WorldWideScience

Sample records for base nuclear installations

  1. 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

  2. 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.)

  3. 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)

  4. 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

  5. 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.

  6. 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

  7. The potential of knowledge based systems in nuclear installations

    International Nuclear Information System (INIS)

    The integration of the knowledge based systems (KBS) with processes is a new challenge for artificial intelligence developments. Integration requires improved robustness of the KBS, using methodologies which cater for building well structured, modular applications, and for verification and validation. The following key points related to KBS development were discussed during the meeting: state of the art in knowledge representation and reasoning; methods for building KBS; tools and computers used for building and implementing KBS; requirements for verification and validation; communication between KBS and the process, and between the KBS and the operators. 9 papers were presented by participants. A separate abstract was prepared for each of the papers. Refs and figs

  8. 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...

  9. 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.)

  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. 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

  12. 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

  13. 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.)

  14. 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

  15. 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

  16. 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

  17. 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

  18. Experience in installing a microprocessor-based protection system on a UK nuclear power plant

    International Nuclear Information System (INIS)

    This paper describes a recently completed project to install a microprocessor-based reactor protection system on a twin reactor station in the United Kingdom. This represented the first application of digital technology as part of such a system in the UK. The background of the application and details of the chosen solution are provided. The experience gained during the installation, commissioning and early operation of the equipment is reviewed by the operators. Interactions between the utility and the regulatory body are outlined and the impact of the regulatory process on the utility's resources and the project timescales are discussed

  19. 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

  20. 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

  1. 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

  2. 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.)

  3. Installation and evaluation of a nuclear power plant Operator Advisor based on artificial intelligence technology

    International Nuclear Information System (INIS)

    The Artificial Intelligence Group in the Nuclear Engineering Program has designed and built an Operator Advisor (OA), an AI system to monitor nuclear power plant parameters, detect component and system malfunctions, dispose their causes, and provide the plant operators with the correct procedures for mitigating the consequences of the malfunctions. It then monitors performance of the procedures, and provides backup steps when specific operator actions fail. The OA has been implemented on Sun 4 workstations in Common Lisp, and has been interfaced to run in real time on the Perry Nuclear Power Plant full-function simulator in the plant training department. The eventual goal for a fully functioning Operator Advisor would be to have reactor operators receive direction for all plant operations. Such a goal requires considerable testing of the system within limited malfunction boundaries, an extensive Verification ampersand Validation (V ampersand V) effort, a large knowledge base development effort, and development of tools as part of the system to automate its maintenance. Clearly, these efforts are beyond the scope of the feasibility effort expended during this project period. However, as a result of this project, we have an AI based platform upon which a complete system can be built

  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. 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.)

  6. 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.)

  7. 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.)

  8. 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.)

  9. 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

  10. 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

  11. 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

  12. Good practice recommendations - medical-professional control of internal exposure to radionuclides in nuclear base installations

    International Nuclear Information System (INIS)

    The first part of this voluminous report presents the context and method of definition of recommendations for a clinical practice and comprises a literature review of national, European and international recommendations, standards and work-group reports. The second part develops recommendations under four main themes: assessment of the committed effective dose (objectives, implementation, communication, traceability and archiving), control programs, dosimetric estimation based on results, and health risk and taking into care by the occupational physician. The authors adopted the same structure for each sub-theme or issue: target extract of regulatory and standard requirements and international recommendations, analysis of literature and of data from professional practices, opinion of the work-group, and graded recommendations with respect to the proof level

  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. 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

  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. 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.)

  17. Decree of January 11, 2016 bearing homologation of the decision nr 2015-DC-0532 of the Nuclear Safety Authority on November 17, 2015 related to the report on the safety of base nuclear installations

    International Nuclear Information System (INIS)

    This legal publication specifies the other related and reference legal texts and discusses the legal content of a safety report made for a given base nuclear installation: its objectives, its general elaboration principles (modalities, compliance), the content of the preliminary report, and the content of the safety report in the perspective of the installation entry into service

  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. 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

  20. 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

  1. 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)

  2. 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)

  3. 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

  4. 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)

  5. 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)

  6. 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)

  7. 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

  8. 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)

  9. 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

  10. 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)

  11. 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.

  12. 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

  13. 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.

  14. 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.)

  15. 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)

  16. 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

  17. 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

  18. 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)

  19. 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

  20. 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)

  1. 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)

  2. 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)

  3. Evaluation guideline for the study of the radiological impact of based nuclear installations (INB) presented in support of releases authorization demands

    International Nuclear Information System (INIS)

    In the case of a license demand for the effluents release and water taking for a nuclear installation, the operating must realize a study of the nuclear effluents radiological impact on the environment and the public health. In this context, the study presents technical and methodological specifications which led the Direction of the Nuclear Installations Safety (DSIN) and the General Direction of the Health (DGS) to ask the IPSN the elaboration of a guideline to help these studies evaluation. The guideline presents the regulatory context, the description of the installations, the treatment and the control processes, the rules of management, the description of the environment, the estimation of the radiological impacts and the environment control system definition. (A.L.B.)

  4. 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)

  5. 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

  6. 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'

  7. 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

  8. 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)

  9. 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)

  10. 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

  11. 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

  12. 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)

  13. 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)

  14. 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.)

  15. 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)

  16. 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.

  17. 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

  18. 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.

  19. 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

  20. 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

  1. 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.

  2. 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)

  3. 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

  4. 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

  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. 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.

  8. Opinion No. 2012-AV-0141 of the Nuclear Safety Authority on the 24 January 2012 on the order project defining the general rules related to base nuclear installations

    International Nuclear Information System (INIS)

    While specifying the definition of some terms which are used in the order project, this text presents and comments or explains the content of the different articles of the order project. It also indicates the different related legal or regulatory texts the order project refers to: organization and liabilities, integrated management, radiation protection, public information, the demonstration of nuclear security (application of the in-depth defence concept), the control of nuisances and of the impact on health and on the environment (water sampling, effluent releases in air and in water, control, prevention of pollution and nuisances, information of the control authority), pressurized equipment, waste management, preparation and management of emergency situation, and other additional measures

  9. 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)

  10. 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)

  11. 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)

  12. 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)

  13. 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

  14. 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

  15. The research for the neutron ambient dose possibility of measurement using the instrument based on the 10B-counter with moderator in the fields at JINR nuclear-physics installations

    International Nuclear Information System (INIS)

    The results of the research for the neutron ambient dose equivalent H*(10) possibility of measurement using the instrument based on the 10B-counter (CHM-14) with polyethylene moderator in the fields of JINR nuclear-physics installations have been presented. It was shown that the instrument can be used to measure H*(10) of neutrons in the energy range from 0.4 eV to 20 MeV with the uncertainty within 46% in radiation monitoring at JINR. The use of the correction factors can extend the energy range of the measurement of the neutron dose H*(10) up to hundreds of MeV. Neutron spectra, which were measured in the fields of nuclear installations of JINR earlier, places and conditions of their measurement, are presented too

  16. 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

  17. 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)

  18. 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)

  19. 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)

  20. 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

  1. 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. 

  2. 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.

  3. 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

  4. 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)

  5. 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

  6. 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)

  7. 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)

  8. 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)

  9. 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.)

  10. 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)

  11. 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)

  12. 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)

  13. 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)

  14. 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

  15. 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)

  16. 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

  17. 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.)

  18. 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

  19. 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)

  20. Medical-professional control of internal exposure to radionuclides in base nuclear installations. Extract from recommendations elaborated according to the methodological guide 'Recommendations for clinical practice' published by the Health High Authority in July 2011 - Occupational health references Nr 130

    International Nuclear Information System (INIS)

    This sheet addresses the medical-professional control of the internal exposure to radionuclides in relationship with professional activity of workers exposed to this risk in base nuclear installations. It presents and discusses published recommendations which aimed at optimizing the prevention of the internal exposure risk and the medical follow-up of workers exposed to this risk. Different themes are addressed which concerns the implementation, communication, traceability and archiving, control programmes, the assessment of the efficient dose, the health risk and the taking on by labour medicine

  1. 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)

  2. 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)

  3. Designing Software-Based Interactive Installations

    DEFF Research Database (Denmark)

    Andreasen, Troels; Juul, Niels Christian; Rosendahl, Mads

    2014-01-01

    installations and support the description of the approach with a single case- a bumper car competition. Why. To some extent, standard techniques for software development can be adapted for interactive installations. However, there is a need to emphasize the unique aspects of installations, bringing tangible...

  4. 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

  5. Evaluation guideline for the study of the radiological impact of based nuclear installations (INB) presented in support of releases authorization demands; Guide d'examen pour l'etude de l'impact radiologique d'une installation nucleaire de base (INB) fournie a l'appui des demandes d'autorisation de rejets

    Energy Technology Data Exchange (ETDEWEB)

    Chartier, M.; Despres, A.; Supervil, S.; Conte, D.; Hubert, P.; Oudiz, A.; Champion, D

    2002-10-01

    In the case of a license demand for the effluents release and water taking for a nuclear installation, the operating must realize a study of the nuclear effluents radiological impact on the environment and the public health. In this context, the study presents technical and methodological specifications which led the Direction of the Nuclear Installations Safety (DSIN) and the General Direction of the Health (DGS) to ask the IPSN the elaboration of a guideline to help these studies evaluation. The guideline presents the regulatory context, the description of the installations, the treatment and the control processes, the rules of management, the description of the environment, the estimation of the radiological impacts and the environment control system definition. (A.L.B.)

  6. 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

  7. 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

  8. 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

  9. 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.)

  10. 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

  11. 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

  12. 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)

  13. 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)

  14. 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)

  15. 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)

  16. 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

  17. 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

  18. 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)

  19. 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

  20. 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

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

    International Nuclear Information System (INIS)

    objective is timely prevention, detection of and response to the attempts to use accounted nuclear material for illicit trafficking. In addition to traditional measures, a centralized automated system to detect unauthorized intrusion, to register and suppress the penetration attempts and to organize controlled access to nuclear installation Chernobyl NPP and its internal areas is being established. This system covers three levels of hierarchical physical protection system of all facilities of Chernobyl NPP. The distinguishing features of this system are: high level of stability and reliability, automatic self-diagnostic functions, detection of performance intrusion and restoration of the normal operability. This system has a number of local physical protection subsystems which are the key data base users and are capable to operate off-line in case of the short-time loss of connection with the top level. The access means will include full-height turnstiles and tripods. In the areas of particular importance video identification is envisaged. Passive remote inductive cards encoded on-site will be used as passes. In addition, the issue of control, accountancy and physical protection to be exercised throughout the whole process of fuel discharge, cooling and transportation to KHOYAT -2 (interim storage facility), which will house nuclear material of the total activity more than 1.2 million Ci and about 4.00 tonnes Pu-239, is under review. It is envisaged to create complex to support nuclear material management processes. A provisional engineering solution provides for visual control and video recording, automated record of processes, casks' integrity control, communication means, blocking of the further operations when the precedent operations are inconsistent with QA program requirements, routing control and response forces notification. It shall be emphasized that so far we do not know for sure the amount of nuclear and radioactive materials inside the Shelter Object which is

  2. 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)

  3. 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.)

  4. 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

  5. Fessenheim INB 75 basic nuclear facilities. 2009 annual report; Installations nucleaires de base (INB) de Fessenheim INB 75. Rapport annuel 2009

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2010-07-01

    This annual report is established on account of article 21 of the 2006-686 French law from June 13, 2006, relative to the transparency and safety in the nuclear domain. It describes, first, the basic nuclear facilities of Fessenheim INB 75, and then the measures taken to ensure their safety (personnel radioprotection, actions implemented for nuclear safety improvement, organisation in crisis situation, external and internal controls, technical assessment of the facilities, administrative procedures carried out in 2009), incidents and accidents registered in 2009, radioactive and chemical effluents released by the facilities in the environment, other pollutions, management of radioactive wastes, and, finally, the actions carried out in the domain of transparency and public information. A glossary and the viewpoint of the Committee of Hygiene, safety and working conditions about the content of the document conclude the report. (J.S.)

  6. 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.)

  7. 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

  8. 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

  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. 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

  11. 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)

  12. Nuclear safety and radiation protection report of the basic nuclear facilities of the Tricastin nuclear power plant - 2010; Rapport sur la surete nucleaire et la radioprotection des installations nucleaires de base (INB) du CNPE du Tricastin - 2010

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-06-15

    This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Tricastin nuclear power plant (INB 87 and 88, Saint-Paul-Trois-Chateaux, Drome (FR)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2010, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

  13. Review of the seismic risk in the design of civil engineering of nuclear installations excepted the long term storage of radioactive wastes; Prise en compte du risque sismique a la conception des ouvrages de genie civil d'installations nucleaires de base a l'exception des stockages a long terme des dechets radioactifs

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-07-01

    This guide aims to define, for the nuclear installations excepted the long term storage of radioactive wastes, from site data, the design specifications of earthquake resistant civil engineering and the possible methods for: the determination of the seismic response of the buildings, taking into account the interactions with the materials and the evaluation of the associated strains to size the installation; the determination of seismic displacements to be considered to size the materials. (A.L.B.)

  14. 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)

  15. Modalities of declaration and codification of criteria related to significant events in the field of radioprotection besides base nuclear installations and transports of radioactive substances

    International Nuclear Information System (INIS)

    This document specifies provisions which must be applied by those in charge of a nuclear activity when declaring significant events regarding radioprotection. It describes the general principles, evokes the declaration criteria (they are more precisely presented in appendix), the declaration delay, and the declaration modalities (the informant, the documents, the addressee). It also evokes obligations regarding population information. A declaration form and a model of event report are provided in appendix

  16. 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

  17. 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)

  18. 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.)

  19. 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)

  20. 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)

  1. 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.)

  2. 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

  3. 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.)

  4. The legal provisions and practices of public participation in the decision-making process relating to siting and operation of nuclear installations: results and conclusions of a survey based on national replies to an NEA/IAEA international questionnaire

    International Nuclear Information System (INIS)

    This study is structured in the same way that the questionnaire submitted by NEA and IAEA. The chapter one is on the institutional frame governing the elaboration of nuclear policy, elaboration of safety rules, and installations agreements. It takes the question of the distribution of competences relative to authorize nuclear facilities in the case of federal states. The chapter two makes an inventory of juridical dispositions to public participation in nuclear decision-making. The chapter three explains the definition of what is the 'public'; how he can participate is studied in chapters four and five; finally the advertising to public participation and cost estimation are made in the chapters six and seven

  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. 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)

  7. Report on the behalf of Commission for National Defence and Armed Forces on the bill project (nr 1365) aiming at strengthening conditions of access to nuclear base installations (INB). Nr 2527

    International Nuclear Information System (INIS)

    This report first outlines that nuclear installations are subject to illegal intrusions which challenge their safety and security. It outlines that these installations are extremely sensitive and particularly threatened (the energy sector, as a key sector, is submitted to a specific regulation, and threats are potentially serious), that, beyond the terrorist threat and the risk of sabotage, nuclear installations are regularly facing other illegal behaviours (illegal intrusions are a recurrent issue, and drones are emerging as a new kind of threat), that the protection of nuclear installations is carried out by forces dedicated to this mission (a specialised military force for EDF sites, civil forces for the CEA and Areva, the role of the French Air Force to protect airspace), and that recent legal advances must be deepened. The second part outlines that the present legal protection framework in inadequate and incomplete. The French legal regime is presented and some foreign examples are evoked, and the need of creation of a specific penal regime is outlined. The general discussion and the discussion of the bill project articles are reported. A table proposes a comparative overview between the existing arrangement, the bill project text, and the Commission's text

  8. 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....

  9. 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

  10. 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)

  11. 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

  12. 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

  13. 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)

  14. 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)

  15. 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

  16. Decree n. 2007-534 of the 4. april 2007 allowing the creation of the base nuclear installation named Flamanville 3, including a EPR type reactor, on the site of Flamanville (Manche)

    International Nuclear Information System (INIS)

    This decree gives the authorization to EDF to create on the site of Flamanville a nuclear installation including a PWR type reactor for a power of 4500 MW and devoted to the electric production. This reactor will can use uranium oxide or a mixture of uranium oxide and plutonium oxide. Considerations concerning the safety are given, as well as the control of the impact of this exploitation on the populations and the environment. (N.C.)

  17. 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)

  18. 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)

  19. 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)

  20. 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....

  1. 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)

  2. 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)

  3. 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.)

  4. 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)

  5. 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.)

