvement of the performance of HEPA filter media during abnormal conditions, the effect of elevated temperatures up to 400 degree C on the resistance of medium to penetration of water under pressure has been investigated. The test results showed that the resistance of the medium to penetration of water decreases with increase in temperature and thermal exposure time. This could be attributed to burnout of the organic binder used to improve the resistance of the medium to the penetration of water. The results also showed that at 400 degree C the resistance of the medium to the penetration of water disappeared. This was confirmed by inspection of the filter medium samples after exposure to high temperature using a scanning electron microscope. The inspection of the medium samples showed that the organic binder in the medium was deformed and finally collapsed at 400 degree C. Also, a best estimate model for the relation of filter medium resistance to water penetration under elevated temperature has been implemented. The results of this study can help in establishing a regulatory operating limit conditions (OLCs) for HEPA filter operation at high temperatures conditions in nuclear installations.

  3. Agreement between Portugal and Spain on cooperation with regard to the safety of nuclear installations in border areas

    International Nuclear Information System (INIS)

    This Agreement provides for exchange of information on nuclear safety and radiation protection in nuclear installations likely to affect mutually the territories of Portugal and Spain. The Agreement defines the type of nuclear installation concerned, the border areas and the respective competent authorities. The competent authorities of both Parties undertake to establish in their respective territories, the systems required to detect any radiation emergency and to inform each other in cases where such emergency may affect them. The Agreement was concluded for a period of the years as from its entry into force. (NEA)

  4. Alteration of installation of reactors (additional installation of No.3 and No.4 plants) in the Genkai Nuclear Power Station, Kyushu Electric Power Co., Inc

    International Nuclear Information System (INIS)

    On October 19, 1982, Kyushu Electric Power Co. made an application to the Minister of International Trade and Industry on the alteration of the installation of reactors. The contents of the application are to install two PWRs of 3423 MWh (1180 MWe) as No.3 and No.4 plants. After the deliberation in the MITI, theMinister made the inquiry to the Nuclear Safety Commission on November 30, 1983. The Nuclear Safety Commission instructed the Committee on Examination of Nuclear Reactor Safety to investigate and deliberate this case on December 8, 1983. The MITI recognized that Kyushu Electric Power Co. has the technical capability to carry out the alteration and to operate the reactors, and that this alteration does not hinder the prevention of disasters due to nuclear fuel and reactors. The examination were made on the conditions of location such as the site, earthquakes, the ground, weather and social environment, and the position of the reactor facilities, the aseismatic design of the reactor facilities, the reactor proper, fuel handling and storing facilities, reactor cooling system, measuring and control system, radioactive waste facilities, radiation control facilities and reactor containment facilities. (Kako, I.)

  5. Manual on quality assurance for installation and commissioning of instrumentation, control and electrical equipment in nuclear power plants

    International Nuclear Information System (INIS)

    The present Manual on Quality Assurance (QA) for Installation and Commissioning of Instrumentation, Control and Electrical (ICE) Equipment of Nuclear Power Plants contains supporting material and illustrative examples for implementing basic requirements of the quality assurance programme in procurement, receiving, installation and commissioning of this equipment. The Manual on Quality Assurance for Installation and Commissioning of ICE Equipment is designed to supplement and be consistent with the Guidebook as well as with the IAEA Code and Safety Guides on Quality Assurance. It is intended for the use of managerial staff and QA personnel of nuclear power plant owners or the organizations respectively responsible for the legal, technical, administrative and financial aspects of a nuclear power plant. The information provided in the Manual will also be useful to the inspection staff of the regulatory organization in the planning and performance of regulatory inspections at nuclear power plants

  6. Earthquake experience and seismic qualification by indirect methods in nuclear installations

    International Nuclear Information System (INIS)

    In recent years, many operational nuclear power plants around the world have conducted seismic re-evaluation programmes either as part of a review of seismic hazards or to comply with best international nuclear safety practices. In this connection, Member States have called on the IAEA to carry out several seismic review missions at their plants, primarily those of WWER and RBMK design. One of the critical safety issues that arose during these missions was that of seismic qualification (determination of fitness for service) of already installed plant distribution systems, equipment and components. The qualification of new components, equipment and distribution systems cannot be replicated for equipment that is already installed and operational in plants, as this process is neither feasible nor appropriate. For this reason, seismic safety experts have developed new procedures for the qualification of installed equipment: these procedures seek to demonstrate that installed equipment, through a process of comparison with new equipment, is apt for service. However, these procedures require large sets of criteria and qualification databases and call for the use of engineering judgement and experience, all of which open the door to wide margins of interpretation. In order to guarantee a sound technical basis for the qualification of in-plant equipment, currently applied to 70% to 80% of all plant equipment, the regulatory review of this type of qualification process calls for a detailed assessment of the technical procedures applied. Such an assessment is the first step towards eliminating the risk of large differences in qualification results between different plants, operators and countries, and guaranteeing the reliability of seismic re-evaluation programmes. Bearing this in mind, in 1999, the IAEA convened a seminar and technical meeting on seismic qualification under the auspices of the IAEA Technical Co-operation programme. Altogether 66 senior experts attended the

  7. The implementation of CP1 computer code in the Honeywell Bull computer in Brazilian Nuclear Energy Commission (CNEN)

    International Nuclear Information System (INIS)

    The implementation of the CP1 computer code in the Honeywell Bull computer in Brazilian Nuclear Energy Comission is presented. CP1 is a computer code used to solve the equations of punctual kinetic with Doppler feed back from the system temperature variation based on the Newton refrigeration equation (E.G.)

  8. The Brazilian position during the final transactions the treaty for the proscriptions of nuclear weapons in Latin America

    International Nuclear Information System (INIS)

    The Brazilian position during the final transactions on the treaty for the proscription of Nuclear Weapons in Latin America is presented. An analysis of the main clauses of this treaty is given, well as a comparative study between the principle points of Tlatelolco Treaty and Non-Proliferation Treaty

  9. Licensing and decommissioning of nuclear installations -interpretation and further development of legal provisions by licensing authorities and by law courts

    International Nuclear Information System (INIS)

    Working Group 1, from this conference, whose brief was to deal with ''Licensing and Decommissioning of Nuclear Installations'', has based its results on the findings elaborated at earlier International Nuclear Law Association conferences, especially on the activities of Working Group 1 of Nuclear Inter Jura'85 (Constance), Nuclear Inter Jura'87 (Antwerp), and Nuclear Inter Jura'89 (Tokyo). Since then the Working Group has investigated the legal framework of licensing and decommissioning of nuclear installations on the basis of an international comparison. The legal and technical aspects of decommissioning measures are becoming more and more important and, consequently, continue to be topical subjects, both nationally and internationally. In the past, the Working Group had looked into the general aspects of the legal framework and its practical implementation; this time, the Group's deliberations focussed on some points of detail within these overall subjects. (author)

  10. Determination of 93Zr in medium and low level radioactive wastes from Brazilian nuclear power plants

    International Nuclear Information System (INIS)

    The majority of long-lived radionuclides produced in the nuclear power plants can be regarded as difficult-to-measure radionuclides (RDM), hence chemical separation is necessary before the nuclear measurement of them. The zirconium isotope 93Zr is a long-lived pure β-particle-emitting radionuclide produced from 235U fission and from neutron activation of the stable isotope 92Zr and thus occurring as one of the radionuclides found in nuclear reactors. Due to its long half-life, 93Zr is one of the radionuclides of interest for the performance of assessment studies of waste storage or disposal. Two different methodologies based on extractive resins and LSC and ICP-MS techniques that enables the 93Zr determination in medium (ILW) and low level (LLW) radioactive wastes samples from Brazilian nuclear power plants has been developed in our laboratory. Analyzing real samples 65% and 75% chemical yields for 93Zr recovery were achieved for ICP-MS and LSC techniques, respectively. The detection limits were 0.045 μg.L-1 for ICP-MS and 0.05 Bq.L-1 for LSC techniques. (author)

  11. Study on uranium, thorium, and potassium in soil around a nuclear installation by using INAA

    International Nuclear Information System (INIS)

    Soil samples collected around a nuclear installation in southwest China have been analyzed for U, Th and K using instrumental neutron activation analysis (INAA). Samples were irradiated with an integral thermal neutron flux of 3 x 1017 /cm2 in the high flux reactor at Nuclear Power Institute of China, Chengdu, China. The three elements have been determined from 150 samples by high-resolution gamma spectrometry. To evaluate the accuracy of analytical data, certified reference materials NIST SRM 1633a and GBW 07045 were analyzed together with unknown samples and the results were found to be in good agreement with certified values for these three elements. The results of correlation analysis for both the contents of the three elements and the Th/U ratio indicate that the nuclear field releases a little uranium to environment. Moreover, the results of size distribution indicate that the uranium and thorium contents are higher in clay than in other kinds of soil particles, especially for uranium. (authors)

  12. Applicability of ISO 9001: 2000 standard to design and research activities in nuclear objectives and installations

    International Nuclear Information System (INIS)

    The ISO 9001: 2000 standard contains the results of the latest studies concerning the design and implementation of quality management systems. The continuous improvement of these systems required a new approach, namely, the process-based approach. A process-based model of quality management is presented in terms of client request, input data, management responsibility, resource management, product realisation, measurement / analysis and optimization, product, output data and client request fulfilment. Thus, the quality management system becomes an ensemble of interconnected or interacting processes. Consequently, to implement such a system the necessary processes have to be identified and their ISO 9001: 2000 standard based management ensured. Process based approach also allows better evidencing the input and output data specific to each process. Such an approach grants a wider applicability to the design and research activities in nuclear objectives and installations. This work aims at identifying additional requirements implied in design and research activities in nuclear field, as stipulated in the following standards / documents: - IAEA SG Q8 'Quality assurance in research and development'; - IAEA SG Q10 'Quality assurance in design'; - CAN / CSA N 286.2 - 00 'Design Quality Assurance for Nuclear Power Plants'; CAN 3 - CSA Z 299.1 'Quality Assurance Program - Category 1'; - NQA - 1, SUPPLEMENT 3S-1 'Supplementary requirements for design control'

