WorldWideScience

Sample records for nuclear facilities situated

  1. Current situation of the facilities, equipments and human resources in nuclear medicine in Argentina

    International Nuclear Information System (INIS)

    Chiliutti, Claudia A.

    2008-01-01

    The current situation of nuclear medicine in Argentina, taking into account the facilities, their equipment and human resources available is presented in this paper. A review and analysis of the equipment, including technical characteristics and a survey of the professionals and technicians of the area, was carried out. In Argentina, there are 266 centers of nuclear medicine distributed all over the country. The operating licenses are granted by the Nuclear Regulatory Authority (Autoridad Regulatoria Nuclear - ARN). Forty four percent of the installed equipment are SPECT of 1 or 2 heads and 39,4 % are gamma camera. Besides, there are eleven PET operating in Argentina. There are 416 nuclear medicine physicians with individual permit for diagnostic purposes and 50% of them has also individual permit for treatment purposes. With the purpose of analyzing the regional distribution of the available resources in nuclear medicine, the country was divided into 7 geographical regions: City of Buenos Aires, Province of Buenos Aires, Pampa, Cuyo, Northeast, Northwest and Patagonia. From the analysis of the gathered information it is possible to conclude that the nuclear medicine equipment as well as the personnel present an irregular distribution, with a major concentration in the City of Buenos Aires and Province of Buenos Aires. The Northeast region presents the lowest number of Nuclear Medicine centers and the Patagonia region has the lowest number of medicine nuclear physicians with individual permits. The number of SPECT and gamma cameras is 7,3 per million of inhabitants. The information about the available resources in nuclear medicine presented in this paper and its comparison with the international information available provide elements for a better planning of the future activities in the area not only for the operators but also from the regulatory point of view. (author)

  2. R and D strategy on remote response technology for emergency situations of nuclear facilities in KAERI

    International Nuclear Information System (INIS)

    Jeong, Kyung Min; Cho, Jae Wan; Choi, Young Soo; Eom, Heung Seup; Seo, Yong Chil; Shin, Hoch Ul; Lee, Sung Uk; Kim, Chang Hoi; Jeong, Seung Ho; Kim, Seung Ho

    2012-01-01

    Generally speaking, robotic technologies are anticipated to be very useful for hazardous works in nuclear facilities because robotic systems are relatively immune to radiation exposure. But the application of robotic systems for such environments has not been increasing during past 20 years. Applying highly reliable and conservative 'defense in depth' concepts in the design and construction of NPPs, there is very little probability of accidents occurring or radioactive materials being released into the environments. As a precaution, however NPPs are prepared with emergency response procedures and routinely conduct exercises for post accident circumstances based on these procedures. The last year's accident at the Fukushima Daiichi nuclear power plant promotes the needs for remote response technologies based on mobile robotic system to recognize the internal status and mitigate the unanticipated events of nuclear power plants in emergency situations. For initial observation of reactor buildings two robots named 'PackBot' were used because the internal conditions were unknown so as to allow human workers for entrance into the reactor building. But there were severe limitations for the robots to perform the given tasks from various obstacles and poor visibility inside though they provided crucial information such as views of internal structures, dose level and temperature that supported the decision for human worker's entrance. The application of robots for emergency response tasks for post accidents in nuclear facilities is not a new concept. Robots were sent to recover the damaged reactor at Chernobyl where human workers could have received a lifetime dose of radiation in minutes. Based on NRC's TMI 2 Cleanup Program, several robots were built in the 1980s to help gather information and remove debris from a reactor at the Three Mile Island nuclear power plant that partially melted down in 1979. A robot was used for several years equipped with various tools allowing

  3. R and D strategy on remote response technology for emergency situations of nuclear facilities in KAERI

    Energy Technology Data Exchange (ETDEWEB)

    Jeong, Kyung Min; Cho, Jae Wan; Choi, Young Soo; Eom, Heung Seup; Seo, Yong Chil; Shin, Hoch Ul; Lee, Sung Uk; Kim, Chang Hoi; Jeong, Seung Ho; Kim, Seung Ho [KAERI, Daejeon (Korea, Republic of)

    2012-10-15

    Generally speaking, robotic technologies are anticipated to be very useful for hazardous works in nuclear facilities because robotic systems are relatively immune to radiation exposure. But the application of robotic systems for such environments has not been increasing during past 20 years. Applying highly reliable and conservative 'defense in depth' concepts in the design and construction of NPPs, there is very little probability of accidents occurring or radioactive materials being released into the environments. As a precaution, however NPPs are prepared with emergency response procedures and routinely conduct exercises for post accident circumstances based on these procedures. The last year's accident at the Fukushima Daiichi nuclear power plant promotes the needs for remote response technologies based on mobile robotic system to recognize the internal status and mitigate the unanticipated events of nuclear power plants in emergency situations. For initial observation of reactor buildings two robots named 'PackBot' were used because the internal conditions were unknown so as to allow human workers for entrance into the reactor building. But there were severe limitations for the robots to perform the given tasks from various obstacles and poor visibility inside though they provided crucial information such as views of internal structures, dose level and temperature that supported the decision for human worker's entrance. The application of robots for emergency response tasks for post accidents in nuclear facilities is not a new concept. Robots were sent to recover the damaged reactor at Chernobyl where human workers could have received a lifetime dose of radiation in minutes. Based on NRC's TMI 2 Cleanup Program, several robots were built in the 1980s to help gather information and remove debris from a reactor at the Three Mile Island nuclear power plant that partially melted down in 1979. A robot was used for several years

  4. Fukushima Daiichi nuclear acccident. Damaged facilities of the site - Situation as on March 2018

    International Nuclear Information System (INIS)

    2018-03-01

    After a recall of the events that led to the Fukushima Daiichi accident, this note presents the situation in March 2018 of the actions of control of the damaged facilities and of their effluents. The last part presents the three steps of the facility control recovery plan retained by TEPCO

  5. Nuclear situation in Japan

    International Nuclear Information System (INIS)

    2006-01-01

    This analysis takes stock on the nuclear situation in Japan. It discusses the ambitious equipment program in collaboration with the France, the destabilization of the japanese nuclear industry following the accidents and the energy policy evolutions. It presents the projects of the japanese nuclear industry: the Monju reactor restart, the Pluthermal project, the reprocessing power plant of Rokkasho Mura, the new reactors, the russian weapons dismantling, the ITER site selection and the buy out of Westinghouse by Toshiba. (A.L.B.)

  6. Nuclear facilities

    International Nuclear Information System (INIS)

    Anon.

    2000-01-01

    Here is given the decree (2000-1065) of the 25. of October 2000 reporting the publication of the convention between the Government of the French Republic and the CERN concerning the safety of the LHC (Large Hadron Collider) and the SPS (Proton Supersynchrotron) facilities, signed in Geneva on July 11, 2000. By this convention, the CERN undertakes to ensure the safety of the LHC and SPS facilities and those of the operations of the LEP decommissioning. The French legislation and regulations on basic nuclear facilities (concerning more particularly the protection against ionizing radiations, the protection of the environment and the safety of facilities) and those which could be decided later on apply to the LHC, SPS and auxiliary facilities. (O.M.)

  7. Nuclear facilities

    International Nuclear Information System (INIS)

    Anon.

    2002-01-01

    During September and October 2001, 15 events were recorded on the first grade and 1 on the second grade of the INES scale. The second grade event is in fact a re-classification of an incident that occurred on the second april 2001 at Dampierre power plant. This event happened during core refueling, a shift in the operation sequence led to the wrong positioning of 113 assemblies. A preliminary study of this event shows that this wrong positioning could have led, in other circumstances, to the ignition of nuclear reactions. Even in that case, the analysis made by EDF shows that the consequences on the staff would have been limited. Nevertheless a further study has shown that the existing measuring instruments could not have detected the power increase announcing the beginning of the chain reaction. The investigation has shown that there were deficiencies in the control of the successive operations involved in refueling. EDF has proposed a series of corrective measures to be implemented in all nuclear power plants. The other 15 events are described in the article. During this period 121 inspections have been made in nuclear facilities. (A.C.)

  8. Situation of nuclear industry in Japan

    International Nuclear Information System (INIS)

    2002-08-01

    This document is a reprint of a note published by the nuclear service of the French embassy in Japan. It evokes the present day situation of nuclear facilities in Japan, the public acceptance and its attitude in front of accidents, the national energy program, the deregulation and competitiveness of nuclear power, the carrying out of the nuclear program, the future reactors, the fast neutron reactors, the dismantling activities, the fuel enrichment and reprocessing of spent fuels, the use of MOX fuel, the off-site storage, the vitrified and radiological wastes, the geological disposal of wastes, the prospects of the nuclear program, the companies involved in the Japan nuclear industry, the French-Japanese bilateral cooperation, and the ITER project in the domain of nuclear fusion. (J.S.)

  9. Emergency situation in a medical cyclotron facility

    International Nuclear Information System (INIS)

    Kumar, Rajeev; Bhat, M.K.; Singh, D.K.; Pthania, B.S.; Pandit, A.G.; Jacob, M.J.

    2010-01-01

    Full text: Medical cyclotron is a particle accelerator used in producing short lived radioisotopes such as 18 F, 11 C, 15 O, 13 N, 18 F-2 gas etc. Positron Emission Tomography (PET) is a nuclear imaging modality that has rapidly gained favour. 18 F-FDG is the most widely used radiopharmaceutical with a half-life of 109.8 min. Having more than five years experience in this field we face lots of emergency conditions in the medical cyclotron facility. On the basis of harm we have divided in to three categories i.e. Harm of (a) working personnel, (b) Equipment and (c) environment. Radioactive gas leak and Target foil rupture is considered as the major emergency situations during medical cyclotron operations because there is a potential of over exposure to the working personnel. Radiation protection survey of a self-shielded medical cyclotron installation was carried out during normal and emergency conditions. It is found that the induced activity in the target foil increases with its successive usages. Recommendations have also been made to reduce personal exposure while handling the radioactive gas leak and target foil rupture conditions

  10. Nuclear data. Situation and future projects

    International Nuclear Information System (INIS)

    Bioux, P.

    1995-01-01

    Nuclear power provides the major part of the electricity generation in France, using a system of highly developed Pressurized Water Reactors. Electricite de France, which is responsible for the exploitation of this system, is concerned to ensure the continuity of the expertise and facilities which provide relevant basic scientific information contributing to the efficient exploitation of the system and, in particular, the continuity of the means for providing relevant nuclear data. The nuclear data requirements for the exploitation of the existing nuclear power system have been largely met. However, there remain some needs, in particular in the field of reactor neutronics. Furthermore if one considers the future (for example, the next 10 years) it is not certain that will be possible to meet the needs which are expected to arise. The review, commissioned on behalf of EDF, about the current status and future expectations for work in this field, has shown certain tendencies in the international situation. In particular one notes a general reduction in the effort both in Western Europe and the United States. This negative tendency can perhaps be explained by the almost general reduction world-wide in new nuclear power developments. However, unresolved problems remain, such as the development of methods for reducing the stocks of plutonium and the incineration and storage of a nuclear waste of long duration. In addition improvements in the accuracy of nuclear data could result in non-negligible economic benefits in the exploitation of the existing nuclear facilities. For these very important reasons it is desirable to reverse the present trend. (author). 2 annexes

  11. Facilities inventory protection for nuclear facilities

    International Nuclear Information System (INIS)

    Schmitt, F.J.

    1989-01-01

    The fact that shut-down applications have been filed for nuclear power plants, suggests to have a scrutinizing look at the scopes of assessment and decision available to administrations and courts for the protection of facilities inventories relative to legal and constitutional requirements. The paper outlines the legal bases which need to be observed if purposeful calculation is to be ensured. Based on the different actual conditions and legal consequences, the author distinguishes between 1) the legal situation of facilities licenced already and 2) the legal situation of facilities under planning during the licencing stage. As indicated by the contents and restrictions of the pertinent provisions of the Atomic Energy Act and by the corresponding compensatory regulation, the object of the protection of facilities inventor in the legal position of the facility owner within the purview of the Atomic Energy Act, and the licensing proper. Art. 17 of the Atomic Energy Act indicates the legislators intent that, once issued, the licence will be the pivotal point for regulations aiming at protection and intervention. (orig./HSCH) [de

  12. Decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    Lunning, W.H.

    1977-01-01

    Collaborative studies are in progress in the U.K. between the U.K.A.E.A., the Generating Boards and other outside bodies, to identify the development issues and practical aspects of decommissioning redundant nuclear facilities. The various types of U.K.A.E.A. experimental reactors (D.F.R., W.A.G.R , S.G.H.W.R.) in support of the nuclear power development programme, together with the currently operating commercial 26 Magnox reactors in 11 stations, totalling some 5 GW will be retired before the end of the century and attention is focussed on these. The actual timing of withdrawal from service will be dictated by development programme requirements in the case of experimental reactors and by commercial and technical considerations in the case of electricity production reactors. Decommissioning studies have so far been confined to technical appraisals including the sequence logic of achieving specific objectives and are based on the generally accepted three stage progression. Stage 1, which is essentially a defuelling and coolant removal operation, is an interim phase. Stage 2 is a storage situation, the duration of which will be influenced by environmental pressures or economic factors including the re-use of existing sites. Stage 3, which implies removal of all active and non-active waste material and returning the site to general use, must be the ultimate objective. The engineering features and the radioactive inventory of the system must be assessed in detail to avoid personnel or environmental hazards during Stage 2. These factors will also influence decisions on the degree of Stage 2 decommissioning and its duration, bearing in mind that for Stage 3 activation may govern the waste disposal route and the associated radiation man-rem exposure during dismantling. Ideally, planning for decommissioning should be considered at the design stage of the facility. An objective of present studies is to identify features which would assist decommissioning of future systems

  13. Nuclear physics accelerator facilities

    International Nuclear Information System (INIS)

    1988-12-01

    This paper describes many of the nuclear physics heavy-ion accelerator facilities in the US and the research programs being conducted. The accelerators described are: Argonne National Laboratory--ATLAS; Brookhaven National Laboratory--Tandem/AGS Heavy Ion Facility; Brookhaven National Laboratory--Relativistic Heavy Ion Collider (RHIC) (Proposed); Continuous Electron Beam Accelerator Facility; Lawrence Berkeley Laboratory--Bevalac; Lawrence Berkeley Laboratory--88-Inch Cyclotron; Los Alamos National Laboratory--Clinton P. Anderson Meson Physics Facility (LAMPF); Massachusetts Institute of Technology--Bates Linear Accelerator Center; Oak Ridge National Laboratory--Holifield Heavy Ion Research Facility; Oak Ridge National Laboratory--Oak Ridge Electron Linear Accelerator; Stanford Linear Accelerator Center--Nuclear Physics Injector; Texas AandM University--Texas AandM Cyclotron; Triangle Universities Nuclear Laboratory (TUNL); University of Washington--Tandem/Superconducting Booster; and Yale University--Tandem Van de Graaff

  14. Nuclear situation in Japan; La situation du nucleaire au Japon

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-07-01

    This analysis takes stock on the nuclear situation in Japan. It discusses the ambitious equipment program in collaboration with the France, the destabilization of the japanese nuclear industry following the accidents and the energy policy evolutions. It presents the projects of the japanese nuclear industry: the Monju reactor restart, the Pluthermal project, the reprocessing power plant of Rokkasho Mura, the new reactors, the russian weapons dismantling, the ITER site selection and the buy out of Westinghouse by Toshiba. (A.L.B.)

  15. Recent situations around nuclear ships

    International Nuclear Information System (INIS)

    Mizuno, Hiroshi

    1978-01-01

    The philosophy when the safety standard for nuclear ships is drawn up and the international rules specifically for nuclear ships are summarized. As for the safety standard for nuclear ships, the safety requirements for ordinary ships, for the ships transporting nuclear reactors, for ordinary nuclear reactors, and for the reactors moving around the seas must be included. As for the international rules for nuclear ships, there are chapter 8 ''Nuclear ships'' in the International Convention on the Safety of Life at Sea, 1960 and 1974, and Safety Consideration in the Use of Ports and Approaches by Nuclear Merchant Ships. Also there are national rules and standards in Japan and foreign countries. One of the means to explore the practicality of nuclear ships is the investigation of the economy. At this time, the social merits and demerits of nuclear ships must be compared with conventional ships by taking total expenses into account without omission. When oil is depleted, the age of nuclear ships will not necessarily begin, and the will be still some competitors. The investigations concerning the economy of nuclear ships have been carried out in various countries. The present state of the development of nuclear ships in Japan and foreign countries is explained. Many conferences and symposia have been held concerning nuclear ships, and those held recently are enumerated. The realization of nuclear ship age cannot be anticipated from existing papers and shipbuilding projects. (Kako, I.)

  16. On present situation of radioactive waste management and exposure of workers in nuclear reactor facilities for commercial power generation in fiscal 1988

    International Nuclear Information System (INIS)

    1989-01-01

    The article summarizes the contents of some reports including the Report on Radiation Management in 1988 that were submitted by the operators of nuclear reactor facilities for commercial power generation according to the requirements specified in the Law Concerning Regulation on Nuclear Material, Nuclear Fuel and Nuclear Reactor. According to these reports, the annual radiation release in all nuclear power generation plants was well below the radiation release limits set up in the report 'On Guidelines for Target Dose in Areas around Light Water Reactor Facilities for Power Generation'. Data submitted also show that there are no significant problems with the management of radioactive solid waste. In all nuclear generation plants, the personal exposure of workers is below the permissible exposure dose specified in law. The Agency of Natural Resources and Energy is planned to further promote the development of advanced techniques for automatization and remote control of light water reactors and to provide effective guidance to electrical contractors for positive radiation management. (N.K.)

  17. Pumps for nuclear facilities

    International Nuclear Information System (INIS)

    1999-01-01

    The guide describes how the Finnish Radiation and Nuclear Safety Authority (STUK) controls pumps and their motors at nuclear power plants and other nuclear facilities. The scope of the control is determined by the Safety Class of the pump in question. The various phases of the control are: (1) review of construction plan, (2) control of manufacturing, and construction inspection, (3) commissioning inspection, and (4) control during operation. STUK controls Safety Class 1, 2 and 3 pumps at nuclear facilities as described in this guide. STUK inspects Class EYT (non-nuclear) pumps separately or in connection with the commissioning inspections of the systems. This guide gives the control procedure and related requirements primarily for centrifugal pumps. However, it is also applied to the control of piston pumps and other pump types not mentioned in this guide

  18. Energy situation and nuclear power

    Energy Technology Data Exchange (ETDEWEB)

    Megahid, M R [Reactor and Neutron physics Department Nuclear Research Center A.E., Cairo (Egypt)

    1997-12-31

    A brief general review is given concerning the requirements of power throughout history with an indication to the world capital reserves of energy. The energy released from the conversion of mass in chemical and nuclear processes is also discussed with comparative analysis between conventional fuel fired plant and nuclear power plant having the same energy output. The advantages and disadvantages arising from having a nuclear power programme are also discussed. 1 fig.

  19. International Nuclear Security Situation And China’s Approach

    Institute of Scientific and Technical Information of China (English)

    Liu Chong

    2016-01-01

    Since 2010,the three Nuclear Security Summits have made a number of achievements,but the international nuclear security situation is still not relaxed.The rapid development of China’s domestic nuclear facilities and a large amount of nuclear and radioactive materials related to nuclear power,active international nuclear black market in China’s surrounding regions,rather serious domestic and international terrorist threats as well as the emerging technology development bring about new challenges to nuclear security.Facing the complicated and long-term nuclear security situation,China from the perspective of monitoring mechanism,laws and regulations system,technical capability-building and nuclear emergency preparedness,takes a series of effective measures to build the national nuclear security capacity,and strictly fulfills its international obligations,actively participates in upgrading the international nuclear non-proliferation regime and relevant international rules,and actively takes part in the Nuclear Security Summit process,strengthens bilateral cooperation on nuclear security with major countries especially the United States of America,and jointly organizes various training with International Atomic Energy Agency,which has made great contributions to upgrading the global nuclear security level.At the end of the Nuclear Security Summit process,China should continue to strengthen its domestic nuclear security capacity building,and promote the international community to treat the root causes and symptoms,adopt a comprehensive strategy,and work together,effectively prevent and dissolve the nuclear terrorist threats.

  20. Radiation protection in nuclear facilities

    International Nuclear Information System (INIS)

    Piechowski, J.; Lochard, J.; Lefaure, Ch.; Schieber, C.; Schneider, Th; Lecomte, J.F.; Delmont, D.; Boitel, S.; Le Fauconnier, J.P.; Sugier, A; Zerbib, J.C.; Barbey, P.

    1998-01-01

    Close ties exist between nuclear safety and radiation protection. Nuclear safety is made up of all the arrangements taken to prevent accidents occurring in nuclear facilities, these accidents would certainly involved a radiological aspect. Radiation protection is made up of all the arrangements taken to evaluate and reduce the impact of radiation on workers or population in normal situations or in case of accident. In the fifties the management of radiological hazards was based on the quest for minimal or even zero risk. This formulation could lead to call some activities in question whereas the benefits for the whole society were evident. Now a new attitude more aware of the real risks and of no wasting resources prevails. This attitude is based on the ALARA principle whose purpose is to maintain the exposure to radiation as low as reasonably achievable taking into account social and economic concerns. This document regroups articles illustrating different aspects of the radiation protection in nuclear facilities such as a research center, a waste vitrification workshop and a nuclear power plant. The surveillance of radiological impacts of nuclear sites on environment is examined, a point is made about the pending epidemiologic studies concerning La Hague complex. (A.C.)

  1. Present situation of floating nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Sakurai, A [Central Research Inst. of Electric Power industry, Tokyo (Japan)

    1975-08-01

    The present situation of investigation and the future problems of floating nuclear power plants in Japan are examined, referring to those in USA. The committee report on a new power generation system in 1970 is quoted. In this report, the site conditions are supposed to be 5 km offshore, 100m water depth, 60 m/sec wind velocity, 10 m wave height, 200 m wave length, 12 seconds wave period 0.2 g earthquake acceleration, and 2.5 knots tide current. The semisubmersible hull of double construction 15 m under water is employed. A pair of 1,000,000 kW BWR reactors are utilized. A sea water desalting unit using bleed steam from turbines is installed. The solid radioactive wastes packed in drums are disposed in the sea. The design and cost estimation were made. The names of the organizations who have made investigation in this field, namely the Civil Engineering Society, the Sience and Technology Agency and other several centers, are reported. The Chubu Electric Power Company is forwarding its project. Referring to the investigations in USA, the project of Atlantic nuclear power station unit is described. A report of plant design has been submitted by O.P.S. to United States Atomic Energy Commission in 1973. The Coastal Area Facilities Act was instituted in New Jersey in 1973. Although the Atlantic nuclear power station has been postponed, it is the most feasible project. For the realization of a floating nuclear power plant in Japan, investigation must be started on the ground construction that can endure the construction of breakwater in water depth of 14 to 30 meter.

  2. Decommissioning nuclear facilities

    International Nuclear Information System (INIS)

    Harmon, K.M.; Jenkins, C.E.; Waite, D.A.; Brooksbank, R.E.; Lunis, B.C.; Nemec, J.F.

    1976-01-01

    This paper describes the currently accepted alternatives for decommissioning retired light water reactor fuel cycle facilities and the current state of decommissioning technology. Three alternatives are recognized: Protective Storage; Entombment; and Dismantling. Application of these alternatives to the following types of facilities is briefly described: light water reactors; fuel reprocessing plants, and mixed oxide fuel fabrication plants. Brief descriptions are given of decommissioning operations and results at a number of sites, and recent studies of the future decommissioning of prototype fuel cycle facilities are reviewed. An overview is provided of the types of operations performed and tools used in common decontamination and decommissioning techniques and needs for improved technology are suggested. Planning for decommissioning a nuclear facility is dependent upon the maximum permitted levels of residual radioactive contamination. Proposed guides and recently developed methodology for development of site release criteria are reviewed. 21 fig, 32 references

  3. Dismantling of nuclear facilities

    International Nuclear Information System (INIS)

    Tallec, Michele; Kus, Jean-Pierre; Mogavero, Robert; Genelot, Gabriel

    2009-01-01

    Although the operational life of nuclear plants is long (around 60 years for French reactors) it is nonetheless limited in time, the stopping of it being essentially due to the obsolescence of materials and processes or to economic or safety considerations. The nuclear power plants are then subjected to cleanup and dismantling operations which have different objectives and require specific techniques. The cleanup and/or dismantling of a nuclear power produces significant quantities of waste which is generally of a different nature to that produced during the operation of the concerned plant. The radioactive waste produced by these operations is destined to be sent to the waste disposal facilities of the French National Agency for the Management of Nuclear Waste. (authors)

  4. Nuclear power situation in Finland

    Energy Technology Data Exchange (ETDEWEB)

    Miettinen, J K

    1976-01-01

    Finland plans to have its future energy policy as well-balanced and economical as possible. Dependence on oil has to be reduced and savings have to be achieved wherever possible. Some growth of energy demand will be inevitable, and most of this growth has to be nuclear. Practically all hydropower that can be reasonably exploited is being utilized already. Finland has an abundance of peat, but it can be economically used only as a regional source of energy. This leaves, as the only real alternatives for the coming decennia, coal and fission; of the two, fission is evidently the better choice. Although other forms of energy such as fusion, solar, tidal, and wind energy have to be studied as longer-range alternatives. Four nuclear power plants are presently under construction in Finland and at least a few additional ones will evidently be built before 1990. Several of them will probably be of the combined district heat and electricity-producing type. The planning of nuclear energy has recently become complicated due to financing difficulties, uncertainties regarding long-range fuel services, and public opposition. The latter is partly caused by lack of information, partly by fears of a change of life-style in communities near the planned power plant sites. (From Conclusions)

  5. Robotics for nuclear facilities

    International Nuclear Information System (INIS)

    Abe, Akira; Nakayama, Ryoichi; Kubo, Katsumi

    1988-01-01

    It is highly desirable that automatic or remotely controlled machines perform inspection and maintenance tasks in nuclear facilities. Toshiba has been working to develop multi-functional robots, with one typical example being a master-slave manipulator for use in reprocessing facilities. At the same time, the company is also working on the development of multi-purpose intelligent robots. One such device, an automatic inspection robot, to be deployed along a monorail, performs inspection by means of image processing technology, while and advanced intelligent maintenance robot is equipped with a special wheel-locomotion mechanism and manipulator and is designed to perform maintenance tasks. (author)

  6. Nuclear physics accelerator facilities

    International Nuclear Information System (INIS)

    1985-01-01

    The Department of Energy's Nuclear Physics program is a comprehensive program of interdependent experimental and theoretical investigation of atomic nuclei. Long range goals are an understanding of the interactions, properties, and structures of atomic nuclei and nuclear matter at the most elementary level possible and an understanding of the fundamental forces of nature by using nuclei as a proving ground. Basic ingredients of the program are talented and imaginative scientists and a diversity of facilities to provide the variety of probes, instruments, and computational equipment needed for modern nuclear research. Approximately 80% of the total Federal support of basic nuclear research is provided through the Nuclear Physics program; almost all of the remaining 20% is provided by the National Science Foundation. Thus, the Department of Energy (DOE) has a unique responsibility for this important area of basic science and its role in high technology. Experimental and theoretical investigations are leading us to conclude that a new level of understanding of atomic nuclei is achievable. This optimism arises from evidence that: (1) the mesons, protons, and neutrons which are inside nuclei are themselves composed of quarks and gluons and (2) quantum chromodynamics can be developed into a theory which both describes correctly the interaction among quarks and gluons and is also an exact theory of the strong nuclear force. These concepts are important drivers of the Nuclear Physics program

  7. Dismantling of nuclear facilities

    International Nuclear Information System (INIS)

    Tallec, M.; Kus, J.P.

    2009-01-01

    Nuclear facilities have a long estimable lifetime but necessarily limited in time. At the end of their operation period, basic nuclear installations are the object of cleansing operations and transformations that will lead to their definitive decommissioning and then to their dismantling. Because each facility is somewhere unique, cleansing and dismantling require specific techniques. The dismantlement consists in the disassembly and disposing off of big equipments, in the elimination of radioactivity in all rooms of the facility, in the demolition of buildings and eventually in the reconversion of all or part of the facility. This article describes these different steps: 1 - dismantling strategy: main de-construction guidelines, expected final state; 2 - industries and sites: cleansing and dismantling at the CEA, EDF's sites under de-construction; 3 - de-construction: main steps, definitive shutdown, preparation of dismantling, electromechanical dismantling, cleansing/decommissioning, demolition, dismantling taken into account at the design stage, management of polluted soils; 4 - waste management: dismantlement wastes, national policy of radioactive waste management, management of dismantlement wastes; 5 - mastery of risks: risk analysis, conformability of risk management with reference documents, main risks encountered at de-construction works; 6 - regulatory procedures; 7 - international overview; 8 - conclusion. (J.S.)

  8. Filters in nuclear facilities

    International Nuclear Information System (INIS)

    Berg, K.H.; Wilhelm, J.G.

    1985-01-01

    The topics of the nine papers given include the behavior of HEPA filters during exposure to air flows of high humidity as well as of high differential pressure, the development of steel-fiber filters suitable for extreme operating conditions, and the occurrence of various radioactive iodine species in the exhaust air from boiling water reactors. In an introductory presentation the German view of the performance requirements to be met by filters in nuclear facilities as well as the present status of filter quality assurance are discussed. (orig.) [de

  9. Decommissioning nuclear facilities

    International Nuclear Information System (INIS)

    Buck, S.

    1996-01-01

    Nuclear facilities present a number of problems at the end of their working lives. They require dismantling and removal but public and environmental protection remain a priority. The principles and strategies are outlined. Experience of decommissioning in France and the U.K. had touched every major stage of the fuel cycle by the early 1990's. Decommissioning projects attempt to restrict waste production and proliferation as waste treatment and disposal are costly. It is concluded that technical means exist to deal with present civil plant and costs are now predictable. Strategies for decommissioning and future financial provisions are important. (UK)

  10. Nuclear reactor facility

    International Nuclear Information System (INIS)

    Wampole, N.C.

    1978-01-01

    In order to improve the performance of manitenance and inspections it is proposed for a nuclear reactor facility with a primary circuit containing liquid metal to provide a thermally insulated chamber, within which are placed a number of components of the primary circuit, as e.g. valves, recirculation pump, heat exchangers. The isolated placement permit controlled preheating on one hand, but prevents undesirable heating of adjacent load-bearing elements on the other. The chamber is provided with heating devices and, on the outside, with cooling devices; it is of advantage to fill it with an inert gas. (UWI) 891 HP [de

  11. Steel structures for nuclear facilities

    International Nuclear Information System (INIS)

    1993-01-01

    In the guide the requirements concerning design and fabrication of steel structures for nuclear facilities and documents to be submitted to the Finnish Centre for Radiation and Nuclear Safety (STUK) are presented. Furthermore, regulations concerning inspection of steel structures during construction of nuclear facilities and during their operation are set forth

  12. The situation of nuclear research in Brazil

    International Nuclear Information System (INIS)

    Alves, R.N.

    1989-04-01

    In order to understand the nuclear research situation in Brazil, one must examine the historical facts and their political, economical and social dimensions. In the first part of this work, the international aspects of the nuclear area and the corresponding measures adopted in Brazil are examined. The reasons that caused the country to adopt the current development model are presented. A proposal that will permit Brazil to develop and use nuclear energy in the way it wants and not as it might be imposed is presented. 4 tabs

  13. Nuclear energy : Present situation and future prospects

    International Nuclear Information System (INIS)

    Gray, J.E.

    1986-01-01

    In 1953, President Eisenhower announced the U.S. ''Atoms for Peace'' program. After slightly more than 30 years, there are in operation, under construction or on order more than 400,000 MW of commercial nuclear power generation capacity located in 35 nations, representing a total investment around a trillion U.S. dollars. The situation is noteworthy in terms of the rate of technical development, deployment and transfer, the magnitude of the financial investment, economic benefits, the favorable impact on public health and safety, and the usual and positive character of cooperation among all concerned. The fundamentals of nuclear power generation with regard to economics, safety and environmental impact are likely to favor the increased use of nuclear power. The future prospect of the nuclear power in the U.S. also will be clarified positively. In many ways, U.S. commercial nuclear power continues to benefit from the Navy nuclear propulsion program. The prospect of supply demand situation in the conversion, enrichment and fabrication of uranium fuel is explained. The amount of spent fuel arising in OECD countries and their storage capability up to 2000 are shown, and the storage capability projected is well in excess. (Kako, I.)

  14. Security culture for nuclear facilities

    Science.gov (United States)

    Gupta, Deeksha; Bajramovic, Edita

    2017-01-01

    Natural radioactive elements are part of our environment and radioactivity is a natural phenomenon. There are numerous beneficial applications of radioactive elements (radioisotopes) and radiation, starting from power generation to usages in medical, industrial and agriculture applications. But the risk of radiation exposure is always attached to operational workers, the public and the environment. Hence, this risk has to be assessed and controlled. The main goal of safety and security measures is to protect human life, health, and the environment. Currently, nuclear security considerations became essential along with nuclear safety as nuclear facilities are facing rapidly increase in cybersecurity risks. Therefore, prevention and adequate protection of nuclear facilities from cyberattacks is the major task. Historically, nuclear safety is well defined by IAEA guidelines while nuclear security is just gradually being addressed by some new guidance, especially the IAEA Nuclear Security Series (NSS), IEC 62645 and some national regulations. At the overall level, IAEA NSS 7 describes nuclear security as deterrence and detection of, and response to, theft, sabotage, unauthorized access, illegal transfer or other malicious acts involving nuclear, other radioactive substances and their associated facilities. Nuclear security should be included throughout nuclear facilities. Proper implementation of a nuclear security culture leads to staff vigilance and a high level of security posture. Nuclear security also depends on policy makers, regulators, managers, individual employees and members of public. Therefore, proper education and security awareness are essential in keeping nuclear facilities safe and secure.

  15. Nuclear fuel storage facility

    International Nuclear Information System (INIS)

    Matsumoto, Takashi; Isaka, Shinji.

    1987-01-01

    Purpose: To increase the spent fuel storage capacity and reduce the installation cost in a nuclear fuel storage facility. Constitution: Fuels handled in the nuclear fuel storage device of the present invention include the following four types: (1) fresh fuels, (2) 100 % reactor core charged fuels, (3) spent fuels just after taking out and (4) fuels after a certain period (for example one half-year) from taking out of the reactor. Reactivity is high for the fuels (1), and some of fuels (2), while low in the fuels (3) (4), Source intensity is strong for the fuels (3) and some of the fuels (2), while it is low for the fuels (1) and (4). Taking notice of the fact that the reactivity, radioactive source intensity and generated after heat are different in the respective fuels, the size of the pool and the storage capacity are increased by the divided storage control. While on the other hand, since the division is made in one identical pool, the control method becomes important, and the working range is restricted by means of a template, interlock, etc., the operation mode of the handling machine is divided into four, etc. for preventing errors. (Kamimura, M.)

  16. The Physical Protection of Nuclear Material and Nuclear Facilities

    International Nuclear Information System (INIS)

    1999-08-01

    Physical protection against the theft or unauthorized diversion of nuclear materials and against the sabotage of nuclear facilities by individuals or groups has long been a matter of national and international concern. Although responsibility for establishing and operating a comprehensive physical protection system for nuclear materials and facilities within a State rests entirely with the Government of that State, it is not a matter of indifference to other States whether and to what extent that responsibility is fulfilled. Physical protection has therefore become a matter of international concern and co-operation. The need for international co-operation becomes evident in situations where the effectiveness of physical protection in one State depends on the taking by other States also of adequate measures to deter or defeat hostile actions against nuclear facilities and nuclear materials, particularly when such materials are transported across national frontiers

  17. The Physical Protection of Nuclear Material and Nuclear Facilities

    International Nuclear Information System (INIS)

    1999-06-01

    Physical protection against the theft or unauthorized diversion of nuclear materials and against the sabotage of nuclear facilities by individuals or groups has long been a matter of national and international concern. Although responsibility for establishing and operating a comprehensive physical protection system for nuclear materials and facilities within a State rests entirely with the Government of that State, it is not a matter of indifference to other States whether and to what extent that responsibility is fulfilled. Physical protection has therefore become a matter of international concern and co-operation. The need for international co-operation becomes evident in situations where the effectiveness of physical protection in one State depends on the taking by other States also of adequate measures to deter or defeat hostile actions against nuclear facilities and nuclear materials, particularly when such materials are transported across national frontiers [es

  18. The Physical Protection of Nuclear Material and Nuclear Facilities

    International Nuclear Information System (INIS)

    1999-06-01

    Physical protection against the theft or unauthorized diversion of nuclear materials and against the sabotage of nuclear facilities by individuals or groups has long been a matter of national and international concern. Although responsibility for establishing and operating a comprehensive physical protection system for nuclear materials and facilities within a State rests entirely with the Government of that State, it is not a matter of indifference to other States whether and to what extent that responsibility is fulfilled. Physical protection has therefore become a matter of international concern and co-operation. The need for international co-operation becomes evident in situations where the effectiveness of physical protection in one State depends on the taking by other States also of adequate measures to deter or defeat hostile actions against nuclear facilities and nuclear materials, particularly when such materials are transported across national frontiers

  19. Radiation protection at nuclear fuel cycle facilities

    International Nuclear Information System (INIS)

    Endo, K.; Momose, T.; Furuta, S.