  6. 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)

  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. 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.

  13. 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)

  14. 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.)

  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. Guide relative to the modalities of statements and to the codification of criteria relative to the significant events involving the safety, the radiation protection or the environment applicable to the base nuclear installations and to the transport of radioactive matters

    International Nuclear Information System (INIS)

    It is necessary to analyze the events detected on an installation in order to be sure that an already occurred event does not be repeated, by taking into account the appropriate remedial measures, to avoid a worsen situation could occur by analyzing the potential consequences of precursory events of more serious ones, to promote the correct practices to improve the safety. The present guide has for vocation to define the arrangements enforceable to nuclear operators about the statements modalities of such events when these ones concern the safety of nuclear facilities, transport of radioactive matters, radiation protection or environmental protection. In any case it can substitute to the specific obligations coming from the work code, public health code and environment code, licensing decrees about releases. (N.C.)

  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. 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'

  4. 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.)

  5. 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)

  6. 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)

  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. 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

  15. 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)

  16. 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)

  17. 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

  18. 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

  19. 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

  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. 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.)

  3. 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.)

  4. 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)

  5. 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

  6. 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.)

  7. 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)

  8. 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)

  9. 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)

  10. 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

  11. 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

  12. 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

  13. 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

  14. 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

  15. 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

  16. 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)

  17. 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)

  18. 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)

  19. 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)

  20. 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)

  1. 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)

  2. 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)

  3. 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)

  4. 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)

  5. Order of the 9. of March 2010 approving the decision no 2010-DC-0172 of the 5. of January 2010 by the Nuclear Safety Authority specifying the limits of releases in the environment of liquid and gaseous effluents of civil base nuclear installations of the Cadarache Centre operated by the Atomic Energy Commissariat (CEA) on the district of Saint-Paul-lez-Durance (Bouches-du-Rhone department)

    International Nuclear Information System (INIS)

    This legal publication contains references to the different legal and official documents (codes, orders, minister's opinion, public surveys, administrative authorizations, local community opinion) at the root of this specification of limits related to releases in the environment of liquid and gaseous effluents of civil base nuclear installations of the Cadarache Centre operated by the Atomic Energy Commissariat (CEA) on the district of Saint-Paul-lez-Durance. These installations are listed and tables present the limits for different radioactive emissions (carbon 14, hydrogen 3, iodine, radioactive rare earths, and alpha, beta and gamma emitters) from these different installations, but also the maximum admitted concentrations for gaseous chemical effluents (HCl, HF, NOx, CO, and so on), as well as limits for thermal releases

  6. 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.)

  7. Cost Control Guide For Decommissioning Of Nuclear Installations

    International Nuclear Information System (INIS)

    This cost control guide was prepared in response to the request from the OECD/NEA Working Party on Decommissioning and Dismantling (WPDD) - Decommissioning Cost Estimation Group (DCEG) to offer the industry guidance in preparing and implementing cost and schedule controls during decommissioning. The DCEG sent out a survey questionnaire in 2010 soliciting comments from OECD member states on their use of cost controls during decommissioning. While the response was limited, the consensus was to proceed with the preparation of this guide. Cost and schedule control systems have been in use for more than 30 years, and in the last 10 years or so have evolved into a more formalised earned value management system (EVMS). This guide is based on the internationally recognised standard, Earned Value Management Systems (ANSI, 2007). The EVMS is built on a work breakdown structure (WBS) of decommissioning activities, and a defined process for controlling a project. The EVMS not only provides measurement of project status and future performance, but also builds a structure and culture for accountability on project performance. This guide describes the performance metrics used to determine the value earned based on what was planned to be done, what was actually accomplished and what it actually cost. Variances measured monthly at a minimum indicate where potential problems are arising and raise a flag for the project manager to implement corrective actions for the next reporting period. The success of the EVMS programme depends on management commitment to implement a culture change for its employees, and to impose the EVMS on potential future contractors performing decommissioning work at a facility. Formal training is required to ensure all elements of the process are understood and put into action. It is recommended to begin with a small project, and graduate to larger projects as the staff learns how to use the system. The EVMS process has been used internationally for small

  8. 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

  9. 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

  10. 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...

  11. 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

  12. 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

  13. 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)

  14. 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)

  15. 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

  16. Decree n. 2007-534 of the 4. april 2007 allowing the creation of the base nuclear installation named Flamanville 3, including a EPR type reactor, on the site of Flamanville (Manche); Decret no 2007-534 du 10 avril 2007 autorisant la creation de l'installation nucleaire de base denommee Flamanville 3, comportant un reacteur nucleaire de type EPR, sur le site de Flamanville (Manche)

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2007-04-15

    This decree gives the authorization to EDF to create on the site of Flamanville a nuclear installation including a PWR type reactor for a power of 4500 MW and devoted to the electric production. This reactor will can use uranium oxide or a mixture of uranium oxide and plutonium oxide. Considerations concerning the safety are given, as well as the control of the impact of this exploitation on the populations and the environment. (N.C.)

  17. 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

  18. 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

  19. 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

  20. 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)

  1. 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

  2. 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).

  3. 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)

  4. 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

  5. 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)

  6. 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

  7. 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

  8. 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)

  9. 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)

  10. 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

  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. 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

  13. 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

  14. 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)

  15. 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

  16. 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)

  17. 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

  18. 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).

  19. Optimization of activities purposed to enhance the security of nuclear materials and installations

    International Nuclear Information System (INIS)

    Full text: Assurance of the security for sites belonging to the atomic science, industry, and energy of the Russian Federation is based on the number of principles the top-priority of which is prevention of nuclear terrorist acts using political, communications, socioeconomic, administrative and technical, legal, and other measures. The following activities in the security area as applied to critical sites are being performed: 1. Development of the state regulations and definition of security levels for protection of critical sites from a terrorist threat (primarily hazardous nuclear sites). Introduction of unification requirements for newly designed and constructing sites. 2. Transition from 'programming-adaptive method' of management to the management by objectives according to the scheme - 'predictor-reviser'. 3. Monitoring and prevention of a terrorist threat of a direct or indirect character based on the list of potential threats developed for each specific site. Preventive activities are identified by the adversary model (number of people, used equipment and weapons, and awareness) and the adversary scenario (terrorist act). 4. All critical sites are classified by categories depending on the degree of terrorist act after-effects (damage). The damage is estimated in monetary terms based on the approved methods. 5. A complex factor is determined for an evaluation of the site protection effectiveness, namely, 'a probability of undesirable event'. 6. A standard risk is evaluated for each critical site. The risk is equal to the product of multiplication of a probability of undesirable event by the damage. The 'risk management' means that the risk reduction may be accomplished by the reduction of the probability of undesirable event or the damage value. 7. Differentiation of spheres of activities and distribution of responsibilities in the area of sites security have been established, in particularly: security technology customers; security technology designers

  20. 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.

  1. 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)

  2. 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

  3. 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

  4. 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)

  5. 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)

  6. 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

  7. Implementation of activity based cost management aboard base installations

    OpenAIRE

    Stanley, James; Perkins, Nicholas R.; Zander, Laura

    2004-01-01

    Approved for public release; distribution is unlimited. MBA Professional Report This project is a comparative analysis of the implementation process of Activity Based Cost Management of Marine Corps Logistics Base, (MCLB), Albany, and the implementation procedures used aboard MCB Camp Lejeune. Interviews and data gathering were conducted to identify how the respective Business Performance Offices (BPO), plan, implement, monitor, and measure performance of their process to introduce ABCM...

  8. 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

  9. 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.

  10. 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

  11. 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

  12. 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)

  13. Guide relative to the modalities of statements and to the codification of criteria relative to the significant events involving the safety, the radiation protection or the environment applicable to the base nuclear installations and to the transport of radioactive matters; Guide relatif aux modalites de declaration et a la codification des criteres relatifs aux evenements significatifs impliquant la surete, la radioprotection ou l'environnement applicable aux installations nucleaires de base et au transport de matieres radioactives

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-07-01

    It is necessary to analyze the events detected on an installation in order to be sure that an already occurred event does not be repeated, by taking into account the appropriate remedial measures, to avoid a worsen situation could occur by analyzing the potential consequences of precursory events of more serious ones, to promote the correct practices to improve the safety. The present guide has for vocation to define the arrangements enforceable to nuclear operators about the statements modalities of such events when these ones concern the safety of nuclear facilities, transport of radioactive matters, radiation protection or environmental protection. In any case it can substitute to the specific obligations coming from the work code, public health code and environment code, licensing decrees about releases. (N.C.)

  14. 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

  15. 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

  16. 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

  17. 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

  18. 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)

  19. 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

  20. DEVELOPMENT, INSTALLATION AND OPERATION OF THE MPC&A OPERATIONS MONITORING (MOM) SYSTEM AT THE JOINT INSTITUTE FOR NUCLEAR RESEARCH (JINR) DUBNA, RUSSIA

    Energy Technology Data Exchange (ETDEWEB)

    Kartashov,V.V.; Pratt,W.; Romanov, Y.A.; Samoilov, V.N.; Shestakov, B.A.; Duncan, C.; Brownell, L.; Carbonaro, J.; White, R.M.; Coffing, J.A.

    2009-07-12

    The Material Protection, Control and Accounting (MPC&A) Operations Monitoring (MOM) systems handling at the International Intergovernmental Organization - Joint Institute for Nuclear Research (JINR) is described in this paper. Category I nuclear material (plutonium and uranium) is used in JINR research reactors, facilities and for scientific and research activities. A monitoring system (MOM) was installed at JINR in April 2003. The system design was based on a vulnerability analysis, which took into account the specifics of the Institute. The design and installation of the MOM system was a collaborative effort between JINR, Brookhaven National Laboratory (BNL) and the U.S. Department of Energy (DOE). Financial support was provided by DOE through BNL. The installed MOM system provides facility management with additional assurance that operations involving nuclear material (NM) are correctly followed by the facility personnel. The MOM system also provides additional confidence that the MPC&A systems continue to perform effectively.

  1. 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)

  2. 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

  3. Decision no 2009-DC-0155 of the 15. of September 2009 by the Nuclear Safety Authority specifying the limits of releases in the environment of liquid and gaseous effluents of base nuclear installations n. 18, 35, 40, 49, 50, 72, 77 and 101 operated by the Atomic Energy Commissariat (CEA) in its Saclay Centre, located on the districts of Saclay, Saint-Aubin and Villiers-le-Bacle (Essonne department); Decision n. 2009-DC-0155 de l'Autorite de surete nucleaire du 15 septembre 2009 fixant les limites de rejets dans l'environnement des effluents gazeux des installations nucleaires de base n. 18, 35, 40, 49, 50, 72, 77 et 101 exploitees par le Commissariat a l'energie atomique (CEA) sur son centre de Saclay, situe sur les territoires des communes de Saclay, Saint-Aubin et Villiers-le-Bacle (departement de l'Essonne)

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2009-07-01

    This document contains references to the different legal and official documents (codes, orders, minister's opinion, public surveys, administrative authorizations, local community opinion) at the root of this specification of limits related to releases in the environment of liquid and gaseous effluents of base nuclear installations of the Saclay Centre operated by the Atomic Energy Commissariat (CEA). Tables present the limits for different radioactive emissions (carbon 14, hydrogen 3, iodine, radioactive rare earths, and other alpha, beta and gamma emitters) from these different installations, but also the maximum admitted concentrations for gaseous chemical effluents (HCl, HF, NOx, CO, and so on), as well as limits for thermal releases

  4. Study of basic safety-related aspects of decommissioning nuclear installations. Pt. 1. Legal aspects and set of technical rules

    International Nuclear Information System (INIS)

    The set of nuclear rules is checked for its applicability to the decommissioning, safe containment and dismantling of nuclear installations. In the foreground of the individual parts of the set of rules is the question about the relevance of licensing procedures according to No. 7 para. 3 of the Atomic Energy Law. The set of rules checked, basically consists of: 1. the Atomic Energy Law (AtG), the ordinances adopted on its basis (AtVfV, StrSchV, AtDeckV, AtKostV, EndlagerVIV, AtSMV) and on neighbouring laws (StrVG, BImschG, UVPG, AbfG); 2. the announcements of the BMU, BMI and BMFT: 3. the recommendations of the RSK, SSK, the rules of the KTA, the DIN standards, and 4. several international guidelines and recommendations (European Union EU, IAEA, NEA of the OECD). A generic assessment is performed, in the course of which, starting from the content or treated facts, reference to defined licensing facts and the wording, it is determined whether a specific regulation or rule is relevant or irrelevant in the licensing procedure according to No. 7 para. 3 Atomic Energy Law. In addition, a plant-related evaluation based on implemented licensing procedures is done. The expertises and licensing notifications referred to for this purpose, which represent a wide cross-section of German nuclear installations, were evaluated to find out which of the regulations and rules were explicitely applied. (orig./HP)

  5. 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

  6. 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

  7. 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

  8. 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)

  9. 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)

  10. 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

  11. 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)

  12. 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.

  13. 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)

  14. 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

  15. 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

  16. 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

  17. 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)

  18. 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.)

  19. 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)

  20. A DICOM based PACS for nuclear medicine

    International Nuclear Information System (INIS)

    The installation of a radiology information system (RIS) connected to a hospital information system (HIS) and a picture archiving and communications system (PACS) seems mandatory for a nuclear medicine department in order to guarantee a high patient throughput. With these systems a fast transmission of reports, images to the in- and out-patients' wards and private practitioners is realized. Therefore, since April 2000, at the department of nuclear medicine of the university of Wuerzburg a completely DICOM based PACS has been implemented in addition to the RIS. With this system a DICOM based workflow is realized throughout the department of nuclear medicine for reporting and archiving. The PACS is connected to six gamma-cameras, a PET scanner, a bone densitometry system and an ultrasound device. The volume of image data archived per month is 4 GByte. Patient demographics are provided to the modalities via DICOM-Worklist. With these PACS components a department specific archive purely based on DICOM can be realized. During the installation process problems occurred mainly because of the complex DICOM standard for nuclear medicine. Related to that is the problem that most of the software implementations still contain bugs or are not adapted to the needs of a nuclear medicine department (particularly for PET). A communication software for the distribution of nuclear medicine reports and images based on techniques used for the worldwide web is currently tested. (orig.)

  1. 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.)

  2. 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...

  3. 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

  4. 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

  5. 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.

  6. 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

  7. 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

  8. 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

  9. 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)

  10. 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

  11. 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

  12. Order of the 9. of March 2010 approving the decision no 2010-DC-0172 of the 5. of January 2010 by the Nuclear Safety Authority specifying the limits of releases in the environment of liquid and gaseous effluents of civil base nuclear installations of the Cadarache Centre operated by the Atomic Energy Commissariat (CEA) on the district of Saint-Paul-lez-Durance (Bouches-du-Rhone department); Arrete du 9 mars 2010 portant homologation de la decision no 2010-DC-0172 de l'Autorite de surete nucleaire du 5 janvier 2010 fixant les limites de rejets dans l'environnement des effluents liquides et gazeux des installations nucleaires de bases civiles du centre de Cadarache exploitees par le Commissariat a l'energie atomique (CEA) sur la commune de Saint-Paul-lez-Durance (departement des Bouches-du-Rhone)

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2010-07-01

    This legal publication contains references to the different legal and official documents (codes, orders, minister's opinion, public surveys, administrative authorizations, local community opinion) at the root of this specification of limits related to releases in the environment of liquid and gaseous effluents of civil base nuclear installations of the Cadarache Centre operated by the Atomic Energy Commissariat (CEA) on the district of Saint-Paul-lez-Durance. These installations are listed and tables present the limits for different radioactive emissions (carbon 14, hydrogen 3, iodine, radioactive rare earths, and alpha, beta and gamma emitters) from these different installations, but also the maximum admitted concentrations for gaseous chemical effluents (HCl, HF, NOx, CO, and so on), as well as limits for thermal releases

  13. 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

  14. 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

  15. The current CEA/DRN safety approach for the design and the assessment of future nuclear installations

    International Nuclear Information System (INIS)

    The purpose of the document is to present the basis of the safety approach currently implemented by the CEA/DRN, both for the design and the assessment of innovative systems and future nuclear installations. This approach is the result of the experience maturated, within the context of the CEA/DRN Innovative Programme through practical applications over several future concepts, both for fission and fusion reactors, as well as for waste disposal. The background of this experience is structured coherently with the European Safety Authorities recommendations and the European Utilities Requirements (EUR). The Defence In Depth principle and its application, by means, among others, of the barrier concept, remains the basis of the safety design process of future nuclear installations. Its adequacy is checked through the safety assessment. The methodology for Lines Of Defence (LOD) implementation as well as the one for the LOD architecture assessment is shown and motivated. The document shows that the clear and unambiguous definition of the safety approach provides an essential base for the organisation of the design tasks, being sure that the safety aspects are correctly taken into account and implemented, and for an adequate safety assessment of the final design, both from qualitative point of view as well as for the quantitative safety analysis. (author)

  16. 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)

  17. 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

  18. 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.

