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. 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)

  3. 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

  4. 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.

  5. 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

  6. 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

  7. 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

  8. 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

  9. 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

  10. 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

  11. 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

  12. 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

  13. 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

  14. 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

  15. 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.)

  16. 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.)

  17. 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

  18. 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

  19. 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)

  20. 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

  1. 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.)

  2. Nondestructive Evaluation of Functionally Graded Subsurface Damage on Cylinders in Nuclear Installations Based on Circumferential SH Waves

    Directory of Open Access Journals (Sweden)

    Zhen Qu

    2016-01-01

    Full Text Available Subsurface damage could affect the service life of structures. In nuclear engineering, nondestructive evaluation and detection of the evaluation of the subsurface damage region are of great importance to ensure the safety of nuclear installations. In this paper, we propose the use of circumferential horizontal shear (SH waves to detect mechanical properties of subsurface regions of damage on cylindrical structures. The regions of surface damage are considered to be functionally graded material (FGM and the cylinder is considered to be a layered structure. The Bessel functions and the power series technique are employed to solve the governing equations. By analyzing the SH waves in the 12Cr-ODS ferritic steel cylinder, which is frequently applied in the nuclear installations, we discuss the relationship between the phase velocities of SH waves in the cylinder with subsurface layers of damage and the mechanical properties of the subsurface damaged regions. The results show that the subsurface damage could lead to decrease of the SH waves’ phase velocity. The gradient parameters, which represent the degree of subsurface damage, can be evaluated by the variation of the SH waves’ phase velocity. Research results of this study can provide theoretical guidance in nondestructive evaluation for use in the analysis of the reliability and durability of nuclear installations.

  3. 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

  4. The Swiss nuclear installations. Annual report 1994

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-06-01

    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.

  5. The Swiss nuclear installations. Annual report 1993

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1994-08-01

    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.

  6. 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

  7. 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

  8. 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)

  9. 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.

  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. 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)

  12. 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

  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. 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)

  15. 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.)

  16. 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

  17. Reliability of sprinkler systems. Exploration and analysis of data from nuclear and non-nuclear installations

    Energy Technology Data Exchange (ETDEWEB)

    Roenty, V.; Keski-Rahkonen, O.; Hassinen, J.P. [VTT Building and Transport, Espoo (Finland)

    2004-12-01

    Sprinkler systems are an important part of fire safety of nuclear installations. As a part of effort to make fire-PSA of our utilities more quantitative a literature survey from open sources worldwide of available reliability data on sprinkler systems was carried out. Since the result of the survey was rather poor quantitatively, it was decided to mine available original Finnish nuclear and non-nuclear data, since nuclear power plants present a rather small device population. Sprinklers are becoming a key element for the fire safety in modern, open non-nuclear buildings. Therefore, the study included both nuclear power plants and non-nuclear buildings protected by sprinkler installations. Data needed for estimating of reliability of sprinkler systems were collected from available sources in Finnish nuclear and non-nuclear installations. Population sizes on sprinkler system installations and components therein as well as covered floor areas were counted individually from Finnish nuclear power plants. From non-nuclear installations corresponding data were estimated by counting relevant things from drawings of 102 buildings, and plotting from that sample needed probability distributions. The total populations of sprinkler systems and components were compiled based on available direct data and these distributions. From nuclear power plants electronic maintenance reports were obtained, observed failures and other reliability relevant data were selected, classified according to failure severity, and stored on spreadsheets for further analysis. A short summary of failures was made, which was hampered by a small sample size. From non-nuclear buildings inspection statistics from years 1985.1997 were surveyed, and observed failures were classified and stored on spreadsheets. Finally, a reliability model is proposed based on earlier formal work, and failure frequencies obtained by preliminary data analysis of this work. For a model utilising available information in the non-nuclear

  18. 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)

  19. 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)

  20. 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

  1. 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)

  2. 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.)

  3. 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

  4. 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

  5. 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)

  6. 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

  7. 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

  8. 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.

  9. 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.

  10. 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.

  11. 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

  12. 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

  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. Determination of the standards of the thermo-physiological tolerance for working in basic nuclear installation in TIVA protective clothing; Determination des normes de tolerance thermophysiologique pour le travail en installation nucleaire de base en tenue TIVA

    Energy Technology Data Exchange (ETDEWEB)

    Casanova, P.; Daret, J.L. [AREVA NC- etablissement de La Hague, service de sante au travail, 50444 Beaumont-Hague Cedex (France); Besnard, Y.; Clerc, N.; Savourey, G.; Launay, J.C. [IRBA, Antenne La Tronche CRSSA, 24 avenue du marquis de Gresivaudan, BP 87, 38702 La Tronche Cedex (France)

    2011-04-15

    The purpose of this study was to determine the duration limited exposure (DLE) for working in a contaminated zone in a basic nuclear installation using the new ventilated TIVA protective clothing. Five subjects underwent a treadmill exercise (3.5 km/h, 3% of slope) of up to 2 h in a climatic chamber at 25, 35, and 45 deg. C. Cardiac frequency, rectal temperature and skin temperature were continuously recorded. The dehydration level was measured by the loss of weight during the exercise. At 25 deg. C, thermal and cardiovascular thresholds are not reached; the risk is dehydration if the exercise is prolonged. In contrast, the thresholds for Tre at 39 deg. C (97 {+-} 29 and 69 {+-} 28 min for 35 and 45 deg. C, respectively) and for the increase in Tre (+1.5 deg. C) are reached earlier (84 {+-} 38 min and 57 {+-} 21 min at 35 and 45 deg. C, respectively). This leads to a higher heat storage (42.2 {+-} 22.9 W/m{sup 2} and 63.7 {+-} 29.4 W/m{sup 2}, at 35 and 45 deg. C, respectively), which constitutes a higher risk of heat illnesses. The dehydration level is 2% of the weight for the tests at 35 and 45 deg. C. As a consequence, DLE for working in a contaminated zone in a basic nuclear installation in environmental conditions and using the new ventilated TIVA protective clothing, as encountered in our experiments, are proposed to avoid hyperthermic accidents. (authors)

  15. 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

  16. 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

  17. 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.

  18. 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.

  19. 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)

  20. 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)

  1. 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)

  2. 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

  3. 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

  4. 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)

  5. 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. 

  6. 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

  7. 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.

  8. 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

  9. 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

  10. 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

  11. 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)

  12. 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

  13. 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.)

  14. 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

  15. 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)

  16. 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

  17. 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

  18. 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

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

    International Nuclear Information System (INIS)

    Initiated by the Commission of the European Communities (CEC), this seminar was jointly organized by 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

  20. 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

  1. 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)

  2. 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)

  3. 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.)

  4. 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

  5. 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)

  6. 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

  7. 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.)

  8. 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

  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. 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

  12. 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)

  13. 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

  14. On statistical methods for analysing the geographical distribution of cancer cases near nuclear installations.

    OpenAIRE

    Bithell, J F; Stone, R A

    1989-01-01

    There is great public concern, often based on anecdotal reports, about risks from ionising radiation. Recent interest has been directed at an excess of leukaemia cases in the locality of civil nuclear installations at Sellafield and Sizewell, and epidemiologists have a duty to pursue such information vigorously. This paper sets out to show that the epidemiological methods most commonly used can be improved upon. When analysing geographical data it is necessary to consider location. The most o...

  15. 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.)

  16. 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)

  17. Improvement of piping installation work in nuclear power plant

    International Nuclear Information System (INIS)

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

  18. 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.)

  19. 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

  20. 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)

  1. 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....

  2. 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

  3. 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

  4. 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

  5. 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)

  6. 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)

  7. 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....

  8. 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)

  9. Designing Software-Based Interactive Installations

    DEFF Research Database (Denmark)

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

    2014-01-01

    considers the development of interactive installations for immersive experiences with emphasis on the special design challenges they present. How. The approach described includes four phases: exploration, design, construction, and exhibition. The aim of the exploration is to clarify the general behavior...... architecture as well as esthetic experience, artistic expression, and leisure aspects into focus. The approach presented here has this intended purpose. Where. Building on experience from conventional software development and with inspiration from interaction design and creative programming, this chapter...... of the installation using tools like sketching or storyboarding. The design involves a clarification of available and appropriate building blocks, as well as the linking of these blocks to provide an architectural framework comprising the intended external behavior. The construction phase takes a component...

  10. 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)

  11. 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.)

  12. 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)

  13. 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...

  14. 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)

  15. 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)

  16. 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.

  17. 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.)

  18. 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.)

  19. 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

  20. 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.)

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

    Energy Technology Data Exchange (ETDEWEB)

    Zachar, Matej; Necas, Vladimir [Slovak University of Technology in Bratislava, Faculty of Electrical Engineering and Information Technology, Department of Nuclear Physics and Technology, Ilkovicova 3, 812 19 Bratislava (Slovakia)

    2008-07-01

    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)

  2. 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.)

  3. 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)

  4. 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)

  5. 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.)

  6. 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

  7. 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

  8. 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

  9. 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.)

  10. 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)

  11. 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)

  12. 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

  13. 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

  14. 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.)

  15. 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

  16. 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)

  17. 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

  18. 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

  19. 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)

  20. 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)

  1. 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)

  2. 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)

  3. 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)

  4. 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)

  5. 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)

  6. 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

  7. 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

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

    International Nuclear Information System (INIS)

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

  9. On statistical methods for analysing the geographical distribution of cancer cases near nuclear installations.

    Science.gov (United States)

    Bithell, J F; Stone, R A

    1989-03-01

    There is great public concern, often based on anecdotal reports, about risks from ionising radiation. Recent interest has been directed at an excess of leukaemia cases in the locality of civil nuclear installations at Sellafield and Sizewell, and epidemiologists have a duty to pursue such information vigorously. This paper sets out to show that the epidemiological methods most commonly used can be improved upon. When analysing geographical data it is necessary to consider location. The most obvious quantification of location is ranked distance, though other measures which may be more meaningful in relation to aetiology may be substituted. A test based on distance ranks, the "Poisson maximum test", depends on the maximum of observed relative risk in regions of increasing size, but with significance level adjusted for selection. Applying this test to data from Sellafield and Sizewell shows that the excess of leukaemia incidence observed at Seascale, near Sellafield, is not an artefact due to data selection by region, and that the excess probably results from a genuine, if as yet unidentified cause (there being little evidence of any other locational association once the Seascale cases have been removed). So far as Sizewell is concerned, geographical proximity to the nuclear power station does not seem particularly important. PMID:2592896

  10. 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)

  11. 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

  12. 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

  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. 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...

  15. 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

  16. 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

  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. 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

  19. 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)

  20. Determining the cost of nuclear technology dismantling - software to quantify the costs of clean dismantling of nuclear installations

    International Nuclear Information System (INIS)

    Division ENERGOPROJEKT PRAHA processes within the group UJV Rez, a.s. complex pre-project and project preparation works in the nuclear field. Division prepares studies and documentation necessary for the customer's decision making (feasibility studies, business plans, building plans, etc.), preparatory, conceptual and project documentation), including related engineering services. Further safety documentation processes at all levels and documentation of the evaluation of environmental impact (EIA). In the area of a decommissioning process complete alternate design studies and design documentations of a decommissioning of NPPs in order to choose suitable variant of solution. An important area is the financing of the decommissioning process, creation of financial reserves, the input data to create a cost estimate and methodology for cost estimate. Quantifying the cost demands of the decommissioning process throughout the life cycle is composed of individual cost items for individual decommissioning activities. These also include determining the amount of costs necessary for removing uncontaminated or decontaminated process equipment. In the division ENERGOPROJEKT PRAHA was created software DEMONDEC for the estimation of these costs, which is based on the assumption that the costs to be incurred for dismantling of the above technological nuclear installation, it can be derived from the performance indicators when removing analogue equipment and systems that are part of common industrial buildings. (authors)

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

    Energy Technology Data Exchange (ETDEWEB)

    Mahrenholtz, Philipp, E-mail: philipp@mahrenholtz.net; Eligehausen, Rolf

    2015-06-15

    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.

  2. 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)

  3. 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

  4. 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)

  5. 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

  6. 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

  7. 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)

  8. 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)

  9. 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.)

  10. 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

  11. 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.

  12. 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

  13. 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

  14. 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

  15. 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)

  16. 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).

  17. 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

  18. 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

  19. 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)

  20. 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

  1. 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

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

    International Nuclear Information System (INIS)

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

  3. 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

  4. 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)

  5. 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

  6. 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

  7. 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

  8. 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.

  9. 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

  10. 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

  11. 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)

  12. 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)

  13. 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.

  14. 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

  15. 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.)

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

    International Nuclear Information System (INIS)

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

  18. 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

  19. 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.

  20. 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...

  1. 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

  2. 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

  3. 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

  4. 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)

  5. 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

  6. 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

  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. 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

  9. 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.

  10. 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

  11. 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

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

    Energy Technology Data Exchange (ETDEWEB)

    Gilli, Ludivine; Charron, Sylvie [Institut de Radioprotection et de Surete Nucleaire (IRSN), Fontenay-aux-Roses (France)

    2012-07-01

    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)

  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. 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.

  15. 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

  16. 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.

  17. 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)

  18. 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

  19. 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

  20. 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.

  1. [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

  2. 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.

  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. 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)

  5. 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.)

  6. 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

  7. 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

  8. 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.)

  9. 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.)

  10. 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

  11. ATPu installation - INB 32: complementary safety evaluation in the light of the Fukushima Daiichi nuclear power station accident

    International Nuclear Information System (INIS)

    This report proposes a complementary safety evaluation of the ATPu installation (the Plutonium technology workshop, INB 32) in Cadarache, one of the French basic nuclear installations (BNI, in French INB) in the light of the Fukushima accident. This evaluation takes the following risks into account: risks of flooding, earthquake, loss of power supply and loss of cooling, in addition to operational management of accident situations. It presents some characteristics of the installation (brief description, activities, hazardous and radioactive products, specific risks), identifies the risks of cliff effect and the main structures and equipment, evaluates the seismic risk (installation sizing, installation conformity, margin evaluation), evaluates the flooding risk (installation sizing, installation conformity, margin evaluation), briefly examines other extreme natural phenomena (extreme events, combination of events, risk related to dam failure due to an earthquake). It analyzes the risk of a loss of power supply and of cooling (loss of external and internal electric sources, loss of the ultimate cooling system). It analyzes the management of severe accidents: crisis management organization, available intervention means, robustness of available means. It discusses the conditions of the use of subcontractors

  12. 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)

  13. 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

  14. 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.

  15. 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)

  16. 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)

  17. 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.

  18. 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)

  19. 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)

  20. 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

  1. 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

  2. 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

  3. 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

  4. 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

  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. 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

  7. Compressed Natural Gas Installation. A Video-Based Training Program for Vehicle Conversion. Instructor's Edition.

    Science.gov (United States)

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

    This instructor's guide contains the materials required to teach four competency-based course units of instruction in installing compressed natural gas (CNG) systems in motor vehicles. It is designed to accompany an instructional videotape (not included) on CNG installation. The following competencies are covered in the four instructional units:…

  8. 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

  9. 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

  10. 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

  11. 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)

  12. Release of radioisotopes and activated materials from nuclear installations and facilities

    Energy Technology Data Exchange (ETDEWEB)

    Manfredi, P.F.; Millaud, J. E.

    2001-11-21

    This report discusses the problems of release of items from facilities and installations where radiation-based activities have been carried out. Several situations are reviewed and their release problems are discussed in detail. Particular attention is devoted to the assessment of the activity of the items to be released. A correct assessment of the activity will help the decision about the final use of the items removed from the radiation-related facility, either re-use, entering the public market, recycling, disposal and storage under different procedures. Even the final destination of the building which hosted the facility needs to be decided on the basis of an accurate assessment of the residual activity. The assessment of the activity, besides being fundamental in guaranteeing a safe approach to the procedures related to the release may result in a substantial profit. This is the case of items whose level of activity is so low that they can be put on the public market, reused or recycled for final product subject to very stringent radiation safety requirements. It will be shown that detector techniques play a fundamental role in the release process. In particular, the low-level counting techniques are fundamental in establishing whether or not the unrestrained release is feasible or not.

  13. 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)

  14. 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

  15. Measurements of photon spectra in mixed fields at a nuclear installation

    CERN Document Server

    Drake, P; Ljungberg, M

    2002-01-01

    This paper describes the measurements of photon spectra in mixed neutron/photon radiation fields at a few locations in a nuclear reactor. The measurements were performed inside the containment of reactor 4 at the Swedish reactor site Ringhals, with a Ge-detector (4%). The measurements were carried out as a part of a EURADOS project in co-operation with the Swedish and the reactor operating company. The measurements showed that a large fraction of the photons are high-energy photons (up to 7.6 MeV). This implies that GM-based photon detectors will overread in these fields since this type of detector generally overestimates the ambient dose equivalent in 6-7 MeV photon fields. The measurements also indicated that the photon field was almost isotropic, which in turn implies that the effective dose as well as the personal dose equivalent will be lower than the ambient dose equivalent.

  16. 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

  17. [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

  18. 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

  19. 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)

  20. 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

  1. 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.

  2. 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.)

  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. [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

  5. 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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2009-07-01

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

  7. 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. [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

  9. 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)

  10. 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

  11. 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

  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. 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

  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. 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)

  16. On the reliability of fire detection and alarm systems. Exploration and analysis of data from nuclear and non-nuclear installations

    Energy Technology Data Exchange (ETDEWEB)

    Nyyssoenen, T.; Rajakko, J.; Keski-Rahkonen, O. [VTT Building and Transport, Espoo (Finland)

    2005-01-01

    A literature review of reliability data of fire detection and alarm systems was made resulting to rough estimates of some failure frequencies. No theoretical or technical articles on the structure of reliability models of these installations were found. Inspection records of fire detection and alarm system installations by SPEK were studied, and transferred in electronic data base classifying observed failures in failure modes (59) and severity categories (3) guided by freely written records in the original data. The results of that work are presented without many comments in tabular form in this paper. A small sample of installations was collected, and number of components in them was counted to derive some distributions for determination of national populations of various components based on know total amount of installations. From NPPs (Loviisa, Olkiluoto and Barsebaeck) failure reports were analysed, and observed failures of fire detection and alarm systems were classified by severity and detection mode. They are presented here in tabular form for the original and new addressable systems. Populations were counted individually, but for all installations needed documents were not available. Therefore, presented failure frequencies are just first estimates, which will be refined later. (orig.)

  17. 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

  18. Nuclear

    International Nuclear Information System (INIS)

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

  19. 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.)

  20. 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

  1. 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

  2. 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)

  3. 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

  4. 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.)

  5. Calibration of burnup monitor of spent nuclear fuel installed at Rokkasho reprocessing plant

    Energy Technology Data Exchange (ETDEWEB)

    Oeda, Kaoru; Matoba, Masaru; Wakabayashi, Genichiro [Kyushu Univ., Fukuoka (Japan). Faculty of Engineering; Naito, Hirofumi; Hirota, Masanari [Nuclear Fuel Industries Ltd., Tokyo (Japan); Morizaki, Hidetoshi; Kumanomido, Hironori; Natsume, Koichiro [Toshiba Corp., Tokyo (Japan)

    2001-05-01

    The spent nuclear fuel storage pool of Rokkasho reprocessing plant adopts the burnup credit' conception. Spent fuel assemblies are measured every one by one, by burnup monitors, and stored to a storage rack which is designed with specified residual enrichment. For nuclear criticality control, it is necessary for the burnup monitor that the measured value includes a kind of margin, which consists of errors of the monitor. In this paper, we describe the error of the burnup monitors, and the way of taking of the margin. From the result of calibration of the burnup monitor carried out from July through November, 1999, we describe that the way of taking of the margin is validated. And comments about possibility of error reduction are remarked. (author)

  6. 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

  7. 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)

  8. 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)

  9. 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)

  10. 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.)

  11. 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

  12. 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

  13. 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)

  14. 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

  15. 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.)

  16. Licensing systems and inspection of nuclear installations in NEA Member countries. Part 1, Description of licensing systems

    International Nuclear Information System (INIS)

    This study provides an assessment of the legislative and regulatory provisions applicable and of the practices followed in the countries concerned and is divided into two separate sections. This document is the first part only. It contains the description of national licensing and inspection systems for nuclear installations in the twenty OECD countries which have specific regulations in this field. Each analysis has been presented following a plan which is as standardised as possible so as to facilitate comparison between the national systems. Part II, which is not included in this document, contains the diagrams illustrating the steps in the licensing procedure and the duties of the bodies involved as well as certain additional documents. It also includes a table showing the sequence of the main steps in the licensing process in the countries covered by this Study

  17. Determination of the standards of the thermo-physiological tolerance for working in basic nuclear installation in TIVA protective clothing

    International Nuclear Information System (INIS)

    The purpose of this study was to determine the duration limited exposure (DLE) for working in a contaminated zone in a basic nuclear installation using the new ventilated TIVA protective clothing. Five subjects underwent a treadmill exercise (3.5 km/h, 3% of slope) of up to 2 h in a climatic chamber at 25, 35, and 45 deg. C. Cardiac frequency, rectal temperature and skin temperature were continuously recorded. The dehydration level was measured by the loss of weight during the exercise. At 25 deg. C, thermal and cardiovascular thresholds are not reached; the risk is dehydration if the exercise is prolonged. In contrast, the thresholds for Tre at 39 deg. C (97 ± 29 and 69 ± 28 min for 35 and 45 deg. C, respectively) and for the increase in Tre (+1.5 deg. C) are reached earlier (84 ± 38 min and 57 ± 21 min at 35 and 45 deg. C, respectively). This leads to a higher heat storage (42.2 ± 22.9 W/m2 and 63.7 ± 29.4 W/m2, at 35 and 45 deg. C, respectively), which constitutes a higher risk of heat illnesses. The dehydration level is 2% of the weight for the tests at 35 and 45 deg. C. As a consequence, DLE for working in a contaminated zone in a basic nuclear installation in environmental conditions and using the new ventilated TIVA protective clothing, as encountered in our experiments, are proposed to avoid hyperthermic accidents. (authors)

  18. Methods for volume reduction and recycling of LLW arising from decommissioning of nuclear installations

    International Nuclear Information System (INIS)

    Radioactive contaminated waste is a great cost factor for nuclear power plants and other nuclear industry. On the deregulated electricity market the price of produced kWh is an important competition tool. Therefore many power producers in the process to achieve savings and hence low production costs have given waste minimization and volume reduction highest priority. Studsvik RadWaste AB in Nykoeping, Sweden, is successfully providing incineration and scrap metal treatment services for customers from Europe, Japan and the USA. Since 1987 thousands of tonnes of metal have been released for unrestricted re-use and recycling in commercial steel industry. The incineration service, provided since 1976, results in 97% volume reduction and generates biologically inert ash suitable for disposal in a final radioactive waste repository. Both processes, which are quality and environmentally certified, reduce the cost of interim storage and disposal. In addition, the companies within the Studsvik Group offer a wide range of services such as transportation, measurement and safeguard, site assistance, industrial cleaning and decontamination in connection with demolition on site. (authors)

  19. Regulatory oversight report 2009 concerning nuclear safety in Swiss nuclear installations; Aufsichtsbericht 2009 zur nuklearen Sicherheit in den schweizerischen Kernanlagen/Rapport de surveillance 2009 sur la securite nucleaire dans les installations nucleaires en Suisse/Regulatory oversight report 2009 concerning nuclear safety in Swiss nuclear installations

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2010-04-15

    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

  20. Dynamic Analysis of Nuclear Waste Generation Based on Nuclear Fuel Cycle Transition Scenarios

    Energy Technology Data Exchange (ETDEWEB)

    Yoon, S. R. [University of Science and Technology, Daejeon (Korea, Republic of); Ko, W. I. [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2015-10-15

    According to the recommendations submitted by the Public Engagement Commission on Spent Nuclear Fuel Management (PECOS), the government was advised to pick the site for an underground laboratory and interim storage facilities before the end of 2020 followed by the related research for permanent and underground disposal of spent fuel after 10 years. In the middle of the main issues, the factors of environmentally friendly and safe way to handle nuclear waste are inextricable from nuclear power generating nation to ensure the sustainability of nuclear power. For this purposes, the closed nuclear fuel cycle has been developed regarding deep geological disposal, pyroprocessing, and burner type sodium-cooled fast reactors (SFRs) in Korea. Among two methods of an equilibrium model and a dynamic model generally used for screening nuclear fuel cycle system, the dynamic model is more appropriate to envisage country-specific environment with the transition phase in the long term and significant to estimate meaningful impacts based on the timedependent behavior of harmful wastes. This study aims at analyzing the spent nuclear fuel generation based on the long-term nuclear fuel cycle transition scenarios considered at up-to-date country specific conditions and comparing long term advantages of the developed nuclear fuel cycle option between once-through cycle and Pyro-SFR cycle. In this study, a dynamic analysis was carried out to estimate the long-term projection of nuclear electricity generation, installed capacity, spent nuclear fuel arising in different fuel cycle scenarios based on the up-to-date national energy plans.

  1. Seismic hazard analysis of nuclear installations in France. Current practice and research

    Energy Technology Data Exchange (ETDEWEB)

    Mohammadioun, B. [CEA Centre d`Etudes de Fontenay-aux-Roses, 92 (France). Inst. de Protection et de Surete Nucleaire

    1997-03-01

    The methodology put into practice in France for the evaluation of seismic hazard on the sites of nuclear facilities is founded on data assembled country-wide over the past 15 years, in geology, geophysics and seismology. It is appropriate to the regional seismotectonic context (interplate), characterized notably by diffuse seismicity. Extensive use is made of information drawn from historical seismicity. The regulatory practice described in the RFS I.2.c is reexamined periodically and is subject to up-dating so as to take advantage of new earthquake data and of the results gained from research work. Acquisition of the basic data, such as the identification of active faults and the quantification of site effect, which will be needed to achieve improved preparedness versus severe earthquake hazard in the 21st century, will necessarily be the fruit of close international cooperation and collaboration, which should accordingly be actively promoted. (J.P.N.)