    2011-01-01

    Radiation protection methodologies concerning individual monitoring, workplace monitoring and environmental monitoring in nuclear fuel facilities have been developed and applied to facilities in the Nuclear Fuel Cycle Engineering Laboratories (NCL) of Japan Atomic Energy Agency (JAEA) for over 40 y. External exposure to photon, beta ray and neutron and internal exposure to alpha emitter are important issues for radiation protection at these facilities. Monitoring of airborne and surface contamination by alpha and beta/photon emitters at workplace is also essential to avoid internal exposure. A critical accident alarm system developed by JAEA has been proved through application at the facilities for a long time. A centralised area monitoring system is effective for emergency situations. Air and liquid effluents from facilities are monitored by continuous monitors or sampling methods to comply with regulations. Effluent monitoring has been carried out for 40 y to assess the radiological impacts on the public and the environment due to plant operation. (authors)

  20. Concrete structures for nuclear facilities

    International Nuclear Information System (INIS)

    1996-01-01

    The detailed requirements for the design and fabrication of the concrete structures for nuclear facilities and for the documents to be submitted to the Finnish Centre for Radiation and Nuclear Safety (STUK) are given in the guide. It also sets the requirements for the inspection of concrete structures during the construction and operation of facilities. The requirements of the guide primarily apply to new construction. As regards the repair and modification of nuclear facilities built before its publication, the guide is followed to the extent appropriate. The regulatory activities of the Finnish Centre for Radiation and Nuclear Safety during a nuclear facility's licence application review and during the construction and operation of the facility are summarised in the guide YVL 1.1

  1. Childhood leukemia around nuclear facilities

    International Nuclear Information System (INIS)

    1991-01-01

    This Information Bulletin highlights the conclusion made from an Atomic Energy Control Board of Canada (AECB) study on the incidence of childhood leukemia near nuclear facilities. All of the locations with the nuclear facilities are located in Ontario, the nuclear generating stations at Pickering and Bruce; the uranium mines and mills in Elliot Lake; the uranium refining facility in Port Hope; and nuclear research facilities located at Chalk River plus the small nuclear power plant in Rolphton. Two conclusions are drawn from the study: 1) while the rate of childhood leukemias made be higher or lower than the provincial average, there is no statistical evidence that the difference is due to anything but the natural variation in the occurrence of the disease; and 2) the rate of occurrence of childhood leukemia around the Pickering nuclear power station was slightly greater than the Ontario average both before and after the plant opened, but this, too , could be due to the natural variation

  2. Nuclear facilities situation in Japan after the major earthquake of March 11, 2011. March 23, 2011, 6:00 AM status; Situation des installations nucleaires au Japon suite au seisme majeur survenu le 11 mars 2011. Point de situation du 23 mars 2011 a 06 heures

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-07-01

    This situation note is established according to the information gained on March 23, 2011, at 6:00 AM, by the crisis centre of the French institute of radiation protection and nuclear safety (IRSN). The situation of all 6 reactors of the Fukushima I site (Dai-ichi) and of their spent fuel pools, as well as the situation of the reactors No. 1, 2, 3 and 4 of the Fukushima II site (Daini), and of the Onagawa and Tokai power plants is briefly presented with the progress of the accident management actions. (J.S.)

  3. Nuclear facilities situation in Japan after the major earthquake of March 11, 2011. March 22, 2011, 6:00 AM status; Situation des installations nucleaires au Japon suite au seisme majeur survenu le 11 mars 2011. Point de situation du 22 mars 2011 a 06 heures

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-07-01

    This situation note is established according to the information gained on March 22, 2011, at 6:00 AM, by the crisis centre of the French institute of radiation protection and nuclear safety (IRSN). The situation of all 6 reactors of the Fukushima I site (Dai-ichi) and of their spent fuel pools, as well as the situation of the reactors No. 1, 2, 3 and 4 of the Fukushima II site (Daini), and of the Onagawa and Tokai power plants is briefly presented with the progress of the accident management actions. (J.S.)

  4. Nuclear facilities situation in Japan after the major earthquake of March 11, 2011. March 24, 2011, 8:00 AM status; Situation des installations nucleaires au Japon suite au seisme majeur survenu le 11 mars 2011. Point de situation du 24 mars 2011 a 08 heures

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-07-01

    This situation note is established according to the information gained on March 24, 2011, at 8:00 AM, by the crisis centre of the French institute of radiation protection and nuclear safety (IRSN). The situation of all 6 reactors of the Fukushima I site (Dai-ichi) and of their spent fuel pools, as well as the situation of the reactors No. 1, 2, 3 and 4 of the Fukushima II site (Daini), and of the Onagawa and Tokai power plants is briefly presented with the progress of the accident management actions. (J.S.)

  5. Nuclear facilities situation in Japan after the major earthquake of March 11, 2011. March 29, 2011, 12:00 AM status; Situation des installations nucleaires au Japon suite au seisme majeur survenu le 11 mars 2011. Point de situation du 29 mars 2011 a 12h00

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-07-01

    This situation note is established according to the information gained on March 29, 2011, at 12:00 AM, by the crisis centre of the French institute of radiation protection and nuclear safety (IRSN). The situation of all 6 reactors of the Fukushima I site (Dai-ichi) and of their spent fuel pools, as well as the situation of the reactors No. 1, 2, 3 and 4 of the Fukushima II site (Daini), and of the Onagawa and Tokai power plants is briefly presented with the progress of the accident management actions. (J.S.)

  6. Nuclear facilities situation in Japan after the major earthquake of March 11, 2011. March 21, 2011, 3:00 PM status; Situation des installations nucleaires au Japon suite au seisme majeur survenu le 11 mars 2011. Point de situation du 21 mars 2011 a 15 heures

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-07-01

    This situation note is established according to the information gained on March 21, 2011, at 3:00 PM, by the crisis centre of the French institute of radiation protection and nuclear safety (IRSN). The situation of all 6 reactors of the Fukushima I site (Dai-ichi) and of their spent fuel pools, as well as the situation of the reactors No. 1, 2, 3 and 4 of the Fukushima II site (Daini), and of the Onagawa and Tokai power plants is briefly presented with the progress of the accident management actions. (J.S.)

  7. Nuclear facilities situation in Japan after the major earthquake of March 11, 2011. March 25, 2011, 8:00 AM status; Situation des installations nucleaires au Japon suite au seisme majeur survenu le 11 mars 2011. Point de situation du 25 mars a 08h00

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-07-01

    This situation note is established according to the information gained on March 25, 2011, at 8:00 AM, by the crisis centre of the French institute of radiation protection and nuclear safety (IRSN). The situation of all 6 reactors of the Fukushima I site (Dai-ichi) and of their spent fuel pools, as well as the situation of the reactors No. 1, 2, 3 and 4 of the Fukushima II site (Daini), and of the Onagawa and Tokai power plants is briefly presented with the progress of the accident management actions. (J.S.)

  8. Nuclear facilities situation in Japan after the major earthquake of March 11, 2011. March 26, 2011, 10:00 AM status; Situation des installations nucleaires au Japon suite au seisme majeur survenu le 11 mars 2011. Point de situation du 26 mars 2011 a 10h00

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-07-01

    This situation note is established according to the information gained on March 26, 2011, at 10:00 AM, by the crisis centre of the French institute of radiation protection and nuclear safety (IRSN). The situation of all 6 reactors of the Fukushima I site (Dai-ichi) and of their spent fuel pools, as well as the situation of the reactors No. 1, 2, 3 and 4 of the Fukushima II site (Daini), and of the Onagawa and Tokai power plants is briefly presented with the progress of the accident management actions. (J.S.)

  9. Nuclear facilities situation in Japan after the major earthquake of March 11, 2011. March 28, 2011, 8:00 AM status; Situation des installations nucleaires au Japon suite au seisme majeur survenu le 11 mars 2011. Point de situation du 28 mars 2011 a 08h00

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-07-01

    This situation note is established according to the information gained on March 28, 2011, at 8:00 AM, by the crisis centre of the French institute of radiation protection and nuclear safety (IRSN). The situation of all 6 reactors of the Fukushima I site (Dai-ichi) and of their spent fuel pools, as well as the situation of the reactors No. 1, 2, 3 and 4 of the Fukushima II site (Daini), and of the Onagawa and Tokai power plants is briefly presented with the progress of the accident management actions. (J.S.)

  10. Situation of nuclear industry in Japan

    International Nuclear Information System (INIS)

    2004-03-01

    This document presents the situation of nuclear industry in Japan: cooperation with France in the domain of the fuel cycle (in particular the back-end) and of for the industrial R and D about fast reactors and nuclear safety; present day situation characterized by a series of incidents in the domain of nuclear safety and by an administrative reorganization of the research and safety organizations; power of local representatives, results of April 2003 elections, liberalization of the electric power sector, impact of the TEPCO affair (falsification of safety reports) on the nuclear credibility, re-start up of the Monju reactor delayed by judicial procedures, stopping of the program of MOX fuel loading in Tepco's reactors, discovery of weld defects in the newly built Rokkasho-mura reprocessing plant, an ambitious program of reactors construction, the opportunity of Russian weapons dismantling for the re-launching of sodium-cooled fast reactors; the competition between France and Japan for the setting up of ITER reactor and its impact of the French/Japanese partnership. (J.S.)

  11. Brennilis nuclear facilities. 2009 annual report

    International Nuclear Information System (INIS)

    2010-01-01

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

  12. Civaux nuclear facilities. 2009 annual report

    International Nuclear Information System (INIS)

    2010-01-01

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

  13. Chooz nuclear facilities. 2009 annual report

    International Nuclear Information System (INIS)

    2010-01-01

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

  14. Situation and future outlook of nuclear medicine technologists

    International Nuclear Information System (INIS)

    Kanao, Keisuke

    1981-01-01

    About the situation of nuclear medicine technologists in Japan, survey was made in August, 1979, by sending questionnaire to 219 facilities, and 341 technologists responded, the recovery rate being 70%. About the situation in the United States, the data were taken from the similar survey results in 1975 and 1976. The results in Japan, as compared with those in the United States, are described as follows: years of experience, contents of work, participation in society meetings and others, and occupation prior to the employment as nuclear medicine technologists. The findings are interesting in such items as the sexes of the technologists, the participation in meetings, and the types of works. In Japan, the technologists are dominantly male, while in the United States, more than 80% are female. In Japan, 97% of the technologists participated in society meetings and others. (J.P.N.)

  15. Earthquake engineering for nuclear facilities

    CERN Document Server

    Kuno, Michiya

    2017-01-01

    This book is a comprehensive compilation of earthquake- and tsunami-related technologies and knowledge for the design and construction of nuclear facilities. As such, it covers a wide range of fields including civil engineering, architecture, geotechnical engineering, mechanical engineering, and nuclear engineering, for the development of new technologies providing greater resistance against earthquakes and tsunamis. It is crucial both for students of nuclear energy courses and for young engineers in nuclear power generation industries to understand the basics and principles of earthquake- and tsunami-resistant design of nuclear facilities. In Part I, "Seismic Design of Nuclear Power Plants", the design of nuclear power plants to withstand earthquakes and tsunamis is explained, focusing on buildings, equipment's, and civil engineering structures. In Part II, "Basics of Earthquake Engineering", fundamental knowledge of earthquakes and tsunamis as well as the dynamic response of structures and foundation ground...

  16. Environmental monitoring of nuclear facilities

    International Nuclear Information System (INIS)

    Winter, M.

    1983-01-01

    The objectives of one environmental monitoring program for nuclear facilities, are presented. The program in Federal Republic of Germany, its goals, its basic conditions, its regulations, and its dose limits are emphasized. (E.G.) [pt

  17. Nuclear facilities licensing

    International Nuclear Information System (INIS)

    Carvalho, A.J.M. de.

    1978-01-01

    The need for the adoption of a legal and normative system, defining objectives, pescriptions and the process of nuclear licensing and building of nuclear power plants in Brazil is enphasized. General rules for the development of this system are presented. The Brazilian rules on the matter are discussed. A general view of the German legal system for nuclear power plant licensing and the IAEA recommendations on the subject are finally presented. (A.L.S.L.) [pt

  18. Fatigue damage of nuclear facilities

    International Nuclear Information System (INIS)

    2001-01-01

    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.)

  19. Decontamination of nuclear facilities

    International Nuclear Information System (INIS)

    1982-01-01

    Thirty-seven papers were presented at this conference in five sessions. Topics covered include regulation, control and consequences of decontamination; decontamination of components and facilities; chemical and non-chemical methods of decontamination; and TMI decontamination experience

  20. Socket welds in nuclear facilities

    International Nuclear Information System (INIS)

    Anderson, P.A.; Torres, L.L.

    1995-01-01

    Socket welds are easier and faster to make than are butt welds. However, they are often not used in nuclear facilities because the crevices between the pipes and the socket sleeves may be subject to crevice corrosion. If socket welds can be qualified for wider use in facilities that process nuclear materials, the radiation exposures to welders can be significantly reduced. The current tests at the Idaho Chemical Processing Plant (ICPP) are designed to determine if socket welds can be qualified for use in the waste processing system at a nuclear fuel processing plant

  1. The decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    Niel, J.Ch.; Rieu, J.; Lareynie, O.; Delrive, L.; Vallet, J.; Girard, A.; Duthe, M.; Lecomte, C.; Rozain, J.P.; Nokhamzon, J.G.; Davoust, M.; Eyraud, J.L.; Bernet, Ph.; Velon, M.; Gay, A.; Charles, Th.; Leschaeva, M.; Dutzer, M.; Maocec, Ch.; Gillet, G.; Brut, F.; Dieulot, M.; Thuillier, D.; Tournebize, F.; Fontaine, V.; Goursaud, V.; Birot, M.; Le Bourdonnec, Th.; Batandjieva, B.; Theis, St.; Walker, St.; Rosett, M.; Cameron, C.; Boyd, A.; Aguilar, M.; Brownell, H.; Manson, P.; Walthery, R.; Wan Laer, W.; Lewandowski, P.; Dorms, B.; Reusen, N.; Bardelay, J.; Damette, G.; Francois, P.; Eimer, M.; Tadjeddine, A.; Sene, M.; Sene, R.

    2008-01-01

    This file includes five parts: the first part is devoted to the strategies of the different operators and includes the following files: the decommissioning of nuclear facilities Asn point of view, decommissioning of secret nuclear facilities, decommissioning at the civil Cea strategy and programs, EDF de-construction strategy, Areva strategy for decommissioning of nuclear facilities; the second one concerns the stakes of dismantling and includes the articles as follow: complete cleanup of buildings structures in nuclear facilities, decommissioning of nuclear facilities and safety assessment, decommissioning wastes management issues, securing the financing of long-term decommissioning and waste management costs, organizational and human factors in decommissioning projects, training for the decommissioning professions: the example of the Grenoble University master degree; the third part is devoted to the management of dismantling work sites and includes the different articles as follow: decommissioning progress at S.I.C.N. plant, example of decommissioning work site in Cea Grenoble: Siloette reactor decommissioning, matters related to decommissioning sites, decommissioning of french nuclear installations: the viewpoint of a specialist company, specificities of inspections during decommissioning: the Asn inspector point of view; the fourth part is in relation with the international approach and includes as follow: IAEA role in establishing a global safety regime on decommissioning, towards harmonization of nuclear safety practices in Europe: W.E.N.R.A. and the decommissioning of nuclear facilities, EPA superfund program policy for decontamination and decommissioning, progress with remediation at Sellafield, progress and experiences from the decommissioning of the Eurochemic reprocessing plant in Belgium, activities of I.R.S.N. and its daughter company Risk-audit I.r.s.n./G.r.s. international in the field of decommissioning of nuclear facilities in eastern countries

  2. The nuclear situation in India; La situation nucleaire en Inde

    Energy Technology Data Exchange (ETDEWEB)

    Macias, R.M

    2006-07-01

    This report first recalls that India lacks of energy natural resources, faces a high demographic growth and high electricity demand, and launched a civil nuclear program in the 1960's which comprises three stages: a first one with natural uranium fuelled PHWR type reactors, a second one with fast neutron reactors (which is now at its beginning), and a third one which will use the thorium-uranium 233 cycle both in fast neutron and AHWR (advanced heavy water reactor)type reactors. After the indication of some data on the present and foreseen nuclear capacity, this report presents the authorities and actors of the nuclear sector, the national laws related to nuclear activities, the Indian position with respect to international treaties and conventions, indicates the location of the numerous nuclear installations, gives some characteristics of the existing and projected nuclear power stations and research reactors. It presents the fuel manufacturing and reprocessing activities, the sites of heavy water production and their capacities. It gives an overview of the waste management activity (origin, classification, processing and packaging for the different types of wastes, warehousing and storage with different technologies and technical options depending on the waste type)

  3. The present situation of nuclear wastes

    International Nuclear Information System (INIS)

    Courtois, Charles

    2012-01-01

    This Power Point presentation contains graphs, tables and comments on different aspects of nuclear wastes: origin in France (fuel composition, long-life and short life wastes), definition of the different types of wastes (with respect to their life and their activity level), fuel cycle (processing of the different wastes, actors in France, waste management), waste characterization (controls, tests), laws on wastes published in 1991 (objectives with respect to separation and transmutation technologies, to storage possibilities, to conditioning and long term storage) and in 2006 (which defines a national plan for radioactive material and waste management, and a research program), the French national inventory, low activity wastes (production and storage), the transmutation technology (notably the Astrid project), the geological storage (the Cigeo project for a geological storage), and the situation in other countries

  4. Computer Security at Nuclear Facilities (French Edition)

    International Nuclear Information System (INIS)

    2013-01-01

    The possibility that nuclear or other radioactive material could be used for malicious purposes cannot be ruled out in the current global situation. States have responded to this risk by engaging in a collective commitment to strengthen the protection and control of such material and to respond effectively to nuclear security events. States have agreed to strengthen existing instruments and have established new international legal instruments to enhance nuclear security worldwide. Nuclear security is fundamental in the management of nuclear technologies and in applications where nuclear or other radioactive material is used or transported. Through its Nuclear Security Programme, the IAEA supports States to establish, maintain and sustain an effective nuclear security regime. The IAEA has adopted a comprehensive approach to nuclear security. This recognizes that an effective national nuclear security regime builds on: the implementation of relevant international legal instruments; information protection; physical protection; material accounting and control; detection of and response to trafficking in such material; national response plans; and contingency measures. With its Nuclear Security Series, the IAEA aims to assist States in implementing and sustaining such a regime in a coherent and integrated manner. The IAEA Nuclear Security Series comprises Nuclear Security Fundamentals, which include objectives and essential elements of a State's nuclear security regime; Recommendations; Implementing Guides; and Technical Guidance. Each State carries the full responsibility for nuclear security, specifically: to provide for the security of nuclear and other radioactive material and associated facilities and activities; to ensure the security of such material in use, storage or in transport; to combat illicit trafficking and the inadvertent movement of such material; and to be prepared to respond to a nuclear security event. This publication is in the Technical Guidance

  5. Ventilation of nuclear facilities

    International Nuclear Information System (INIS)

    1982-01-01

    In this work an examination is made of ventilation problems in nuclear installations, of the fuel cycle or the handling of radioactive compounds. The study covers the detection of radioactive aerosols, purification, iodine trapping, ventilation equipment and its maintenance, engineering, safety of ventilation, fire efficiency, operation, regulations and normalization [fr

  6. LAMPF: a nuclear research facility

    International Nuclear Information System (INIS)

    Livingston, M.S.

    1977-09-01

    A description is given of the recently completed Los Alamos Meson Physics Facility (LAMPF) which is now taking its place as one of the major installations in this country for the support of research in nuclear science and its applications. Descriptions are given of the organization of the Laboratory, the Users Group, experimental facilities for research and for applications, and procedures for carrying on research studies

  7. Nuclear Station Facilities Improvement Planning

    International Nuclear Information System (INIS)

    Hooks, R. W.; Lunardini, A. L.; Zaben, O.

    1991-01-01

    An effective facilities improvement program will include a plan for the temporary relocation of personnel during the construction of an adjoining service building addition. Since the smooth continuation of plant operation is of paramount importance, the phasing plan is established to minimize the disruptions in day-to-day station operation and administration. This plan should consider the final occupancy arrangements and the transition to the new structure; for example, computer hookup and phase-in should be considered. The nuclear industry is placing more emphasis on safety and reliability of nuclear power plants. In order to do this, more emphasis is placed on operations and maintenance. This results in increased size of managerial, technical and maintenance staffs. This in turn requires improved office and service facilities. The facilities that require improvement may include training areas, rad waste processing and storage facilities, and maintenance facilities. This paper discusses an approach for developing an effective program to plan and implement these projects. These improvement projects can range in magnitude from modifying a simple system to building a new structure to allocating space for a future project. This paper addresses the planning required for the new structures with emphasis on site location, space allocation, and internal layout. Since facility planning has recently been completed by Sargent and Leyden at six U. S. nuclear stations, specific examples from some of those plants are presented. Site planning and the establishment of long-range goals are of the utmost importance when undertaking a facilities improvement program for a nuclear station. A plan that considers the total site usage will enhance the value of both the new and existing facilities. Proper planning at the beginning of the program can minimize costs and maximize the benefits of the program

  8. Disaster countermeasures around nuclear facilities

    International Nuclear Information System (INIS)

    Tatsuta, Yoshinori

    1982-01-01

    The following matters are described. Safety regulation administration for nuclear power plants; nuclear disaster countermeasures in the United States; disaster countermeasures around nuclear facilities (a report of the ad hoc committee in Nuclear Safety Commission), including general requirements, the scope of areas to take the countermeasures, emergency environmental monitoring, guidelines for taking the countermeasures, and emergency medical treatment. In the nuclear safety administration, the system of stationing safety expert personnel on the sites of nuclear power generation and qualifying the persons in charge of reactor operation in the control room is also introduced. As for the disaster countermeasures, such as the detection of an abnormal state, the notification of the abnormality to various organs concerned, the starting of emergency environmental monitoring, the establishment of the countermeasure headquarters, and emergency measures for the local people. (Mori, K.)

  9. Market situation in nuclear fuel cycle

    International Nuclear Information System (INIS)

    Anon.

    1985-01-01

    The existing uranium reserves cover the needs for at least 80 years, the probable ones are 2 to 5 times larger, seawater is an unlimited source of uranium. On the spot market the price was in 1985 355 SEK/kg U, the long-period contracts are expected to be at 700 SEK/kg U. Uranium is supplied to Finland and Sweden from Australia, Canada, France, Niger and Gabon. Conversion (about 50 SEK/kg U) is supplied to Finland and Sweden by Eldorado Resources Canada, Comurhex France, BNFL Great Britain and Allied Chemical USA. Prices for enrichment are at least 1200 SEK/kg SWU for USA and 900 SEK/kg SWU for European enrichment. Enrichment is supplied to Finland and Sweden by Eurodif France, Urenco Holland, West Germany and Great Britain, USA DOE and Techsnabexport USSR. There is about 90% exceeding capacity of fabrication. Fabrication is supplied by ASEA-ATOM Sweden, Exxon USA and FRG FRAGEMA France, KWU/FRG and Atomenergoexport USSR. These five suppliers offer 7 essentially different designs. Prices range from 1200 to 1800 SEK/kg U. Sweden established storage facility for used fuel CLAB in 1985, Finland will have such facility ready in 1987. Both Sweden and Finland are investigating disposal. Sweden has a contract for processing of a minor burnt-out fuel batch in England and France. Sweden attempts to reduce the quantities to be processed. A levellized fuel price for a nuclear power plant set into operation in 1990-ties is estimated as 6.6 SE oere/kWh. (eg)

  10. Introduction to nuclear facilities engineering

    International Nuclear Information System (INIS)

    Sapy, Georges

    2012-06-01

    Engineering, or 'engineer's art', aims at transforming simple principle schemes into operational facilities often complex especially when they concern the nuclear industry. This transformation requires various knowledge and skills: in nuclear sciences and technologies (nuclear physics, neutronics, thermal-hydraulics, material properties, radiation protection..), as well as in non-nuclear sciences and technologies (civil engineering, mechanics, electricity, computer sciences, instrumentation and control..), and in the regulatory, legal, contractual and financial domains. This book explains how this huge body of knowledge and skills must be organized and coordinated to create a reliable, exploitable, available, profitable and long-lasting facility, together with respecting extremely high safety, quality, and environmental impact requirements. Each aspect of the problem is approached through the commented presentation of nuclear engineering macro-processes: legal procedures and administrative authorizations, nuclear safety/radiation protection/security approach, design and detailed studies, purchase of equipments, on-site construction, bringing into operation, financing, legal, contractual and logistic aspects, all under the global control of a project management. The 'hyper-complexness' of such an approach leads to hard points and unexpected events. The author identifies the most common ones and proposes some possible solutions to avoid, mitigate or deal with them. In a more general way, he proposes some thoughts about the performance factors of a nuclear engineering process

  11. Meteorological instrumentation for nuclear facilities

    International Nuclear Information System (INIS)

    Costa, A.C.L. da.

    1983-01-01

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

  12. Nuclear reactor containing facility

    International Nuclear Information System (INIS)

    Hidaka, Masataka; Murase, Michio.

    1994-01-01

    In a reactor containing facility, a condensation means is disposed above the water level of a cooling water pool to condensate steams of the cooling water pool, and return the condensated water to the cooling water pool. Upon occurrence of a pipeline rupture accident, steams generated by after-heat of a reactor core are caused to flow into a bent tube, blown from the exit of the bent tube into a suppression pool and condensated in a suppression pool water, thereby suppressing the pressure in the reactor container. Cooling water in the cooling water pool is boiled by heat conduction due to the condensation of steams, then the steams are exhausted to the outside of the reactor container to remove the heat of the reactor container to the outside of the reactor. In addition, since cooling water is supplied to the cooling water pool quasi-permanently by gravity as a natural force, the reactor container can be cooled by the cooling water pool for a long period of time. Since the condensation means is constituted with a closed loop and interrupted from the outside, radioactive materials are never released to the outside. (N.H.)

  13. Nuclear power generation facility

    International Nuclear Information System (INIS)

    Kubo, Mitsuji.

    1996-01-01

    Main steams are introduced from a moisture separation device for removing moisture content of the main steams to a low pressure turbine passing through a cross-around pipe. A condensate desalter comprising a mixed floor-type desalting tower using granular ion exchange resins is disposed at the downstream of the main condensator by way of condensate pipelines, and a feedwater heater is disposed at the downstream. Structural members of the main condensator are formed by weather proof steels. Low alloy steels are used partially or entirely for the cross-around pipe, gas extraction pipelines, heat draining pipelines, inner structural members other than pipelines in the feedwater heater, and the body and the inner structural members of the moisture separator. Titanium or a titanium alloy is used for the pipelines in the main condensator. With such a constitution, BWR type reactor facilities, in which the concentration of cruds inflown to the condensate cleanup system is reduced to simplify the condensate cleanup device can be obtained. (I.N.)

  14. Iraq nuclear facility dismantlement and disposal project

    Energy Technology Data Exchange (ETDEWEB)

    Cochran, J R; Danneels, J [Sandia National Laboratories, Albuquerque, NM (United States); Kenagy, W D [U.S. Department of State, Bureau of International Security and Nonproliferation, Office of Nuclear Energy, Safety and Security, Washington, DC (United States); Phillips, C J; Chesser, R K [Center for Environmental Radiation Studies, Texas Tech University, Lubbock, TX (United States)

    2007-07-01

    The Al Tuwaitha nuclear complex near Baghdad contains a significant number of nuclear facilities from Saddam Hussein's dictatorship. Because of past military operations, lack of upkeep and looting there is now an enormous radioactive waste problem at Al Tuwaitha. Al Tuwaitha contains uncharacterised radioactive wastes, yellow cake, sealed radioactive sources, and contaminated metals. The current security situation in Iraq hampers all aspects of radioactive waste management. Further, Iraq has never had a radioactive waste disposal facility, which means that ever increasing quantities of radioactive waste and material must be held in guarded storage. The Iraq Nuclear Facility Dismantlement and Disposal Program (the NDs Program) has been initiated by the U.S. Department of State (DOS) to assist the Government of Iraq (GOI) in eliminating the threats from poorly controlled radioactive materials, while building human capacities so that the GOI can manage other environmental cleanups in their country. The DOS has funded the International Atomic Energy Agency (IAEA) to provide technical assistance to the GOI via a Technical Cooperation Project. Program coordination will be provided by the DOS, consistent with U.S. and GOI policies, and Sandia National Laboratories will be responsible for coordination of participants and for providing waste management support. Texas Tech University will continue to provide in-country assistance, including radioactive waste characterization and the stand-up of the Iraq Nuclear Services Company. The GOI owns the problems in Iraq and will be responsible for the vast majority of the implementation of the NDs Program. (authors)

  15. Nuclear materials facility safety initiative

    International Nuclear Information System (INIS)

    Peddicord, K.L.; Nelson, P.; Roundhill, M.; Jardine, L.J.; Lazarev, L.; Moshkov, M.; Khromov, V.V.; Kruchkov, E.; Bolyatko, V.; Kazanskij, Yu.; Vorobeva, I.; Lash, T.R.; Newton, D.; Harris, B.

    2000-01-01

    Safety in any facility in the nuclear fuel cycle is a fundamental goal. However, it is recognized that, for example, should an accident occur in either the U.S. or Russia, the results could seriously delay joint activities to store and disposition weapons fissile materials in both countries. To address this, plans are underway jointly to develop a nuclear materials facility safety initiative. The focus of the initiative would be to share expertise which would lead in improvements in safety and safe practices in the nuclear fuel cycle.The program has two components. The first is a lab-to-lab initiative. The second involves university-to-university collaboration.The lab-to-lab and university-to-university programs will contribute to increased safety in facilities dealing with nuclear materials and related processes. These programs will support important bilateral initiatives, develop the next generation of scientists and engineers which will deal with these challenges, and foster the development of a safety culture

  16. Physical security of nuclear facilities

    International Nuclear Information System (INIS)

    Dixon, H.

    1987-01-01

    A serious problem with present security systems at nuclear facilities is that the threats and standards prepared by the NRC and DOE are general, and the field offices are required to develop their own local threats and, on that basis, to prepared detailed specifications for security systems at sites in their jurisdiction. As a result, the capabilities of the systems vary across facilities. Five steps in particular are strongly recommended as corrective measures: 1. Those agencies responsible for civil nuclear facilities should jointly prepare detailed threat definitions, operational requirements, and equipment specifications to protect generic nuclear facilities, and these matters should be issued as policy. The agencies should provide sufficient detail to guide the design of specific security systems and to identify candidate components. 2. The DOE, NRC, and DOD should explain to Congress why government-developed security and other military equipment are not used to upgrade existing security systems and to stock future ones. 3. Each DOE and NRC facility should be assessed to determine the impact on the size of the guard force and on warning time when personnel-detecting radars and ground point sensors are installed. 4. All security guards and technicians should be investigated for the highest security clearance, with reinvestigations every four years. 5. The processes and vehicles used in intrafacility transport of nuclear materials should be evaluated against a range of threats and attack scenarios, including violent air and vehicle assaults. All of these recommendations are feasible and cost-effective. The appropriate congressional subcommittees should direct that they be implemented as soon as possible

  17. Laundry monitor for nuclear facilities

    Energy Technology Data Exchange (ETDEWEB)

    Ishibashi, Mitsuo (Toshiba Corp., Fuchu (Japan). Fuchu Works)

    1984-06-01

    A laundry monitor has been developed for the detection and cleansification of radiation contamination on the clothes, headgear, footgear, etc. of workers in nuclear facilities. With this monitor, measurement is made irrespective of the size and shape of the objects; a large-area plastic scintillation detector is incorporated; it has stable and highly sensitive characteristics, with the merits of swift measurement, economical operation and easy maintenance. Connected with a folding machine, automatic carrying and storing compartment through a conveyor, it is capable of saving energy and man power, contributing to scheduled operation, and improving the efficiency of the facilities.

  18. Laundry monitor for nuclear facilities

    International Nuclear Information System (INIS)

    Ishibashi, Mitsuo

    1984-01-01

    A laundry monitor has been developed for the detection and cleansification of radiation contamination on the clothes, headgear, footgear, etc. of workers in nuclear facilities. With this monitor, measurement is made irrespective of the size and shape of the objects ; a large-area plastic scintillation detector is incorporated ; it has stable and highly sensitive characteristics, with the merits of swift measurement, economical operation and easy maintenance. Connected with a folding machine, automatic carrying and storing compartment through a conveyor, it is capable of saving energy and man power, contributing to scheduled operation, and improving the efficiency of the facilities. (author)

  19. Survey of the market situation within the nuclear fuels cycle

    International Nuclear Information System (INIS)

    1983-05-01

    A brief survey of the global situation in 1983 regarding resources, production costs, supply of, and demand for, uranium including a prognosis of the nuclear effect and the capacity of the western countries for conversion, with emphasis on the Scandinavian countries. The situation concerning management of spent nuclear fuels is also elaborated. (AB)

  20. Particulate filtration in nuclear facilities

    International Nuclear Information System (INIS)

    1991-01-01

    The removal of particulate radioactive material from exhaust air or gases is an essential feature of virtually all nuclear facilities. Recent IAEA publications have covered the broad designs of off-gas and air cleaning systems for the range of nuclear power plants and other facilities. This report is a complementary guidebook that examines in detail the latest developments in the design, operation, maintenance and testing of fibrous air filters. The original draft of the report was prepared by three consultants, M.W. First, of the School of Public Health, Harvard University, United States of America, K.S. Robinson, from the UKAEA Harwell Laboratory, United Kingdom, and H.G. Dillmann, of the Kernforschungzentrum, Karlsruhe, Germany. The Technical Committee Meeting (TCM), at which the report was reviewed and much additional information contributed, was attended by 11 experts and was held in Vienna, from 30 May to 3 June 1988. 64 refs, 41 figs, 10 tabs

  1. PROJECTIZING AN OPERATING NUCLEAR FACILITY

    International Nuclear Information System (INIS)

    Adams, N

    2007-01-01

    This paper will discuss the evolution of an operations-based organization to a project-based organization to facilitate successful deactivation of a major nuclear facility. It will describe the plan used for scope definition, staff reorganization, method estimation, baseline schedule development, project management training, and results of this transformation. It is a story of leadership and teamwork, pride and success. Workers at the Savannah River Site's (SRS) F Canyon Complex (FCC) started with a challenge--take all the hazardous byproducts from nearly 50 years of operations in a major, first-of-its-kind nuclear complex and safely get rid of them, leaving the facility cold, dark, dry and ready for whatever end state is ultimately determined by the United States Department of Energy (DOE). And do it in four years, with a constantly changing workforce and steadily declining funding. The goal was to reduce the overall operating staff by 93% and budget by 94%. The facilities, F Canyon and its adjoined sister, FB Line, are located at SRS, a 310-square-mile nuclear reservation near Aiken, S.C., owned by DOE and managed by Washington Group International subsidiary Washington Savannah River Company (WSRC). These facilities were supported by more than 50 surrounding buildings, whose purpose was to provide support services during operations. The radiological, chemical and industrial hazards inventory in the old buildings was significant. The historical mission at F Canyon was to extract plutonium-239 and uranium-238 from irradiated spent nuclear fuel through chemical processing. FB Line's mission included conversion of plutonium solutions into metal, characterization, stabilization and packaging, and storage of both metal and oxide forms. The plutonium metal was sent to another DOE site for use in weapons. Deactivation in F Canyon began when chemical separations activities were completed in 2002, and a cross-functional project team concept was implemented to successfully

  2. Environmental monitoring of nuclear facilities

    International Nuclear Information System (INIS)

    Koelzer, W.

    1988-01-01

    Environmental monitoring of nuclear facilities is part of general monitoring for environmental radioactivity all over the territory of the Federal Republic of Germany. General principles of environmental monitoring were formulated by the ICRP in 1965. In 1974 guidelines for measures of monitoring the environment of NPP incorporating LWR were drafted, which helped to standardize environmental monitoring programs. Since 1958, data on environmental radioactivity from measurements by authorized laboratories have been published in reports. (DG)

  3. Decommissioning of nuclear power facilities

    International Nuclear Information System (INIS)

    Nosovskij, A.V.; Vasil'chenko, V.N.; Klyuchnikov, A.A.; Yashchenko, Ya.V.

    2005-01-01

    This is the first manual in Ukraine giving the complete review of the decommissioning process of the nuclear power facilities including the issues of the planning, design documentation development, advanced technology description. On the base of the international and domestic experience, the issues on the radwaste management, the decontamination methods, the equipment dismantling, the remote technology application, and also the costs estimate at decommissioning are considered. The special attention to the personnel safety provision, population and environment at decommissioning process is paid

  4. Computer Security at Nuclear Facilities

    International Nuclear Information System (INIS)

    Cavina, A.

    2013-01-01

    This series of slides presents the IAEA policy concerning the development of recommendations and guidelines for computer security at nuclear facilities. A document of the Nuclear Security Series dedicated to this issue is on the final stage prior to publication. This document is the the first existing IAEA document specifically addressing computer security. This document was necessary for 3 mains reasons: first not all national infrastructures have recognized and standardized computer security, secondly existing international guidance is not industry specific and fails to capture some of the key issues, and thirdly the presence of more or less connected digital systems is increasing in the design of nuclear power plants. The security of computer system must be based on a graded approach: the assignment of computer system to different levels and zones should be based on their relevance to safety and security and the risk assessment process should be allowed to feed back into and influence the graded approach

  5. Childhood leukemia around nuclear facilities

    International Nuclear Information System (INIS)

    Hatch, M.

    1992-01-01

    Epidemiologic studies on health effects of living near nuclear facilities have been rare and, indeed, radiobiological models would not predict any detectable increase in cancer risk to the general public from very low levels of radioactivity emitted by nuclear installations. Thus recent evidence suggesting an excess of childhood leukemias in the vicinity of certain nuclear sites in the United Kingdom has generated considerable controversy. To help resolve the uncertainty and enhance interpretability of results, future epidemiologic studies will need to be designed with great care (and within realistic cost limits). This commentary suggests three areas for methodologic consideration: 1. definition and modelling of radiation exposure; 2. selection of cancer sites and sensitive subgroups, and 3. use of incidence of mortality data. Specific suggestions for further epidemiologic research are offered as well. (author). 8 refs

  6. Situation of nuclear power generation in Sweden

    Energy Technology Data Exchange (ETDEWEB)

    Sandstroem, S [Swedish Atomic Forum

    1978-01-01

    In Sweden, nuclear power generation was received initially favorably. In the end of 1960s, however, nuclear power generation got involved in the activities of environment preservation. Then, political parties became opposed to nuclear power generation, and now, the need of nuclear power generation itself is regarded as questionable. In the general election in 1976, the Government opposing the nuclear power generation won. As the result, the conditional nuclear power development law and the energy committee were set up. The committee composed of parliament members, experts, and representatives of enterprises and trade unions is to submit its report so that the parliament can prepare a new energy program in the fall of 1978. Meanwhile, the nuclear fuel safety project formed newly has studied to satisfy the conditions of the law. In Sweden, which has developed nuclear reactors independently from the technology of USA, the oppositions are on the decrease, however. It is awaited what decision will be made by the Government in this fall.