  13. Implementing Stakeholders' Access to Expertise: Experimenting on Nuclear Installations' Safety Cases - 12160

    International Nuclear Information System (INIS)

    In 2009 and 2010, the Institute for Nuclear Safety and Radiation Protection (IRSN) led two pilot actions dealing with nuclear installations' safety cases. One concerned the periodical review of the French 900 MWe nuclear reactors, the other concerned the decommissioning of a workshop located on the site of Areva's La Hague fuel-reprocessing plant site in Northwestern France. The purpose of both these programs was to test ways for IRSN and a small number of stakeholders (Non-Governmental Organizations (NGOs) members, local elected officials, etc.) to engage in technical discussions. The discussions were intended to enable the stakeholders to review future applications and provide valuable input. The test cases confirmed there is a definite challenge in successfully opening a meaningful dialogue to discuss technical issues, in particular the fact that most expertise reports were not public and the conflict that exists between the contrary demands of transparency and confidentiality of information. The test case also confirmed there are ways to further improvement of stakeholders' involvement. (authors)

  14. Human-robot collaborative navigation for autonomous maintenance management of nuclear installation

    International Nuclear Information System (INIS)

    Development of human and robot collaborative navigation for autonomous maintenance management of nuclear installation has been conducted. The human-robot collaborative system is performed using a switching command between autonomous navigation and manual navigation that incorporate a human intervention. The autonomous navigation path is conducted using a novel algorithm of MLG method based on Lozano-Perezs visibility graph. The MLG optimizes the shortest distance and safe constraints. While the manual navigation is performed using manual robot tele operation tools. Experiment in the MLG autonomous navigation system is conducted for six times with 3-D starting point and destination point coordinate variation. The experiment shows a good performance of autonomous robot maneuver to avoid collision with obstacle. The switching navigation is well interpreted using open or close command to RS-232C constructed using LabVIEW

  15. Study on the financing mechanism and management for decommissioning of nuclear installations in Malaysia

    International Nuclear Information System (INIS)

    The whole cycle of the decommissioning process development of repository requires the relevant bodies to have a financial system to ensure that it has sufficient funds for its whole life cycle (over periods of many decades). Therefore, the financing mechanism and management system shall respect the following status: the national position, institutional and legislative environment, technical capabilities, the waste origin, ownership, characteristics and inventories. The main objective of the studies is to focus on the cost considerations, alternative funding managements and mechanisms, technical and non-technical factors that may affect the repository life-cycle costs. As a conclusion, the outcomes of this paper is to make a good recommendation and could be applied to the national planners, regulatory body, engineers, or the managers, to form a financial management plan for the decommissioning of the Nuclear Installation

  16. Development and implementation of computerized operator support systems in nuclear installations

    International Nuclear Information System (INIS)

    This report has been prepared to address the development and implementation of computerized operator support systems (COSS) in nuclear installations. The requirements of operators in information management and job performance in a control room environment are discussed. These requirements, which must be agreed to by the operators, provide a focus for the developers of COSS for implementation in an operational environment. The design methodology presents good practice approaches derived from the experience gained and the lessons learned during actual development of the COSS. The team concept, pilot study and structured step by step phases of software development and implementation should help COSS developers to achieve the level of quality and reliability required. 8 figs, 1 tab

  17. Public health at the vicinity of nuclear installations: how to address the raised issues

    International Nuclear Information System (INIS)

    This document is proposed by a work-group which gathered the IRSN, public local information commissions and the French Health Survey Institute (InVS). It is designed to be a methodological document on the benefits and limits of health analysis tools with respect to real situations. The first part discusses the implementation of a public health survey, its approach, its modalities and how its results are published. The second part deals with methodological issues for the definition of the specifications of a public health survey, and its protocol. Thus, it discusses how releases in the environment are to be addressed (releases from nuclear installations and from other activities involving radioactivity), the different pathologies to be studied, the existing health data and survey tools (mortality and cancer incidence data, medical-administrative data), and the possible survey types (descriptive or analytical epidemiological surveys) and their limitations

  18. Electrochemical techniques to detect corrosion in concrete structures in nuclear installations - Technical note

    International Nuclear Information System (INIS)

    The mechanism of corrosion in aqueous media is of electrochemical nature. This means that the oxidation of the metal is counterbalanced by the reduction of another substance in another region of the metallic surface. Therefore, zones (anodes and cathodes) with different electrochemical potential, develop. In the case of concrete the electrolyte is constituted by the pore solution, which is very alkaline. This pore solution is formed by mainly a mixture of KOH and NaOH presenting pH values ranging between 12.6-14. The solution is saturated in Ca(OH)2. Steel embedded in concrete is naturally protected by this high alkalinity and by the barrier effect of the cover itself. The two main causes of electrochemical corrosion are carbonation and the presence of chlorides. Carbonation usually induces a generalized corrosion while chloride will lead into pitting or localized attack. The corrosion can be easily recognized by the rust presence on the rebar and by the appearance of cracks running parallel to the rebars. The objective of this report is to describe the electrochemical non-destructive techniques that can be used in real size reinforced concrete structures to assess the corrosion condition of their reinforcement. These techniques can be used indistinctly in conventional civil engineering structures or in those of nuclear installations. Electrochemical techniques are used to detect electrochemical corrosion activity of metallic reinforcements. They cannot quantify stress corrosion cracking or hydrogen embrittlement although may give some qualitative information about them. The aims of their applications may be one of the following circumstances: 1. Quality control of new constructions; 2. Condition evaluation of existing structures for: - Identification of steel de-passivation, - Detecting corroding areas for rehabilitation purposes, - Calculation of residual load-bearing capacity of the structure, - Prediction of the damage evolution, - Determination of the optimum

  19. Study on the financing mechanism and management for decommissioning of nuclear installations in Malaysia

    Energy Technology Data Exchange (ETDEWEB)

    Saleh, Lydia Ilaiza, E-mail: lydiailaiza@gmail.com; Ryong, Kim Tae [KEPCO International Nuclear Graduate School (KINGS) 658-91 Haemaji-ro, Seosaeng-myeon, Ulju-gun, Ulsan 689-882 (Korea, Republic of)

    2015-04-29

    The whole cycle of the decommissioning process development of repository requires the relevant bodies to have a financial system to ensure that it has sufficient funds for its whole life cycle (over periods of many decades). Therefore, the financing mechanism and management system shall respect the following status: the national position, institutional and legislative environment, technical capabilities, the waste origin, ownership, characteristics and inventories. The main objective of the studies is to focus on the cost considerations, alternative funding managements and mechanisms, technical and non-technical factors that may affect the repository life-cycle costs. As a conclusion, the outcomes of this paper is to make a good recommendation and could be applied to the national planners, regulatory body, engineers, or the managers, to form a financial management plan for the decommissioning of the Nuclear Installation.

  20. Study on the financing mechanism and management for decommissioning of nuclear installations in Malaysia

    Science.gov (United States)

    Saleh, Lydia Ilaiza; Ryong, Kim Tae

    2015-04-01

    The whole cycle of the decommissioning process development of repository requires the relevant bodies to have a financial system to ensure that it has sufficient funds for its whole life cycle (over periods of many decades). Therefore, the financing mechanism and management system shall respect the following status: the national position, institutional and legislative environment, technical capabilities, the waste origin, ownership, characteristics and inventories. The main objective of the studies is to focus on the cost considerations, alternative funding managements and mechanisms, technical and non-technical factors that may affect the repository life-cycle costs. As a conclusion, the outcomes of this paper is to make a good recommendation and could be applied to the national planners, regulatory body, engineers, or the managers, to form a financial management plan for the decommissioning of the Nuclear Installation.

  1. The Contribution of Paleoseismology to Seismic Hazard Assessment in Site Evaluation for Nuclear Installations

    Science.gov (United States)

    Decker, Kurt; Guerrieri, Luca; Fukushima, Yoshimitsu

    2015-04-01

    In the framework of site evaluation/re-evaluation procedures for nuclear power plants (NPP), paleoseismology plays an essential role not only for Fault Displacement Hazard Assessment (FDHA) but also for Seismic Hazard Assessment (SHA). The relevance of paleoseismology is recommended in the reference IAEA Safety Guide (IAEA SSG-9) and has been dramatically confirmed in recent time especially after the accident at the Fukushima Daiichi NPP caused by the disastrous great Tohoku earthquake and tsunami occurred on 11 March 2011. After this event, the IAEA International Seismic Safety Center promoted a technical document aimed at encouraging and supporting Member States, especially from newcomer countries, to include paleoseismic investigations into the geologic database, highlighting the value of earthquake geology studies and paleoseismology for nuclear safety and providing standard methodologies to perform such investigations. In detail, paleoseismic investigations in the context of site evaluation of nuclear installations have the following main objectives: i) identification of seismogenic structures based on the recognition of effects of past earthquakes in the regional area; ii) improvement of the completeness of earthquake catalogs, through the identification and dating of ancient moderate to large earthquakes, whose trace has been preserved in the geologic records; iii) estimation of the maximum seismic potential associated with an identified seismogenic structure/source, typically on the basis of the amount of displacement per event (evaluable in paleoseismic trenches), as well as of the geomorphic and stratigraphic features interpretable as the cumulative effect of repeated large seismic events (concept of "seismic landscape"); iv) rough calibration of probabilistic seismic hazard assessment (PSHA), by using the recurrence interval of large earthquakes detectable by paleoseismic investigations, and providing a "reality check" based on direct observations of

  2. Third party liability of nuclear installation decommissioning with Russian nuclear submarines as an example: insurance versus technologies

    International Nuclear Information System (INIS)