  2. Process of Judging Significant Modifications for Different Transportation Systems compared to the Approach for Nuclear Installations

    Directory of Open Access Journals (Sweden)

    Nicolas Petrek

    2015-12-01

    Full Text Available The implementation of the CSM regulation by the European Commission in 2009 which harmonizes the risk assessment process and introduces a rather new concept of judging changes within the European railway industry. This circumstance has risen the question how other technology sectors handle the aspect of modifications and alterations. The paper discusses the approaches for judging the significance of modifications within the three transport sectors of European railways, aviation and maritime transportation and the procedure which is used in the area of nuclear safety. We will outline the similarities and differences between these four methods and discuss the underlying reasons. Finally, we will take into account the role of the European legislator and the fundamental idea of a harmonization of the different approaches.

  3. Study and installation of concrete shielding in the civil engineering of nuclear construction (1960)

    International Nuclear Information System (INIS)

    The object of this report is to give technical information about high density concretes which have become very important for radiation biological shielding. The most generally used heavy aggregates (barytes, ilmenite, ferrophosphorus, limonite, magnetite and iron punching) to make these concretes are investigated from the point of view prospecting and physical and chemical characteristics. At first, a general survey of shielding concretes is made involving the study of components, mixing and placing methods, then, a detailed investigation of some high density concretes: barytes concrete, with incorporation of iron punching or iron shot, ferrophosphorus concrete, ilmenite concrete and magnetite concrete, more particularly with regard to grading and mix proportions and testing process. To put this survey in concrete form, two practical designs are described such as they have been carried out at the Saclay Nuclear Station. Specifications are given for diverse concretes and for making the proton-synchrotron 'Saturne' shielding blocks. (author)

  4. Leukaemia among persons under 25 years old living near nuclear installations, in France and abroad: review of epidemiologic descriptive studies

    International Nuclear Information System (INIS)

    Starting in 1984, many epidemiologic studies have analyzed the risk of leukemia among young people aged 0-24 years living near nuclear sites principally in Great Britain, but also in the United States, Canada, France, Germany, Sweden, Israel, and Japan. Local studies have observed abnormally high concentrations of leukemia cases near nuclear sites, especially near the Sellafield and Dounreay reprocessing plants in Great Britain. More recently, and excess of leukemia cases has been observed among the 0-14 year-old near the Kruemmel nuclear power plant in Germany. All these studies are based on very low numbers of cases. In parallel, extensive studies considering several sites simultaneously have been carried out. The conclusions do not suggest that the frequency of leukemia among young people is higher near nuclear sites than elsewhere. Clusters of leukemia cases have also been observed in zones far from any nuclear site. In France, some studies have been conducted around the La Hague and Marcoule nuclear sites, and two multi-sites mortality studies have been performed. Their results do not indicate the existence of a significant excess of leukemia cases among young people around any nuclear plant in France. (author)

  5. Philippine Bases and U.S. Nuclear Weapons Policy

    OpenAIRE

    Schirmer, Daniel Boone

    1983-01-01

    In 1947, when the newly independent Philippine government granted the United States the right to use military bases at Subic Bay and Clark Air Field, the United States government saw to it that the terms included the right of the U.S. to install on these bases "any type of weapons." From the very beginning the Pentagon insisted on establishing the right to relate U.S. bases in the Philippines to possible plans for nuclear war. Also, from the very beginning many Filipinos opposed U.S. bases th...

  6. Virtual reality technology used to estimate radiation doses in nuclear installations

    International Nuclear Information System (INIS)

    The physical integrity of people when walking in places subjected to radiation can be preserved by following some rules. Among these rules are safe limits of radiation level, proximity of radiation sources, time of exposition to radiation sources, and a combination of these factors. In this way, previous training and simulations of operation proceedings to be executed in places subjected to radiation help to better prepare the course in such places, minimizing the absorbed dose. On the other hand, virtual reality is a technology applicable in several areas, enabling the training and simulation of real places and hypothetical scenarios, with a good level of realism, but without danger if compared to the same activities in the real world. As a virtual environment does not presents any health risks, it is possible to train workers beforehand to several operation or maintenance scenarios. In this virtual environment, the dose tax distribution can be visualized, and the dose absorbed by the worker, represented and simulated in the virtual environment by a virtual character (avatar) can be shown. Therefore, the tasks to be done can be better planned, evaluating the workers actions and the performance so to reduce failures and health risks. Finally, this work presents a tool to build and navigate in virtual environments, enabling the training of activities in nuclear facilities. To that end is proposed a methodology to modify and adapt a free game engine. (author)

  7. A structured approach to the assessment of the quality culture in nuclear installation

    International Nuclear Information System (INIS)

    INSAG has emphasized that safety culture has two general components: the organizational framework and the attitude of the staff. To develop a structured approach to the assessment of safety culture, we propose that the highly formalized nature of nuclear power plant organizations be exploited. The prime coordinating mechanism of NPP organizations is the standardization of work processes, where a work process is defined as a standardized sequence of tasks designed to achieve a specific goal (an example is the maintenance work process). The predictable nature of work processes is exploited by the Work Process Analysis Model (WPAM) to conduct a systematic analysis that identifies the desirable characteristics of work processes and develops performance measures for their strengths and weaknesses. These can provide a set of tangible characteristics of a good safety culture. It is argued in this paper that the analysis of normal power production and investment protection and the analysis of safety cannot be separated when culture is investigated. The organizational dependencies are too strong for such a division. It is proposed that the plant should be viewed as an integrated sociotechnical system and that the broader concept of quality culture should replace the more limited one of safety culture. (author)

  8. The installation of the defective identification device for irradiated fuel in nuclear power plant

    International Nuclear Information System (INIS)

    The sipping test devices are used to identify the defective fuel. The defective fuel can be identified by detecting the occurrence of the fission products entrained by the medium rising around the fuel rods. There are two kinds of sipping test device to inspect the tightness of the irradiated fuel assembly from nuclear power plant (NPP). The in-mast sipping taking the mast as the isolator, the air as the medium, and the Xe 133 as the indication nuclide is used for qualitative tightness test of each fuel assembly during refueling operation above the reactor. The poolside sipping taking the sipping cell as the isolator, the air and water as the medium is used for quantitative confirming the diagnosis of the in-mast sipping and identifying the tightness of the fuel at the side of the fuel storage pool after refueling. The design manufacture and calibration of three devices were successfully completed domestically step by step with serious quality assurance and quality control. (author)

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

    Directory of Open Access Journals (Sweden)

    Ioannis Zafeiropoulos

    2009-12-01

    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.

  10. 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.

  11. Order of the 4 March 2014 on the homologation of the decision nr 2014-DC-4016 of the Nuclear Safety Authority of the 16 January 2014 defining the limits of releases in the environment of liquid and gaseous effluents by the basic nuclear installations nr 124, 125, 126 and 137 exploited by EDF-SA in Cattenom (Moselle district)

    International Nuclear Information System (INIS)

    This order issued by the French Ministry of ecology, sustainable development and energy is based on a decision taken by the ASN. It concerns the management of pollutions and of the impact of a nuclear installation on the environment: applicable limits of gaseous (notably carbon 14, tritium, rare gases, iodines), chemical, and liquid effluent release. Tables indicate the maximum concentrations

  12. 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.

  13. Nuclear reactions video (knowledge base on low energy nuclear physics)

    International Nuclear Information System (INIS)

    The NRV (nuclear reactions video) is an open and permanently extended global system of management and graphical representation of nuclear data and video-graphic computer simulation of low energy nuclear dynamics. It consists of a complete and renewed nuclear database and well known theoretical models of low energy nuclear reactions altogether forming the 'low energy nuclear knowledge base'. The NRV solves two main problems: 1) fast and visualized obtaining and processing experimental data on nuclear structure and nuclear reactions; 2) possibility for any inexperienced user to analyze experimental data within reliable commonly used models of nuclear dynamics. The system is based on the realization of the following principal things: the net and code compatibility with the main existing nuclear databases; maximal simplicity in handling: extended menu, friendly graphical interface, hypertext description of the models, and so on; maximal visualization of input data, dynamics of studied processes and final results by means of real three-dimensional images, plots, tables and formulas and a three-dimensional animation. All the codes are composed as the real Windows applications and work under Windows 95/NT

  14. A risk based approach to re-assessment of existing North Sea installations

    Energy Technology Data Exchange (ETDEWEB)

    Sharp, J.V.; Kam, J.C.; Birkinshaw, M. [Health and Safety Executive, London (United Kingdom). Offshore Safety Div.

    1995-12-31

    Reassessment of installations on the UK Continental Shelf is an important control measure in assuring continuing structural integrity. At present this is achieved via the certification process. Risk based regulations have now been introduced requiring a safety case for each installation; these will be supported by the introduction of additional regulations. Preparation of the safety case requires the identification of major accidental hazards and a demonstration of how the associated risks are to be controlled. Structures installed some time ago have been designed to codes and standards, for which the design requirements may have since changed as a result of more data becoming available. Examples are given for both the static and fatigue strength of tubular joints. Other important factors include the design wave height and the air gap. System behavior and reserve strength are important in justifying performance and an acceptance criterion for reserve strength is included in the draft section 17. Recent HSE studies on benchmarking pushover type software have shown that current industry practice can lead to significant variations in prediction of reserve strength. The key factors required for a risk based approach to reassessment are discussed, associated with the need that the structural integrity should be maintained through the life cycle to a level that the risks to personnel are as low as reasonably practicable.

  15. 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.

  16. Research into the melting/refining of contaminated steel scrap arising in the dismantling of nuclear installations

    International Nuclear Information System (INIS)

    The main part of this report is concerned with the steel-making behaviour of various radioisotopes encountered in steel from decommissioning of nuclear installations (e.g. cobalt 60, caesium 134 and europium 154). Under a wide range of conditions cobalt is largely absorbed by the steel, europium is absorbed by the slag, whereas caesium may be largely volatized, or largely absorbed by the slag. Radiation exposures which might occur during a large-scale recycling operation, during routine operations and accidents would not be significant according to published criteria in the UK. The second part of the report concerns the detection of radioactive materials which may be accidentally delivered to steelworks in scrap steel and used in steel-making. Detectors have been developed which would indicate the presence of radioactivity in scrap. A survey of the steelworks revealed areas where detection might be performed. Experiments have shown that a gamma ray detector of large volume could provide useful sensitivity of detection

  17. Method and means for in situ repair of heat exchanger tubes in nuclear installations or the like

    International Nuclear Information System (INIS)

    A method of sealing leaky heat exchanger tubes in situ in nuclear installations is described which consists of the steps of: providing a sleeve having an outer diameter slightly larger than the inner diameter of the tube whose leak is to be sealed and having a length shorter than the length of the tube yet sufficient to overlap the leak and having a flange at one end thereof, the flange being dimensioned larger than the inner diameter of the tube for limiting insertion of the sleeve into the tube; cooling the sleeve to a temperature at which its outer diameter is sufficiently reduced to allow insertion of the sleeve into the tube; inserting the cooled sleeve into the tube to be sealed through one end of the tube to overlap the leaky portion while the sleeve is so cooled until the insertion is limited by the flange; allowing the sleeve to warm up to the temperature of the tube; the sleeve being open at both ends such that fluids flowing through the heat exchanger tube flow through the sleeve also; and guiding the sleeve into position for insertion by means of a guide fabricated of material which is solid at insertion temperatures but becomes fluid at room temperature, and allowing the guide to become fluid when the insertion of the sleeve is complete, whereby the sleeve forms with the inside of the tube in the region of the leak a leak-proof sealing bond with a generally uniform hoop stress thereby repairing the leak

  18. Using a very low level radioactive steel from decommissioning of nuclear installation for the construction of railway structures

    International Nuclear Information System (INIS)

    During the operation, but especially during decommissioning (SW) of operation, there is a large amount of radioactive waste, whose activity only slightly exceeds the limits for unrestricted use, or for the unconditional release into the environment. In particular, metal and concrete debris. Processing, treatment and disposal of such waste would require considerable funds, and also storage space would be quickly filled up. A convenient way to use a large number of low-activity materials seems to be conditional release, which will reuse the materials for a particular purpose. The paper deals with use of a very low level of steel from decommissioning of nuclear installations for construction of the railway bridge. The task of the present paper is to review the impact of conditionally released steel on population and to determine what level of mass activity of the steel meets the limits prescribed by law. For impact assessment of conditionally released steel on population there was selected computing resource VISIPLAN 3D ALARA Planning Tool. (author)

  19. Energy efficiency of electric pulse installation based on a high-current plasma accelerator

    Directory of Open Access Journals (Sweden)

    Shanenkov I.I.

    2014-01-01

    Full Text Available The energy efficiency of electric pulse installation based on a high-current plasma accelerator was investigated. A series of experiments with different central electrodes was carried out. The system based on carbon electrodes has a greater value of the charge energy conversion into the energy of arc discharge and the less discharge current level in comparison with other electrode systems. The power consumption value for producing 1 gram of powdered product was estimated and it was found this value is comparable to the work of the LED light bulb for 1 hour.

  20. Nuclear Power Plants Shutdown and Alternative Power Plants Installation: A nine-region spatial equilibrium analysis of the electric power market in Japan

    OpenAIRE

    HOSOE Nobuhiro

    2014-01-01

    After the Great East Japan Earthquake and the subsequent nuclear accident, nuclear power stations no longer can be presumed to be perfectly safe and thus hardly can be allowed to restart in Japan. In this study, we develop a nine-region spatial equilibrium model of the Japanese power market and simulate two-part situations: (a) none of the nuclear power plants can operate any longer and (b) gas turbine combined cycle (GTCC) power plants are installed to fully cover the lost capacity of the nu...

  1. Safety of nuclear installations

    International Nuclear Information System (INIS)

    The safety philosophy of a PWR type reactor distinguishing three levels of safety, is presented. At the first level, the concept of reactivity defining coefficients which measure the reactivity variation is introduced. At the second level, the reactor protection system establishing the design criteria to assure the high reliability, is defined. At the third level, the protection barriers to contain the consequences of accident evolution, are defined. (M.C.K.)

  2. Feasibility study of installing a thermal to 14 MeV neutron converter into a research nuclear reactor

    International Nuclear Information System (INIS)

    A deuterium-tritium (DT) based thermal-to-fast neutron converter will be installed into the TRIGA reactor at Jozef Stefan Institute. This paper presents preliminary results of a feasibility study where different aspects have been addressed. The thermal column is the most appropriate irradiation position for the DT converter in the reactor. From potential active converter materials, LiD yields the most 14 MeV neutrons. Lithium enrichment affects the required thickness of the active converter material, but not significantly the 14 MeV neutron yield. For coupled neutron-tritium transport calculations, the modified MCUNED code was used. Relevant DT neutron activation monitor materials for spectrum unfolding have been identified and neutron flux criteria established. (author)

  3. Construction, fabrication, and installation

    International Nuclear Information System (INIS)

    This standard specifies the construction, fabrication, and installation requirements that apply to concrete containment structures of a containment system designated as class containment components, parts and appurtenances for nuclear power plants

  4. Status of Nuclear Safety Culture Through Lessons Learnt from Licensing, Periodic Safety Review and Relicensing of Activities at Nuclear Research Installations in Russian Federation

    International Nuclear Information System (INIS)

    Russian Federation (Russia) has a lot of Nuclear Research Installations (NRIs) of various types and powers for the fundamental and applied sciences in the field of physics, power engineering, material study, biology and medicine. The work is been carried out to optimize the Russian fleet of NRIs, depending on the science and atomic energy needs. Due to the reduction of NRIs in operation in the world the experimental abilities of Russian NRIs as well as their safety conditions, to be in compliance with up-to-date safety requirements, represent the certain interest both to European region and international collaboration as a whole. The effective system for safety regulation in the field of atomic energy use has been established at present in Russia and is being improved. The legal basis and principles of regulation of relations arising in atomic energy use have been put in force at the state level taking into consideration fundamental principles of nuclear law adopted in practice worldwide. The report outlines the results and lessons learnt from licensing of NRIs in Russia as a continuous process having a few stages during the lifetime of a NRI. Enhancement of nuclear and radiation safety and security of NRIs in operation is pointed out at the initial licensing stage in the past, when no sound technical requirements and reference licensing basis were available, and then as a result of further safety evaluations and re-licensing. Through lessons learnt from licensing of NRIs the principal findings are summarized on the safety status of NRIs in Russia and further evaluation of their safety. A sound legal framework, well arranged licensing process and supervision, also scientific and technical support and other advisory organizations can help enhance nuclear safety culture because the activities at NRIs include various aspects related to safety: legal, administrative, technical, economical, ecological, informational, social and even psychological. There exist a few

  5. Nuclear safety in France after Fukushima - Critical analysis of complementary safety assessments (CSA) carried out on French nuclear installations after Fukushima

    International Nuclear Information System (INIS)

    This report proposes a critical analysis of the approach carried out on the basis of the CSA (complementary safety assessment), from their specifications to the IRSN conclusions. It is notably based on the analysis performed by EDF on three nuclear sites (Gravelines, Civaux and Flamanville) which encompass the different levels of the nuclear power plants in France and the EPR project under construction, and on the analysis performed by Areva for La Hague reprocessing plants. Due to the short delay, only some sites and some problems have been considered. The CSA methodology is described. The EDF approach is discussed as well as the IRSN analysis of reports made by EDF, and then the different case studies. Beyond the conclusions of these reports, the authors highlight several major possible accidents which must be taken into account. They also outline that this CSA approach is a good starting point for the strengthening of nuclear safety

  6. Decree of January 11, 2016 bearing homologation of the decision nr 2015-DC-0536 by the Nuclear Safety Authority of December 22, 2015 defining threshold values of releases in the environment of liquid and gaseous effluents from base nuclear installations nr 33 (UP2-400), 38 (STE2 et AT1), 47 (ELAN II B), 80 (HAO), 116 (UP3-A), 117 (UP2-800) and 118 (STE3 effluent processing station) exploited by AREVA NC on the La Hague site (Manche district)

    International Nuclear Information System (INIS)

    After having mentioned the various related and reference legal texts, this legal publication specifies the various threshold values which must be applied to liquid and gaseous releases of nuclear installations located in La Hague for a better control and management of pollutions and of the impact of these installations on the environment. Threshold values are thus specified for various compounds and species, and the document also mentions AREVA's publications which indicate the actual release levels and state that these levels are within the accepted limits

  7. Digital Full-Scope Simulation of a Conventional Nuclear Power Plant Control Room, Phase 2: Installation of a Reconfigurable Simulator to Support Nuclear Plant Sustainability

    Energy Technology Data Exchange (ETDEWEB)

    Ronald L. Boring; Vivek Agarwal; Kirk Fitzgerald; Jacques Hugo; Bruce Hallbert

    2013-03-01

    The U.S. Department of Energy’s Light Water Reactor Sustainability program has developed a control room simulator in support of control room modernization at nuclear power plants in the U.S. This report highlights the recent completion of this reconfigurable, full-scale, full-scope control room simulator buildout at the Idaho National Laboratory. The simulator is fully reconfigurable, meaning it supports multiple plant models developed by different simulator vendors. The simulator is full-scale, using glasstop virtual panels to display the analog control boards found at current plants. The present installation features 15 glasstop panels, uniquely achieving a complete control room representation. The simulator is also full-scope, meaning it uses the same plant models used for training simulators at actual plants. Unlike in the plant training simulators, the deployment on glasstop panels allows a high degree of customization of the panels, allowing the simulator to be used for research on the design of new digital control systems for control room modernization. This report includes separate sections discussing the glasstop panels, their layout to mimic control rooms at actual plants, technical details on creating a multi-plant and multi-vendor reconfigurable simulator, and current efforts to support control room modernization at U.S. utilities. The glasstop simulator provides an ideal testbed for prototyping and validating new control room concepts. Equally importantly, it is helping create a standardized and vetted human factors engineering process that can be used across the nuclear industry to ensure control room upgrades maintain and even improve current reliability and safety.

  8. Methodology for the Systematic Assessment of the Regulatory Competence Needs (SARCoN) for Regulatory Bodies of Nuclear Installations

    International Nuclear Information System (INIS)

    A regulatory body’s competence is dependent, among other things, on the competence of its staff. A necessary, but not sufficient, condition for a regulatory body to be competent is that its staff can perform the tasks related to the functions of the regulatory body. In 2001, the IAEA published TECDOC 1254, Training the Staff of the Regulatory Body for Nuclear Facilities: A Competency Framework, which examines the manner in which the recognized regulatory functions of a nuclear regulatory body results in competence needs. Using the internationally recognized systematic approach to training, TECDOC 1254 provides a framework for regulatory bodies for managing training and developing, and maintaining the competence of its staff. It has been successfully used by many regulatory bodies all over the world, including States embarking on a nuclear power programme. The IAEA has also introduced a methodology and an assessment tool — Guidelines for Systematic Assessment of Regulatory Competence Needs (SARCoN) — which provides practical guidance on analysing the training and development needs of a regulatory body and, through a gap analysis, guidance on establishing competence needs and how to meet them. In 2013, the IAEA published Safety Reports Series No. 79, Managing Regulatory Body Competence, which provides generic guidance based on IAEA safety requirements in the development of a competence management system within a regulatory body’s integrated management system. An appendix in the Safety Report deals with the special case of building up the competence of regulatory bodies as part of the overall process of establishing an embarking State’s regulatory system. This publication provides guidance for the analysis of required and existing competences to identify those required by the regulatory body to perform its functions and therefore associated needs for acquiring competences. Hence, it is equally applicable to the needs of States embarking on nuclear power

  9. Physical and toxic properties of hazardous chemicals regularly stored and transported in the vicinity of nuclear installations

    International Nuclear Information System (INIS)

    This report gives a compilation of data based on information assembled by the US Nuclear Regulatory Commission and completed by the Safety and Reliability Directorate of the UK AEA, the Dutch Reactor Safety Commission, the French Atomic Energy Commission, and the CSNI Secretariat. Data sheets for a large number of hazardous chemicals are presented (from acetaldehyde to xylene), giving details of their physical and toxic properties such as: molecular weight, boiling point, vapor density, heat of vaporization, toxic concentration in air, flammability limits, toxic effects, vapor pressure data, etc.

  10. The dismantling of nuclear installations and the radioactive wastes management. Report of the President of the Republic followed by the answers of concerned administrations and organisms

    International Nuclear Information System (INIS)

    The discussed subjects concerns the situation and the challenges of the nuclear installations dismantling and the radioactive wastes management (main intervenors, panorama of the situation, rules applied to the dismantling and the radioactive wastes), the first experiences of dismantling and radioactive wastes disposal (experiences at the CEA and EDF, implementing of solutions for the disposal), interrogations and certainties (provision for future expenses, public information). (A.L.B.)

  11. Evaluation of the impact and the releases of operating nuclear facilities; Evaluation de l'impact et des rejets des installations nucleaires en fonctionnement normal

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-07-01

    The monitoring of nuclear installations releases, the associated impacts evaluation and the radiation monitoring of the environment are of an increase interest since the last ten years. Theses two days, organized by the environment section of the SFRP (French Society of Radiation Protection), aim to discuss the following topics: the development of the methods to improve radioactive elements and toxic substances releases in the environment; the structure of the environment control and the objectives of this control; the association of the local actors to the releases monitoring and to the environment control; the perspectives of evolution in matter of nuclear facilities releases management. (A.L.B.)

  12. The role of the Commission for the Environmental Impact Assessment (V.I.A.) in the decommissioning of nuclear installations in Italy

    International Nuclear Information System (INIS)

    In Italy decommissioning of nuclear installation is regulated through two basic main laws: the decree-law n. 230 /1999, regarding licensing and controls procedures in nuclear field, and the Directive of European Community (97/11, 1997.3.3, published 1997.3.14). The duty of National Environmental Assessment Commission is to supply to the Ministry for Environment, the view, based on technical examination of the concerned planes and Study of Environmental Impact. Environmental Impact Assessment Commission individualise and value every, direct or indirect, effect, possible to have during the planed accomplishment of a project, particularly regarding man, fauna and flora, soil, water, air, climate and landscape, interactions between two former factors, material property, and cultural, natural and artistic patrimony. During the assessment implementation, so, in particular, are focused: Individuation of best procedures and technologies for the whole of planned operations; Identification of all possible impacts may be originated, for each actions, beyond the matter of radioprotection, like noise emissions, liquid and gaseous pollutants emissions, traffic, disturbance against natural protected areas etc.; Individuation of strategies and methods to reduce inevitable impacts; Guarantee the opportunity for the public to participate. Decommissioning of an nuclear installation in considered in the same way of a complex industrial installation decommissioning and so the evaluation is operated into three 'classic' frameworks: programmatic, plan- relative, environmental-relative. In the field of nuclear plants decommissioning, the development of the valuation of three mentioned frameworks is absolutely diverse in confront with the cases that the Commission has had in Italy as routine during several years. The programmatic framework, in fact, is very uniform because is disciplined in Italy with decree of the Ministry of Productive Activities. Local differences occur only in local

  13. Nuclear safety based on nuclear knowledge - A Romanian approach

    International Nuclear Information System (INIS)

    Full text: The recognized 'father' of the nuclear field, the scientist A. Einstein inherited us with a CONTRADICTION. On one hand he was the supporter of researches in the nuclear field, but on the other hand, when he saw the first devastating results of the atomic explosions he suddenly became a fervent opponent. In such conditions, the nuclear field made its first step in the conscience of humanity. Unfortunately it was a left first step. For this reason and also because of the nuclear incidents passed over the history of the field and due to yet unclear strategies regarding the final disposal of radioactive waste, a part of public opinion 'embraced' the concept 'NIMBY - Not In My Back Yard'. At present and for the future we have to fight against this concept in order to transform it in 'PIMY - Please In My Yard'. As a consequence, alongside numerous activities well-known by the specialists in the field, regulated and authorized by the regulatory body in the nuclear field, associated programmes for the CONTINUOUS qualification and education of human resources are needed. The Concept of Nuclear Security covers all the activities resulted from the nuclear fuel cycle. Taking into consideration the international experience in this field in our country's case, these activities were estimated for periods of approximately 70 years, as following: 10 years: the characterization and selection of the site, the design, construction and the commission of a nuclear power plant; 40 years: the operation, maintenance and modernization of a nuclear power plant; 20 years: the preservation for the decommissioning and the decommissioning of the nuclear power plant. In all these stages until present Romania based a lot on the indigene component regarding the activities of research and development, design, construction - assembling, exploitation and maintenance (both for NPP Unit 1 and Unit 2, where this component was approximately of 50%). In such conditions, it was needed the

  14. Procedure of calculation of the spatial distribution of temperatures and heat fluxes in the steam generator of a nuclear power installation with an RBEC fast-neutron reactor

    Science.gov (United States)

    Frolov, A. A.; Sedov, A. A.