  7. Terrorist threats of nuclear facilities

    International Nuclear Information System (INIS)

    Jozsef Solymosi; Jozser Ronaky; Zoltan Levai; Arpad Vincze; Laszlo Foldi

    2004-01-01

    More than one year has passed since the terrible terrorist attacks against the United States. The tragic event fundamentally restructured our security policy approach and made requirements of countering terrorism a top priority of the 21st century. In one year a lot of studies were published and the majority of them analyses primarily the beginnings of terrorism then focus on the interrelations of causes and consequences of the attacks against the WTC. In most of the cases the authors can only put their questions most of which have remained unanswered to date. Meanwhile, in a short while after the attacks the secret assessments of threat levels of potential targets and areas were also prepared. One of the high priority fields is the issue of nuclear, biological, and chemical security, in short NBC-security. Here and now we focus on component N, that is the assessment techniques of nuclear security in short, without aiming at completeness. Our definite objective is to make non-expert readers understand - and present a concrete example as it is done in risk analysis - the real danger-level of nuclear facilities and especially the terrorist threat. Our objective is not to give tips to terrorists but to provide them with deterring arguments and at the same time calm worried people. In our communique we give an overview of international practice of nuclear antiterrorism and of preventive nuclear protection in Hungary. (author)

  8. Situation of nuclear power generation in Europe

    International Nuclear Information System (INIS)

    Toukai, Kunihiro

    2003-01-01

    Nuclear power plants began to be built in Europe in the latter half of 1960. 146 plants are operating and generating about 33% of total power in 2002. France is top of Europe and operating 59 plants, which generate about 75% of power generation in the country. Germany is second and 30%. England is third and 30%. However, Germany decided not to build new atomic power plant in 2000. Movement of non-nuclear power generation is decreasing in Belgium and Switzerland. The liberalization of power generation decreased the wholesale price and BE Company in England was financial difficulties. New nuclear power generation is planning in Finland and France. (S.Y.)

  9. Teachers and nuclear energy - German situation

    International Nuclear Information System (INIS)

    Schaeferhenrich, B.

    1994-01-01

    School education in Germany is the responsibility of each federal state; there is no national curriculum. Nevertheless, all pupils of all types of school are confronted with the energy topic; nuclear energy is a compulsory topic in a subject where pupils' achievements are marked; interdisciplinary thinking is encouraged. The approach may however fail because of inflexible teachers (against nuclear energy), organizational structures and complementary training

  10. Nuclear exportation and importation - the Brazilian situation

    International Nuclear Information System (INIS)

    Lavos Coimbra, G.

    1986-01-01

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

  11. Past and present situation of nuclear research at Forschungszentrum Karlsruhe

    International Nuclear Information System (INIS)

    Scholtyssek, W.

    2001-01-01

    The case of Forschungszentrum Karlsruhe is presented which had to transform from a centre devoted to nuclear power R and D to one in which this activity is allocated only 20% of the resources. A large number of operating nuclear power reactors coupled with the Government decision to phase out nuclear power is causing serious concerns regarding the availability of human resources for meeting the long term needs of nuclear facilities. The Energy Division of the research centre currently focuses mainly on safety research and on nuclear fusion. Another Division of the centre has nuclear facility decommissioning as one of the programmes. Independent research in areas of essential need for nuclear facilities must be carried out to maintain know how. (author)

  12. Environmental monitoring of nuclear facilities

    International Nuclear Information System (INIS)

    Papadopoulos, D.; Winter, M.

    1982-01-01

    Environmental monitoring adds to the control of emissions of radioactive substances from nuclear facilities. The radioactive substances released with the exhaust air and the liquid effluent result in impact levels in the immediate vicinity, which must be ascertained by measurement. Impact control serves for the quantitative assessment of man-made radioactivity in different media of relevant pathways and for the direct assessment of the radiation exposure of the public living in the vicinity. In this way, the radiation exposure of the environment, which can be calculated if the emission data and the meteorological diffusion parameters are known, is controlled directly. (orig./RW)

  13. The nuclear power situation in Finland

    International Nuclear Information System (INIS)

    Miettinen, J.K.

    1976-01-01

    and's limited choice of energy sources makes nuclear power especially lly attractive and it is estimated that in 1985 14% of the energy consumed will be nuclear, which will then be the second most important source after oil (49%). Four power reactors, Loviisa 1 and 2 and TVO 1 and 2, are at present under construction. The first two are Russian PWRs, the latter two Asea-Atom BWRs. Loviisa 3 and 4 are planned but not yet ordered, and plans for a 1000 MWe plant to the West of Helsinki exist. The nuclear controversy in Finland has mainly been repetitions of the US and Swedish debates since 1970. However, local opposition to the project W. of Helsinki, based on the sociological effects of the inflow of Finnish speaking workers into a rural Swedish speaking district has become apparent. In the long term 13 major nuclear power plants are envisaged by the year 2000. Finland is party to the NPT and the IAEA safeguard system. (JIW)

  14. Current situation of nuclear engineering education

    International Nuclear Information System (INIS)

    Queral, C.; Minguez, E.

    2001-01-01

    The last few years have seen a growing concern with the decreasing number of suitably qualified engineers and university graduates in the field of Nuclear Technology. The gap between supply and demand is now a fact in several countries, and for the reason the international community has prepared several reports on the issue that are summarized here. (Author) 4 refs

  15. Russian Federal nuclear center facilities for nuclear spectroscopy investigations

    International Nuclear Information System (INIS)

    Ilkaev, R.I.; Punin, V.T.; Abramovich, S.N.

    2001-01-01

    Russian Federal Nuclear Center facilities for Spectroscopy investigation in the field of nuclear spectroscopy are described. Here are discussed basic properties of used radiation sources, facilities and technologies for target material production and manufacture of targets from rare, high-toxic or radioactive materials. Here are also reported basic features of complex detector systems and technologies for manufacture of scintillation detectors with special properties VNIIEF was founded as a weapons laboratory. The development of nuclear and thermonuclear bombs was followed by a wide complex of nuclear-physics investigations. Naturally, data on nuclear-physics properties of active and structure materials being part of nuclear weapons were of greatest interest.At the initial stage of work on the development of nuclear weapons the information on nuclear constants of materials including the most important neutron ones was rather scant. Data published in scientific literature had low exactness and were insecure. Results of measurements sometimes differed greatly by various groups of investigators. At the same time it was clear that, for example, a 1,5-times mistake in the fission cross-section could cause a several times mistake in the choice of uranium or plutonium mass, which is necessary for the bomb development. These circumstances determined importance of the nuclear-physics investigations. Demands on knowledge of process details occurring inside the nuclei conditioned by a problem of developing and improving of nuclear weapons and atomic power are rather limited. However, the further development of nuclear industry has proved a well-known point that this knowledge being accumulated forms a critical mass that leads to an explosive situation in the elaboration both of ideological and technological aspects of these problems. It is the tendency of inside development of nuclear science that has conditioned preparedness of knowledge about intranuclear processes for

  16. Nuclear fuel treatment facility for 'Mutsu'

    International Nuclear Information System (INIS)

    Kanazawa, Toshio; Fujimura, Kazuo; Horiguchi, Eiji; Kobayashi, Tetsuji; Tamekiyo, Yoshizou

    1989-01-01

    A new fixed mooring harbor in Sekinehama and surrounding land facilities to accommodate a test voyage for the nuclear-powered ship 'Mutsu' in 1990 were constructed by the Japan Atomic Energy Research Institute. Kobe Steel took part in the construction of the nuclear fuel treatment process in various facilities, beginning in October, 1988. This report describes the outline of the facility. (author)

  17. Trend of development of robots for nuclear facilities

    International Nuclear Information System (INIS)

    Maki, Hideo; Sasaki, Masayoshi

    1984-01-01

    Robot technology becomes more and more important in the field of atomic energy industries. Hitachi Ltd. has energetically engaged in the development of the robot technology for nuclear facilities, recognizing these situations. The course of the development of robot technology and the robots for nuclear facilities is described. As the practical examples of the robots for nuclear facilities, there have been automatic fuel exchangers, the remotely operated automatic exchangers for control rod driving mechanism, automatic and semi-automatic ultrasonic flaw detectors and so on. As the robots for nuclear facilities under development, control rod driving mechanism disassembling and cleaning system, the volume reduction device for spent fuel channel boxes and control rods and others are reported. (Kako, I.)

  18. Application of robotics in nuclear facilities

    International Nuclear Information System (INIS)

    Byrd, J.S.; Fisher, J.J.

    1986-01-01

    Industrial robots and other robotic systems have been successfully applied at the Savannah River nuclear site. These applications, new robotic systems presently under development, general techniques for the employment of robots in nuclear facilities, and future systems are discussed

  19. New situation and future of nuclear power plants

    International Nuclear Information System (INIS)

    Castejon, F.

    2008-01-01

    The situation of the nuclear power plants in the World is commented, making emphasis on the Spanish case. It is also pointed the difficulty of the nuclear industry to overcome the main caveats of this energy source: To guarantee the safety of the reactors, the management of the high radioactive level waste, and high investments necessary to build a nuclear power plant. These caveats have made that the public opinion is against the nuclear energy in Europe, and especially in Spain. It is difficult that a re launching of nuclear energy without the economical support of the governments, which guarantees the return of the investments. (Author) 7 refs

  20. Present situation and future prospects for French nuclear power plants

    International Nuclear Information System (INIS)

    Carle, R.

    1984-01-01

    The author depicts the present situation and future of the French nuclear power programme which has now become a major industrial reality after successful acceptance of a twofold challenge: the technical problem and that of training the personnel responsible for operating the power stations. The large number of nuclear plants now in operation and planned for the next few years makes electricity generated from nuclear power a ''new industrial reality'', which we must still learn to utilize to the best effect [fr

  1. Tritium transport around nuclear facilities

    International Nuclear Information System (INIS)

    Murphy, C.E. Jr.; Sweet, C.W.

    1981-01-01

    The transport and cycling of tritium around nuclear facilities is reviewed with special emphasis on studies at the Savannah River Laboratory, Aiken, South Carolina. These studies have shown that the rate of deposition from the atmosphere, the site of deposition, and the subsequent cycling are strongly influenced by the compound with which the tritium is associated. Tritiated hydrogen is largely deposited in the soil, while tritiated water is deposited in the greatest quantity in the vegetation. Tritiated hydrogen is converted in the soil to tritiated water that leaves the soil slowly, through drainage and transpiration. Tritiated water deposited directly to the vegetation leaves the vegetation more rapidly after exposure. Only a small part of the tritium entering the vegetation becomes bound in organic molecules. However, it appears tht the existence of soil organic compounds with tritium concentrations greater than the equilibrium concentration in the associated water can be explained by direct metabolism of tritiated hydrogen in vegetation

  2. Neutron skyshine from nuclear facilities

    International Nuclear Information System (INIS)

    Nakamura, Takashi; Hayashi, Katsumi.

    1984-01-01

    The advance in neutron skyshine research and the significance are first described. Then, skyshine calculation methods in 1980s particularly and the skyshine experiment in Japan with various nuclear facilities (reactors, D-T neutron sources, accelerators) are reviewed. In comparison with such experiment usable as bench mark, the skyshine calculation methods (Monte Carlo method, transport calculation method) are evaluated for their accuracy and merits and demerits. The values by Monte Carlo calculation were in agreement within about 30 % with the experimental values. Those by DOT 3.5 calculation were twice as large as the experimental values. Those by PALLAS calculation were in good agreement in dose with the experimental values, but the spectra were considerably different. The values by SKYSHINE-2 were in good agreement with the experimental values, but since the ground effect was ignored, the values may deviate from the experimental ones if it is taken into account. (Mori, K.)

  3. Complementary safety assessment assessment of nuclear facilities - Tricastin facility - AREVA

    International Nuclear Information System (INIS)

    2011-01-01

    This complementary safety assessment analyses the robustness of the Areva part of the Tricastin nuclear site to extreme situations such as those that led to the Fukushima accident. This study includes the following facilities: Areva NC Pierrelatte, EURODIF production, Comurhex Pierrelatte, Georges Besse II plant and Socatri. Robustness is the ability for the plant to withstand events beyond which the plant was designed. Robustness is linked to safety margins but also to the situations leading to a sudden deterioration of the accidental sequence. Moreover, safety is not only a matter of design or engineered systems but also a matter of organizing: task organization (including subcontracting) as well as the setting of emergency plans or the inventory of nuclear materials are taken into consideration in this assessment. This report is divided into 10 main chapters: 1) the feedback experience of the Fukushima accident; 2) description of the site and its surroundings; 3) featuring of the site's activities and installations; 4) accidental sequences; 5) protection from earthquakes; 6) protection from floods; 7) protection from other extreme natural disasters; 8) the loss of electrical power and of the heat sink; 9) the management of severe accidents; and 10) subcontracting policy. This analysis has identified 5 main measures to be taken to limit the risks linked to natural disasters: -) continuing the program for replacing the current conversion plant and the enrichment plant; -) renewing the storage of hydrofluoric acid at the de-fluorination workshop; -) assessing the seismic behaviour of some parts of the de-fluorination workshop and of the fluorine fabrication workshop; -) improving the availability of warning and information means in case of emergency; and -) improving the means to mitigate accidental gaseous releases. (A.C.)

  4. Database on radioecological situation in Semipalatinsk nuclear test site

    International Nuclear Information System (INIS)

    Turkebaev, T.Eh.; Kislitsin, S.B.; Lopuga, A.D.; Kuketaev, A.T.; Kikkarin, S.M.

    1999-01-01

    One of the main objectives of the National Nuclear Center of the Republic of Kazakstan is to define radioecological situation in details, conduct a continuous monitoring and eliminate consequences of nuclear explosions at Semipalatinsk nuclear test site. Investigations of Semipalatinsk nuclear test site area contamination by radioactive substances and vindication activity are the reasons for development of computer database on radioecological situation of the test site area, which will allow arranging and processing the available and entering information about the radioecological situation, assessing the effect of different testing factors on the environment and health of the Semipalatinsk nuclear test site area population.The described conception of database on radioecological situation of the Semipalatinsk nuclear test site area cannot be considered as the final one. As new information arrives, structure and content of the database is updated and optimized. New capabilities and structural elements may be provided if new aspects in Semipalatinsk nuclear test site area contamination study (air environment study, radionuclides migration) arise

  5. Nonreactor nuclear facilities: standards and criteria guide

    International Nuclear Information System (INIS)

    Brynda, W.J.; Junker, L.; Karol, R.C.; Lobner, P.R.; Goldman, L.A.

    1981-09-01

    This guide is a source document that identifies standards, codes, and guides that address the nuclear safety considerations pertinent to nuclear facilities as defined in DOE Order 5480.1, Chapter V, Safety of Nuclear Facilities. The guidance and criteria provided are directed toward areas of safety usually addressed in a Safety Analysis Report. The areas of safety include, but are not limited to, siting, principal design criteria and safety system design guidelines, radiation protection, accident analysis, and quality assurance. The guide is divided into two sections: general guidelines and appendices. Those guidelines that are broadly applicable to most nuclear facilities are presented in the general guidelines. These general guidelines may have limited applicability to subsurface facilities such as waste repositories. Guidelines specific to the various types or categories of nuclear facilities are presented in the appendices. These facility-specific appendices provide guidelines and identify standards and criteria that should be considered in addition to, or in lieu of, the general guidelines

  6. Nonreactor nuclear facilities: Standards and criteria guide

    International Nuclear Information System (INIS)

    Brynda, W.J.; Scarlett, C.H.; Tanguay, G.E.; Lobner, P.R.

    1986-09-01

    This guide is a source document that identifies standards, codes, and guides that address the nuclear safety considerations pertinent to nuclear facilities as defined in DOE 5480.1A, Chapter V, ''Safety of Nuclear Facilities.'' The guidance and criteria provided is directed toward areas of safety usually addressed in a Safety Analysis Report. The areas of safety include, but are not limited to, siting, principal design criteria and safety system design guidelines, radiation protection, accident analysis, conduct of operations, and quality assurance. The guide is divided into two sections: general guidelines and appendices. Those guidelines that are broadly applicable to most nuclear facilities are presented in the general guidelines. Guidelines specific to the various types or categories of nuclear facilities are presented in the appendices. These facility-specific appendices provide guidelines and identify standards and criteria that should be considered in addition to, or in lieu of, the general guidelines. 25 figs., 62 tabs

  7. Base isolation for nuclear power and nuclear material facilities

    International Nuclear Information System (INIS)

    Eidinger, J.M.; Kircher, C.A.; Vaidya, N.; Constantinou, M.; Kelly, J.M.; Seidensticker, R.; Tajirian, F.F.; Ovadia, D.

    1989-01-01

    This report serves to document the status of the practice for the use of base isolation systems in the design and construction of nuclear power and nuclear material facilities. The report first describes past and current (1989) applications of base isolation in nuclear facilities. The report then provides a brief discussion of non-nuclear applications. Finally, the report summarizes the status of known base-isolation codes and standards

  8. Standards for psychological assessment of nuclear facility personnel. Technical report

    International Nuclear Information System (INIS)

    Frank, F.D.; Lindley, B.S.; Cohen, R.A.

    1981-07-01

    The subject of this study was the development of standards for the assessment of emotional instability in applicants for nuclear facility positions. The investigation covered all positions associated with a nuclear facility. Conclusions reached in this investigation focused on the ingredients of an integrated selection system including the use of personality tests, situational simulations, and the clinical interview; the need for professional standards to ensure quality control; the need for a uniform selection system as organizations vary considerably in terms of instruments presently used; and the need for an on-the-job behavioral observation program

  9. Policy on the decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    1988-08-01

    This Regulatory Policy Statement describes the policy of the Atomic Energy Control Board (AECB) on the decommissioning of those facilities defined as nuclear facilities in the Atomic Energy Control (AEC) Regulations. It is intended as a formal statement, primarily for the information of licensees, or potential licensees, of the regulatory process and requirements generally applicable to the decommissioning of nuclear facilities licensed and regulated by the AECB pursuant to the authority of the AEC Act and Regulations

  10. Estimating Fire Risks at Industrial Nuclear Facilities

    International Nuclear Information System (INIS)

    Coutts, D.A.

    1999-01-01

    The Savannah River Site (SRS) has a wide variety of nuclear production facilities that include chemical processing facilities, machine shops, production reactors, and laboratories. Current safety documentation must be maintained for the nuclear facilities at SRS. Fire Risk Analyses (FRAs) are used to support the safety documentation basis. These FRAs present the frequency that specified radiological and chemical consequences will be exceeded. The consequence values are based on mechanistic models assuming specific fire protection features fail to function as designed

  11. Overview of nuclear data measurement facilities in OECD countries

    International Nuclear Information System (INIS)

    Bioux, P.; Rowlands, J.L.

    1996-06-01

    In 1992 EDF commissioned a review of activity in the fields of nuclear data for fission power technology applications in OECD countries. The review was carried out in cooperation with the consultants EUROGRAM. This paper presents a summary. The situation is of concern to the French nuclear industry because of the few measurement facilities which are now funded for work in the field and the reductions in the numbers of scientists expert in measurement and evaluation of nuclear data. There are requirements which justify work to improve knowledge of many items of nuclear data. To ensure maintenance of expertise the French Nuclear Industry has arranged for several young scientists to work with leading experts in the different fields. However, the problem of continued availability of facilities remains. (authors)

  12. Waste management considerations in nuclear facility decommissioning

    International Nuclear Information System (INIS)

    Elder, H.K.; Murphy, E.S.

    1981-01-01

    Decommissioning of nuclear facilities involves the management of significant quantities of radioactive waste. This paper summarizes information on volumes of waste requiring disposal and waste management costs developed in a series of decommissioning studies performed for the U.S. Nuclear Regulatory Commission by the Pacific Northwest Laboratory. These studies indicate that waste management is an important cost factor in the decommissioning of nuclear facilities. Alternatives for managing decommissioning wastes are defined and recommendations are made for improvements in waste management practices

  13. Inventory of stress situations in nuclear power plants

    International Nuclear Information System (INIS)

    Saint-Jean, T.

    1986-04-01

    Anxious to pursue an in-depth analysis of stress phenomena in nuclear power plants in order to offer utilities appropriate solutions, Electricite de France and the Commissariat a l'Energie Atomique have jointly asked the Laboratoire de Psychologie du Travail to prepare an inventory of stress situations in nuclear electricity-generating centers. This document describes the approach used, the main concepts which have served as guidelines, and the methods of interpreting the results obtained through observations and questionnaires

  14. Visitor centres at nuclear facility sites

    International Nuclear Information System (INIS)

    1993-01-01

    Communications strategies in the nuclear field are often based on the creation of visitor centres at nuclear facility sites. Today, the design, as well as the realization and management of such centres has become a specialized function, and its role is very complementary to the nuclear operator's. It also uses the latest technology in the field of audio-visual, experiment and interactivity. This publication contains the proceedings of an international seminar organized by the OECD Nuclear Energy Agency on the role of visitor centres at nuclear facility sites. It includes the main papers presented at this Seminar

  15. Study on HVAC system in nuclear facility

    International Nuclear Information System (INIS)

    Baeg, S. Y.; Song, W. S.; Oh, Y. O.; Ju, Y. S.; Hong, K. P.

    2003-01-01

    Heating, Ventilation and Air Conditioning (HVAC) system in nuclear facility should be equipped and constructed more stable and allowable than that in common facility. The purpose of HVAC system is the maintenance of optimum working environment, the protection of worker against a contaminated air and the prevention of atmospheric contamination due to an outward ventilation, etc.. The basic scheme of a safety operation of nuclear facility is to prevent the atmospheric contamination even in low level. The adaptability of HVAC system which is in operation. In this study, the design requirements of HVAC system in nuclear facility and the HVAC systems in foreign countries are reviewed, and the results can be utilized in the design of HVAC system in nuclear facility

  16. The situation of radioactive waste management in the fuel reprocessing facility (for fiscal 1979)

    International Nuclear Information System (INIS)

    1981-01-01

    In the fuel reprocessing facility of Power Reactor and Nuclear Fuel Development Corporation (PNC), the release of radioactive gaseous and liquid wastes was so controlled as not to exceed the set standards. Of the radioactive liquid wastes, concentrated wastes and sludge are stored in tanks. Radioactive solid wastes are suitably stored in containers. The situation of radioactive waste management in the fuel reprocessing facility in fiscal 1979 (from April, 1979, to March, 1980) is presented on the basis of the radiation control report made by PNC. The release of radioactive gaseous and liquid wastes was below the set standards. The following data are given in tables: the released quantity of radioactive gaseous and liquid wastes, the cumulative stored amount of radioactive liquid wastes, the produced quantity and cumulative stored amount of radioactive solid wastes; (for reference) the released quantity of radioactive gaseous and liquid wastes in fiscal 1977, 1978 and 1979. (J.P.N.)

  17. The situation of nuclear power in the world

    International Nuclear Information System (INIS)

    1995-03-01

    This report presents a world panorama of nuclear power for electricity generation purposes. The economic aspects, the fuel cycle market, the reactor technology development, as well as environmental aspects are presented. This report is updated annually and the present issue covers the situation up to December 1993. (F.E.). 196 refs, 23 figs, 28 tabs

  18. Nuclear physics accelerator facilities of the world

    International Nuclear Information System (INIS)

    1991-12-01

    this report is intended to provide a convenient summary of the world's major nuclear physics accelerator facility with emphasis on those facilities supported by the US Department of Energy (DOE). Previous editions of this report have contained only DOE facilities. However, as the extent of global collaborations in nuclear physics grows, gathering summary information on the world's nuclear physics accelerator facilities in one place is useful. Therefore, the present report adds facilities operated by the National Science Foundation (NSF) as well as the leading foreign facilities, with emphasis on foreign facilities that have significant outside user programs. The principal motivation for building and operating these facilities is, of course, basic research in nuclear physics. The scientific objectives for this research were recently reviewed by the DOE/NSF Nuclear Science Advisory Committee, who developed a long range plan, Nuclei, Nucleons, and Quarks -- Nuclear Science in the 1990's. Their report begins as follows: The central thrust of nuclear science is the study of strongly interacting matter and of the forces that govern its structure and dynamics; this agenda ranges from large- scale collective nuclear behavior through the motions of individual nucleons and mesons, atomic nuclei, to the underlying distribution of quarks and gluons. It extends to conditions at the extremes of temperature and density which are of significance to astrophysics and cosmology and are conducive to the creation of new forms of strongly interacting matter; and another important focus is on the study of the electroweak force, which plays an important role in nuclear stability, and on precision tests of fundamental interactions. The present report provides brief descriptions of the accelerator facilities available for carrying out this agenda and their research programs

  19. Saint-Laurent-des-Eaux nuclear facilities. 2009 annual report

    International Nuclear Information System (INIS)

    2010-01-01

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

  20. Recent situation of the establishment of nuclear fuel cycle

    International Nuclear Information System (INIS)

    Hoshiba, Shizuo

    1982-01-01

    In Japan, the development of nuclear power as principal petroleum substitute is actively pursued. Nuclear power generation now accounts for about 17 % of the total power generation in Japan. The business related to nuclear fuel cycle should be established by private enterprises. The basic policy in the establishment of nuclear fuel cycle is the stabilized supply of natural uranium, raise in domestic production of enriched uranium, dFomestic fuel reprocessing in principle, positive plutonium utilization, and so on. After explaining this basic policy, the present situation and problems in the establishment of nuclear fuel cycle are described: securing of uranium resources, securing of enriched uranium, reprocessing of used fuel, utilization of plutonium, management of radioactive wastes. (Mori, K.)

  1. The situation of energy and nuclear energy in Switzerland

    International Nuclear Information System (INIS)

    Truempy, E.

    1981-01-01

    The Swiss energy supply is one-sided and depends strongly on foreign countries. Therefore, the mineral oil share of about 70% and the import share of more than 80% should be decreased and substituted respectively. The electricity is one of the most important mineral oil alternatives. Today, this energy is produced at 30% in nuclear plants. For covering the moreover increasing demand of about 4%/year a 1000 MW nuclear power plant is under construction and two further plants are in advanced planning situation. The general conditions for the future extension of nuclear energy have been defined for 1979 in a supplement of the atomic law of 1959, approved by a plebiscite. Shortly before that event an initiative against nuclear energy was defeated. The statements are completed with some aspects of waste elimination, environment protection and economy of nuclear energy in Switzerland. (Auth.)

  2. Lifting devices in nuclear facilities

    International Nuclear Information System (INIS)

    The rule is valid for lifts, cranes, winches, rail travel trolleys, load lifting devices and fuel element changing devices for light-water reactors, insofar as these are used in plants to produce or to fission nuclear fuels or to process irradiated nuclear fuels or in the storage or other use of nuclear fuels. (LH) [de

  3. Potential Benefits to the Philippines of a Nuclear Facility

    International Nuclear Information System (INIS)

    Asuncion-Astronomo, A.; Romallosa, K.M.D.; Olivares, R.U.

    2015-01-01

    During the late 1950’s, the Philippines was one of the many countries which began the pursuit of the beneficial applications of atomic energy. With the commissioning of the first Philippine Research Reactor (PRR-1) which attained its first criticality in 1963, our country had the capability for radioisotope production, activation analysis of materials, irradiation studies and various opportunities for basic and applied nuclear science research. The Nuclear Power Plant (PNNP-1) in training plant operators and regulators for the first Philippine Nuclear Power Plant (PNPP-1) in Bataan, which was eventually mothballed in 1986. It is thus unfortunate that the only operating nuclear facility in the country, the PRR-1 encountered technical problems during an upgrade and was shut down in 1988. The problem was not resolved and eventually led to the decommissioning of the PRR-1 in 2005. Without an operating nuclear facility available in the country, the number of personnel knowledgeable and skilled in reactor and nuclear science and engineering has greatly declined and lagged behind our counterparts. This has been the situation for more than two decaded and can only be addressed if the country decides to put up a new nuclear facility. It is acknowledged that putting up a nuclear facility is a major undertaking which requires careful planning, preparation and investment. Thus, a decision by any country to embark on this poster, we will provide an overview of the many potential benefits as well as challenges of establishing a new research reactor and/or accelerator facility in the country. The global distribution, comparisons, capabilities and the different application of these facilities will presented as well.(author)

  4. Importance of tests in nuclear facilities

    International Nuclear Information System (INIS)

    Guillemard, B.

    1985-10-01

    In nuclear facilities, safety related systems and equipments are subject, along their whole service-life, to numerous tests. This paper analyses the role of tests in the successive stages of design, construction, exploitation of a nuclear facility. It examines several aspects of test quality control: definition of needs, test planning, intrinsic quality of each test, control of interfaces (test are both the end and the starting point of many actions concerned by quality) and the application [fr

  5. Methodology and technology of decommissioning nuclear facilities

    International Nuclear Information System (INIS)

    1986-01-01

    The decommissioning and decontamination of nuclear facilities is a topic of great interest to many Member States of the International Atomic Energy Agency (IAEA) because of the large number of older nuclear facilities which are or soon will be retired from service. In response to increased international interest in decommissioning and to the needs of Member States, the IAEA's activities in this area have increased during the past few years and will be enhanced considerably in the future. A long range programme using an integrated systems approach covering all the technical, regulatory and safety steps associated with the decommissioning of nuclear facilities is being developed. The database resulting from this work is required so that Member States can decommission their nuclear facilities in a safe time and cost effective manner and the IAEA can effectively respond to requests for assistance. The report is a review of the current state of the art of the methodology and technology of decommissioning nuclear facilities including remote systems technology. This is the first report in the IAEA's expanded programme and was of benefit in outlining future activities. Certain aspects of the work reviewed in this report, such as the recycling of radioactive materials from decommissioning, will be examined in depth in future reports. The information presented should be useful to those responsible for or interested in planning or implementing the decommissioning of nuclear facilities

  6. Present situation and proposal for nuclear medicine development

    International Nuclear Information System (INIS)

    Oliva Gonzalez, Juan P.

    2003-01-01

    In the present paper, the current situation of the Cuban nuclear medicine, after its introduction in the country in the 40s of the 20 th century and its expansion since 1962 and, particularly, from the installation of the first gamma camera in 1980, is analyzed. Nowadays, there is a total 14 Nuclear Medicine Departments or Services in our country within the National Oncology Networks and national Health System (SNS), which provide medical attention to the population depending on the nuclear equipment available A Program for the medical and technical personnel's training is proposed, as well as for gradual development of nuclear medicine department's (including the installation of gamma cameras, divided into two stages: 2003-2004 and 2005-2006). The prospective results of the proposed program are analyzed, as well as the impact on the populations health

  7. Auxiliary facilities on nuclear ship 'MUTSU'

    International Nuclear Information System (INIS)

    Tsujimura, Shotaro; Takigami, Yoshio.

    1989-01-01

    The nuclear ship 'MUTSU' has been moored at SEKINEHAMA, MUTU City in AOMORI Prefecture and several tests and works are being carried out on the ship. The construction of the auxiliary facilities for these works on the ship was completed in safety in August 1988. After that the facilities have fulfilled their function. The outlines of design, fabrication and construction of the facilities are described in this paper. (author)

  8. Knowledge Management in Nuclear Facilities

    International Nuclear Information System (INIS)

    Strba, M.

    2007-01-01

    Rebirth of and return to nuclear energy conditioned by an increasing worldwide energy consumption and decreasing fuel sources such as crude oil, gas and oil has aroused the question how to maintain nuclear knowledge obtained by previous generations and at the same time to deliver it to their successors in as complete form as possible. (author)

  9. Nuclear astrophysics experiments with Pohang neutron facility

    International Nuclear Information System (INIS)

    Kim, Yeong Duk; Yoo, Gwang Ho

    1998-01-01

    Nuclear astrophysics experiments for fundamental understanding of Big Bang nucleosynthesis was performed at Pohang Neutron Facility. Laboratory experiments, inhomogeneous Big Bang nucleosynthesis and S-process were used for nucleosynthesis. For future study, more study on S-process for the desired data and nuclear network calculation are necessary

  10. Quality management in nuclear facilities decommissioning

    International Nuclear Information System (INIS)

    Garonis, Omar H.

    2002-01-01

    Internationally, the decommissioning organizations of nuclear facilities carry out the decommissioning according to the safety requirements established for the regulatory bodies. Some of them perform their activities in compliance with a quality assurance system. This work establishes standardization through a Specifications Requirement Document, for the management system of the nuclear facilities decommissioning organizations. It integrates with aspects of the quality, environmental, occupational safety and health management systems, and also makes these aspects compatible with all the requirements of the nuclear industry recommended for the International Atomic Energy Agency (IAEA). (author)

  11. Radioiodine removal in nuclear facilities

    International Nuclear Information System (INIS)

    1980-01-01

    Technical means are reviewed available for the retention of radioiodine in nuclear power plants and fuel reprocessing plants, its immobilization, storage, and disposal. The removal of iodine species from gaseous effluents of nuclear power plants using impregnated activated charcoal is dealt with. Various scrubbing techniques for trapping iodine from the head-end and dissolver off-gases are discussed as well as solid adsorbents for iodine which may be used to clean up other gaseous streams. Current practices and activities for radioiodine treatment and management in Belgian, Dutch, Swedish, USSR and UK nuclear installations are presented

  12. Significant incidents in nuclear fuel cycle facilities

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-03-01

    In contrast to nuclear power plants, events in nuclear fuel cycle facilities are not well documented. The INES database covers all the nuclear fuel cycle facilities; however, it was developed in the early 1990s and does not contain information on events prior to that. The purpose of the present report is to collect significant events and analyze them in order to give a safety related overview of nuclear fuel cycle facilities. Significant incidents were selected using the following criteria: release of radioactive material or exposure to radiation; degradation of items important to safety; and deficiencies in design, quality assurance, etc. which include criticality incidents, fire, explosion, radioactive release and contamination. This report includes an explanation, where possible, of root causes, lessons learned and action taken. 4 refs, 4 tabs.

  13. Integrated engineering system for nuclear facilities building

    International Nuclear Information System (INIS)

    Tomura, H.; Miyamoto, A.; Futami, F.; Yasuda, S.; Ohtomo, T.

    1995-01-01

    In the construction of buildings for nuclear facilities in Japan, construction companies are generally in charge of the building engineering work, coordinating with plant engineering. An integrated system for buildings (PROMOTE: PROductive MOdeling system for Total nuclear Engineering) described here is a building engineering system including the entire life cycle of buildings for nuclear facilities. A Three-dimensional (3D) building model (PRO-model) is to be in the core of the system (PROMOTE). Data sharing in the PROMOTE is also done with plant engineering systems. By providing these basic technical foundations, PROMOTE is oriented toward offering rational, highquality engineering for the projects. The aim of the system is to provide a technical foundation in building engineering. This paper discusses the characteristics of buildings for nuclear facilities and the outline of the PROMOTE. (author)

  14. Significant incidents in nuclear fuel cycle facilities

    International Nuclear Information System (INIS)

    1996-03-01

    In contrast to nuclear power plants, events in nuclear fuel cycle facilities are not well documented. The INES database covers all the nuclear fuel cycle facilities; however, it was developed in the early 1990s and does not contain information on events prior to that. The purpose of the present report is to collect significant events and analyze them in order to give a safety related overview of nuclear fuel cycle facilities. Significant incidents were selected using the following criteria: release of radioactive material or exposure to radiation; degradation of items important to safety; and deficiencies in design, quality assurance, etc. which include criticality incidents, fire, explosion, radioactive release and contamination. This report includes an explanation, where possible, of root causes, lessons learned and action taken. 4 refs, 4 tabs

  15. Childhood leukaemia around nuclear facilities

    Energy Technology Data Exchange (ETDEWEB)

    Wojcik, Andrzej (Centre for Radiation Protection Research, GMT Dept., Stockholm Univ., Stockholm (Sweden)); Feychting, Maria (Inst. of Environmental Medicine, Karolinska Inst., Stockholm (Sweden))

    2010-06-15

    In December 2007 the German Federal Office for Radiation Protection (BfS) published a report on the incidence of childhood cancers among children living in the vicinity of 16 German nuclear power plants. The results show a significantly enhanced risk of leukaemia in children aged below 5 years, who live within 5 km from a nuclear power plant. The study is known as KiKK (Epidemiologische Studie zu Kinderkrebs in der Umgebung von Kernkraftwerken) and stirred considerable concern about the safety of nuclear installations. In this review we summarise the present state-of-the art regarding childhood leukaemia in the vicinity of nuclear installations and present the main results of the KiKK study with a critical evaluation

  16. Childhood leukaemia around nuclear facilities

    International Nuclear Information System (INIS)

    Wojcik, Andrzej; Feychting, Maria

    2010-06-01

    In December 2007 the German Federal Office for Radiation Protection (BfS) published a report on the incidence of childhood cancers among children living in the vicinity of 16 German nuclear power plants. The results show a significantly enhanced risk of leukaemia in children aged below 5 years, who live within 5 km from a nuclear power plant. The study is known as KiKK (Epidemiologische Studie zu Kinderkrebs in der Umgebung von Kernkraftwerken) and stirred considerable concern about the safety of nuclear installations. In this review we summarise the present state-of-the art regarding childhood leukaemia in the vicinity of nuclear installations and present the main results of the KiKK study with a critical evaluation

  17. Technical Cybersecurity Controls for Nuclear Facilities

    International Nuclear Information System (INIS)

    Oh, Jinseok; Ryou, Jaecheol; Kim, Youngmi; Jeong, Choonghei

    2014-01-01

    To strengthen cybersecurity for nuclear facilities, many countries take a regulatory approach. For example, US Government issued several regulations . Title 10, of the Code of Federal Regulations, Section 73.54, 'Protection of Digital Computer and Communication Systems and Networks (10 CFR 73.54) for cybersecurity requirements and Regulatory Guide 5.71 (RG. 5.71) for cybersecurity guidance and so on. In the case of Korea, Korean Government issued '8.22 Cybersecurity of I and C systems (KINS/RG-NO8.22). In particular, Reg. 5.71 provides a list of security controls to address the potential cyber risks to a nuclear facilities. Implementing and adopting security controls, we can improve the level of cybersecurity for nuclear facilities. RG 5.71 follows the recommendation of NIST SP 800-53. NIST standard provides security controls for IT systems. And NRC staff tailored the controls in NIST standards to unique environments of nuclear facilities. In this paper, we are going to analysis and compare NRC RG 5.71 and NIST SP800-53, in particular, for technical security controls. If RG 5.71 omits the specific security control that is included in SP800-53, we would review that omitting is adequate or not. If RG 5.71 includes the specific security control that is not included in SP800-53, we would also review the rationale. And we are going to some security controls to strengthen cybersecurity of nuclear facilities. In this paper, we compared and analyzed of two regulation in technical security controls. RG 5.71 that is based on NIST standard provides well-understood security controls for nuclear facility. But some omitting from NIST standard can threaten security state of nuclear facility

  18. Technical Cybersecurity Controls for Nuclear Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Oh, Jinseok; Ryou, Jaecheol [Chungnam National Univ., Daejeon (Korea, Republic of); Kim, Youngmi; Jeong, Choonghei [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

    2014-05-15

    To strengthen cybersecurity for nuclear facilities, many countries take a regulatory approach. For example, US Government issued several regulations . Title 10, of the Code of Federal Regulations, Section 73.54, 'Protection of Digital Computer and Communication Systems and Networks (10 CFR 73.54) for cybersecurity requirements and Regulatory Guide 5.71 (RG. 5.71) for cybersecurity guidance and so on. In the case of Korea, Korean Government issued '8.22 Cybersecurity of I and C systems (KINS/RG-NO8.22). In particular, Reg. 5.71 provides a list of security controls to address the potential cyber risks to a nuclear facilities. Implementing and adopting security controls, we can improve the level of cybersecurity for nuclear facilities. RG 5.71 follows the recommendation of NIST SP 800-53. NIST standard provides security controls for IT systems. And NRC staff tailored the controls in NIST standards to unique environments of nuclear facilities. In this paper, we are going to analysis and compare NRC RG 5.71 and NIST SP800-53, in particular, for technical security controls. If RG 5.71 omits the specific security control that is included in SP800-53, we would review that omitting is adequate or not. If RG 5.71 includes the specific security control that is not included in SP800-53, we would also review the rationale. And we are going to some security controls to strengthen cybersecurity of nuclear facilities. In this paper, we compared and analyzed of two regulation in technical security controls. RG 5.71 that is based on NIST standard provides well-understood security controls for nuclear facility. But some omitting from NIST standard can threaten security state of nuclear facility.