    Third party and environment of civil liability damage caused by incidents at military nuclear installations, for instance at decommissioned NPS (nuclear powered submarines), may be divided into three main trends: -) Liability of NPS without high-enriched irradiated nuclear fuel (SNF) for its self-submersion (radiation incident); -) Liability of NPS with SNF aboard for its self-submersion (radiation incident); and -) Liability of floating NPS for its SNF discharge (nuclear accident). Without step-by-step transition from the Russian Federation guaranties to insurance and making allowance for liability limits according to the Vienna Convention approach, the sizes of the financial guarantee for the civil liability of the NPS owner (Russian state), in US dollars of 2000, are approximately assessed as the following: -) storing decommissioned NPS or a floating module without SNF - from 12 to 25 thousand dollars per year (per one submarine or module); -) storing decommissioned NPS with SNF inside reactors cores - from 25 to 40 thousand dollars per year; -) assembly-by-assembly removing SNF from reactors' core of decommissioned NPS - up to 1.5 million dollars for undamaged reactor per the discharging period; -) SNF removing within reactor using the filled in-space reactor's core by liquid-phased hardened or dispersed solid-phase materials from decommissioned NPS - from 30 to 50 thousand dollars for undamaged reactor per the discharging period. Both rates and sums for NPS with damaged reactors are to be estimated for the each damaged reactor and NPS at all. It is necessary to perform the measures reducing the risk of nuclear accidents of NPS with undamaged SNF and NPS with damaged reactors in possibly short time. It will allow not only to cut risks by ten times and more, but also to accumulate necessary insurance reserves faster. These measures can be partially or completely executed using the preventing measures reserves assigned to all decommissioned Russian NPS and

  3. Advances and Challenges in the Implementation of DiD in Siting, Design, and Construction of Nuclear Installations in Vietnam

    International Nuclear Information System (INIS)

    Vietnam is embarking on a development of a nuclear power program. The main focus is now on the initial 1000 MWe x 2 units of the nuclear power plant in Ninh Thuan province. Now, the nuclear projects of Vietnam are in the phase of siting approval and investment projects approval. The design assessment will be performed in 2013-2014; the construction and installation will be performed from now until the operating licensing is obtained in 2020-2021. With state of development of a nuclear power program in Vietnam, this paper only focuses on advances and challenges in the implementation of Defence in Depth (DID) in siting, design, and construction of nuclear installations in Vietnam. (author)

  4. Authorization procedure for the construction and operation of nuclear installations within the EC Member States, including supervision and control

    International Nuclear Information System (INIS)

    This report is an updating of the report EUR 5284, Authorization procedure for the construction and operation of nuclear installations within the EEC Member States, prepared in 1974 by J.M. Didier and Associates. Recent developments regarding the authorization procedure for the construction and operation of nuclear installations have taken place in Italy (introduction of a site approval procedure) and in Denmark (adoption of an overall legislation on the subject, however not yet in force). With respect to supervision and control of nuclear installations during construction and operation, competences of, as well as their exercise by, supervisory authorities in all EC Member States, with the exception of Ireland, are also analysed in the current study

  5. Report by the national commission of assessment of financing of costs of decommissioning base nuclear installations and installations of management used fuels and radioactive wastes (CNEF) - July 2012

    International Nuclear Information System (INIS)

    This report is a first assessment of the control which must be performed by the administrative authority to ensure the compliance with long term financial obligations for operators of base nuclear installations. After a presentation of the administrative authority, this document reports the assessment of liabilities and of dedicated assets, and the remarks made by the commission regarding the administrative authority organisation and function, the previous assessments, uncertainties concerning the cost of the deep geological storage project, and the future activity of the Commission

  6. Intercomparison of 67 Ga activity measurements in Brazilian nuclear medicine services

    International Nuclear Information System (INIS)

    Since 1998 the National Metrology Laboratory for Ionizing Radiation (LNMRI) of the Institute of Radiation Protection and Dosimetry, of the National Commission on Nuclear Energy (IRD/CNEN), with delegation of the National Institute of Metrology and Industrial Quality (INMETRO), is conducting an intercomparison program for activity measurements of radiopharmaceuticals applied to the patients in the field of Nuclear Medicine with the purpose of quality control. This intercomparison program has been carrying out measurements of 123 I, 131 I and 99m Tc throughout the country and, recently, initiated the first intercomparison run with 67 Ga with the participation of 27 hospitals of the State of Rio de Janeiro. The results had been analyzed under the point of view of conformity with the norms of the Regulatory Authority and the accuracy of the measurements in relation to the reference value of the LNMRI which is traceable to the National Institute of Standards and Technology (NIST/USA). The results showed that these intercomparisons are necessary to improve the quality of the activity measurements of radiopharmaceuticals, to identify fails in the equipment and in the technical procedures used by the Brazilian Nuclear Medicine Services. (author)

  7. Evaluation of Heterogeneity Degree of U Compounds to be used in Intercomparison Programs in the Brazilian Nuclear Facilities

    International Nuclear Information System (INIS)

    The Brazilian nuclear facilities must dispose of measurement systems that allow the determination of their nuclear material inventories. The main goal of this work is the characterization of enriched uranium dioxide (UO2) pellets to use as secondary standard to evaluate and verify these systems through the participation of the involved laboratories in inter-laboratory comparison programs. The programs are formed by a network of specialized laboratories in determining the material the nuclear fuel cycle. Therefore, before being sent to laboratories, the materials must have their homogeneity certified. The technique used was Davies and Gray/NBL titrimetric method. No statistical significant differences were observed in the results of total U concentration for two different batches. Therefore, the UO2 pellets are considered homogeneous and can be used in an independent Brazilian measurement systems evaluation program. (authors)

  8. Study of Formosa's electrical offer for installing a commercial nuclear power plant

    International Nuclear Information System (INIS)

    Within the specific agreement for the siting study of the CAREM nuclear power plant in Formosa Province, signed between the National Atomic Energy Commission and the Government of Formosa, a detailed study of electrical supply was conducted in order to analyze the requirements and the electricity supply as a result of its future installation. This topic is part of the analysis developed in the Level II of the site survey study. The analysis focuses on a plan for long-term projections from 2005 to 2030, using the IAEA’s MESSAGE model (Model for Energy Supply Strategy Alternatives and Their General Environmental Impacts). The existing electrical infrastructure and the plans for expansion of transmission and distribution lines, the generation technologies and the electricity flows with the provinces and neighboring countries have been taken into account. The study was based on the evaluation of two site scenarios based on the availability of infrastructure in the province and the conclusions obtained in the Level I of the siting study. The modelling results indicate that the current situation that characterizes the Province as a net importer of electricity will be reversed due to the operation of the nuclear plant since 2019. However, it is important to note that to keep Formosa’s feature as an electricity exporter from the year 2026, according to the less favorable scenario (highest demand), ongoing energy planning and investment in the province will be done. (author)

  9. Safety and siting of nuclear installations near international borders in NEA member countries

    International Nuclear Information System (INIS)

    The CSNI Sub-Committee on Licensing expressed interest in the siting of nuclear plants near international borders and beside international waters. On these grounds, the NEA Secretariat deemed it appropriate to collect the available information about the solutions adopted by the NEA Member countries sharing international frontiers and having nuclear installations located or planned near those borders. The report presents the results of this work of compilation. An analysis is presented of the existing arrangements between the following bordering countries: Austria-Fed. Rep. of Germany, Austria-Italy, Austria-Switzerland, Belgium-France, Belgium-Fed. Rep. of Germany, Belgium-Luxembourg, Belgium-The Netherlands, Denmark-Fed. Rep. of Germany, France-Fed. Rep. of Germany, France-Italy, France-Luxembourg, France-Spain, France-Fed. Rep. of Germany-Switzerland, Fed. Rep. of Germany-Luxembourg, Fed. Rep. of Germany-Switzerland, Fed. Rep. of Germany-The Netherlands, Greece-Turkey, Italy-Switzerland, Portugal-Spain, Canada-The United States, Scandinavian countries (Denmark, Finland, Norway, Sweden), European Communities

  10. Renewable energy sources and nuclear installations; Erneuerbare Energien und neue Nuklearanlagen

    Energy Technology Data Exchange (ETDEWEB)

    Hirschberg, S.; Bauer, Ch.; Burgherr, P.; Stucki, S.; Vogel, F.; Biollaz, S.; Schulz, T.; Durisch, W.; Hardegger, P.; Foskolos, K.; Meier, A.; Schenler, W.