    2016-08-01

    A method for combined 3D/1D-modeling of thermohydraulics of a once-through steam generator (SG) based on the joint analysis of three-dimensional thermo- and hydrodynamics of a single-phase heating coolant in the intertube space and one-dimensional thermohydraulics of steam-generating channels (tubes) with the use of well-known friction and heat-transfer correlations under various boiling conditions is discussed. This method allows one to determine the spatial distribution of temperatures and heat fluxes of heat-exchange surfaces of SGs with a single-phase heating coolant in the intertube space and with steam generation within tubes. The method was applied in the analytical investigation of typical operation of a once-through SG of a nuclear power installation with an RBEC fast-neutron heavy-metal reactor that is being designed by Kurchatov Institute in collaboration with OKB GIDROPRESS and Leipunsky Institute of Physics and Power Engineering. Flow pattern and temperature fields were obtained for the heavy-metal heating coolant in the intertube space. Nonuniformities of heating of the steam-water coolant in different heat-exchange tubes and nonuniformities in the distribution of heat fluxes at SG heat-exchange surfaces were revealed.

  15. Structural damage detection using sparse sensors installation by optimization procedure based on the modal flexibility matrix

    Science.gov (United States)

    Zare Hosseinzadeh, A.; Ghodrati Amiri, G.; Seyed Razzaghi, S. A.; Koo, K. Y.; Sung, S. H.

    2016-10-01

    This paper is aimed at presenting a novel and effective method to detect and estimate structural damage by introducing an efficient objective function which is based on Modal Assurance Criterion (MAC) and modal flexibility matrix. The main strategy in the proposed objective function relies on searching a geometrical correlation between two vectors. Democratic Particle Swarm Optimization (DPSO) algorithm, a modified version of original PSO approach, is used to minimize the objective function resulting in the assessment of damage in different structure types. Finally, the presented method is generalized for a condition in which a limited number of sensors are installed on the structure using Neumann Series Expansion-based Model Reduction (NSEMR) approach. To evaluate the efficiency of the proposed method, different damage patterns in three numerical examples of engineering structures are simulated and the proposed method is employed for damage identification. Moreover, the stability of the method is investigated by considering the effects of a number of important challenges such as effects of different locations for sensor installation, prevalent modeling errors and presence of random noises in the input data. It is followed by different comparative studies to evaluate not only the robustness of the proposed method, but also the necessity of using introduced techniques for problem solution. Finally, the applicability of the presented method in real conditions is also verified by an experimental study of a five-story shear frame on a shaking table utilizing only three sensors. All of the obtained results demonstrate that the proposed method precisely identifies damages by using only the first several modes' data, even when incomplete noisy modal data are considered as input data.

  16. Leukaemia in the vicinity of nuclear installations - a review; Leukaemiehaeufigkeit in der Umgebung kerntechnischer Anlagen - eine Uebersicht

    Energy Technology Data Exchange (ETDEWEB)

    Grosche, B. [Bundesamt fuer Strahlenschutz, Aussenstelle Oberschleissheim, Fachbereich Strahlung und Gesundheit, Oberschleissheim (Germany)

    2006-07-01

    Based on the finding of an increased leukaemia risk among young people (aged 0-24) in the small village of Seascale, south of the Sellafield reprocessing plant, a discussion started on whether there is in general an elevated number of leukaemia cases to be observed in the vicinity of nuclear power plants. An overview on existing findings leads to the conclusion that this is not the case among adults. Among children and juveniles, a slight increase can be observed, which is most pronounced among the youngest age groups in the nearest vicinity of the plants. Estimates of radiation exposures to the public make a causal relationship between the radioactive discharges and the cases implausible. Other explanations are discussed, namely that population influx into a relatively sparsely populated area, e.g. due to new industry settlements, might lead to an altered infection situation in the respective area which than causes an increased leukaemia rate. Recent results are indicative for a causative role of infections in relation to childhood leukaemias. This explanation is opposed by the finding, that elevated rates have also been observed around potential nuclear sites where there was no population influx. Overall, current findings have to be considered as not fully understood. (orig.)

  17. The Report on Activities of the Nuclear Regulatory Authority of the Slovak Republic and on Safety of Nuclear Installations in the Slovak Republic in 2011

    International Nuclear Information System (INIS)

    A brief account of activities carried out by the Nuclear Regulatory Authority of the Slovak Republic (UJD SR) in 2011 is presented. These activities are reported under the headings: Foreword; (1) Legislative activities; (2) Regulatory Activities; (3) Nuclear safety of nuclear power plants; (4) Nuclear Materials in SR; (5) Nuclear materials and physical protection of nuclear materials; (6) Scope of powers of the office building; (7) Emergency planning and preparedness; (8) International activities; (9) Public communication; (10) Nuclear Regulatory Authority of the Slovak Republic; (11) UJD SR organization chart; The International Nuclear Event Scale (INES); (12) Abbreviations.

  18. Installation and Commissioning of RCP Cartridge for Nuclear Power Stations%核电厂主泵密封系统的安装与调试

    Institute of Scientific and Technical Information of China (English)

    霍亚邦; 王玉旭

    2011-01-01

    The installation process and method for the cooling pump sealing system of CPR1000 nuclear power plant reactor is studied, and various cases occurred during the installation and commisioning of RCP sealing systems are analyzed. The scheme for flushing of the nuclear loop in the various cases is developed to provide a reference for the installation and commissioning of RCP sealing system in the coming CPR1000 project.%研究CPR1000堆型核电厂反应堆冷却剂泵(RCP)密封安装工艺流程及方法,对RCP密封系统安装和调试过程中的各种情况进行分析,制定各种情况下核回路冲洗采取的特殊处理方案,为后续CPR1000项目RCP密封系统安装调试提供参考.

  19. The Report on Activities of the Nuclear Regulatory Authority of the Slovak Republic and on Safety of Nuclear Installations in the Slovak Republic in 2010

    International Nuclear Information System (INIS)

    A brief account of activities carried out by the Nuclear Regulatory Authority of the Slovak Republic (UJD SR) in 2010 is presented. These activities are reported under the headings: Address of the Chairperson; (1) Legislative activities; (2) Issuance of authorizations, assessment, supervisory activities and enforcement; (3) Nuclear safety of nuclear power plants; (4) Nuclear materials and physical protection of nuclear materials; (5) Powers of the office building; (6) Emergency planning and preparedness; (7) International activities; (8) Public communication; (9) Nuclear Regulatory Authority of the Slovak Republic; (10) Appendix: UJD SR organization chart; The International Nuclear Event Scale (INES); Abbreviations.

  20. Decree N0 75-306 of 30 April 1975 on the protection of workers against the hazards of ionizing radiation in large nuclear installations

    International Nuclear Information System (INIS)

    This Decree supplements French regulations on radiation protection established by the Decree of 20 June 1966 on general radiation protection principles and that of 15 March 1967 on protection of workers against ionizing radiation hazards in other types of nuclear installation. This Decree refers to the provisions of the above-mentioned Decrees concerning maximum permissible dose equivalents and maximum permissible concentrations of the different radionuclides to be complied with in workplaces. It also lays down the provisions the head of the establishment must implement at administrative, technical and medical levels to ensure radiation protection in such premises. (NEA)

  1. The investigation of correspondence of indications of the albedo dosemeter DVGN-01 to personnel irradiation doses in the fields of neutron radiation at the JINR nuclear power installations

    International Nuclear Information System (INIS)

    The calculated results of the research correspondence of the indication of the individual albedo dosemeter DVGN-01 to the individual equivalent dose for neutrons Hp(10) and to the effective dose for neutrons Eeff in the neutron fields at the JINR Nuclear Power Installations (JNPI) at different geometries of irradiations are presented. It has been shown that the correction coefficients are required for specific estimation of doses by the dosemeter. The coefficients were calculated using the energy sensitivity curve of the dosemeter and the known neutron spectra at the JNPI. By using the correction factors the uncertainties of both doses would not exceed the limits given to the personnel according to standards

  2. The development of regulatory expectations for computer-based safety systems for the UK nuclear programme

    International Nuclear Information System (INIS)

    The Nuclear Installations Inspectorate (NII) of the UK's Health and Safety Executive (HSE) has completed a review of their Safety Assessment Principles (SAPs) for Nuclear Installations recently. During the period of the SAPs review in 2004-2005 the designers of future UK naval reactor plant were optioneering the control and protection systems that might be implemented. Because there was insufficient regulatory guidance available in the naval sector to support this activity the Defence Nuclear Safety Regulator (DNSR) invited the NII to collaborate with the production of a guidance document that provides clarity of regulatory expectations for the production of safety cases for computer based safety systems. A key part of producing regulatory expectations was identifying the relevant extant standards and sector guidance that reflect good practice. The three principal sources of such good practice were: IAEA Safety Guide NS-G-1.1 (Software for Computer Based Systems Important to Safety in Nuclear Power Plants), European Commission consensus document (Common Position of European Nuclear Regulators for the Licensing of Safety Critical Software for Nuclear Reactors) and IEC nuclear sector standards such as IEC60880. A common understanding has been achieved between the NII and DNSR and regulatory guidance developed which will be used by both NII and DNSR in the assessment of computer-based safety systems and in the further development of more detailed joint technical assessment guidance for both regulatory organisations. (authors)

  3. Ministerial Decree of 3 March 1978 approving the general conditions of the third party liability insurance policy for operators of nuclear installations and the general conditions of insurance policies for third party liability for transport of nuclear materials

    International Nuclear Information System (INIS)

    This Decree by the Ministry for Industry, Commerce and Crafts and the Ministry for transport of Italy was made in implementation of Section 2 of the Decree No. 519 by the president of the Republic of 2 May 1975 amending Section 15 to 24 of Act No. 1860 of 31 December 1962 on the Peaceful Uses of Nuclear Energy. This present Decree approves the general conditions of third party liability insurance policies for operators of nuclear installations and for transport of radioactive materials. (NEA)

  4. Nuclear installations in the baltic sea region and the stake holders cooperation: a crucial step towards energy security, environmental sustainability and political stability in the region

    Energy Technology Data Exchange (ETDEWEB)

    Zakaria, M.; Mandere, N.; Olsson, L. [Lund Univ., Centre for Sustainability Studies (LUCSUS) (Sweden)

    2006-07-01

    Radiation hazards are trans-boundary. The prevention of accidents must be managed locally. But the awareness, preparedness, and the responsibilities in the case of emergencies must be managed at the local and regional level, and must rely on close interaction between the local and regional levels. The Baltic Sea Region contains over 40 nuclear reactors contributing to energy security, but also posing a potential threat to human, environmental, and political security. The aim of this paper is to integrate the four fields of security: health, environment, energy, and political by analysing awareness, preparedness responsibility and decision making related to nuclear installations. With increasing political, economical, cultural and physical (in term of energy infrastructure) integration, the region needs to take a comprehensive approach to create adequate structure for managing risks and thereby promote security. (authors)

  5. Nuclear installations in the baltic sea region and the stake holders cooperation: a crucial step towards energy security, environmental sustainability and political stability in the region

    International Nuclear Information System (INIS)

    Radiation hazards are trans-boundary. The prevention of accidents must be managed locally. But the awareness, preparedness, and the responsibilities in the case of emergencies must be managed at the local and regional level, and must rely on close interaction between the local and regional levels. The Baltic Sea Region contains over 40 nuclear reactors contributing to energy security, but also posing a potential threat to human, environmental, and political security. The aim of this paper is to integrate the four fields of security: health, environment, energy, and political by analysing awareness, preparedness responsibility and decision making related to nuclear installations. With increasing political, economical, cultural and physical (in term of energy infrastructure) integration, the region needs to take a comprehensive approach to create adequate structure for managing risks and thereby promote security. (authors)

  6. Classification of containers for handling and transporting of radioactive materials and of radiation protection tables and safes in installations for nuclear medicine

    International Nuclear Information System (INIS)

    This standard describes the regulations for handling and transporting radioactive materials which are subject to obligatory license. He corresponds partly with the German standard DIN 6850 of Feb. 1977. Aside from the difinitions about containers, radiation protection tables and safes to be used in installations for nuclear medicine, tables are given showing the maximal permissible dose in mCi as a function of the wall thickness of the containers resp. of the lead shielding and of the iron, normal or baryte concrete shield equivalent to a lead shielding for 57 gamma sources most commonly used in nuclear medicine. Finally, two tables show the conversion from the old units to the new SI-units. (M.T.)

  7. Decree no. 76-480 of 24 May 1976 implementing Section 17 of the Amended Revenue Act for 1975 (no. 75-1242 of 27 December 1975) concerning the fees required for large nuclear installations

    International Nuclear Information System (INIS)

    This Decree was published in the Official French Gazette of 4 June 1976 and lays down measures for fixing and collecting the dues required for large nuclear installations. These dues are fixed by the Minister of Industry and Research for each operator on the basis of information supplied by the Head of the Central Service for the Safety of Nuclear Installations. The sums thus collected are used in particular to reimburse the expenses incurred for the safety analyses made by the Commissariat a l'Energie Atomique and for the inspections prescribed for installations. (N.E.A.)

  8. Circumstances and consequences of Oural nuclear plant spoils; Circonstances et consequences des rejets des installations nucleaires de l`Oural

    Energy Technology Data Exchange (ETDEWEB)

    Nenot, J.C.

    1994-12-31

    The environment pollution frames serious long-dated problem. The civil nuclear power unhappily does not rest. The liquid waste fuel cycle plant prospective, particularly at their working beginning. 14 refs., 5 tabs.

  9. INSTALLATION OF A POST-ACCIDENT CONFINEMENT HIGH-LEVEL RADIATION MONITORING SYSTEM IN THE KOLA NUCLEAR POWER STATION (UNIT 2) IN RUSSIA

    International Nuclear Information System (INIS)

    This is the final report on the INSP project entitled, ''Post-Accident Confinement High-Level Radiation Monitoring System'' conducted by BNL under the authorization of Project Work Plan WBS 1.2.2.6 (Attachment 1). This project was initiated in February 1993 to assist the Russians in reducing risks associated with the continued operation of older Soviet-designed nuclear power plants, specifically the Kola VVER-440/230 Unit 2, through improved accident detection capability, specifically by the installation of a dual train high-level radiation detection system in the confinement of Unit 2 of the Kola NPP. The major technical objective of this project was to provide, install and make operational the necessary hardware inside the confinement of the Kola NPP Unit 2 to provide early and reliable warning of the release of radionuclides from the reactor into the confinement air space as an indication of the occurrence of a severe accident at the plant. In addition, it was intended to provide hands-on experience and training to the Russian plant workers in the installation, operation, calibration and maintenance of the equipment in order that they may use the equipment without continued US assistance as an effective measure to improve reactor safety at the plant

  10. Study on the state-of-the-arts technologies and policy trends for the decommissioning of nuclear installations and facilities

    International Nuclear Information System (INIS)

    D and D project of the nuclear facilities is now the one of the biggest projects among the nuclear ones in the world. The nuclear facilities have their unique characteristics so making preparations about technical research in advance is very important in economic side and worker's protection side. Especially, because workers have a high possibility to contact radioactive material directly, an automation technology and shielding technology for worker's protection as well as a system development which can perform D and D work efficiently are necessary for D and D project. The waste reduction technology development, D and D equipment development, container development, and the study related the establishment of the level of the release regulation for radioactive waste are also important. The purpose of this research is to grasp of the national and internal D and D status for the nuclear facilities and to estimate them so we expect to prevent the possibility of a tremendous economical loss as the initiative of the nuclear D and D market is lost due to not understand the situation about the status of the related technologies. And we also expect to practical use the accumulated experience to decommissioning facilities in North

  11. A study of design features of civil works of nuclear installations facilitating their eventual refurbishing, renewal, dismantling or demolition

    International Nuclear Information System (INIS)

    This report describes a study that has been carried out to identify civil engineering features which could be incorporated in future gas cooled and light water cooled nuclear power plants to facilitate their decommissioning. The report reviews the problems likely to be met in decommissioning present day nuclear power plants and concludes that there is a number of such features which could be introduced in future designs to overcome or eliminate the problems. The report identifies and describes these features and recommends that further work be carried out to confirm their feasibility. The study briefly considered the possibility of refurbishing nuclear plants and concluded that this is not a realistic option in present circumstances. (author)

  12. Equipment for leak monitoring of walls separating media in power and chemical installations, mainly nuclear power plants steam generators

    International Nuclear Information System (INIS)

    Equipment is described for leak monitoring of walls separating media in power and chemical installations. The partition walls consistf o two coaxial tubes. The inner surface of the outer tube and the outer surface of the inner tube are in contact. The contact surface is broken by at least one groove. Slots between both contact surfaces are connected to the intertube space into which one or more slots open. The configuration decreases or excludes the adverse effect of thermal resistance. In case of a medium penetrating in between the inner and the outer tubes, pressure in the slots, groove and intertube space changes. The change in the pressure value is recorded and is a measure of the average size of medium penetration. (J.B.)

  13. Sustaining nuclear fuel science and technology base

    International Nuclear Information System (INIS)

    To fulfil energy demand, the Indonesian Government has made efforts to optimize the use of various-fossil and non fossil-potential energy resources in synergy (energy mix), which is stated in national energy policy. According to national energy policy, Indonesia is going to use nuclear energy for electricity supply, and up to 2025, the use of nuclear energy is projected at about 2% of the total primary energy or 4 to 5% of the national electricity supply. This energy demand is described in NPP road map, which consists of NPP preparation, construction and operation up to 2025. To sustain the activity of nuclear power plants, the continuity of nuclear reactor fuel supply is an absolute necessity; therefore, it will become industrially prospective and have an effect on national industries. As a nuclear research center and guidance in nuclear energy system in Indonesia, Batan also plays a role to promote this prospect and to increase the national content at NPP construction. In this point of view, Batan should have the competency especially in nuclear fuel cycle technology, and in this case PTBN is viewed as the competent center since PTBN's main task is to conduct the development of Nuclear Fuel Technology. This competency is performed as mastering its science and technology base. In this case, PTBN is noticed to have the capability to function suitably since PTBN is equipped with documents for fuel fabrication industry such as bidding, construction and commissioning and qualified man power. Basically, PTBN does not have the mandatory to operate nuclear fuel fabrication commercially. However, PTBN has the capability to prepare competent man power through training and coaching in nuclear fuel fabrication. In fact, the present condition shows that some of the equipments does not function properly or are not utilized optimally or are not operable. Besides, the process documents available have not yet validated and qualified, and the man power is not qualified yet

  14. Diagnosis and suggestions for the knowledge management applied to a nuclear installation: the uranium hexafluoride production unit

    International Nuclear Information System (INIS)

    It has been more than 25 years since Brazilian Navy started applying resources and staff in a nuclear power program in which the main objective is the necessary technology for project and construction of a nuclear power reactor and nuclear fuel production for naval propulsion. A long period project tends to be susceptible to loss of essential parcels of knowledge. The objective of the present research is to identify actions and initiatives that may improve learning and dissemination of knowledge in an organization that develops complexes projects during a long period of time. The revision of the literature about Knowledge Management allowed the researcher to select a reference that indicates how people involved in a project gets the necessary information and knowledge for developing their activities and uses them to add value and to learn how to contribute for the organization, in order to prevent nature difficulties. The adopted methodology was a case study on the implantation of the Unidade de Hexafluoreto de Uranio, which is being developed by the Centro Tecnologico da Marinha in Sao Paulo. With the application of structured and opened interviews, it was possible to identify some factors related with the attainment and dissemination of knowledge that can be developed. The result of this work was a proposal of action and initiatives that will improve the attainment of the knowledge, its structure and maintenance by the organization and the contribution by the people, of the knowledge acquired. (author)

  15. Implications of Recent Legislation and Strategy Developments in UK - Impact on regulation of radioactive waste management at nuclear installations

    International Nuclear Information System (INIS)

    Recently a number of factors are having a significant impact on the environment within which the UK nuclear industry operates. This presents a challenge for regulators and how they ensure delivery of proportionate regulation. The traditional organisations that made up the nuclear operators/ licensees that Health and Safety Executive (HSE) has regulated for over 30 years have changed radically with new company structures still being developed leading to the increased nuclear industry fragmentation. HSE already has some regulatory experience in this area but the pace of change is increasing as a result of competition for contracts to operate UK sites or facilities. This has already resulted in HSE undertaking a significant programme of work to regulate the re-licensing of such sites to new organisations. In response to this more dynamic environment we are examining our approach to regulation plus the safety assessment standards that need to be adopted within this changing environment. This paper will outline recent examples of how HSE has adapted its regulatory approach to specific case studies, along with discussion of how it intends to apply standards at a national and international level to illustrate the challenges that are faced in a changing operating environment. (authors)

  16. Nuclear Site Remediation and Restoration during Decommissioning of Nuclear Installations. A Report by the NEA Co-operative Programme on Decommissioning

    International Nuclear Information System (INIS)

    Decommissioning of nuclear facilities and related remedial actions are currently being undertaken around the world to enable sites or parts of sites to be reused for other purposes. Remediation has generally been considered as the last step in a sequence of decommissioning steps, but the values of prevention, long-term planning and parallel remediation are increasingly being recognised as important steps in the process. This report, prepared by the Task Group on Nuclear Site Restoration of the NEA Co-operative Programme on Decommissioning, highlights lessons learnt from remediation experiences of NEA member countries that may be particularly helpful to practitioners of nuclear site remediation, regulators and site operators. It provides observations and recommendations to consider in the development of strategies and plans for efficient nuclear site remediation that ensures protection of workers and the environment. (authors)

  17. Decree no. 2002-447 of the 27 march 2002 authorizing the Normandy society of preserve and sterilization to realize definitive shutdowns and dismantling operations of the nuclear installation no. 152 situated on the territory of Osmanville (Calvados); Decret no. 2002-447 du 27 mars 2002 autorisant le Societe normande de conserve et sterilisation a proceder aux operations de mise a l'arret definitif et de demantelement de l'installation nucleaire de base no. 152 situee sur le territoire de la commune d'Osmanville (Calvados)

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2002-07-01

    The decree presents the shutdown preliminary obligations, the installation quality, the prevention of radioactivity dissemination risk, the workers protection, the wastes management, the fire prevention. (A.L.B.)

  18. Scenario-based roadmapping assessing nuclear technology development paths for future nuclear energy system scenarios

    International Nuclear Information System (INIS)

    Nuclear energy may play a significant role in a future sustainable energy mix. The transition from today's nuclear energy system towards a future more sustainable nuclear energy system will be dictated by technology availability, energy market competitiveness and capability to achieve sustainability through the nuclear fuel cycle. Various scenarios have been investigated worldwide each with a diverse set of assumptions on the timing and characteristics of new nuclear energy systems. Scenario-based roadmapping combines the dynamic scenario-analysis of nuclear energy systems' futures with the technology roadmap information published and analysed in various technology assessment reports though integrated within the nuclear technology roadmap Nuclear-Roadmap.net. The advantages of this combination is to allow mutual improvement of scenario analysis and nuclear technology roadmapping providing a higher degree of confidence in the assessment of nuclear energy system futures. This paper provides a description of scenario-based roadmapping based on DANESS and Nuclear-Roadmap.net. (author)

  19. Design, installation and testing of a bioremediation-based system for treating regulated medical waste

    OpenAIRE

    Garg, Anil Kumar

    1994-01-01

    Disposal of regulated waste has become a major challenge for the generators. Disposal of such waste is regulated by local, state and federal agencies and the problem is intensified because of liability issues, public perception and increasing cost. This document describes the mechanical design, installation and testing of a system that employs bioremediation to disinfect regulated medical waste. Currently marketed treatment systems generally use either heat or extreme pH to...