  19. 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)

  20. 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.)

  1. 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

  2. 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

  3. Project-based learning used for teaching electrical installations and lighting installations in architecture

    Directory of Open Access Journals (Sweden)

    Alicia Martinez Anton

    2011-04-01

    Full Text Available Purpose: This paper discusses the use of Project-Based Learning (PBL in the subject "Acondicionamiento y Servicios 2", which is taught at the Escuela de Arquitectura at the UPV.Design/methodology/approach: Case study.Findings: The results show that the goals (motivation, improved learning outcomes, independent learning and connection with professional practice, which led to the introduction of this kind of learning, have been achieved.Research limitations/implications: This work has been proved in two groups of a subject. Therefore, conclusions are specifically related to this context and generalization is not proved.Practical implications: Increase motivation, improved learning outcomes, independent learning and connection with professional practice.Originality/value: This work confirms previous studies about the useful of PBL in engineering matters.

  4. 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)

  5. 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)

  6. 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

  7. 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

  8. 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

  9. 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

  10. 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.

  11. 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.

  12. Alteration in reactor installation (addition of Unit 2) in the Sendai Nuclear Power Station of Kyushu Electric Power Co., Inc. (report)

    International Nuclear Information System (INIS)

    A report by the Nuclear Safety Commission to the Ministry of International Trade and Industry was presented concerning the addition of Unit 2 to the Sendai Nuclear Power Station, Kyushu Electric Power Co., Inc.. The technical capabilities of Kyushu Electric Power Co., Inc., for the installation and operation of the Unit 2 and the safety in hazard prevention concerning the Unit 2 were confirmed by the NSC, based on the experiences in the similar installation of nuclear power plants of Kyushu Electric Power Co., Inc., and according to the results of examination by the Committee on Examination of Reactor Safety. The contents of the examination are given as follows: site conditions, the safety design of reactor facilities, radiation exposure evaluation in normal plant operation, the analysis of abnormal transients in plant operation, accident analysis, and site evaluation. (J.P.N.)

  13. 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

  14. 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)

  15. 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

  16. Classe 1E (category K1) measurement, control and power cables installed in PWR nuclear power plants in France

    International Nuclear Information System (INIS)

    The very special ambient conditions defined for a reactor building of a PWR nuclear power plant are such that very different types of cable from those used traditionally in the conventional parts of the power plant are required for class 1E and category K1 safety circuits. These new types of cables are intended for installation in the parts of nuclear power plants submitted to ionising radiation and to ambient temperatures which are often high. The reliability of this type of cable has been checked by means of an EDF qualification test, based partially on US standards and partly on original tests (long duration cyclical ageing tests, lasting 5000 hours) conducted by EDF on power cables which are representative of the behaviour of the service equipment. It is intended that these ageing methods should later be adopted and generalised for the qualification of future cables. Pursuant to this procedure, a qualification campaign has been carried out, during which the electrical and mechanical properties of the cables were measured and analysed after every stage. EDF has approved this type of cables for class 1E and category K1 safety circuits in 900 and 1300 MW PWR nuclear power plants

  17. Effect of dust loading due to fire accident on pressure drop across HEPA filters in a nuclear installation

    International Nuclear Information System (INIS)

    HEPA filters are the principal air cleaning components in ventilation systems of nuclear facilities. They must be capable of continued operation under severe conditions created during emergency situations. Of considerable interest to the Regulatory Body is the filter performance during fire accidental conditions in nuclear installations. This study aims at the investigation of combustion products effect, resulting from a postulated fire accident in a nuclear fuel processing facility, on the performance of HEPA filter as a part of the evaluation of air cleaning system components physical performance. A theoretical study has been performed to investigate how a simulated combustion aerosol affects the pressure drop across a HEPA filter. Several theoretical models have been verified with previous experimental work. The comparisons showed that, the agreement is not quantitative, and these theoretical models are not capable for use to determine the pressure drop caused by particle loading. Therefore , new assumptions as well as new parameters have been implemented, and a new correlation has been derived for the resistance ratio with the filter mass gain for polystyrene aerosols. A best estimate computer model calculations based on this formula have been developed for the prediction of the filter resistance,aerosol particles concentration and accumulated mass on the HEPA filter performance

  18. 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

  19. 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

  20. 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

  1. 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)

  2. 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.)

  3. 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

  4. [Cyclotron based nuclear science

    International Nuclear Information System (INIS)

    This report contains papers on the following topics: Heavy ion reactors, nuclear structure and fundamental interactions; atomic and materials studies; nuclear theory; and superconducting cyclotron and instrumentation

  5. Review of regulatory activities associated with safety culture and management of safety at UK nuclear installations

    International Nuclear Information System (INIS)

    The management of health and safety and the culture of the people who participate in the process have been fundamental to the development of the United Kingdom's nuclear power programme. In the early years of development, the organizations and systems set up in companies which designed, manufactured, constructed and operated nuclear power stations were based upon the best practices needed to ensure, not only the operability of the plant, but also the safety of the workers at the power stations and the public. Over the years the nuclear industry in the UK has changed as has the regulatory body responsible for licensing. The economic environment within which the nuclear electricity generators operate has caused them to review their business and organizational structures. The UK nuclear industry has developed its approach to health and safety management and it is generally recognized that commercially successful companies have excellent health and safety records. This paper discusses the importance of effective health and safety management to the maintenance of high safety standards and the delivery of business goals. It also discusses the model that has been developed to help assess safety management in the changing UK nuclear industry. Finally, it comments upon regulatory developments in management of safety and safety culture. (author)

  6. 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)

  7. 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.

  8. 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

  9. 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.)

  10. The Cabri installation - INB 24. Additional safety assessment with respect to the accident which occurred in the Fukushima-Daiichi nuclear power station

    International Nuclear Information System (INIS)

    After a presentation of some characteristics of the Cabri base nuclear installation located in Cadarache (brief description, buildings, operation), this document reports the identification of cliff-edge effect risks and of critical structures and equipment. Then, it addresses the different risks: earthquake (installation sizing and compliance, margin assessment for the different structures and equipment), external flooding (installation sizing and compliance, margin assessment in relationship with the different flooding origins), other extreme natural events (extreme meteorological conditions related to flooding, earthquake exceeding the design level), and loss of external or internal electric supplies and of cooling systems. The next parts address severe accident management (means and organization for crisis management, robustness of available means), and subcontracting conditions and practices

  11. The Rapsodie installation - INB 25. Additional safety assessment with respect to the accident which occurred in the Fukushima-Daiichi nuclear power station

    International Nuclear Information System (INIS)

    After a presentation of some characteristics of the Rapsodie base nuclear installation located in Cadarache (brief description of buildings, radioactive and chemical material inventory, specific risks, and present status), this document reports the identification of cliff-edge effect risks and of critical structures and equipment. Then, it addresses the different risks: earthquake (reference earthquake, installation sizing and compliance issues, margin assessment for the different structures and equipment), external flooding (installation sizing, compliance, and margin assessment in relationship with the different flooding origins), other extreme natural events (extreme meteorological conditions related to flooding, earthquake exceeding the design level), and loss of external or internal electric supplies and of cooling systems. The next parts address severe accident management (risks related to the industrial environment, means and organization for crisis management, exercises and training, robustness of available means), and subcontracting conditions, modalities and practices

  12. The CHICADE installation - INB 156. Additional safety assessment with respect to the accident which occurred in the Fukushima-Daiichi nuclear power station

    International Nuclear Information System (INIS)

    After a presentation of some characteristics of the Chicade base nuclear installation located in Cadarache (brief description, radioactive and chemical material inventory, specific risks, and present status), this document reports the identification of cliff-edge effect risks and of critical structures and equipment. Then, it addresses the different risks: earthquake (installation sizing and compliance, margin assessment for the different structures and equipment), external flooding (installation sizing, compliance, and margin assessment in relationship with the different flooding origins), other extreme natural events (extreme meteorological conditions related to flooding like tempest, rainfalls and so on, earthquake exceeding the design level), and loss of external or internal electric supplies. The next parts address severe accident management (risks related to the industrial environment, means and organization for crisis management, exercises and training, robustness of available means), and subcontracting conditions and practices

  13. The Pegase installation - INB 22. Additional safety assessment with respect to the accident which occurred in the Fukushima-Daiichi nuclear power station

    International Nuclear Information System (INIS)

    After a presentation of some characteristics of the Pegase base nuclear installation located in Cadarache (description and functions, radioactive and chemical materials, specific risks, present status), this document reports the identification of cliff-edge effect risks and of critical structures and equipment. Then, it addresses the different risks: earthquake (installation sizing and compliance, margin assessment), external flooding (installation sizing and compliance, margin assessment in relationship with the different flooding origins), other extreme natural events (hail, extreme rainfalls, strong winds, lightning, and earthquake exceeding the design level), and loss of external or internal electric supplies. The next parts address severe accident management (means and organization for crisis management, robustness of available means), and subcontracting conditions and practices

  14. 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)

  15. 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...

  16. 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.

  17. 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)

  18. Decree no 2007-1557 from November 2, 2007, relative to basic nuclear facilities and to the nuclear safety control of nuclear materials transport; Decret no 2007-1557 du 2 novembre 2007 relatif aux installations nucleaires de base et au controle, en matiere de surete nucleaire, du transport de substances radioactives

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2007-11-15

    This decree concerns the enforcement of articles 5, 17 and 36 of the law 2006-686 from June 13, 2006, relative to the transparency and safety in the nuclear domain. A consultative commission of basic nuclear facilities is established. The decree presents the general dispositions relative to basic nuclear facilities, the dispositions relative to their creation and operation, to their shutdown and dismantling. It precises the dispositions in the domain of public utility services, administrative procedures and sanctions. It stipulates also the particular dispositions relative to other facilities located in the vicinity of nuclear facilities, relative to the use of pressure systems, and relative to the transport of radioactive materials. (J.S.)

  19. 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.)

  20. 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

  1. 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

  2. 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

  3. 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.)

  4. 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

  5. Case-control study of leukaemia and non-Hodgkin's lymphoma in children in Caithness near the Dounreay nuclear installation

    International Nuclear Information System (INIS)

    A case-control study was performed 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. No raised relative risks were found for prenatal exposure to X-rays, social class of parents, employment at Dounreay before conception or diagnosis, father's dose of ionising radiation before conception, or child's residence within 50 m of the path of microwave transmission beams. Results also proved negative for all lifestyle factors except an apparent association with use of beaches within 25 km of Dounreay. However, this result was based on small numbers, arose in the context of multiple hypothesis testing, and is certainly vulnerable to possible systematic bias. It was concluded that the raised incidence of childhood leukaemia and non-Hodgkin's lymphoma around Dounreay cannot be explained by paternal occupation at Dounreay or by paternal exposure to external ionising radiation before conception. The observation of an apparent association between the use of beaches around Dounreay and the development of childhood leukaemia and non-Hodgkin's lymphoma might be an artefact of multiple testing and influenced by recall bias. (author)

  6. 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)

  7. 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)

  8. 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

  9. Main Conclusions and Recommendations of International Conference on Topical Issues in Nuclear Installation Safety: Ensuring Safety for Sustainable Nuclear Development

    International Nuclear Information System (INIS)

    Over 200 participants from 33 countries and three international organizations came and actively participated and contributed to focused discussions and the success of the conference. The following points summarize the key conclusions and recommendations of the conference with respect to nuclear safety. 1. The nuclear safety approach is based on the philosophy developed in the 60's: defense in depth principles and deterministic criteria. When properly applied and completed by probabilistic analyses and operational experience feedback, it continues to be a successful approach. However, guarding against the risk of accidents requires constant vigilance and high technical competence and a never ending fight against complacency. In this context, having a strong leadership with a commitment to continuous improvement and a vision of sustained excellence is a key element of nuclear safety. Continuous improvement in safety also should be pursued through scientific research and operational experience feedback. 2. An accident anywhere is of concern to all Member States. Therefore, it is in the interest of all Member States to share and collaborate on safety matters. Participation of all Member States in international nuclear safety instruments and conventions, including liability for nuclear damage, is considered beneficial to global safety. The Convention on Nuclear Safety, the Joint Convention, international cooperation through IAEA and other organizations, bilateral or multilateral arrangements are important elements for establishing networks for sharing and transferring knowledge. It is acknowledged that the IAEA's Safety Fundamentals and Safety Requirements provide a sound foundation for high level nuclear safety. IAEA Safety Standards should be the basis for the establishment and maintenance of safety infrastructure. The IAEA's peer reviews and services such as IRRS, OSART, Site Evaluation and Reactor Safety Reviews provide also a valuable platform for sharing

  10. The IAEA Response and Assistance Network (RANET) and the New Nuclear Installation Assessment and Advice Functional Area

    International Nuclear Information System (INIS)

    Full text: The Incident and Emergency Centre (IEC) of the International Atomic Energy Agency (IAEA) is the global focal point for international preparedness and response to nuclear and radiological safety or security related incidents, emergencies, threats or events of media interest. The Convention on Assistance in Case of a Nuclear Accident or Radiological Emergency (Assistance Convention) and the Convention on Early Notification of a Nuclear Accident (Early Notification Convention) are the prime legal instruments that establish an international framework to facilitate the exchange of information and the prompt provision of assistance in the event of a nuclear accident or radiological emergency. They place specific obligations on the Parties and the IAEA, with the aim of minimizing consequences for health, property and the environment. Parties to the Assistance Convention have agreed to cooperate with each other and with the IAEA to facilitate prompt provision of assistance in case of a nuclear or radiological emergency, in order to mitigate its consequences. As part of the IAEA’s strategy for supporting practical implementation of the Assistance Convention and in order to coordinate a global response, the IEC manages the IAEA’s Response and Assistance Network (RANET). RANET aims to facilitate assistance in case of a nuclear or radiological incident or emergency in a timely and effective manner on a regional basis. States Parties shall, within the limits of their capabilities, identify and notify the Agency of experts, equipment and materials which could be made available for the provision of assistance and register these capabilities in RANET. These capabilities are registered in eight difference Functional Areas which are grouped by the type of assistance that could be provided. Experience gained from past emergencies and based on feedback and direction clearly received from Member States under the IAEA Action Plan on Nuclear Safety resulted in the

  11. 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)

  12. Enhancing the safety culture of non-power nuclear installations: Initiatives within the forum for nuclear cooperation in Asia

    International Nuclear Information System (INIS)

    The development and application of safety culture principles has naturally focused on nuclear power plants 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 criticality incidents, unrelated to nuclear power plant operations. Within the Forum on Nuclear Cooperation in Asia (FNCA), Australia has promoted initiatives to apply safety culture principles across all nuclear and radiation application activities and in a manner that is culturally appropriate for Asian countries. The major focus has been on research reactors and to a lesser extent on fuel cycle facilities. The process has been motivated by annual workshops, where participants have reported against agreed indicators and shared their experiences in initiating safety culture programmes in these non-power nuclear activities. This paper provides a summary of some of the outcomes and conclusions on the effectiveness of these initiatives and some experiences from reviews of incidents in the participating countries. (author)

  13. 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)

  14. 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)

  15. 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

  16. 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.

  17. 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)

  18. 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

  19. Personalising Mobile Advertising Based on Users Installed Apps

    OpenAIRE

    Reps, Jenna; Aickelin, Uwe; Garibaldi, Jonathan M.; Damski, Chris

    2015-01-01

    Mobile advertising is a billion pound industry that is rapidly expanding. The success of an advert is measured based on how users interact with it. In this paper we investigate whether the application of unsupervised learning and association rule mining could be used to enable personalised targeting of mobile adverts with the aim of increasing the interaction rate. Over May and June 2014 we recorded advert interactions such as tapping the advert or watching the whole advert video along with t...