  19. Building a medical system for nuclear facilities

    International Nuclear Information System (INIS)

    Maeda, Mitsuya

    2016-01-01

    To build a medical system for nuclear facilities, I explained what kinds of actions were performed with the TEPCO Fukushima Daiichi Nuclear Power Plant Accident and what kinds of actions are going to be performed in the future. We examined the health and medical care of the emergency workers in nuclear facilities including TEPCO Fukushima Daiichi Nuclear Power Plant from 2014 to 2015 in the Ministry of Health, Labour and Welfare (MHLW). We carried out a detailed hearing from stakeholders of electric companies and medical institutions about the medical system in nuclear facilities carrying out urgent activities. It has been said that the electric company is responsible to maintain the medical system for affected workers in nuclear facilities. However, TEPCO could not find the medical staff, such as doctors, by their own effort at the TEPCO Fukushima Daiichi Nuclear Power Plant Accident. The network of doctors familiar with emergency medical care support dispatched the medical staff after July of 2011. The stakeholders indicated that the following six tasks must be resolved: (1) the fact that no electric company performs the action of bringing up medical staff who can be dispatched into nuclear facilities in emergencies in 2015; (2) bringing up personnel in charge of radiation management and logistics other than the medical staff, such as doctors; (3) cooperation with the community medicine system given the light and shade by nuclear facilities; (4) performing training for the many concurrent wounded based on the scenario of a severe accident; (5) indicating both the condition of the contract and the guarantee of status that is appropriate for dispatched medical staffs; and (6) clarifying the organization of the network of stakeholders. The stakeholders showed the future directionality as follows: (1) To recruit the medical staff expected to be dispatched into nuclear facilities, (2) to carry out the discussion and conveyance training to strengthen cooperation with

  20. Methodology for analyzing risk at nuclear facilities

    International Nuclear Information System (INIS)

    Yoo, Hosik; Lee, Nayoung; Ham, Taekyu; Seo, Janghoon

    2015-01-01

    Highlights: • A new methodology for evaluating the risk at nuclear facilities was developed. • Five measures reflecting all factors that should be concerned to assess risk were developed. • The attributes on NMAC and nuclear security culture are included as attributes for analyzing. • The newly developed methodology can be used to evaluate risk of both existing facility and future nuclear system. - Abstract: A methodology for evaluating risks at nuclear facilities is developed in this work. A series of measures is drawn from the analysis of factors that determine risks. Five measures are created to evaluate risks at nuclear facilities. These include the legal and institutional framework, material control, physical protection system effectiveness, human resources, and consequences. Evaluation attributes are developed for each measure and specific values are given in order to calculate the risk value quantitatively. Questionnaires are drawn up on whether or not a state has properly established a legal and regulatory framework (based on international standards). These questionnaires can be a useful measure for comparing the status of the physical protection regime between two countries. Analyzing an insider threat is not an easy task and no methodology has been developed for this purpose. In this study, attributes that could quantitatively evaluate an insider threat, in the case of an unauthorized removal of nuclear materials, are developed by adopting the Nuclear Material Accounting & Control (NMAC) system. The effectiveness of a physical protection system, P(E), could be analyzed by calculating the probability of interruption, P(I), and the probability of neutralization, P(N). In this study, the Tool for Evaluating Security System (TESS) code developed by KINAC is used to calculate P(I) and P(N). Consequence is an important measure used to analyze risks at nuclear facilities. This measure comprises radiological, economic, and social damage. Social and

  1. Measuring strategy in case of a nuclear emergency situation

    International Nuclear Information System (INIS)

    Bieringer, J.; Bieringer, P.

    2003-01-01

    In the case of a nuclear emergency situation there are other demands -compared to normal operation - of kind, availability in time and volume of information providing the description of the radiological situation and allowing the recommendation of countermeasures in time. These requirements depend on the different phases of the emergency situation and the intense operation, respectively. In the first phase e. g. even before the radioactive release starts, information from the nuclear power plant is needed besides weather forecasts, trajectories and prognoses about the expected external dose and the contamination. In addition fast available results from dose rate measurements and information about the radionuclide spectrum are necessary. The aim is to get an overview about the actual radiological situation and its possible development in time in order to introduce countermeasures, where necessary. In the second phase, short time after the distribution of the radioactive substances has stopped, measurements according to Paragraph 3 of the precautionary radiation protection law (StrVG) are of primary interest, especially the determination of the contamination of human food and animal feed. In this phase after the end of the deposition process, where the spectrum of the deposited radionuclides is known, the behaviour of the external dose as a function of time can be well predicted. In the third phase, this means weeks after the emergency situation, the measurements are used to observe the activity concentrations in different media on a long time scale. In the beginning (phase one and two) the availability of information in time is of great importance. With increasing time this shifts more and more to the diversity of the analysed media. (orig.)

  2. Computer Security at Nuclear Facilities. Reference Manual (Arabic Edition)

    International Nuclear Information System (INIS)

    2011-01-01

    The possibility that nuclear or other radioactive material could be used for malicious purposes cannot be ruled out in the current global situation. States have responded to this risk by engaging in a collective commitment to strengthen the protection and control of such material and to respond effectively to nuclear security events. States have agreed to strengthen existing instruments and have established new international legal instruments to enhance nuclear security worldwide. Nuclear security is fundamental in the management of nuclear technologies and in applications where nuclear or other radioactive material is used or transported. Through its Nuclear Security Programme, the IAEA supports States to establish, maintain and sustain an effective nuclear security regime. The IAEA has adopted a comprehensive approach to nuclear security. This recognizes that an effective national nuclear security regime builds on: the implementation of relevant international legal instruments; information protection; physical protection; material accounting and control; detection of and response to trafficking in such material; national response plans; and contingency measures. With its Nuclear Security Series, the IAEA aims to assist States in implementing and sustaining such a regime in a coherent and integrated manner. The IAEA Nuclear Security Series comprises Nuclear Security Fundamentals, which include objectives and essential elements of a State's nuclear security regime; Recommendations; Implementing Guides; and Technical Guidance. Each State carries the full responsibility for nuclear security, specifically: to provide for the security of nuclear and other radioactive material and associated facilities and activities; to ensure the security of such material in use, storage or in transport; to combat illicit trafficking and the inadvertent movement of such material; and to be prepared to respond to a nuclear security event. This publication is in the Technical Guidance

  3. Computer Security at Nuclear Facilities. Reference Manual (Russian Edition)

    International Nuclear Information System (INIS)

    2012-01-01

    The possibility that nuclear or other radioactive material could be used for malicious purposes cannot be ruled out in the current global situation. States have responded to this risk by engaging in a collective commitment to strengthen the protection and control of such material and to respond effectively to nuclear security events. States have agreed to strengthen existing instruments and have established new international legal instruments to enhance nuclear security worldwide. Nuclear security is fundamental in the management of nuclear technologies and in applications where nuclear or other radioactive material is used or transported. Through its Nuclear Security Programme, the IAEA supports States to establish, maintain and sustain an effective nuclear security regime. The IAEA has adopted a comprehensive approach to nuclear security. This recognizes that an effective national nuclear security regime builds on: the implementation of relevant international legal instruments; information protection; physical protection; material accounting and control; detection of and response to trafficking in such material; national response plans; and contingency measures. With its Nuclear Security Series, the IAEA aims to assist States in implementing and sustaining such a regime in a coherent and integrated manner. The IAEA Nuclear Security Series comprises Nuclear Security Fundamentals, which include objectives and essential elements of a State's nuclear security regime; Recommendations; Implementing Guides; and Technical Guidance. Each State carries the full responsibility for nuclear security, specifically: to provide for the security of nuclear and other radioactive material and associated facilities and activities; to ensure the security of such material in use, storage or in transport; to combat illicit trafficking and the inadvertent movement of such material; and to be prepared to respond to a nuclear security event. This publication is in the Technical Guidance

  4. Computer Security at Nuclear Facilities. Reference Manual (Chinese Edition)

    International Nuclear Information System (INIS)

    2012-01-01

    The possibility that nuclear or other radioactive material could be used for malicious purposes cannot be ruled out in the current global situation. States have responded to this risk by engaging in a collective commitment to strengthen the protection and control of such material and to respond effectively to nuclear security events. States have agreed to strengthen existing instruments and have established new international legal instruments to enhance nuclear security worldwide. Nuclear security is fundamental in the management of nuclear technologies and in applications where nuclear or other radioactive material is used or transported. Through its Nuclear Security Programme, the IAEA supports States to establish, maintain and sustain an effective nuclear security regime. The IAEA has adopted a comprehensive approach to nuclear security. This recognizes that an effective national nuclear security regime builds on: the implementation of relevant international legal instruments; information protection; physical protection; material accounting and control; detection of and response to trafficking in such material; national response plans; and contingency measures. With its Nuclear Security Series, the IAEA aims to assist States in implementing and sustaining such a regime in a coherent and integrated manner. The IAEA Nuclear Security Series comprises Nuclear Security Fundamentals, which include objectives and essential elements of a State's nuclear security regime; Recommendations; Implementing Guides; and Technical Guidance. Each State carries the full responsibility for nuclear security, specifically: to provide for the security of nuclear and other radioactive material and associated facilities and activities; to ensure the security of such material in use, storage or in transport; to combat illicit trafficking and the inadvertent movement of such material; and to be prepared to respond to a nuclear security event. This publication is in the Technical Guidance

  5. IAEA calls for urgent action on nuclear situation in Iraq

    International Nuclear Information System (INIS)

    2003-01-01

    Full text: The Director General of the International Atomic Energy Agency (IAEA), Dr. Mohamed ElBaradei, called on the United States and other Coalition authorities to allow IAEA experts to return to Iraq to address a possible radiological emergency there. 'I am deeply concerned by the almost daily reports of looting and destruction at nuclear sites and about the potential radiological safety and security implications of nuclear and radiological materials that may no longer be under control.' Such reports have described among other things yellow cake emptied on the ground from containers then taken for domestic use, and radioactive sources being stolen and removed from their shielding. 'We have a moral responsibility to establish the facts without delay and take urgent remedial action,' said Dr. ElBaradei. As hostilities in Iraq were coming to an end, Dr. ElBaradei wrote on 10 April to the US government bringing its attention to the need to secure the nuclear material stored at Tuwaitha - Iraq's nuclear research centre - and under IAEA seal since 1991. The IAEA also provided the United States with information about the nuclear material, radioactive sources, and nuclear waste in Iraq. The IAEA received oral assurances that physical protection of the site was in place; but following reports of looting there and at other sites, Dr. ElBaradei wrote again on 29 April, emphasizing the responsibility of the Coalition forces to maintain appropriate protection over the materials in question. This includes natural and low-enriched uranium, radioactive sources such as Cobalt 60 and Caesium 137, and nuclear waste. Dr. ElBaradei regrets that the IAEA has to date not received a response. He again urged that the Agency be allowed to send a safety and security team to Iraq so that a potentially serious humanitarian situation can be addressed without further delay. The IAEA has experienced international teams of radiation safety, nuclear security and emergency response specialists

  6. Nuclear material inventory estimation in a nuclear fuel reprocessing facility

    International Nuclear Information System (INIS)

    Bennett, J.E.; Beyerlein, A.L.

    1981-01-01

    A new approach in the application of modern system identification and estimation techniques is proposed to help nuclear reprocessing facilities meet the nuclear accountability requirement proposed by the International Atomic Energy Agency. The proposed identification and estimation method considers the material inventory in a portion of the chemical separations area of a reprocessing facility. The method addresses the nonlinear aspects of the problem, the time delay through the separation facility, and the lack of measurement access. The method utilizes only input-output measured data and knowledge of the uncertainties associated with the process and measured data. 14 refs

  7. Operational status of nuclear facilities in Japan. 2008 edition

    International Nuclear Information System (INIS)

    2008-01-01

    This document is a summary of the outline of the safety regulation administration of nuclear facilities as well as various data on the commercial nuclear power reactor facilities, research and development nuclear power reactor facilities, fabrication facilities, reprocessing facilities, and disposal facilities in fiscal year 2007 (from April 2007 to March 2008). I sincerely hope this document is used widely by many people engaged in work related to ensuring nuclear safety. (J.P.N.)

  8. Operational status of nuclear facilities in Japan. 2010 edition

    International Nuclear Information System (INIS)

    2010-01-01

    This document is a summary of the outline of the safety regulation administration of nuclear facilities as well as various data on the commercial nuclear power reactor facilities, research and development nuclear power reactor facilities, fabrication facilities, reprocessing facilities, and disposal facilities in fiscal year 2009 (from April 2009 to March 2010). We sincerely hope this document is used widely by many people engaged in work related to ensuring nuclear safety. (author)

  9. Over view of nuclear fuel cycle examination facility at KAERI

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Key-Soon; Kim, Eun-Ga; Joe, Kih-Soo; Kim, Kil-Jeong; Kim, Ki-Hong; Min, Duk-Ki [Korea Atomic Energy Research Institute, Taejon (Korea)

    1999-09-01

    Nuclear fuel cycle examination facilities at the Korea Atomic Energy Research Institute (KAERI) consist of two post-irradiation examination facilities (IMEF and PIEF), one chemistry research facility (CRF), one radiowaste treatment facility (RWTF) and one radioactive waste form examination facility (RWEF). This paper presents the outline of the nuclear fuel cycle examination facilities in KAERI. (author)

  10. On the present situation and future role of nuclear power

    International Nuclear Information System (INIS)

    1990-05-01

    The engaged public debate about the need for, and responsibility of, the continued use of nuclear power goes on unabated between the political parties and other groups of social relevance in the Federal Republic of Germany. And yet, some tentative changes seem to appear in the spectrum of opinions. In this situation, the German public utility companies operating nuclear power plants felt it necessary to express once more in a position paper their attitude with respect to nuclear power for the benefit of those bearing political responsibility at Federal and State Government level and the political parties. Their statements are guided by the responsibility the public utilities have for a reliable, sufficient, environmentally clean, and economic provision of electricity. They are convinced that nuclear power should remain a major constituent part of a comprehensive supply concept also in the future. This supply concept, which is based on the efficient use of power, relies on nuclear energy, run-of-river power, and lignite for the base load and on domestic hard coal for the medium load range; renewable energy sources are included. It underscores the social responsibility of the public utilities in ensuring electricity supply in a way which helps to conserve resources and is compatible with the environment. (orig.) [de

  11. Environmental monitoring around the Swedish Nuclear Facilities

    International Nuclear Information System (INIS)

    Bondesson, A.; Luening, M.; Wallberg, L.; Wijk, H.

    1999-01-01

    The environmental monitoring programme for the nuclear facilities has shown that the radioactive discharges increase the concentrations of some radionuclides in the local marine environment around the Swedish nuclear facilities. Samples from the terrestrial environment rarely show increased radionuclide concentrations. From a radiological point of view the most important nuclide in the environmental samples usually is CS-137. However, the largest part of the present concentrations of Cs-137 in the Swedish environment originate from the Chernobyl accident. The concentrations of radionuclides that can be found in biota around the nuclear facilities are much lower than the concentration levels that are known to give acute damage to organisms. The total radiation doses from the discharges of radionuclides are small. (au)

  12. Identification of Vital Areas at Nuclear Facilities. Technical Guidance

    International Nuclear Information System (INIS)

    2012-01-01

    The possibility that nuclear or other radioactive material could be used for malicious purposes cannot be ruled out in the current global situation. States have responded to this risk by engaging in a collective commitment to strengthen the protection and control of such material and to effectively respond to nuclear security events. States have agreed to strengthen existing and established new international legal instruments to enhance nuclear security around the world. Nuclear security is fundamental in the management of nuclear technologies and in applications where nuclear or other radioactive material is used or transported. Through its nuclear security programme, the IAEA supports States to establish, maintain and sustain an effective nuclear security regime. The IAEA has adopted a comprehensive approach to nuclear security. This recognizes that an effective national nuclear security regime builds on: the implementation of relevant international legal instruments; information protection; physical protection; material accounting and control; detection of and response to trafficking in such material; national response plans; and contingency measures. With its nuclear security series, the IAEA aims to assist States to implement and sustain such a regime in a coherent and integrated manner. The IAEA Nuclear Security Series comprises: Nuclear Security Fundamentals, which include objectives and essential elements of a State?s nuclear security regime; Recommendations; Implementing Guides; and Technical Guidance publications. Each State carries the full responsibility for nuclear security, i.e. to provide for the security of nuclear and other radioactive material and associated facilities and activities; to ensure the security of such material in use, storage or in transport; and to combat illicit trafficking and the inadvertent movement of such material. It should also be prepared to respond to a nuclear security event. The IAEA recommendations for the protection of

  13. Institutionalizing Safeguards By Design for Nuclear Facilities

    International Nuclear Information System (INIS)

    Morgan, James B.; Kovacic, Donald N.; Whitaker, J. Michael

    2008-01-01

    Safeguards for nuclear facilities can be significantly improved by developing and implementing methodologies for integrating proliferation resistance into the design of new facilities. This paper proposes a method to systematically analyze a facility's processes, systems, equipment, structures and management controls to ensure that all relevant proliferation scenarios that could potentially result in unacceptable consequences have been identified, evaluated and mitigated. This approach could be institutionalized into a country's regulatory structure similar to the way facilities are licensed to operate safely and are monitored through inspections and incident reporting to ensure compliance with domestic and international safeguards. Furthermore, taking credit for existing systems and equipment that have been analyzed and approved to assure a facility's reliable and safe operations will reduce the overall cost of implementing intrinsic and extrinsic proliferation-resistant features. The ultimate goal is to integrate safety, reliability, security and safeguards operations into the design of new facilities to effectively and efficiently prevent diversion, theft and misuse of nuclear material and sensitive technologies at both the facility and state level. To facilitate this approach at the facility level, this paper discusses an integrated proliferation resistance analysis (IPRA) process. If effectively implemented, this integrated approach will also facilitate the application of International Atomic Energy Agency (IAEA) safeguards

  14. AECL's strategy for decommissioning Canadian nuclear facilities

    International Nuclear Information System (INIS)

    Joubert, W.M.; Pare, F.E.; Pratapagiri, G.

    1992-01-01

    The Canadian policy on decommissioning of nuclear facilities as defined in the Atomic Energy Control Act and Regulations is administered by the Atomic Energy Control Board (AECB), a Federal Government agency. It requires that these facilities be decommissioned according to approved plans which are to be developed by the owner of the nuclear facility during its early stages of design and to be refined during its operating life. In this regulatory environment, Atomic Energy of Canada (AECL) has developed a decommissioning strategy for power stations which consists of three distinctive phases. After presenting AECL's decommissioning philosophy, its foundations are explained and it is described how it has and soon will be applied to various facilities. A brief summary is provided of the experience gained up to date on the implementation of this strategy. (author) 3 figs.; 1 tab

  15. Management of the high-level nuclear power facilities

    International Nuclear Information System (INIS)

    Preda, Marin

    2003-05-01

    This thesis approaches current issues in the management of the high power nuclear facilities and as such it appears to be important particularly for nuclear power plant operation topics. Of special interest are the failure events entailing possible catastrophic situations. The contents is structured onto ten chapters. The first chapter describes the operation regimes of the nuclear high power facilities. Highlighted here are the thesis scope and the original features of the work. The second chapter deals with operational policies developed in order to ensure the preventive maintenance of the nuclear installations. Also managing structures are described devoted to practical warranting the equipment safety function of non-classical power stations. In the third chapter cases of nuclear accidents are analyzed especially stressing the probabilistic risk and the operation regimes having in view the elimination of catastrophic events. In the fourth and fifth chapters the control of nuclear radiation emission is treated focusing the quality issue of nuclear installations required to avoid hazardous effects at level of nuclear reactor operation stage. At the same time set of operational measures is given here for preventing risks, catastrophes and chaotic situations. The chapter five presents both theoretical and practical approaches of the nuclear reactor core management concerning particularly the fuel testing, the water primary system and the quality of the involved equipment. In the sixth and seventh chapters issues of risk-quality correlations are approached as well as the structure of expert systems for monitoring the operational regimes of nuclear facilities. The efficiency of the power systems with nuclear injection is discussed and some original ideas developed in this work are evidenced in the eighth and ninth chapters. Presented are here both the operational principles and models of raising the efficiency of the interconnected nuclear stations and prices' policy

  16. Conducting Computer Security Assessments at Nuclear Facilities

    International Nuclear Information System (INIS)

    2016-06-01

    Computer security is increasingly recognized as a key component in nuclear security. As technology advances, it is anticipated that computer and computing systems will be used to an even greater degree in all aspects of plant operations including safety and security systems. A rigorous and comprehensive assessment process can assist in strengthening the effectiveness of the computer security programme. This publication outlines a methodology for conducting computer security assessments at nuclear facilities. The methodology can likewise be easily adapted to provide assessments at facilities with other radioactive materials

  17. Quality Assurance for Operation of Nuclear Facilities

    International Nuclear Information System (INIS)

    Park, C. G.; Kwon, H. I.; Kim, K. H.; Oh, Y. W.; Lee, Y. G.; Ha, J. H.; Lim, N. J.

    2008-12-01

    This report describes QA activities performed within 'Quality Assurance for Nuclear facility project' and results thereof. Efforts were made to maintain and improve quality system of nuclear facilities. Varification activities whether quality system was implemented in compliance with requirements. QA department assisted KOLAS accredited testing and calibration laboratories, ISO 9001 quality system, establishment of QA programs for R and D, and carried out reviews and surveys for development of quality assurance technologies. Major items of this report are as follows : - Development and Improvement of QA Programs - QA Activities - Assessment of Effectiveness and Adequacy for QA Programs

  18. Emergency planning and preparedness for nuclear facilities

    International Nuclear Information System (INIS)

    Koelzer, W.

    1988-01-01

    Nuclear installations are designed, constructed and operated in such a way that the probability for an incident or accident is very low and the probability for a severe accident with catastrophic consequences is extremely small. These accidents represent the residual risk of the nuclear installation, and this residual risk can be decreased on one hand by a better design, construction and operation and on the other hand by planning and taking emergency measures inside the facility and in the environment of the facility. By way of introduction and definition it may be indicated to define some terms pertaining to the subject in order to make for more uniform understanding. (orig./DG)

  19. Management of agricultural aspects in nuclear and/or radiological emergency situations

    International Nuclear Information System (INIS)

    Griperay, Gerard

    1997-01-01

    In revealing the agricultural aspects of the nuclear and/or radiological emergency situations the paper stresses upon the shocking role which the Chernobyl nuclear accident had on the agricultural management in France. Merely, the misunderstand, unawareness and lack of information relative to production as well as contamination conditions led to damages of FF 150 millions to the detriment of French farmers. Reflexions upon and analysis of this case has led to several conclusions concerning the role of information, the situation of international standards, and the lack of knowledge in important practical issues related to radioisotope migration in plants and agricultural products. Among the future lines of action in this field there are discussed the issues of indemnity, post-accident planning, drilling and information. In conclusion the following points are highlighted: 1. Redefinition of the EU standards; 2. Updating the situation of food and agricultural production units located around basic nuclear facilities in order to dispose of the necessary statistics to make decisions in emergency situations; 3. In absence of a post-accident plan, a scheme of action should be elaborated able to be rapidly implemented by public authorities in order to protect the consumer and restrict the supply to local market and exportation only to warranted agricultural products

  20. Appraisal of the radiological situation following a nuclear explosion

    International Nuclear Information System (INIS)

    Andreev, E.

    1976-01-01

    The physical laws governing a nuclear explosion and the characteristics of initial and residual radiation are set forth for an atomic and a neutron bomb. Consequent issues are successively discussed for local, continental, and global fallout, and formation of the radioactive trace. Impact aspects considered include: physico-chemical characteristics of fission products; inhalation, ingestion, and percutaneous routes of intake; distribution, localization, and removal from the body. Assessment is also made of external gamma irradiation from the radioactive trace. Finally, consideration is given to problems of radiation injuries sorting, of dosimetry, and early diagnostics in an emergency situation. (A.B.)

  1. Nuclear safety and radiation protection report of the Cruas-Meysse nuclear facilities - 2014

    International Nuclear Information System (INIS)

    2015-01-01

    This safety report was established in accordance with articles L. 125-15 and L. 125-16 of the French environmental code. It presents, first, the NPPs (INBs no. 111 and 112). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2014, if any, are reported as well as the radioactive and non-radioactive effluents discharge in the environment. Finally, the radioactive materials and wastes generated by the facility are presented (type of waste, quantities, conditioning process). The document concludes with a presentation of the actions of communication and public information made by the direction of the facility. A glossary and the list of recommendations from the Committees for health, safety and working conditions are given in appendix

  2. Nuclear safety and radiation protection report of the Belleville-sur-Loire nuclear facilities - 2013

    International Nuclear Information System (INIS)

    2014-01-01

    This safety report was established in accordance with articles L. 125-15 and L. 125-16 of the French environmental code. It presents, first, the NPPs (INBs no. 127 and 128). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2013, if any, are reported as well as the radioactive and non-radioactive effluents discharge in the environment. Finally, the radioactive materials and wastes generated by the facility are presented (type of waste, quantities, conditioning process). The document concludes with a presentation of the actions of communication and public information made by the direction of the facility. A glossary and the list of recommendations from the Committees for health, safety and working conditions are given in appendix

  3. Nuclear safety and radiation protection report of the Paluel nuclear facilities - 2014

    International Nuclear Information System (INIS)

    2015-01-01

    This safety report was established in accordance with articles L. 125-15 and L. 125-16 of the French environmental code. It presents, first, the NPPs (INBs no. 103, 104, 114 and 115). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2014, if any, are reported as well as the radioactive and non-radioactive effluents discharge in the environment. Finally, the radioactive materials and wastes generated by the facility are presented (type of waste, quantities, conditioning process). The document concludes with a presentation of the actions of communication and public information made by the direction of the facility. A glossary and the list of recommendations from the Committees for health, safety and working conditions are given in appendix

  4. Nuclear safety and radiation protection report of the Belleville-sur-Loire nuclear facilities - 2014

    International Nuclear Information System (INIS)

    2015-01-01

    This safety report was established in accordance with articles L. 125-15 and L. 125-16 of the French environmental code. It presents, first, the NPPs (INBs no. 127 and 128). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2014, if any, are reported as well as the radioactive and non-radioactive effluents discharge in the environment. Finally, the radioactive materials and wastes generated by the facility are presented (type of waste, quantities, conditioning process). The document concludes with a presentation of the actions of communication and public information made by the direction of the facility. A glossary and the list of recommendations from the Committees for health, safety and working conditions are given in appendix

  5. Nuclear safety and radiation protection report of the Penly nuclear facilities - 2014

    International Nuclear Information System (INIS)

    2015-01-01

    This safety report was established in accordance with articles L. 125-15 and L. 125-16 of the French environmental code. It presents, first, the NPPs (INBs no. 136 and 140). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2014, if any, are reported as well as the radioactive and non-radioactive effluents discharge in the environment. Finally, the radioactive materials and wastes generated by the facility are presented (type of waste, quantities, conditioning process). The document concludes with a presentation of the actions of communication and public information made by the direction of the facility. A glossary and the list of recommendations from the Committees for health, safety and working conditions are given in appendix

  6. Nuclear safety and radiation protection report of Belleville-Sur-Loire nuclear facilities - 2012

    International Nuclear Information System (INIS)

    2013-01-01

    This safety report was established in accordance with articles L. 125-15 and L. 125-16 of the French environmental code. It presents, first, the NPPs (INBs no. 127 and 128). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2012, if any, are reported as well as the radioactive and non-radioactive effluents discharge in the environment. Finally, the radioactive materials and wastes generated by the facility are presented (type of waste, quantities, conditioning process). The document concludes with a presentation of the actions of communication and public information made by the direction of the facility. A glossary and the list of recommendations from the Committees for health, safety and working conditions are given in appendix. (J.S.)

  7. Nuclear safety and radiation protection report of the Flamanville nuclear facilities - 2013

    International Nuclear Information System (INIS)

    2014-01-01

    This safety report was established in accordance with articles L. 125-15 and L. 125-16 of the French environmental code. It presents, first, the NPPs (INBs no. 108, 109 and 167 (under construction)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2013, if any, are reported as well as the radioactive and non-radioactive effluents discharge in the environment. Finally, the radioactive materials and wastes generated by the facility are presented (type of waste, quantities, conditioning process). The document concludes with a presentation of the actions of communication and public information made by the direction of the facility. A glossary and the list of recommendations from the Committees for health, safety and working conditions are given in appendix

  8. Nuclear safety and radiation protection report of Fessenheim nuclear facilities - 2012

    International Nuclear Information System (INIS)

    2013-01-01

    This safety report was established in accordance with articles L. 125-15 and L. 125-16 of the French environmental code. It presents, first, the NPPs (INB no. 75). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2012, if any, are reported as well as the radioactive and non-radioactive effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facility are presented (type of waste, quantities, conditioning process). The document concludes with a presentation of the actions of communication and public information made by the direction of the facility. A glossary and the list of recommendations from the Committees for health, safety and working conditions are given in appendix. (J.S.)

  9. Nuclear safety and radiation protection report of Blayais nuclear facilities - 2012

    International Nuclear Information System (INIS)

    2013-01-01

    This safety report was established in accordance with articles L. 125-15 and L. 125-16 of the French environmental code. It presents, first, the NPPs (INBs no. 86 and 110). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2012, if any, are reported as well as the radioactive and non-radioactive effluents discharge in the environment. Finally, the radioactive materials and wastes generated by the facility are presented (type of waste, quantities, conditioning process). The document concludes with a presentation of the actions of communication and public information made by the direction of the facility. A glossary and the list of recommendations from the Committees for health, safety and working conditions are given in appendix. (J.S.)

  10. Nuclear safety and radiation protection report of Nogent-Sur-Seine nuclear facilities - 2012

    International Nuclear Information System (INIS)

    2013-01-01

    This safety report was established in accordance with articles L. 125-15 and L. 125-16 of the French environmental code. It presents, first, the NPPs (INBs no. 129 and 130). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2012, if any, are reported as well as the radioactive and non-radioactive effluents discharge in the environment. Finally, the radioactive materials and wastes generated by the facility are presented (type of waste, quantities, conditioning process). The document concludes with a presentation of the actions of communication and public information made by the direction of the facility. A glossary and the list of recommendations from the Committees for health, safety and working conditions are given in appendix. (J.S.)

  11. Nuclear safety and radiation protection report of the Paluel nuclear facilities - 2013

    International Nuclear Information System (INIS)

    2014-01-01

    This safety report was established in accordance with articles L. 125-15 and L. 125-16 of the French environmental code. It presents, first, the NPPs (INBs no. 103, 104, 114 and 115). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2013, if any, are reported as well as the radioactive and non-radioactive effluents discharge in the environment. Finally, the radioactive materials and wastes generated by the facility are presented (type of waste, quantities, conditioning process). The document concludes with a presentation of the actions of communication and public information made by the direction of the facility. A glossary and the list of recommendations from the Committees for health, safety and working conditions are given in appendix

  12. Nuclear safety and radiation protection report of the Civaux nuclear facilities - 2014

    International Nuclear Information System (INIS)

    2015-01-01

    This safety report was established in accordance with articles L. 125-15 and L. 125-16 of the French environmental code. It presents, first, the NPPs (INBs no. 158 and 159). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2014, if any, are reported as well as the radioactive and non-radioactive effluents discharge in the environment. Finally, the radioactive materials and wastes generated by the facility are presented (type of waste, quantities, conditioning process). The document concludes with a presentation of the actions of communication and public information made by the direction of the facility. A glossary and the list of recommendations from the Committees for health, safety and working conditions are given in appendix

  13. Nuclear safety and radiation protection report of Cruas-Meysse nuclear facilities - 2012

    International Nuclear Information System (INIS)

    2013-01-01

    This safety report was established in accordance with articles L. 125-15 and L. 125-16 of the French environmental code. It presents, first, the NPPs (INBs no. 111 and 112). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2012, if any, are reported as well as the radioactive and non-radioactive effluents discharge in the environment. Finally, the radioactive materials and wastes generated by the facility are presented (type of waste, quantities, conditioning process). The document concludes with a presentation of the actions of communication and public information made by the direction of the facility. A glossary and the list of recommendations from the Committees for health, safety and working conditions are given in appendix. (J.S.)

  14. Nuclear safety and radiation protection report of the Dampierre-en-Burly nuclear facilities - 2013

    International Nuclear Information System (INIS)

    2014-01-01

    This safety report was established in accordance with articles L. 125-15 and L. 125-16 of the French environmental code. It presents, first, the NPPs (INBs no. 84 and 85). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2013, if any, are reported as well as the radioactive and non-radioactive effluents discharge in the environment. Finally, the radioactive materials and wastes generated by the facility are presented (type of waste, quantities, conditioning process). The document concludes with a presentation of the actions of communication and public information made by the direction of the facility. A glossary and the list of recommendations from the Committees for health, safety and working conditions are given in appendix

  15. Nuclear safety and radiation protection report of Dampierre-En-Burly nuclear facilities - 2012

    International Nuclear Information System (INIS)

    2013-01-01

    This safety report was established in accordance with articles L. 125-15 and L. 125-16 of the French environmental code. It presents, first, the NPPs (INBs no. 84 and 85). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2012, if any, are reported as well as the radioactive and non-radioactive effluents discharge in the environment. Finally, the radioactive materials and wastes generated by the facility are presented (type of waste, quantities, conditioning process). The document concludes with a presentation of the actions of communication and public information made by the direction of the facility. A glossary and the list of recommendations from the Committees for health, safety and working conditions are given in appendix. (J.S.)

  16. Nuclear safety and radiation protection report of Civaux nuclear facilities - 2012

    International Nuclear Information System (INIS)

    2013-01-01

    This safety report was established in accordance with articles L. 125-15 and L. 125-16 of the French environmental code. It presents, first, the NPPs (INBs no. 158 and 159). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2012, if any, are reported as well as the radioactive and non-radioactive effluents discharge in the environment. Finally, the radioactive materials and wastes generated by the facility are presented (type of waste, quantities, conditioning process). The document concludes with a presentation of the actions of communication and public information made by the direction of the facility. A glossary and the list of recommendations from the Committees for health, safety and working conditions are given in appendix. (J.S.)

  17. Nuclear safety and radiation protection report of the Penly nuclear facilities - 2013

    International Nuclear Information System (INIS)

    2014-01-01

    This safety report was established in accordance with articles L. 125-15 and L. 125-16 of the French environmental code. It presents, first, the NPPs (INBs no. 136 and 140). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2013, if any, are reported as well as the radioactive and non-radioactive effluents discharge in the environment. Finally, the radioactive materials and wastes generated by the facility are presented (type of waste, quantities, conditioning process). The document concludes with a presentation of the actions of communication and public information made by the direction of the facility. A glossary and the list of recommendations from the Committees for health, safety and working conditions are given in appendix

  18. Nuclear safety and radiation protection report of Golfech nuclear facilities - 2012

    International Nuclear Information System (INIS)

    2013-01-01

    This safety report was established in accordance with articles L. 125-15 and L. 125-16 of the French environmental code. It presents, first, the NPPs (INBs no. 135 and 142). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2012, if any, are reported as well as the radioactive and non-radioactive effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facility are presented (type of waste, quantities, conditioning process). The document concludes with a presentation of the actions of communication and public information made by the direction of the facility. A glossary and the list of recommendations from the Committees for health, safety and working conditions are given in appendix. (J.S.)

  19. Nuclear safety and radiation protection report of Penly nuclear facilities - 2012

    International Nuclear Information System (INIS)

    2013-01-01

    This safety report was established in accordance with articles L. 125-15 and L. 125-16 of the French environmental code. It presents, first, the NPPs (INBs no. 136 and 140). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2012, if any, are reported as well as the radioactive and non-radioactive effluents discharge in the environment. Finally, the radioactive materials and wastes generated by the facility are presented (type of waste, quantities, conditioning process). The document concludes with a presentation of the actions of communication and public information made by the direction of the facility. A glossary and the list of recommendations from the Committees for health, safety and working conditions are given in appendix. (J.S.)

  20. Nuclear safety and radiation protection report of the Fessenheim nuclear facilities - 2014

    International Nuclear Information System (INIS)

    2015-01-01

    This safety report was established in accordance with articles L. 125-15 and L. 125-16 of the French environmental code. It presents, first, the NPPs (INB no. 75). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2014, if any, are reported as well as the radioactive and non-radioactive effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facility are presented (type of waste, quantities, conditioning process). The document concludes with a presentation of the actions of communication and public information made by the direction of the facility. A glossary and the list of recommendations from the Committees for health, safety and working conditions are given in appendix

  1. Nuclear safety and radiation protection report of Saint-Alban Saint-Maurice nuclear facilities - 2012

    International Nuclear Information System (INIS)

    2013-01-01

    This safety report was established in accordance with articles L. 125-15 and L. 125-16 of the French environmental code. It presents, first, the NPPs (INBs no. 119 and 120). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2012, if any, are reported as well as the radioactive and non-radioactive effluents discharge in the environment. Finally, the radioactive materials and wastes generated by the facility are presented (type of waste, quantities, conditioning process). The document concludes with a presentation of the actions of communication and public information made by the direction of the facility. A glossary and the list of recommendations from the Committees for health, safety and working conditions are given in appendix. (J.S.)