  20. Nacelle Chine Installation Based on Wind-Tunnel Test Using Efficient Global Optimization

    Science.gov (United States)

    Kanazaki, Masahiro; Yokokawa, Yuzuru; Murayama, Mitsuhiro; Ito, Takeshi; Jeong, Shinkyu; Yamamoto, Kazuomi

    Design exploration of a nacelle chine installation was carried out. The nacelle chine improves stall performance when deploying multi-element high-lift devices. This study proposes an efficient design process using a Kriging surrogate model to determine the nacelle chine installation point in wind-tunnel tests. The design exploration was conducted in a wind-tunnel using the JAXA high-lift aircraft model at the JAXA Large-scale Low-speed Wind Tunnel. The objective was to maximize the maximum lift. The chine installation points were designed on the engine nacelle in the axial and chord-wise direction, while the geometry of the chine was fixed. In the design process, efficient global optimization (EGO) which includes Kriging model and genetic algorithm (GA) was employed. This method makes it possible both to improve the accuracy of the response surface and to explore the global optimum efficiently. Detailed observations of flowfields using the Particle Image Velocimetry method confirmed the chine effect and design results.

  1. Installation Art

    DEFF Research Database (Denmark)

    Petersen, Anne Ring

    . In Installation Art: Between Image and Stage, Anne Ring Petersen aims to change that. She begins by exploring how installation art developed into an interdisciplinary genre in the 1960s, and how its intertwining of the visual and the performative has acted as a catalyst for the generation of new artistic......Despite its large and growing popularity – to say nothing of its near-ubiquity in the world’s art scenes and international exhibitions of contemporary art –installation art remains a form whose artistic vocabulary and conceptual basis have rarely been subjected to thorough critical examination...... phenomena. It investigates how it became one of today’s most widely used art forms, increasingly expanding into consumer, popular and urban cultures, where installation’s often spectacular appearance ensures that it meets contemporary demands for sense-provoking and immersive cultural experiences. The main...

  2. The radioprotection challenges associated with the dismantling of nuclear facilities; Les enjeux de radioprotection associes au demantelement des installations nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    Anon.

    2011-01-15

    This document proposes an overview of the different studies performed by the CEPN (the French Centre of investigation on protection assessment in the nuclear sector) to develop principles and good practices in the field of radiation protection in the case of dismantling activities. These issues are addressed with respect to the characteristics of these dismantling activities, i.e. the evolution of radiological conditions under which workers are intervening, the production and handling of very important volumes of radioactive and conventional wastes, and the possible existence of a site rehabilitation project

  3. Installation of Reactor Vessel in AP1000 Nuclear Unit%AP1000核电机组反应堆压力容器的安装

    Institute of Scientific and Technical Information of China (English)

    许跃武; 高宝宁

    2012-01-01

    Hoisting orientation, rotation and location adjustment of reactor vessel in Sanmen Power Unit 1 were illustrated. By calculating the hoisting height, weight and the wind load, analyzed the safety of "open top" way on lifting reactor vessel. The methods to measure and adjust the location, levelness and elevation were also introduced, which after reactor vessel in place. Furthermore, the installation of supports and keeper plates were discussed. It supply reference value for the same nuclear plant in the hoisting and installation of main components.%阐述了某核电1号机组反应堆压力容器吊装定位、筒体翻转和就位调整的过程.通过对吊装高度、重量及风载荷进行计算,分析“开顶法”吊装反应堆压力容器的安全性.介绍了反应堆压力容器就位后方位、水平度、标高的测量与调整方法,以及护板、支撑的安装.对同类核电站的主设备吊装具有一定参考价值.

  4. U.S. Forward Operating Base Applications of Nuclear Power

    International Nuclear Information System (INIS)

    This paper provides a high level overview of current nuclear power technology and the potential use of nuclear power at military bases. The size, power ranges, and applicability of nuclear power units for military base power are reviewed. Previous and current reactor projects are described to further define the potential for nuclear power for military power.

  5. U.S. Forward Operating Base Applications of Nuclear Power

    Energy Technology Data Exchange (ETDEWEB)

    Griffith, George W. [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2015-01-01

    This paper provides a high level overview of current nuclear power technology and the potential use of nuclear power at military bases. The size, power ranges, and applicability of nuclear power units for military base power are reviewed. Previous and current reactor projects are described to further define the potential for nuclear power for military power.

  6. About the interest of an agreement for a European passport for workers in European nuclear fuel cycle installations

    International Nuclear Information System (INIS)

    The European directive 96/29 applicable to EEC 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 whore radioprotection, and medical and dosimetric follow-up are concerned. In April 2001, initiated by a group of French company medical officers (EDT' CEA COGEMA), a meeting with company medical officers 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 nuclear power plants. The group proposes the creation of a 'European Worker Passport', with knowledge and agreement of all. This passport, property of workers, could contained (apart from indispensable official data on the employee, his employer, the company medical officer and the radiation monitoring service): - dosimetric data; - medical fitness data; - level of training; - establishment in return of a radiation pass book with an ongoing account of exposure received by the worker on the nuclear power plant. (authors)

  7. Phosphonate Based High Nuclearity Magnetic Cages.

    Science.gov (United States)

    Sheikh, Javeed Ahmad; Jena, Himanshu Sekhar; Clearfield, Abraham; Konar, Sanjit

    2016-06-21

    Transition metal based high nuclearity molecular magnetic cages are a very important class of compounds owing to their potential applications in fabricating new generation molecular magnets such as single molecular magnets, magnetic refrigerants, etc. Most of the reported polynuclear cages contain carboxylates or alkoxides as ligands. However, the binding ability of phosphonates with transition metal ions is stronger than the carboxylates or alkoxides. The presence of three oxygen donor sites enables phosphonates to bridge up to nine metal centers simultaneously. But very few phosphonate based transition metal cages were reported in the literature until recently, mainly because of synthetic difficulties, propensity to result in layered compounds, and also their poor crystalline properties. Accordingly, various synthetic strategies have been followed by several groups in order to overcome such synthetic difficulties. These strategies mainly include use of small preformed metal precursors, proper choice of coligands along with the phosphonate ligands, and use of sterically hindered bulky phosphonate ligands. Currently, the phosphonate system offers a library of high nuclearity transition metal and mixed metal (3d-4f) cages with aesthetically pleasing structures and interesting magnetic properties. This Account is in the form of a research landscape on our efforts to synthesize and characterize new types of phosphonate based high nuclearity paramagnetic transition metal cages. We quite often experienced synthetic difficulties with such versatile systems in assembling high nuclearity metal cages. Few methods have been emphasized for the self-assembly of phosphonate systems with suitable transition metal ions in achieving high nuclearity. We highlighted our journey from 2005 until today for phosphonate based high nuclearity transition metal cages with V(IV/V), Mn(II/III), Fe(III), Co(II), Ni(II), and Cu(II) metal ions and their magnetic properties. We observed that

  8. Report on activities of Nuclear Regulatory Authority of the Slovak Republic and safety of nuclear installations in the Slovak Republic in 1997. Annual report 1997

    International Nuclear Information System (INIS)

    A brief account of activities carried out by the Nuclear Regulatory Authority of the Slovak Republic (NRA SR) in 1997 is presented. These activities are reported under the headings: (1) Foreword; (2) Role of the Nuclear Regulatory Authority of the Slovak Republic; (3) Supervisory and assessment activities in activities; (3.1) NPP V-1 Bohunice; (3.2) NPP V-2 Bohunice; (3.3) NPP Mochovce; (3.4) NPP A-1 Bohunice; (3.5) Radioactive wastes repository in Mochovce; (3.6) Interim spent fuel storage in Jaslovske Bohunice; (4) Nuclear materials and physical protection; (5) Radioactive wastes; (6) Quality assurance; (7) Personnel qualification and training; (8) Emergency management; (9) Legislation; (10) International co-operation; (11) Public information; (12) Conclusions; (13) Appendices

  9. Report on activities of Nuclear Regulatory Authority of the Slovak Republic and safety of nuclear installations in the Slovak Republic in 1996. Annual report 1996

    International Nuclear Information System (INIS)

    A brief account of activities carried out by the Nuclear Regulatory Authority of the Slovak Republic (NRA SR) in 1996 is presented. These activities are reported under the headings: (1) Foreword; (2) NPP V-1 Bohunice; (3) NPP V-2 Bohunice; (4) NPP Mochovce; (5) Nuclear materials; ((6) NPP A-1 Bohunice; (7) Treatment; (8) Qualification and personnel training; (9) Emergency management; (10) Legislation; (11) Quality assurance; (12) International cooperation; (13) Public relations; (14) Organization structure of the NRA SR; (15) Conclusions; (16) Appendices

  10. Installation of a Plasmatron at the Belgian Nuclear Research Centre and its Use for Plasma-Wall Interaction Studies

    International Nuclear Information System (INIS)

    In JET and ITER, the first wall will be covered by beryllium and a full or partial W divertor will be common. In DEMO, only high-Z, low erosion material such as tungsten will be present as a plasma facing material. In present day tokamaks, the very high fluence/low temperature plasma cannot be obtained. Important key issues to be resolved according to plasma wall interaction studies are the tritium retention, dust production, resilience to large steady-state fluences, transient loads, surface erosion, material redeposition and neutron damage. Some linear plasma simulators come close to the very high fluences expected in ITER and DEMO such as PSI -2; PISCES-B; NAGDIS-II and pilot-PSI. In future the larger device MAGNUM-PSI will have even higher fluences and lower temperatures for large scale components. The plasmatron facility VISION I to be installed in Mol, will have the capability to investigate mixed materials (with beryllium/tritium contaminations) and in the long term neutron activated samples. The ETHEL plasmatron VISION I from JRC-Ispra was transferred to SCKCEN (Mol, Belgium) recently. The equipment is meant to study plasma-wall interaction, in particular the interaction with hydrogen isotopes. The facility is capable to produce relatively cold self-sustained volumetric plasmas with a high plasma flux density at the target of about 1020-1021 ions/m2 .s. The plasmatron has a volume of 18 litres, a target diameter of ∼25 cm and modular ion energies in the range of 20-500 eV

  11. A web-based nuclear accident illumination system based on multilevel flow model - for risk communication and nuclear safety culture

    International Nuclear Information System (INIS)

    This paper introduces a new method to illuminate the nuclear accident by Multilevel Flow Model, and based on the method, a web-based nuclear accident illumination system is proposed to represent the current nuclear accident in nuclear power plant of Japan in an understandable way. The MFM is a means-end and part-whole modeling method to describe the structure and the intention of a plant process. The relationship between the MFM functions enables accident prediction for a plant process. Thus, a web-based accident illumination system based by MFM can describe the nuclear accident in the nuclear power plant clearly and be accessed by public to make the public get to know and understand the nuclear power and nuclear risk. The public can build their own confidence of the nuclear power by their understanding of the nuclear accident with this system and this is helpful to build a harmonious development environment for nuclear power. (author)

  12. Patterns identification in supervisory systems of nuclear reactors installations and gas pipelines systems using self-organizing maps

    International Nuclear Information System (INIS)

    Self-Organizing Maps, SOM, of Kohonen were studied, implemented and tested with the aim of developing, for the energy branch, an effective tool especially for transient identification in nuclear reactors and for gas pipelines networks logistic supervision, by classifying operations and identifying transients or abnormalities. The digital system for the test was developed in Java platform, for the portability and scalability, and for belonging to free development platforms. The system, executed in personal computers, showed satisfactory results to aid in decision taking, by classifying IRIS (International Reactor Innovative and Secure) reactor operation conditions (data from simulator) and by classifying Southeast (owner: TRANSPETRO - Brazil) gas pipeline network. Various adaptations were needed for such business, as new topologies for the output layer of artificial neural network and particular preparation for the input data. (author)

  13. Measurement-Based Evaluation of Installed Filtration System Performance in Single-Family Homes

    Energy Technology Data Exchange (ETDEWEB)

    Chan, Wanyu Rengie; Singer, Brett C.

    2014-04-03

    This guide discusses important study design issues to consider when conducting an on-site evaluation of filtration system performance. The two most important dichotomies to consider in developing a study protocol are (1) whether systems are being evaluated in occupied or unoccupied homes and (2) whether different systems are being compared in the same homes or if the comparison is between systems installed in different homes. This document provides perspective and recommendations about a suite of implementation issues including the choice of particle measurement devices, selection of sampling locations, ways to control and/or monitor factors and processes that can impact particle concentrations, and data analysis approaches.

  14. Study of a brazilian cask and its installation for PWR spent nuclear fuel dry storage; Estudo de um casco nacional e sua instalacao para armazenagem seca de combustivel nuclear queimado gerado em reatores PWR

    Energy Technology Data Exchange (ETDEWEB)

    Romanato, Luiz Sergio

    2009-07-01

    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)

  15. Application of Spatial Data Modeling Systems, Geographical Information Systems (GIS), and Transportation Routing Optimization Methods for Evaluating Integrated Deployment of Interim Spent Fuel Storage Installations and Advanced Nuclear Plants

    Energy Technology Data Exchange (ETDEWEB)

    Mays, Gary T [ORNL; Belles, Randy [ORNL; Cetiner, Sacit M [ORNL; Howard, Rob L [ORNL; Liu, Cheng [ORNL; Mueller, Don [ORNL; Omitaomu, Olufemi A [ORNL; Peterson, Steven K [ORNL; Scaglione, John M [ORNL

    2012-06-01

    The objective of this siting study work is to support DOE in evaluating integrated advanced nuclear plant and ISFSI deployment options in the future. This study looks at several nuclear power plant growth scenarios that consider the locations of existing and planned commercial nuclear power plants integrated with the establishment of consolidated interim spent fuel storage installations (ISFSIs). This research project is aimed at providing methodologies, information, and insights that inform the process for determining and optimizing candidate areas for new advanced nuclear power generation plants and consolidated ISFSIs to meet projected US electric power demands for the future.

  16. Study on the establishment of nuclear education and training network based on the nuclear knowledge management

    Energy Technology Data Exchange (ETDEWEB)

    Lee, U. J.; Han, K. W.; Jeon, P. I.; Kim, Y. T.; Nam, Y. M.; Won, J. Y.; Kim, H. K. [KAERI, Taejon (Korea, Republic of)

    2004-07-01

    The preservation and succession of nuclear knowledge are essential for the sustainable development of nuclear energy. Nuclear knowledge management is inseparably related with education and training, also should be considered as future oriented activities for the next generation. Nevertheless mankind has enormously benefited worldwide from the use of the nuclear energy over the last half a century, nuclear energy has faced with difficulties from the public. The current nuclear workforce is getting older, less of youth are studying nuclear science and engineering. These issues should be discussed together with the government, research institutes, universities, and industries in terms of the preservation and succession of nuclear knowledge. Therefore, education and training of nuclear technology is requested to develop its role with cooperation of the national level, furthermore of regional and interregional level. This paper provides the methodology of the establishment of a regional network of nuclear education and training based on the nuclear knowledge management.

  17. RESULTS FROM A DEMONSTRATION OF RF-BASED UF6 CYLINDER ACCOUNTING AND TRACKING SYSTEM INSTALLED AT A USEC FACILITY

    Energy Technology Data Exchange (ETDEWEB)

    Pickett, Chris A [ORNL; Kovacic, Donald N [ORNL; Morgan, Jim [Innovative Solutions; Younkin, James R [ORNL; Carrick, Bernie [USEC, Inc.; Ken, Whittle [USEC, Inc.; Johns, R E [Pacific Northwest National Laboratory (PNNL)

    2008-09-01

    Approved industry-standard cylinders are used globally for storing and transporting uranium hexafluoride (UF{sub 6}) at uranium enrichment plants and processing facilities. To verify that no diversion or undeclared production of nuclear material involving UF{sub 6} cylinders at the facility has occurred, the International Atomic Energy Agency (IAEA) conducts periodic, labor-intensive physical inspections to validate facility records, cylinder identities, and cylinder weights. A reliable cylinder monitoring system that would improve overall inspector effectiveness would be a significant improvement to the current international safeguards inspection regime. Such a system could include real-time unattended monitoring of cylinder movements, situation-specific rules-based event detection algorithms, and the capability to integrate with other types of safeguards technologies. This type of system could provide timely detection of abnormal operational activities that may be used to ensure more appropriate and efficient responses by the IAEA. A system of this type can reduce the reliance on paper records and have the additional benefit of facilitating domestic safeguards at the facilities at which it is installed. A radio-frequency (RF)-based system designed to track uranium hexafluoride (UF{sub 6}) cylinders during processing operations was designed, assembled, and tested at the United States Enrichment Corporation (USEC) facility in Portsmouth, Ohio, to determine the operational feasibility and durability of RF technology. The overall objective of the effort was to validate the robustness of RF technology for potential use as a future international safeguards tool for tracking UF6 cylinders at uranium-processing facilities. The results to date indicate that RF tags represent a feasible technique for tracking UF{sub 6} cylinders in operating facilities. Additional work will be needed to improve the operational robustness of the tags for repeated autoclave processing and to

  18. Licensing system for primary category radioactive installations

    International Nuclear Information System (INIS)

    The development of a licensing system for primary category radioactive installations is described, which aims to satisfy the needs of the Chilean Nuclear Energy Commission's Department of Nuclear and Radiological Safety, particularly the sections for Licensing Outside Radioactive Installations and Safety Control. This system involves the identification, control and inspection of the installations, their personnel and connected activities, for the purpose of protecting the population's health and the environment. Following the basic cycle methodology, a systems analysis and engineering stage was prepared, establishing the functions of the system's elements and defining the requirements, based on interviews with the users. This stage was followed by the design stage, focusing on the data structure, the software architecture and the procedural detail. The codification stage followed, which translated the design into legible machine-readable format. In the testing stage, the entries that were defined were proven to produce the expected data. Finally and operational and maintenance stage was developed, when the system was installed and put to use. All the above generated a useful system for the Licensing section of the Department of Nuclear and Radiological Safety, since it provides faster and easier access to information. A project is described that introduces new development tools in the Computer department following standards established by the C.CH.E.N. (author)

  19. Investigation of stillbirth risk among the offspring of male radiation workers at the Sellafield nuclear installation, west Cumbria

    Energy Technology Data Exchange (ETDEWEB)

    Pearce, M.S

    2000-04-01

    Ionising radiation is a known mutagen, much of the evidence coming from studies on animals, and from studies of occupationally exposed workforces and those exposed after the atomic bombings of Hiroshima and Nagasaki. However, few studies have examined transgenerational effects of paternal exposure in humans. The workforce at the Sellafield nuclear reprocessing plant in west Cumbria, is the most highly exposed such workforce in Western Europe and North America. This epidemiological investigation set out to determine whether there was evidence of an association between stillbirth risk and paternal preconceptional exposure to external ionising radiation or internal radionuclides. Logistic regression was used to analyse the relationship between stillbirth risk and paternal preconceptional irradiation (ppi). Further modelling of the risk of stillbirth in relation to ppi was carried out using overdispersion and variance components models. The form of doseresponse was investigated using both threshold and broken-stick models, in addition to varying the power function of the dose term. To assess the effect of errors in the dose estimates for the immediate preconceptional period resulting from the derivation of doses for short intervals pro rata from annual dose summaries, a nested case-control study was also carried out. This used more precise estimates of external doses estimated directly from monthly film badges and internal doses from special dose assessments, which were very time consuming to collate and would have taken several years to compile for the entire workforce. A significant positive association was found between the risk of a child being stillborn and total external ppi (adjusted odds ratio per 100 mSv, 1.25 95% CI 1.04-1.46, p=0.019). The risk was higher for stillbirths with congenital anomaly and was highest for the nine stillbirths with neural tube defects, eight of which were anencephalic, the other spina bifida. Although, the possibility of an

  20. Investigation of stillbirth risk among the offspring of male radiation workers at the Sellafield nuclear installation, west Cumbria

    International Nuclear Information System (INIS)

    Ionising radiation is a known mutagen, much of the evidence coming from studies on animals, and from studies of occupationally exposed workforces and those exposed after the atomic bombings of Hiroshima and Nagasaki. However, few studies have examined transgenerational effects of paternal exposure in humans. The workforce at the Sellafield nuclear reprocessing plant in west Cumbria, is the most highly exposed such workforce in Western Europe and North America. This epidemiological investigation set out to determine whether there was evidence of an association between stillbirth risk and paternal preconceptional exposure to external ionising radiation or internal radionuclides. Logistic regression was used to analyse the relationship between stillbirth risk and paternal preconceptional irradiation (ppi). Further modelling of the risk of stillbirth in relation to ppi was carried out using overdispersion and variance components models. The form of doseresponse was investigated using both threshold and broken-stick models, in addition to varying the power function of the dose term. To assess the effect of errors in the dose estimates for the immediate preconceptional period resulting from the derivation of doses for short intervals pro rata from annual dose summaries, a nested case-control study was also carried out. This used more precise estimates of external doses estimated directly from monthly film badges and internal doses from special dose assessments, which were very time consuming to collate and would have taken several years to compile for the entire workforce. A significant positive association was found between the risk of a child being stillborn and total external ppi (adjusted odds ratio per 100 mSv, 1.25 95% CI 1.04-1.46, p=0.019). The risk was higher for stillbirths with congenital anomaly and was highest for the nine stillbirths with neural tube defects, eight of which were anencephalic, the other spina bifida. Although, the possibility of an

  1. Hydraulic performance improvement of the bidirectional pit pump installation based on CFD

    Science.gov (United States)

    Chen, H. X.; Zhou, D. Q.

    2013-12-01

    At present, the efficiency of bidirectional pit pump installation with lift under 2m is still low because of lack of research on it in the past. In the paper, the CFD numerical method and experimental test were applied to study flow characteristic of bidirectional pit pump installation under positive and reverse condition. Through changing airfoil type and position of blade and stay vane, the comprehensive performance of improved model were obtained by calculating many different models. The results showed that when improved model is obtained with type A runner with 4 blades that is 0.7D away from pit exit and unsymmetrical guide vane 0.25dh which away from the impeller outlet, and the flow pattern of the improved solution is steady with high efficiency. Compared with the original scheme, the efficiency of positive and reverse design condition reach to 67.23% and 58.32% respectively, which is increased 6% more than original model on the design condition and 5% on the optimum operating condition, and it achieved the purpose of improvement. According to the runner blade angle of the optimization solution, model synthetic characteristic curve was drawn and internal flow field characteristics was analyzed under optimal positive and reverse conditions. The numerical calculation shows that owing to the lack of stay vane to recycle the energy in outlet runner chamber, the water flow regime is not steady enough in the outlet passage, and that is the main reason for lower efficiency at reverse condition than that at positive condition.

  2. Inquiry relating to modifications of reactor installation in Ikata No. 1 and 2 nuclear power plants of Shikoku Electric Power Company, Inc

    International Nuclear Information System (INIS)

    Application was made to the Minister of International Trade and Industry for the license relating to the modifications of reactor installation in the Ikata No. 1 and 2 nuclear power plants of the Shikoku Electric Power Company, Inc., on February 13, 1979, from the president of the company. After the safety evaluation was finished by the Ministry of International Trade and Industry, inquiry was conducted to the Atomic Energy Safety Commission (AESC) on June 15, 1979, from the Minister of International Trade and Industry. The investigation and discussion were commenced by the AESC on June 19, 1979. The modifications of the reactor installation are the increase of new fuel storage capacity from about 1/3 to about 2/3 of in-core fuel for No. 1 plant and the modification of driving mechanism from the roller nut type to the magnetic jack type for the control rod cluster for adjusting power distribution in the No. 2 plant. The contents of the safety examination for each item written above are presented. The prevention of criticality is carefully practiced for the new fuel storage by putting fuel assemblies in stainless steel can type racks and locating the fuel assemblies at the proper distance. Relating to the driving mechanism for the control rod cluster adjusting power distribution, the driving speed is not modified and the reliability is kept by carrying out the continuous operation test and the electric power black out test as the demonstration test. The magnetic jack type mechanism has the locking device to prevent reactor tripping at the time of electric power black out, and the cluster is held at the location where the cluster existed at the time of black out. (Nakai, Y.)

  3. Decision no. 2011-DC-0224 of the French nuclear safety authority from May 5, 2011, ordering the French atomic energy and alternative energies commission (CEA) to proceed to a complementary safety evaluation of some of its basic nuclear facilities in the eyes of the Fukushima Daiichi nuclear power plant accident; Decision no. 2011-DC-0224 de l'Autorite de surete nucleaire du 5 mai 2011 prescrivant au Commissariat a l'Energie Atomique et aux energies alternatives (CEA) de proceder a une evaluation complementaire de la surete de certaines de ses installations nucleaires de base au regard de l'accident survenu a la centrale nucleaire de Fukushima Daiichi

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-07-01

    As a consequence of the accident of the Fukushima Daiichi nuclear power plant (Japan), the French Prime Minister entrusted the French nuclear safety authority (ASN) with the mission to carry out a safety analysis re-evaluation of the French nuclear facilities, and in particular the nuclear power plants. A decision has been addressed by the ASN to each nuclear operator with the specifications of this safety re-evaluation analysis and the list of facilities in concern. This document is the decision addressed to the French atomic energy commission (CEA). (J.S.)

  4. Characterization and disposal of ion exchange resins used in nuclear installations; Caracterizacion y disposicion de resinas de intercambio ionico utilizadas en instalaciones nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Flores E, R.M.; Ortiz O, H.B.; Olguin G, M.T.; Emeterio H, M.; Garcia M, H. [ININ, 52045 Ocoyoacac, Estado de Mexico (Mexico)

    2006-07-01

    To dispose of an appropriate way the used ion exchange resins so much in the pool water purification systems of the TRIGA Mark III reactor like in the JS6500 gamma irradiator, of the National Institute of Nuclear Research, were carried out a series of analytic nuclear techniques and complementary conventional to those recommended by the ASTM, with the object of to control and to manage 14 lots of worn out resins appropriately. For its were identified the radioactive isotopes, the resins type, the grade of chemical pollution and the physicochemical degradation of the same ones. The lots of resins that didn't contain radioactive isotopes its were regenerated in an usual way, as long as those that if they controlled them they selected options for its final disposition. The first selected option was the extraction method of ion radioactive isotopes, concentrating the elution product by evaporation. As second option it was carried out the resins stabilization damaged by micro-encapsulation by forged to ambient temperature, using an organic polymer. Previous to the immobilization the resins were pretreated by vacuum drying, pulverization and thermal drying, however before carrying out this last, it was carried out a thermal gravimetric analysis to determine the drying conditions of the resins avoiding its chemical decomposition. (Author)

  5. Organisationskultur i Virum Installation

    OpenAIRE

    Dansgaard, Peter Ulrik; Monberg, Thomas; Petersen, Kristoffer Just

    2013-01-01

    This report identifies the organizational culture in the electrician company, Virum Installation, and examines which elements of the organizational culture that contributes positively as well as negatively to the integration of new employees. The main research question is: How is the phenomenon of corporate culture constituted in Virum Installation, and witch forces and mechanisms are acting as barriers in regards to the integration of new employees? Based on Claus Nygaard's methodical approa...