  20. Emergency Preparedness technology support to the Health and Safety Executive (HSE), Nuclear Installations Inspectorate (NII) of the United Kingdom

    International Nuclear Information System (INIS)

    The Nuclear Installations Inspectorate (NII) of the United Kingdom (UK) suggested the use of an accident progression logic model method developed by Westinghouse Savannah River Company (WSRC) and Science Applications International Corporation (SAIC) for K Reactor to predict the magnitude and timing of radioactivity releases (the source term) based on an advanced logic model methodology. Predicted releases are output from the personal computer-based model in a level-of-confidence format. Additional technical discussions eventually led to a request from the NII to develop a proposal for assembling a similar technology to predict source terms for the UK's advanced gas-cooled reactor (AGR) type. To respond to this request, WSRC is submitting a proposal to provide contractual assistance as specified in the Scope of Work. The work will produce, document, and transfer technology associated with a Decision-Oriented Source Term Estimator for Emergency Preparedness (DOSE-EP) for the NII to apply to AGRs in the United Kingdom. This document, Appendix A is a part of this proposal

  1. Regulatory oversight report 2010 concerning nuclear safety in Swiss nuclear installations; Aufsichtsbericht 2010 zur nuklearen Sicherheit in den schweizerischen Kernanlagen

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-06-15

    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

  2. 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)

  3. On the use of installed base information for spare parts logistics: a revieuw of ideas and industry practice

    NARCIS (Netherlands)

    R. Dekker (Rommert); C. Pinçe (Çerağ); R.A. Zuidwijk (Rob); M.N. Jalil (Muhammad)

    2010-01-01

    textabstractDemand for spare parts is often difficult to forecast using historical data only. In this paper, we give an overview of installed based information and provide several ways in which installed base forecasting can be used. We discuss cases of installed based forecasting at four companies

  4. Regulatory oversight report 2012 concerning nuclear safety in Swiss nuclear installations; Aufsichtsbericht 2012 zur nuklearen Sicherheit in den schweizerischen Kernanlagen

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2013-04-15

    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

  5. Role of Laws and Regulations For Nuclear Energy Installation in Developing Safety Measures Against Accident

    International Nuclear Information System (INIS)

    The energy industry has been considered as an economic development driver. The fundamental safety policy for nuclear facilities is to protect health and safety of the public and the site personnel against undue risks associated with radiation and radioactive materials resulting from normal operation and abnormal conditions. This policy is implemented, based on the as low as reasonably achievable (ALARA) principle for normal operation and the defense-in-depth principle (prevention of the occurrence of anomalies, prevention of the escalation of anomalies into accidents, and prevention of excessive release of radioactive materials into the environment), through establishment of safety guides and standards. More over the consideration of suitable site selection and safety design, verification by safety evaluation, quality assurance for manufacturing, construction and operation, periodic testing and inspection, confirmation by regulatory bodies, and reflection of experienced troubles to safety countermeasures. Are of these paramount importance concepts are applied variety of nuclear facilities, which is, nuclear reactors, uranium enrichment plants, fuel conversion/fabrication plants, reprocessing plants, radioactive waste management facilities, and so on, considering unique features of each facility.

  6. Design of a mobile neutron radiography installation based on a compact sealed tube neutron generator

    International Nuclear Information System (INIS)

    A series of optimum conditions are taken into account in the construction of neutron radiography (NR) installation based on a sealed tube neutron generator capable of generating 1010 n/s with 14 MeV. The characteristics of NNU screens, a kind of self-made 6LiF·ZnS(Ag) scintillation intensifying screen are presented. Finally, some neutron radiographers taken by this NR installation and NNU screens are given

  7. Design of a mobile neutron radiography installation based on a compact sealed tube neutron generator

    Institute of Scientific and Technical Information of China (English)

    MaWei-Chao; YaoAn-Ju; 等

    1997-01-01

    A series of optimum conditions are taken into account in the construction of neutron radiography(NR) installation based on a sealed tube neutron generator capable of gnerating 1010 n/s with 14MeV.The characteristics of NNU screens,a kind of self-made 6LiF.ZnS(Ag)scintillation intensifying screen are presented.Finally,some neutron radiographies taken by this NR installation and NNU screens are given.

  8. 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

  9. Complementary Safety Margin Assessment f the Nuclear Installations of the research reactor in Petten, Netherlands

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2012-02-15

    On March 11, 2011, a large part of the Japanese eastern coastal area was devastated by an earthquake, followed by an immense tsunami. As a result, thousands of people were killed, injured or made homeless. In the days that followed, the situation was further complicated because of the failing nuclear reactors on the Fukushima coast. The local environment suffered from radioactive releases, requiring evacuation zones, and generating international concerns about nuclear safety. In the wake of this disaster the European Union decided to assess safety on all operating nuclear reactors in its member states. This safety evaluation initiated by the European Union focusses on extreme natural hazards, beyond the standard safety evaluations which regularly have to be performed to demonstrate the safety of a nuclear power plant. Consequences of these extreme hazards for the research reactor in Petten, Netherlands, have been evaluated based on available safety analyses, supplemented by engineering judgement. In this way, the robustness of the existing plant has been assessed and possible measures to further increase the safety margins have been identified. This document presents the results of the Complementary Safety margin Assessment (CSA) performed for the 'Onderzoekslocatie Petten'. The distinct difference between this report and former risk analysis reports in general and the existing Safety Report of the Petten reactor is that the maximum resistance of the plant against redefined and more challenging events has been investigated, whereas traditionally the plant design is investigated against certain events that are determined on a historical basis. This different approach requires different analyses and studies, which in turn presents new insights into the robustness of the plant. The main purpose of this report is to answer the questions posed by the Ministry of Economic Affairs, Agriculture and Innovation. It was decided to write at the same time a report in

  10. Chinese Nuclear Science Basic Data Base (CNSBDB)

    Institute of Scientific and Technical Information of China (English)

    2002-01-01

    A new research project on "Development of the Chinese Nuclear Science Basic Database (CNSBDB)for Fundamental Researches of Nuclear Physics and Interrelated Subjects, and Requirements of NuclearPower and Nuclear Technologies Application" has been commenced. The CNSBDB contains thefollowing eight segments: 1) Information on Nuclear Science (INFO); 2) Nuclear Structure Data Base(NSDB); 3) Nuclear Decay Data Base (NDDB); 4) Nuclear Reaction Data Base (NRDB); 5) Nuclear

  11. Regulatory oversight report 2011 concerning nuclear safety in Swiss nuclear installations; Aufsichtsbericht 2011 zur nuklearen Sicherheit in den schweizerischen Kernanlagen

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2012-06-15

    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

  12. 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

  13. 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

  14. ACSNI [Advisory Committee on the Safety of Nuclear Installations] study group on human factors. Third report: organising for safety

    International Nuclear Information System (INIS)

    Inquiries into a number of recent major accidents within and without the nuclear industry have found that faults in organisational structures and procedures have been contributory factors at least as important as physical failures or even individual human error. A study group set up by the united Kingdom Advisory Committee on the Safety of Nuclear Installations (ACSNI) has examined a wide variety of evidence on this matter. They conclude that: different organisations doing similar work are known to have different safety records, and specific factors in the organisation are related to safety; particular methods for changing organisations have been found to be useful in improving these factors; as part of the total system, the actions of regulators may affect the organisation. Recommendations are made to the nuclear industry which include: that the same emphasis should be given to organisational factors as to equipment failure and individual human error; that the value of learning from the experience of the non-nuclear industry should be recognised; that the Nuclear Installations Inspectorate (NII) should recognise the organisational health of the licensee and act accordingly; that the NII should take note of its own role in the total system and its likely effects on the licensees; that research to fill the remaining identified gaps in knowledge on this subject should be considered. (UK)

  15. Extrabudgetary programme on the safety of nuclear installations in South East Asia Pacific and Far East countries. Report of the consultative meeting

    International Nuclear Information System (INIS)

    Based on the good experience with the rapid expansion of nuclear utilization in Japan and South Korea, China is planning to significantly expand its nuclear programme, and other countries in the region are likely to follow this example in order to meet their expected high electricity demand growth. The building of NPPs is being considered in Indonesia, Malaysia, the Philippines, Thailand, and Vietnam. It is however recognized that countries in the region are in different stages of nuclear power programme, and that their needs for assistance in nuclear safety will be substantially different. In this situation it would be advantageous for all countries to establish regional co-operation on nuclear safety to learn from each other, use the experience accumulated in the world, and to commonly assess the progress made in nuclear safety matters. The objective of this Consultative Meeting was to discuss co-operation and the needs for assistance by Member States in South-East Asia, Pacific and Far East to strengthen the safety of their nuclear installations. Refs, figs, tabs

  16. Korsar: a new generation computer code for numerically modeling dynamic behavior of nuclear power installations

    International Nuclear Information System (INIS)

    In the years 1990, the knowledge gained in the area of interest and advances in computer technology provided the basis for developing the new generation computer codes within Russia. The development of computer codes intended for system modeling of NPP reactor dynamics was motivated by the need in reconstruction and life extension of ageing NPPs; construction of Russian-design NPPs abroad; development of the new generation NPPs with passive safety features. Solution to these problems involves, a depth numerical analysis of transients, design-basis and beyond design-basis accidents at NPPs as an integral part of nuclear safety research required by both domestic and international standards. NITI researchers started developing the KORSAR code in 1996. It was planned to develop three base versions of the code. Code developers faced three problems presented and discussed in this paper. (author)

  17. Recycle and reuse of components arising from decommissioning nuclear installations: an overview

    International Nuclear Information System (INIS)

    Recycling offers savings in both acquiring new materials and disposing of old. But this must be set against the associated economic, social and administrative costs. There is considerable experience of the problems involved and research is in hand to expand the authors understanding of these. Materials may be recycled within the nuclear industry only if there is a ready use for it. Release for unrestricted use depends on the existence of suitable criteria and a means to assure compliance with them. The interaction between these two factors could be a deciding factor. Work is in hand to prepare workable release criteria based on a dose to the public of not more than 10 microsieverts, and a figure of 1 Bq/gm is proposed. Quality assurance will be important in any recycling program. Public acceptance is crucial and unrestricted release must not operate so as to jeopardize this

  18. The physical protection systems at the Czech nuclear installations and the Y2K issue

    International Nuclear Information System (INIS)

    The paper describes the joint effort of the State Office for Nuclear Safety, EZ, a.s., Nuclear Power Plant Dukovany and EBIS Ltd., as a subcontractor, to solve the problem of the Y2K particularly in connection with real time operation of the integrated physical protection system at Nuclear Power Plant Dukovany. (author)

  19. Characterization of a Planetary Boundary Layer model to evaluate radionuclides releases in nuclear installations

    International Nuclear Information System (INIS)

    A two layer bulk model is used to simulate numerically the time and spatial evolution of concentration of radionuclides in the Planetary Boundary Layer (PBL) for convective and stable conditions. In this model, the closure hypothesis are based on the integrated version of the Turbulent Kinetics Energy (TKE) equation (Smeda,1979). This type of model was adopted here because it is numerically simple to be applied operationally in routine and emergency support systems of atmospheric releases at nuclear power plants, and the hypothesis of the efficiency of the vertical mixing seems to be physically reasonable to simulated PBL evolution for high wind conditions and stable conditions in Subtropical latitudes regions. In order to validate the model to the nuclear power plants of the Centro Experimental Aramar (CEA), located in Ipero, State of Sao Paulo, Brazil, numerical simulations were carried out with initial and boundary conditions based on vertical profiles of temperature and horizontal wind speed and direction obtained from tethered balloon soundings, synoptic charts at 850 hPa and surface observations. Comparisons between a 24 hour long numerical simulation and observations indicate that the model is capable of reproduce the diurnal evolution of temperature and horizontal wind during the convective regime. During stable conditions, the slab model was able to simulate the intensity of the surface inversion as a difference between the mixed layer and surface temperatures. The simulated mixed layer height matches with observations during the convective and stable regime. A daytime release of radionuclides was simulated for CEA region and the results indicated that the maximum relative concentration reaches a distance about 15 Km in 1 hour, varing from 100 times background at the moment of the release to 15 times the background. For night releases, the maximum concentration reaches the same distance in 45 minutes, varing from 100 to 30 times the background values

  20. Guidelines for Nordic Co-operation concerning nuclear installations in the border areas between Denmark, Finland, Norway and Sweden in respect of nuclear safety conditions

    International Nuclear Information System (INIS)

    These Guidelines came into force between the four Contracting Parties (Denmark, Finland, Norway and Sweden) to the Agreement on 15th November 1976. The Agreement is the outcome of work undertaken these past years in the Nordic Reactor Safety Working Group and the Nordic Atomic Energy Liaison Group. The purpose of the Guidelines is to establish a consultation mechanism between the authorities of Nordic countries likely to be affected by a nuclear installation siting project by another party to the Agreement near their borders. Information imparted during such consultation is intended mainly to improve assessment of the projected site for the installation and its environment. Discussions may also cover the actual safety of the installation itself. (NEA)

  1. Electromagnetic compatibility of new installations of digital/analog and electrical/electronic equipment in nuclear power plants

    International Nuclear Information System (INIS)

    This paper recommends electromagnetic compatibility (EMC) requirements of new digital/analog and electrical/electronic equipment installations in nuclear power plant areas including control rooms, remote shutdown panels, cable spreading rooms, equipment/relay rooms and the turbine deck. A nuclear plant electromagnetic environment (EME) consists of electromagnetic noises from portable two-way radios, arc welders, etc; and high-energy fast transients from generator and transmission / distribution voltages. Trends in current plant modifications suggest that Instrumentation and Control (I and C) systems with analog equipment are being replaced with more efficient computerized/microprocessor-based digital systems. As digital systems are evolving with higher clock frequencies and lower logic level voltages, digital equipment are more vulnerable to electromagnetic/radio frequency interference (EMI/RFI) random noise causing errors in their logic functions. US NRC Regulatory Guide (RG) 1.180, providing guidelines for evaluating EMI/RFI in safety-related I and C systems, endorsed EPRI guidelines TR-102323-RI for EMI emission/susceptibility testing and limiting practices as an acceptable qualification method of digital equipment EMC. Numerous US nuclear utilities have used these EPRI requirements in their equipment specifications. The basis for this paper is derived from these guidelines, military/industry standards, federal regulations and various international publications on EMC. Plant emission levels are selected 8dB below digital equipment susceptibility testing levels and the equipment emissions are conservatively limited to 22dB or more below these levels depending on frequency. Digital equipment is also required to satisfy the EMI limiting practices of EPRI TR-102323-R1 and IEEE 1050-1996. On the other hand, electrical/electronic equipment that operates at higher voltages at power frequency is not as vulnerable to the plant EMI as digital equipment, but could

  2. Development of a computer system for support and documentation of clearance of buildings of nuclear installations - 59278

    International Nuclear Information System (INIS)

    Clearance of buildings of nuclear installations in Germany has to comply with general requirements laid down in Section 29 of the German Radiation Protection Ordinance (RPO; Strahlenschutzverordnung), clearance levels as stipulated in Table 1 of Annex III RPO and technical guidance given in the technical standard DIN 25457. Clearance procedures are usually proposed by the licensee and are made part of a decommissioning licence after appropriate review by the authorities. The clearance procedures consist of a radiological characterisation of the various parts of the buildings, a decontamination step if necessary, followed by measurements for checking the success of decontamination, and the actual decision measurements for demonstrating compliance with clearance levels. These three steps rely on various measurement methods, selected depending on the relevant radionuclides to be measured, like sampling with subsequent gamma spectrometry (and if necessary separate evaluation of beta and alpha emitting nuclides), measurements with surface contamination monitory and in situ gamma spectrometry. For a nuclear power plant, the number of samples taken during this procedure can easily reach a few 10, 000, while the number of single measurements can reach several 100, 000 single surface measurements and several 10, 000 measurements with in situ gamma spectrometry. This large number of data together with the correct interpretation according to the valid nuclide vector, the penetration depth of the contamination, the correction for radioactive decay etc have to be managed, which is a error-prone process if carried out manually or with insufficient support by customised software. For this reason, a versatile software tool has been developed by Brenk Systemplanung GmbH that supports the operator in all aspects of clearance of buildings, based on the extensive experience with various clearance procedures in nuclear power plants that Brenk Systemplanung has carried out in the past

  3. Analysis and discussion on reports of additional safety assessment of nuclear installations with respect to the Fukushima accident

    International Nuclear Information System (INIS)

    This document proposes an analysis of the reports made by the different operators of nuclear installations within the frame of a safety audit of the French nuclear installations with respect to the Fukushima accident. Operators (mainly AREVA, the CEA and EDF) were asked to perform additional safety assessments. In a first part, the conclusions of EDF reports are analysed regarding the seismic risk, the flooding risk, the situation of some specific sites (Fessenheim, Tricastin), other phenomena (rains, winds), loss of electricity supplies and of cooling systems, severe accidents, hydrogen issue, chemical hazards, subcontractors, crisis management. Conclusions of AREVA reports are analysed for the different sites (Tricastin, La Hague, MELOX factory, Romans factory). Conclusions of CEA reports are analysed for the different concerned installations (ATPu, Masurca, Osiris, Phenix, Jules Horowitz reactor). A second part proposes a global analysis of EDF's additional safety assessment reports regarding earthquake, flooding, other extreme natural phenomena, loss of electricity supplies and cooling system, subcontracting conditions, crisis management, and radiation protection organisation. AREVA's and CEA's reports are then analysed in terms of report structure and content, and for the different concerned sites

  4. The nuclear installations dismantling and the management of radioactive wastes; Le demantelement des installations nucleaires et la gestion des dechets radioactifs

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-01-15

    As other industrial activities, the nuclear industry causes risks. The risks bound to the dismantling operations are known and controlled. After a presentation of the dismantling and radioactive wastes challenge, this document proposes recommendations based on the first experiences of dismantling and wastes storage. It aims then to answer to the questions relative to the cost and the financing of the operations. Finally it wonders on the public information modalities. (A.L.B.)