    2005-02-15

    This comprehensive work report for the Swiss Federal Office of Energy (SFOE) made by the Paul Scherrer Institute PSI takes a look at work done in connection with the updating of the office's Energy Perspectives. In particular, the topic of electricity is reviewed in the light of pending important decisions in the area of nuclear energy and the newer renewable sources of energy. The report makes an attempt to estimate the effect on Swiss power production that the new renewables and new nuclear installations could have in the next 30-40 years and to what costs this could be done and which obstacles would have to overcome. The renewable energy sources include small hydro, wind, photovoltaics, solar thermal power plants, biogas, geothermal energy, wave-power and solar chemistry. The methods used include literature study and contacts with internal PSI experts on the various areas involved. The most important system characteristics were noted and learning curves for the various technologies were taken into account. Ecological and social factors were also considered

  11. Nuclear reactor installation with outer shell enclosing a primary pressure vessel

    International Nuclear Information System (INIS)

    The high temperature nuclear reactor installation described includes a fluid cooled nuclear heat source, a primary pressure vessel containing the heat source, an outer shell enclosing the primary pressure vessel and acting as a secondary means of containment for this vessel against outside projectiles. Multiple auxiliary equipment points are arranged outside the outer shell which comprises a part of a lower wall around the primary pressure vessel, an annular part integrated in the lower wall and extending outwards as from this wall and an upper part integrated in the annular part and extending above this annular part and above the primary pressure vessel. The annular part and the primary pressure vessel are formed with vertical penetrations which can be closed communicating respectively with the auxiliary equipment points and with inside the pressure vessel whilst handling gear is provided in the upper part for vertically raising reactor components through these penetrations and for transporting them over the annular part and over the primary pressure vessel

  12. Contributions by emissions from nuclear installations to concentrations of radionuclides in milk

    International Nuclear Information System (INIS)

    A year-long study has been carried out to determine whether milk produced near nuclear sites contains concentrations of radionuclides that can be attributed to discharges from the installations, and, as a consequence, whether there is enhanced exposure of those members of the public who consume this milk. Eight creameries were chosen and monthly samples of milk were taken for analysis. The concentrations of caesium-137 and strontium-90 were measured and compared with results from a national survey conducted as part of the Board's environmental radioactivity surveillance programme. No effect attributable to discharges from the nuclear establishments was identified. The activity concentrations ranged between 0.1 and 3 times the national average; the variation relates mainly to rainfall in the area, although other factors may also have an effect. However, milk contributes only a small fraction of the total dietary intake of caesium-137 and strontium-90, and so the exposure of persons consuming the milk varies only slightly about the national average. (author)

  13. Protection of base nuclear installations against external flooding - Guide nr 13, release of the 08/01/2013

    International Nuclear Information System (INIS)

    As the French law requires the flooding risk to be taken into account in the demonstration of the nuclear safety of base nuclear installations (INB), this guide aims at defining situations to be taken into account when assessing the flooding risk for a site (identification of water sources and of flooding causes, definition of flooding situations), at proposing an acceptable method to quantify these situations (local rains, rise of water level, problems on hydraulic works, dam failure, ocean waves, and so on), and at listing recommendations to define the protection means which are adapted to the specificities of the flooding risk, and are implemented by the operator with respect to the installation lifetime

  14. Activities of Brazilian Nuclear Energy Commission in the field of nuclear power plant licesing

    International Nuclear Information System (INIS)

    The objectives, the procedures and the ways of implementation of measures aiming at safety use of nuclear energy are presented. The juridical aspects in the licensing area and the regulatory activities used by CNEN. The description of nuclear power plants and the methodology used in studies of environmental protection and radiation protection are presented

  15. Technical Orders of 10 August 1976 on the limits and procedures applicable to radioactive effluent discharges from nuclear installations

    International Nuclear Information System (INIS)

    Seven technical Orders by the competent Ministers (mainly the Ministers of Health, of Industry and Research, of the Quality of Life) lay down the procedures, conditions and limits applicable to gaseous and liquid radioactive effluent discharges from nuclear installations. These Orders of 10 August were published on 12 September 1976 in the Official French Gazette and were made in implementation of the Decree of 6 November 1974 on gaseous radioactive effluent discharges from nuclear installations and the Decree of 31 December 1974 on liquid radioactive effluent discharges from nuclear installations. Apart from the general rules for setting limits and methods for effluent discharges, they specify the measures for environmental monitoring and for control by the Central Service for Protection against Ionizing Radiations. Certain of them contain the general rules for liquid or gaseous effluent discharges from all nuclear installations, while others lay down the rules proper to light water nuclear power plants. Other types of reactor ie. fast breeders are not yet subject to such regulations. (N.E.A.)

  16. Evaluation of Argentinian industrial capacity and of suppliers for nuclear installations

    International Nuclear Information System (INIS)

    This work describes and analyses the Argentinian system of purchasing, the laws and decrees which must be observed by the State enterprises and dependent bodies such as the National Atomic Energy Commission (C.N.E.A.). Within the system there are regulations which must be observed by the State suppliers, and to which the purchasing bodies must conform. Furthermore, there is a thorough analysis of the methods implemented before beginning the construction of the third nuclear plant in Argentina, the Atucha II Nuclear Plant. For this, all the existing antecedents were taken into account, insofar as they were related to the prior projects, and an exhaustive questionnaire was elaborated, in which the examined enterprises described in detail their installed capacity, their antecedents, their human resources, etc. The data thus obtained were evaluated and the task was concluded by drawing up lists of the possible enterprises to supply the most diverse components, services or equipment required both by the electrical plant and for any other large scale work. The evaluation obtained would allow an analysis of the foreign offers concerning the entire project and of the possible participation with each bidder of Argentinian industry and engineering. A description is given of the advanced method used to assess bidders with respect to such participation, to assess the replies to the questionnaire, which were analysed in detail, and the weighting factors applied to each item. Also described are some major contracts concluded with enterprises in the country. These contracts relate to the external acquisition of technology for nuclear plants and the essential points are outlined. Also analysed are the results obtained during the execution of the programmes of technology transfer and training, both for parts of different enterprises selected to produce the components, and for the State, through C.N.E.A. and ENACE S.A. 6 refs, 5 tabs

  17. Establishment of the nuclear regulatory framework for the process of decommissioning of nuclear installations in Mexico; Establecimiento del marco regulador nuclear para el proceso de cierre de instalaciones nucleares en Mexico

    Energy Technology Data Exchange (ETDEWEB)

    Salmeron V, J. A.; Camargo C, R.; Nunez C, A., E-mail: juan.salmeron@cnsns.gob.mx [Comision Nacional de Seguridad Nuclear y Salvaguardias, Dr. Barragan 779, Col. Narvarte, 03020 Ciudad de Mexico (Mexico)

    2015-09-15

    Today has not managed any process of decommissioning of nuclear installations in the country; however because of the importance of the subject and the actions to be taken to long term, the Comision Nacional de Seguridad Nuclear y Salvaguardias (CNSNS) in Mexico, accordance with its objectives is developing a National Nuclear Regulatory Framework and defined requirements to ensure the implementation of appropriate safety standards when such activities are performed. In this regard, the national nuclear regulatory framework for nuclear installations and the particular case of nuclear power reactors is presented, as well as a proposed licensing process for the nuclear power plant of Laguna Verde based on international regulations and origin country regulations of the existing reactors in nuclear facilities in accordance with the license conditions of operation to allow to define and incorporate such regulation. (Author)

  18. 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)

  19. Concerning partial revision of regulations on installation, operation, etc., of nuclear reactor, etc., for test and research

    International Nuclear Information System (INIS)

    To enforce the rules relating to nuclear material protection at nuclear power facilities as covered by the Nuclear Reactor Control Law, which was revised in May last year, orders should be issued by the Prime Minister's Office (or Ministry of International Trade and Industry) to specify the following matters: (1) measures to be carried out by the operators of nuclear facilities to ensure the protection of specially designated nuclear fuel materials, (2) procedures for the application for permission as covered by nuclear material protection rules, and (3) requirements for managers in charge of nuclear material protection. The new regulations should cover the following: (1) rules relating to the business of refining of nuclear fuels, and raw materials for nuclear substances, (2) rules relating to the business of processing of nuclear fuels, (3) rules relating to the installation, operation, etc., of nuclear reactor, etc., for test and research, (4) rules relating to the business of reprocessing of spent fules, (5) rules relating to the business of management of nuclear fuels or waste contaminated with nuclear fuels, and (6) rules relating to the application of nuclear fuels. (N.K)

  20. Determining the cost of nuclear technology dismantling - software to quantify the costs of clean dismantling of nuclear installations

    International Nuclear Information System (INIS)

    Division ENERGOPROJEKT PRAHA processes within the group UJV Rez, a.s. complex pre-project and project preparation works in the nuclear field. Division prepares studies and documentation necessary for the customer's decision making (feasibility studies, business plans, building plans, etc.), preparatory, conceptual and project documentation), including related engineering services. Further safety documentation processes at all levels and documentation of the evaluation of environmental impact (EIA). In the area of a decommissioning process complete alternate design studies and design documentations of a decommissioning of NPPs in order to choose suitable variant of solution. An important area is the financing of the decommissioning process, creation of financial reserves, the input data to create a cost estimate and methodology for cost estimate. Quantifying the cost demands of the decommissioning process throughout the life cycle is composed of individual cost items for individual decommissioning activities. These also include determining the amount of costs necessary for removing uncontaminated or decontaminated process equipment. In the division ENERGOPROJEKT PRAHA was created software DEMONDEC for the estimation of these costs, which is based on the assumption that the costs to be incurred for dismantling of the above technological nuclear installation, it can be derived from the performance indicators when removing analogue equipment and systems that are part of common industrial buildings. (authors)

  1. From the first nuclear power plant to fourth-generation nuclear power installations [on the 60th anniversary of the World's First nuclear power plant

    Science.gov (United States)

    Rachkov, V. I.; Kalyakin, S. G.; Kukharchuk, O. F.; Orlov, Yu. I.; Sorokin, A. P.