  6. Statistical analysis of electromagnetic radiation measurements in the vicinity of GSM/UMTS base station installed on buildings in Serbia.

    Science.gov (United States)

    Koprivica, Mladen; Slavkovic, Vladimir; Neskovic, Natasa; Neskovic, Aleksandar

    2016-03-01

    As a result of dense deployment of public mobile base stations, additional electromagnetic (EM) radiation occurs in the modern human environment. At the same time, public concern about the exposure to EM radiation emitted by such sources has increased. In order to determine the level of radio frequency radiation generated by base stations, extensive EM field strength measurements were carried out for 664 base station locations, from which 276 locations refer to the case of base stations with antenna system installed on buildings. Having in mind the large percentage (42 %) of locations with installations on buildings, as well as the inevitable presence of people in their vicinity, a detailed analysis of this location category was performed. Measurement results showed that the maximum recorded value of total electric field strength has exceeded International Commission on Non-Ionizing Radiation Protection general public exposure reference levels at 2.5 % of locations and Serbian national reference levels at 15.6 % of locations. It should be emphasised that the values exceeding the reference levels were observed only outdoor, while in indoor total electric field strength in no case exceeded the defined reference levels.

  7. Statistical analysis of electromagnetic radiation measurements in the vicinity of GSM/UMTS base station installed on buildings in Serbia

    International Nuclear Information System (INIS)

    As a result of dense deployment of public mobile base stations, additional electromagnetic (EM) radiation occurs in the modern human environment. At the same time, public concern about the exposure to EM radiation emitted by such sources has increased. In order to determine the level of radio frequency radiation generated by base stations, extensive EM field strength measurements were carried out for 664 base station locations, from which 276 locations refer to the case of base stations with antenna system installed on buildings. Having in mind the large percentage (42 %) of locations with installations on buildings, as well as the inevitable presence of people in their vicinity, a detailed analysis of this location category was performed. Measurement results showed that the maximum recorded value of total electric field strength has exceeded International Commission on Non-Ionizing Radiation Protection general public exposure reference levels at 2.5 % of locations and Serbian national reference levels at 15.6 % of locations. It should be emphasised that the values exceeding the reference levels were observed only outdoor, while in indoor total electric field strength in no case exceeded the defined reference levels. (authors)

  8. Post-Fukushima additional safety assessments: behaviour of French nuclear installations in case of extreme situations and relevance of improvement propositions; Evaluations complementaires de surete post-Fukushima: comportement des installations nucleaires francaises en cas de situations extremes et pertinence des propositions d'ameliorations

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-07-01

    After the Fukushima accident, additional safety assessments (ECS, evaluation complementaire de securite) have been commissioned to assess the resistance of French nuclear installations to extreme scenarios (earthquake, loss of electricity supply, and loss of cooling sources). This report is a synthesis of a more important one. It briefly describes the international context and notices that, in foreign countries, only power reactors are submitted to such additional safety assessments. It describes the approach adopted by the IRSN by considering that severe accidental situation are possible and may have characteristics exceeding the current referential. This approach enables the identification of safety functions which must maintained in these situations, and of some limitations of the current safety referential. The report then discusses the current status of installations, notices that actions are to be performed. It comments the results obtained in terms of installation robustness with respect to risks of earthquake or flooding, or those associated with other external hazards. It comments the analysis performed in case of total loss of cooling sources or of energy supplies in power reactors, in the EPR, and in some other nuclear installations (ILL, CEA's installations, AREVA's laboratories and factories). It finally comments the ability of operators in managing a crisis situation under these conditions, and briefly evokes the subcontracting issue

  9. Optimum repair-level analysis (ORLA) and life cycle cost (LCC) models for the base and installation security system (BISS)

    Energy Technology Data Exchange (ETDEWEB)

    York, A.A.; Chipchak, J.S.

    1979-03-01

    Models for Optimum Repair-Level Analysis (ORLA) and Life Cycle Cost (LCC) analysis for Base and Installation Security System (BISS) equipment are described. The ORLA model determines the costs of alternative maintenance approaches for selection of the most economic maintenance approach. The LCC model determines the total cost to the Government for the development, acquisition, initial logistics support, and recurring support of a system over the projected inventory usage period. A unique feature of these models is the marriage of ORLA and ICC which enables LCC to utilize completely the most economic ORLA decision costs. This significantly reduces the overall LCC effort.

  10. StressDB: A Locally Installable Web-Based Relational Microarray Database Designed for Small User Communities

    OpenAIRE

    Madhusmita Mitra; Nigam Shah; Lukas Mueller; Scuth Pin; Nina Fedoroff

    2002-01-01

    We have built a microarray database, StressDB, for management of microarray data from our studies on stress-modulated genes in Arabidopsis. StressDB provides small user groups with a locally installable web-based relational microarray database. It has a simple and intuitive architecture and has been designed for cDNA microarray technology users. StressDB uses Windows™ 2000 as the centralized database server with Oracle™ 8i as the relational database management system. It allows users to manag...

  11. Reactors 2000: consultation on the technical and economical requirements connected with the possible realization of nuclear installations in Switzerland after the year 2000

    International Nuclear Information System (INIS)

    In 1989 the OECD started a consultation on the development of nuclear reactors of small and medium size (SMR). The present study is part of the Swiss contribution to this international work. Beyond this primary goal, without being limited solely to SMRs, but exclusively in the Swiss framework, the study attempts to determine a profile for reactors which could be built in Switzerland after the year 2000. The study ''Reactors 2000'' is based on two polls which were conducted among about 70 persons from concerned professional circles (industry, utilities, scientific groups, energy policy makers, safety authorities, public organizations) in June 1990 and February 1991. A large majority of the persons interviewed think that - Switzerland should not jeopardize its energetic future by phasing out all activity in the nuclear field, based on circumstances which could be only temporary, - Switzerland should continue its activities in the nuclear field in order to maintain the necessary know-how and a sufficient number of highly qualified specialists both for the safe operation of the existing plants and for the continuation of the development of nuclear technology, - for future plants the goal of an even higher safety level should be aimed for, although, according to the explicit comments of many interviews, today's reactors are considered to be sufficiently safe, - future nuclear power plants should be designed in such a way that the possibility of a severe accident necessitating an evacuation of the Swiss population could be excluded, - Switzerland should participate in international projects, in order to maintain contact to the international development of nuclear technology; on the other hand, it should avoid any single-handed effort (including in the domain of small heating reactors). (author)

  12. 3D Projection Installations

    DEFF Research Database (Denmark)

    Halskov, Kim; Johansen, Stine Liv; Bach Mikkelsen, Michelle

    2014-01-01

    Three-dimensional projection installations are particular kinds of augmented spaces in which a digital 3-D model is projected onto a physical three-dimensional object, thereby fusing the digital content and the physical object. Based on interaction design research and media studies, this article...... contributes to the understanding of the distinctive characteristics of such a new medium, and identifies three strategies for designing 3-D projection installations: establishing space; interplay between the digital and the physical; and transformation of materiality. The principal empirical case, From...... Fingerplan to Loop City, is a 3-D projection installation presenting the history and future of city planning for the Copenhagen area in Denmark. The installation was presented as part of the 12th Architecture Biennale in Venice in 2010....

  13. A Study on the Ultrasonic Sensor and Accelerometer Installation and Signal Acquisition Method for Engine Condition Diagnosis on EDG in Nuclear Power Plant

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Sang Guk; Choi, Kwang Hee; Choi, You Sung [Korea Hydro and Nuclear Power Co., Daejeon (Korea, Republic of)

    2012-05-15

    As a plan for the improvement of the EDG (Emergency Diesel Generator) maintenance program, the research project is being done by changing from time to condition based maintenance. First of all, the condition of EDG was analyzed and CBM(Condition Based Maintenance) was applied. The diagnoses for EDG are mainly composed of combustion in cylinders, vibration and ultrasonic signal analysis. The combustion analysis provides information of the combustion performance on each cylinder of EDG. Vibration and ultrasonic analysis provide timing signal on each event and information on mechanical condition. These signals can be collected without trouble causing on the operation of EDG. In this paper, the optimum sensor installation and the signal acquisition method are described for monitoring and diagnosis of EDG

  14. Independent technical support for the frozen soil barrier installation and operation at the Fukushima Daiichi Nuclear Power Station (F1 Site)

    Energy Technology Data Exchange (ETDEWEB)

    Looney, Brian B. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Jackson, Dennis G. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Truex, Michael J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Johnson, Christian D. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

    2015-02-23

    TEPCO is implementing a number of water countermeasures to limit the releases and impacts of contaminated water to the surrounding environment. The diverse countermeasures work together in an integrated manner to provide different types, and several levels, of protection. In general, the strategy represents a comprehensive example of a “defense in depth” concept that is used for nuclear facilities around the world. One of the key countermeasures is a frozen soil barrier encircling the damaged reactor facilities. The frozen barrier is intended to limit the flow of water into the area and provide TEPCO the ability to reduce the amount of contaminated water that requires treatment and storage. The National Laboratory team supports the selection of artificial ground freezing and the incorporation of the frozen soil barrier in the contaminated water countermeasures -- the technical characteristics of a frozen barrier are relatively well suited to the Fukushima-specific conditions and the need for inflow reduction. Further, our independent review generally supports the TEPCO/Kajima design, installation strategy and operation plan.

  15. Virtual reality technology used to estimate radiation doses in nuclear installations; Utilizacao de ambientes virtuais na estimativa de dose de radiacao em instalacoes nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Augusto, Silas Cordeiro

    2008-03-15

    The physical integrity of people when walking in places subjected to radiation can be preserved by following some rules. Among these rules are safe limits of radiation level, proximity of radiation sources, time of exposition to radiation sources, and a combination of these factors. In this way, previous training and simulations of operation proceedings to be executed in places subjected to radiation help to better prepare the course in such places, minimizing the absorbed dose. On the other hand, virtual reality is a technology applicable in several areas, enabling the training and simulation of real places and hypothetical scenarios, with a good level of realism, but without danger if compared to the same activities in the real world. As a virtual environment does not presents any health risks, it is possible to train workers beforehand to several operation or maintenance scenarios. In this virtual environment, the dose tax distribution can be visualized, and the dose absorbed by the worker, represented and simulated in the virtual environment by a virtual character (avatar) can be shown. Therefore, the tasks to be done can be better planned, evaluating the workers actions and the performance so to reduce failures and health risks. Finally, this work presents a tool to build and navigate in virtual environments, enabling the training of activities in nuclear facilities. To that end is proposed a methodology to modify and adapt a free game engine. (author)

  16. Proprietary, standard, and government-supported nuclear data bases

    International Nuclear Information System (INIS)

    This study presents an assessment of the complex situation surrounding nuclear data bases for nuclear power technology. Requirements for nuclear data bases are identified as regards engineering functions and system applications for the many and various user groups that rely on nuclear data bases. Current practices in the development and generation of nuclear data sets are described, and the competitive aspect of design nuclear data set development is noted. The past and current role of the federal government in nuclear data base development is reviewed, and the relative merits of continued government involvement are explored. National policies of the United States and other industrial countries regarding the availability of nationally supported nuclear data information are reviewed. Current proprietary policies of reactor vendors regarding design library data sets are discussed along with the basis for such proprietary policies. The legal aspects of protective policies are explored as are their impacts on the nuclear power industry as a whole. The effect of the regulatory process on the availability and documentation of nuclear data bases is examined. Current nuclear data standard developments are reviewed, including a discussion of the standard preparation process. Standards currently proposed or in preparation that directly relate to nuclear data bases are discussed in some detail. (auth)

  17. Economical analysis of an alternative strategy for CO2 mitigation based on nuclear power

    International Nuclear Information System (INIS)

    Many countries are pursuing greenhouse gas (GHG) mitigation policies resulting in the increase of use of renewable sources in the electricity sector to mitigate CO2 emissions. Nuclear energy is a non-emitting CO2 source that could be used as part of that policy. However, its main drawback is the high investment required for its deployment. On the other hand, wind power is the clean source preferred option to mitigate CO2 emissions. However, due to its intermittence backup power is needed, in most of the cases it must be provided with combined cycle thermal plants using natural gas. This study performs an economical comparison of a hypothetical implementation of a nuclear strategy to meet the same CO2 emissions reduction goal that has been obtained by the actual Spaniard strategy (2005–2010) based on wind power. The investment required in both strategies is assessed under different investment scenarios and electricity production conditions for nuclear power. Also, the cost of electricity generation is compared for both strategies. - Highlights: ► Wind power electricity cost including its backup in Spain is assessed. ► Nuclear power is proposed as an alternative to produce the same CO2 reduction. ► Nuclear power requires less installed capacity deployment. ► Investment to produce the same CO2 reduction is smaller using nuclear power. ► Electricity generating cost is less expensive using the nuclear option

  18. The dismantling of nuclear installations and the radioactive wastes management. Report of the President of the Republic followed by the answers of concerned administrations and organisms; Le demantelement des installations nucleaires et la gestion des dechets radioactifs. Rapport au President de la Republique suivi des reponses des administrations et des organismes interesses

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-01-15

    The discussed subjects concerns the situation and the challenges of the nuclear installations dismantling and the radioactive wastes management (main intervenors, panorama of the situation, rules applied to the dismantling and the radioactive wastes), the first experiences of dismantling and radioactive wastes disposal (experiences at the CEA and EDF, implementing of solutions for the disposal), interrogations and certainties (provision for future expenses, public information). (A.L.B.00.

  19. Perceived benefits of adopting Standard – Based pricing mechanism for mechanical and electrical services installations

    OpenAIRE

    Ganiyu Amuda Yusuf; Sarajul Fikri Mohamed

    2014-01-01

    Cost is an important measure of project success and clients will expect a reliable forecast at the early stage of construction projects to inform their business decision. This study was undertaken to investigate the current practices in managing cost of mechanical and electrical (M&E) services in buildings. The perceptions of practitioners on the benefits of adopting Standard – Based Pricing Mechanism for M&E services as used for building fabrics and finishes was ascertained. The meth...

  20. Ground-based Nuclear Detonation Detection (GNDD) Technology Roadmap

    Energy Technology Data Exchange (ETDEWEB)

    Casey, Leslie A.

    2014-01-13

    This GNDD Technology Roadmap is intended to provide guidance to potential researchers and help management define research priorities to achieve technology advancements for ground-based nuclear explosion monitoring science being pursued by the Ground-based Nuclear Detonation Detection (GNDD) Team within the Office of Nuclear Detonation Detection in the National Nuclear Security Administration (NNSA) of the U.S. Department of Energy (DOE). Four science-based elements were selected to encompass the entire scope of nuclear monitoring research and development (R&D) necessary to facilitate breakthrough scientific results, as well as deliver impactful products. Promising future R&D is delineated including dual use associated with the Comprehensive Nuclear-Test-Ban Treaty (CTBT). Important research themes as well as associated metrics are identified along with a progression of accomplishments, represented by a selected bibliography, that are precursors to major improvements to nuclear explosion monitoring.

  1. Ground-based Nuclear Detonation Detection (GNDD) Technology Roadmap

    International Nuclear Information System (INIS)

    This GNDD Technology Roadmap is intended to provide guidance to potential researchers and help management define research priorities to achieve technology advancements for ground-based nuclear explosion monitoring science being pursued by the Ground-based Nuclear Detonation Detection (GNDD) Team within the Office of Nuclear Detonation Detection in the National Nuclear Security Administration (NNSA) of the U.S. Department of Energy (DOE). Four science-based elements were selected to encompass the entire scope of nuclear monitoring research and development (R&D) necessary to facilitate breakthrough scientific results, as well as deliver impactful products. Promising future R&D is delineated including dual use associated with the Comprehensive Nuclear-Test-Ban Treaty (CTBT). Important research themes as well as associated metrics are identified along with a progression of accomplishments, represented by a selected bibliography, that are precursors to major improvements to nuclear explosion monitoring.

  2. Perceived benefits of adopting Standard – Based pricing mechanism for mechanical and electrical services installations

    Directory of Open Access Journals (Sweden)

    Ganiyu Amuda Yusuf

    2014-06-01

    Full Text Available Cost is an important measure of project success and clients will expect a reliable forecast at the early stage of construction projects to inform their business decision. This study was undertaken to investigate the current practices in managing cost of mechanical and electrical (M&E services in buildings. The perceptions of practitioners on the benefits of adopting Standard – Based Pricing Mechanism for M&E services as used for building fabrics and finishes was ascertained. The methodology adopted for the study was semi – structure interview and questionnaire survey.  Inferential statistics technique was used to analyse the data collected. The results revealed that, M&E services tender documents are often based on lump sum contract. Practitioners are of the opinion that the adoption of Standard – Based Pricing Mechanism (SBPM could enhance the quality of M&E services price forecast; ensure active post contract cost monitoring and control; encourage collaborative working relationship; enhance efficient whole life cycle cost management; improve risk management and facilitate efficient tendering process. The study suggested the development of local Standard Method of Measurement for M&E services and proposed strategies to facilitate the adoption of SBPM as basis for forecasting contract price of mechanical and electrical services in buildings.

  3. Installation of a digitizer based pulse processing and data acquisition system and related developments

    International Nuclear Information System (INIS)

    The use of digitizer based pulse processing and data acquisition system at the recent campaign of the Indian National Gamma Array (INGA) at Tata Institute of Fundamental Research (TIFR), Mumbai, has emanated the use of digital signal processing in spectroscopic endeavours being pursued in the country. The long and successful operation of the system at TIFR, and several experiments carried out therein, have contributed in edifying the user community on the nuances of the new technology and the possible refinements/ requirements in the context of the γ-ray spectroscopic endeavours

  4. AUTOMATISATION D’UNE INSTALLATION SOLAIRE A BASE D’UN MICROPROCESSEUR

    OpenAIRE

    MERAD, La.; MERAD, Lo.; BOUSSOUKAIA, T.; B. Benyoucef

    2003-01-01

    Le système photovoltaïque offre un large champ d'application pour les microprocesseurs. Tel que le développement d'algorithmes d’optimisation efficaces, facilement programmables et utilisant les paramètres réels à l’environnement. La structure matérielle et le logiciel requis comportent des contrôleurs à base de microprocesseur utilisés pour le contrôle de puissance délivrée par un générateur photovoltaïque, de la vitesse de rotation d'une machine asynchrone e...

  5. Decree no. 2010-402 from April 23, 2010, giving permission to Electricite de France to create, on the territory of the town of Saint-Vulbas (Ain, France), a basic nuclear facility named activated waste conditioning and storage facility (ICEDA); Decret no. 2010-402 du 23 avril 2010 autorisant Electricite de France a creer, sur le territoire de la commune de Saint-Vulbas (departement de l'Ain), une installation nucleaire de base denommee Installation de conditionnement et d'entreposage de dechets actives (ICEDA)

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2010-07-01

    The purpose of the nuclear facility named 'activated waste conditioning and storage facility' (ICEDA) is to process and store the wastes generated by the dismantlement of the Creys-Malville nuclear power plant (Superphenix reactor), and those generated by the exploitation, maintenance and modification of the PWR power plants of Electricite de France (EdF). The facility comprises a reception/evacuation hall, a processing unit, a waste storage building, an effluent treatment plant and some annexe buildings with offices and technical workshops. Wastes are of 3 type: medium activity/long living, low to medium activity/short living, and low activity/long living. The facility ensures the storage of the Chooz A power plant source rods as well. This decree defines the specifications of the facility in the following domains: confinement of radioactive or toxic compounds, protection against internal and external risks (fire hazards, explosions, earthquakes, other environmental risks), exploitation of the facility, management of liquid and gaseous effluents and other wastes generated by the facility. (J.S.)

  6. Progress report for cyclotron based nuclear science

    International Nuclear Information System (INIS)

    Research activities and progress on construction of the new cyclotron facility are summarized. Research is described under the headings heavy-ion reactions, nuclear structure, nuclear theory, and atomic studies. Progress in instrumentation and systems development is discussed. Publications are listed

  7. Development and Testing of a Friction-Based Post-Installable Sensor for Subsea Fiber-Optic Monitoring Systems

    Science.gov (United States)

    Bentley, Nicole; Brower, David; Le, Suy Q.; Seaman, Calvin; Tang, Henry

    2017-01-01

    This paper presents the design and development of a friction-based coupling device for a fiber-optic monitoring system that can be deployed on existing subsea structures. This paper provides a summary of the design concept, prototype development, prototype performance testing, and design refinements of the device. The results of the laboratory testing of the first prototype performed at the National Aeronautics and Space Administration (NASA) Johnson Space Center (JSC) are included in this paper. Limitations of the initial design were identified and future design improvements were proposed. These new features will enhance the coupling of the device and improve the monitoring system measurement capabilities. A major challenge of a post-installed instrumentation monitoring system is to ensure adequate coupling between the instruments and the structure of interest for reliable measurements. Friction-based coupling devices have the potential to overcome coupling limitations caused by marine growth and soil contamination on subsea structures, flowlines or risers. The work described in this paper investigates the design of a friction-based coupling device (friction clamp), which is applicable for pipelines and structures that are suspended in the water column and those that are resting on the seabed. The monitoring elements consist of fiber-optic sensors that are bonded to a metal clamshell with a high-friction coating. The friction clamp has a single hinge design to facilitate the operation of the clamp and dual rows of opposing fasteners to distribute the clamping force on the structure. The friction clamp can be installed by divers in shallow depths or by remotely operated vehicles in deep-water applications. NASA-JSC was involved in the selection and testing of the friction coating, and in the design and testing of the prototype clamp device. Four-inch diameter and eight-inch diameter sub-scale friction clamp prototypes were built and tested to evaluate the strain

  8. Multiparametric electronic devices based on nuclear tracks

    Energy Technology Data Exchange (ETDEWEB)

    Fink, D. [HMI Berlin, Glienicker Str. 100, 14109 Berlin (Germany)], E-mail: FINK@HMI.DE; Saad, A. [HMI Berlin, Glienicker Str. 100, 14109 Berlin (Germany); Basic Science Department, Faculty of Science, Al Balqa University, Salt (Jordan); Dhamodaran, S. [HMI Berlin, Glienicker Str. 100, 14109 Berlin (Germany); School of Physics, University of Hyderabad, Hyderabad 500 046 (India); Chandra, A. [HMI Berlin, Glienicker Str. 100, 14109 Berlin (Germany); Department of Physics and Astrophysics, University of Delhi, Delhi 110 007 (India); Fahrner, W.R. [Chair of Electronic Devices, Institute of Electrotechnique, Fernuniversitaet, Hagen (Germany); Hoppe, K. [South Westfalia University of Applied Sciences, Hagen (Germany); Chadderton, L.T. [Institute of Advanced Studies, ANU Canberra, GPO Box 4, ACT (Australia)

    2008-08-15

    An overview is given on a family of novel electronic devices consisting of an insulating layer containing conducting or semiconducting nuclear tracks, deposited on a semiconducting substrate, and connected by at least one back and two surface contacts. Conducting and semiconducting latent tracks may emerge directly from swift heavy ion irradiation. Etched tracks in insulators can be filled with adequate materials to make them conducting or semiconducting. For this purpose metallic or semiconducting nanoclusters were deposited. We have denoted termed these devices made with latent tracks as 'tunable electronic anisotropic material on semiconductor' (TEAMS), if based on latent ion tracks, and as 'tunable electronic material in pores in oxide on semiconductor' (TEMPOS), if based on etched tracks. Depending on the band-to-band transition between tracks and substrate and on the ratio of surface to track conductivity, the current/voltage characteristics of TEAMS and TEMPOS structures can be modified in many different ways leading to tunable resistors, capacitors and diodes. Both devices show negative differential resistances. This should enable tunable tunneldiodes. TEAMS or TEMPOS structures can be controlled by various external physical and/or chemical parameters leading to sensors. It is even possible to combine different input currents and/or external parameters according to AND/OR logics. The currents through a clustered layer on a TEMPOS structure can be described by the Barbasi-Albert model of network theory enabling to calculate a 'radius of influence'r{sub ROI} around each surface contact, beyond which neighboring contacts do not influence each other. The radius of influence can be well below 1{mu}m leading to nanometric TEMPOS structures.

  9. Capacitor-based detection of nuclear magnetization: nuclear quadrupole resonance of surfaces.

    Science.gov (United States)

    Gregorovič, Alan; Apih, Tomaž; Kvasić, Ivan; Lužnik, Janko; Pirnat, Janez; Trontelj, Zvonko; Strle, Drago; Muševič, Igor

    2011-03-01

    We demonstrate excitation and detection of nuclear magnetization in a nuclear quadrupole resonance (NQR) experiment with a parallel plate capacitor, where the sample is located between the two capacitor plates and not in a coil as usually. While the sensitivity of this capacitor-based detection is found lower compared to an optimal coil-based detection of the same amount of sample, it becomes comparable in the case of very thin samples and even advantageous in the proximity of conducting bodies. This capacitor-based setup may find its application in acquisition of NQR signals from the surface layers on conducting bodies or in a portable tightly integrated nuclear magnetic resonance sensor.