  2. Nuclear safety and radiation protection report of the Golfech nuclear facilities - 2014

    International Nuclear Information System (INIS)

    2015-01-01

    This safety report was established in accordance with articles L. 125-15 and L. 125-16 of the French environmental code. It presents, first, the NPPs (INBs no. 135 and 142). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2014, if any, are reported as well as the radioactive and non-radioactive effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facility are presented (type of waste, quantities, conditioning process). The document concludes with a presentation of the actions of communication and public information made by the direction of the facility. A glossary and the list of recommendations from the Committees for health, safety and working conditions are given in appendix

  3. Nuclear safety and radiation protection report of the Civaux nuclear facilities - 2013

    International Nuclear Information System (INIS)

    2014-01-01

    This safety report was established in accordance with articles L. 125-15 and L. 125-16 of the French environmental code. It presents, first, the NPPs (INBs no. 158 and 159). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2013, if any, are reported as well as the radioactive and non-radioactive effluents discharge in the environment. Finally, the radioactive materials and wastes generated by the facility are presented (type of waste, quantities, conditioning process). The document concludes with a presentation of the actions of communication and public information made by the direction of the facility. A glossary and the list of recommendations from the Committees for health, safety and working conditions are given in appendix

  4. Nuclear safety and radiation protection report of the Nogent-sur-Seine nuclear facilities - 2013

    International Nuclear Information System (INIS)

    2014-01-01

    This safety report was established in accordance with articles L. 125-15 and L. 125-16 of the French environmental code. It presents, first, the NPPs (INBs no. 129 and 130). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2013, if any, are reported as well as the radioactive and non-radioactive effluents discharge in the environment. Finally, the radioactive materials and wastes generated by the facility are presented (type of waste, quantities, conditioning process). The document concludes with a presentation of the actions of communication and public information made by the direction of the facility. A glossary and the list of recommendations from the Committees for health, safety and working conditions are given in appendix

  5. Nuclear safety and radiation protection report of the Dampierre-en-Burly nuclear facilities - 2014

    International Nuclear Information System (INIS)

    2015-01-01

    This safety report was established in accordance with articles L. 125-15 and L. 125-16 of the French environmental code. It presents, first, the NPPs (INBs no. 84 and 85). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2014, if any, are reported as well as the radioactive and non-radioactive effluents discharge in the environment. Finally, the radioactive materials and wastes generated by the facility are presented (type of waste, quantities, conditioning process). The document concludes with a presentation of the actions of communication and public information made by the direction of the facility. A glossary and the list of recommendations from the Committees for health, safety and working conditions are given in appendix

  6. Nuclear safety and radiation protection report of the Chooz nuclear facilities - 2014

    International Nuclear Information System (INIS)

    2015-01-01

    This safety report was established in accordance with articles L. 125-15 and L. 125-16 of the French environmental code. It presents, first, the NPPs (INBs no. 139, 144 and 163 (under dismantling)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2014, if any, are reported as well as the radioactive and non-radioactive effluents discharge in the environment. Finally, the radioactive materials and wastes generated by the facility are presented (type of waste, quantities, conditioning process). The document concludes with a presentation of the actions of communication and public information made by the direction of the facility. A glossary and the list of recommendations from the Committees for health, safety and working conditions are given in appendix

  7. Nuclear safety and radiation protection report of the Cattenom nuclear facilities - 2013

    International Nuclear Information System (INIS)

    2014-01-01

    This safety report was established in accordance with articles L. 125-15 and L. 125-16 of the French environmental code. It presents, first, the NPPs (INBs no. 124, 125, 126 and 137). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2013, if any, are reported as well as the radioactive and non-radioactive effluents discharge in the environment. Finally, the radioactive materials and wastes generated by the facility are presented (type of waste, quantities, conditioning process). The document concludes with a presentation of the actions of communication and public information made by the direction of the facility. A glossary and the list of recommendations from the Committees for health, safety and working conditions are given in appendix

  8. Nuclear safety and radiation protection report of the Chooz nuclear facilities - 2013

    International Nuclear Information System (INIS)

    2014-01-01

    This safety report was established in accordance with articles L. 125-15 and L. 125-16 of the French environmental code. It presents, first, the NPPs (INBs no. 139, 144 and 163 (under dismantling)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2013, if any, are reported as well as the radioactive and non-radioactive effluents discharge in the environment. Finally, the radioactive materials and wastes generated by the facility are presented (type of waste, quantities, conditioning process). The document concludes with a presentation of the actions of communication and public information made by the direction of the facility. A glossary and the list of recommendations from the Committees for health, safety and working conditions are given in appendix

  9. Nuclear safety and radiation protection report of the Cattenom nuclear facilities - 2014

    International Nuclear Information System (INIS)

    2015-01-01

    This safety report was established in accordance with articles L. 125-15 and L. 125-16 of the French environmental code. It presents, first, the NPPs (INBs no. 124, 125, 126 and 137). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2014, if any, are reported as well as the radioactive and non-radioactive effluents discharge in the environment. Finally, the radioactive materials and wastes generated by the facility are presented (type of waste, quantities, conditioning process). The document concludes with a presentation of the actions of communication and public information made by the direction of the facility. A glossary and the list of recommendations from the Committees for health, safety and working conditions are given in appendix

  10. Nuclear safety and radiation protection report of the Flamanville nuclear facilities - 2014

    International Nuclear Information System (INIS)

    2015-01-01

    This safety report was established in accordance with articles L. 125-15 and L. 125-16 of the French environmental code. It presents, first, the NPPs (INBs no. 108, 109 and 167 (under construction)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2014, if any, are reported as well as the radioactive and non-radioactive effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facility are presented (type of waste, quantities, conditioning process). The document concludes with a presentation of the actions of communication and public information made by the direction of the facility. A glossary and the list of recommendations from the Committees for health, safety and working conditions are given in appendix

  11. Nuclear safety and radiation protection report of the Blayais nuclear facilities - 2013

    International Nuclear Information System (INIS)

    2014-01-01

    This safety report was established in accordance with articles L. 125-15 and L. 125-16 of the French environmental code. It presents, first, the NPPs (INBs no. 86 and 110). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2013, if any, are reported as well as the radioactive and non-radioactive effluents discharge in the environment. Finally, the radioactive materials and wastes generated by the facility are presented (type of waste, quantities, conditioning process). The document concludes with a presentation of the actions of communication and public information made by the direction of the facility. A glossary and the list of recommendations from the Committees for health, safety and working conditions are given in appendix

  12. Life Management and Safety of Nuclear Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Fabbri, S.; Diluch, A.; Vega, G., E-mail: fabbri@cnea.gov.ar [Comisión Nacional de Energía Atómica, Buenos Aires (Argentina)

    2014-10-15

    The nuclear programme in Argentina includes: nuclear power and related supplies, medical and industrial applications, waste management, research and development and human training. Nuclear facilities require life management programs that allow a safe operation. Safety is the first priority for designers and operators. This can be attained with defence in depth: regular inspections and maintenance procedures to minimize failure risks. CNEA objectives in this area are to possess the necessary capability to give safe and fast technical support. Within this scheme, one of the main activities undertaken by CNEA is to provide technological assistance to the nuclear plants and research reactors. As a consequence of an increasing concern about safety and ageing a Life Management Department for safe operation was created to take care of these subjects. The goal is to elaborate a Safety Evaluation Process for the critical components of nuclear plants and other facilities. The overall objectives of a safety process are to ensure a continuous safe, reliable and effective operation of nuclear facilities and it means the implementation of the defence in deep concept to enhance safety for the protection of the public, the workers and the environment. (author)

  13. Stakeholder involvement in decommissioning nuclear facilities

    International Nuclear Information System (INIS)

    2007-01-01

    Significant numbers of nuclear facilities will need to be decommissioned in the coming decades. In this context, NEA member countries are placing increasing emphasis on the involvement of stakeholders in the associated decision procedures. This study reviews decommissioning experience with a view to identifying stakeholder concerns and best practice in addressing them. The lessons learnt about the end of the facility life cycle can also contribute to better foresight in siting and building new facilities. This report will be of interest to all major players in the field of decommissioning, in particular policy makers, implementers, regulators and representatives of local host communities

  14. The situation of nuclear energy in the USA

    International Nuclear Information System (INIS)

    Barthelt, K.

    1984-01-01

    Owing to the fact that peaceful utilization of nuclear energy receives much coverage in the mass media, at party congresses and lately even in respectable journals in a way characterized by much emotional commitment and little factual knowledge, there is a danger of transferring the situation in the USA too easily to the Federal Republic of Germany along with all those well-known arguments. In the article, the author points out the differences between the continent USA and the comparatively small country Federal Republic of Germany reading the conclusion that any sweeping comparison of both countries is misleading so, too, in energy supply. In detail, there is a brief overview on the historical development of nuclear power utilization in the USA, a discussion of the reasons for cancelling/shutting-down nuclear power plants in the USA, an analysis of the effects of modified demand predictions on power station construction and of funding problems as well as an investigation into the profitability of nuclear energy in the USA. (orig./UA) [de

  15. Engineering thinking in emergency situations: A new nuclear safety concept.

    Science.gov (United States)

    Guarnieri, Franck; Travadel, Sébastien

    2014-11-01

    The lessons learned from the Fukushima Daiichi accident have focused on preventive measures designed to protect nuclear reactors, and crisis management plans. Although there is still no end in sight to the accident that occurred on March 11, 2011, how engineers have handled the aftermath offers new insight into the capacity of organizations to adapt in situations that far exceed the scope of safety standards based on probabilistic risk assessment and on the comprehensive identification of disaster scenarios. Ongoing crises in which conventional resources are lacking, but societal expectations are high, call for "engineering thinking in emergency situations." This is a new concept that emphasizes adaptability and resilience within organizations-such as the ability to create temporary new organizational structures; to quickly switch from a normal state to an innovative mode; and to integrate a social dimension into engineering activities. In the future, nuclear safety oversight authorities should assess the ability of plant operators to create and implement effective engineering strategies on the fly, and should require that operators demonstrate the capability for resilience in the aftermath of an accident.

  16. Nuclear energy: Environmental issues at DOE's nuclear defense facilities

    International Nuclear Information System (INIS)

    1986-01-01

    GAO's review of nine Department of Energy defense facilities identified a number of significant environmental issues: (1) eight facilities have groundwater contaminated with radioactive and/or hazardous substances to high levels; (2) six facilities have soil contamination in unexpected areas, including offsite locations; (3) four facilities are not in full compliance with the Clean Water Act; and (4) all nine facilities are significantly changing their waste disposal practices to obtain a permit under the Resource Conservation and Recovery Act. GAO is recommending that DOE develop and overall groundwater and soil protection strategy that would provide a better perspective on the environmental risks and impacts associated with operating DOE's nuclear defense facilities. GAO also recommends that DOE allow outside independent inspections of the disposal practices used for any waste DOE self-regulates and revise its order governing the management of hazardous and mixed waste

  17. Nuclear safety and radiation protection report of the Bugey nuclear facilities - 2010

    International Nuclear Information System (INIS)

    2011-06-01

    This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Bugey nuclear power plant (Ain (FR)): 4 PWR reactors in operation (INB 78 and 89), one partially dismantled graphite-gas reactor (INB 45), an inter-regional fuel storage facility (MIR, INB 102), and a radioactive waste storage and conditioning facility under construction (ICEDA, INB 173). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2010, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise, microbial proliferation in cooling towers) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

  18. SETT facility of International Nuclear Security Academy

    International Nuclear Information System (INIS)

    Seo, Hyung Min

    2012-01-01

    After the Cold War was put to an end, the international community, especially the Western world, was concerned about Soviet nuclear materials falling into wrong hands, especially of terrorists. Later, the growing threat posed by terrorist networks such as the Taliban and al Qaeda led to a global campaign to deny such networks materials which may be used for the development of Weapons of Mass Destruction (WMD). The 9 11 attacks made a section of the international community highly apprehensive of WMD terrorism, especially its nuclear version. From this point of view, it is clear that nuclear facilities which contain nuclear materials are very attractive targets for those who have intention of nuclear terror

  19. SETT facility of International Nuclear Security Academy

    Energy Technology Data Exchange (ETDEWEB)

    Seo, Hyung Min [Korea Institute of Nuclear Non-proliferation and Control, Daejeon (Korea, Republic of)

    2012-05-15

    After the Cold War was put to an end, the international community, especially the Western world, was concerned about Soviet nuclear materials falling into wrong hands, especially of terrorists. Later, the growing threat posed by terrorist networks such as the Taliban and al Qaeda led to a global campaign to deny such networks materials which may be used for the development of Weapons of Mass Destruction (WMD). The 9 11 attacks made a section of the international community highly apprehensive of WMD terrorism, especially its nuclear version. From this point of view, it is clear that nuclear facilities which contain nuclear materials are very attractive targets for those who have intention of nuclear terror

  20. Neutron fluence measurement in nuclear facilities

    International Nuclear Information System (INIS)

    Camacho L, M.E.

    1997-01-01

    The objective of present work is to determine the fluence of neutrons in nuclear facilities using two neutron detectors designed and built at Instituto Nacional de Investigaciones Nucleares (ININ), Mexico. The two neutron detectors are of the passive type, based on solid state nuclear tracks detectors (SSNTD). One of the two neutron detectors was used to determine the fluence distribution of the ports at the nuclear research reactor TRIGA Mark III, which belongs to ININ. In these facilities is important to know the neutron fluence distribution characteristic to carried out diverse kind of research activities. The second neutron detector was employed in order to carry out environmental neutron surveillance. The detector has the property to separate the thermal, intermediate and fast components of the neutron fluence. This detector was used to measure the neutron fluence at hundred points around the primary container of the first Mexican Nuclear Power plant 'Laguna Verde'. This last detector was also used to determine the neutron fluence in some points of interest, around and inside a low scattering neutron room at the 'Centro de Metrologia de Radiaciones Ionizantes' of the ININ, to know the background neutron field produced by the neutron sources used there. The design of the two neutron detector and the results obtained for each of the surveying facilities, are described in this work. (Author)

  1. Image processing technology for nuclear facilities

    International Nuclear Information System (INIS)

    Lee, Jong Min; Lee, Yong Beom; Kim, Woong Ki; Park, Soon Young

    1993-05-01

    Digital image processing technique is being actively studied since microprocessors and semiconductor memory devices have been developed in 1960's. Now image processing board for personal computer as well as image processing system for workstation is developed and widely applied to medical science, military, remote inspection, and nuclear industry. Image processing technology which provides computer system with vision ability not only recognizes nonobvious information but processes large information and therefore this technique is applied to various fields like remote measurement, object recognition and decision in adverse environment, and analysis of X-ray penetration image in nuclear facilities. In this report, various applications of image processing to nuclear facilities are examined, and image processing techniques are also analysed with the view of proposing the ideas for future applications. (Author)

  2. Gas processing at DOE nuclear facilities

    Energy Technology Data Exchange (ETDEWEB)

    Jacox, J.

    1995-02-01

    The term {open_quotes}Gas Processing{close_quotes} has many possible meanings and understandings. In this paper, and panel, we will be using it to generally mean the treatment of gas by methods other than those common to HVAC and Nuclear Air Treatment. This is only a working guideline not a rigorous definition. Whether a rigorous definition is desirable, or even possible is a question for some other forum. Here we will be discussing the practical aspects of what {open_quotes}Gas Processing{close_quotes} includes and how existing Codes, Standards and industry experience can, and should, apply to DOE and NRC Licensed facilities. A major impediment to use of the best engineering and technology in many nuclear facilities is the administrative mandate that only systems and equipment that meet specified {open_quotes}nuclear{close_quotes} documents are permissible. This paper will highlight some of the limitations created by this approach.

  3. A systems approach to nuclear facility monitoring

    International Nuclear Information System (INIS)

    Argo, P.E.; Doak, J.E.; Howse, J.W.

    1996-01-01

    Sensor technology for use in nuclear facility monitoring has reached an advanced stage of development. Research on where to place these sensors in a facility and how to combine their outputs in a meaningful fashion does not appear to be keeping pace. In this paper, the authors take a global view of the problem where sensor technology is viewed as only one piece of a large puzzle. Other pieces of this puzzle include the optimal location and type of sensors used in a specific facility, the rate at which sensors record information, and the risk associated with the materials/processes at a facility. If the data are analyzed off-site, how will they be transmitted? Is real-time analysis necessary? Is one monitoring only the facility itself, or might one also monitor the processing that occurs there (e.g., tank levels and concentrations)? How is one going to combine the outputs from the various sensors to give us an accurate picture of the state of the facility? This paper will not try to answer all these questions, but rather it will attempt to stimulate thought in this area by formulating a systems approach to the problem demonstrated by a prototype system and a system proposed for an actual facility. The focus will be on the data analysis aspect of the problem. Future work in this area should focus on recommendations and guidelines for a monitoring system based upon the type of facility and processing that occurs there

  4. Tritium surveillance around nuclear facilities in Japan

    International Nuclear Information System (INIS)

    Inoue, Y.; Kasida, Y.

    1978-01-01

    In order to measure the tritium levels in the environmental water around the nuclear facilities, the tritium surveillance program began in 1967 locally at Tsuruga and Mihama districts. Nowadays it has been expanded to the ten commercial nuclear power stations and three nuclear facilities. For samples whose tritium concentration is believed less than about 100 pCi/l, they were electrolytically enriched, and then counted by the liquid scintillation counter. Some of samples believed higher than 100 pCi/l were analysed without any enrichment by the low background liquid scintillation counters, Aloka LB 600 or Aloka LB 1. The results of each station are listed in Table. The sampling points corresponding to each results are shown in Figure. Tritium from the effluent was not reflected in all the land water and the tap water around the nuclear power stations and the nuclear facilities. Tritium concentration in rivers, streams, and reservoirs (pools) decreased exponentially from about 600 pCi/l in 1967 to about 150 pCi/l in 1972 at Tsuruga and Mihama, and 360 pCi/l in 1968 to 120 pCi/l in 1973 at Genkai, with the half life of about 2.5 years in both cases. After around 1972, tritium levels of river system in all districts of Japan kept nearly constant up to the end of 1975 and they were in the range from 100 to 300 pCi/l corresponding to the districts. Thereafter, it seems to start to decrease again in 1976. Sea water sampled at the intake of the station or on the seashore far from the outlet was regarded not to be influenced by the effluent from the nuclear reactors or facilities. Tritium concentration in these coastal waters decreased from 100 - 300 pCi/l in 1971 to 30 - 40 pCi/l in 1972 in Fukushima, Ibaraki and Fukui prefectures. (author)

  5. Gas separation techniques in nuclear facilities

    International Nuclear Information System (INIS)

    Hioki, Hideaki; Morisue, Tetsuo; Ohno, Masayoshi

    1983-01-01

    The literatures concerning the gas separation techniques which are applied to the waste gases generated from nuclear power plants and nuclear fuel reprocessing plants, uranium enrichment and the instrumentation of nuclear facilities are reviewed. The gas permeability and gas separation performance of membranes are discussed in terms of rare gas separation. The investigation into the change of the gas permeability and mechanical properties of membranes with exposure to radiation is reported. The theoretical investigation of the separating cells used for the separation of rare gas and the development of various separating cells are described, and the theoretical and experimental investigations concerning rare gas separation using cascades are described. The application of membrane method to nuclear facilities is explained showing the examples of uranium enrichment, the treatment of waste gases from nuclear reactor buildings and nuclear fuel reprocessing plants, the monitoring of low level β-emitters in stacks, the detection of failed fuels and the detection of water leak in fast breeder reactors. (Yoshitake, I.)

  6. Pt. 1: Decommissioning of nuclear facilities. Pt. 2: Methods of decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    Steinkilberg, W.

    1982-01-01

    In the present paper the different steps of dismantlement of nuclear facilities are dealt with. First the planning principles for decomminconing are discussed and then the planning of the reactorblock dismantlement in the FR2 research reactor is described. (RW)

  7. The physical protection of nuclear material and nuclear facilities

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-06-01

    The latest review (1993) of this document was of limited scope and resulted in changes to the text of INFCIRC/225/Rev.2 designed to make the categorization table in that document consistent with the categorization table contained in the Convention on Physical Protection of Nuclear Materials. Consequently, a comprehensive review of INFCIRC/225 has not been conducted since 1989. Consequently, a meeting of national experts was convened from 2-5 June 1998 and from 27-29 October 1998 for a thorough review of INFCIRC/225/Rev.3. The revised document reflects the recommendations of the national experts to improve the structure and clarity of the document and to take account of improved technology and current international and national practices. In particular, a chapter has been added which provides specific recommendations related to sabotage of nuclear facilities and nuclear material. As a result of this addition, the title has been changed to 'The Physical Protection of Nuclear Material and Nuclear Facilities'. The recommendations presented in this IAEA document reflect a broad consensus among Member States on the requirements which should be met by systems for the physical protection of nuclear materials and facilities. It is hoped that they will provide helpful guidance for Member States.

  8. The physical protection of nuclear material and nuclear facilities

    International Nuclear Information System (INIS)

    1999-06-01

    The latest review (1993) of this document was of limited scope and resulted in changes to the text of INFCIRC/225/Rev.2 designed to make the categorization table in that document consistent with the categorization table contained in the Convention on Physical Protection of Nuclear Materials. Consequently, a comprehensive review of INFCIRC/225 has not been conducted since 1989. Consequently, a meeting of national experts was convened from 2-5 June 1998 and from 27-29 October 1998 for a thorough review of INFCIRC/225/Rev.3. The revised document reflects the recommendations of the national experts to improve the structure and clarity of the document and to take account of improved technology and current international and national practices. In particular, a chapter has been added which provides specific recommendations related to sabotage of nuclear facilities and nuclear material. As a result of this addition, the title has been changed to 'The Physical Protection of Nuclear Material and Nuclear Facilities'. The recommendations presented in this IAEA document reflect a broad consensus among Member States on the requirements which should be met by systems for the physical protection of nuclear materials and facilities. It is hoped that they will provide helpful guidance for Member States

  9. Decommissioning of nuclear facilities using current criteria

    International Nuclear Information System (INIS)

    Shum, E.Y.; Swift, J.J.; Malaro, J.C.

    1991-01-01

    When a licensed nuclear facility ceases operation, the US Nuclear Regulatory Commission (NRC) is responsible for ensuring that the facility and its site are decontaminated to an acceptable level so that it is safe to release that facility and site for unrestricted public use. Currently, the NRC is developing decommissioning criteria based on reducing public doses from residual contamination in soils and structures at sites released for unrestricted use to as low as is reasonably achievable (ALARA). Plans are to quantify ALARA in terms of an annual total effective dose equivalent (TEDE) to an average member of the most highly exposed population group. The NRC is working on a regulatory guidance document to provide a technical basis for translating residual contamination levels to annual dose levels. Another regulatory guide is being developed to provide guidance to the licensee on how to conduct radiological surveys to demonstration compliance with the NRC decommissioning criteria. The methods and approaches used in these regulatory guides on the decommissioning of a nuclear facility are discussed in the paper

  10. Hematite nuclear fuel cycle facility decommissioning

    International Nuclear Information System (INIS)

    Hayes, K.

    2004-01-01

    Westinghouse Electric Company LLC ('Westinghouse') acquired a nuclear fuel processing plant at Hematite, Missouri ('Hematite', the 'Facility', or the 'Plant') in April 2000. The plant has subsequently been closed, and its operations have been relocated to a newer, larger facility. Westinghouse has announced plans to complete its clean-up, decommissioning, and license retirement in a safe, socially responsible, and environmentally sound manner as required by internal policies, as well as those of its parent company, British Nuclear Fuels plc. ('BNFL'). Preliminary investigations have revealed the presence of environmental contamination in various areas of the facility and grounds, including both radioactive contamination and various other substances related to the nuclear fuel processing operations. The disparity in regulatory requirements for radiological and nonradiological contaminants, the variety of historic and recent operations, and the number of previous owners working under various contractual arrangements for both governmental and private concerns has resulted in a complex project. This paper discusses Westinghouse's efforts to develop and implement a comprehensive decontamination and decommissioning (D and D) strategy for the facility and grounds. (author)

  11. International safeguards in large scale nuclear facilities

    International Nuclear Information System (INIS)

    Gupta, D.; Heil, J.

    1977-01-01

    The trend in the energy sector in most of the industrialized areas of the world shows rather clearly, that the rate of installation of nuclear plants will be very high and that the largest possible units of nuclear material handling and storage facilities will be built. Various experiments and analyses of measurement methods relevant to safeguards, in typical nuclear facilities like a fuel reprocessing or a fabrication plant, have shown that the associated measurement errors as obtained under normal operating conditions are such that they are mainly dominated by systematic errors and that such systematic errors may lie in the range of percentages of the measured amount so that a material balance in such a plant could not normally be closed with high accuracy. The simplest way of going around the problem would be to increase the frequency of striking a material balance over a given period of time. This could however lead to an anormous increase in the technical and financial burden for the operator of a facility. The present paper analyses this problem in some detail for some facilities and shows that with a properly developed information system in such plants and a combination of containment, surveillance and accountancy measures, safeguards statements for relatively low significant amounts can be made with the attainable range of measurement accuracies

  12. The International Atomic Energy Agency: orientations for the 21. century. Nuclear facilities exploitation: three questions to Remy Carle. The civil nuclear and the electric power generation in Germany. Usa: the electric power marker deregulation and the perspective of the nuclear energy. The situation of nuclear energy in Japan. Finland.. debate about the 5. reactor. The electronuclear development in China. The last act of the swedish nuclear saga. The Korean nuclear programme. The civil nuclear energy in Eastern Europe... in brief

    International Nuclear Information System (INIS)

    Carle, R.; Thiebaud, Ph.; Heuraux, Ch.; Tinturier, B.; Lavergne, B. de; Lavigne, J.J.; Soyer, B.; Edin, K.A.; Chaucheprat, P.

    2000-01-01

    This issue is dedicated to nuclear programmes throughout the world. A few articles give an overview of the major trends of nuclear industry, from the standpoints of economy, industry, environment and international regulations. A few articles give an overview of the major trends of nuclear industry, from the standpoints of economy, industry, environment and international regulations. A few specific countries or groups of countries are then highlighted, together with a typical economic and political backgrounds. The countries dealt with are Germany, China, Korea, the U.S., Finland, Japan and Sweden. Some specific data are given on nuclear industry in Eastern Europe. (author)

  13. A system approach to nuclear facility monitoring

    Energy Technology Data Exchange (ETDEWEB)

    Argo, P.E.; Doak, J.E.; Howse, J.W.

    1996-09-01

    Sensor technology for use in nuclear facility monitoring has reached and advanced stage of development. Research on where to place these sensors in a facility and how to combine their outputs in a meaningful fashion does not appear to be keeping pace. In this paper, we take a global view of the problem where sensor technology is viewed as only one piece of a large puzzle. Other pieces of this puzzle include the optimal location and type of sensors used in a specific facility, the rate at which sensors record information, and the risk associated with the materials/processes at a facility. If the data are analyzed off-site, how will they be transmitted? Is real-time analysis necessary? Are we monitoring only the facility itself, or might we also monitor the processing that occurs there? How are we going to combine the output from the various sensors to give us an accurate picture of the state of the facility? This paper will not try to answer all these questions, but rather it will attempt to stimulate thought in this area by formulating a systems approach to the problem demonstrated by a prototype system and a systems proposed for an actual facility. Our focus will be on the data analysis aspect of the problem.

  14. Deactivating a major nuclear fuels reprocessing facility

    International Nuclear Information System (INIS)

    LeBaron, G.J.

    1997-01-01

    This paper describes three key processes used in deactivating the Plutonium Uranium Extraction (PUREX) Facility, a large, complex nuclear reprocessing facility, 15 months ahead of schedule and $77 million under budget. The organization was reengineered to refine its business processes and more effectively organize around the deactivation work scope. Multi-disciplined work teams were formed to be self-sufficient and empowered to make decisions and perform work. A number of benefits were realized by reengineering. A comprehensive process to develop end points which clearly identified specific results and the post-project facility configuration was developed so all areas of a facility were addressed. Clear and specific end points allowed teams to focus on completing deactivation activities and helped ensure there were no unfulfilled end-of-project expectations. The RCRA regulations require closure of permitted facilities within 180 days after cessation of operations which may essentially necessitate decommissioning. A more cost effective approach was adopted which significantly reduced risk to human health and the environment by taking the facility to a passive, safe, inexpensive-to-maintain surveillance and maintenance condition (deactivation) prior to disposition. PUREX thus became the first large reprocessing facility with active TSD [treatment, storage, and disposal] units to be deactivated under the RCRA regulations

  15. Nuclear safety and radiation protection report of the Creys-Malville nuclear facilities - 2011

    International Nuclear Information System (INIS)

    2012-01-01

    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 partially dismantled facilities of the Creys-Malville nuclear power plant (also known as Superphenix power plant, INB no. 91, Creys-Mepieu - Isere (FR)) and the other fuel and waste storage facilities of the site (INB no. 141). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities. The incidents and accidents which occurred in 2011, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

  16. Nuclear safety and radiation protection report of the Chinon nuclear facilities - 2011

    International Nuclear Information System (INIS)

    2012-01-01

    This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Chinon nuclear power plant (Indre-et-Loire, 37 (FR)): 4 PWR reactors in operation (Chinon B, INB 107 and 132), 3 partially dismantled graphite-gas reactors (Chinon A, INB 133, 153 and 161), a workshop for irradiated materials (AMI, INB 94), and an inter-regional fuel storage facility (MIR, INB 99). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2011, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise, microbial proliferation in cooling towers) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

  17. Nuclear safety and radiation protection report of the Creys-Malville nuclear facilities - 2012

    International Nuclear Information System (INIS)

    2013-01-01

    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 partially dismantled facilities of the Creys-Malville nuclear power plant (also known as Superphenix power plant, INB no. 91, Creys-Mepieu - Isere (FR)) and the other fuel and waste storage facilities of the site (INB no. 141). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities. The incidents and accidents which occurred in 2012, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions

  18. Nuclear safety and radiation protection report of the Chinon nuclear facilities - 2010

    International Nuclear Information System (INIS)

    2011-06-01

    This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Chinon nuclear power plant (Indre-et-Loire, 37 (FR)): 4 PWR reactors in operation (Chinon B, INB 107 and 132), 3 partially dismantled graphite-gas reactors (Chinon A, INB 133, 153 and 161), a workshop for irradiated materials (AMI, INB 94), and an inter-regional fuel storage facility (MIR, INB 99). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2010, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise, microbial proliferation in cooling towers) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

  19. Present status of nuclear medicine - Situation in France

    International Nuclear Information System (INIS)

    Swiniarski, R. de

    2002-01-01

    Contrary to the general belief the nuclear medicine (NM) is a rather old science; actually, Henry Becquerel, the discoverer of the natural radioactivity in 1896, is deemed often as the initiator of this science and that would be the first stage. Discovery of artificial radioactivity by Irene and Frederic Joliot-Curie in 1934 marks the second essential stage and as such the initiation of NM. Nuclear medicine recorded significant progress since its inception, essentially after the WW1 due mainly to the advance of nuclear physics, nuclear electronics and the associated information techniques. But, the development of general physics boosted also other new methods of medical imaging as MRI (Magnetic Resonance Imaging), ultrasonic imaging, X-ray scanner, magnetic encephalography (MEG), etc. Several services of nuclear medicine currently functioning in France, in public or private hospitals, are all equipped at least with one Anger chamber, possibly two, what allows making the scintigraphy of most of human organs, or else, planar gamma-scintigraphy or tomo-scintigraphy. Unfortunately, regarding the positron chambers (positron computed tomography-PCT) the situation in France is not satisfactory. For the time being only three centres, particularly designed for research, are equipped with cyclotrons plus PCT technology, namely SHFJ at Orsay, Cyceron at Caen and SERMEP at Lyon (especially devoted to cardiologic investigation). Other two installations will be soon available at Toulouse and at Tenon (Paris). Officials, responsible of health services and medical schools and hospitals have defined a national index for PCT in France. Thus, starting from 2001, a machine for every million of inhabitants is provided, i.e. about 60 PCTs are planned to be installed till 2003 in Lille, Grenoble, Nantes, Rennes and other large French cities. France is committed not to miss the European bus of nuclear oncology of installing this equipment absolutely necessary in cancer detection and

  20. Testing lifting systems in nuclear facilities

    International Nuclear Information System (INIS)

    Kling, H.; Laug, R.

    1984-01-01

    Lifting systems in nuclear facilities must be inspected at regular intervals after having undergone their first acceptance test. These inspections are frequently carried out by service firms which not only employ the skilled personnel required for such jobs but also make available the necessary test equipment. The inspections in particular include a number of sophisticated load tests for which test load systems have been developed to allow lifting systems to be tested so that reactor specific boundary conditions are taken into account. In view of the large number of facilities to be inspected, the test load system is a modular system. (orig.) [de

  1. Nuclear fuel cycle facility accident analysis handbook

    International Nuclear Information System (INIS)

    Ayer, J.E.; Clark, A.T.; Loysen, P.; Ballinger, M.Y.; Mishima, J.; Owczarski, P.C.; Gregory, W.S.; Nichols, B.D.

    1988-05-01

    The Accident Analysis Handbook (AAH) covers four generic facilities: fuel manufacturing, fuel reprocessing, waste storage/solidification, and spent fuel storage; and six accident types: fire, explosion, tornado, criticality, spill, and equipment failure. These are the accident types considered to make major contributions to the radiological risk from accidents in nuclear fuel cycle facility operations. The AAH will enable the user to calculate source term releases from accident scenarios manually or by computer. A major feature of the AAH is development of accident sample problems to provide input to source term analysis methods and transport computer codes. Sample problems and illustrative examples for different accident types are included in the AAH

  2. Risk communication for existing exposure situation after the nuclear disaster

    International Nuclear Information System (INIS)

    Yamaguchi, Ichiro

    2011-01-01

    The title subject is explained for its better understanding and recognition. The present state (Oct. 2011) where crisis of Fukushima Nuclear Accident has reached a settlement with release of 0.1 GBq/hr from the reactor container, is called the existing exposure situation. Radiation risk must be reduced under such a situation as people have to live in. Risk is defined to be a probability of matters undesirable, its size is assessed by various conditions and assumptions, it is manageable on its assessment, but its realization largely depends on subjectivity. Measures for lessening the risk usually accompany a load and disadvantage, leading to an antinomy structure (trade-off), of which problem is ultimately an ethical task of public health and cannot be solved in the form everybody agrees with. Therefore, a mutual consent among concerned people is required for deciding the principle of the risk management, for which the risk communication is essential. Risk communication about radiation is an unavoidable task of medical staffs as guided by International Commission of Radiological Protection (ICRP) (2001), International Atomic Energy Agency (IAEA) (2008) reports, World Health Organization (WHO), etc. However, the communication about radiation has now become also a task of the ordinary public under the present situation. For this, medical staffs are expected to play their role by acquiring the statistical literacy as well as with the radiological concept because the risk assessment accompanies the uncertainty. The author concludes that the risk communication is a problem of resolution to act, not of coping with. (T.T.)

  3. Nuclear training facilities at the Royal Naval College, Greenwich

    International Nuclear Information System (INIS)

    Head, J.L.; Lowther, C.A.; Marsh, J.R.W.

    1986-01-01

    The paper describes some of the nuclear training facilities at the Royal Naval College and the way the facilities are used in the training of personnel for the Naval nuclear propulsion programme. (author)

  4. The US nuclear science user facilities - 5276

    International Nuclear Information System (INIS)

    Kennedy, J.R.

    2015-01-01

    The primary mission of the NSUF (Nuclear Science User Facilities) is to provide access, at no cost to the researcher, to world-class, state-of-the art capabilities and expertise to advance nuclear science and technology through high impact research. Through the NSUF, nuclear energy researchers can access specialized and often unique and expensive equipment and facilities, as well as the accompanying expertise, including nuclear test reactors, ion beam accelerators, hot cell post-irradiation examination (PIE) equipment, synchrotron beam lines, and advanced radiologically qualified materials science PIE instrumentation. The NSUF can also support the design and fabrication of an irradiation experiment, the transport of that experiment to and from the reactor, the PIE activities, the analysis and interpretation of the data, and final material disposition. A special feature of the NSUF is its Sample Library of irradiated specimens made available to users that reduces investigation time and costs. Enhancing the Sample Library for future applications of advanced instrumentation and new ideas is a key goal of the NSUF. Similar to the effort on building a Sample Library, the NSUF is creating a searchable database of the infrastructure available to DOE-NE (Department Of Energy - Office of Nuclear Energy) supported researchers

  5. Nuclear power plant simulation facility evaluation methodology

    International Nuclear Information System (INIS)

    Haas, P.M.; Carter, R.J.; Laughery, K.R. Jr.

    1985-01-01

    A methodology for evaluation of nuclear power plant simulation facilities with regard to their acceptability for use in the US Nuclear Regulatory Commission (NRC) operator licensing exam is described. The evaluation is based primarily on simulator fidelity, but incorporates some aspects of direct operator/trainee performance measurement. The panel presentation and paper discuss data requirements, data collection, data analysis and criteria for conclusions regarding the fidelity evaluation, and summarize the proposed use of direct performance measurment. While field testing and refinement of the methodology are recommended, this initial effort provides a firm basis for NRC to fully develop the necessary methodology

  6. Management of tritium at nuclear facilities

    International Nuclear Information System (INIS)

    1984-01-01

    This report presents extending summaries of the works of the participants to an IAEA co-ordinated research programme, ''Handling Tritium - bearing effluents and wastes''. The subjects covered include production of tritium in nuclear power plants (mainly heavy water and light water reactors), as well as at reprocessing plants; removal and enrichment of tritium at nuclear facilities; conditioning methods and characteristics of immobilized tritium of low and high concentration; some potential methods of storage and disposal of tritium. In addition to the conclusions of this three-years work, possible activities in the field are recommended

  7. Case for one nuclear waste facility

    International Nuclear Information System (INIS)

    Colgate, S.A.