  5. [Cyclotron based nuclear science

    International Nuclear Information System (INIS)

    The period 1 April 1992--31 March 1993 saw the initial runs of three new spectrometers, which constitute a major portion of the new detection capabilities developed for this facility. These devices are the Proton Spectrometer (PSP) (data from which are shown on the cover of this document), the Mass Achroniat Recoil Mass Spectrometer (MARS), and the Multipole Dipole Multipole (MDM) Particle Spectrometer. The ECR-K500 cyclotron combination operated 5,849 hours. The beam was on target 39% of this time. Studies of nuclear dynamics and nuclear thermodynamics using the neutron ball have come to fruition. A critical re-evaluation of the available data on the giant monopole resonance indicated that the incompressibility is not specified to a range smaller than 200--350 MeV by those data. New systematic experiments using the MDM spectrometer are now underway. The MEGA collaboration obtained the first data on the μ → eγ decay rate and determination of the Michel parameter in normal μ decay. Experiments appear to confirm the existence of monoenergetic pair peaks even for relatively low Zprojectile -- Ztarget combinations. Studies of the (α,2α) knockout reaction indicate that this reaction may prove to be a valuable tool for determination of reaction rates of astrophysical interest. Theoretical work reported in this document ranges from nuclear structure calculations using the IBM-2 model to calculations of kaon production and the in-medium properties of the rho and phi mesons. Nuclear dynamics and exotic shapes and fragmentation modes of hot nuclei are also addressed. New measurements of x-ray emission from highly ionized ions, of molecular dissociation and of surface interactions are reported. The research is presented in nearly 50 brief summaries usually including data and references

  6. Risk zoning around nuclear power plants in comparison to other major hazardous industrial installations

    International Nuclear Information System (INIS)

    The background and current status of the information basis leading to the definition of risk and emergency zones around Nuclear Power Plants (NPPs) in different countries in Europe and beyond are analysed. Although dependable plant-specific Probabilistic Safety Assessment (PSA) of Level 2 and/or Level 3 could in principle provide sufficiently detailed input to define the geographical dimension of a NPP's risk and emergency zones, the analysis of the status in some European and other countries shows that other, 'deterministic' approaches using a Reference Accident are actually used in practice. Regarding use of Level 2 PSA for emergency planning, the approach so far has been to use the Level 2 PSA information retrospectively to provide the justification for the choice of Reference Accident(s) used to define the emergency plans and Emergency Planning Zones (EPZs). There are significant differences in the EPZs that are defined in different countries, ranging from about 1 km to 30 km. Further, there is a striking contrast in the extent of using probabilistic information to define emergency zones between the nuclear and other high risk industry sectors, such as the chemical process industry, and the reasons for these differences are not entirely clear, but seem to be more related to risk perception than actual risk potential. Finally, based on consensus discussions at a recent JRC/OECD International Seminar on Risk and Emergency Zoning around NPPs, recommendations are given in the areas of more comprehensive use of available risk information for risk zoning purposes, risk communication and comparative risk assessment. (author)

  7. Engineering development of a digital replacement protection system at an operating US PWR nuclear power plant: Installation and operational experiences

    Energy Technology Data Exchange (ETDEWEB)

    Miller, M.H. [Duke Power Co., Seneca, SC (United States)

    1995-04-01

    The existing Reactor Protection Systems (RPSs) at most US PWRs are systems which reflect 25 to 30 year-old designs, components and manufacturing techniques. Technological improvements, especially in relation to modern digital systems, offer improvements in functionality, performance, and reliability, as well as reductions in maintenance and operational burden. The Nuclear power industry and the US nuclear regulators are poised to move forward with the issues that have slowed the transition to modern digital replacements for nuclear power plant safety systems. The electric utility industry is now more than ever being driven by cost versus benefit decisions. Properly designed, engineered, and installed digital systems can provide adequate cost-benefit and allow continued nuclear generated electricity. This paper describes various issues and areas related to an ongoing RPS replacement demonstration project which are pertinant for a typical US nuclear plant to consider cost-effective replacement of an aging analog RPS with a modern digital RPS. The following subject areas relative to the Oconee Nuclear Station ISAT{trademark} Demonstrator project are discussed: Operator Interface Development; Equipment Qualification; Validation and Verification of Software; Factory Testing; Field Changes and Verification Testing; Utility Operational, Engineering and Maintenance; Experiences with Demonstration System; and Ability to operate in parallel with the existing Analog RPS.

  8. Authorization Decree Application for the creation of the Flamanville-3 Basic Nuclear Installation. Executive Summary of the Technical Review

    International Nuclear Information System (INIS)

    On 9 May 2006, Electricite de France (EDF) submitted to the Ministers for Nuclear Safety an authorization decree application for an EPR-type reactor on the site of the Flamanville Nuclear Power Plant (NPP). Article 29 of Act No. 2006-686 of 13 June 2006 on Transparency and Security in the Nuclear Field prescribes that the creation of any basic nuclear installation shall be issued by a decree taken after consultation with the Nuclear Safety Authority (Autorite de surete nucleaire - ASN). The purpose of this report is to provide ASN's Board with a summary of the technical review led by ASN services and carried out by their technical support agencies, namely the IRSN, the GPR and the Standing Nuclear Section of the CCAP between 2001 and 2006. After summing up the conclusions of the review on the safety options of the European Pressurized Reactor (EPR) Project, as carried out between 1993 and 2000, this report describes the process and modalities of the review conducted from 2001 to 2006. Besides providing the opinion of ASN's services on the creation-licence application, it also outlines the further review to be carried out, if the authorization decree is issued. (authors)

  9. Installation of a new type of nuclear reactor in Mexico: advantages and disadvantages; Instalacion de un nuevo tipo de reactor nuclear en Mexico: ventajas y desventajas

    Energy Technology Data Exchange (ETDEWEB)

    Jurado P, M.; Martin del Campo M, C. [FI-UNAM, 04510 Mexico D.F. (Mexico)]. e-mail: mjp_green@hotmail.com

    2005-07-01

    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)

  10. Methods and devices for characterization of neutron field in controlled nuclear fusion installations. Resume of Ph.D thesis

    International Nuclear Information System (INIS)

    The abstract presents the essential features of the Ph.D. thesis which is dealing with the development of advanced methods and devices for characterization of neutron emission in controlled nuclear fusion systems. This work presents the author's contribution to neutron diagnosis in fusion systems and especially in investigation and understanding of fusion mechanisms in dense Z-pinch installations in their most preferment variant plasma focus, aiming to optimization of neutron production and applications. The work is structured in 6 chapters and 4 appendices. The first chapter presents the numerical and analytical models for the main characteristics of neutron emission in fusion systems. To extract quantitative information on the distribution function of reacting deuterons from neutron measurements analytical expressions for flux anisotropy and energy spectrum of the fusion neutrons emitted in Z-pinch installations were derived. The second chapter introduces the main calibration method of total neutron yield in pulsed fusion system. The conclusions of this study were used for selecting the optimal method of experimental determination of neutron yield in plasma focus installations operating in the laboratory of plasma physics and nuclear fusion of the Institute for Physics and Technology of Radiation Devices, Bucharest and in the Focalized Plasma Group in the Institute of Experimental Physics of the Heinrich-Heine University, Dusseldorf. The third chapter describes the theoretical principles in the spectroscopy of fusion neutrons. The fourth chapter is entirely dedicated to the characterization of neutron emission in the focalized plasma installation SPEED-2 of the University of Dusseldorf. In the fifth chapter there are introduced and applied original methods for determination of energy and angular characteristics of the distribution function of reactant deuterons in focalized plasma. In the sixth chapter it is developed an original concept of collimation and

  11. [Cyclotron based nuclear science

    International Nuclear Information System (INIS)

    This report contains descriptions of research programs carried out by Institute staff, in nuclear physics as well as progress on new instrumentation during the period April 1, 1989, to July 31, 1990. During this year the ECR source was completed and beams were injected into the cyclotron. In November, 1989 experiments began with beams from the ECR + K500 cyclotron. To date, the highest velocity beam accelerated has been 43 MeV/nucleon 14N, and the highest energy beam has been 1.57 GeV 63Cu. Heavy ion reaction experiments and cyclotron operation and instrumentation are briefly described in this paper

  12. Maintaining the design integrity of nuclear installations throughout their operating life. INSAG-19. A report by the International Nuclear Safety Advisory Group

    International Nuclear Information System (INIS)

    A nuclear power plant design is the product of the activities of many organizations, and changes to that design will occur continuously over the plant's lifetime. Reactor plants are designed to operate for a long period of time, typically 40 years, which may be extended for several decades. This period of time spans several working lifetimes of the staff of the plant, and its length represents a very specific challenge to safety and to the corporate asset management of the enterprise. It also implies that the vendor structure required to support the plant can be expected to change substantially during the plant's lifetime. this INSAG report discusses the problem of maintaining the integrity of design of a nuclear power plant over its entire lifetime in order to achieve a continuous high level of safety. A nuclear power plant design is the product of the activities of many organizations, and changes to that design will occur continuously over the plant's operating lifetime. Reactor plants are designed to operate for a long period of time, typically 40 years, which may be extended for several decades. This period of time spans several working lifetimes of the staff of the plant, and its length represents a very specific challenge to safety and to the corporate asset management of the enterprise. It also implies that the vendor structure required to support the plant can be expected to change substantially during the plant's lifetime. The purpose of this report is to identify the issues and some of the principles that should be addressed, discuss some of the solutions to the problem, and highlight the specific responsibilities of designers, operators and regulators. The issues and principles discussed here are also applicable to other nuclear installations (for example, research reactors and fuel cycle facilities). This INSAG report is directed at senior executives who are responsible for: the overall safety of nuclear installations; the operation, maintenance and

  13. Law nr 2015-588 of June 2, 2015 related to the strengthening of the protection of civil nuclear installations housing nuclear materials

    International Nuclear Information System (INIS)

    This publication contains the official text of a law adopted by the French Parliament for the strengthening of civil nuclear installations housing nuclear materials. The first article of this law is made of modifications introduced in the Defence Code. The second article states that a report is to be submitted by the Government to the Parliament on the risk and threat assessment of illegal UAVs flyovers, and on technical solutions to improve the detection and neutralisation of these aircraft, as well as on necessary legal adaptations to punish such infringements

  14. Maintaining the design Integrity of nuclear installations throughout their operating life. INSAG-19. A report by the International Nuclear Safety Advisory Group (Russian Edition)

    International Nuclear Information System (INIS)

    A nuclear power plant design is the product of the activities of many organizations, and changes to that design will occur continuously over the plant's lifetime. Reactor plants are designed to operate for a long period of time, typically 40 years, which may be extended for several decades. This period of time spans several working lifetimes of the staff of the plant, and its length represents a very specific challenge to safety and to the corporate asset management of the enterprise. It also implies that the vendor structure required to support the plant can be expected to change substantially during the plant's lifetime. this INSAG report discusses the problem of maintaining the integrity of design of a nuclear power plant over its entire lifetime in order to achieve a continuous high level of safety. A nuclear power plant design is the product of the activities of many organizations, and changes to that design will occur continuously over the plant's operating lifetime. Reactor plants are designed to operate for a long period of time, typically 40 years, which may be extended for several decades. This period of time spans several working lifetimes of the staff of the plant, and its length represents a very specific challenge to safety and to the corporate asset management of the enterprise. It also implies that the vendor structure required to support the plant can be expected to change substantially during the plant's lifetime. The purpose of this report is to identify the issues and some of the principles that should be addressed, discuss some of the solutions to the problem, and highlight the specific responsibilities of designers, operators and regulators. The issues and principles discussed here are also applicable to other nuclear installations (for example, research reactors and fuel cycle facilities). This INSAG report is directed at senior executives who are responsible for: the overall safety of nuclear installations; the operation

  15. The Legal Position of the Operator and the Constructor of a Nuclear Installation

    International Nuclear Information System (INIS)

    This Note analyses the procedures required in Italy for nuclear power plant construction and operation under Act No. 1860 of 31 December 1962 on the peaceful uses of nuclear energy and Presidential Decree No. 185 of 13 February 1964 on radiation protection, made under that Act; this latter Decree lays down the licensing system for nuclear power plants. The Note describes the standards for plant construction; the third party liability regime for nuclear damage; the step-by-step licensing procedure, siting; the supply of fuel elements and fuel loading; the protection of workers involved with ionizing radiation and finally the penal provisions in case of violation of the Act and Decree. (NEA)

  16. CNN's evaluation of the radiological monitoring special programs at the sites of nuclear installations

    International Nuclear Information System (INIS)

    In 2008, occurred in the Spanish plants various events related to the existence on the sites of the Spanish nuclear facilities or areas dotted with radioactive contamination outside the buildings, events that were reported to the Nuclear Safety Council (CSN) in accordance with the provisions of the regulation, as a result of the analysis of those events, the CSN issued in July 2008, a complementary technique INSTRUCTIONAL requiring the implementation of environmental monitoring programs in outdoor areas within sites nuclear tacilities. First, the CSN nuclear facilities referred to the programs and methodologies intended to perform such monitoring, and, in late 2009, reports of program results.

  17. Three-dimensional seismic isolation floor system using air spring and its installation into a nuclear facility

    International Nuclear Information System (INIS)

    As high-precision equipments such as computer systems have been highly advanced in the nuclear field, it is important to protect them from earthquakes. The use of seismic isolation system may provide a practical solution for the object. Research on the use of laminated rubber bearings as seismic isolators has been primarily focused on the development of base-isolated buildings. The laminated rubber bearing shows excellent seismic isolation performance to horizontal directions. However, it cannot reduce the response due to vertical seismic motion. Strength of buildings is usually sufficient to vertical earthquake motion, but high-precision equipments inside of buildings are easily resonant to vertical motion as well as horizontal one. Hence, the use of three-dimensional isolators is necessary to protect them from earthquakes. Development of three-dimensional isolators for base-isolated buildings may not be practical because of its high cost and of the difficulty in suppressing a rocking motion. One of the practical methods for protecting these equipments may be use of a three-dimensional seismic floor isolation system, on which they are set up. A three-dimensional seismic isolation floor system has been developed, where the isolator is constructed by the combination of an air spring and a laminated rubber bearing. In general, isolated structure should be sufficiently stiff relative to an isolator. In three-dimensional seismic isolation floor systems, however, vertical stiffness of floor structure is limited as compared with an isolator, and load distribution on the isolated floor is non-uniform. Therefore, bending deformations of floor structure is easily caused by vertical seismic motion. The use of air springs as vertical isolators enables to attain uniform vertical motion without bending deformations, because its vertical stiffness is proportional to air pressure i.e. its supporting load. The present three-dimensional seismic isolation floor system has been

  18. An analysis of inhabitants opinion on energy issues. Comparison between localities of nuclear installation sites and of urban communities

    International Nuclear Information System (INIS)

    For the purpose of comparing the mental attitudes toward nuclear power generation held by the public between localities containing nuclear installation sites and those of urban communities, a survey has been conducted by mail and by direct interviews. The survey conversed Fukushima, Niigata and Fukui Prefectures, representing the former group of localities, whereas Tokyo and Osaka, representing the latter. The mail survey revealed differences between the two groups of localities in their image of power and in their perception of its present status, as well as in their sense of values in daily life. The interview survey indicated that the factors behind the differences included regional characteristics such as temperaments of resident population, and effects on the private life style brought by nuclear installation. Narrowing down this gap of mental attitude between the two groups of localities should call indispensably for better mutual understanding. In bringing this about, consideration should be given to particular local characteristics, including popular mentality and personal view of life, as well as image and knowledge of energy sources held by the individuals. (author)

  19. 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

  20. 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

  1. Installed Base Registration of Decentralised Solar Panels with Applications in Crisis Management

    Science.gov (United States)

    Aarsen, R.; Janssen, M.; Ramkisoen, M.; Biljecki, F.; Quak, W.; Verbree, E.