  10. Human Resources Capacity Building as a Strategy in Strengthening Nuclear Knowledge Sustainability in the Experimental Fuel Element Installation of BATAN-Indonesia

    International Nuclear Information System (INIS)

    Strategy in Strengthening Nuclear Knowledge Sustainability: • In order to maintain human resources capacity related to nuclear fuel production technology, a nuclear knowledge preservation program is implemented in the EFEI. • The program includes coaching/training, mentoring and documenting important knowledge. • The program activities are monitored and evaluated quarterly for its improvement in the following year

  11. The improvement of KINR NASU experimental base and methods of nondestructive control of functional characteristics of nuclear power stations' equipment and materials

    International Nuclear Information System (INIS)

    The ways of the improvement of technical base of the INR of NAS of Ukraine for functional researches, and new technologies of control over the state of the equipment on NPPs are discussed. The scientific work is completed in the department of radiation technologies within the national program of the enhancement of the reliability of nuclear energetic and the prolongation of exploitation terms of nuclear power installations

  12. Galloping-based piezo-aeroelastic energy harvester for wireless sensors to be installed on freight trains

    Science.gov (United States)

    Tomasini, Gisella; Giappino, Stefano; Costa, Andrea

    2016-04-01

    Energy harvesting from galloping oscillations of a bluff body can be used to supply power to a wireless sensor. In this paper we investigate the possibility to use a galloping-based piezo-aeroelastic energy harvester to supply power to a wireless sensors network installed on a freight train to measure the accelerations in correspondence of axle boxes. The monitoring system will be used to detect possible deteriorations of the running conditions that, in the worst cases, can lead to the vehicle derailment. Unlike other applications in this case the air speed relative to the body is due to the train motion and, for typical freight trains and standard running conditions, is equal to about 20 m/s. In the paper we discuss the design of the harvester on the basis of the constrains due to the application. Preliminary aerodynamic tests shows the limitation of the classical quasi-steady theory of galloping as a consequence of the interaction with the vortex shedding phenomenon.

  13. A Discrepancy-Based Methodology for Nuclear Training Program Evaluation.

    Science.gov (United States)

    Cantor, Jeffrey A.

    1991-01-01

    A three-phase comprehensive process for commercial nuclear power training program evaluation is presented. The discrepancy-based methodology was developed after the Three Mile Island nuclear reactor accident. It facilitates analysis of program components to identify discrepancies among program specifications, actual outcomes, and industry…

  14. Designing a nuclear data base prototype using Oracle and Prolog

    International Nuclear Information System (INIS)

    An ever-increasing demand exists for easily accessible nuclear data base systems. The purpose of this work is to analyze the feasibility of using artificial intelligence methods as tools to provide the necessary functionality to extract information from nuclear data files in a user-friendly manner. For the prototype of this work, a sample of data that can be later enlarged to a complete, evaluated nuclear data base has been used. To implement this prototype, two approaches have been followed: a conventional approach using the commercially available Oracle relational data base management system; and an artificial intelligence approach using the Prolog programming language. This prototypic work shows the feasibility of applying artificial intelligence methods to data bases, and represents a first step toward development of intelligent nuclear data base systems. The characteristics of the query language from both approaches make the second one preferable from a user's point of view. 23 refs., 7 tabs

  15. The ATALANTE installation; L'installation atalante

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-10-01

    In the Atalante installation of the CEA/Marcoule, researches on the reprocessing of irradiated fuel from nuclear reactors, are performed. In the framework of the law (30 december 1991) on the public policy concerning the radioactive wastes management, the ATALANTE project has to proposed solutions for the long-dated management of these wastes and to help the reprocessing industry. The specifications of the installation and the research programs are detailed with a special interest for the glass durability and the plutonium purifying cycle. The public policy stakes are also recalled. (A.L.B.)

  16. Ship-Based Nuclear Energy Systems for Accelerating Developing World Socioeconomic Advance

    Science.gov (United States)

    Petroski, Robert; Wood, Lowell

    2014-07-01

    Technological, economic, and policy aspects of supplying energy to newly industrializing and developing countries using ship-deployed nuclear energy systems are described. The approach analyzed comprises nuclear installations of up to gigawatt scale deployed within currently mass-produced large ship hulls which are capable of flexibly supplying energy for electricity, water desalination and district heating-&-cooling with low latencies and minimized shoreside capital expenditures. Nuclear energy is uniquely suited for mobile deployment due to its combination of extraordinary energy density and high power density, which enable enormous supplies of energy to be deployed at extremely low marginal costs. Nuclear installations on ships also confer technological advantages by essentially eliminating risk from earthquakes, tsunamis, and floods; taking advantage of assured access to an effectively unlimited amount of cooling water, and involving minimal onshore preparations and commitments. Instances of floating nuclear power stations that have been proposed in the past, some of which are currently being pursued, have generally been based on conventional LWR technology, moreover without flexibility or completeness of power output options. We consider nuclear technology options for their applicability to the unique opportunities and challenges of a marine environment, with special attention given to low-pressure, high thermal margin systems with continuous and assured afterheat dissipation into the ambient seawater. Such systems appear promising for offering an exceptionally high degree of safety while using a maximally simple set of components. We furthermore consider systems tailored to Developing World contexts, which satisfy societal requirements beyond electrification, e.g., flexible sourcing of potable water and HVAC services, servicing time-varying user requirements, and compatibility with the full spectrum of local renewable energy supplies, specifically including

  17. Concerning modification of installation plan for reactor (modification of No.3 and No.4 reactor facilities) at Genkai nuclear power plant of Kyushu Electric Power Co., Ltd. (reply to inquiry)

    International Nuclear Information System (INIS)

    In response to an inquiry on the title issue, the Nuclear Safety Commission made an examination and submitted the findings to the Minister of International Trade and Industry. The modifications include the construction of combustion facilities for volume reduction of miscellaneous solid wastes. In the facilities, miscellaneous solid wastes will be combusted for volume reduction, and the combustion residue will be cooled with water and processed into glass-like granules, which will be stored in drums in the solid waste storage facilities. It is confirmed that the release of radioactive substances into the environment will be negligible, that the facilities have been designed to the Class B anti-earthquake standards, and that radiation monitors will be installed. The modifications also include the installation of an improved cement solidification system to replace a conventional-type system and a change in the capacity of the solid waste storage facilities. It is concluded that all proposed modifications should be approved. (Nogami, K.)

  18. Decree no 96-761 from August 27, 1996 authorizing the company for industrial wastes and effluents conditioning to create a basic nuclear installation, named Centraco, in the town of Codolet (Gard department)

    International Nuclear Information System (INIS)

    This decree from the French prime minister, the minister of environment and the minister of industry and postal services gives permission to the Socodei company to create a basic nuclear installation, named Centraco, in the town of Codolet (Gard department, France) for the selection, decontamination, valorization, treatment and conditioning of low radioactive effluents and wastes from French and foreign industries. The decree describes the Centraco installation (buildings, incineration and storage unit, maintenance unit). It summarizes the technical rules which must be applied concerning the quality assurance, the protection against risks of radioactive or chemical materials dissemination, the personnel and public protection against ionizing radiations, the control of environmental pollution with liquid and gaseous effluents, the reduction of volume and radioactivity of solid wastes, the transport and handling of radioactive materials, the protection against earthquakes and fire, the safety systems for plant operation, and the personnel training. (J.S.)

  19. International Nuclear Model. Volume 2. Data base relationships

    International Nuclear Information System (INIS)

    This volume presents Data Base Relationships of the International Nuclear Model (INM), which was developed for the Nuclear and Alternate Fuels Division (NAFD), Office of Coal, Nuclear, Electric and Alternate Fuels, Energy Information Administration (EIA), US Department of Energy (DOE). The International Nuclear Model (INM) is a comprehensive model of the commercial nuclear power industry. It simulates economic decision for reactor deployment and fuel management decisions based on an input set of technical, economic and scenario parameters. The technical parameters include reactor operating characteristics, fuel cycle timing and mass loss factors, and enrichment tails assays. Economic parameters include fuel cycle costs, financial data, and tax alternatives. INM has a broad range of scenario options covering, for example, process constraints, interregional activities, reprocessing, and fuel management selection. INM reports reactor deployment schedules, electricity generation, and fuel cycle requirements and costs. It also has specialized reports for extended burnup and permanent disposal. 8 refs., 22 figs

  20. Decree no. 96-978 from October 31, 1996 giving permission to the French atomic energy Commission (CEA) to create a basic nuclear installation intended to maintain under supervision and in an intermediate dismantling state the old basic nuclear installation no. 28, named Monts d'Arree-EL 4 nuclear power plant (a decommissioned reactor), in the Monts d'Arree site of the Loqueffret town (Finistere, Brittany)

    International Nuclear Information System (INIS)

    This decree from the French ministry of industry and postal services gives permission to the CEA to create a new basic nuclear installation, named EL 4D, which is devoted to the storage of materials from the partially dismantled Monts d'Arree EL 4 reactor. Thus, the CEA is allowed to carry out confining works on the reactor building with the closure of all apertures with the exception of the personnel entry sieve, on the circuits and equipments of the reactor vessel with the plugging of fuel channels, heavy water, helium and demineralized water pipes and of the heads of control rod drive mechanisms and other channels, and on the primary coolant circuit outside the reactor vessel and the steam generators with the installation of welded hatches. The irradiated fuels building, the solid wastes repository, the ventilation building, the heavy water and helium circuits, the fuel handling systems and the effluents treatment plant will be completely dismantled. The other buildings will be pulled down. The rest of the decree enumerates the general technical and safety prescriptions which have to be followed in order to ensure the protection of the personnel against ionizing radiations and of the environment against radioactive pollution. (J.S.)

  1. Reports by the Parliamentary Office for scientific and technological assessments. Thursday, May 19, 2011. The French nuclear installations in front of natural risks; Comptes rendus de l' Office Parlementaire d'Evaluation des Choix Scientifiques et Technologiques. Jeudi 19 mai 2011. Les installations nucleaires francaises face aux risques naturels

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-05-15

    Members of the French Parliament, representatives of the French nuclear safety authority (ASN), of the Academy of Sciences, researchers, and associations argue on major natural risks and their evaluation, notably by referring to the earthquake and tsunami which caused the Fukushima accident. They discuss the predictability of these phenomena, and evoke the context and consequences of climate change. A representative of the Academy of Technologies discusses the risks of land-slips and dam failure, outlines that earthquakes only caused some cracks in dams, and evokes the legal context and organisation regarding dam safety. Possible effects of earthquakes in France are discussed. A second part addresses the way natural risks are taken into account in the protection of nuclear installations

  2. Installation NR-31R for neutron radiography

    International Nuclear Information System (INIS)

    NR-31R installation, intended for neutron radiography of extended radioactive items using horizontal neutron beam from the nuclear reactor of WWER-type, is described. The installation is located directly in the reactor hall. It comprises the following main units: collimator, radiographic chamber, two containers (upper and bottom), neutron beam trap, distance and local control pannels. Obtaining neutron images of the controlled items is possible at NR-31R installation both by the method of direct exposure, and by the transfer method

  3. Automation correlation installation on-line with a computer

    International Nuclear Information System (INIS)

    On the base of the SM-4 computer and CAMAC equipment the automatic three-dimensional spectrometer was made in order to carry out the correlation experiment at the U-240 cyclotron at the Institute for Nuclear Research, The Ukr. Ac. of Sci. A block-diagram of correlation installation, units of automatic equipment and software implemented for automatic installation procedure were described. A package of SPECTR programmes for interpretation of linear γ-spectra and γγ-coincidence spectra was established. Reslts of check experiments were cited

  4. NUCLEAR SAFETY DESIGN BASES FOR LICENSE APPLICATION

    Energy Technology Data Exchange (ETDEWEB)

    R.J. Garrett

    2005-03-08

    The purpose of this report is to identify and document the nuclear safety design requirements that are specific to structures, systems, and components (SSCs) of the repository that are important to safety (ITS) during the preclosure period and to support the preclosure safety analysis and the license application for the high-level radioactive waste (HLW) repository at Yucca Mountain, Nevada. The scope of this report includes the assignment of nuclear safety design requirements to SSCs that are ITS and does not include the assignment of design requirements to SSCs or natural or engineered barriers that are important to waste isolation (ITWI). These requirements are used as input for the design of the SSCs that are ITS such that the preclosure performance objectives of 10 CFR 63.111 [DIRS 156605] are met. The natural or engineered barriers that are important to meeting the postclosure performance objectives of 10 CFR 63.113 [DIRS 156605] are identified as ITWI. Although a structure, system, or component (SSC) that is ITS may also be ITWI, this report is only concerned with providing the nuclear safety requirements for SSCs that are ITS to prevent or mitigate event sequences during the repository preclosure period.

  5. Nuclear Safety Design Base for License Application

    Energy Technology Data Exchange (ETDEWEB)

    R.J. Garrett

    2005-09-29

    The purpose of this report is to identify and document the nuclear safety design requirements that are specific to structures, systems, and components (SSCs) of the repository that are important to safety (ITS) during the preclosure period and to support the preclosure safety analysis and the license application for the high-level radioactive waste (HLW) repository at Yucca Mountain, Nevada. The scope of this report includes the assignment of nuclear safety design requirements to SSCs that are ITS and does not include the assignment of design requirements to SSCs or natural or engineered barriers that are important to waste isolation (ITWI). These requirements are used as input for the design of the SSCs that are ITS such that the preclosure performance objectives of 10 CFR 63.111(b) [DIRS 173273] are met. The natural or engineered barriers that are important to meeting the postclosure performance objectives of 10 CFR 63.113(b) and (c) [DIRS 173273] are identified as ITWI. Although a structure, system, or component (SSC) that is ITS may also be ITWI, this report is only concerned with providing the nuclear safety requirements for SSCs that are ITS to prevent or mitigate event sequences during the repository preclosure period.

  6. Rules and regulations on ionizing radiations sources installations

    International Nuclear Information System (INIS)

    The finality of this legislative text is to establish the standards and procedures for site, design, building, operation and decommissioning of nuclear installations, radioactive installations and ionizing radiations sources. This text include the commercialization of radioactive substances and equipment fabrication

  7. Order implementing Section 18 of Decree no 75-306 of 28 April 1975 on the protection of workers against the hazards of ionizing radiations in large nuclear installations

    International Nuclear Information System (INIS)

    This Order was made in implementation of Decree No 75-306 of 28 April 1975 on the Protection of Workers Against the Hazards of Ionizing Radiations in Large Nuclear Installations and lays down that areas subject to special regulations or which are prohibited within each controlled area, in accordance with the above-mentioned Decree, are those where the equivalent dose rate for external radiation is likely to exceed 2.5 millirems per hour. The Order also lays down the way these areas should be marked. (NEA)

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

    Energy Technology Data Exchange (ETDEWEB)

    Kibrit, Eduardo

    2008-07-01

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

  9. ICT based training on nuclear technology applications in Tanzania

    International Nuclear Information System (INIS)

    Peaceful application of nuclear technology has contributed to socio-economic resource development in Tanzania. The Tanzania Atomic Energy Commission has taken some active steps for the incorporation and or adoption of ICT-based training modules in nuclear science and technology and its applications. The overall objective of this programme is to establish a sustainable national capability for using the potential of information communication technologies (ICTs) for training and education in the field of nuclear science and technology. This paper reviews some of the experience which the authors gained in the area of ICT based training in nuclear technology applications, it describes some of the challenges experienced, and some proposals to address the issues involved. (author)

  10. The detection of bulk explosives using nuclear-based techniques

    Energy Technology Data Exchange (ETDEWEB)

    Morgado, R.E.; Gozani, T.; Seher, C.C.

    1988-01-01

    In 1986 we presented a rationale for the detection of bulk explosives based on nuclear techniques that addressed the requirements of civil aviation security in the airport environment. Since then, efforts have intensified to implement a system based on thermal neutron activation (TNA), with new work developing in fast neutron and energetic photon reactions. In this paper we will describe these techniques and present new results from laboratory and airport testing. Based on preliminary results, we contended in our earlier paper that nuclear-based techniques did provide sufficiently penetrating probes and distinguishable detectable reaction products to achieve the FAA operational goals; new data have supported this contention. The status of nuclear-based techniques for the detection of bulk explosives presently under investigation by the US Federal Aviation Administration (FAA) is reviewed. These include thermal neutron activation (TNA), fast neutron activation (FNA), the associated particle technique, nuclear resonance absorption, and photoneutron activation. The results of comprehensive airport testing of the TNA system performed during 1987-88 are summarized. From a technical point of view, nuclear-based techniques now represent the most comprehensive and feasible approach for meeting the operational criteria of detection, false alarms, and throughput. 9 refs., 5 figs., 2 tabs.

  11. Compact Short-Pulsed Electron Linac Based Neutron Sources for Precise Nuclear Material Analysis

    Science.gov (United States)

    Uesaka, M.; Tagi, K.; Matsuyama, D.; Fujiwara, T.; Dobashi, K.; Yamamoto, M.; Harada, H.

    2015-10-01

    An X-band (11.424GHz) electron linac as a neutron source for nuclear data study for the melted fuel debris analysis and nuclear security in Fukushima is under development. Originally we developed the linac for Compton scattering X-ray source. Quantitative material analysis and forensics for nuclear security will start several years later after the safe settlement of the accident is established. For the purpose, we should now accumulate more precise nuclear data of U, Pu, etc., especially in epithermal (0.1-10 eV) neutrons. Therefore, we have decided to modify and install the linac in the core space of the experimental nuclear reactor "Yayoi" which is now under the decommission procedure. Due to the compactness of the X-band linac, an electron gun, accelerating tube and other components can be installed in a small space in the core. First we plan to perform the time-of-flight (TOF) transmission measurement for study of total cross sections of the nuclei for 0.1-10 eV energy neutrons. Therefore, if we adopt a TOF line of less than 10m, the o-pulse length of generated neutrons should be shorter than 100 ns. Electronenergy, o-pulse length, power, and neutron yield are ~30 MeV, 100 ns - 1 micros, ~0.4 kW, and ~1011 n/s (~103 n/cm2/s at samples), respectively. Optimization of the design of a neutron target (Ta, W, 238U), TOF line and neutron detector (Ce:LiCAF) of high sensitivity and fast response is underway. We are upgrading the electron gun and a buncher to realize higher current and beam power with a reasonable beam size in order to avoid damage of the neutron target. Although the neutron flux is limited in case of the X-band electron linac based source, we take advantage of its short pulse aspect and availability for nuclear data measurement with a short TOF system. First, we form a tentative configuration in the current experimental room for Compton scattering in 2014. Then, after the decommissioning has been finished, we move it to the "Yayoi" room and perform

  12. Sub-Critical Nuclear Reactor Based on FFAG-Accelerator

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Hee Seok; Kang, Hung Sik; Lee, Tae Yeon [Pohang Accelerator Laboratory, Pohang (Korea, Republic of)

    2011-10-15

    After the East-Japan earthquake and the subsequent nuclear disaster, the anti-nuclear mood has been wide spread. It is very unfortunate both for nuclear science community and for the future of mankind, which is threatened by two serious challenges, the global warming caused by the greenhouse effect and the shortage of energy cause by the petroleum exhaustion. While the nuclear energy seemed to be the only solution to these problems, it is clear that it has its own problems, one of which broke out so strikingly in Japan. There are also other problems such as the radiotoxic nuclear wastes that survive up to even tens of thousands years and the limited reserves of Uranium. To solve these problems of nuclear fission energy, accelerator-based sub-critical nuclear reactor was once proposed. (Its details will be explained below.) First of all, it is safe in a disaster such as an earthquake, because the deriving accelerator stops immediately by the earthquake. It also minimizes the nuclear waste problem by reducing the amount of the toxic waste and shortening their half lifetime to only a few hundred years. Finally, it solves the Uranium reserve problem because it can use Thorium as its fuel. The Thorium reserve is much larger than that of Uranium. Although the idea of the accelerator-driven nuclear reactor was proposed long time ago, it has not been utilized yet first by technical difficulty and economical reasons. The accelerator-based system needs 1 GeV, 10 MW power proton accelerator. A conventional linear accelerator would need several hundred m length, which is highly costly particularly in Korea because of the high land cost. However, recent technologies make it possible to realize that scale accelerator by a reasonable size. That is the fixed-field alternating gradient (FFAG) accelerator that is described in this article

  13. The evaluation of the nuclear facilities safety at the CEA from 1999 to 2001; Le bilan de la surete des installations nucleaires du CEA du 1999 a 2001

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2002-11-01

    The aim of this document is the presentation of an evaluation of the problems and the safety methods in the concerned period. The first chapter presents the nuclear safety in the CEA. The second chapter is devoted to the organization and the quality for the safety: liabilities, audits, relations with the safety authorities and with the public. The chapters three and four deal respectively with the methodological and technical abilities supporting the exploitation teams and with the nuclear safety projects. The last chapter presents the experiments and events from 1999 to 2001. (A.L.B.)

  14. Calculation of an analytical memory for the installation of a PET-CT equipment in the Nuclear Medicine Department of the National Institute of Cancerology

    International Nuclear Information System (INIS)

    The studies with a PET-CT equipment combines the metabolic information that provides the Positron Emission Tomography technique (PET), with the morphological data offered by the Computerized Tomography (CT). In Mexico, it will have the first PET-CT equipment, for a public service hospital. Since that makes use of radioactive material (emission of annihilation photons with 511 keV) and X rays, is necessary to calculate the necessary shielding for the PET-CT equipment room and for the area where it is managed or have presence of radioactive material (mainly fluorodeoxyglucose labelled with F-18, i.e. FDG-F18). It is presented a summary of the calculations and necessary considerations so that the shielding allows to fulfill with the official doses limits in Mexico (50 mSv/year for Occupationally Exposure Personnel, OEP and 5 mSv/year for public in general), taking into account the adjacent areas to the installation. It is concluded with the shielding thickness required for the walls and roof of the installation, having a maximum of 20 cm of concrete (ρ = 2.35 g/cm3) for the administration room of radioactive material to the patients and a minimum of 1 mm of lead for the room of the PET-CT equipment, having taken into account the dimensions of each area. (Author)

  15. Knowledge based diagnostics in nuclear power plants

    International Nuclear Information System (INIS)

    In the paper to be given a special process diagnostic system (PDS) will be presented, taking into account corresponding user experiences. It must be seen the result of a long term work on computerized process surveillance and control on NPP; it includes a model based system for noise analysis of mechanical vibrations, which has been enhanced by using of knowledge based technique (expert systems). The paper will discuss the process diagnostic frame concept and emphasize the vibration analysis expertsystem RADEX, with the parts modelling (building a knowledge base), man-machine communication aspects, implementation. (author). 5 refs, 5 figs

  16. Design and construction of a type testing and production test facility for HEPA filters to be installed in ventilation systems of German nuclear power plants

    International Nuclear Information System (INIS)

    High-efficiency particulate air filters (HEPA filters) in nuclear plants frequently constitute part of the last barrier separating potentially contaminated areas from the environment. Their failure may cause radioactive substances to be released. The sensitivity of the filter media employed, and the problems associated with manufacturing the HEPA filters normally used in nuclear plants, result in considerable differences in the quality of commercial HEPA filters. Aging of filter components during operation may greatly reduce the loading capacity of the entire filter. A relatively large number of HEPA filters were found to be defective at the end of service life. In order to be able to guarantee the removal efficiency of HEPA filters over a sufficient length of service life and under accident conditions, quality control measures must be introduced. Type tests of the HEPA filters to be used in nuclear plants must include a number of criteria beyond the loads imposed by the rated volumetric flow rate under the usual room air conditions. These criteria have been combined in a special type test (DIN 25 414), and passing this test should be made a prerequisite for the use of HEPA filters in nuclear plants. In addition, random inspections of production HEPA filters should be carried out to allow an adequate standard of quality to be guaranteed for a long time. (orig./GL)

  17. Solar Installation Labor Market Analysis

    Energy Technology Data Exchange (ETDEWEB)

    Friedman, B.; Jordan, P.; Carrese, J.

    2011-12-01

    The potential economic benefits of the growing renewable energy sector have led to increased federal, state, and local investments in solar industries, including federal grants for expanded workforce training for U.S. solar installers. However, there remain gaps in the data required to understand the size and composition of the workforce needed to meet the demand for solar power. Through primary research on the U.S. solar installation employer base, this report seeks to address that gap, improving policymakers and other solar stakeholders understanding of both the evolving needs of these employers and the economic opportunity associated with solar market development. Included are labor market data covering current U.S. employment, expected industry growth, and employer skill preferences for solar installation-related occupations. This study offers an in-depth look at the solar installation sectors. A study published by the Solar Foundation in October 2011 provides a census of labor data across the entire solar value chain.