    2014-05-01

    Successful commissioning in the 1954 of the World's First nuclear power plant constructed at the Institute for Physics and Power Engineering (IPPE) in Obninsk signaled a turn from military programs to peaceful utilization of atomic energy. Up to the decommissioning of this plant, the AM reactor served as one of the main reactor bases on which neutron-physical investigations and investigations in solid state physics were carried out, fuel rods and electricity generating channels were tested, and isotope products were bred. The plant served as a center for training Soviet and foreign specialists on nuclear power plants, the personnel of the Lenin nuclear-powered icebreaker, and others. The IPPE development history is linked with the names of I.V. Kurchatov, A.I. Leipunskii, D.I. Blokhintsev, A.P. Aleksandrov, and E.P. Slavskii. More than 120 projects of various nuclear power installations were developed under the scientific leadership of the IPPE for submarine, terrestrial, and space applications, including two water-cooled power units at the Beloyarsk NPP in Ural, the Bilibino nuclear cogeneration station in Chukotka, crawler-mounted transportable TES-3 power station, the BN-350 reactor in Kazakhstan, and the BN-600 power unit at the Beloyarsk NPP. Owing to efforts taken on implementing the program for developing fast-neutron reactors, Russia occupied leading positions around the world in this field. All this time, IPPE specialists worked on elaborating the principles of energy supertechnologies of the 21st century. New large experimental installations have been put in operation, including the nuclear-laser setup B, the EGP-15 accelerator, the large physical setup BFS, the high-pressure setup SVD-2; scientific, engineering, and technological schools have been established in the field of high- and intermediate-energy nuclear physics, electrostatic accelerators of multicharge ions, plasma processes in thermionic converters and nuclear-pumped lasers, physics of compact

  2. Optimization of the availability and safety relationship of nuclear propulsion installations for military vessels; Otimizacao do conjugado disponibilidade versus seguranca das instalacoes propulsoras nucleares para navios militares

    Energy Technology Data Exchange (ETDEWEB)

    Santos Guimaraes, Leonam dos [Centro Tecnologico da Marinha (CTMSP), Sao Paulo, SP (Brazil)

    1997-12-01

    The relationship between energy generation availability and the safety of the nuclear installation which produces this energy assumes a very especial characteristic when we are dealing with naval propulsion plants. This relationship has no parallel with commercial nuclear power plants. A ship at sea is safety only if he could dispose quickly of the energy produced by his nuclear propulsion plant. This paper presents briefly the main aspects of that relation. 14 refs., 3 figs., 1 tab.

  3. Quality assurance for safety in nuclear power plants and other nuclear installations. Code and safety guides Q1-Q14. A publication within the NUSS programme

    International Nuclear Information System (INIS)

    The code provides the basic requirements for establishing and implementing quality assurance programmes for the stages of siting, design, construction, commissioning, operation and decommissioning of nuclear power plants. These basic requirements apply to all individuals and organizations, including designers, suppliers, constructors, manufacturers and operators. The basic quality assurance requirements presented in this Code also apply, with appropriate modifications, to nuclear installations other than nuclear power plants

  4. Nuclear facilities and the environment: feedback experiences; Les installations nucleaires et l'environnement: retour d'experience

    Energy Technology Data Exchange (ETDEWEB)

    Hedin, F. [Societe Francaise d' Energie Nucleaire (SFEN), 75 - Paris (France); Brownless, G. [Nuclear Energy Agency, Radiation Protection and Waste Management Div., 92 - Issy les Moulineaux (France); Stoltz, M. [Autorite de Surete Nucleaire, 75 - Paris (France); Louet, Ch.A. [Autorite de Surete Nucleaire, Div. de Lyon, 69 - Lyon (France); Chartier, M.; Monier, C. [Institut de Radioprotection et de Surete Nucleaire, 92 - Clamart (France); Devin, P. [AREVA, 92 - Paris la Defense (France); Andrieux, D. [AREVA NC la Hague, 50 (France); Levy, F. [CEA Valrho, 30 - Marcoule (France); Guidez, J. [CEA Saclay, 91 - Gif sur Yvette (France); Dubois, F. [Electricite de France (EDF), Div. Production Nucleaire, 75 - Paris (France); Kusz, J.P. [Centre Nucleaire de Production d' Electricite de Gravelines, 59 (France); Lamine, C. [Centre Nucleaire de Tihange (Belgium); Colacicco, M. [Electricite de France (EDF), 75 - Paris (France); Nicaise, N. [AREVA NP-SAS, 92 - Paris la Defense (France)

    2008-01-15

    This series of articles deals with the experience feedback concerning the environmental impacts of nuclear installation operations. A large range of aspects are dealt with, among them: -)the release of radioactive effluents, -) the production of radioactive and non-radioactive wastes, -) occupational exposure, -) the radiological protection of the environment, or -) the control of nuclear installations by the French Nuclear Safety Authority (ASN). The feedback experiences from La Hague plant, from the Marcoule site, from the Phenix reactor and from the Gravelines and Tihange nuclear power plants are detailed. The last article describes the design options that have been taken to reduce the environment impact of the EPR (European Pressurized Reactor) reactor. (A.C.)

  5. Homogeneity study of enriched uranium dioxide to be used in intercomparison programs in the brazilian nuclear facilities

    International Nuclear Information System (INIS)

    The Brazilian nuclear facilities must dispose of measurement systems that allow the determination of their nuclear material inventories. The main goal of this work is the characterization of enriched uranium dioxide (UO2) pellets to use as test sample to evaluate and verify these systems through the participation of the involved laboratories in interlaboratorial comparison programs. The programs are formed by a network of specialized laboratories in determining materials of the nuclear fuel cycle. Therefore, before being sent to laboratories, the materials must have their homogeneity confirmed. The homogeneity study of the UO2 pellets has being carried out in the Safeguards Laboratory (LASAL) of Brazilian Nuclear Energy Commission (CNEN) through Destructives Analysis technique. The technique used was Davies and Gray/NBL titrimetric method. For this purpose, 25 pellets of enriched uranium dioxide from two different batches were randomly chosen. The model for homogeneity study between-unit variation (between-bottle homogeneity study) and minimum sample intake (within-bottle homogeneity study) adopted is a one-way ANOVA. No statistical significant differences were observed in the results of total uranium concentration for both batches. Thus, the UO2 pellets are considered homogeneous and can be used in a Brazilian measurement systems evaluation program.(author)

  6. Ordinance of 28 November 1983 on protection in case of emergencies in the neighbourhood of nuclear installations

    International Nuclear Information System (INIS)

    This Ordinance (RS 732.23) lays down the measures to be taken to assure the security of the population neighbouring nuclear installations. It defines the tasks of the nuclear operator, the Federal services as well as those of the Cantons and Communes. The Ordinance fixes the exact allocation of the costs of the emergency organisation and alarm system. The Ordinance entered into effect on 1 January 1984. (NEA)

  7. Case-control study of leukaemia and non-Hodgkin's lymphoma in children in Caithness near the Dounreay nuclear installation.

    OpenAIRE

    Urquhart, J. D.; Black, R J; Muirhead, M. J.; Sharp, L; Maxwell, M.; Eden, O B; Jones, D. A.

    1991-01-01

    OBJECTIVE--To examine whether the observed excess of childhood leukaemia and non-Hodgkin's lymphoma in the area around the Dounreay nuclear installation is associated with established risk factors, or with factors related to the plant, or with parental occupation in the nuclear industry. DESIGN--Case-control study. SETTING--Caithness local government district. SUBJECTS--14 cases of leukaemia and non-Hodgkin's lymphoma occurring in children aged under 15 years diagnosed in the area between 197...

  8. Regulatory oversight report 2008 concerning nuclear safety in Swiss nuclear installations; Aufsichtsbericht 2008 ueber die nukleare Sicherheit in den schweizerischen Kernanlagen

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2009-04-15

    This annual report issued by the Swiss Federal Nuclear Inspectorate (ENSI) reports on the work carried out by the Inspectorate in 2008. This report reviews the regulatory activities in the four Swiss nuclear power stations and in four further nuclear installations in various Swiss research facilities. It deals with topics such as operational details, technologies in use, radiation protection, radioactive wastes, emergency dispositions, personnel and provides an assessment of operations from the safety point of view. Also, the transportation of nuclear materials - both nuclear fuels and nuclear wastes - is reported on. General topics discussed include probabilistic safety analyses and accident management, earthquake damage analysis and agreements on nuclear safety. The underground disposal of highly-radioactive nuclear wastes and work done in the rock laboratories are discussed, as are proposals for additional nuclear power stations.

  9. The creation of the analytical information system to serve the process of complex decommissioning of nuclear submarines (NSM) and surface ships (SS) with nuclear power installations (NPI)

    International Nuclear Information System (INIS)

    Management of the decommissioning of nuclear vessels includes information collection, accumulation, systematisation and analysis on the complex utilization of nuclear submarines and surface ships with nuclear power installations and on treatment of spent nuclear fuel and radioactive wastes. The relevant data on radiation and ecology, science and technology, law and economy, administration and management should be properly processed. The general objective of the analytical information system (AIS) development, described in the present paper, is the efficiency upgrading for nuclear submarine utilization management and decision making. The report considers information provision and functioning principles as well as software/hardware solutions associated with the AIS creation. (author)

  10. Alteration in reactor installation (addition of Unit 2) in the Sendai Nuclear Power Station of Kyushu Electric Power Co., Inc

    International Nuclear Information System (INIS)

    The deliveration by the Nuclear Safety Commission was commenced on the alteration in reactor installation, as it had been inquired by the Ministry of International Trade and Industry. The alteration is the additional installation of the reactor No. 2 in the Sendai Nuclear Power Station, Kyushu Electric Power Co., Inc. It is a PWR power plant with thermal output of about 2,660 MW (electric output of 890 MW), to be installed, adjoining to the reactor No. 1 of the same type and capacity under construction. In the examination by MITI, it was confirmed that the technological capabilities for its construction and operation and the radiation protection measures in power generation are both sufficient. The contents of the examination include the siting conditions, the location and construction of reactor facilities, etc. (J.P.N.)