    2015-08-01

    In case of a calamity in the Netherlands - e.g. a dike breach - parts of the nationwide electric network can fall out. In these occasions it would be useful if decentralised energy sources of the Smart Grid would contribute to balance out the fluctuations of the energy network. Decentralised energy sources include: solar energy, wind energy, combined heat and power, and biogas. In this manner, parts of the built environment - e.g. hospitals - that are in need of a continuous power flow, could be secured of this power. When a calamity happens, information about the Smart Grid is necessary to control the crisis and to ensure a shared view on the energy networks for both the crisis managers and network operators. The current situation of publishing, storing and sharing data of solar energy has been shown a lack of reliability about the current number, physical location, and capacity of installed decentralised photovoltaic (PV) panels in the Netherlands. This study focuses on decentralised solar energy in the form of electricity via PV panels in the Netherlands and addresses this challenge by proposing a new, reliable and up-to-date database. The study reveals the requirements for a registration of the installed base of PV panels in the Netherlands. This new database should serve as a replenishment for the current national voluntary registration, called Production Installation Register of Energy Data Services Netherland (EDSN-PIR), of installed decentralised PV panel installations in the Smart Grid, and provide important information in case of a calamity.

  2. Plutonium: resuspension of aerosols in nuclear installations: bibliographic survey; Le plutonium: mise en suspension d'aerosols dans les installations nucleaires: synthese bibliographique

    Energy Technology Data Exchange (ETDEWEB)

    Guetat, Ph.; Monfort, M.; Armand, P. [CEA Bruyeres-le-Chatel, Dept. Analyse Surveillance Environnement, Service Radioanalyse Chimie Environnement, 91 (France); Alloul-Marmor, L. [Societe APTUS, 78 - Versailles (France)

    2006-07-01

    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)

  3. [Cyclotron based nuclear science

    International Nuclear Information System (INIS)

    This report contains descriptions of research programs carried out by Institute staff, as well as progress on new instrumentation during the period, April 1, 1990, to March 31, 1991. The K500 cyclotron and ECR source provided beam for 4140 hours during the period. The beam was actually available for experiments 1927.50 hours and 1110.50 hours was devoted to developing new beams and exploring cyclotron performance. A wide range of beams from protons to Xe with energies from 2.4 MeV/u to 60 MeV/U have been used in experiments. The highest total energy beam accelerated was 35 MeV/u 63Cu. The ECR source, made a tremendous improvement in accelerator performance and reliability. Substantial amounts of beam time were devoted to investigations of hot nuclei, electron-positron, giant resonances, atomic effects of high velocity ion beams, astrophysics related reactions and proton and alpha bremsstrahlung. Scientific accomplishments included determination of the heat capacity of nuclei through new insight into the level densities and establishing a lower limit for electron positron resonances a factor of ten better than previous measurements. The proton spectrometer, constructed for studies of the Gamow-Teller interaction is complete, and initial physics measurements will be made in the next few months. All of the BaF2 crystals have been delivered and acceptance tests are underway. A K=315 MDM spectrometer has been obtained from Oxford University and is scheduled for installation in Spring 1992, after removal of the K=150 Enge split pole spectrometer. Institute groups continue participation in MEGA, instrumentation projects for RHIC, and few nucleon studies at LAMPF and KEK. Reports of these activities are included

  4. Legal and administrative problems in regulating public participation in licensing of nuclear installations

    International Nuclear Information System (INIS)

    This general analysis of the question of public acceptance of nuclear activities focuses on the problems met by all governmental authorities in implementing their nuclear programmes. The author highlights the need for more specific regulations aimed at guaranteeing fuller information of the public and ensuring closer participation by it. (NEA)

  5. Design approaches to mitigate electrical installation problems in nuclear power generating stations

    International Nuclear Information System (INIS)

    Large power generating stations have experienced a constant rise in the in-plant costs of electrical installation. Many techniques can be employed such as computerized cable and conduit schedules, open type raceway supports, bulk cable pulling, setting up of planning teams for cable, termination, etc. The improvements recommended in this study can result in significant cost savings as shown in Table 2 as a result of minimized rework during construction, increased productivity of field personnel, and construction schedule improvements. The method include additional design details to the constructor, improved design of cable tray supports, increased use of computer aided design for electrical raceways and cable pulling and cable termination, without using cable lugs. The implementation of these methods on the Large Scale Prototype Breeder Plant has resulted in an estimated installation cost saving of over $11 million

  6. New tolerance standard for installation of piping supports in nuclear power plants

    International Nuclear Information System (INIS)

    When the support positions are shifted from the designed position up on installation, the designer must decide whether the new support position is acceptable. Evaluation of these support shift effects led to the following new support installation tolerance standard proposed: (1) The support shift value is evaluated in terms of the design margin and the response fluctuation ratio for the support shift. (2) The response fluctuation ratios are determined in the case of the single-support position shift and the single-support angle shift. (3) The response fluctuation values for multiple support shifts are given by the square root of the sum of the square of the response fluctuation value for the single-support shift

  7. Childhood leukaemia near British nuclear installations: Methodological issues and recent results

    International Nuclear Information System (INIS)

    In 2008, the German Childhood Cancer Registry published the results of the Kinderkrebs in der Umgebung von Kernkraftwerken (KiKK) study of childhood cancer and leukaemia around German nuclear power stations. The positive findings appeared to conflict with the results of a recent British analysis carried out by the Committee on Medical Aspects of Radiation in the Environment (COMARE), published in 2005. The present paper first describes the COMARE study, which was based on data from the National Registry of Children's Tumours (NRCT); in particular, the methodology used in this study is described. Although the results of the COMARE study were negative for childhood leukaemia, this apparent discrepancy could be accounted for by a number of differences in approach, especially those relating to the distances from the power stations and the ages of the children studied. The present study was designed to match the KiKK study as far as possible. The incidence observed (18 cases within 5 km against 14.58 expected, p = 0.21) was not significantly raised. The risk estimate for proximity in the regression fitted was actually negative, though the confidence intervals involved are so wide that the difference from that reported in the KiKK study is only marginally statistically significant (p = 0.063). (authors)

  8. Fire protection requirements for the layout and structural components of the main buildings and installations of Soviet nuclear power plants

    International Nuclear Information System (INIS)

    The paper outlines those provisions of current Soviet regulatory documentation governing the design, construction and operation of nuclear power plants which concern fire resistance and non-transmission of fire in the main structures of the buildings and installations, and the premises constituting the greatest radiation and fire hazards. A description is given of the sectionalization of premises which constitute a fire hazard and the establishment of fire protection zones and sections. Also presented are the measures taken to improve the fire safety of the cable system at power plants in the USSR. (author)

  9. About the interest of an agreement for a european passport for workers in european regulated nuclear installations

    International Nuclear Information System (INIS)

    The European directive 96/29 applicable to EU member states is, or will be transposed in each country according to national conditions which could prove to be more restrictive than the demands of the directive. Additionally, specific organisations in each country, reinforce the disparities where radioprotection, and medical and dosimetric follow-up are concerned. In April 2001, on the initiative of a group of French company medical officers (EDF CEA COGEMA), a meeting with company medical officers from various member states of the EEC: Great Britain, Italy, Spain, Belgium, Germany, was organised in order to bring to attention the issue of the movement of contract workers in European regulated nuclear installations

  10. PANTHERE, simulation software of dose flow rates for complex nuclear installations

    International Nuclear Information System (INIS)

    The authors present the PANTHERE simulation software developed by EDF-SEPTEN to determine gamma dose flow rate in any point of complex industrial installations. They present the current industrial version (PANTHEREV1) and its different applications, and more particularly an investigation in the field of qualification of hardware under irradiation in case of severe accident. They present the currently under development version (PANTHEREV2) which will be exploited in 2011

  11. Decision of the Federal Administrative Court of January 19, 1989 - 7 C 31.87, concerning physical protection of nuclear installations

    International Nuclear Information System (INIS)

    Section 7, sub-sec. 2, no. 5 of the Atomic Energy Act forms the legal basis of a duty defined by the licensing authority in addition to the operating licence, to provide for physical protection of a nuclear power station by an armed works protection force. Decisions of a competent authority on the scope of required physical protection of a nuclear installation against interference or other intervention by third persons within the purview of sec. 7, sub-sec. 2, no. 5 Atomic Energy Act, as well as instructions within the purview of sec. 7, sub-sec. 2, no. 3, are subject to judicial review only with regard to the question of whether the decisions are based on non-arbitrary assumptions and sufficient investigations, (court decision referred to: BVerwG 72, 300 [316] = DVBl. 1986, 160). First-instance court ruling is VGH Mannheim, December 4, 1986, - 10 S 1840/82. (orig.)

  12. Safety culture in nuclear installations. Guidance for the use in enhancement of safety culture

    International Nuclear Information System (INIS)

    This guidance has been developed for use in the IAEA Safety Culture Services, which provides support to Member States in their efforts to develop a sound safety culture of their organizations. It will be of particular use in seminars and training workshops that are part of these services. Much of the information in this publication reflects the approach the IAEA has adopted to assist nuclear organizations in Member States in improving their safety culture. This guidance covers topics such as: what is culture, and in particular what is safety culture; what are the stages of development of safety culture, and how you can assess its development using employee surveys; what practices can be used to develop safety culture, and what indicators will help monitor progress. The symptoms of a weakening safety culture are described, as well as the lessons learned from organizations who have experienced safety culture problems. This guide also contains information on how to undertake the process of transforming the existing safety culture, and develop a learning culture in an organization that is based on continuous improvement. The relationship between quality and safety is discussed. The safety culture services offered by the IAEA are also described. The IAEA perspective of safety culture has expanded with time as its understanding of the complexities of the concept developed. The concept of safety culture was first introduced by the International Nuclear Safety Advisory Group formed by the IAEA. In their report (INSAG-4, 1991) they maintained that the establishment of a safety culture within an organization is one of the fundamental management principles necessary for the safe operation of a nuclear facility. The definition recognized that safety culture is both structural and attitudinal in nature and relates to the organization and its style, as well as to attitudes, approaches and the commitment of individuals at all levels in the organization. In the framework of the

  13. Improvement program of state supervision system for radioactive and nuclear installations

    International Nuclear Information System (INIS)

    The current program begins as part of a policy to take care of the development of the cuban nuclear program and with the objective of improving the state supervision system of nuclear and radioactive facilities on the basis of the national experience, good skills internationally accepted and taking into account IAEA recommendations. The program develops the following topics: reorientation and restructure of state supervision, review of the current nuclear legislature, update of regulations of facility safety and qualification and training of state supervision personnel

  14. The role of experts in the safety and reliability of nuclear installations

    International Nuclear Information System (INIS)

    The role of experts in the licencing construction and surveillance of nuclear power plant operation in the FRG is described. The time needed for the assessment of the construction of nuclear power plants Philippsburg I, Isar I and Unterweser was 130 - 190 man-years per power plant. The demands placed on experts' qualifications and their in-service education are summed up. A group of experts carries oUt surveillance and thus contributes to the high level of reliability and safety of nuclear power plants in the FRG. (Ha)

  15. Use of probabilistic safety assessment for nuclear installations with large inventory of radioactive material

    International Nuclear Information System (INIS)

    Experts from several countries, including most of the countries with major nuclear fuel reprocessing programmes, presented their work and related experience in the area of probabilistic safety assessment (PSA) for non-reactor nuclear facilities. The report drafted during the meeting focuses on the following topics: review of experience from PSAs for different types of facilities; development of a structured framework for conducting PSAs for non-reactor nuclear facilities; recommendations regarding the enhancement of information exchange on related matters among Member States; recommendations on areas which need further development and support. 9 papers were presented. A separate abstract was prepared for each of them. Refs, figs and tabs

  16. Subsidy Policy Design for Increasing Solar Photovoltaic Installed Capacity in China -A System Dynamics Based Study

    OpenAIRE

    Yan, Hai Yan

    2009-01-01

    China's photovoltaic (PV) based electricity generating capacity is obviously lagging behind the world level, although its manufacturing capacity of PV cells and modules has remained ahead worldwide since 2006. The Chinese government is the major investor contributing to PV-based installed generating capacity in China. A trial subsidy policy has been implemented by the Chinese government since 2007 to encourage the participation of enterprise investment. In terms of Chinese government's goals...

  17. German-Dutch memorandum of 28 October 1977 on mutual information and consultation with regard to nuclear installations close to the border

    International Nuclear Information System (INIS)

    By the German-Dutch memorandum of October 28, 1977, the Home Minister of the Federal Republic of Germany and the Dutch Minister of Public Health, Einvironment and Social Security undertake to mutually inform on the erection of nuclear installations close to the border, i.e. within 100 km of the border. For installations within 30 km of the border, an appropriate documentation must be provided. A commission is to be established consulting on nuclear installations close to the border and meeting at least once in a year. (HP)

  18. The licensing procedure and the safety of nuclear installations in Italy

    International Nuclear Information System (INIS)

    This paper analyses the concept of safety and radiation protection in the framework of the licensing procedure for nuclear power plants in Italy with particular attention to siting, and also refers to international rules and Conventions on the subject of safety. A description follows of the Italian competent bodies and their responsibilities in nuclear safety notably the CNEN (Nuclear Energy Commission), the Ministry of Industry and the CIPE (Interministerial Committee for Economic Programming), in accordance with the legislation in force. The paper concludes with an analysis of the technical safety criteria to be complied with in the preparation of the safety reports for the granting of licences for siting, construction and operation of nuclear power plants. (NEA)

  19. Assessments of conditioned radioactive waste arisings from existing and committed nuclear installations and assuming a moderate growth in nuclear electricity generation - June 1985

    International Nuclear Information System (INIS)

    This report describes an assessment of conditioned radioactive waste arisings from existing and committed nuclear installations, DOE Revised Scheme 1, and from an assumed nuclear power generation scenario, DOE Revised Scheme 3, representing a moderate growth in nuclear generation. Radioactive waste arise from 3 main groups of installations and activities: i. existing and committed commercial reactors; ii. fuel reprocessing plants, iii. research, industrial and medical activities. Stage 2 decommissioning wastes are considered together with WAGR decommissioning and the 1983 Sea Dump Consignment. The study uses the SIMULATION 2 code which models waste material flows through a system of waste treatment and packaging to disposal. With a knowledge of the accumulations and average production rates of untreated wastes and their isotopic compositions (or total activities), the rates at which conditioned wastes become available for transportation and disposal are calculated, with specific activity levels. The data for the inventory calculations have previously been documented. Some recent revisions and assumptions concerning future operation of nuclear facilities are presented in this report. (author)

  20. The irradiated fuel transport and handling system used in E.D.F. nuclear installations

    International Nuclear Information System (INIS)

    Since the problem of removal of irradiated fuels is highly important, the solution adopted by the PWR-Plants ensemble of the EDF has been the object of an in-depth study. First, a certain number of directions were defined for the study to be affected: the adoption of a means of removal which is unique for each type of power level (900 and 1300 MW); decrease of the risks of incident by reducing the number of handling steps and by simplifying the operations; decreasing the irradiation of personnel to a minimum by employing systems of protection, decontamination, and appropriate intervention, and by the smallest possible number of removals; and transport by railroad over long distances with the possibility of exceptional removal or short distance transport by motor vehicle. The restraints involved with the following have been considered: the conception of installation and the means of handling, at the station as well as at the recycling plant; handling security in the fuel building which is either active (redundant bridge), or passive (dash pot, concrete cells) or the two; the conception and rules of approbation of irradiated fuel containers, as well as the available possibilities on the market; and the means of transport (weight and speed limits). The result of the study is, for normal transport, a 100 ton container with a 12 element capacity. The delicate tilting manoeuvre must be performed with a specialized installation. Protection against contamination is to be obtained by an hermetic system which encloses the container. An automatic hydrolaser system is envisaged for principal decontamination. The adoption of these principles will thus permit the EDF to evacuate, and the recycler to receive, the irradiated fuel under the most favorable conditions for the public and for the personnel of the installations involved

  1. Regulatory aspects of the decommissioning of nuclear installations in some OECD countries

    International Nuclear Information System (INIS)

    Several OECD countries engaged in an active nuclear programme now have detailed regulatory provisions in this field or are on the point of publishing them. Nevertheless, even though numerous studies and international recommendations have been published on the technical rules for the dismantling of nuclear facilities, and that several OECD countries concerned are now co-operating actively in this area, the actual regulatory mechanism has fallen behind. The regulation of the decommissioning of nuclear facilities includes several aspects: The general legislative and regulatory framework; the procedure governing the different decommmissioning stages; the management of the radioactive waste resulting from shutdown or dismantling of the facility; the funding of the operations; the liability and insurance provisions. They are discussed in the sections concerning the different countries covered by this study. (orig.)