  18. Application of condition based maintenance to nuclear power plants

    International Nuclear Information System (INIS)

    Device Karte management system which supports application of condition based maintenance to nuclear power plants has been developed. The purpose of this system is to support maintenance personnel in device inspection scheduling based on operating condition monitoring and maintenance histories. There are four functions: field database, degradation estimation, inspection time decision and maintenance planning. The authors have been applying this system to dozens of devices of Onagawa Nuclear Power Station Unit No. 1 for one year. This paper represents the system concept and its application experiences. (author)

  19. Characterization of a Planetary Boundary Layer model to evaluate radionuclides releases in nuclear installations; Caracterizacao de um modelo de camada limite planetaria para avaliar liberacoes de radionuclideos em instalacoes nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Molnary, Leslie de

    1993-07-01

    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. Method for installing submarine pipelines using a marine railway system

    International Nuclear Information System (INIS)

    A method of installing a cold water conduit for use with Ocean Thermal Energy Conversion (OTEC), fossil or nuclear power plants comprises installing a marine railway system on the ocean floor and subsequently using the railway system as an aid to the installation of the cold water conduit and as a support structure for the conduit

  1. Systems-based modeling of generation variability under alternate geographic configurations of photovoltaic (PV) installations in Virginia

    International Nuclear Information System (INIS)

    With increased focus on renewable energy in our modern era, it is increasingly important to understand the impact of policies on the performance and reliability of regional energy systems. This research develops a model to understand how geographic dispersion of PV installations impacts the reliability of electricity generated from the total PV network, measured by the variance of the distribution of generated electricity. Using NREL data, beta probability distributions of sunlight (kWh/m2/day) in various regions of Virginia are estimated using a fitting method that minimizes the Kolmogorov-Smirnov test statistic. A Monte Carlo simulation model is developed to measure PV electricity generation from multiple centralized and dispersed configurations over 100,000 days of probabilistic sunlight. There is a calculable tradeoff between average generation and generation variability, and increased geographic dispersion of PV installations can decrease this variability. Controlling variable generation through policies that promote efficient PV siting can help provide reliable power, minimizing the need for load-balancing peaking power infrastructure and costly electricity purchases from the grid. Using a tradeoff framework of generation and costs, this paper shows that geographically dispersed generation can mitigate the risk of unreliable solar generation that can significantly impact the end-user costs and make PV infrastructure unattractive. - Highlights: → We model how uncertain sunlight affects generation of different PV systems. → We show that geographically dispersed systems decrease generation variability. → Geographically dispersed PV systems are potentially more costly in the short run. → Controlling variability provides reliable power, which can decrease long-run costs. → Promoting mixes of uncertain energy sources requires assessment of these tradeoffs.

  2. Primary system fission product release and transport. A state-of-the-art report to the committee on the safety of nuclear installations

    International Nuclear Information System (INIS)

    This report presents a summary of the status of research activities associated with fission product behavior (release and transport) under severe accident conditions within the primary systems of water-moderated and water-cooled nuclear reactors. For each of the areas of fission product release and fission product transport, the report summarizes relevant information on important phenomena, major experiments performed, relevant computer models and codes, comparisons of computer code calculations with experimental results, and general conclusions on the overall state of the art. Finally, the report provides an assessment of the overall importance and knowledge of primary system release and transport phenomena and presents major conclusions on the state of the art

  3. Primary system fission product release and transport: A state-of-the-art report to the committee on the safety of nuclear installations

    International Nuclear Information System (INIS)

    This report presents a summary of the status of research activities associated with fission product behavior (release and transport) under severe accident conditions within the primary systems of water-moderated and water-cooled nuclear reactors. For each of the areas of fission product release and fission product transport, the report summarizes relevant information on important phenomena, major experiments performed, relevant computer models and codes, comparisons of computer code calculations with experimental results, and general conclusions on the overall state of the art. Finally, the report provides an assessment of the overall importance and knowledge of primary system release and transport phenomena and presents major conclusions on the state of the art

  4. 16. national conference of the presidents of the local commissions of information (C.L.I.) around nuclear facilities; 16. conference nationale des presidents de commissions locales d'information (CLI) autour des installations nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-07-01

    This conference contained two plenary sessions. The first one concerned the epidemiology with the following subjects: the epidemiology, its contributions and its limits; the epidemiological surveillance of cancers in France: role of registers within the device; the aggregates of leukaemia near the nuclear installations; perception and management of the risk; the point of view of the scientific committee of the A.N.C.L.I.; Followed a work in a workshop on the subjects relative to the functioning of the C.L.I. (Organization, relations, information) then the second plenary session with as subjects: organization and functioning of C.L.I., relations and links with A.N.C.L.I., information received and diffused by the C.L.I. (N.C.)

  5. Nuclear liability legislation in Ukraine

    International Nuclear Information System (INIS)

    The present report contains certain information concerning the current situation dealing with provision of nuclear and radiation safety during the performance of all types of activity associated with nuclear installations, facilities of radioactive waste management and utilization of ionizing radiation sources in 1999. We try to make a concise analysis o legal bases of ensuring safety and to present general information concerning the Nuclear Insurance Pool of Ukraine. (author)

  6. Condition based maintenance of the motor operated valve in nuclear power plant

    International Nuclear Information System (INIS)

    Approximately 20,000 valves are installed in each nuclear power plant and the inspection by TBM had been adapted mainly. With the application of the new inspection system that has been implemented from January 2009, the need for adapting method conforming to CBM has been examined to optimize the conservation activities in the nuclear power plants. The method of condition monitoring for motor-operated valve with the new diagnosis device and the effectiveness are to be addressed in the speech. (author)

  7. Knowledge Based Help desk System in Nuclear Malaysia

    International Nuclear Information System (INIS)

    Knowledge based (K-based) Help desk system is a knowledge oriented web based system that provides support to business process of the technical service providers. It is a multi-centric system which focuses on end-users, technical workers and higher level management through utilization of knowledge which resides and grows within the system. The objectives of the system are to be a user-friendly, capture technical knowledge for efficient performance and educating users for self reliance. These were achieved through the improvement of the help desk business process and better management of technical knowledge. This system has been tested and implemented in Information Technology Center (IT), Engineering Division (BKJ) and Instrumentation and Automation Center (IAC) at the Malaysian Nuclear Agency (Nuclear Malaysia). Higher levels of user satisfaction and faster growth in technical knowledge repository have been recorded in the system. This paper describes the help desk system in the perspective of management of its technical knowledge contributing to strengthening organizational knowledge asset of Nuclear Malaysia as national nuclear research institution. (Author)

  8. An internet-based teaching file on clinical nuclear medicine

    International Nuclear Information System (INIS)

    Objective: The goal of this project was to develop an internet-based interactive digital teaching file on nuclide imaging in clinical nuclear medicine, with the capability of access to internet. Methods: On the basis of academic teaching contents in nuclear medicine textbook for undergraduates who major in nuclear medicine, Frontpage 2000, HTML language, and JavaScript language in some parts of the contents, were utilized in the internet-based teaching file developed in this study. Results: A practical and comprehensive teaching file was accomplished and may get access with acceptable speed to internet. Besides basic teaching contents of nuclide imagings, a large number of typical and rare clinical cases, questionnaire with answers and update data in the field of nuclear medicine were included in the file. Conclusion: This teaching file meets its goal of providing an easy-to-use and internet-based digital teaching file, characteristically with the contents instant and enriched, and with the modes diversified and colorful

  9. Theme day: corrosion and surface treatments in nuclear facilities. Proceedings; Journee Thematique: Corrosion et Traitements de surface dans les Installations Nucleaires. Recueil des presentations

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2012-02-15

    This document brings together the available presentations given at the theme day organized by the Bourgogne Nuclear Pole on the topic of corrosion and surface treatments in nuclear facilities. Eleven presentations (slides) are compiled in this document: 1 - Introduction - PNB centre of competitiveness and R and D activities (A. Mantovan, PNB); 2 - Corrosion damage (M. Foucault, Areva NP - Centre Technique Le Creusot); 3 - Corrosion mechanisms (R. Oltra, UB-ICB); 4 - Examples of expertise management (C. Duret-Thual, Institut de la corrosion/Corrosion Institute); 5 - General framework of surface treatments (C. Nouveau, ENSAM Cluny Paris Tech); 6 - Surfaces et interfaces characterisation - Part A (C. Langlade, Y. Gachon, UTBM and HEF); 7 - Surfaces et interfaces characterisation - Part B (C. Langlade, Y. Gachon, UTBM and HEF); 8 - Ion beam surface treatment (Y. Le Guellec, Quertech Ingenierie); 9 - Impact surface treatment (G. Saout, Sonats); 10 - Metal oxides Characterisation by US laser (R. Oltra, UB-ICB); 11 - Detection and Characterisation of intergranular corrosion (Y. Kernin, Stephane Bourgois, Areva Intercontrole)

  10. Surveillance monitoring of Qinshan nuclear power base external environment

    International Nuclear Information System (INIS)

    The practice of surveillance monitoring in the recent 18 years for Qinshan Nuclear Power Base external environment was mainly introduced in the article, including the monitoring of the real-time γ radiation level around Qinshan NPP, the available gathering of all kinds of environmental medium samples, and the analysis of the radionuclide in the samples. The monitoring results of the changing trends of the environmental radiation around Qinshan NPP were also introduced in the sequence of the γ environmental radiation dose rates, the radionuclide in the air, water, soil, soil of tideland and the radionuclide in the biology samples, then the suggestions were advanced to strengthen the supervisory monitoring about the effluent of the nuclear power plant, and make a regulations of surveillance monitoring for environmental nuclear radiation as soon as possible. (authors)

  11. Broken Arrows: Radiological hazards from nuclear warhead accidents (the Minot USAF base nuclear weapons incident)

    CERN Document Server

    Liolios, Theodore

    2009-01-01

    According to numerous press reports, in 2007 at Minot US Air Force Base six AGM-129 Advanced Cruise Missiles mistakenly armed with W80-1 thermonuclear warheads were loaded on a B-52H heavy bomber in place of six unarmed AGM-129 missiles that were awaiting transport to Barksdale US Air Force Base for disposal. The live nuclear missiles were not reported missing, and stood unsecured and unguarded while mounted to the aircraft for a period of 36 hours. The present work investigates the radiological hazards associated with a worst-case postulated accident that would disperse the nuclear material of the six warheads in large metropolitan cities. Using computer simulations approximate estimates are derived for the ensuing cancer mortality and land contamination after the accident. Health, decontamination and evacuation costs are also estimated in the framework of the linear risk model.

  12. LHC installation planning

    CERN Document Server

    Weisz, S

    2005-01-01

    installation of the general services, the installation of the cryogenic line (QRL), the installation of the machine elements and the hardware commissioning. While the installation of the general services is now almost finished (see presentation by Katy Foraz and Serge Grillot), several problems and delays with the QRL made it unavoidable to revise the installation strategy and to schedule a number tasks in parallel. A new compressed installation planning has been issued, that fulfils the strategic objectives and allows starting new activities with minimal delays in sectors 7-8 and 8-1. However, the shortcuts that are introduced increase the level of risk that we will have to face and the coordination of such a large and complex variety of simultaneous activities makes the project even more challenging. The document will describe how the input from the different equipment groups is taken into account by the master schedule planning team with respect to equipment availability and production as well as logistics...

  13. Getting Good Installation Guides

    OpenAIRE

    Karlström, Erik; Nydén, Johan

    2010-01-01

    Implementations and installations of Enterprise Resource Planning systems (ERP-systems)are often time consuming and complex processes. Technicians who workwith installations of ERP-systems require tools and utilities in order to perform theirwork in a time efficient and qualitative manner.This study is performed at the company Industrial and Financial Systems (IFS) inLinköping and has focused on the technical documentation that describes theinstallation process, "IFS Installation Guide". This...

  14. Electrical installation calculations

    CERN Document Server

    Watkins, AJ

    2006-01-01

    Designed to provide a step by step guide to successful application of the electrical installation calculations required in day to day electrical engineering practice, the Electrical Installation Calculations series has proved an invaluable reference for over forty years, for both apprentices and professional electrical installation engineers alike.Now in its seventh edition, Volume 1 has been fully updated to meet the requirements of the 2330 Level 2 Certificate in Electrotechnical Technology from City & Guilds, and will also prove a vi

  15. A knowledge based method for nuclear plant loading pattern determination

    International Nuclear Information System (INIS)

    This paper deals with the design of a knowledge based system for solving an industrial problem which occurs in nuclear fuel management. The problem lies in determining satisfactory loading patterns for nuclear plants. Its primary feature consists in the huge search space involved. Conventional resolution processes are formally defined and analyzed: there is no general algorithm which guarantees to always provide a reasonable solution in each situation. We propose a new approach to solve this constrained search problem using domain-specific knowledge and general constraint-based heuristics. During a preprocessing step, a problem dependent search algorithm is designed. This procedure is then automatically implemented in FORTRAN. The generated routines have proved to be very efficient finding solutions which could not have been provided using logic programming. A prototype expert system has already been applied to actual reload pattern searches. While combining efficiency and flexibility, this knowledge based system enables human experts to rapidly match new constraints and requirements

  16. Developing competence based qualification system in the nuclear energy sector

    Energy Technology Data Exchange (ETDEWEB)

    Ceclan, Mihail [European Commission, Petten (Netherlands). Inst. for Energy and Transport

    2016-04-15

    The Institute for Energy and Transport of the Joint Research Centre, European Commission, developed a strategy and road map for ECVET implementation. The JRC road map for European Credit System for Vocational Education and Training (ECVET) implementation has reached the stage of Competence-Based Qualification System development. The Competence-Based Qualification System can help bridge the gap between Human Resources demand and supply in the nuclear market by structuring qualifications in small independent parts. This very specific ECVET feature of a qualification, facilitates the process of competences accumulation and the lifelong learning, mobility and flexible learning pathways. New developments are presented about the Competence-Based Qualification System development for the nuclear energy sector.

  17. Developing competence based qualification system in the nuclear energy sector

    International Nuclear Information System (INIS)

    The Institute for Energy and Transport of the Joint Research Centre, European Commission, developed a strategy and road map for ECVET implementation. The JRC road map for European Credit System for Vocational Education and Training (ECVET) implementation has reached the stage of Competence-Based Qualification System development. The Competence-Based Qualification System can help bridge the gap between Human Resources demand and supply in the nuclear market by structuring qualifications in small independent parts. This very specific ECVET feature of a qualification, facilitates the process of competences accumulation and the lifelong learning, mobility and flexible learning pathways. New developments are presented about the Competence-Based Qualification System development for the nuclear energy sector.

  18. Licensing framework of storage for spent fuel installation in Indonesia

    International Nuclear Information System (INIS)

    Full text: Indonesia has operated three research reactors i.e. TRIGA 2000 reactor at Bandung, Kartini reactor at Yogyakarta and Multi Purpose Reactor-GA Siwabesy (MPR-GAS) at Serpong. Besides Indonesia has also operated some nuclear installations such as radioisotope production installation, radio-metallurgy installation, and transfer channel-interim storage for spent fuel installation (TC-ISFSFI ). While being operated for research activities, reactors produce spent fuel that has the potential for radiation hazard. The utilities shall collect spent fuel temporarily throughout the life time of reactor. To control the spent fuel storage according to requirements (Act No. 10 year 1997 article 24.2), the National Nuclear Energy Agency (BATAN) has constructed the TC-ISFSFI, managed by the Center for Development of Research Reactor Technology (CDRRT). TC-ISFSFI is intended to collect spent fuel and other irradiated materials produced by MPR-GAS, the radioisotope production installation, the radio-metallurgy installation and other institutions. The control of TC-ISFSFI is conducted by the regulatory body (BAPETEN). It is implemented by establishing regulations, carrying out licensing and performing inspections. The TC-ISFSFI shall be subjected to licensing. According to the Act (No. 10 year 1997 article 17), the construction and operation of nuclear reactors and other nuclear installations as well as the decommissioning of nuclear reactors shall be subjected to the licensing. Implementation of the Act, especially the licensing regulations, includes the Chairman Decree of Bapeten (CD) No. 06 year 1999 on the Licensing Construction and Operation of Nuclear Reactor. In performing a review of the licensing requirements, BAPETEN uses government regulations and the other regulations on nuclear and radiation safety such as: - Government Regulation (GR) No. 64 year 2000 on Licensing of Nuclear Energy Utilization, - Government Regulation No. 27 year 2002 on Radioactive Waste

  19. Nuclear safety and radiation protection report of the Tricastin operational hot base nuclear facilities - 2013

    International Nuclear Information System (INIS)

    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 Tricastin operational hot base facility (INB no. 157, Bollene, Vaucluse (FR)), a nuclear workshop for storage and maintenance and qualification operations on some EdF equipments. Then, the nuclear safety and radiation protection measures taken regarding the facility 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 2013, if some, are reported as well as the effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facility is presented and sorted by type of waste, quantities and type of conditioning. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions

  20. Report by the AERES on the unit: Unit of researches on neutron transport and radioactivity confinement in nuclear installations under the supervision of the establishments and bodies: IRSN

    International Nuclear Information System (INIS)

    This report is a kind of audit report on a research laboratory whose activity is organized in three departments: neutron transport and criticality (themes: numerical methods, maths and statistics related to the simulation of neutral particle propagation, nuclear data, uncertainty propagation and bias estimation, code qualification and associated experimental programs, neutron transport in reactors and fuel cycle, criticality accidents), radionuclide transfer in radioactive waste disposals (site identification strategy, hydro-mechanical phenomena affecting storage performance, physical-chemical evolution factors, storage modelling), and metrology and confinement of radioactive gases and aerosols. The authors discuss an assessment of the unit activities in terms of strengths and opportunities, aspects to be improved and recommendations, productions and publications. A more detailed assessment is presented for each department in terms of scientific quality, influence and attractiveness (awards, recruitment capacity, capacity to obtain financing and to tender, participation to international programs), strategy and governance, and project

  1. Electrical installation calculations basic

    CERN Document Server

    Kitcher, Christopher

    2013-01-01

    All the essential calculations required for basic electrical installation workThe Electrical Installation Calculations series has proved an invaluable reference for over forty years, for both apprentices and professional electrical installation engineers alike. The book provides a step-by-step guide to the successful application of electrical installation calculations required in day-to-day electrical engineering practice. A step-by-step guide to everyday calculations used on the job An essential aid to the City & Guilds certificates at Levels 2 and 3Fo

  2. Electrical installations and regulations

    CERN Document Server

    Whitfield, J F

    1966-01-01

    Electrical Installations and Regulations focuses on the regulations that apply to electrical installations and the reasons for them. Topics covered range from electrical science to alternating and direct current supplies, as well as equipment for providing protection against excess current. Cables, wiring systems, and final subcircuits are also considered, along with earthing, discharge lighting, and testing and inspection.Comprised of 12 chapters, this book begins with an overview of electrical installation work, traits of a good electrician, and the regulations governing installations. The r

  3. Electrical installation calculations advanced

    CERN Document Server

    Kitcher, Christopher

    2013-01-01

    All the essential calculations required for advanced electrical installation workThe Electrical Installation Calculations series has proved an invaluable reference for over forty years, for both apprentices and professional electrical installation engineers alike. The book provides a step-by-step guide to the successful application of electrical installation calculations required in day-to-day electrical engineering practiceA step-by-step guide to everyday calculations used on the job An essential aid to the City & Guilds certificates at Levels 2 and 3For apprentices and electrical installatio

  4. "Life without nuclear power": A nuclear plant retirement formulation model and guide based on economics. San Onofre Nuclear Generating Station case: Economic impacts and reliability considerations leading to plant retirement

    Science.gov (United States)

    Wasko, Frank

    Traditionally, electric utilities have been slow to change and very bureaucratic in nature. This culture, in and of itself, has now contributed to a high percentage of United States electric utilities operating uneconomical nuclear plants (Crooks, 2014). The economic picture behind owning and operating United States nuclear plants is less than favorable for many reasons including rising fuel, capital and operating costs (EUCG, 2012). This doctoral dissertation is specifically focused on life without nuclear power. The purpose of this dissertation is to create a model and guide that will provide electric utilities who currently operate or will operate uneconomical nuclear plants the opportunity to economically assess whether or not their nuclear plant should be retired. This economic assessment and stakeholder analysis will provide local government, academia and communities the opportunity to understand how Southern California Edison (SCE) embraced system upgrade import and "voltage support" opportunities to replace "base load" generation from San Onofre Nuclear Generating Station (SONGS) versus building new replacement generation facilities. This model and guide will help eliminate the need to build large replacement generation units as demonstrated in the SONGS case analysis. The application of The Nuclear Power Retirement Model and Guide will provide electric utilities with economic assessment parameters and an evaluation assessment progression needed to better evaluate when an uneconomical nuclear plant should be retired. It will provide electric utilities the opportunity to utilize sound policy, planning and development skill sets when making this difficult decision. There are currently 62 nuclear power plants (with 100 nuclear reactors) operating in the United States (EIA, 2014). From this group, 38 are at risk of early retirement based on the work of Cooper (2013). As demonstrated in my model, 35 of the 38 nuclear power plants qualify to move to the economic

  5. Wind power installations in Switzerland - Regional planning basics and impact; Eoliennes en Suisse. Bases de planification pour l'amenagement du territoire et effets. Rapport de base

    Energy Technology Data Exchange (ETDEWEB)

    Ott, W.; Kaufmann, Y.; Steiner, P. [Econcept AG, Zuerich (Switzerland); Gilgen, K.; Sartoris, A. [IRAP-HSR, Institut fuer Raumentwicklung an der Hochschule fuer Technik Rapperswil, Rapperswil (Switzerland)

    2008-07-01

    This report published by the Swiss Federal Office of Energy (SFOE) takes a look at the basics of regional planning and its impact on the construction of wind-energy installations in Switzerland. The authors state that the planning and realisation of wind turbine installations is often time and resource consuming: this document presents and discusses the results obtained in a project that aimed to supply consolidated knowledge on project-relevant basics and their effect with respect to wind-energy installations. Experience gained in Switzerland and in other countries is discussed. This report on the basics of wind-energy planning with its detailed information formed the basis of a checklist described in a further report. In nine chapters, regional planning aspects, environment and landscape-relevant aspects, effects on the national and regional economies and social acceptance factors are discussed. Also, success-factors and possible solutions for the successful realisation of wind-energy projects are looked at.

  6. Polarized nuclear target based on parahydrogen induced polarization

    Energy Technology Data Exchange (ETDEWEB)

    Budker, D., E-mail: dbudker@gmail.com [Department of Physics, University of California at Berkeley, Berkeley, CA 94720-7300 (United States); Nuclear Science Division, Lawrence Berkeley National Laboratory, Berkeley, CA 94720 (United States); Ledbetter, M.P. [Department of Physics, University of California at Berkeley, Berkeley, CA 94720-7300 (United States); Appelt, S. [Central Institute for Electronics, Research Center Juelich, D-52425 Juelich (Germany); Bouchard, L.S. [Department of Chemistry and Biochemistry, California NanoSystems Institute, Biomedical Engineering IDP, Jonsson Comprehensive Cancer Center, University of California, Los Angeles, CA 90095 (United States); Wojtsekhowski, B. [Thomas Jefferson National Accelerator Facility, Newport News, VA 23606 (United States)

    2012-12-01

    We discuss a novel concept of a polarized nuclear target for accelerator fixed-target scattering experiments, which is based on parahydrogen induced polarization (PHIP). One may be able to reach a 33% free-proton polarization in the ethane molecule. The potential advantages of such a target include operation at zero magnetic field, fast ({approx}100Hz) polarization oscillation (akin to polarization reversal), and operation with large intensity of an electron beam. -- Highlights: Black-Right-Pointing-Pointer Novel concept for polarized nuclear targets. Black-Right-Pointing-Pointer The target features fast reversal and operates at near-zero magnetic field. Black-Right-Pointing-Pointer Based on the technique of parahydrogen induced polarization that is revolutionizing NMR and enables NMR/MRI without magnets. Black-Right-Pointing-Pointer Competitive figure-of-merit for polarized targets.

  7. Development of a severe accident module of a nuclear power plant based in the MELCOR nuclear code and its incorporation to the room simulator

    International Nuclear Information System (INIS)

    This work describes the development of the Severe Accidents Module (MAS) based on the Code MELCOR and its incorporation to the Simulator of Classroom of the Group of Nuclear Engineering of the Engineering Faculty (GrINFI) of the National Autonomous University of Mexico (UNAM). The module of Severe Accidents has the purpose of counting with installed and operational capacity for the simulation of accident sequences with capacitation purposes, training, analysis and design. A shallow description of SimAula is presented, and the philosophy used to obtain the interactive version of MELCOR are discussed, as well as its implementation in the atmosphere of SimAula. Finally, after confirming the correct operation of the development of the tool, some possible topics are discussed for specific applications of the MAS. (Author)

  8. Estimating SCR installation costs

    Energy Technology Data Exchange (ETDEWEB)

    Marano, M.; Sharp, G. [American Electric Power (United States)

    2006-01-15

    The EUCG surveyed 72 separate US installations of selective catalytic reduction (SCR) systems at coal-fired units totalling 41 GW of capacity to identify the systems' major cost drivers. The results, summarized in this article, provide excellent first-order estimates and guidance for utilities considering installing the downstream emissions-control technology. 4 figs., 1 tab.

  9. Polarized nuclear target based on parahydrogen induced polarization

    Energy Technology Data Exchange (ETDEWEB)

    D. Budker, M.P. Ledbetter, S. Appelt, L.S. Bouchard, B. Wojtsekhowski

    2012-12-01

    We discuss a novel concept of a polarized nuclear target for accelerator fixed-target scattering experiments, which is based on parahydrogen induced polarization (PHIP). One may be able to reach a 33% free-proton polarization in the ethane molecule. The potential advantages of such a target include operation at zero magnetic field, fast ({approx}100 HZ) polarization oscillation (akin to polarization reversal), and operation with large intensity of an electron beam.

  10. Prof. Cristoforo Benvenuti stands in front of solar panels installed on the roof of Geneva airport. These panels, produced by the commpany SRB, are based on a technology developed at CERN by Cristoforo Benvenuti.

    CERN Document Server

    Maximilien Brice

    2012-01-01

    Prof. Cristoforo Benvenuti stands in front of solar panels installed on the roof of Geneva airport. These panels, produced by the commpany SRB, are based on a technology developed at CERN by Cristoforo Benvenuti.