  11. ATPu installation - INB 32: complementary safety evaluation in the light of the Fukushima Daiichi nuclear power station accident

    International Nuclear Information System (INIS)

    This report proposes a complementary safety evaluation of the ATPu installation (the Plutonium technology workshop, INB 32) in Cadarache, one of the French basic nuclear installations (BNI, in French INB) in the light of the Fukushima accident. This evaluation takes the following risks into account: risks of flooding, earthquake, loss of power supply and loss of cooling, in addition to operational management of accident situations. It presents some characteristics of the installation (brief description, activities, hazardous and radioactive products, specific risks), identifies the risks of cliff effect and the main structures and equipment, evaluates the seismic risk (installation sizing, installation conformity, margin evaluation), evaluates the flooding risk (installation sizing, installation conformity, margin evaluation), briefly examines other extreme natural phenomena (extreme events, combination of events, risk related to dam failure due to an earthquake). It analyzes the risk of a loss of power supply and of cooling (loss of external and internal electric sources, loss of the ultimate cooling system). It analyzes the management of severe accidents: crisis management organization, available intervention means, robustness of available means. It discusses the conditions of the use of subcontractors

  12. Safety culture in nuclear installations. Management of safety and safety culture in Indian NPPs

    International Nuclear Information System (INIS)

    Nuclear Power Corporation Of India Ltd. (NPCIL) is a company owned by Government of India and is responsible for Design, Construction, Commissioning, Operation and Decommissioning of Nuclear Power plants in India. Presently, a total of 13 Nuclear power Stations are in operation with an installed capacity of 2620 MWe and 2 VVR type PWR Units of 1000 MWe capacity each, 2 PHWR type units of 500 MWe capacity each and 4 PHWR type 220 MWe capacity each are under construction. NPPs generation capacity has been increased from 70% to 85% in the span Of last 7 years with high level of safety standards. This could be achieved through Management commitment towards building a strong Safety Culture. Safety culture is that assembly of characteristics and attitudes in organisation and individuals which establishes that as an overriding priority nuclear plant safety issues receives the attention warranted by their significance. This definition of safety culture brings out two major components in its manifestation. The framework within which individuals within the organisation works.The attitude and response of individual towards the safety issues over productivity and economics in the organisational work practices. The two attributes of safety culture are built in and upgraded in each individuals through special training at the time of entry in the organisation and later through in built procedures in the work practices, motivation and encouragement for free participation of each individuals. Individuals are encouraged to participate in Quality circle teams at the sectional level and review of safety proposal originated by individuals in Station operation Review Committee at Station level, in addition to this to continuously enhance the safety culture, refresher training courses are being organised at regular intervals. The safety related proposals are categorised in to two namely: Proposals from Operating Plants, and Proposals from projects and Design. The concept of safety

  13. The Community's research and development programme on decommissioning of nuclear installations (1989-1993). Annual progress report 1991

    International Nuclear Information System (INIS)

    This is the second annual progress report of the European Community's programme (1989-93) of research on decommissioning of nuclear installations. It shows the status of the programme on 31 December 1991. This second progress report summarizes the objectives, scope and work programme of the 76 research contracts concluded, as well as the progress of work achieved and the results obtained in 1991

  14. Installation modification of the reactor in Onagawa Nuclear Power Station, Tohoku Electric Power Company, Inc

    International Nuclear Information System (INIS)

    The head of Japan Atomic Energy Commission submitted on September 29, 1978, to the Prime Minister the report that the modification of the reactor installation in Onagawa Nuclear Power Station which is constructed by the Tohoku Electric Power Company, Inc., is in conformity with the relevant laws, annexing the evaluating report that had been deliberated by the Nuclear Reactor Safety Evaluation Committee. The modification is related to the fuel assemblies, the minimum critical power ratio (MCPR), the falling speed of control rods, the maximum reactivity worth of control rods, the independent back-up reactor shut down system, the concentration control system for burnable gas, the iodine removal efficiency of emergency gas process system and the discharge position of condenser-cooling water. The evaluated results of these modifications are explained one by one. By the adoption of 8 x 8 fuel pin array, the maximum linear output density of a fuel pin is decreased, and it was confirmed that the MCPR would be kept always more than the minimum critical value of 1.06. Also, it was evaluated that the channel hydraulics, the core and the plant are stable, and the xenon spatial oscillation can be sufficiently controlled. The limit of the free falling speed of control rods is modified to 0.95 m/s from 1.5 m/s, and the scram time for 90% stroke is revised to less than 3.5 s from about 5.0 s. The maximum reactivity worth of control rods is corrected to less than 0.015 Δk from 0.025 Δk. Considering LOCA, the concentrations of hydrogen and oxygen gases are kept less than 4% and 5%, respectively, utilizing the recombining system in the containment vessel. The discharge point of condenser cooling water is relocated to the offshore about 260 m from the coast. (Nakai, Y.)

  15. EU research in 'operational safety of existing installations' under the nuclear fission programme 1998-2002

    International Nuclear Information System (INIS)

    In this paper, an overview is given of the most important aspects of the research activities organised by the European Union (EU) in the area of reactor safety under the current 5th Euratom Framework Programme 1998-2002 (FP-5). This area is focussing on 'Operational Safety of Existing Installations'. The fundamental safety objective for nuclear power plants (NPPs) consists in protecting the public and the environment from the harmful effects resulting from ionising radiations. Community research with this objective is carried out through both 'indirect actions' (organised by DG Research) and 'direct actions' (carried out by DG Joint Research Centre/JRC). The mid-term achievements of this area were discussed at the symposium FISA-2001 (EC Luxembourg, 12-14 November 2001/750 pages, EUR 20281 EN, OPOCE Luxembourg 2002). This research area is actually part of the FP-5 Key Action NUCLEAR FISSION, which consists of the following four areas: reactor safety, waste management (including partitioning and transmutation), future systems (including high temperature reactors), and radiation protection. More specifically, this paper deals with the strategy, the organisation and the main achievements of the 73 multi-partner projects cosponsored by the European Union as 'indirect actions' (shared-cost and concerted actions). These projects are organised in three clusters, each devoted to one key safety issue. Each cluster is treated in a separate section of this paper, namely: (1) Plant Life Extension and Management (PLEM cluster), (2) Severe Accident Management (SAM cluster), and (3) Evolutionary Safety Concepts (EVOL cluster). The total cost of the 'indirect actions' of this Community research area is approximately Euro 82.5 million, out of which Euro 43 million is contributed by the EU budget. At FISA-2001, only the 'indirect actions' that started before 1 January 2001, were formally presented, i.e. a total of 41 projects - the 32 more recent multi-partner projects were

  16. Management of disused sealed sources received by the Brazilian Center for Development of Nuclear Technology - CDTN, MG

    International Nuclear Information System (INIS)

    The increasing use of radioactive sources in Brazil brought as a consequence the increased number of disused sources because, after the withdrawal of the service, the sources are discarded by users of radioisotopes. These sources have been forwarded to the research institutes of the CNEN, among them CDTN - Brazilian Center for Development of Nuclear Technology -, who have received a significant amount of them, including more intense activity sources, such as from the teletherapy. For effective control of the sources, the compliance of the CNEN - Brazilian Nuclear Energy Commission - and the recommendations of IAEA -International Atomic Energy Agency - implemented a management system that enables the monitoring of the entire process, from the initial contact to the delivery of supplies to its appropriate packaging. This paper describes the progress that has been made

  17. The Brazilian experience in the implementation of nuclear security activities for the 2007 Pan-American Games

    International Nuclear Information System (INIS)

    The actions taken by the Brazilian Nuclear Energy Commission (CNEN) related to nuclear and radiological security for the Pan-American Games and for the Para Pan- American Games, held in Rio de Janeiro, Brazil in 2007, are presented. This was part of a multi-institutional plan for the security of the games, coordinated by the National Secretary of Public Security of the Ministry of Justice (SENASP/MJ). The support provided by the IAEA under a cooperation arrangement with the Brazilian authorities was a key factor for the success of the whole operation. The organization and concept of operations adopted are described, and the results of the survey of venues before the start of the games and of the access control are presented. (author)

  18. Transfer coefficients to terrestrial food products in equilibrium assessment models for nuclear installations

    International Nuclear Information System (INIS)

    Transfer coefficients have become virtually indispensible in the study of the fate of radioisotopes released from nuclear installations. These coefficients are used in equilibrium assessment models where they specify the degree of transfer in food chains of individual radioisotopes from soil to plant products and from feed or forage and drinking water to animal products and ultimately to man. Information on transfer coefficients for terrestrial food chain models is very piecemeal and occurs in a wide variety of journals and reports. To enable us to choose or determine suitable values for assessments, we have addressed the following aspects of transfer coefficients on a very broad scale: (1) definitions, (2) equilibrium assumption, which stipulates that transfer coefficients be restricted to equilibrium or steady rate conditions, (3) assumption of linearity, that is the idea that radioisotope concentrations in food products increase linearly with contamination levels in the soil or animal feed, (4) methods of determination, (5) variability, (6) generic versus site-specific values, (7) statistical aspects, (8) use, (9) sources of currently used values, (10) criteria for revising values, (11) establishment and maintenance of files on transfer coefficients, and (12) future developments. (auth)

  19. Condition assessment of installed nuclear power plant (I and C) cables

    International Nuclear Information System (INIS)

    Twenty-five to thirty-five year old nuclear power plants are undergoing rehabilitation programs to extend the plant life to 50 or 60 years. Instrumentation and control (I and C) cables are identified as one of the major components examined in the life extension programs. Cable insulation is exposed to ionizing radiation, elevated thermal, vibration, and moist environments during normal operation in addition to extra ordinary radiation and thermal conditions in a postulated design basis accident event. Aged insulations are prone to either embrittlement and cracking or an alteration in material chemistry causing changes in dielectric properties which leads to shorting when moisture is present. This presentation discusses the techniques used to perform a condition assessment of cable insulation by means of visual and other non destructive techniques, namely, EPRI Indenter measurements and near infrared (NIR) scanning technology. Low voltage installed cables which are insulated with PVC, FRXLPE, and FREPR, and which are jacketed with PVC, are considered. The techniques discussed will allow plant personnel to extend cable life without additional qualification tests. (author)

  20. The Non-Proliferation Treaty of Nuclear Weapons (NPT) and the insertion of the Brazilian State in its regime

    International Nuclear Information System (INIS)