  2. INSTALLING AN ERP SYSTEM WITH A METHODOLOGY BASED ON THE PRINCIPLES OF GOAL DIRECTED PROJECT MANAGEMENT

    Directory of Open Access Journals (Sweden)

    Ioannis Zafeiropoulos

    2010-01-01

    Full Text Available This paper describes a generic methodology to support the process of modelling, adaptation and implementation (MAI of Enterprise Resource Planning Systems (ERPS based on the principles of goal directed project management (GDPM. The proposed methodology guides the project manager through specific stages in order to successfully complete the ERPS implementation. The development of the proper MAI methodology is deemed necessary because it will simplify the installation process of ERPS. The goal directed project management method was chosen since it provides a way of focusing all changes towards a predetermined goal. The main stages of the methodology are the promotion and preparation steps, the proposal, the contract, the implementation and the completion. The methodology was applied as a pilot application by a major ERPS development company. Important benefits were the easy and effective guidance for all installation and analysis stages, the faster installation for the ERPS and the control and cost reduction for the installation, in terms of time, manpower, technological equipment and other resources.

  3. Experiences with the guidelines regarding the monitoring of emission and immission of nuclear installations

    International Nuclear Information System (INIS)

    Initially the question is investigated of whether and how the guidelines regarding immission monitoring stood the test in the past. After the general demonstration of their suitability in the past, the relationship towards the remote monitoring of nuclear power stations is touched on, whereby investigation is made into the question of whether this can and should completely or partially replace environmental monitoring. In conclusion, a description is given of those measures for the monitoring of immissions which appear appropriate and necessary according to the current state of knowledge and taking into consideration the remote monitoring of emissions and nuclear power stations. (orig./PW)

  4. Basic terminology regarding the safety of nuclear installations. German/Russian/English. 3. rev. ed.

    International Nuclear Information System (INIS)

    GRS has produced a glossary in order to make it easier for the experts from East and West to understand each other in the fields of nuclear safety and radiation protection. This glossary contains definitions of those technical terms that are misleadingly defined in other dictionaries or are not included in them at all. The definitions of this glossary are used by the institutions responsible for the safety of nuclear facilities in the CIS, the Baltic States and the CEES, by GRS itself, by the lecturers and interpreters at the seminars, workshops and meetings, and in the preparation or revision of codes and guides in accordance with international standards. (orig./DG)

  5. Human performance and its influence on the safety of nuclear installations

    Energy Technology Data Exchange (ETDEWEB)

    Berg, Karl-Heinz; Fechner, Jochen B. [Bundesministerium des Innern, Bonn (Germany)

    2015-05-15

    Nuclear facilities need to be handled in all safety considerations as ''man-machine-system'' as humans considered as liveware are of equally importance ensuring safety as hardware and software. The Federal Minister of the Interior is attempting to give greater focus to this knowledge for the practice of nuclear safety measures. Therefore hardware and software need to be improved according to ergonomic findings and greater importance needs to be issued to the qualification of the operational staff as well as to the qualification of experts consulted by local authorities.

  6. Human performance and its influence on the safety of nuclear installations

    International Nuclear Information System (INIS)

    Nuclear facilities need to be handled in all safety considerations as ''man-machine-system'' as humans considered as liveware are of equally importance ensuring safety as hardware and software. The Federal Minister of the Interior is attempting to give greater focus to this knowledge for the practice of nuclear safety measures. Therefore hardware and software need to be improved according to ergonomic findings and greater importance needs to be issued to the qualification of the operational staff as well as to the qualification of experts consulted by local authorities.

  7. Basic causes of legal problems arising from nuclear installations close to the frontier - the point of view of the neighbouring state

    International Nuclear Information System (INIS)

    Legal problems arise from different safety standards in the states concerning the operation of nuclear power plants. The EURATOM treaty contains only a few regulations for these legal problems. A harmonization of safety standards for nuclear installations and of the radiation protection limits is necessary. (CW)

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

    International Nuclear Information System (INIS)

    To enhance the outer coordination on emergency response for nuclear accidents, the NNSA laid stress in 1999 on the control of radiation environment and re-evaluate the monitoring ability for Chinese radioactive environment, to establish a technical supporting organization, i.e., the Monitoring Center on Radioactive Environment, SEPA

  9. Safety regulation on emergency response and radiation protection in civilian nuclear installation

    International Nuclear Information System (INIS)

    In 1998, the NNSA promulgated the >, and organized to compile and translate the Draw-up Methods on NPP Emergency Action Level, the Evaluation Program on Health Physics, the Dose Control at NPP and related technical documents in order to strengthen the basis work about the nuclear accident emergency inspection

  10. The management of public exposures associated with the radioactive releases of nuclear installations

    International Nuclear Information System (INIS)

    This document presents the speeches and discussions occurred during the seminar of decision makers on the radioprotection optimization in complex situations. The goal of this seminar was the exploration of the various criteria taken into account in decision making processes associated to the public exposure management and more particularly, to the nuclear facilities releases. (A.L.B.)

  11. Development of public inquiry procedures in relation to proposals for nuclear installations in the United Kingdom

    International Nuclear Information System (INIS)

    Following a description of the procedures followed for formal investigations on matters of public policy in the UK, this paper reviews public enquiry procedures regarding nuclear site licences and gives specific examples of such enquiries (Windscale, Sizewell), showing how the system has evolved over the years. (NEA)

  12. Operation experience with nuclear power installations in the Federal Republic of Germany

    International Nuclear Information System (INIS)

    In this report a comprehensive review is given of operational results achieved with the nuclear power stations functioning in the Federal Republic of Germany during 1987. Following a general review, the individual power reactors are considered in detail, presenting operational charts for 1987 and other tabulated information or illustrations. (orig.)

  13. Self-assessment of safety culture in nuclear installations. Highlights and good practices

    International Nuclear Information System (INIS)

    This report summarizes the findings of two IAEA Technical Committee Meetings on Safety Culture Self-Assessment Highlights and Good Practices. The meetings took place on 3-5 June 1998 and 23-25 October 2000 in Vienna, and involved an international cross-section of representatives who participated both in plenary discussions and working groups. The purpose of the meetings was to discuss the practical implications of evolutionary changes in the development of safety culture, and to share international experience, particularly on the methods used for the assessment of safety culture and good practices for its enhancement in an organization. The working groups were allocated specific topics for discussion, which included the following: organizational factors influencing the implementation of actions to improve safety culture; how to measure, effectively, progress in implementing solutions to safety culture problems; the symptoms of a weakening safety culture; the suitability of different methods for assessing safety culture; the achievement of sustainable improvements in safety culture using the results of assessment; the potential threats to the continuation of a strong safety culture in an organization from the many challenges facing the nuclear industry. The working groups, when appropriate, considered issues from both the utility's and the regulator's perspectives. This report will be of interest to all organizations who wish to assess and achieve a strong and sustainable safety culture. This includes not only nuclear power plants, but also other sectors of the nuclear industry such as uranium mines and mills, nuclear fuel fabrication facilities, nuclear waste repositories, research reactors, accelerators, radiography facilities, etc. The report specifically supplements other IAEA publications on this subject

  14. Nuclear basic installations and transport of radioactive matters: a decree of the 2. november 2007 overrules the decree of the 11. december 1963

    International Nuclear Information System (INIS)

    The law relative to the transparency and to the safety in nuclear subject was taken back then enriched. In constant law, the law would have been able to be only the resumption of the decree of 1963, only legal foundation of the activities and the nuclear installations. By giving it the authority of the law, the legislator and policy intended to renew totally the legal frame of the installations and the nuclear activities, shape of symbolic expiation of the former systems. (N.C.)

  15. President's closing comments [International conference on topical issues in nuclear installation safety: Continuous improvement of nuclear safety in a changing world

    International Nuclear Information System (INIS)

    My first broad theme is the need to harmonize regulatory approaches: There is a need to build on the IAEA safety standards to provide vendors, operators and regulatory authorities with internationally accepted standards for designing, licensing, operating and regulating nuclear installations; - The variant opinions on design certification; - The question of how to harmonize the transition point between safety standards and industrial standards; - Role of the IRRT to act as a vehicle to promote regulatory consistency. Emphasis on the new IRRT process that addresses self-assessment. Recognition of the generic call for all Member States with nuclear installations to consider availing themselves of this valuable peer review service; - The need to establish the right balance in using, in a complementary manner, both deterministic and probabilistic approaches during design, operations and regulatory activities; - Globalization and the provision of reactors to Member States with no vendor knowledge (or allowing for the new business concepts where new corporate owners or individual site managers are 'business-oriented and experienced' as opposed to being 'operationally experienced') calls into questions who 'owns' the design (design conscience), who is responsible for providing the necessary focus (decision making and resources) on safety (safety conscience) and security (security conscience). My second broad theme relates to the concept of operating experience and the need to foster an environment conducive to becoming 'learning organizations': - Maintaining a transparent environment is essential, with other owner-operators, with the regulatory authorities and with the public; - Recurrent events are taking place! How do we ensure that the lessons learned in the past are not forgotten during the present and lost in the future? - The process for identifying low level and near miss events must be stimulated and serve as a repository of lessons learned for all members of the

  16. INSTALLED BASE REGISTRATION OF DECENTRALISED SOLAR PANELS WITH APPLICATIONS IN CRISIS MANAGEMENT

    Directory of Open Access Journals (Sweden)

    R. Aarsen

    2015-08-01

    Full Text Available In case of a calamity in the Netherlands - e.g. a dike breach - parts of the nationwide electric network can fall out. In these occasions it would be useful if decentralised energy sources of the Smart Grid would contribute to balance out the fluctuations of the energy network. Decentralised energy sources include: solar energy, wind energy, combined heat and power, and biogas. In this manner, parts of the built environment - e.g. hospitals - that are in need of a continuous power flow, could be secured of this power. When a calamity happens, information about the Smart Grid is necessary to control the crisis and to ensure a shared view on the energy networks for both the crisis managers and network operators. The current situation of publishing, storing and sharing data of solar energy has been shown a lack of reliability about the current number, physical location, and capacity of installed decentralised photovoltaic (PV panels in the Netherlands. This study focuses on decentralised solar energy in the form of electricity via PV panels in the Netherlands and addresses this challenge by proposing a new, reliable and up-to-date database. The study reveals the requirements for a registration of the installed base of PV panels in the Netherlands. This new database should serve as a replenishment for the current national voluntary registration, called Production Installation Register of Energy Data Services Netherland (EDSN-PIR, of installed decentralised PV panel installations in the Smart Grid, and provide important information in case of a calamity.

  17. Some aspects of the safety of nuclear installations in Great Britain. Replies to questions submitted by the Secretary of State for Energy to the Nuclear Installations Inspectorate in October 1976

    International Nuclear Information System (INIS)

    Following an explanatory introduction, the material is set out under heading: the organisation of the Nuclear Installations Inspectorate; the policy of the Health and Safety Commission; reactor systems and the fuel cycle (including thermal and fast reactors); fast reactor safety (assessing fast reactor problems; containment; sodium coolant; deterioration of materials in the reactor; fault detection and accident prevention; consequences of a fast reactor accident; the safety advantages in building a full-scale commercial demonstration fast reactor (CFR 1)); the fuel cycle (reprocessing; plutonium problems; high, moderate and low activity wastes); security; glossary; appendices (questions submitted by the Secretary of State for Energy; by Mr. Nigel Forman MP; and by the Friends of the Earth). (U.K.)

  18. Accident consequence analysis models applied to licensing process of nuclear installations, radioactive and conventional industries

    International Nuclear Information System (INIS)

    The industrial accidents happened in the last years, particularly in the eighty's decade, had contributed in a significant way to call the attention to government authorities, industry and society as a whole, demanding mechanisms for preventing episodes that could affect people's safety and environment quality. Techniques and methods already thoroughly used in the nuclear, aeronautic and war industries were then adapted for performing analysis and evaluation of the risks associated to other industrial activities, especially in the petroleum, chemistry and petrochemical areas. Some models for analyzing the consequences of accidents involving fire and explosion, used in the licensing processes of nuclear and radioactive facilities, are presented in this paper. These models have also application in the licensing of conventional industrial facilities. (author)

  19. Nuclear facilities: repair and replacement technologies; Installations nucleaires: technologies de reparation et de remplacement

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-07-01

    The oldest operating reactors are more than 35 years old and are now facing major maintenance operations. The first replacement of a pressurizer took place in autumn 2005 at the St-Lucie plant (Usa) while steam generators have been currently replaced since 1983. Nuclear industry has to adapt to this new market by proposing innovative technological solutions in the reactor maintenance field. This document gathers the 9 papers presented at the conference. The main improvements concern repair works on internal components of PWR-type reactors, the replacement of major components of the primary coolant circuit and surface treatments to limit the propagation of damages. The first paper shows that adequate design and feedback experience are good assets to manage the ageing of a nuclear unit. Another paper shows that a new repair method of a relief valve can avoid its replacement. (A.C.)

  20. Chi-Chi (Taiwan) earthquake of September 21, 1999. Findings for the nuclear installations in Switzerland: short report

    International Nuclear Information System (INIS)

    The Swiss Federal Nuclear Safety Inspectorate (HSK) has a great interest to be rapidly informed and documented on relevant consequences of major earthquakes in industrialized countries in the world, in particular with respect to nuclear installations. The main goal is to recognize within a short time after such events, if measures should be taken at the Swiss nuclear installations. Therefore, Basler and Hofmann have prepared a report on the Chi-Chi (1999) earthquake for HSK within a few weeks after the event. The information was obtained primarily from the Internet and by directly contacting local authorities and other selected organisations in Taiwan. This short report is a summary representation of the HSK report of November 23, 1999. No updated or additional information on the earthquake is included herein. The summary concentrates on the findings for the Swiss nuclear installations. Compared with Taiwan, Switzerland is situated in a seismically much less active region. However, similarities exist with respect to the focal mechanism (thrust), the compressional stress regime and the low focal depth. Thus, the pattern of the iso-seismal lines and the maximum acceleration values would be similar in Switzerland in the case of an equally strong event. Such a strong event has been considered as unrealistic to occur in Switzerland so far. In the PSA studies for the Swiss nuclear power plants, a maximum magnitude up to 7.5 was considered, but only with a low weight. Under the assumption of a magnitude 7.6 event in the seismically most active region in Switzerland (Valais), the SSE accelerations at the closest site (Muehleberg NPP) could probably be exceeded. Most effects at components observed during the Chi-Chi earthquake (at non-nuclear sites) are already known to HSK and they have been considered systematically at the Swiss NPPs. A rather sensitive point is the possible loss of power from emergency diesel generators, as observed at non-nuclear sites in Taiwan. The

  1. The tasks of the employer's liability insurance association and their commitment in nuclear installations

    International Nuclear Information System (INIS)

    The employers liability insurance association in the field of precision engineering and electrical engineering is the competent association for commitment in nuclear power plant. Their activities include advising and supervisory functions as well as training and other tasks for the purpose of accident prevention in the power plants, as are done in the all in all 800.000 industrial facilities liable to insurance by this association, covering well over 2 millions of insured persons. (orig./HP)

  2. The importance of servicing for the safety and economic efficiency of nuclear installations

    International Nuclear Information System (INIS)

    Experience-oriented preventive maintenance is the central and decisive instrument for plant safety. Preventive maintenance, in the overriding sense of the entire system consisting of man and machine, is identical with service. Such service must be readily available, efficient, purposeful, innovative and of high quality. The high quality of German nuclear power plants and their reliability are the result of a constructive cooperation between producer, supplier, service enterprise and operator. (DG)

  3. Updating of nuclear magnetic resonance installation on the basis of IBM PC computers

    International Nuclear Information System (INIS)

    Updating of nuclear magnetic resonance spectrometers TESLA BS-567 and BRUKER SXP-100 is carried out by means of the application of the multifunctional extension plate ACL-812 PG and IBM PC. This extension plate consists of the 16-channel analog multiplexer, the 12-digit ADC, the timer and the logic access circuits for DMA and IRQ. The software consists of the control program working in the operation system MS DOS

  4. Assessing the effect of nuclear power installation construction and operation on the socio-economic sphere

    International Nuclear Information System (INIS)

    A demographic analysis is made of the area within 25 km from the Dukovany nuclear power plant. The problem is discussed of sources and requirements for manpower for the construction and operation of the power plant. It was found that the capacity of creches and nursery schools for children of power plant employees is inadequate, as are health care facilities for personnel. (E.S.)