    1979-01-01

    There should be only one nuclear waste disposal facility, and that should be located adjacent to the Nevada Test Site where prior experience has demonstrated the relative impervious nature of bomb produced cavities. Federal dedication in perpetuity, security, management, experience, stratigraphy, and land values dictate the location. Proven natural mineral aqueous surface chemistry assures against radioactive migration. An additional level of assurance - stress engineering - a new technology, can be developed to mimic, far exceed, and then be applied retroactively, similar to the same phenomena occurring in underground nuclear explosions

  8. Performing a nuclear facility EMI audit

    International Nuclear Information System (INIS)

    White, D.R.J.

    1993-01-01

    This paper addresses several questions which may arise when performing a nuclear facility EMI audit. Among the issues addressed are how a nuclear electrical power plant can ensure that it has taken adequate EMC measures to protect it from hostile electromagnetic ambient environments, means by which these measures can be implemented with sufficient integrity and reliability, and how often an inspection or audit should be performed to assess the EMC measures. Means of assessing EMI hardening and effective control of aging effects are also discussed. 2 figs

  9. Sites with nuclear facilities in the state of dismantling and their future from the public perspective

    International Nuclear Information System (INIS)

    Kretz, Simon Philipp

    2015-01-01

    The thesis on the public perspective at sites of nuclear facility dismantling covers the following issues: the change of German energy landscapes under social and political points of view, theoretical frame of the work, combination of empirical studies and the theoretical approaches in a space concept, action model and hypotheses on the situation and development in communities with nuclear facilities in the state of dismantling, description of the interviewees, and the empirical results of the interviews.

  10. Nuclear facilities in the Federal Republic of Germany

    International Nuclear Information System (INIS)

    1991-01-01

    The information brochure is a survey of installed nuclear facilities in Germany, presenting on one page each a picture of a nuclear power plant together with the main relevant data, or of other type of nuclear facilities belonging to the nuclear fuel cycle (such as fuel production plant, fuel production plant, fuel element storage facilities, and facilities for spent fuel and waste management). (UA) [de

  11. Environmental radiation monitoring around the nuclear facilities

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Chang Woo; Choi, Geun Sik and others

    2001-02-01

    Environmental Radiation Monitoring was carried out with measurement of environment. Radiation and environmental radioactivity analysis around KAERI nuclear facilities and Seoul Research Reactor. The results of environmental radiation monitoring around KAERI nuclear facilities and Seoul Research Reactor are the follows : The average level of environmental radiation dose measured by NaI scintillation counter and accumulated radiation dose by TLD was almost same level compared with the past years. Gross {alpha}, {beta} radioactivity in environmental samples showed a environmental level. {gamma}-radionuclides in water samples were not detected. But only radionuclide K-40, which is natural radionuclide, was detected in the all samples and Cs-137 was detected in the surface soil and discharge sediment. The average level of environmental radiation dose around Seoul Research Reactor was almost same level compared with the past years, and Be-7 and Cs-137 were detected in some surface soil and discharge sediment by {gamma}-spectrometry.

  12. Environmental radiation monitoring around the nuclear facilities

    International Nuclear Information System (INIS)

    Lee, Chang Woo; Choi, Young Ho

    2000-02-01

    Environmental radiation monitoring was carried out with measurement of environment radiation and environmental radioactivity analysis around KAERI nuclear facilities and Seoul Research Reactor. The results of environmental radiation monitoring around KAERI nuclear facilities and Seoul Research Reactor are the follows: The average level of environmental radiation dose measured by NaI scintillation counter and accumulated radiation dose by TLD was almost some level compared with the past years. Gross α, β radioactivity in environmental samples showed a environmental level. γ-radionuclides in water sample were not detected. But only radionuclide K-40, which is natural radionuclide, was detected in the all samples and Cs-137 was detected in the surface soil and discharge sediment. The average level of environmental radiation dose around Seoul Research Reactor was almost same level compared with the past years, and Be-7 and Cs-137 were detected in some surface soil and discharge sediment by γ-spectrometry. (author)

  13. Industrial fans used in nuclear facilities

    International Nuclear Information System (INIS)

    Carlson, J.A.

    1987-01-01

    Industrial fans are widely used in nuclear facilities, and their most common use is in building ventilation. To control the spread of contamination, airflows are maintained at high levels. Therefore, the selection of the fan and fan control are important to the safety of people, equipment and the environment. As a result, 80% of all energy used in nuclear facilities is fan energy. Safety evolves from the durability, control and redundancy in the system. In new or retrofit installations, testing and qualification of fans and systems are completed prior to start-up. Less important but necessary is the energy conservation aspect of fan selection and installations. Fan efficiency, type of control and system installation are evaluated for energy use

  14. Environmental radiation monitoring around the nuclear facilities

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Chang Woo; Choi, Young Ho

    2000-02-01

    Environmental radiation monitoring was carried out with measurement of environment radiation and environmental radioactivity analysis around KAERI nuclear facilities and Seoul Research Reactor. The results of environmental radiation monitoring around KAERI nuclear facilities and Seoul Research Reactor are the follows: The average level of environmental radiation dose measured by NaI scintillation counter and accumulated radiation dose by TLD was almost some level compared with the past years. Gross {alpha}, {beta} radioactivity in environmental samples showed a environmental level. {gamma}-radionuclides in water sample were not detected. But only radionuclide K-40, which is natural radionuclide, was detected in the all samples and Cs-137 was detected in the surface soil and discharge sediment. The average level of environmental radiation dose around Seoul Research Reactor was almost same level compared with the past years, and Be-7 and Cs-137 were detected in some surface soil and discharge sediment by {gamma}-spectrometry. (author)

  15. Environmental radiation monitoring around the nuclear facilities

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Chang Woo; Choi, Young Ho; Lee, M.H. [and others

    1999-02-01

    Environmental radiation monitoring was carried out with measurement of environment radiation and environmental radioactivity analysis around KAERI nuclear facilities and Seoul research reactor. The results of environmental radiation monitoring around KAERI nuclear facilities and Seoul research reactor are the follows : The average level of environmental radiation dose measured by NaI scintillation counter and accumulated radiation dose by TLD was almost same level compared with the past years. Gross {alpha}, {beta} radioactivity in environmental samples showed a environmental level. {gamma}-radionuclides in water samples were not detected. But only radionuclide K-40, which is natural radionuclide, was detected in the all samples and Cs-137 was detected in the surface soil and discharge sediment. The average level of environmental radiation dose around Seoul research reactor was almost same level compared with the past years, and Be-7 and Cs-137 were detected in some surface soil and discharge sediment by {gamma}-spectrometry. (author). 3 refs., 50 tabs., 12 figs.

  16. Protection of nuclear facilities against outer aggressions

    International Nuclear Information System (INIS)

    Aussourd, P.; Candes, P.; Le Quinio, R.

    1976-01-01

    The various types of outer aggressions envisaged in safety analysis for nuclear facilities are reviewed. These outer aggressions are classified as natural and non-natural phenomena, the latter depending on the human activities in the vicinity of nuclear sites. The principal natural phenomena able to constitute aggressions are atmospheric phenomena (strong winds, snow storms, hail, frosting mists), hydrologie phenomena such as tides, surges, flood, low waters, and geologic phenomena such as earthquakes. Artificial phenomena are concerned with aircraft crashes, projectiles, fire, possible ruptures of dams, and intentional human aggressions. The protection against intentional human aggressions is of two sorts: first, the possibility of access to the installations mostly sensitive to sabotage are to be prevented or reduced, secondly redundant circuits and functions must be separated for preventing their simultaneous destruction in the case when sabotage actors have reach the core of the facility [fr

  17. Environmental radiation monitoring around the nuclear facilities

    International Nuclear Information System (INIS)

    Lee, Chang Woo; Choi, Geun Sik and others

    2001-02-01

    Environmental Radiation Monitoring was carried out with measurement of environment. Radiation and environmental radioactivity analysis around KAERI nuclear facilities and Seoul Research Reactor. The results of environmental radiation monitoring around KAERI nuclear facilities and Seoul Research Reactor are the follows : The average level of environmental radiation dose measured by NaI scintillation counter and accumulated radiation dose by TLD was almost same level compared with the past years. Gross α, β radioactivity in environmental samples showed a environmental level. γ-radionuclides in water samples were not detected. But only radionuclide K-40, which is natural radionuclide, was detected in the all samples and Cs-137 was detected in the surface soil and discharge sediment. The average level of environmental radiation dose around Seoul Research Reactor was almost same level compared with the past years, and Be-7 and Cs-137 were detected in some surface soil and discharge sediment by γ-spectrometry

  18. Present situation of occupational radiation exposure in nuclear power plants

    International Nuclear Information System (INIS)

    Imabori, Akira

    1979-01-01

    The present situation of the radiation exposure of workers, including both employes and subcontractors, in the nuclear power plants in Japan, is presented. Twenty seven nuclear power reactors in operation and under construction are tabulated with the name, the owner, the electric output and the commissioning year of each plant. The results of exposure of the workers in these plants are shown, classifying the dose rate into less than 0.5 rem, 0.5 - 1.5 rem, 1.5 - 2.5 rem, 2.5 - 5 rem and more than 5 rem, and the workers into employes and subcontractors. It is noted that the exposure dose of the subcontractors occupies about 88% of all exposure dose, and the exposure is concentrated during regular inspection period. The exposure dose of about 80% of the workers is less than 0.5 rem, and no one was irradiated more than 5 rem in a year. The total exposure dose, which has especially the tendency of increasing with extended maintenance period and decreasing during plant operation period, shows also the trend of increasing with the lapse of operation years. As for the point of view of whole exposure dose, the value is 0.06 -- 0.43 man-rem/10 6 kWh in 1976 FY. It is considered to be necessary to grasp the total exposure dose of each worker wandering from one plant to another, and the central registration center for the workers in radioactive environment was established in 1978. The whole exposure dose data of each worker are stored in the central computer in this center. This system is highly appreciated in radiation exposure management. The total exposure dose is related to the rate of utilization of nuclear plants, and it is expected to decrease with the decrease of plant outage. (Nakai, Y.)

  19. Air filters for use at nuclear facilities

    Energy Technology Data Exchange (ETDEWEB)

    Linder, P [Aktiebolaget Atomenergi, Studsvik, Nykoeping (Sweden)

    1970-12-01

    The ventilation system of a nuclear facility plays a vital role in ensuring that the air in working areas and the environment remains free from radioactive contamination. An earlier IAEA publication, Techniques for Controlling Air Pollution from the Operation of Nuclear Facilities, Safety Series No. 17, deals with the design and operation of ventilation systems at nuclear facilities. These systems are usually provided with air-cleaning devices which remove the contaminants from the air. This publication is intended as a guide to those who are concerned with the design of air-filtering systems and with the testing, operation and maintenance of air-filter installations at nuclear facilities. Emphasis is mainly placed on so-called high-efficiency particulate air filters (HEPA filters) and on providing general information on them. Besides describing the usual filter types, their dimensions and construction materials, the guidebook attempts to explain their properties and behaviour under different operating conditions. It also gives advice on testing and handling the filters so that effective and safe performance is ensured. The guidebook should serve as an introduction to the use of high efficiency particulate air filters in countries where work with radioactive materials has only recently commenced. The list of references at the end of the book indicates sources of more advanced information for those who already have comprehensive experience in this field. It is assumed here that the filters are obtained from a manufacturer, and the guidebook thus contains no information on the design and development of the filter itself, nor does it deal with the cleaning of the intake air to a plant, with gas sorption or protective respiratory equipment.

  20. Computer codes for ventilation in nuclear facilities

    International Nuclear Information System (INIS)

    Mulcey, P.

    1987-01-01

    In this paper the authors present some computer codes, developed in the last years, for ventilation and radioprotection. These codes are used for safety analysis in the conception, exploitation and dismantlement of nuclear facilities. The authors present particularly: DACC1 code used for aerosol deposit in sampling circuit of radiation monitors; PIAF code used for modelization of complex ventilation system; CLIMAT 6 code used for optimization of air conditioning system [fr

  1. Air filters for use at nuclear facilities

    International Nuclear Information System (INIS)

    Linder, P.

    1970-01-01

    The ventilation system of a nuclear facility plays a vital role in ensuring that the air in working areas and the environment remains free from radioactive contamination. An earlier IAEA publication, Techniques for Controlling Air Pollution from the Operation of Nuclear Facilities, Safety Series No. 17, deals with the design and operation of ventilation systems at nuclear facilities. These systems are usually provided with air-cleaning devices which remove the contaminants from the air. This publication is intended as a guide to those who are concerned with the design of air-filtering systems and with the testing, operation and maintenance of air-filter installations at nuclear facilities. Emphasis is mainly placed on so-called high-efficiency particulate air filters (HEPA filters) and on providing general information on them. Besides describing the usual filter types, their dimensions and construction materials, the guidebook attempts to explain their properties and behaviour under different operating conditions. It also gives advice on testing and handling the filters so that effective and safe performance is ensured. The guidebook should serve as an introduction to the use of high efficiency particulate air filters in countries where work with radioactive materials has only recently commenced. The list of references at the end of the book indicates sources of more advanced information for those who already have comprehensive experience in this field. It is assumed here that the filters are obtained from a manufacturer, and the guidebook thus contains no information on the design and development of the filter itself, nor does it deal with the cleaning of the intake air to a plant, with gas sorption or protective respiratory equipment

  2. Cathodic protection of a nuclear fuel facility

    International Nuclear Information System (INIS)

    Corbett, R.A.

    1989-01-01

    This article discusses corrosion on buried process piping and tanks at a nuclear fuel facility and the steps taken to design a system to control underground corrosion. Collected data have indicated that cathodic protection is needed to supplement the regular use of high-integrity, corrosion-resistant coatings; wrapping systems; special backfills; and insulation material. The technical approach discussed in this article is generally applicable to other types of power and/or industrial plants with extensive networks of underground steel piping

  3. Decommissioning engineering systems for nuclear facilities and knowledge inheritance for decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    Tachibana, Mitsuo

    2016-01-01

    Information on construction, operation and maintenance of a nuclear facility is essential in order to plan and implement the decommissioning of the nuclear facility. A decommissioning engineering system collects these information efficiently, retrieves necessary information rapidly, and support to plan the reasonable decommissioning as well as the systematic implementation of dismantling activities. Then, knowledge of workers involved facility operation and dismantling activities is important because decommissioning of nuclear facility will be carried out for a long period. Knowledge inheritance for decommissioning has been carried out in various organizations. This report describes an outline of and experiences in applying decommissioning engineering systems in JAEA and activities related to knowledge inheritance for decommissioning in some organizations. (author)

  4. Nuclear safety and radiation protection report of the Bugey nuclear facilities - 2013

    International Nuclear Information System (INIS)

    2014-01-01

    This safety report was established in accordance with articles L. 125-15 and L. 125-16 of the French environmental code. It presents, first, the facilities (INBs no. 78, 89 (NPPs in operation), 465 (NPP under deconstruction), 102 (fuel storage facility), and 173 (radioactive waste conditioning and storage facility under construction)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2013, if any, are reported as well as the radioactive and non-radioactive effluents discharge in the environment. Finally, the radioactive materials and wastes generated by the facility are presented (type of waste, quantities, conditioning process). The document concludes with a presentation of the actions of communication and public information made by the direction of the facility. A glossary and the list of recommendations from the Committees for health, safety and working conditions are given in appendix

  5. Nuclear safety and radiation protection report of the Bugey nuclear facilities - 2014

    International Nuclear Information System (INIS)

    2015-01-01

    This safety report was established in accordance with articles L. 125-15 and L. 125-16 of the French environmental code. It presents, first, the facilities (INBs no. 78, 89 (NPPs in operation), 465 (NPP under deconstruction), 102 (fuel storage facility), and 173 (radioactive waste conditioning and storage facility under construction)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2014, if any, are reported as well as the radioactive and non-radioactive effluents discharge in the environment. Finally, the radioactive materials and wastes generated by the facility are presented (type of waste, quantities, conditioning process). The document concludes with a presentation of the actions of communication and public information made by the direction of the facility. A glossary and the list of recommendations from the Committees for health, safety and working conditions are given in appendix

  6. ERC Maintenance Implementation Plan for nuclear facilities

    International Nuclear Information System (INIS)

    Franquero, R.C.

    1997-05-01

    The inactive and surplus facilities assigned to the Environmental Restoration Contractor are shut down and have no operating production processes or production materials except for residual contamination. There is a minimal number of operating systems to support surveillance and maintenance or decontamination and decommissioning activities (D ampersand D). These systems may include heating and ventilation, air conditioning, lighting, and other electrical systems. Inactive and surplus facilities will be subject to periodic long-term surveillance to ensure the integrity of structures until D ampersand D. D ampersand D projects are of relatively short duration and end with all systems deactivated. Therefore, a rigorous in-depth maintenance program such as that required for producing nuclear facilities is not required or cost effective

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

    International Nuclear Information System (INIS)

    2014-07-01

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

  8. Nuclear facility decommissioning and site remedial actions

    International Nuclear Information System (INIS)

    Knox, N.P.; Webb, J.R.; Ferguson, S.D.; Goins, L.F.; Owen, P.T.

    1990-09-01

    The 394 abstracted references on environmental restoration, nuclear facility decommissioning, uranium mill tailings management, and site remedial actions constitute the eleventh in a series of reports prepared annually for the US Department of Energy's Remedial Action Programs. Citations to foreign and domestic literature of all types -- technical reports, progress reports, journal articles, symposia proceedings, theses, books, patents, legislation, and research project descriptions -- have been included. The bibliography contains scientific, technical, economic, regulatory, and legal information pertinent to the US Department of Energy's Remedial Action Programs. Major sections are (1) Surplus Facilities Management Program, (2) Nuclear Facilities Decommissioning, (3) Formerly Utilized Sites Remedial Action Programs, (4) Facilities Contaminated with Naturally Occurring Radionuclides, (5) Uranium Mill Tailings Remedial Action Program, (6) Grand Junction Remedial Action Program, (7) Uranium Mill Tailings Management, (8) Technical Measurements Center, (9) Remedial Action Program, and (10) Environmental Restoration Program. Within these categories, references are arranged alphabetically by first author. Those references having no individual author are listed by corporate affiliation or by publication title. Indexes are provided for author, corporate affiliation, title word, publication description, geographic location, subject category, and keywords. This report is a product of the Remedial Action Program Information Center (RAPIC), which selects and analyzes information on remedial actions and relevant radioactive waste management technologies

  9. Nuclear facility decommissioning and site remedial actions

    Energy Technology Data Exchange (ETDEWEB)

    Knox, N.P.; Webb, J.R.; Ferguson, S.D.; Goins, L.F.; Owen, P.T.

    1990-09-01

    The 394 abstracted references on environmental restoration, nuclear facility decommissioning, uranium mill tailings management, and site remedial actions constitute the eleventh in a series of reports prepared annually for the US Department of Energy's Remedial Action Programs. Citations to foreign and domestic literature of all types -- technical reports, progress reports, journal articles, symposia proceedings, theses, books, patents, legislation, and research project descriptions -- have been included. The bibliography contains scientific, technical, economic, regulatory, and legal information pertinent to the US Department of Energy's Remedial Action Programs. Major sections are (1) Surplus Facilities Management Program, (2) Nuclear Facilities Decommissioning, (3) Formerly Utilized Sites Remedial Action Programs, (4) Facilities Contaminated with Naturally Occurring Radionuclides, (5) Uranium Mill Tailings Remedial Action Program, (6) Grand Junction Remedial Action Program, (7) Uranium Mill Tailings Management, (8) Technical Measurements Center, (9) Remedial Action Program, and (10) Environmental Restoration Program. Within these categories, references are arranged alphabetically by first author. Those references having no individual author are listed by corporate affiliation or by publication title. Indexes are provided for author, corporate affiliation, title word, publication description, geographic location, subject category, and keywords. This report is a product of the Remedial Action Program Information Center (RAPIC), which selects and analyzes information on remedial actions and relevant radioactive waste management technologies.

  10. Nuclear facility decommissioning and site remedial actions

    International Nuclear Information System (INIS)

    Owen, P.T.; Knox, N.P.; Ferguson, S.D.; Fielden, J.M.; Schumann, P.L.

    1989-09-01

    The 576 abstracted references on nuclear facility decommissioning, uranium mill tailings management, and site remedial actions constitute the tenth in a series of reports prepared annually for the US Department of Energy's Remedial Action Programs. Citations to foreign and domestic literature of all types--technical reports, progress reports, journal articles, symposia proceedings, theses, books, patents, legislation, and research project descriptions--have been included. The bibliography contains scientific, technical, economic, regulatory, and legal information pertinent to the US Department of Energy's Remedial Action Programs. Major sections are (1) Surplus Facilities Management Program, (2) Nuclear Facilities Decommissioning, (3) Formerly Utilized Sites Remedial Action Program, (4) Facilities Contaminated with Naturally Occurring Radionuclides, (5) Uranium Mill Tailings Remedial Action Program, (6) Uranium Mill Tailings Management, (7) Technical Measurements Center, and (8) General Remedial Action Program Studies. Within these categories, references are arranged alphabetically by first author. Those references having no individual author are listed by corporate affiliation or by publication description. Indexes are provided for author, corporate affiliation, title work, publication description, geographic location, subject category, and keywords

  11. Nuclear facility decommissioning and site remedial actions

    Energy Technology Data Exchange (ETDEWEB)

    Owen, P.T.; Knox, N.P.; Ferguson, S.D.; Fielden, J.M.; Schumann, P.L.

    1989-09-01

    The 576 abstracted references on nuclear facility decommissioning, uranium mill tailings management, and site remedial actions constitute the tenth in a series of reports prepared annually for the US Department of Energy's Remedial Action Programs. Citations to foreign and domestic literature of all types--technical reports, progress reports, journal articles, symposia proceedings, theses, books, patents, legislation, and research project descriptions--have been included. The bibliography contains scientific, technical, economic, regulatory, and legal information pertinent to the US Department of Energy's Remedial Action Programs. Major sections are (1) Surplus Facilities Management Program, (2) Nuclear Facilities Decommissioning, (3) Formerly Utilized Sites Remedial Action Program, (4) Facilities Contaminated with Naturally Occurring Radionuclides, (5) Uranium Mill Tailings Remedial Action Program, (6) Uranium Mill Tailings Management, (7) Technical Measurements Center, and (8) General Remedial Action Program Studies. Within these categories, references are arranged alphabetically by first author. Those references having no individual author are listed by corporate affiliation or by publication description. Indexes are provided for author, corporate affiliation, title work, publication description, geographic location, subject category, and keywords.

  12. Radioactive waste management from nuclear facilities

    International Nuclear Information System (INIS)

    2005-06-01

    This report has been published as a NSA (Nuclear Systems Association, Japan) commentary series, No. 13, and documents the present status on management of radioactive wastes produced from nuclear facilities in Japan and other countries as well. Risks for radiation accidents coming from radioactive waste disposal and storage together with risks for reactor accidents from nuclear power plants are now causing public anxiety. This commentary concerns among all high-level radioactive waste management from nuclear fuel cycle facilities, with including radioactive wastes from research institutes or hospitals. Also included is wastes produced from reactor decommissioning. For low-level radioactive wastes, the wastes is reduced in volume, solidified, and removed to the sites of storage depending on their radioactivities. For high-level radioactive wastes, some ten thousand years must be necessary before the radioactivity decays to the natural level and protection against seismic or volcanic activities, and terrorist attacks is unavoidable for final disposals. This inevitably results in underground disposal at least 300 m below the ground. Various proposals for the disposal and management for this and their evaluation techniques are described in the present document. (S. Ohno)

  13. Improvement of management systems for nuclear facilities

    International Nuclear Information System (INIS)

    2005-01-01

    The area of Quality Management/ Quality Assurance has been changed dramatically over the past years. The nuclear facilities moved from the 'traditional' Quality Assurance approach towards Quality Management Systems, and later a new concept of Integrated Management Systems was introduced. The IAEA is developing a new set of Standards on Integrated Management Systems, which will replace the current 50-C-Q/SG-Q1-Q14 Code. The new set of document will require the integration of all management areas into one coherent management system. The new set of standards on Management Systems promotes the concept of the Integrated Management Systems. Based on new set a big number of documents are under preparation. These documents will address the current issues in the management systems area, e.g. Management of Change, Continuous Improvement, Self-assessment, and Attributes of effective management, etc. Currently NPES is providing a number of TC projects and Extra Budgetary Programmes to assist Member States in this area. The new Standards on Management Systems will be published in 2006. A number of Regulatory bodies already indicated that they would take the new Management System Standards as a basis for the national regulation. This fact will motivate a considerable change in the management of nuclear utilities, requiring a new approach. This activity is suitable for all IAEA Members States with large or limited nuclear capabilities. The service is directed to provide assistance for the management of all organizations carrying on or regulating nuclear activities and facilities

  14. The situation of the nuclear energy in the world

    International Nuclear Information System (INIS)

    Souza, Jair Albo Marques de

    1996-12-01

    This work presents an overview of the nuclear energy in the world. It approaches the following main topics: kinds of nuclear power plants; operation experience of the nuclear plants; environmental and social aspects of the nuclear energy; economic aspects of the nuclear energy; development of the reactors technology and supply of the nuclear fuel

  15. Emergency planning and preparedness for nuclear facilities

    International Nuclear Information System (INIS)

    1986-01-01

    In order to review the advances made over the past seven years in the area of emergency planning and preparedness supporting nuclear facilities and consider developments which are on the horizon, the IAEA at the invitation of the Government of Italy, organized this International Symposium in co-operation with the Italian Commission for Nuclear and Alternative Energy Sources, Directorate of Nuclear Safety and Health Protection (ENEA-DISP). There were over 250 designated participants and some 70 observers from 37 Member States and four international organizations in attendance at the Symposium. The Symposium presentations were divided into sessions devoted to the following topics: emergency planning (20 papers), accident assessment (30 papers), protective measures and recovery operations (10 papers) and emergency preparedness (16 papers). A separate abstract was prepared for each of these papers

  16. Study on Nuclear Facility Cyber Security Awareness and Training Programs

    International Nuclear Information System (INIS)

    Lee, Jung-Woon; Song, Jae-Gu; Lee, Cheol-Kwon

    2016-01-01

    Cyber security awareness and training, which is a part of operational security controls, is defined to be implemented later in the CSP implementation schedule. However, cyber security awareness and training is a prerequisite for the appropriate implementation of a cyber security program. When considering the current situation in which it is just started to define cyber security activities and to assign personnel who has responsibilities for performing those activities, a cyber security awareness program is necessary to enhance cyber security culture for the facility personnel to participate positively in cyber security activities. Also before the implementation of stepwise CSP, suitable education and training should be provided to both cyber security teams (CST) and facility personnel who should participate in the implementation. Since such importance and urgency of cyber security awareness and training is underestimated at present, the types, trainees, contents, and development strategies of cyber security awareness and training programs are studied to help Korean nuclear facilities to perform cyber security activities more effectively. Cyber security awareness and training programs should be developed ahead of the implementation of CSP. In this study, through the analysis of requirements in the regulatory standard RS-015, the types and trainees of overall cyber security training programs in nuclear facilities are identified. Contents suitable for a cyber security awareness program and a technical training program are derived. It is suggested to develop stepwise the program contents in accordance with the development of policies, guides, and procedures as parts of the facility cyber security program. Since any training programs are not available for the specialized cyber security training in nuclear facilities, a long-term development plan is necessary. As alternatives for the time being, several cyber security training courses for industrial control systems by

  17. Study on Nuclear Facility Cyber Security Awareness and Training Programs

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Jung-Woon; Song, Jae-Gu; Lee, Cheol-Kwon [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2016-10-15

    Cyber security awareness and training, which is a part of operational security controls, is defined to be implemented later in the CSP implementation schedule. However, cyber security awareness and training is a prerequisite for the appropriate implementation of a cyber security program. When considering the current situation in which it is just started to define cyber security activities and to assign personnel who has responsibilities for performing those activities, a cyber security awareness program is necessary to enhance cyber security culture for the facility personnel to participate positively in cyber security activities. Also before the implementation of stepwise CSP, suitable education and training should be provided to both cyber security teams (CST) and facility personnel who should participate in the implementation. Since such importance and urgency of cyber security awareness and training is underestimated at present, the types, trainees, contents, and development strategies of cyber security awareness and training programs are studied to help Korean nuclear facilities to perform cyber security activities more effectively. Cyber security awareness and training programs should be developed ahead of the implementation of CSP. In this study, through the analysis of requirements in the regulatory standard RS-015, the types and trainees of overall cyber security training programs in nuclear facilities are identified. Contents suitable for a cyber security awareness program and a technical training program are derived. It is suggested to develop stepwise the program contents in accordance with the development of policies, guides, and procedures as parts of the facility cyber security program. Since any training programs are not available for the specialized cyber security training in nuclear facilities, a long-term development plan is necessary. As alternatives for the time being, several cyber security training courses for industrial control systems by

  18. An international contribution to decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    Lazo, T.

    1995-01-01

    Nuclear power plants and fuel cycle facilities must be retired from service when they have completed their design objective, become obsolete or when they no longer fulfill current safety, technical or economic requirements. Decommissioning is defined as the set of technical and administrative operations that provides adequate protection of workers and public against radiation risks, minimizes impact on the environment and involves manageable costs. A traditional definition of the stages of decommissioning has been proposed by the IAEA and is largely used worldwide. A number of factors have to be considered when selecting the optimum strategy, which include the national nuclear policy, characteristics of the facility, health and safety, environmental protection, radioactive waste management, future use of the site, improvements of the technology that may be achieved in the future, costs and availability of funds and various social considerations. The paper describes the current situation of nuclear facilities and the associated forthcoming requirements and problems of decommissioning. This task requires a complete radionuclide inventory, decontamination methods, disassembly techniques and remote operations. Radiation safety presents three aspects: nuclear safety, protection of workers and protection of the public. An appropriate delay to initiate decommissioning after shutdown of a facility may considerably reduce workers exposures and costs. Decommissioning also generates significant quantities of neutron-activated and surface contaminated materials which require a specific management. A vigorous international cooperation and coordinated research programs have been encouraged by the NEA for a minimization of costs and efforts and to provide a basis for consensus of opinions on policies, strategies and criteria. (J.S.). 19 refs., 5 figs., 3 tabs

  19. New nuclear facilities and their analytical applications in China

    International Nuclear Information System (INIS)

    Zhang, Z.Y.; He, X.; Ma, Y.H.; Ding, Y.Y.; Chai, Z.F.

    2014-01-01

    Nuclear analytical techniques are a family of modern analytical methods that are based on nuclear reactions, nuclear effects, nuclear radiations, nuclear spectroscopy, nuclear parameters, and nuclear facilities. Because of their combined characteristics of sensitivity and selectivity, they are widely used in projects ranging from life sciences to deep-space exploration. In this review article, new nuclear facilities and their analytical applications in China are selectively reviewed, covering the following aspects: large scientific facilities, national demands, and key scientific issues with the emphasis on the new achievements. (orig.)

  20. Nuclear safety and radiation protection report of the Gravelines nuclear facilities - 2013

    International Nuclear Information System (INIS)

    2014-01-01

    This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Gravelines nuclear power plant (INB 96, 97 and 122, Nord (FR)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2013, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, the radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions

  1. Nuclear safety and radiation protection report of the Tricastin nuclear facility (BCOT) - 2011

    International Nuclear Information System (INIS)

    2012-01-01

    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 2011, if some, are reported as well as the effluents discharge in the environment. Finally, the management of the radioactive materials and wastes generated by the facility is presented and sorted by type of waste, quantities and type of conditioning. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

  2. Nuclear safety and radiation protection report of the Fessenheim nuclear facilities - 2011

    International Nuclear Information System (INIS)

    2012-01-01

    This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Fessenheim nuclear power plant (INB 75, Haut-Rhin, 68 (FR)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2011, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

  3. Nuclear safety and radiation protection report of the Cattenom nuclear facilities - 2011

    International Nuclear Information System (INIS)

    2012-01-01

    This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Cattenom nuclear power plant (INB 124, 125, 126 and 137, Moselle (FR)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2011, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise, microbial proliferation in cooling towers) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

  4. Nuclear safety and radiation protection report of the Saint-Laurent-des-Eaux nuclear facilities - 2011

    International Nuclear Information System (INIS)

    2012-01-01

    This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Saint-Laurent-des-Eaux nuclear power plant (Saint-Laurent-Nouan (FR)): 2 partially dismantled graphite-gas reactors and a graphite sleeves storage silo (INB 46 and 74), and 2 PWR reactors in operation (INB 100). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2011, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise, microbial proliferation in cooling towers) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

  5. Nuclear safety and radiation protection report of the Saint-Laurent-des-Eaux nuclear facilities - 2010

    International Nuclear Information System (INIS)

    2011-06-01

    This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Saint-Laurent-des-Eaux nuclear power plant (Saint-Laurent-Nouan (FR)): 2 partially dismantled graphite-gas reactors and a graphite sleeves storage silo (INB 46 and 74), and 2 PWR reactors in operation (INB 100). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2010, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise, microbial proliferation in cooling towers) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

  6. Nuclear safety and radiation protection report of the CNPE EDF nuclear facilities of Tricastin - 2011

    International Nuclear Information System (INIS)

    2012-01-01

    This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Tricastin nuclear power plant (INB 87 and 88, Saint-Paul-Trois-Chateaux, Drome (FR)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2011, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

  7. Nuclear safety and radiation protection report of the Gravelines nuclear facilities - 2010

    International Nuclear Information System (INIS)

    2011-06-01

    This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Gravelines nuclear power plant (INB 96, 97 and 122, Nord (FR)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2010, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

  8. Nuclear safety and radiation protection report of the Penly nuclear facilities - 2010

    International Nuclear Information System (INIS)

    2011-06-01

    This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Penly nuclear power plant (INB 136 and 140, Seine-Maritime, 76 (FR)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2010, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

  9. Nuclear safety and radiation protection report of the Fessenheim nuclear facilities - 2010

    International Nuclear Information System (INIS)

    2011-06-01

    This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Fessenheim nuclear power plant (INB 75, Haut-Rhin, 68 (FR)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2010, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

  10. Nuclear safety and radiation protection report of the Chooz nuclear facilities - 2011

    International Nuclear Information System (INIS)

    2012-01-01

    This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Chooz nuclear power plant (Ardennes (FR)): 2 PWR reactors in operation (Chooz B, INB 139 and 144) and one partially dismantled PWR reactor (Chooz A, INB 163). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2011, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise, microbial proliferation in cooling towers) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary followed by the viewpoint of the Committees for health, safety and working conditions. (J.S.)

  11. Nuclear safety and radiation protection report of the Blayais nuclear facilities - 2011

    International Nuclear Information System (INIS)

    2012-01-01

    This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Blayais nuclear power plant (INB 86 and 110, Gironde (FR)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2011, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

  12. Nuclear safety and radiation protection report of the Nogent-sur-Seine nuclear facilities - 2011

    International Nuclear Information System (INIS)

    2012-01-01

    This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Nogent-sur-Seine nuclear power plant (INB 129 and 130, Aube (FR)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2011, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise, microbial proliferation in cooling towers) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

  13. Nuclear safety and radiation protection report of the Cruas-Meysse nuclear facilities - 2011

    International Nuclear Information System (INIS)

    2012-01-01

    This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Cruas-Meysse nuclear power plant (INB 111 and 112, Ardeche (FR)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2011, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise, microbial proliferation in cooling towers) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

  14. Nuclear safety and radiation protection report of the Gravelines nuclear facilities - 2011

    International Nuclear Information System (INIS)

    2012-01-01

    This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Gravelines nuclear power plant (INB 96, 97 and 122, Nord (FR)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2011, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

  15. Nuclear safety and radiation protection report of the Paluel nuclear facilities - 2010

    International Nuclear Information System (INIS)

    2011-01-01

    This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Paluel nuclear power plant (INB no. 103 - Paluel 1, no. 104 - Paluel 2, no. 114 - Paluel 3 and no. 115 - Paluel 4, Cany-Barville - Seine-Maritime (FR)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities. The incidents and accidents which occurred in 2010, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document ends with a glossary and no recommendation from the Committees for health, safety and working conditions. (J.S.)