    The issue of nuclear weapons continues to appear as a focal point of International Relations. The efforts and concrete actions on disarmament, non-proliferation, and nuclear arms control are still issues that generate recurring tensions between States. However, in Brazil, there is little analysis of an academic nature about these issues and, with respect to current and prospective position of the Brazilian State in the Nuclear Weapons Non- Proliferation Regime, studies and analysis are even more scarce, or incipient. The present dissertation has as its object of study to the Treaty on the Non-Proliferation of Nuclear Weapons (NPT), the Regime arisen from NPT, and the Brazilian State insertion process in this Regime. Therefore our research work is structured in three areas: the first one is about the role of nuclear weapons in States security perception, the second is about NPT and its Regime, the third runs over the insertion of the Brazilian state in this regime. So, in summary, the research performed included the reasons that make a State to develop nuclear weapons, the NPT genesis and evolution of the perception of the meaning of that Treaty by the States, and the process and the degree of insertion of Brazil in the Nuclear Weapons Non- Proliferation Regime. The inquiry sought to place this object of study in the broader debate on Foreign Relations, based on the approaches of the discipline devoted to the question of managing the security of States, id est, the two approaches that constitute the mainstream of the discipline: the perspective theoretical liberal (and neoliberal variants) and realistic thinking (and neo-realist). Thus, we have used different theoretical lenses, which we think necessary for understanding the specific parts and causal connections between these parts of a complex issue. (author)

  1. The Brazilian nuclear industries - INB - in the field of the rare earth

    International Nuclear Information System (INIS)

    The Brazilian Nuclear Industries - INB is responsible for the execution of part of the cycle of uranium as nuclear reactor fuel for alternative energy generation. Soon INB shall increase the participation in this cycle, through the implantation of the line of powder and pastille. INB is also the successor of the monazite processing industries. The last one was NUCLEMON that was incorporated by INB. The connection of INB with this area is due to the presence of the strategic elements uranium and thorium in the monazite. The know-how was and continues to be developed by a chemical team of the National Commission of Nuclear Energy (CNEN) with the collaboration of the technical team of INB. The ever wider applications of the individual Rare Earth in the most different fields of the electrical, electronics, communication, optical, metallurgical, catalysis and other industries, as well as INB incessant inquire for the economical workability, brought INB to appraise the position regarding to the industrial production of the Rare Earth. The choice is bringing to the separation and commercialization of the individual elements and/or in groups containing a reduced number of Rare Earth, instead of the production and commercialization of the mixture of monazitic Rare Earth. This paper illustrates through quantitative information some aspects regarding to reserves, mining and physical separations of the monazite, as well as projections about INB resuming its industrial activities with insertion of technical improvements in both, the chemical treatment of the monazite and the Rare Earth separation. In this field, there will be presented in this paper the qualitative and quantitative results recently reached in a large dimension pilot plant. These results add to the technical conquest reached in the late years by the foregoers of INB, and that will be also presented. The paper contains also some appreciations regarding to the perspectives of INB's ingression in the field of

  2. Inspection of the brazilian nuclear regulatory body in the area of radiotherapy. A critical analysis

    International Nuclear Information System (INIS)

    The National Commission of Nuclear Energy (CNEN) is responsible in Brazil for the activities of licensing and control of radioactive installations in the radiotherapy medical area. The majority of these activities are developed by CNEN Co-ordination of Radioactive Installations (CORAD). One of the necessary stages for the development of licensing and control activities is the inspection of radiotherapy services (clinics and hospitals). Almost all of these inspections are carried out by CNEN Inst. of Radiation Protection and Dosimetry (IRD), through its Service of Medical Physics in Radiotherapy and Nuclear Medicine (SEFME). This work makes a survey of the main nonconformities found during ten years of inspections in radiotherapy services (1995 - 2004) and analyses the efficiency of these inspections in making the radiotherapy services develop their activities according to the norms in vigour in the country and adopt corrective actions against, at least, the nonconformities evidenced by CNEN inspectors. Additionally, it analyses the possibility of improvement and / or the optimisation of the process, through a procedure able to be unified and controlled, aiming a prompt communication to those involved in the licensing process (SEFME and CORAD) about the attendance by the radiotherapy services to the non-conformity items observed during the inspection. (author)

  3. Committee on the safety of nuclear installations - Operating plan (2006 - 2009)

    International Nuclear Information System (INIS)

    In 2004, NEA issued its Strategic Plan covering the period 2005-2009, addressing the NEA activities associated with nuclear safety and regulation. Committee on the Safety of Nuclear Installations (CSNI) and Committee on Nuclear Regulatory Activities (CNRA), which have the primary responsibility for activities in this area, have developed and issued a joint strategic plan covering this same time period. As requested in the Joint Strategic Plan, each committee is to prepare an operating plan which describes in more detail the committee's organisation, planned activities, priorities and operating procedures to be used to implement the Joint Strategic Plan. In effect, the Joint Strategic Plan defines what type of work CSNI should do, whereas the Operating Plan describes the overall work scope and how to accomplish it to meet the joint CSNI/CNRA Strategic Plan objectives and mission. The present Operating Plan follows and takes into account the outcome of a CSNI assessment group, which has evaluated the CSNI activities. The assessment group expressed appreciation for the CSNI role and activity, while making recommendations with regards to scope of work and way to operate in order to further improve efficiency. The main objectives of CSNI are to: - Keep all member countries involved in and abreast of developments in safety technology. - Review operating experience with the objective to identify safety issues that need to be addressed by new research. - Review the state-of-knowledge on selected topics of nuclear safety technology and safety assessment. - Promote training and research projects that serve to maintain competence in nuclear safety matters. - Promote research as needed to reach consensus on nuclear safety issues of common interest. - Consider the safety implications of scientific and technical developments. To accomplish these objectives, CSNI is organised into six permanent working groups (as described in Section II), each covering a different set of

  4. Accountability and non-proliferation nuclear regime: a review of the mutual surveillance Brazilian-Argentine model for nuclear safeguards; Accountability e regime de nao proliferacao nuclear: uma avaliacao do modelo de vigilancia mutua brasileiro-argentina de salvaguardas nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Xavier, Roberto Salles

    2014-08-01

    The regimes of accountability, the organizations of global governance and institutional arrangements of global governance of nuclear non-proliferation and of Mutual Vigilance Brazilian-Argentine of Nuclear Safeguards are the subject of research. The starting point is the importance of the institutional model of global governance for the effective control of non-proliferation of nuclear weapons. In this context, the research investigates how to structure the current arrangements of the international nuclear non-proliferation and what is the performance of model Mutual Vigilance Brazilian-Argentine of Nuclear Safeguards in relation to accountability regimes of global governance. For that, was searched the current literature of three theoretical dimensions: accountability, global governance and global governance organizations. In relation to the research method was used the case study and the treatment technique of data the analysis of content. The results allowed: to establish an evaluation model based on accountability mechanisms; to assess how behaves the model Mutual Vigilance Brazilian-Argentine Nuclear Safeguards front of the proposed accountability regime; and to measure the degree to which regional arrangements that work with systems of global governance can strengthen these international systems. (author)

  5. Optimization of activities purposed to enhance the security of nuclear materials and installations

    International Nuclear Information System (INIS)

    ; security technology users; security technology evaluators. A security level and the effectiveness of physical protection of nuclear materials and installations in Rosatom are identified in accordance with the requirements of government and international normative legal documents and regulations. (author)

  6. Nuclear Liability and Insurance Cover for Risk of Nuclear Power Plants - Situation for Nuclear Installations in Germany

    International Nuclear Information System (INIS)

    A dispute about nuclear liability and insurance cover for risks of nuclear power plants from an insurer's point of view has to determine and to judge the essential risk relevant factors. These are beside plant and site specific factors considerations of insurance restrictions in the extent of cover compared with the legal scope of liability for (re-)insurability's sake. Among such consideration are: financial limitation and obligation for its reinstatement, exclusions for gradual emissions of approved activities, armed conflicts, hostilities, civil war, insurrections or grave natural disaster and restrictions in the limitation and preclusion periods. In comparison with conventional liability risks there are some specialties to be considered some of which prove to be a risk relief other as a risk burden for insurance: Salvage expenses or interests and court costs to be paid by unsuccessful party in a lost litigation do not fall under legal liability and hence are excluded from the financial security cover so that are compensation is subject to agreed separate limits. A serious burden for the insurers can result out of the loss regulation costs in case of a severe nuclear accident. These expenses, which can exceed hundred million DM by far, are to be carried by the insurers in the frame of their obligation to investigate raised claims. Therefore the insurers should aim a fixed limitation in order to restrict their limit. (author)

  7. Role of the Regulatory Body in Implementing Defence in Depth in Nuclear Installations - Regulatory Oversight in Egypt

    International Nuclear Information System (INIS)

    The fundamental objective of all nuclear safety regulatory bodies is to ensure that nuclear facilities are operated at all times in an acceptably safe manner including the safe conduct of decommissioning activities. Defence in depth is recognized as one of the fundamental safety principles that underlie the safety of nuclear power plants. Defence in depth is implemented to provide a graded protection against a wide variety of transients, incidents and accidents, including equipment failures and human errors within nuclear power plants and events initiated outside plants. The Regulator Body plays an important role in implementing defence in depth in nuclear installations in the context of a clear allocation of responsibilities with an operating organization. This role starting with setting safety objectives and by its own independent review and technical assessment of the safety justifications provided by the operating organization in addition to safety culture investigating within relevant organizations. This paper briefly reviews this role in normal operation and post accidents, and its effects on overall nuclear safety in nuclear installations with reference to Egyptian regulatory oversight. (author)

  8. Applied methodology to study the population distribution and survey land and wastes use, habits and diets in the vicinities of nuclear installations

    International Nuclear Information System (INIS)

    With the purpose to fulfill the national and international requirements for licensing nuclear installations this work outlines the methodology used to study population distribution and to survey land and water use, habits and diets in the vicinities of nuclear installations. (B.C.A.). 08 refs, 01 fig, 03 tabs

  9. A model for environmental scanning oriented for the strategic planning of the Brazilian Nuclear Energy Commission (CNEN)

    International Nuclear Information System (INIS)

    Presently, all the organizations involved with nuclear activities must be one step ahead of what happens in the specific activity areas in order to avoid surprises, to guarantee their activity continuity and the objective extents, and taking into account the external environment influence exercised by the organization on their activities. So, it is necessary a continuous follow up of their transformations. This paper aims to structure a model of the environmental monitoring system oriented to the strategic planning of the Brazilian Nuclear Energy Commission, as function of that new informational needs viewing the fulfilment of that observed gap. (author)

  10. Regulatory oversight report 2007 concerning nuclear safety in Swiss nuclear installations; Aufsichtsbericht 2007 ueber die nukleare Sicherheit in den schweizerischen Kernanlagen

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2008-04-15

    This annual report issued by the Swiss Federal Nuclear Inspectorate (HSK) reports on the work carried out by the Inspectorate in 2007. This report reviews the regulatory activities in the four Swiss nuclear power stations and in four further nuclear installations in various Swiss research facilities. It deals with topics such as operational details, technologies in use, radiation protection, radioactive wastes, emergency dispositions and personnel and provides an assessment of operations from the point of view of safety. Also, the transportation of nuclear materials - both nuclear fuels and nuclear wastes - is reported on. General topics discussed include probabilistic safety analyses and accident management. Finally, the disposal of nuclear wastes and work done in the rock laboratories in Switzerland is commented on.