  5. Proceedings of a specialist meeting on the anti-seismic design of nuclear installations

    International Nuclear Information System (INIS)

    This meeting is composed of 26 papers, grouped into 6 sessions. Session I: Introduction (reports on previous meetings related to seismic issues and mechanical structures for nuclear power plants). Session II: seismology. Session III: soil-foundation interaction. Session IV: structures and equipment; Session V: experimental techniques and instrumentation of power plants. Session VI: Synthesis and regulations. Each session is followed by a general discussion. The meeting is concluded with the chairman's report

  6. Evaluation and surveillance of radioactive waste of the nuclear installations in Switzerland

    International Nuclear Information System (INIS)

    The evaluation and surveillance of nuclear power plants aims to guarantee the protection of the population and of the environment against ionizing radiation. Facing this challenge requires to put in place a liable control program concerning the radioactive releases as well as a thorough radiological surveillance of the environment and a comprehensible information system of the public. In order to obtain public acceptance, the surveillance of the releases and the evaluation of their impact have to be confined to an accredited organism which is independent of the nuclear power industry. Such is the case in Switzerland, where the radioprotection law requires that the federal office of public health (SFOPH) is responsible for this task in collaboration with local and university laboratories and institutes. This publication presents a overview of the actually used evaluation methods concerning the impact of the radioactive releases from the Swiss nuclear power plants on the local environment and population as well as the role of the surveillance organization. Also presented are certain lessons to be learned and perspectives to be considered in this field. (author)

  7. Radioactivity around naval nuclear bases

    International Nuclear Information System (INIS)

    Between 12th July and 2nd August 1988, Greenpeace took sediment samples from around four Royal Navy bases in the United Kingdom. Faslane, where nuclear powered submarines are berthed; Devonport and Rosyth where refit work is carried out and Portsmouth where US and UK nuclear submarines often visit. Samples were also taken from the US Navy base at Holy Loch, Scotland, where nuclear powered ballistic missile submarines are based. The samples were analysed at St Bartholomew Hospital Medical School, London. Identical samples were provided to the MoD personnel at Faslane and Devonport on the date taken. The purpose of carrying out the sampling programme was to highlight the fact that publicly available statistics from Ministry of Agriculture Fisheries and Food (MAFF) are too limited in range, concentrating as they do merely on radioactive levels found between tides. The findings point to the necessity of monitoring subtidal as well as intertidal areas since levels of radioactivity found in the samples at Faslane and Holy Loch were four to nine times the figures published by MAFF. Until such time as nuclear power is no longer used at sea, it is the contention of Greenpeace that a more independent and comprehensive picture of the nature of radioactive contamination from around UK naval establishments must be obtained, than that presently available from MAFF. (author)

  8. Development of a Preliminary Decommissioning Plan Following the International Structure for Decommissioning Costing (ISDC) of Nuclear Installations - 13361

    International Nuclear Information System (INIS)

    The International Structure for Decommissioning Costing (ISDC) of Nuclear Installations, published by OECD/NEA, IAEA and EC is intended to provide a uniform list of cost items for decommissioning projects and provides a standard format that permits international cost estimates to be compared. Candesco and DECOM have used the ISDC format along with two costing codes, OMEGA and ISDCEX, developed from the ISDC by DECOM, in three projects: the development of a preliminary decommissioning plan for a multi-unit CANDU nuclear power station, updating the preliminary decommissioning cost estimates for a prototype CANDU nuclear power station and benchmarking the cost estimates for CANDU against the cost estimates for other reactor types. It was found that the ISDC format provides a well defined and transparent basis for decommissioning planning and cost estimating that assists in identifying gaps and weaknesses and facilitates the benchmarking against international experience. The use of the ISDC can also help build stakeholder confidence in the reliability of the plans and estimates and the adequacy of decommissioning funding. (authors)

  9. The radiation exposure of the UK population from airborne effluents discharged from civil nuclear installations in the UK in 1978

    International Nuclear Information System (INIS)

    An assessment is made of the radiation exposure of the UK population from airborne effluents discharged in 1978 from civil nuclear installations in the UK. The results are, however, presented in a manner whereby the dose from discharges in other years can be readily estimated. The total collective dose and the contribution from each nuclear establishment are evaluated; in addition, attention is given to the distribution of the collective dose both in time and among the exposed population as these features may be important in judging the significance of given collective dose. The total collective effective dose equivalent commitment is estimated to be about 14 man Sv; about one half is delivered within a few years of the discharges, with the remainder delivered fairly uniformly over a period of several thousand years. Carbon-14 is the major contributor to the total collective dose and to that from many of the individual nuclear establishments; other significant contributors are caesium-137, uranium, argon-41, tritium and some transuranic nuclides. Iodine-129 and krypton-85 make major contributions to the collective dose equivalent commitments to the thyroid and skin, respectively, but not to the effective dose. (author)

  10. Radiation Control Coatings Installed on Federal Buildings at Tyndall Air Force Base

    Energy Technology Data Exchange (ETDEWEB)

    Kaba, R.L.; Petrie, T.W.

    1999-03-16

    The technical objectives of this CRADA comprise technology deployment and energy conservation efforts with the radiation control coatings industry and the utility sector. The results of this collaboration include a high-level data reporting, analysis and management system to support the deployment efforts. The technical objectives include successfully install, commission, operate, maintain and document the performance of radiation control coatings on roofs at Tyndall AFB and the Buildings Technology Center at the Oak Ridge National Laboratory; determine the life cycle savings that can be achieved by using radiation control coatings on entire roofs at Tyndall AFB, based on documented installed cost and operating maintenance costs with and without the coatings; determine if any specific improvements are required in the coatings before they can be successfully deployed in the federal sector; determine the most effective way to facilitate the widespread and rapid deployment of radiation control coatings in the federal sector; and clearly define any barriers to deployment.

  11. Decommissioning and dismantling of nuclear installations - The perspective from the OECD/NEA

    International Nuclear Information System (INIS)

    The Member countries of the OECD/Nuclear Energy Agency are among those that were involved in the earliest developments of nuclear technology in the 1940's and 1950's. They thus have a range of plants and equipment that has now served its purpose and needs to be decommissioned and dismantled. Decommissioning of all types of nuclear fuel cycle facilities can and has been done. The decommissioning and dismantling (D and D) work done on earlier facilities has provided a substantial body of knowledge and experience over a wide range of complex technical issues, but the requirement now is to apply the available techniques to the D and D of the larger commercial facilities. A new range of challenges opens up as the more modern nuclear power programmes mature and large commercial nuclear power plants approach the end of their useful life by reason of age, economics or change of policy on the use of nuclear power. The scale of such challenges may be judged from the fact that over 400 nuclear power plants have been constructed and operated world-wide, most of them in NEA member countries. Given an average planned operating life span of 30 to 40 years and given that the average age of nuclear power plants is, at present, about 15 years, the rate of withdrawal from service will peak some time after 2015. The peak will, however, be sometime later if the tendency to extend operating lifetimes continues. The statistical distribution is wide, anyhow, with some countries having already retired certain commercial nuclear power plants from service, and having even decommissioned and dismantled them in some cases, whilst in other countries it will be some years before any plants are retired. We have some time to prepare, but not indefinite time and it can be expected that a decommissioning industry will grow even stronger than what it is today. In addition to technical issues, plans and procedures will need to address other major issues associated with impacts on society and the

  12. An integrated management system to improve the performance of nuclear installations

    International Nuclear Information System (INIS)

    A integrated management system encompasses all management and assessment activities. The integration of DM, QM, safety management and occupational health into an integrated management system is shown for structures, systems and components of waste repositories because they have to fulfill reliability requirements derived from comprehensive safety assessments, and these structures, systems and components (such as transport vehicles and stacker trucks for the underground emplacement activities) are especially manufactured for this purpose and are not series products. QM institutes a QM system which ensures that there are clearly defined and auditable procedures. The requirements are written down in specifications or operation manuals and/or maintenance manuals. The QM system provides assurance that the installed structures, systems or components meet and continue to meet the prescribed goals with the help of DM and that safety management and occupational health specified requirements are fulfilled. DM focuses on the use of engineering analyses, assessments and methods to improve the design, specification, construction, dependability and operation of important systems, structures and components. (author)

  13. Transport and the dismantling of nuclear facilities; Les transports lies a la deconstruction des installations nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    Hartenstein, M.

    2011-11-15

    Transport is not a real limiting constraint for the dismantling of nuclear facility if transport is taking into account very early in the dismantling process since numerous packages in various sizes already exist. For instance the TN-Gemini package allows the constitution of B-type packages for high radioactive level wastes, its volume capacity of about 16 m{sup 3} can store up to 5.8 tones of wastes, its external dimensions make it look like a sea container. One difficulty would be to find the adequate waste classification for a package containing heterogeneous wastes. (A.C.)

  14. Evaluation of Seismic Safety for Existing Nuclear Installations. Safety Guide (Russian Edition)

    International Nuclear Information System (INIS)

    The IAEA's Statute authorizes the Agency to establish safety standards to protect health and minimize danger to life and property - standards which the IAEA must use in its own operations, and which a State can apply by means of its regulatory provisions for nuclear and radiation safety. A comprehensive body of safety standards under regular review, together with the IAEA's assistance in their application, has become a key element in a global safety regime. In the mid-1990s, a major overhaul of the IAEA's safety standards programme was initiated, with a revised oversight committee structure and a systematic approach to updating the entire corpus of standards. The new standards that have resulted are of a high calibre and reflect best practices in Member States. With the assistance of the Commission on Safety Standards, the IAEA is working to promote the global acceptance and use of its safety standards. Safety standards are only effective, however, if they are properly applied in practice. The IAEA's safety services - which range in scope from engineering safety, operational safety, and radiation, transport and waste safety to regulatory matters and safety culture in organizations - assist Member States in applying the standards and appraise their effectiveness. These safety services enable valuable insights to be shared and I continue to urge all Member States to make use of them. Regulating nuclear and radiation safety is a national responsibility, and many Member States have decided to adopt the IAEA's safety standards for use in their national regulations. For the contracting parties to the various international safety conventions, IAEA standards provide a consistent, reliable means of ensuring the effective fulfilment of obligations under the conventions. The standards are also applied by designers, manufacturers and operators around the world to enhance nuclear and radiation safety in power generation, medicine, industry, agriculture, research and education

  15. Some questions of monitoring on nuclear installations and quality of safety assessments

    International Nuclear Information System (INIS)

    The paper is prepared on the basis of assessment performed by the State Scientific and Technical Centre on Nuclear and Radiation safety which deals with scientific and technical support of the Regulatory Authorities of Ukraine concerning integrity of pressurised elements in the NPP. A number of acute issues on control equipment could be distinguished: placement of sensors should provide adequate information on the data under control necessary for safety analysis; properties of instrumentation should provide trustworthy information about measured values; accurate recommendations should be imposed to operating organisations for performing special analyses for control devices

  16. Radiation protection of personnel in designing and management of nuclear power installations

    International Nuclear Information System (INIS)

    An analysis of the current state of the radiation burden of personnel in light water nuclear power plants and a survey of introduced and developed measures for its reduction indicates the complexity of the problem. Doses to personnel will have to be reduced to 20% as compared with the current state. There is a wide range of possibilities ranging from the elimination of primary causes to organizational measures. A satisfactory solution can only be brought about by an economically optimized system of well-founded measures. (Ha)

  17. Enhancing Regulatory Inspection Practices and Safety Culture of Regulatory Body Personnel for Improving Safety of Nuclear Fuel Cycle Installations

    International Nuclear Information System (INIS)

    The nuclear fuel cycle installations (NFCIs) are characterized by different physical and chemical processes applied on fissile and radioactive materials in different physical forms, as well as many human interventions required for the control of these operation and maintenance of NFCIs equipments. Therefore, personnel radiation protection requirement is more demanding in these installations. Accordingly, it is necessary to apply a wide range of specific safety measures or actions in addition to inherent design features in the form of administrative safety actions during normal operation of these processes in NFCIs. In this paper, emphasis is focusing on operational administrative safety control measures in NFCIs as a major factor for preventing abnormal conditions and accidents in the NFCIs and hence protection of personnel against release of radiation. The paper presents a systematic and improved Operational Safety Management Approach focusing on administrative safety measures and enhancement of safety culture of NFCIs operators and a Regulatory Inspection Methodology (OSMARIM). This approach can help for enhancing regulatory inspection practices of regulatory body inspectors and ensuring operational safety management in NFCIs. (author)

  18. Radiation risk from the nuclear power installation of space vehicle in case of reentry to the atmosphere

    International Nuclear Information System (INIS)

    Main directions of space using of nuclear power are considered. Nuclear energy has found many applications in space projects. The first application is the use of nuclear energy for the production of electricity in space and the second main application is the use of nuclear power for propulsion purposes in space flight. History of usage nuclear power systems in space technic is shown. Today there are 54 satellites with NPS in space near the Earth. The main principle of radical solution of the problem of radiation safety is based on the accommodation of space objects with nuclear units in orbits, such that the ballistic lifetime is greater than the time necessary for complete decay of the accumulated radioactivity. Radiation safety on various stages of space nuclear systems exploitation is discussed. If Main System Ensuring Radiation Safety is failed, it must operates Reserved System Ensuring Radiation Safety. Concrete development of a booster system for nuclear unit and a system for the reactor destruction in order to ensure aerodynamic destruction of fuel has been realized in satellite of 'Cosmos' series. The investigations on reserved system ensuring radiation safety in Moscow Physical - Engineering Institute are discussed. The results show that we can in principle ensure the radiation safety in accordance to ICRP recommendations. (author)

  19. Instrumentation report 1: specification, design, calibration, and installation of instrumentation for an experimental, high-level, nuclear waste storage facility

    International Nuclear Information System (INIS)

    The Spent Fuel Test-Climax (SFT-C) is being conducted 420 m underground at the Nevada Test Site under the auspices of the US Department of Energy. The test facility houses 11 spent fuel assemblies from an operating commercial nuclear reactor and numerous other thermal sources used to simulate the near-field effects of a large repository. We developed a large-scale instrumentation plan to ensure that a sufficient quality and quantity of data were acquired during the three- to five-year test. These data help satisfy scientific, operational, and radiation safety objectives. Over 800 data channels are being scanned to measure temperature, electrical power, radiation, air flow, dew point, stress, displacement, and equipment operation status (on/off). This document details the criteria, design, specifications, installation, calibration, and current performance of the entire instrumentation package

  20. Aspects of the licensing practice and project management in the decommissioning of nuclear installations, as seen by the licensee

    International Nuclear Information System (INIS)

    Any modification of a nuclear installation after its final shutdown which is intended to reduce the plant in principle is regarded as a decommissioning activity and therefore requires a licence under paragraph 7 sub-sec. 3 Atomic Energy Act, if the modification is essential. The existing legal instruments are sufficient for steadily progressing in the licensing procedure for decommissioning. A project management subdividing the entire procedure into suitable steps allows to carry out the licensing procedure without causing undue delay of the entire decommissioning procedure. There is a lack of appropriate regulatory provisions relating to the high-priority tasks of safe recycling of non-contaminated or low-level radioactive materials. (orig.)