  16. Nuclear safety and radiation protection report of the Paluel nuclear facilities - 2011

    International Nuclear Information System (INIS)

    2012-01-01

    This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Paluel nuclear power plant (INB no. 103 - Paluel 1, no. 104 - Paluel 2, no. 114 - Paluel 3 and no. 115 - Paluel 4, Cany-Barville - Seine-Maritime (FR)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities. The incidents and accidents which occurred in 2011, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

  17. Nuclear safety and radiation protection report of the Dampierre-en-Burly nuclear facilities - 2011

    International Nuclear Information System (INIS)

    2012-01-01

    This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Dampierre-en-Burly nuclear power plant (INB 84 and 85, Loiret, 45 (FR)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2011, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise, microbial proliferation in cooling towers) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

  18. Nuclear safety and radiation protection report of the Gravelines nuclear facilities - 2012

    International Nuclear Information System (INIS)

    2013-01-01

    This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Gravelines nuclear power plant (INB 96, 97 and 122, Nord (FR)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2012, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions

  19. Nuclear safety and radiation protection report of the Golfech nuclear facilities - 2011

    International Nuclear Information System (INIS)

    2012-01-01

    This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Golfech nuclear power plant (INB 135 and 142, Tarn-et-Garonne (FR)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2011, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise, microbial proliferation in cooling towers) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

  20. Nuclear safety and radiation protection report of the Penly nuclear facilities - 2011

    International Nuclear Information System (INIS)

    2012-01-01

    This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Penly nuclear power plant (INB 136 and 140, Seine-Maritime, 76 (FR)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2011, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

  1. Nuclear safety and radiation protection report of the Cruas-Meysse nuclear facilities - 2010

    International Nuclear Information System (INIS)

    2011-06-01

    This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Cruas-Meysse nuclear power plant (INB 111 and 112, Ardeche (FR)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2010, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise, microbial proliferation in cooling towers) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

  2. Nuclear safety and radiation protection report of the Gravelines nuclear facilities - 2014

    International Nuclear Information System (INIS)

    2015-01-01

    This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Gravelines nuclear power plant (INB 96, 97 and 122, Nord (FR)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2014, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions

  3. Nuclear safety and radiation protection report of the Civaux nuclear facilities - 2011

    International Nuclear Information System (INIS)

    2012-01-01

    This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Civaux nuclear power plant (INB 158 and 159, Vienne (FR)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2011, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise, microbial proliferation in cooling towers) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

  4. Nuclear safety and radiation protection report of the Blayais nuclear facilities - 2010

    International Nuclear Information System (INIS)

    2011-06-01

    This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Blayais nuclear power plant (INB 86 and 110, Gironde (FR)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2010, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

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

    International Nuclear Information System (INIS)

    2014-01-01

    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

  6. Nuclear safety and radiation protection report of the Dampierre-en-Burly nuclear facilities - 2010

    International Nuclear Information System (INIS)

    2011-06-01

    This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Dampierre-en-Burly nuclear power plant (INB 84 and 85, Loiret, 45 (FR)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2010, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise, microbial proliferation in cooling towers) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

  7. Nuclear safety and radiation protection report of the nuclear facilities - 2014

    International Nuclear Information System (INIS)

    2015-01-01

    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 2014, 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

  8. Nuclear safety and radiation protection report of the Cattenom nuclear facilities - 2010

    International Nuclear Information System (INIS)

    2011-06-01

    This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Cattenom nuclear power plant (INB 124, 125, 126 and 137, Moselle (FR)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2010, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise, microbial proliferation in cooling towers) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

  9. Nuclear safety and radiation protection report of the Saint-Alban-Saint-Maurice nuclear facilities - 2011

    International Nuclear Information System (INIS)

    2012-01-01

    This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Saint-Alban-Saint-Maurice nuclear power plant (INB 119 and 120, Isere (FR)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2011, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

  10. Nuclear safety and radiation protection report of the Nogent-sur-Seine nuclear facilities - 2010

    International Nuclear Information System (INIS)

    2011-06-01

    This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Nogent-sur-Seine nuclear power plant (INB 129 and 130, Aube (FR)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2010, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise, microbial proliferation in cooling towers) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

  11. Nuclear safety and radiation protection report of the Belleville-sur-Loire nuclear facilities - 2011

    International Nuclear Information System (INIS)

    2012-01-01

    This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Belleville-sur-Loire nuclear power plant (INB no. 127 - Belleville 1 and no. 128 - Belleville 2, Belleville-sur-Loire and Sury-pres-Lere - Cher (FR)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities. The incidents and accidents which occurred in 2011, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise, microbial proliferation in cooling towers) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

  12. Nuclear safety and radiation protection report of the Civaux nuclear facilities - 2010

    International Nuclear Information System (INIS)

    2011-06-01

    This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Civaux nuclear power plant (INB 158 and 159, Vienne (FR)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2010, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise, microbial proliferation in cooling towers) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

  13. Nuclear safety and radiation protection report of the Saint-Alban-Saint-Maurice nuclear facilities - 2010

    International Nuclear Information System (INIS)

    2011-06-01

    This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Saint-Alban-Saint-Maurice nuclear power plant (INB 119 and 120, Isere (FR)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2010, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

  14. Nuclear safety and radiation protection report of the Golfech nuclear facilities - 2010

    International Nuclear Information System (INIS)

    2011-06-01

    This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Golfech nuclear power plant (INB 135 and 142, Tarn-et-Garonne (FR)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2010, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise, microbial proliferation in cooling towers) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

  15. Nuclear safety and radiation protection report of the Flamanville nuclear facilities - 2011

    International Nuclear Information System (INIS)

    2012-01-01

    This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Flamanville nuclear power plant (Manche (FR)): 2 PWR reactors in operation (INB 108 and 109), and 1 PWR under construction (Flamanville 3, INB 167). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2011, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise, water consumption and waste management at Flamanville 3 construction site) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

  16. Nuclear safety and radiation protection report of the Flamanville nuclear facilities - 2010

    International Nuclear Information System (INIS)

    2011-06-01

    This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Flamanville nuclear power plant (Manche (FR)): 2 PWR reactors in operation (INB 108 and 109), and 1 PWR under construction (Flamanville 3, INB 167). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2010, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise, water consumption and waste management at Flamanville 3 construction site) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

  17. Nuclear safety and radiation protection report of the Chooz nuclear facilities - 2010

    International Nuclear Information System (INIS)

    2011-06-01

    This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Chooz nuclear power plant (Ardennes (FR)): 2 PWR reactors in operation (Chooz B, INB 139 and 144) and one partially dismantled PWR reactor (Chooz A, INB 163). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2010, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise, microbial proliferation in cooling towers) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

  18. Financing Strategies for Nuclear Fuel Cycle Facility

    International Nuclear Information System (INIS)

    David Shropshire; Sharon Chandler

    2005-01-01

    To help meet our nation's energy needs, reprocessing of spent nuclear fuel is being considered more and more as a necessary step in a future nuclear fuel cycle, but incorporating this step into the fuel cycle will require considerable investment. This report presents an evaluation of financing scenarios for reprocessing facilities integrated into the nuclear fuel cycle. A range of options, from fully government owned to fully private owned, was evaluated using a DPL (Dynamic Programming Language) 6.0 model, which can systematically optimize outcomes based on user-defined criteria (e.g., lowest life-cycle cost, lowest unit cost). Though all business decisions follow similar logic with regard to financing, reprocessing facilities are an exception due to the range of financing options available. The evaluation concludes that lowest unit costs and lifetime costs follow a fully government-owned financing strategy, due to government forgiveness of debt as sunk costs. Other financing arrangements, however, including regulated utility ownership and a hybrid ownership scheme, led to acceptable costs, below the Nuclear Energy Agency published estimates. Overwhelmingly, uncertainty in annual capacity led to the greatest fluctuations in unit costs necessary for recovery of operating and capital expenditures; the ability to determine annual capacity will be a driving factor in setting unit costs. For private ventures, the costs of capital, especially equity interest rates, dominate the balance sheet; the annual operating costs dominate the government case. It is concluded that to finance the construction and operation of such a facility without government ownership could be feasible with measures taken to mitigate risk, and that factors besides unit costs should be considered (e.g., legal issues, social effects, proliferation concerns) before making a decision on financing strategy

  19. Nuclear right and South Market Common : health citizen protection and environment: comparative study Mercosur situation:critical analysis Uruguay situation

    International Nuclear Information System (INIS)

    Puig, D

    1998-01-01

    The present work presents to general study on: the applications of nuclear techniques, technical fundamental for stablishment of to program of radiation protection, to comparative study legislation in radiation protection in the South Market Common (MERCOSUR)Argentina,Brazil,Paraguay,Uruguay as well as Treaties and Agreements. The author carries out a critical analysis from the situation to Institutional level in the Uruguay and it outlines some alternatives to improve the situation [es

  20. Nuclear safety and radiation protection report of the Chinon nuclear facilities - 2014

    International Nuclear Information System (INIS)

    2015-01-01

    This safety report was established in accordance with articles L. 125-15 and L. 125-16 of the French environmental code. It presents, first, the facilities (INBs no. 94 (irradiated materials workshop), 99 (fuel storage facility), 107 and 132 (NPPs in operation), 133, 153 and 161 (NPPs under deconstruction)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2014, if any, are reported as well as the radioactive and non-radioactive effluents discharge in the environment. Finally, the radioactive materials and wastes generated by the facility are presented (type of waste, quantities, conditioning process). The document concludes with a presentation of the actions of communication and public information made by the direction of the facility. A glossary and the list of recommendations from the Committees for health, safety and working conditions are given in appendix

  1. Nuclear safety and radiation protection report of Chinon nuclear facilities - 2012

    International Nuclear Information System (INIS)

    2013-01-01

    This safety report was established in accordance with articles L. 125-15 and L. 125-16 of the French environmental code. It presents, first, the facilities (INBs no. 94 (irradiated materials workshop), 99 (fuel storage facility), 107 and 132 (NPPs in operation), 133, 153 and 161 (NPPs under deconstruction)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2012, if any, are reported as well as the radioactive and non-radioactive effluents discharge in the environment. Finally, the radioactive materials and wastes generated by the facility are presented (type of waste, quantities, conditioning process). The document concludes with a presentation of the actions of communication and public information made by the direction of the facility. A glossary and the list of recommendations from the Committees for health, safety and working conditions are given in appendix. (J.S.)

  2. Nuclear safety and radiation protection report of the Chinon nuclear facilities - 2013

    International Nuclear Information System (INIS)

    2014-01-01

    This safety report was established in accordance with articles L. 125-15 and L. 125-16 of the French environmental code. It presents, first, the facilities (INBs no. 94 (irradiated materials workshop), 99 (fuel storage facility), 107 and 132 (NPPs in operation), 133, 153 and 161 (NPPs under deconstruction)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2013, if any, are reported as well as the radioactive and non-radioactive effluents discharge in the environment. Finally, the radioactive materials and wastes generated by the facility are presented (type of waste, quantities, conditioning process). The document concludes with a presentation of the actions of communication and public information made by the direction of the facility. A glossary and the list of recommendations from the Committees for health, safety and working conditions are given in appendix

  3. ICT security- aspects important for nuclear facilities

    International Nuclear Information System (INIS)

    Thunem, Atoosa P-J.

    2005-09-01

    Rapid application growth of complex Information and Communication Technologies (ICT) in every society and state infrastructure as well as industry has revealed vulnerabilities that eventually have given rise to serious security breaches. These vulnerabilities together with the course of the breaches from cause to consequence are gradually about to convince the field experts that ensuring the security of ICT-driven systems is no longer possible by only relying on the fundaments of computer science, IT, or telecommunications. Appropriating knowledge from other disciplines is not only beneficial, but indeed very necessary. At the same time, it is a common observation today that ICT-driven systems are used everywhere, from the nuclear, aviation, commerce and healthcare domains to camera-equipped web-enabled cellular phones. The increasing interdisciplinary and inter-sectoral aspects of ICT security worldwide have been providing updated and useful information to the nuclear domain, as one of the emerging users of ICT-driven systems. Nevertheless, such aspects have also contributed to new and complicated challenges, as ICT security for the nuclear domain is in a much more delicate manner than for any other domains related to the concept of safety, at least from the public standpoint. This report addresses some important aspects of ICT security that need to be considered at nuclear facilities. It deals with ICT security and the relationship between security and safety from a rather different perspective than usually observed and applied. The report especially highlights the influence on the security of ICT-driven systems by all other dependability factors, and on that basis suggests a framework for ICT security profiling, where several security profiles are assumed to be valid and used in parallel for each ICT-driven system, sub-system or unit at nuclear facilities. The report also covers a related research topic of the Halden Project with focus on cyber threats and

  4. No nuclear power. No disposal facility?

    Energy Technology Data Exchange (ETDEWEB)

    Feinhals, J. [DMT GmbH und Co.KG, Hamburg (Germany)

    2016-07-01

    Countries with a nuclear power programme are making strong efforts to guarantee the safe disposal of radioactive waste. The solutions in those countries are large disposal facilities near surface or in deep geological layers depending on the activity and half-life of the nuclides in the waste. But what will happen with the radioactive waste in countries that do not have NPPs but have only low amounts of radioactive waste from medical, industrial and research facilities as well as from research reactors? Countries producing only low amounts of radioactive waste need convincing solutions for the safe and affordable disposal of their radioactive waste. As they do not have a fund by an operator of nuclear power plants, those countries need an appropriate and commensurate solution for the disposal of their waste. In a first overview five solutions seem to be appropriate: (i) the development of multinational disposal facilities by using the existing international knowhow; (ii) common disposal with hazardous waste; (iii) permanent storage; (iv) use of an existing mine or tunnel; (v) extension of the borehole disposal concept for all the categories of radioactive wastes.

  5. Financing the Decommissioning of Nuclear Facilities

    International Nuclear Information System (INIS)

    2016-01-01

    Decommissioning of both commercial and R and D nuclear facilities is expected to increase significantly in the coming years, and the largest of such industrial decommissioning projects could command considerable budgets. It is important to understand the costs of decommissioning projects in order to develop realistic cost estimates as early as possible based on preliminary decommissioning plans, but also to develop funding mechanisms to ensure that future decommissioning expenses can be adequately covered. Sound financial provisions need to be accumulated early on to reduce the potential risk for residual, unfunded liabilities and the burden on future generations, while ensuring environmental protection. Decommissioning planning can be subject to considerable uncertainties, particularly in relation to potential changes in financial markets, in energy policies or in the conditions and requirements for decommissioning individual nuclear installations, and such uncertainties need to be reflected in regularly updated cost estimates. This booklet offers a useful overview of the relevant aspects of financing the decommissioning of nuclear facilities. It provides information on cost estimation for decommissioning, as well as details about funding mechanisms and the management of funds based on current practice in NEA member countries. (authors)

  6. Research Facilities for the Future of Nuclear Energy

    International Nuclear Information System (INIS)

    Ait Abderrahim, H.

    1996-01-01

    The proceedings of the ENS Class 1 Topical Meeting on Research facilities for the Future of Nuclear Energy include contributions on large research facilities, designed for tests in the field of nuclear energy production. In particular, issues related to facilities supporting research and development programmes in connection to the operation of nuclear power plants as well as the development of new concepts in material testing, nuclear data measurement, code validation, fuel cycle, reprocessing, and waste disposal are discussed. The proceedings contain 63 papers

  7. High-risk facilities. Emergency management in nuclear, chemical and hazardous waste facilities

    International Nuclear Information System (INIS)

    Kloepfer, Michael

    2012-01-01

    The book on emergency management in high-risk facilities covers the following topics: Change in the nuclear policy, risk management of high-risk facilities as a constitutional problem - emergency management in nuclear facilities, operational mechanisms of risk control in nuclear facilities, regulatory surveillance responsibilities for nuclear facilities, operational mechanism of the risk control in chemical plants, regulatory surveillance responsibilities for chemical facilities, operational mechanisms of the risk control in hazardous waste facilities, regulatory surveillance responsibilities for hazardous waste facilities, civil law consequences in case of accidents in high-risk facilities, criminal prosecution in case of accidents in high-risk facilities, safety margins as site risk for emission protection facilities, national emergency management - strategic emergency management structures, warning and self-protection of the public in case of CBRN hazards including aspects of the psych-social emergency management.

  8. Emergency facility control device for nuclear reactor

    International Nuclear Information System (INIS)

    Ikehara, Morihiko.

    1981-01-01

    Purpose: To increase the reliability of a nuclear reactor by allowing an emergency facility to be manually started and stopped to make its operation more convenient and eliminate the possibility of erroneous operation in an emergency. Constitution: There are provided a first water level detector for detecting a level lower than the first low water level in a reactor container and a second water level detector for detecting a level lower than the second low water level lower than the first low water level, and an emergency facility can be started and stopped manually only when the level is higher than the second low water level, but the facility will be started regardless of the state of the manual operation when the level is lower than the second low water level. Thus, the emergency facility can be started by manual operation, but will be automatically started so as to secure the necessary minimum operation if the level becomes lower than the second low water level and the stopping operation thereafter is forgotten. (Kamimura, M.)

  9. Storage facilities of spent nuclear fuel in dry for Mexican nuclear facilities

    International Nuclear Information System (INIS)

    Salmeron V, J. A.; Camargo C, R.; Nunez C, A.; Mendoza F, J. E.; Sanchez J, J.

    2013-10-01

    In this article the relevant aspects of the spent fuel storage and the questions that should be taken in consideration for the possible future facilities of this type in the country are approached. A brief description is proposed about the characteristics of the storage systems in dry, the incorporate regulations to the present Nuclear Regulator Standard, the planning process of an installation, besides the approaches considered once resolved the use of these systems; as the modifications to the system, the authorization periods for the storage, the type of materials to store and the consequent environmental impact to their installation. At the present time the Comision Nacional de Seguridad Nuclear y Salvaguardias (CNSNS) considers the possible generation of two authorization types for these facilities: Specific, directed to establish a new nuclear installation with the authorization of receiving, to transfer and to possess spent fuel and other materials for their storage; and General, focused to those holders that have an operation license of a reactor that allows them the storage of the nuclear fuel and other materials that they possess. Both authorizations should be valued according to the necessities that are presented. In general, this installation type represents a viable solution for the administration of the spent fuel and other materials that require of a temporary solution previous to its final disposal. Its use in the nuclear industry has been increased in the last years demonstrating to be appropriate and feasible without having a significant impact to the health, public safety and the environment. Mexico has two main nuclear facilities, the nuclear power plant of Laguna Verde of the Comision Federal de Electricidad (CFE) and the facilities of the TRIGA Reactor of the Instituto Nacional de Investigaciones Nucleares (ININ) that will require in a future to use this type of disposition installation of the spent fuel and generated wastes. (Author)

  10. Decontamination Technology Development for Nuclear Research Facilities

    International Nuclear Information System (INIS)

    Oh, Won Zin; Jung, Chong Hun; Choi, Wang Kyu; Won, Hui Jun; Kim, Gye Nam

    2004-02-01

    Technology development of surface decontamination in the uranium conversion facility before decommissioning, technology development of component decontamination in the uranium conversion facility after decommissioning, uranium sludge treatment technology development, radioactive waste soil decontamination technology development at the aim of the temporary storage soil of KAERI, Optimum fixation methodology derivation on the soil and uranium waste, and safety assessment methodology development of self disposal of the soil and uranium waste after decontamination have been performed in this study. The unique decontamination technology applicable to the component of the nuclear facility at room temperature was developed. Low concentration chemical decontamination technology which is very powerful so as to decrease the radioactivity of specimen surface under the self disposal level was developed. The component decontamination technology applicable to the nuclear facility after decommissioning by neutral salt electro-polishing was also developed. The volume of the sludge waste could be decreased over 80% by the sludge waste separation method by water. The electrosorption method on selective removal of U(VI) to 1 ppm of unrestricted release level using the uranium-containing lagoon sludge waste was tested and identified. Soil decontamination process and equipment which can reduce the soil volume over 90% were developed. A pilot size of soil decontamination equipment which will be used to development of real scale soil decontamination equipment was designed, fabricated and demonstrated. Optimized fixation methodology on soil and uranium sludge was derived from tests and evaluation of the results. Safety scenario and safety evaluation model were development on soil and uranium sludge aiming at self disposal after decontamination

  11. Human factors methods in DOE nuclear facilities

    International Nuclear Information System (INIS)

    Bennett, C.T.; Banks, W.W.; Waters, R.J.

    1993-01-01

    The US Department of Energy (DOE) is in the process of developing a series of guidelines for the use of human factors standards, procedures, and methods to be used in nuclear facilities. This paper discusses the philosophy and process being used to develop a DOE human factors methods handbook to be used during the design cycle. The following sections will discuss: (1) basic justification for the project; (2) human factors design objectives and goals; and (3) role of human factors engineering (HFE) in the design cycle

  12. Guidance for air sampling at nuclear facilities

    International Nuclear Information System (INIS)

    Breslin, A.J.

    1976-11-01

    The principal uses of air sampling at nuclear facilities are to monitor general levels of radioactive air contamination, identify sources of air contamination, and evaluate the effectiveness of contaminant control equipment, determine exposures of individual workers, and provide automatic warning of hazardous concentrations of radioactivity. These applications of air sampling are discussed with respect to standards of occupational exposure, instrumentation, sample analysis, sampling protocol, and statistical treatment of concentration data. Emphasis is given to the influence of spacial and temporal variations of radionuclide concentration on the location, duration, and frequency of air sampling

  13. Evaluation of Nuclear Facility Decommissioning Projects program

    International Nuclear Information System (INIS)

    Baumann, B.L.

    1983-01-01

    The objective of the Evaluation of Nuclear Facility Decommissioning Projects (ENFDP) program is to provide the NRC licensing staff with data which will allow an assessment of radiation exposure during decommissioning and the implementation of ALARA techniques. The data will also provide information to determine the funding level necessary to ensure timely and safe decommissioning operations. Actual decommissioning costs, methods and radiation exposures are compared with those estimated by the Battelle-PNL and ORNL NUREGs on decommissioning. Exposure reduction techniques applied to decommissioning activities to meet ALARA objectives are described. The lessons learned concerning various decommissioning methods are evaluated

  14. Innovative ways of decontaminating nuclear facilities

    International Nuclear Information System (INIS)

    Bremmer, Jan; Gentes, Sascha; Ambos, Frank

    2009-01-01

    The great variety of surfaces to be decontaminated in a nuclear power plant increases demand for economic solutions and efficient processing systems. The Institute for Technology and Management in Building (TMB) of the University of Karlsruhe (TH) is working on this task in the new professorship of Sascha Gentes and, together with sat Kerntechnik GmbH, developing innovative techniques and tools for surface decontamination. In this effort, sat.Kerntechnik GmbH contributes 50% to the funding of the new professorship at the Karlsruhe Institute of Technology, the merger of the University of Karlsruhe and the Karlsruhe Research Center. The new professorship will extend its work also to various other innovative concepts to be employed not only in demolition but also in maintenance and operation of nuclear facilities. Above and beyond theoretical approaches, practical solutions are in the focus of work. For this reason, new developments are elaborated in close cooperation with the respective users. (orig.)

  15. Environmental radiation monitoring around the nuclear facilities

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Chang Woo

    2012-03-15

    Environmental Radiation Monitoring was carried out with measurement of environment. radiation and environmental radioactivity analysis on the sites of KAERI nuclear facilities and Seoul Research Reactors and their environments. The average level of environmental radiation dose measured by an ERM and the accumulated radiation dose by a TLD were almost same level compared with the previous years. The activity of gross {alpha} and gross {beta}, Tritium, Uranium and Strontium in environmental samples showed a environmental level. The {gamma}-radionuclides such as natural radionuclides 40K or 7Be were detected in pine needle and food. The nuclear radionuclides 134Cs, 137Cs or 131I were temporarily detected in the samples of air particulate and rain in April and of fall out in 2nd quarter from the effect of Fukusima accident.

  16. Robotic inspection of nuclear waste storage facilities

    International Nuclear Information System (INIS)

    Fulbright, R.; Stephens, L.M.

    1995-01-01

    The University of South Carolina and the Westinghouse Savannah River Company have developed a prototype mobile robot designed to perform autonomous inspection of nuclear waste storage facilities. The Stored Waste Autonomous Mobile Inspector (SWAMI) navigates and inspects rows of nuclear waste storage drums, in isles as narrow as 34 inches with drums stacked three high on each side. SWAMI reads drum barcodes, captures drum images, and monitors floor-level radiation levels. The topics covered in this article reporting on SWAMI include the following: overall system design; typical mission scenario; barcode reader subsystem; video subsystem; radiation monitoring subsystem; position determination subsystem; onboard control system hardware; software development environment; GENISAS, a C++ library; MOSAS, an automatic code generating tool. 10 figs

  17. Decommissioning and deactivation of nuclear facilities

    International Nuclear Information System (INIS)

    Anasco, Roberto; Harriague, Santiago; Hey, Alfredo M.; Fabbri, Silvio; Garonis, Omar H.

    2003-01-01

    The National Atomic Energy Commission (CNEA) is responsible for the decommissioning and deactivation of all relevant nuclear facilities in Argentina. A D and D Subprogram was created in 2000, within Technology Branch of the CNEA, in order to fulfill this responsibility. The D and D Subprogram has organized its activities in four fields: Planning; Technology development; Human resources development and training; International cooperation. The paper describes the work already done in those 4 areas, as well as the nuclear facilities existing in the country. Planning is being developed for the decommissioning of research reactors, beginning with RA-1, as well as for the Atucha I nuclear power station. An integral Management System has been developed, compatibilizing requirements from ISO 9001, ISO 14001, the national norm for Safety and Occupational Health (equivalent to BS 8800), and IAEA 50-SG Q series. Technology development is for the time being concentrated on mechanical decontamination and concrete demolition. A review has been made of technologies already developed both by CNEA and Nucleoelectrica Argentina S.A. (the nuclear power utility) in areas of chemical and electrochemical decontamination, cutting techniques and robotics. Human resources development has been based on training abroad in the areas of decontamination, cutting techniques, quality assurance and planning, as well as on specific courses, seminars and workshops. An IAEA regional training course on D and D has been given on April 2002 at CNEA's Constituyentes Atomic Center, with the assistance of 22 university graduates from 13 countries in the Latin American and Caribbean Region, and 11 from Argentina. CNEA has also given fellowships for PhD and Master thesis on the subject. International cooperation has been intense, and based on: - IAEA Technical Cooperation Project and experts missions; - Cooperation agreement with the US Department of Energy; - Cooperation agreement with Germany

  18. Pattern of Eclampsia in a Tertiary Health Facility Situated in a Semi ...

    African Journals Online (AJOL)

    ANNALS

    Annals of African Medicine. Vol. 6, No.4; 2007:164 – 167. Pattern of Eclampsia in a Tertiary Health Facility Situated in a Semi-Rural ... In Kano State (which is in the same zone as the place where this study was conducted), eclampsia .... eclampsia. RHL commentary. The WHO. Reproductive Health Library No 8. Update Soft.

  19. Waste management practices in decommissioning nuclear facilities

    International Nuclear Information System (INIS)

    Dickson, H.W.

    1979-01-01

    Several thousand sites exist in the United States where nuclear activities have been conducted over the past 30 to 40 years. Questions regarding potential public health hazards due to residual radioactivity and radiation fields at abandoned and inactive sites have prompted careful ongoing review of these sites by federal agencies including the Department of Energy (DOE) and the Nuclear Regulatory Commission (NRC). In some instances, these reviews are serving to point out poor low-level waste management practices of the past. Many of the sites in question lack adequate documentation on the radiological conditions at the time of release for unrestricted use or were released without appropriate restrictions. Recent investigations have identified residual contamination and radiation levels on some sites which exceed present-day standards and guidelines. The NRC, DOE, and Environmental Protection Agency are all involved in developing decontamination and decommissioning (D and D) procedures and guidelines which will assure that nuclear facilities are decommissioned in a manner that will be acceptable to the nuclear industry, various regulatory agencies, other stakeholders, and the general public

  20. Nuclear safety and radiation protection report of the basic nuclear facilities of the Tricastin nuclear power plant - 2010

    International Nuclear Information System (INIS)

    2011-06-01

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

  1. Nuclear trade: An approach to the Argentine situation

    International Nuclear Information System (INIS)

    Antoniotti, A.A.; Paez, M.R.

    2006-01-01

    Under the Argentine nuclear trade regime, from the early stages of nuclear development an actual and strict monopoly governed the transfer of nuclear materials. That meant that the Federal State took the control as user, producer, purchaser or seller. This policy was inspired and clearly echoed by similar ones developed by other countries with important development in the nuclear field. This paper discusses the types of contract on nuclear commerce, the relation with costs incurred by the nuclear industry, ways in which the Federal State intervenes in nuclear commerce, and comparative policies in other fields or products in Argentina. (author)

  2. Nuclear safety and radiation protection report of the nuclear facility of Brennilis - 2011

    International Nuclear Information System (INIS)

    2012-01-01

    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 partially dismantled facilities of the Monts d'Arree (EL4-D or Brennilis) site (INB 162 (FR)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2011, are reported as well as the radioactive effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

  3. Nuclear safety and radiation protection report of the nuclear facilities of Brennilis - 2010

    International Nuclear Information System (INIS)

    2011-06-01

    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 partially dismantled facilities of the Monts d'Arree (EL4-D or Brennilis) site (INB 162 (FR)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2010, are reported as well as the radioactive effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

  4. Radiological dose assessment from the operation of Daeduk nuclear facilities

    Energy Technology Data Exchange (ETDEWEB)

    Hwang, Won Tae; Kim, Eun Han; Suh, Kyung Suk; Choi, Young Gil [Korea Atomic Energy Research Institute, Taejon (Korea)

    2000-02-01

    The objective of this project is to assure the public acceptance for nuclear facilities, and the environmental safety from the operation of Daeduk nuclear facilities, such as HANARO research reactor, nuclear fuel processing facilities and others. For identifying the integrity of their facilities, the maximum individual doses at the site boundary and on the areas with high population density were assessed. Also, the collective doses within radius 80 km from the site were assessed. The radiation impacts for residents around the site from the operation of Daeduk nuclear facilities in 1999 were neglectable. 8 refs., 10 figs., 27 tabs. (Author)

  5. The role of economic incentives in nuclear waste facility siting

    International Nuclear Information System (INIS)

    Davis, E.M.

    1986-01-01

    There is a need to provide some public benefit and/or reward for accepting a ''locally unwanted land use'' (LULU) facility such as a nuclear waste storage or disposal facility. This paper concludes that DOE, Congress and the states should immediately quantify an economic incentive for consideration ''up front'' by society on siting decisions for nuclear waste storage and disposal facilities

  6. Creation of a new-generation research nuclear facility

    International Nuclear Information System (INIS)

    Girchenko, A.A.; Matyushin, A.P.; Kudryavtsev, E.M.; Skopin, V.P.; Shchepelev, R.M.

    2013-01-01

    The SO-2M research nuclear facility operated on the industrial area of the institute. The facility is now removed from service. In view of this circumstance, it is proposed to restore the facility at the new qualitative level, i.e., to create a new-generation research nuclear facility with a very high safety level consisting of a subcritical bench and a proton accelerator (electronuclear facility). Competitive advantages and design features have been discussed and the productive capacity of the research nuclear facility under development has been evaluated [ru

  7. The Physical Protection of Nuclear Material and Nuclear Facilities; Proteccion Fisica De Los Materiales Y Las Instalaciones Nucleares

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-06-15

    Physical protection against the theft or unauthorized diversion of nuclear materials and against the sabotage of nuclear facilities by individuals or groups has long been a matter of national and international concern. Although responsibility for establishing and operating a comprehensive physical protection system for nuclear materials and facilities within a State rests entirely with the Government of that State, it is not a matter of indifference to other States whether and to what extent that responsibility is fulfilled. Physical protection has therefore become a matter of international concern and co-operation. The need for international co-operation becomes evident in situations where the effectiveness of physical protection in one State depends on the taking by other States also of adequate measures to deter or defeat hostile actions against nuclear facilities and nuclear materials, particularly when such materials are transported across national frontiers [Spanish] La proteccion fisica contra el robo o la desviacion no autorizada de materiales nucleares y contra el sabotaje de las instalaciones nucleares por parte de individuos o grupos es motivo de preocupacion nacional e internacional desde hace mucho tiempo. Aunque la obligacion de crear y hacer funcionar un sistema completo de proteccion fisica de las instalaciones y materiales nucleares en el territorio de un Estado determinado incumbe exclusivamente al Gobierno de dicho Estado, el que esa obligacion se cumpla o no, y si se cumple, en que medida o hasta que punto, son cosas que no dejan indiferentes a los demas Estados. Por ello, la proteccion fisica se ha convertido en motivo de interes y cooperacion internacional. La necesidad de la cooperacion internacional se hace evidente en los casos en que la eficacia de la proteccion fisica en el territorio de un Estado depende de que otros Estados tomen tambien medidas apropiadas para evitar o hacer fracasar los actos hostiles dirigidos contra instalaciones y

  8. Proceeding of the 7. Seminar on Technology and Safety of Nuclear Power Plants and Nuclear Facilities

    International Nuclear Information System (INIS)

    Hastowo, Hudi; Antariksawan, Anhar R.; Soetrisnanto, Arnold Y; Jujuratisbela, Uju; Aziz, Ferhat; Su'ud, Zaki; Suprawhardana, M. Salman

    2002-02-01

    The seventh proceedings of seminar safety and technology of nuclear power plant and nuclear facilities, held by National Nuclear Energy Agency. The Aims of seminar is to exchange and disseminate information about safety and nuclear Power Plant Technology and Nuclear Facilities consist of technology; high temperature reactor and application for national development sustain able and high technology. This seminar level all aspects technology, Power Reactor research reactor, high temperature reactor and nuclear facilities. The article is separated by index

  9. Database for environmental monitoring at nuclear facilities

    International Nuclear Information System (INIS)

    Raceanu, M.; Varlam, C.; Enache, A.; Faurescu, I.

    2006-01-01

    To ensure that an assessment could be made of the impact of nuclear facilities on the local environment, a program of environmental monitoring must be established well in advance of nuclear facilities operation. Enormous amount of data must be stored and correlated starting with: location, meteorology, type sample characterization from water to different kind of food, radioactivity measurement and isotopic measurement (e.g. for C-14 determination, C-13 isotopic correction it is a must). Data modelling is a well known mechanism describing data structures at a high level of abstraction. Such models are often used to automatically create database structures, and to generate code structures used to access databases. This has the disadvantage of losing data constraints that might be specified in data models for data checking. Embodiment of the system of the present application includes a computer-readable memory for storing a definitional data table for defining variable symbols representing respective measurable physical phenomena. The definitional data table uniquely defines the variable symbols by relating them to respective data domains for the respective phenomena represented by the symbols. Well established rules of how the data should be stored and accessed, are given in the Relational Database Theory. The theory comprise of guidelines such as the avoidance of duplicating data using technique call normalization and how to identify the unique identifier for a database record. (author)

  10. Database for environmental monitoring in nuclear facilities

    International Nuclear Information System (INIS)

    Raceanu, Mircea; Varlam, Carmen; Iliescu, Mariana; Enache, Adrian; Faurescu, Ionut

    2006-01-01

    To ensure that an assessment could be made of the impact of nuclear facilities on the local environment, a program of environmental monitoring must be established well before of nuclear facility commissioning. Enormous amount of data must be stored and correlated starting with: location, meteorology, type sample characterization from water to different kind of foods, radioactivity measurement and isotopic measurement (e.g. for C-14 determination, C-13 isotopic correction it is a must). Data modelling is a well known mechanism describing data structures at a high level of abstraction. Such models are often used to automatically create database structures, and to generate the code structures used to access the databases. This has the disadvantage of losing data constraints that might be specified in data models for data checking. Embodiment of the system of the present application includes a computer-readable memory for storing a definitional data table for defining variable symbols representing the corresponding measurable physical quantities. Developing a database system implies setting up well-established rules of how the data should be stored and accessed what is commonly called the Relational Database Theory. This consists of guidelines regarding issues as how to avoid duplicating data using the technique called normalization and how to identify the unique identifier for a database record. (authors)

  11. Nuclear fuel cycle facility accident analysis handbook

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-03-01

    The purpose of this Handbook is to provide guidance on how to calculate the characteristics of releases of radioactive materials and/or hazardous chemicals from nonreactor nuclear facilities. In addition, the Handbook provides guidance on how to calculate the consequences of those releases. There are four major chapters: Hazard Evaluation and Scenario Development; Source Term Determination; Transport Within Containment/Confinement; and Atmospheric Dispersion and Consequences Modeling. These chapters are supported by Appendices, including: a summary of chemical and nuclear information that contains descriptions of various fuel cycle facilities; details on how to calculate the characteristics of source terms for releases of hazardous chemicals; a comparison of NRC, EPA, and OSHA programs that address chemical safety; a summary of the performance of HEPA and other filters; and a discussion of uncertainties. Several sample problems are presented: a free-fall spill of powder, an explosion with radioactive release; a fire with radioactive release; filter failure; hydrogen fluoride release from a tankcar; a uranium hexafluoride cylinder rupture; a liquid spill in a vitrification plant; and a criticality incident. Finally, this Handbook includes a computer model, LPF No.1B, that is intended for use in calculating Leak Path Factors. A list of contributors to the Handbook is presented in Chapter 6. 39 figs., 35 tabs.

  12. Nuclear fuel cycle facility accident analysis handbook

    International Nuclear Information System (INIS)

    1998-03-01

    The purpose of this Handbook is to provide guidance on how to calculate the characteristics of releases of radioactive materials and/or hazardous chemicals from nonreactor nuclear facilities. In addition, the Handbook provides guidance on how to calculate the consequences of those releases. There are four major chapters: Hazard Evaluation and Scenario Development; Source Term Determination; Transport Within Containment/Confinement; and Atmospheric Dispersion and Consequences Modeling. These chapters are supported by Appendices, including: a summary of chemical and nuclear information that contains descriptions of various fuel cycle facilities; details on how to calculate the characteristics of source terms for releases of hazardous chemicals; a comparison of NRC, EPA, and OSHA programs that address chemical safety; a summary of the performance of HEPA and other filters; and a discussion of uncertainties. Several sample problems are presented: a free-fall spill of powder, an explosion with radioactive release; a fire with radioactive release; filter failure; hydrogen fluoride release from a tankcar; a uranium hexafluoride cylinder rupture; a liquid spill in a vitrification plant; and a criticality incident. Finally, this Handbook includes a computer model, LPF No.1B, that is intended for use in calculating Leak Path Factors. A list of contributors to the Handbook is presented in Chapter 6. 39 figs., 35 tabs

  13. Dismantlement of nuclear facilities decommissioned from the Russian navy: Enhancing regulatory supervision of nuclear and radiation safety

    International Nuclear Information System (INIS)

    Sneve, M.K.

    2013-01-01

    The availability of up to date regulatory norms and standards for nuclear and radiation safety, relevant to the management of nuclear legacy situations, combined with effective and efficient regulatory procedures for licensing and monitoring compliance, are considered to be extremely important. Accordingly the NRPA has set up regulatory cooperation programs with corresponding authorities in the Russian Federation. Cooperation began with the civilian regulatory authorities and was more recently extended to include the military authority and this joint cooperation supposed to develop the regulatory documents to improve supervision over nuclear and radiation safety while managing the nuclear military legacy facilities in Northwest Russia and other regions of the country. (Author)

  14. Dismantlement of nuclear facilities decommissioned from the Russian navy: Enhancing regulatory supervision of nuclear and radiation safety

    Energy Technology Data Exchange (ETDEWEB)

    Sneve, M.K.

    2013-03-01

    The availability of up to date regulatory norms and standards for nuclear and radiation safety, relevant to the management of nuclear legacy situations, combined with effective and efficient regulatory procedures for licensing and monitoring compliance, are considered to be extremely important. Accordingly the NRPA has set up regulatory cooperation programs with corresponding authorities in the Russian Federation. Cooperation began with the civilian regulatory authorities and was more recently extended to include the military authority and this joint cooperation supposed to develop the regulatory documents to improve supervision over nuclear and radiation safety while managing the nuclear military legacy facilities in Northwest Russia and other regions of the country. (Author)

  15. Modern integrated environmental monitoring and processing systems for nuclear facilities

    International Nuclear Information System (INIS)

    Oprea, I.