  11. Physical Protection Study of the Radio metallurgy Installation Using SAVIComputer Program

    International Nuclear Information System (INIS)

    Based on IAEA Recommendation on INFCIR/225/Rev.3 (The Physical Protectionof Nuclear Material), a nuclear installation shall have physical protectionsystem for protection or being secure on sabotage activities in theinstallation and thieve of nuclear materials. The recommendation states therequirements for physical protection of nuclear materials usage, transit andstorage. Radio metallurgy Installation of the Fuel Element and ReprocessingDevelopment Center (BATAN) at Serpong is a nuclear installation for researchon post irradiation of high radioactive spent fuel element, its processingand storage. The installation has risk on threat of a sabotage, which isdominant than thieve. The RMI building was designed and constructed ofphysical protection components and have been integrated with the BATAN Safetyand Security System and the Security Guards functions to be PhysicalProtection System for the RMI. By using the SAVI Computer Program with inputdata from the existing standards, assumptions for detection possibility,delay and response, that will result the probability of interruptions of theworst adversary paths PI = 0.1. These mean that the physical protectionsystems of the RMI shall be upgraded and improved in order to be reliable orbetter if the most of paths to the target PI = 1.0. (author)

  12. Recent progress in EDF-based methods applied to nuclear properties

    Directory of Open Access Journals (Sweden)

    Khan E.

    2014-03-01

    Full Text Available Recent results obtained with energy density functional (EDF based methods are presented, focused on the nuclear phenomenology. EDF approaches aim for an universal description of the nuclear phenomena over the nuclear chart. Achievements from large to small nuclear systems are depicted: equation of state of nuclear matter, heavy and light nuclei. Dynamical aspects such as nuclear excitations, decay and reactions are also presented. EDF methods are progressing towards an unified and systematic description of the rich variety of the nuclear phenomena such as quantum liquid and cluster states, or nuclear structure and reactions.

  13. Recent progress in EDF-based methods applied to nuclear properties

    International Nuclear Information System (INIS)

    Recent results obtained with energy density functional (EDF) based methods are presented, focused on the nuclear phenomenology. EDF approaches aim for an universal description of the nuclear phenomena over the nuclear chart. Achievements from large to small nuclear systems are depicted: equation of state of nuclear matter, heavy and light nuclei. Dynamical aspects such as nuclear excitations, decay and reactions are also presented. EDF methods are progressing towards an unified and systematic description of the rich variety of the nuclear phenomena such as quantum liquid and cluster states, or nuclear structure and reactions. (author)

  14. Measures for Equipment Installation in Nuclear Power Plant CI Main Building%核电厂常规岛主厂房设备安装保证措施研究

    Institute of Scientific and Technical Information of China (English)

    武春霖; 金欣

    2014-01-01

    阐述了AP1000核电是目前世界上最先进的核电堆型之一,海水冷却的常规岛 CI (Conventional Island)主厂房多采用半地下结构,在CI主厂房内的凝汽器、发电机定子、汽水分离再热器、除氧器等设备的重量和外形尺寸均比常规火电的设备重和大,其吊装措施在CI主厂房设计时应综合考虑,对施工质量和工程进度都是有益的。介绍了某AP1000核电厂设备安装的CI主厂房设计与设备安装的配合,为相关工程建设、设计者提供参考。%AP1000 unit is one of the most advanced nuclear reactors at present. The main building of sea water cooling CI (Conventional Island) is mostly of the semi-underground structure. The weight and dimension of CI major equipment in the main building, such as condenser,generator stator,MSR and deaerator etc. are bigger than that of the fossil power plant. In order to ensurre the construction quality and schedule,the equipment installation plan should be considered sufficiently. This paper introduced the design of CI main building and its influence on equipment installation for further reference to other designers.

  15. Scaling of a break small in the hot field of the LSTF installation to a nuclear power plant; Escalado de una rotura pequena en la rama caliente de la instacions LSTF a una central nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Querol, A.; Gallardo, S.; Verdu, G.

    2014-07-01

    The objective of this work is to study if the phenomenology observed during in one break small in the hot branch of a small scale, such as Large Scale Test installation Facility (LSTF), can be extrapolated to a real plant. To do so, is considered the experiment 1-2 of the OECD/NEA rose, which simulates a break in the hot field of 1%, and the code project Thermo-hydraulic TRACE5 to reproduce the LSTF facility and a real plant and thus, power compare the results. They have been considered two models for the actual plant: a scaled model of the LSTF facility while preserving the relationship of power and volume of original LSTF and a typical model Westinghouse PWR of 3 loops. The results obtained show that the scaling LSTF and LSTF installation models reproduce the same behavior during the transient. However, with the Westinghouse model 3 ties there are important differences. The most important thing is that natural circulation does not play properly. The effect of the nodalization of U-tubes and the vessel has been in improving outcomes. The results obtained show that the nodalization of U-tubes affects the reproduction of natural circulation, while the nodalization of the vessel does not have a relevant effect. (Author)

  16. Technical bases for interim storage of spent nuclear fuel

    International Nuclear Information System (INIS)

    The experience base for water storage of spent nuclear fuel has evolved since 1943. The technology base includes licensing documentation, standards, technology studies, pool operator experience, and documentation from public hearings. That base reflects a technology which is largely successful and mundane. It projects probable satisfactory water storage of spent water reactor fuel for several decades. Interim dry storage of spent water reactor fuel is not yet licensed in the US, but a data base and documentation have developed. There do not appear to be technological barriers to interim dry storage, based on demonstrations with irradiated fuel. Water storage will continue to be a part of spent fuel management at reactors. Whether dry storage becomes a prominent interim fuel management option depends on licensing and economic considerations. National policies will strongly influence how long the spent fuel remains in interim storage and what its final disposition will be

  17. report transparency and nuclear safety 2007- CISBIO

    International Nuclear Information System (INIS)

    This report presents the activities of CISBIO, nuclear base installation, for the year 2007. CISBIO realizes at Saclay most of the radiopharmaceuticals and drugs distributed in France for the nuclear medicine. The actions concerning the safety, the radiation protection, the significant events, the release control and the environmental impacts and the wastes stored on the center are discussed. (A.L.B.)

  18. Sensitivity-Uncertainty Based Nuclear Criticality Safety Validation

    Energy Technology Data Exchange (ETDEWEB)

    Brown, Forrest B. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Univ. of New Mexico, Albuquerque, NM (United States). Nuclear Engineering Dept.

    2016-09-20

    These are slides from a seminar given to the University of Mexico Nuclear Engineering Department. Whisper is a statistical analysis package developed to support nuclear criticality safety validation. It uses the sensitivity profile data for an application as computed by MCNP6 along with covariance files for the nuclear data to determine a baseline upper-subcritical-limit for the application. Whisper and its associated benchmark files are developed and maintained as part of MCNP6, and will be distributed with all future releases of MCNP6. Although sensitivity-uncertainty methods for NCS validation have been under development for 20 years, continuous-energy Monte Carlo codes such as MCNP could not determine the required adjoint-weighted tallies for sensitivity profiles. The recent introduction of the iterated fission probability method into MCNP led to the rapid development of sensitivity analysis capabilities for MCNP6 and the development of Whisper. Sensitivity-uncertainty based methods represent the future for NCS validation – making full use of today’s computer power to codify past approaches based largely on expert judgment. Validation results are defensible, auditable, and repeatable as needed with different assumptions and process models. The new methods can supplement, support, and extend traditional validation approaches.

  19. Computer based aids for operator support in nuclear power plants

    International Nuclear Information System (INIS)

    In the framework of the Agency's programme on nuclear safety a survey was carried out based on a questionnaire to collect information on computer based aids for operator support in nuclear power plants in Member States. The intention was to put together a state-of-the-art report where different systems under development or already implemented would be described. This activity was also supported by an INSAG (International Nuclear Safety Advisory Group) recommendation. Two consultant's meetings were convened and their work is reflected in the two sections of the technical document. The first section, produced during the first meeting, is devoted to provide some general background material on the overall usability of Computerized Operator Decision Aids (CODAs), their advantages and shortcomings. During this first meeting, the first draft of the questionnaire was also produced. The second section presents the evaluation of the 40 questionnaires received from 11 Member States and comprises a short description of each system and some statistical and comparative observations. The ultimate goal of this activity was to inform Member States, particularly those who are considering implementation of a CODA, on the status of related developments elsewhere. 8 refs, 10 figs, 4 tabs

  20. Nuclear Power Plant Operator Reliability Research Based on Fuzzy Math

    International Nuclear Information System (INIS)

    This paper makes use of the concept and theory of fuzzy number in fuzzy mathematics, to research for the response time of operator in accident of Chinese nuclear power plant. Through the quantitative analysis for the performance shape factors (PSFs) which influence the response time of operators, the formula of the operator response time is obtained based on the possibilistic fuzzy linear regression model which is used for the first time in this kind of research. The research result shows that the correct research method can be achieved through the analysis of the information from a small sample. This method breaks through the traditional research method and can be used not only for the reference to the safe operation of nuclear power plant, but also in other areas.

  1. Nuclear insurance risk assessment using risk-based methodology

    International Nuclear Information System (INIS)

    This paper presents American Nuclear Insurers' (ANI's) and Mutual Atomic Energy Liability Underwriters' (MAELU's) process and experience for conducting nuclear insurance risk assessments using a risk-based methodology. The process is primarily qualitative and uses traditional insurance risk assessment methods and an approach developed under the auspices of the American Society of Mechanical Engineers (ASME) in which ANI/MAELU is an active sponsor. This process assists ANI's technical resources in identifying where to look for insurance risk in an industry in which insurance exposure tends to be dynamic and nonactuarial. The process is an evolving one that also seeks to minimize the impact on insureds while maintaining a mutually agreeable risk tolerance

  2. Cement-Based Materials for Nuclear Waste Storage

    CERN Document Server

    Cau-di-Coumes, Céline; Frizon, Fabien; Lorente, Sylvie

    2013-01-01

    As the re-emergence of nuclear power as an acceptable energy source on an international basis continues, the need for safe and reliable ways to dispose of radioactive waste becomes ever more critical. The ultimate goal for designing a predisposal waste-management system depends on producing waste containers suitable for storage, transportation and permanent disposal. Cement-Based Materials for Nuclear-Waste Storage provides a roadmap for the use of cementation as an applied technique for the treatment of low- and intermediate-level radioactive wastes.Coverage includes, but is not limited to, a comparison of cementation with other solidification techniques, advantages of calcium-silicate cements over other materials and a discussion of the long-term suitability and safety of waste packages as well as cement barriers. This book also: Discusses the formulation and production of cement waste forms for storing radioactive material Assesses the potential of emerging binders to improve the conditioning of problemati...

  3. Introduction of nuclear power plant based on reliability centered maintenance

    International Nuclear Information System (INIS)

    A maintenance program based on RCM (reliability centered maintenance) is used by many countries and increased safety, reliability and economy of plants. RCM and its application conditions to the nuclear power plants in USA and introduction conditions for Japan are explained. The present situation of maintenance and change of maintenance technologies in the world is stated. RCM is the best tool for working out the maintenance program. The basic approach is selection of system and the sphere of activity, identification of accident mode and causes by the FFA (functional failure analysis) and the FMEA (failure modes and effects analysis), and selection of the effective maintenance method for accident mode by the LTA (logic tree analysis) and optimization of maintenance. The maintenance of nuclear power plants and an on-side inspection of RCM in USA are described. The system for maintenance program and construction of the system for keeping the electric power joint technologies in Japan are illustrated. (S.Y.)

  4. Thorium-based nuclear fuel: current status and perspectives

    International Nuclear Information System (INIS)

    Until the present time considerable efforts have already been made in the area of fabrication, utilization and reprocessing of Th-based fuels for different types of reactors, namely: by FRG and USA - for HTRs; FRG and Brazil, Italy - for LWRs; India - for HWRs and FBRs. Basic research of thorium fuels and thorium fuel cycles are also being undertaken by Australia, Canada, China, France, FRG, Romania, USSR and other countries. Main emphasis has been given to the utilization of thorium fuels in once-through nuclear fuel cycles, but in some projects closed thorium-uranium or thorium-plutonium fuel cycles are also considered. The purpose of the Technical Committee on the Utilization of Thorium-Based Nuclear Fuel: Current Status and Perspective was to review the world thorium resources, incentives for further exploration, obtained experience in the utilization of Th-based fuels in different types of reactors, basic research, fabrication and reprocessing of Th-based fuels. As a result of the panel discussion the recommendations on future Agency activities and list of major worldwide activities in the area of Th-based fuel were developed. A separate abstract was prepared for each of the 9 papers in this proceedings series

  5. Seismic performance assessment of base-isolated safety-related nuclear structures

    Science.gov (United States)

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

    2010-01-01

    Seismic or base isolation is a proven technology for reducing the effects of earthquake shaking on buildings, bridges and infrastructure. The benefit of base isolation has been presented in terms of reduced accelerations and drifts on superstructure components but never quantified in terms of either a percentage reduction in seismic loss (or percentage increase in safety) or the probability of an unacceptable performance. Herein, we quantify the benefits of base isolation in terms of increased safety (or smaller loss) by comparing the safety of a sample conventional and base-isolated nuclear power plant (NPP) located in the Eastern U.S. Scenario- and time-based assessments are performed using a new methodology. Three base isolation systems are considered, namely, (1) Friction Pendulum??? bearings, (2) lead-rubber bearings and (3) low-damping rubber bearings together with linear viscous dampers. Unacceptable performance is defined by the failure of key secondary systems because these systems represent much of the investment in a new build power plant and ensure the safe operation of the plant. For the scenario-based assessments, the probability of unacceptable performance is computed for an earthquake with a magnitude of 5.3 at a distance 7.5 km from the plant. For the time-based assessments, the annual frequency of unacceptable performance is computed considering all potential earthquakes that may occur. For both assessments, the implementation of base isolation reduces the probability of unacceptable performance by approximately four orders of magnitude for the same NPP superstructure and secondary systems. The increase in NPP construction cost associated with the installation of seismic isolators can be offset by substantially reducing the required seismic strength of secondary components and systems and potentially eliminating the need to seismically qualify many secondary components and systems. ?? 2010 John Wiley & Sons, Ltd.

  6. EXTRA: A real time knowledge-based monitoring system for a nuclear power plant

    International Nuclear Information System (INIS)

    EXTRA is an expert system for industrial process control. The main objectives are diagnosis and operation aids. From a methodological point of view, EXTRA is based on a deep knowledge of the plant operation and topology and on qualitative physics principles. This system represents a considerable step forward in the field of expert-systems because of the size of the knowledge-base and the real-time requirements. A specific application of EXTRA is developed for the BUGEY unit 2 (a 900 MWe pressurized water nuclear unit) concerning the electrical power supplies. This system called ''electrical power supplies supervision'' gives diagnosis in real time of the electric incidental situation origin. A connection to a data base make the expert system able to supply operators with information concerning the consequences of the electrical power system failures on the safety systems, the equipment measurement sensors and certain automatic devices (availability, unavailability, validity, etc.). A simulation part of the system, out of real time, can help the operators or the maintenance team to prepare the withdrawal from service of electric equipment by giving information on the consequences of it, in particular, information concerning the technical specifications. The system will be independently used and managed by the operating crews and maintenance team, but a priority is given to the diagnosis real time supervision. This expert-system will be installed for the beginning of 1989. (author). 5 refs, 2 pictures

  7. A Nuclear Safety System based on Industrial Computer

    International Nuclear Information System (INIS)

    The Plant Protection System(PPS), a nuclear safety Instrumentation and Control (I and C) system for Nuclear Power Plants(NPPs), generates reactor trip on abnormal reactor condition. The Core Protection Calculator System (CPCS) is a safety system that generates and transmits the channel trip signal to the PPS on an abnormal condition. Currently, these systems are designed on the Programmable Logic Controller(PLC) based system and it is necessary to consider a new system platform to adapt simpler system configuration and improved software development process. The CPCS was the first implementation using a micro computer in a nuclear power plant safety protection system in 1980 which have been deployed in Ulchin units 3,4,5,6 and Younggwang units 3,4,5,6. The CPCS software was developed in the Concurrent Micro5 minicomputer using assembly language and embedded into the Concurrent 3205 computer. Following the micro computer based CPCS, PLC based Common-Q platform has been used for the ShinKori/ShinWolsong units 1,2 PPS and CPCS, and the POSAFE-Q PLC platform is used for the ShinUlchin units 1,2 PPS and CPCS. In developing the next generation safety system platform, several factors (e.g., hardware/software reliability, flexibility, licensibility and industrial support) can be considered. This paper suggests an Industrial Computer(IC) based protection system that can be developed with improved flexibility without losing system reliability. The IC based system has the advantage of a simple system configuration with optimized processor boards because of improved processor performance and unlimited interoperability between the target system and development system that use commercial CASE tools. This paper presents the background to selecting the IC based system with a case study design of the CPCS. Eventually, this kind of platform can be used for nuclear power plant safety systems like the PPS, CPCS, Qualified Indication and Alarm . Pami(QIAS-P), and Engineering Safety

  8. Visiting the SPS installation

    CERN Multimedia

    1975-01-01

    ...., Guenther Loehr, Hans Horisberger walk along the SPS tunnel: here, on the right, an absorber block of 22 tons for beam dumping in the external beam lines. The chariot serves for the installation of the block.

  9. Biggest semiconductor installed

    CERN Multimedia

    2008-01-01

    Scientists and technicians at the European Laboratory for Particle Physics, commonly known by its French acronym CERN (Centre Europen pour la Recherche Nuclaire), have completed the installation of the largest semiconductor silicon detector.

  10. Installing the World

    Institute of Scientific and Technical Information of China (English)

    1998-01-01

    THE art of installation is an art about concept," explains Qing Qing Chen. The artist wants her audience to look at the development of aesthetics from a pluralistic angle on life. Unlike the expressive format of "art in the frame," the art of installation belongs to the category of "non-framed art." The choice of materials used is as important to expression as the creator’s ideas. Whereas only certain materials can be

  11. Nuclear energy

    International Nuclear Information System (INIS)

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

  12. Installed Base as a Facilitator for User-Driven Innovation: How Can User Innovation Challenge Existing Institutional Barriers?

    Directory of Open Access Journals (Sweden)

    Synnøve Thomassen Andersen

    2012-01-01

    Full Text Available The paper addresses an ICT-based, user-driven innovation process in the health sector in rural areas in Norway. The empirical base is the introduction of a new model for psychiatric health provision. This model is supported by a technical solution based on mobile phones that is aimed to help the communication between professional health personnel and patients. This innovation was made possible through the use of standard mobile technology rather than more sophisticated systems. The users were heavily involved in the development work. Our analysis shows that by thinking simple and small-scale solutions, including to take the user’s needs and premises as a point of departure rather than focusing on advanced technology, the implementation process was made possible. We show that by combining theory on information infrastructures, user-oriented system development, and innovation in a three-layered analytical framework, we can explain the interrelationship between technical, organizational, and health professional factors that made this innovation a success.

  13. Diagnosis and suggestions for the knowledge management applied to a nuclear installation: the uranium hexafluoride production unit; Diagnostico e sugestoes para a gestao do conhecimento aplicada a uma instalacao nuclear: a unidade de producao de hexafluoreto de uranio

    Energy Technology Data Exchange (ETDEWEB)

    Marchesini, Paulo Roberto de Andrade

    2008-07-01

    It has been more than 25 years since Brazilian Navy started applying resources and staff in a nuclear power program in which the main objective is the necessary technology for project and construction of a nuclear power reactor and nuclear fuel production for naval propulsion. A long period project tends to be susceptible to loss of essential parcels of knowledge. The objective of the present research is to identify actions and initiatives that may improve learning and dissemination of knowledge in an organization that develops complexes projects during a long period of time. The revision of the literature about Knowledge Management allowed the researcher to select a reference that indicates how people involved in a project gets the necessary information and knowledge for developing their activities and uses them to add value and to learn how to contribute for the organization, in order to prevent nature difficulties. The adopted methodology was a case study on the implantation of the {sup U}nidade de Hexafluoreto de Uranio{sup ,} which is being developed by the Centro Tecnologico da Marinha in Sao Paulo. With the application of structured and opened interviews, it was possible to identify some factors related with the attainment and dissemination of knowledge that can be developed. The result of this work was a proposal of action and initiatives that will improve the attainment of the knowledge, its structure and maintenance by the organization and the contribution by the people, of the knowledge acquired. (author)

  14. Predictive based monitoring of nuclear plant component degradation using support vector regression

    Energy Technology Data Exchange (ETDEWEB)

    Agarwal, Vivek [Idaho National Lab. (INL), Idaho Falls, ID (United States). Dept. of Human Factors, Controls, Statistics; Alamaniotis, Miltiadis [Purdue Univ., West Lafayette, IN (United States). School of Nuclear Engineering; Tsoukalas, Lefteri H. [Purdue Univ., West Lafayette, IN (United States). School of Nuclear Engineering

    2015-02-01

    Nuclear power plants (NPPs) are large installations comprised of many active and passive assets. Degradation monitoring of all these assets is expensive (labor cost) and highly demanding task. In this paper a framework based on Support Vector Regression (SVR) for online surveillance of critical parameter degradation of NPP components is proposed. In this case, on time replacement or maintenance of components will prevent potential plant malfunctions, and reduce the overall operational cost. In the current work, we apply SVR equipped with a Gaussian kernel function to monitor components. Monitoring includes the one-step-ahead prediction of the component’s respective operational quantity using the SVR model, while the SVR model is trained using a set of previous recorded degradation histories of similar components. Predictive capability of the model is evaluated upon arrival of a sensor measurement, which is compared to the component failure threshold. A maintenance decision is based on a fuzzy inference system that utilizes three parameters: (i) prediction evaluation in the previous steps, (ii) predicted value of the current step, (iii) and difference of current predicted value with components failure thresholds. The proposed framework will be tested on turbine blade degradation data.

  15. Empirical assessment of possible X-band radar installation sites, based on on-site clutter tests

    OpenAIRE

    Goormans, Toon; Willems, Patrick; Jensen, Niels Einar

    2008-01-01

    In a research project of the Hydraulics Laboratory of the Katholieke Universiteit Leuven (K.U.Leuven) for the water company Aquafin, a small, short range, high resolution X-band weather radar, called Local Area Weather Radar - City Radar (LAWR-CR, DHI), is being used for investigation of the spatial rainfall accuracy improvement in urban drainage models. The system is based on standard X-band marine radar technology, making it cost-effective in comparison to other systems. Since marine ra...

  16. NEW WEB-BASED ACCESS TO NUCLEAR STRUCTURE DATASETS.

    Energy Technology Data Exchange (ETDEWEB)

    WINCHELL,D.F.

    2004-09-26

    As part of an effort to migrate the National Nuclear Data Center (NNDC) databases to a relational platform, a new web interface has been developed for the dissemination of the nuclear structure datasets stored in the Evaluated Nuclear Structure Data File and Experimental Unevaluated Nuclear Data List.

  17. ASN report of the status of nuclear safety and radiation protection in France in 2012

    International Nuclear Information System (INIS)

    After a presentation of the French Nuclear Safety Authority (ASN), its missions, some key figures illustrating its activities and its organisation, this report proposes an overview of marking events and of actions undertaken by the ASN after the Fukushima accident. Then, the report proposes a detailed and commented overview of actions undertaken by the ASN in different fields and domains: nuclear activities, principles and actors of nuclear safety and radiation protection control, regulation, control of nuclear activities and of exposures to ionizing radiations, radiological and post-accidental emergency situations, public information and transparency, international relationships, regional overview of nuclear safety and radiation protection. The last part addresses activities controlled by the ASN: medical use of ionizing radiations, industrial, research and veterinary uses and source safety, transport of radioactive materials, electronuclear plants, installations related to nuclear fuel cycle, nuclear research and other nuclear installations, safety of dismantling of base nuclear installations, radioactive wastes and polluted sites

  18. Electric Vehicle Preparedness: Task 2, Identification of Vehicles for Installation of Data Loggers for Marine Corps Base Camp Lejeune

    Energy Technology Data Exchange (ETDEWEB)

    Schey, Stephen [Idaho National Lab. (INL), Idaho Falls, ID (United States); Francfort, Jim [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2015-02-01

    In Task 1, a survey was completed of the inventory of non-tactical fleet vehicles at the Marine Corps Base Camp Lejeune (MCBCL) to characterize the fleet. This information and characterization was used to select vehicles for further monitoring, which involves data logging of vehicle movements in order to identify the vehicle’s mission and travel requirements. Individual observations of these selected vehicles provide the basis for recommendations related to PEV adoption. It also identifies whether a battery electric vehicle or plug-in hybrid electric vehicle (collectively referred to as PEVs) can fulfill the mission requirements and provides observations related to placement of PEV charging infrastructure. This report provides the list of vehicles selected by MCBCL and Intertek for further monitoring and fulfills the Task 2 requirements.

  19. Order of 27 October 1971 on exemptions from classification as radioactive installations

    International Nuclear Information System (INIS)

    This Order was made in implementation of Section 2 of the 1964 Act on nuclear activities which provides that installations where the level of radiation produced entails no significant hazard shall be excluded from the classification of radioactive installations. Consequently, the Order specifies the activity thresholds for radionuclides below which installations containing them are not considered as radioactive installations. (NEA)

  20. Cyclotron based nuclear science. Progress report, April 1, 1985-March 31, 1986

    International Nuclear Information System (INIS)

    Progress report for cyclotron based nuclear science cyclotron facility are summarized. Research is described under the headings heavy ion reactions, nuclear theory, atomic studies and activation analysis, superconducting cyclotron and instrumentation. Publications are listed