  11. Safety of civil basic nuclear installations other than reactors of the French nuclear fleet. Lessons learned by the IRSN and significant events declared in 2013 and 2014

    International Nuclear Information System (INIS)

    Published every two years, this report concerns installations related to fuel nuclear cycle, research laboratories and reactors, installations for waste processing, warehousing or storage of nuclear wastes, as well as installations which have been definitely stopped or are being remediated or dismantled. After a global and synthetic overview of these issues (highlights, lessons learned from significant events, evolution of the number of events, lessons learned from safety-re-examinations), the report first presents the legal and regulatory context, the 82 concerned installations, and aspects related to their safety. The second part proposes an analysis of significant events which occurred in 2013 and 2014: aspects related to event declaration, assessment of events and main noticed trends with respect to previous years, transverse analysis of the main types of events and evolutions with respect to previous years. The third part reports some important events which occurred in the Fontenay-aux-Roses CEA centre, in the Atalante installation, on the Tricastin site, and in the UP3-A plant of Areva NC establishment in La Hague. Some transverse topics are then addressed, i.e. safety re-examinations of various installations (the UP3-A plant in La Hague, the MELOX plant, the CEA Cadarache solid waste processing station, and the Phenix power plant)

  12. Apparatus for installing and removing a control rod drive in a nuclear reactor

    International Nuclear Information System (INIS)

    This patent describes an apparatus for installing and removing a control rod drive from beneath the pressure vessel of a nuclear reactor. It consists of elevator carriage for carrying the control rod drive into and out of the region beneath the pressure vessel in a generally horizontal position, an elevator cradle mounted on the carriage for pivotal movement about an axis between horizontal and vertical positions and for vertical movement, when in the vertical position, means for securing the control rod drive to the elevator cradle, and a winch cart movable horizontally between a first position spaced from the pivot axis and a second position near the pivot axis. The cart has a winch cable supporting the lower end of the elevator carriage for moving the elevator carriage and the control rod drive between horizontal and vertical positions on the elevator carriage when the cart is spaced from the pivot axis and for raising and lowering the elevator cradle and the control rod drive when the cart is positioned near the pivot axis. The control rod drive is mounted on the elevator cradle by a bearing permitting rotational and horizontal movement of the control rod drive when the drive is in a vertical position, a swing arm, a pneumatically actuated cylinder in axial alignment with the control rod drive for raising and lowering the control rod drive, and means pivotally mounting the cylinder on the swing arm for movement about an axis spaced from and generally parallel to the vertically extending axis so that the position of the cylinder and the control rod drive can be shifted horizontally about the vertically extending axes

  13. Preliminary Assessment of Heavy-Water Thorium Reactors in the Brazilian Nuclear Programme

    International Nuclear Information System (INIS)

    Since December 1965, the Instituto de Pesquisas Radioativas has been studying for the Brazilian Nuclear Energy Commission the feasibility of a thorium reactor programme in Brazil; since June 1966, the programme has been developed in close co-operation with the French Atomic Energy Commission. A reference conceptual design of a heavy-water-cooled and -moderated thorium converter reactor has been developed. The main features of that concept are the use of a prestressed-concrete pressure vessel, integrated arrangement of the primary circuit and the possibility of on-load fuel management. Economic competitiveness could be the result of high compactness, low capital costs and low fuel consumption. The technology involved is not very sophisticated; intensive engineering development work must be done in areas like fuel charge machine, concrete vessel insulation, and proper design of heat exchangers, but it is the feeling of the Group that these problems could be solved without seriously compromising the economic feasibility of the concept. Preliminary studies were made on the alternative use of enriched uranium or plutonium as a feed for the programme; in the latter case, plutonium could be produced in natural uranium reactors of the same type. The general conditions favouring each of these approaches to the thorium cycle have been determined, in particular those related to the costs of the fissile materials in the world market and to the country's policy related to nuclear fuel imports. The results of the preliminary studies are very encouraging and could justify the beginning of a research and development programme leading to the construction of a prototype in the 1970's. (author)

  14. Brazilian nuclear politics in the context of contemporary international relations; A politica nuclear brasileira no contexto das relacoes internacionais contemporaneas. Dominio tecnologico como estrategia de insercao internacional

    Energy Technology Data Exchange (ETDEWEB)

    Carpes, Mariana Montez

    2006-09-15

    The present dissertation analyses the retaking of the debate over Brazilian nuclear Program's recovery by Luis Inacio Lula da Silva government, based on the defense of the utilization of an already acquired technology of its own to enrich uranium. In spite of the intrinsic duality on this subject and having in mind the pacific ends concerning the utilization of such technology by Brazil, the hypothesis sustained in this work is that the Program's defense is considered a strategy of sovereign international insertion with relative autonomy and an instrument of national valorization against other powers. In order to verify the hypothesis outlined above, we will analyse the actual government, comparing it to, two other moments in Brazilian History in which the nuclear issue also acquired preponderance on the national agenda, namely, Geisel and Sarney governments. Although these three moments differ in relation to their internal political regime, our goal is to identify their similarities. (author)

  15. The safety of nuclear installations as a source of international conflict

    International Nuclear Information System (INIS)

    The author outlines safety problems regarding nuclear reactors, nuclear power plants and the whole nuclear fuel cycle and gives an account of national supervision in the FRG. Suggestions are made for easing international conflicts. (HP/LN)

  16. The Role of R and D Technical Support for the Assessment, Assurance and Improvement of Nuclear Installation Safety

    International Nuclear Information System (INIS)

    In the introduction of this paper some specific safety aspects of CANDU Cernavoda NPP are considered, emphasizing the importance and the contents of the technical support, including R and D components, for the assessment, assurance and the continued improvement of the nuclear installations safety on a medium and long term basis, with references to the Convention on nuclear safety. It focuses on techniques of nuclear safety assessment, as an essentially step for periodic verification of nuclear safety and the identification of the measures for assurance and improvements of nuclear safety. Considered as an important component of the technical support, the R and D activity in INR Pitesti devoted to the Cernavoda NPP nuclear safety has as main objectives the maintenance and development of the methods and evaluation tools used for the prediction of the plant behavior during accident conditions as well as maintenance and development of the experimental data for different plant components. In this respect the main activities carried out at INR Pitesti in the frame of the nuclear safety and reactor physics R and D program are presented. It is emphasized the importance of maintaining and developing a national competence in the field in order to provide a technical support on a medium and long term basis for a safe operation of the nuclear power plant as well as for a further consolidation of a positive perception of the public for nuclear power

  17. An authority-based machines intelligence measurement technique with implementation to human-machine collaboration navigation in the nuclear installation

    International Nuclear Information System (INIS)

    An authority-based machines intelligence measurement technique with implementation to human-machine collaboration navigation in the nuclear installation. A technique for measuring the machine intelligence quotient (MIQ) has been developed based on authority approach for decision making in 4 sequences operation task and 8 scale degrees of automation. The index of machine intelligence is important for design goals to manifest the intelligence superiority among products. The technique is mostly beneficial for predicting the autonomy level of the system. Moreover the technique is implemented for the human-machine collaboration navigation configuration in the nuclear installation. It can be concluded that MIQ of the system is 26 from the scale of 4 up to 32

  18. Industrias Nucleares do Brasil in the context of the Brazilian nuclear program; A INB no contexto do programa nuclear brasileiro

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-10-01

    The activities carried out by Industrias Nucleares Brasileiras (INB) related to the nuclear fuel cycle are described. These activities comprise presently uranium prospecting and processing and fuel elements assembly.Starting in 1997,INB will also perform the reconversion of enriched uranium hexafluoride and the fabrication of fuel pellets.Furthermore, INB produces as well rare earth oxides 2 figs., 1 tab.

  19. The Community's research and development programme on decommissioning of nuclear installations. Second annual progress report (year 1986)

    International Nuclear Information System (INIS)

    This is the second annual progress report of the European Community's programme (1984-88) of research on the decommissioning of nuclear installations. It shows the status of the programme on 31 December 1986. This second progress report describes the objectives, scope and work programme of the 58 research contracts concluded, as well as the progress of work achieved and the results obtained in 1986

  20. Safety regulation on emergency response and radiation protection in civilian nuclear installations

    International Nuclear Information System (INIS)

    The NNSA organized the review of emergency plan for the Daya Bay Nuclear Power Plant. The China Institute of Atomic Energy, the Institute of Nuclear Energy Technology, Tsinghua University and the Nuclear Power Institute of China in 1995, and organized a surveillance and inspection at site on the preparedness of emergency response and control of radiation protection for nuclear power plants and research reactors