    2000-01-01

    presentation by using on-line dynamic evolution of the events, environment information, evacuation optimization, image and voice processing. These modern systems are proposed for environmental monitoring around nuclear facilities, as open interactive systems supporting the operator in the global overview of the environment and the status of the situation updating the remote GIS data base, assuring man-computer interaction and a good information flow for emergency knowledge exchange, improving the protection of the population and decision makers efforts. The local monitoring systems could be integrated into national or international environmental monitoring systems, achieving desired interoperability between government, civilian and army in disaster preparedness efforts

  16. Nuclear facility safeguards as specified by the Czechoslovak administrative law

    International Nuclear Information System (INIS)

    Elias, J.; Svab, J.

    1978-01-01

    A study is presented of the legal aspects of nuclear safeguards for the operation of nuclear power facilities evaluating the development of the legal arrangement over the past five years, i.e., encoding nuclear safeguards for nuclear facilities in the new building regulations (Act No. 50/1976 Coll. of Laws on Urban Planning and Building Regulations and implementing provisions). It also discusses the juridical position of State surveillance over the nuclear safety of nuclear facilities and its relation to surveillance carried out by specialized bodies of the State work safety inspection and to surveillance carried out by hygiene inspection bodies. (J.S.)

  17. Nuclear facilities of EdF's operational hot base of Tricastin. 2009 annual report

    International Nuclear Information System (INIS)

    2010-01-01

    This annual report is established on account of article 21 of the 2006-686 French law from June 13, 2006, relative to the transparency and safety in the nuclear domain. It describes, first, the nuclear facilities of the EdF operational hot base of Tricastin, then, the measures taken to ensure their safety (personnel radioprotection, actions implemented for nuclear safety improvement, organisation in crisis situation, external and internal controls, technical assessment of the facilities), and finally the procedures of management of radioactive wastes. A glossary and the viewpoint of the Committee of Hygiene, safety and working conditions about the content of the document conclude the report. (J.S.)

  18. Remote maintenance system for nuclear facilities

    International Nuclear Information System (INIS)

    Maeda, Masafumi

    1993-01-01

    In the facilities related to atomic energy, from the viewpoint of the reduction of radiation exposure of workers and the heightening of the rate of operation of the facilities, the development of remote maintenance system is regarded as important. Meidensha Electric Manufacturing Co., Ltd. developed the bilateral control type manipulator, BILARM-83, in 1979, and has developed high performance manipulator systems. As the design of the plant that realizes the remote operation maintenance of process machinery and equipment during plant operation, the remote maintenance system by canyon cell techniques, which was adopted in Savannah River plant, USA, and has been operated for nearly 50 years, has been known. The concept of the full remote maintenance system by large scale cell techniques was shown and has been developed by Power Reactor and Nuclear Fuel Development Corp. In order to realize the remote maintenance of such large scale cells, Meidensha is developing the both arm type bilateral servo manipulator, the single arm type power manipulator, the transport system for moving them, the power and signal system and so on. Those systems were adopted for the glass solidification facilities. (K.I.)

  19. IAEA safeguards in new nuclear facilities

    Energy Technology Data Exchange (ETDEWEB)

    Catton, A. [International Atomic Energy Agency, Vienna (Austria); Durbin, K. [United States Department of Energy, Washington, D.C. (United States); Hamilton, A. [International Atomic Energy Agency, Vienna (Austria); Martikka, E. [STUK, Helsinki (Finland); Poirier, S.; Sprinkle, J. K.; Stevens, R. [International Atomic Energy Agency, Vienna (Austria); Whitlock, J. [Atomic Energy of Canada Limited, Chalk River, ON (Canada)

    2014-07-01

    The inclusion of international safeguards early in the design of nuclear facilities offers an opportunity to reduce project risk. It also has the potential to minimize the impact of safeguards activities on facility operations. Safeguards by design (SBD) encourages stakeholders to become familiar with the requirements of their safeguards agreements and to decide when and how they will fulfil those requirements. As one example, modular reactors are at a design stage where SBD can have a useful impact. Modular reactors might be turnkey projects where the operator takes ownership after commissioning. This comes with a legal obligation to comply with International Atomic Energy Agency (IAEA) safeguards requirements. Some of the newcomer countries entering the reactor market have little experience with IAEA safeguards and the associated non-proliferation obligations. To reduce delays or cost increments, one can embed safeguards considerations in the bid and design phases of the project, along with the safety and security considerations. SBD does not introduce any new requirements - it is a process whereby facility designers facilitate the implementation of the existing safeguards requirements. In short, safeguards experts share their expertise with the designers and vice versa. Once all parties understand the fundamentals of all of the operational constraints, they are better able to decide how best to address them. This presentation will provide an overview of SBD activities. (author)

  20. Seismic design standardization of nuclear facilities

    International Nuclear Information System (INIS)

    Reddy, G.R.; Vaze, K.K.

    2011-01-01

    Full text: Structures, Systems and Components (SSCs) of Nuclear Facilities have to be designed for normal operating loads such as dead weight, pressure, temperature etc., and accidental loads such as earthquakes, floods, extreme, wind air craft impact, explosions etc. Man made accidents such as aircraft impact, explosions etc., some times may be considered as design basis event and some times taken care by providing administrative controls. This will not be possible in the case of natural events such as earthquakes, flooding, extreme winds etc. Among natural events earthquakes are considered as most devastating and need to be considered as design basis event. It is generally felt design of SSCs for earthquake loads is very time consuming and expensive. Conventional seismic design approaches demands for large number of supports for systems and components. This results in large space occupation and in turn creates difficulties for maintenance and in service inspection of systems and components. In addition, complete exercise of design need to be repeated for plants being located at different sites due to different seismic demands. However, advanced seismic response control methods will help to standardize the seismic design meeting the safety and economy. These methods adopt passive, semi active and active devices, and base isolators to control the seismic response. In nuclear industry, it is advisable to go for passive devices to control the seismic responses. Ideally speaking, these methods will make the designs made for normal loads can also satisfy the seismic demand without calling for change in material, geometry, layout etc. in the SSCs. This paper explain the basic ideas of seismic response control methods, demonstrate the effectiveness of control methods through case studies and eventually give the procedure to be adopted for seismic design standardization of nuclear facilities

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2015-07-01

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

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

    International Nuclear Information System (INIS)

    Talarico, M.A.; Melo, P.F. Frutuoso e

    2015-01-01

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

  3. Research in artificial intelligence for nuclear facilities

    International Nuclear Information System (INIS)

    Uhrig, R.E.

    1990-01-01

    The application of artificial intelligence, in the form of expert systems and neural networks, to the control room activities in a nuclear power plant has the potential to reduce operator error and increase plant safety, reliability, and efficiency. Furthermore, artificial intelligence can increase efficiency and effectiveness in a large number of nonoperating activities (testing, routine maintenance, outage planning, equipment diagnostics, and fuel management) and in research facility experiments. Recent work at the University of Tennessee has demonstrated the feasibility of using neural networks to identify six different transients introduced into the simulation of a steam generator of a nuclear power plant. This work is now being extended to utilize data from a nuclear power plant training simulator. In one configuration, the inputs to the neural network are a subset of the quantities that are typical of those available from the safety parameter display system. The outputs of the network represent the various states of the plant (e.g., normal operation, coolant leakage, inadequate core flow, excessive peak fuel temperature, etc.). Training of the neural network is performed by introducing various faults or conditions to be diagnosed into the simulator. The goal of this work is to demonstrate a neural network diagnostic system that could provide advice to the operators in accordance with the emergency operating procedures

  4. Nuclear trade: an approach on the Argentine situation

    International Nuclear Information System (INIS)

    Antoniotti, Americo A.; Paez, Mariano R.

    2005-01-01

    The Argentine nuclear trade regime. Nuclear Materials. Definitions. Stages. From early times of nuclear development an actual and strict monopoly governed the transfers of nuclear materials. That meant: the Federal State took the control as user, producer, purchaser or seller. This policy was inspired and clearly echoed a similar one developed by countries with important development in the nuclear field. Types of contracts on nuclear commerce. Relation with costs implied with the nuclear industry. Uranium mining. System of supplies. Development of factories of nuclear supplies. Incentives. Nuclear Power. Radioisotopes. Human Resources. Ways of intervention of the State on nuclear Commerce. The right of veto. The ownership of shares in private or public corporations. Export- import controls. Security and Safety standards. National Act of Nuclear Activity. Veto of the Executive Power to the monopoly of the exclusive national supply of uranium. Comparative policies on other fields or products in Argentina. A proposal of lege ferenda. State's right of transformation applicable to purchases and sales of nuclear materials. Exchange and loans. Cosignature of contracts, etc. (author)

  5. Outlook of nuclear power generation and international situation

    Energy Technology Data Exchange (ETDEWEB)

    Ekulund, S [International Atomic Energy Agency, Vienna (Austria)

    1978-01-01

    Nuclear power generation is advancing at rapid rate over the world, without any major accident. For the base load of electric power, when choice is made between nuclear energy and petroleum, Nuclear energy has larger economic advantages over petroleum as compared with the days before the oil crisis. The costs of its fuel and fuel cycle technology are reasonable. However, nuclear power generation currently has a number of problems. What causes this uncertainty is not technological, but political, i.e. governmental policy changes, and this is based on the apprehension about nuclear proliferation. What is necessary is to strengthen the existing international framework of nuclear nonproliferation. In this respect, IAEA through comprehensive safeguards will make contributions largely to reduction of the political uncertainty. It is important that the new initiatives toward international nuclear cooperation should eliminate the current trends of restraint and denial.

  6. Interim Storage Facility for LLW of Decommissioning Nuclear Research Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Amato, S.; Ugolini, D.; Basile, F. [European Commission, Joint Research Centre, Nuclear Decommissioning and Facility Management Unit, TP 800, Via E. Fermi 2749, 21027 Ispra - VA (Italy)

    2009-06-15

    JRC-Ispra has initiated a Decommissioning and Waste Management (D and WM) Programme of all its nuclear facilities. In the frame of this programme, it has been decided to build an interim storage facility to host conditioned low level waste (LLW) that had been produced during the operation of JRC-Ispra nuclear research reactors and laboratories and that will be produced from their decommissioning. This paper presents the main characteristics of the facility. The storage ISFISF has a rectangular shape with uniform height and it is about 128 m long, 41 m wide and 9 m high. The entire surface affected by the facility, including screening area and access roads, is about 27.000 m{sup 2}. It is divided in three sectors, a central one, about 16 m long, for loading/unloading operations and operational services and two lateral sectors, each about 55 m long, for the conditioned LLW storage. Each storage sector is divided by a concrete wall in two transversal compartments. The ISFISF, whose operational lifetime is 50 years, is designed to host the conditioned LLW boxed in UNI CP-5.2 packages, 2,5 m long, 1.65 m wide, and 1,25 m high. The expected nominal inventory of waste is about 2100 packages, while the maximum storage is 2540 packages, thus a considerably large reserve capacity is available. The packages will be piled in stacks of maximum number of five. The LLW is going to be conditioned with a cement matrix. The maximum weight allowed for each package has been fixed at 16.000 kg. The total radioactivity inventory of waste to be hosted in the facility is about 30 TBq (mainly {beta}/{gamma} emitters). In order to satisfy the structural, seismic, and, most of all, radiological requirements, the external walls of the ISFISF are made of pre-fabricated panels, 32 cm thick, consisting of, from inside to outside, 20 cm of reinforced concrete, 7 cm of insulating material, and again 5 cm of reinforced concrete. For the same reason the roof is made with pre-fabricated panels in

  7. Operational status of nuclear facilities in Japan. 2012 edition

    International Nuclear Information System (INIS)

    2012-01-01

    This document is a compilation which provides an outline of the administration of nuclear facility safety regulations as well as various data including operational status, the status of periodical and safety inspections, the status of issues, and radiation management on nuclear power reactor facilities, reactor facilities in the research and development stage, and fabrication, reprocessing, disposal, and storage facilities in fiscal year 2011 (from April 2011 to March 2012). (J.P.N.)

  8. Governments' role in decommissioning nuclear power facilities

    International Nuclear Information System (INIS)

    Guindon, S.; Wendling, R.D.; Gordelier, S.; Soederberg, O.; Averous, J.; Orlando, D.

    2005-01-01

    Many nuclear power plants will reach the end of their operating lives over the next 20 years; some may be life-extended, others may not. This development will precipitate enhanced industrial and regulatory activities in the area of decommissioning. We are also witnessing in many countries a significant shift in the role of government itself: new pressures on governments, such as enhanced attention on environmental impact/mitigation and strategies to implement market-oriented approaches in a variety of sectors, including the energy sector are driving the public policy agenda. The paper will examine the range of policy issues, drawing from recent NEA studies on decommissioning policies and the recent NEA study on Government and Nuclear Energy and, strategies and costs, and other current trends and developments in the nuclear industry and in the nuclear policy fields. The paper will reflect on issues to be addressed during the conference and draw conclusions on the appropriate role of government in this area. Decommissioning policy is very specific and focused: it is not a high level policy/political issue in most instances and rarely gets the same attention as the issue surrounding the future of nuclear energy itself and public concerns regarding safety, waste and economics. One reason why decommissioning does not get the same attention as for example disposal of spent nuclear fuel might be the fact that technology is available for decommissioning, while technology for disposal of spent nuclear fuel is under development. High profile or not, it will remain an important issue for governments and industry alike particularly because of the cost and long lead times involved. In some instances, governments are the owners of the facilities to be decommissioned. In addition, decommissioning factors into issues surrounding the economics of nuclear energy and the sustainability of the nuclear option. Based on results of the Tarragona Seminar (Spain, September 2-4, 2003) and

  9. Remote handling technology for nuclear fuel cycle facilities

    International Nuclear Information System (INIS)

    Sakai, Akira; Maekawa, Hiromichi; Ohmura, Yutaka

    1997-01-01

    Design and R and D on nuclear fuel cycle facilities has intended development of remote handling and maintenance technology since 1977. IHI has completed the design and construction of several facilities with remote handling systems for Power Reactor and Nuclear Fuel Development Corporation (PNC), Japan Atomic Energy Research Institute (JAERI), and Japan Nuclear Fuel Ltd. (JNFL). Based on the above experiences, IHI is now undertaking integration of specific technology and remote handling technology for application to new fields such as fusion reactor facilities, decommissioning of nuclear reactors, accelerator testing facilities, and robot simulator-aided remote operation systems in the future. (author)

  10. Physical protection nuclear facilities against sabotage

    International Nuclear Information System (INIS)

    Hagemann, A.

    2001-01-01

    Full text: INFCIRC 225 Rev. 4 has introduced the Design Basis Threat, DBT, as a key element of the states physical protection system. The DBT is a definition which determines the level of physical protection of nuclear material during use, storage, transport and of nuclear facilities. It the basis for physical protection concepts and for the design of measures the operator or licensee has to provide. By this means it is also a definition of the responsibility for the physical protection which the operator accepts with the license. The new chapter designated to the physical protection against sabotage which has resulted also in the amendment of the title in INFCIRC 225 demonstrates the grown international concern about the potential consequences of sabotage. More than the physical protection against unauthorized removal the physical protection against sabotage has interfaces with the nuclear safety field. The basis of protection against sabotage therefore is much more based on the facility design-the safety design of the facility. Using the DBT the competent authority is in the position to determine the level of protection against sabotage and the remaining risk which has to be accepted. This risk of course depends on the real threat which is not known in advance. The acceptance of the remaining risk depends on both the assessment of the threat, its credibility and the potential consequences. There has been no serious act of sabotage in the past nor an attempt of. Despite of this the Harnun attack of the Japanese underground and some other recent terrorist activities could have given reasons to reconsider what threat might be credible. The German physical protection system has been developed since the increasing terrorist activities in the 1970s. From the beginning the protection against sabotage played an important role in the German system of physical protection. The requirements for the physical protection against unauthorized removal and against sabotage were

  11. Master Training in Radiological Protection Facilities Radioactive and Nuclear

    International Nuclear Information System (INIS)

    Verdu, G.; Mayo, P.; Campayo, J. M.

    2011-01-01

    The master includes general aspects of radiation protection in nuclear facilities. also an advanced module to acquire a high level training highlights as nuclear decommissioning, shielding calculation using advanced codes, particle accelerators, international law, etc.

  12. Design Lessons Drawn from the Decommissioning of Nuclear Facilities

    International Nuclear Information System (INIS)

    2011-05-01

    This report provides an updated compilation incorporating the most recent lessons learned from decommissioning and remediation projects. It is intended as a 'road map' to those seeking to apply these lessons. The report presents the issues in a concise and systematic manner, along with practical, thought-provoking examples. The most important lessons learned in recent years are organized and examined to enable the intended audience to gauge the importance of this aspect of the planning for new nuclear facilities. These will be of special interest to those seeking to construct nuclear facilities for the first time. In Sections 1 and 2, the current situation in the field of decommissioning is reviewed and the relevance and importance of beneficial design features is introduced. A more detailed review of previous and current lessons learned from decommissioning is given in Section 3 where different aspects of the decommissioning process are analysed. From this analysis beneficial design features have been extracted and identified in Section 4 which includes two comprehensive tables where brief descriptions of the features are summarized and responsibilities are identified. Conclusions and key design features and key recommendations are given in Section 5. Two Annexes are included to provide lessons from past projects and past experience and to record notes and extracts taken from a comprehensive list of publications listed in the References on page 47.

  13. Nuclear and non-nuclear safety aspects in nuclear facilities dismantling. The example of a PWR pilot decommissioning project

    International Nuclear Information System (INIS)

    Massaut, V.; Deboodt, P.; Dadoumont, J.; Valenduc, P.; Denissen, L.

    2002-01-01

    The dismantling of nuclear facilities, and in particular of nuclear power plants, involves new challenges for the nuclear industry. Although the dismantling of various activated and contaminated components is nowadays considered as almost industrial practice, the safety aspects of decommissioning bring some specific features which are not always taken into account in the operation of the plants. Moreover, most of the plants and facilities currently decommissioned are rather old and were never foreseen to be decommissioned. The operations involved in dismantling and decontamination, often imply new or unforeseen situations. On the nuclear, or radiological side, the radioprotection optimisation of the operations involved often requires to model the environment and to analyse different scenarios to tackle the operation. Recent 3-D software (like the Visiplan software) allowing representation of the actual environment and the influence of the various sources present, is really needed to be able to minimise the radiological impact on the operators. The risk of contamination spread, by opening loops and components or by the dismantling process itself, is also an important aspect of the radiological protection study. Nevertheless, the radiological aspects of the safety approach are not the only ones to be dealt with when decommissioning nuclear facilities. Indeed, classical industrial safety aspects are also important: the dismantling can bring handling and transporting risk (heavy loads, difficult ways, uneasy access, etc.) but also the handling of toxic or hazardous materials. For instance, the removal of asbestos in contaminated areas can lead to additional hazard; the presence of alkali metals (like Na or NaK), of toxic metals (like e.g. Beryllium) or of corrosive fluids (acid,...) have to be tackled often in unstructured environment, and sometimes with limited knowledge of the actual situation. This leads to approach the operations following the ASARA principle (As

  14. Decommissioning of the LURE Nuclear Facility

    International Nuclear Information System (INIS)

    Pauwels, N.; Horodynski, J.M.; Robert, P.; Tadjeddine, A.

    2013-01-01

    With the goal of obtaining the decommissioning of the LURE nuclear facility, three of its accelerators were dismantled and another was modified to be below the thresh- old of 'Installation Nucleaire de Base' status. Operations were carried out with the strategy of mechanical dismantling with no cutting process. As the civil engineering radioactivity level was low, a great majority of it has been left in place with no process- ing, but compensatory measures have been taken for public and environmental protection. The overall result of these operations is a gain in both cost and operating time. They also contribute to a significant decrease in the risks, including radiological ones. The radiological impact after decommissioning remains acceptable. (authors)

  15. Ventilation safety of facilities comprising nuclear reactors

    International Nuclear Information System (INIS)

    Guirlet, J.

    1982-01-01

    The reliability of the ventilation is one of the most important aspects in the prevention of the nuisances that a nuclear installation can provide, since the ventilation is located at the last barrier. A certain number of essential points have been recalled here. But it is necessary to bear in mind other requirements such as the limitation in the number of crossovers, the answers to be found should the system fail, the need to show that ventilation systems do not in themselves bring other nuisances such as noise, irradiation or contamination hazards, likelyhood of recycling the contamination, vibrations, fire. Finally, it is absolutely essential, right from the project stage, that the design ensures that very good accessibility, very easy dismantling and handling, as well as all the facilities needed to make sure of the initial and periodic tests, are guaranteed [fr

  16. Radiation safely culture in nuclear facilities

    International Nuclear Information System (INIS)

    Coates, R.

    2018-01-01

    The importance of developing a sound radiation safety culture is a relatively new development in the practical application of radiation protection in operational facilities. It is instructive to trace the evolution of the fundamental approaches to controlling operational exposures, staring with the engineering-based 'Distance, Shielding and Time' mantra, through the growing emphasis on ALARA and systematic management-based approaches, towards a recognition of the importance of developing a more 'hearts and minds' approach based within the wider safety culture of the organization. The underlying requirements for developing a strong radiation safety culture are not novel, and are largely identical to those necessary for nuclear safety culture, which is why an integrated approach to culture within the organization is essential

  17. Environmental Radiation Monitoring Around the Nuclear Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Choi, Geun Sik; Lee, Chang Woo

    2008-05-15

    Environmental Radiation Monitoring was carried out with measurement of environment. radiation and environmental radioactivity analysis on the sites of KAERI nuclear facilities and Seoul Research Reactors and their environments. The average level of environmental radiation dose measured by an ERM and the accumulated radiation dose by a TLD were almost same level compared with the previous years. The activity of gross {alpha} and gross {beta}, Tritium, Uraniu and Strontium in environmental samples showed a environmental level. The radioactivities of most {gamma}-radionuclides in air particulate, surface water and ground water were less than MDA except {sup 40}K or {sup 7}Be which are natural radionuclides. However, not only {sup 40}K or {sup 7}Be but also {sup 137}Cs were detected at the background level in surface soil, discharge sediment and fallout or pine needle.

  18. Automated entry control system for nuclear facilities

    International Nuclear Information System (INIS)

    Ream, W.K.; Espinoza, J.

    1985-01-01

    An entry control system to automatically control access to nuclear facilities is described. The design uses a centrally located console, integrated into the regular security system, to monitor the computer-controlled passage into and out of sensitive areas. Four types of entry control points are used: an unmanned enclosed portal with metal and SNM detectors for contraband detection with positive personnel identification, a bypass portal for contraband search after a contraband alarm in a regular portal also with positive personnel identification, a single door entry point with positive personnel identification, and a single door entry point with only a magnetic card-type identification. Security force action is required only as a response to an alarm. The integration of the entry control function into the security system computer is also described. The interface between the entry control system and the monitoring security personnel utilizing a color graphics display with touch screen input is emphasized. 2 refs., 7 figs

  19. The nuclear importation and exportation - The Brazilian situation

    International Nuclear Information System (INIS)

    Coimbra, G.L.

    1985-01-01

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

  20. Report on operation of nuclear facilities in 1991

    International Nuclear Information System (INIS)

    1992-06-01

    The Slovenian Nuclear Safety Administration (SNSA) prepared a report on nuclear safety in the republic of Slovenia in 1991 as part of its regular practice of reporting on its work to the Government and the National Assembly of the Republic of Slovenia. The report is divided into three thematic chapters covering the activities of the SNSA, the operation of nuclear facilities in Slovenia, the activity of international missions in Slovenia and the operation of nuclear facilities around the world.

  1. Seismic evaluation of existing nuclear facilities. Proceedings

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-07-01

    Programmes for re-evaluation and upgrading of safety of existing nuclear facilities are presently under way in a number of countries around the world. An important component of these programmes is the re-evaluation of the seismic safety through definition of new seismic parameters at the site and evaluation of seismic capacity of structures, equipment and distribution systems following updated information and criteria. The Seminar is intended to provide a forum for the exchange of information and discussion of the state-of-the-art on seismic safety of nuclear facilities in operation or under construction. Both analytical and experimental techniques for the evaluation of seismic capacity of structures, equipment and distribution systems are discussed. Full scale and field tests of structures and components using shaking tables, mechanical exciters, explosive and shock tests, and ambient vibrations are included in the seminar programme with emphasis on recent case histories. Presentations at the Seminar also include analytical techniques for the determination of dynamic properties of soil-structure systems from experiments as well as calibration of numerical models. Methods and criteria for seismic margin assessment based on experience data obtained from the behaviour of structures and components in real earthquakes are discussed. Guidelines for defining technical requirements for capacity re-evaluation (i.e. acceptable behaviour limits and design and implementation of structure and components upgrades are also presented and discussed. The following topics were covered during 7 sessions: earthquake experience and seismic re-evaluation; country experience in seismic re-evaluation programme; generic WWER studies; analytical methods for seismic capacity re-evaluation; experimental methods for seismic capacity re-evaluation; case studies.

  2. Radiochemical analysis of military nuclear facilities

    International Nuclear Information System (INIS)

    Bayramov, A.A.; Bayramova, S.M.

    2012-01-01

    Full text : Radiochemical Analysis is a branch of analytical chemistry comprising an aggregate of methods for qualitatively determining the composition and content of radioisotopes in the products of transformations. Safety and minimization of radiation impact on human and environment are important demand of operation of Military Nuclear Facilities (MNF). In accordance of recommendations of International Commission on Radiological Protection there are next objects of radiochemical analysis: 1) potential sources of radiochemical pollution; 2) environment (objects of environment, human environment including buildings, agricultural production, water, air et al.); 3) human himself (determination of dose from external and internal radiation, chemical poisoning). The chemical analysis can be carried out using, for example, the Gas Chromatography instrument whish separates chemical mixtures and identifies the components at a molecular level. It is one of the most accurate tools for analyzing environmental samples. The Gas Chromatography works on the principle that a mixture will separate into individual substances when heated. The heated gases are carried through a column with an inert gas (such as helium). As the separated substances emerge from the column opening, they flow into the Mass Spectrometry. Mass spectrometry identifies compounds by the mass of the analyte molecule. Newly developed portable Gas Chromatography and Mass Spectrometry are techniques that can be used to separate volatile organic compounds and pesticides. Other uses of Gas Chromatography, combined with other separation and analytical techniques, have been developed for radionuclides, explosive compounds such as royal demolition explosive and trinitrotoluene, and metals. So, based on the many years experience of operation of dangerous MNF, in concordance with norms of radiation and chemical safety it was considered that the tasks of the radiochemical analysis of Military Nuclear Facilities include

  3. Seismic evaluation of existing nuclear facilities. Proceedings

    International Nuclear Information System (INIS)

    1995-01-01

    Programmes for re-evaluation and upgrading of safety of existing nuclear facilities are presently under way in a number of countries around the world. An important component of these programmes is the re-evaluation of the seismic safety through definition of new seismic parameters at the site and evaluation of seismic capacity of structures, equipment and distribution systems following updated information and criteria. The Seminar is intended to provide a forum for the exchange of information and discussion of the state-of-the-art on seismic safety of nuclear facilities in operation or under construction. Both analytical and experimental techniques for the evaluation of seismic capacity of structures, equipment and distribution systems are discussed. Full scale and field tests of structures and components using shaking tables, mechanical exciters, explosive and shock tests, and ambient vibrations are included in the seminar programme with emphasis on recent case histories. Presentations at the Seminar also include analytical techniques for the determination of dynamic properties of soil-structure systems from experiments as well as calibration of numerical models. Methods and criteria for seismic margin assessment based on experience data obtained from the behaviour of structures and components in real earthquakes are discussed. Guidelines for defining technical requirements for capacity re-evaluation (i.e. acceptable behaviour limits and design and implementation of structure and components upgrades are also presented and discussed. The following topics were covered during 7 sessions: earthquake experience and seismic re-evaluation; country experience in seismic re-evaluation programme; generic WWER studies; analytical methods for seismic capacity re-evaluation; experimental methods for seismic capacity re-evaluation; case studies

  4. Nuclear safety and radiation protection report of the Saint-Laurent-Des-Eaux nuclear facilities - 2014

    International Nuclear Information System (INIS)

    2015-01-01

    This safety report was established in accordance with articles L. 125-15 and L. 125-16 of the French environmental code. It presents, first, the NPPs (INBs no. 46, 74 and 100). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures carried out in 2014. The incidents and accidents which occurred in 2014, if any, are reported as well as the radioactive and non-radioactive effluents discharge in the environment. Finally, the radioactive materials and wastes generated by the facility are presented (type of waste, quantities, conditioning process) as well as the other pollutions. The document concludes with a presentation of the actions of communication and public information made by the direction of the facility. A glossary and the list of recommendations from the Committees for health, safety and working conditions are given in appendix

  5. Nuclear safety and radiation protection report of Flamanville nuclear facilities - 2012

    International Nuclear Information System (INIS)

    2013-01-01

    This safety report was established in accordance with articles L. 125-15 and L. 125-16 of the French environmental code. It presents, first, the NPPs (INBs no. 108, 109 and 167 (under construction)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2012, if any, are reported as well as the radioactive and non-radioactive effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facility are presented (type of waste, quantities, conditioning process). The document concludes with a presentation of the actions of communication and public information made by the direction of the facility. A glossary and the list of recommendations from the Committees for health, safety and working conditions are given in appendix. (J.S.)

  6. Nuclear safety and radiation protection report of the Saint-Laurent-Des-Eaux nuclear facilities - 2012

    International Nuclear Information System (INIS)

    2013-01-01

    This safety report was established in accordance with articles L. 125-15 and L. 125-16 of the French environmental code. It presents, first, the NPPs (INBs no. 46, 74 and 100). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures carried out in 2012. The incidents and accidents which occurred in 2012, if any, are reported as well as the radioactive and non-radioactive effluents discharge in the environment. Finally, the radioactive materials and wastes generated by the facility are presented (type of waste, quantities, conditioning process) as well as the other pollutions. The document concludes with a presentation of the actions of communication and public information made by the direction of the facility. A glossary and the list of recommendations from the Committees for health, safety and working conditions are given in appendix. (J.S.)

  7. Nuclear safety and radiation protection report of Tricastin nuclear facilities - 2012

    International Nuclear Information System (INIS)

    2013-01-01

    This safety report was established in accordance with articles L. 125-15 and L. 125-16 of the French environmental code. It presents, first, the Tricastin NPPs (INBs no. 87 and 88). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2012, if any, are reported as well as the radioactive and non-radioactive effluents discharge in the environment. Finally, the radioactive materials and wastes generated by the facility are presented (type of waste, quantities, conditioning process). The document concludes with a presentation of the actions of communication and public information made by the direction of the facility. A glossary and the list of recommendations from the Committees for health, safety and working conditions are given in appendix. (J.S.)

  8. Nuclear safety and radiation protection report of Cattenom nuclear facilities - 2012

    International Nuclear Information System (INIS)

    2013-01-01

    This safety report was established in accordance with articles L. 125-15 and L. 125-16 of the French environmental code. It presents, first, the NPPs (INBs no. 124, 125, 126 and 137). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2012, if any, are reported as well as the radioactive and non-radioactive effluents discharge in the environment. Finally, the radioactive materials and wastes generated by the facility are presented (type of waste, quantities, conditioning process). The document concludes with a presentation of the actions of communication and public information made by the direction of the facility. A glossary and the list of recommendations from the Committees for health, safety and working conditions are given in appendix. (J.S.)

  9. Nuclear safety and radiation protection report of Chooz nuclear facilities - 2012

    International Nuclear Information System (INIS)

    2013-01-01

    This safety report was established in accordance with articles L. 125-15 and L. 125-16 of the French environmental code. It presents, first, the NPPs (INBs no. 139, 144 and 163 (under dismantling)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2012, if any, are reported as well as the radioactive and non-radioactive effluents discharge in the environment. Finally, the radioactive materials and wastes generated by the facility are presented (type of waste, quantities, conditioning process). The document concludes with a presentation of the actions of communication and public information made by the direction of the facility. A glossary and the list of recommendations from the Committees for health, safety and working conditions are given in appendix. (J.S.)

  10. Nuclear safety and radiation protection report of the Saint-Laurent-Des-Eaux nuclear facilities - 2013

    International Nuclear Information System (INIS)

    2014-01-01

    This safety report was established in accordance with articles L. 125-15 and L. 125-16 of the French environmental code. It presents, first, the NPPs (INBs no. 46, 74 and 100). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures carried out in 2013. The incidents and accidents which occurred in 2013, if any, are reported as well as the radioactive and non-radioactive effluents discharge in the environment. Finally, the radioactive materials and wastes generated by the facility are presented (type of waste, quantities, conditioning process) as well as the other pollutions. The document concludes with a presentation of the actions of communication and public information made by the direction of the facility. A glossary and the list of recommendations from the Committees for health, safety and working conditions are given in appendix

  11. Decommissioning of nuclear facilities: a growing activity in the world

    International Nuclear Information System (INIS)

    Anasco, Raul

    2001-01-01

    Nuclear power plants and nuclear facilities are no different from normal buildings and factories. Eventually, they become worn-out or old fashioned, too expensive to maintain or remodel. Decommissioning a nuclear facility is different from retiring other types because of the radioactivity involved. The most important consideration in nuclear decommissioning is to protect workers and the public from exposure to harmful levels of radiation. General criteria and strategies for the decommissioning of nuclear facilities are described as well as the present decommissioning activities of the Argentine CNEA (author)

  12. Current situation with the centralized storage facilities for non-power radioactive wastes in Latin American countries

    International Nuclear Information System (INIS)

    Benitez, Juan C.; Salgado, Mercedes; Idoyaga Navarro, Maria L.; Escobar, Carolina; Mallaupoma, Mario; Sbriz, Luciano; Moreno, Sandra; Gozalez, Olga; Gomez, Patricia; Mora, Patricia; Miranda, Alberto; Aguilar, Lola; Zarate, Norma; Rodriguez, Carmen

    2008-01-01

    Full text: Several Latin American (LA) countries have been firmly committed to the peaceful applications of ionizing radiations in medicine, industry, agriculture and research in order to achieve socioeconomic development in diverse sectors. Consequently the use of radioactive materials and radiation sources as well as the production of radioisotopes and labeled compounds may always produce radioactive wastes which require adequate management and, in the end, disposal. However, there are countries in the Latin American region whose radioactive waste volumes do not easily justify a national repository. Moreover, such facilities are extremely expensive to develop. It is unlikely that such an option will become available in the foreseeable future for most of these countries, which do not have nuclear industries. Storage has long been incorporated as a step in the management of radioactive wastes. In the recent years, there have been developments that have led some countries to consider whether the roles of storage might be expanded to provide longer-term care of long-live radioactive wastes The aim of this paper is to discuss the current situation with the storage facilities/conditions for the radioactive wastes and disused sealed radioactive sources in Latin-American countries. In some cases a brief description of the existing facilities for certain countries are provided. In other cases, when no centralized facility exists, general information on the radioactive inventories and disused sealed sources is given. (author)

  13. Nuclear chemistry counting facilities: requirements definition

    International Nuclear Information System (INIS)

    O'Brien, D.W.; Baker, J.

    1979-01-01

    In an effort to upgrade outdated instrumentation and to take advantage of current and imminent technologies the Nuclear Chemistry Division at Lawrence Livermore Laboratory is about to undertake a major upgrade of their low level radiation counting and analysis facilities. It is expected that such a project will make a more coordinated data acquisition and data processing system, reduce manual data handling operations and speed up data processing throughput. Before taking on a systems design it is appropriate to establish a definition of the requirements of the facilities. This report examines why such a project is necessary in the context of the current and projected operations, needs, problems, risks and costs. The authors also address a functional specification as a prelude to a system design and the design constraints implicit in the systems implementation. Technical, operational and economic assessments establish necessary boundary conditions for this discussion. This report also establishes the environment in which the requirements definition may be considered valid. The validity of these analyses is contingent on known and projected technical, scientific and political conditions

  14. STRESSFUL SITUATIONS IN THE WORK OF A MULTIPROFILE PEDIATRIC MEDICAL FACILITY'S CALL CENTER

    Directory of Open Access Journals (Sweden)

    I. M. Spivak

    2015-01-01

    Full Text Available Stressful situations in the work of a pediatric medical facility's call center are associated with patients' violation of social communication norms and aggressive behavior, as well as the operator's professional/maternal conflict. The following psychological resources facilitate better stress resistance of operators: self-confidence, mature and rational attitude, personal activity, inner satisfaction, optimism, emotional breadth and emotional colleague support. 

  15. Protection of nuclear facilities and nuclear materials against malevolent actions

    International Nuclear Information System (INIS)

    Cornu, P.; Aurelle, J.; Jalouneix, J.

    2001-01-01

    The french approach for considering malevolent actions affecting the design and operation of nuclear facilities is aimed at determining the extent to which the facilities are protected. When carrying out these studies, operating organizations have to demonstrate that their are complying with the objectives set by the Competent Authority for reducing the risk of internal or external malevolent actions. The approach to be followed consist to determine the sensitivity of each zone and to estimate the vulnerability of the most critical zones to each type of aggression. The sensitivity can be defined by the level of the radiological consequences resulting from a malevolent action. The estimation of the vulnerability is made of the extent to which it is difficult to carry out a malevolent action. 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. 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 the vulnerability of the most sensitive zones should be reduced to a minimum so that an acceptable level of protection can be provided for these areas. Emphasis will be paid on the defence in depth approach organized around prevention, management and mitigation measures. (authors)

  16. A trend of robotics in nuclear facilities

    International Nuclear Information System (INIS)

    Nakayama, Ryoichi

    1993-01-01

    In order to operate stably nuclear power stations, the periodic inspection determined by the law has been carried out once every year in Japan. For reducing the radiation exposure of workers and improving work efficiency and work quality, the automation and the use of robots have been promoted. Also in fuel reprocessing plants and the facilities for storing radioactive wastes, the remotely operated devices for handling uranium and plutonium are indispensable. The course of the development of the robots for nuclear power plants classified by ages is shown. The research and development have been advanced from special automatic machines of first generation since 1965, through versatile robots of second generation since 1980 to intellectual robots of third generation since 1985. Automatic fuel exchanger, control rod moving mechanism and the ultrasonic flaw detector for pipings are those of first generation. As those of second generation, various movable inspection robots and the manipulators for them were developed. The ultimate working robot completed in 1990 is that of third generation. As the trend of the practical use, monorail type inspection robots and underwater inspection robots and various manipulators are reported. (K.I.)

  17. Opening speech: nuclear power today - the situation in germany

    International Nuclear Information System (INIS)

    Gueldner, R.

    2005-01-01

    Nuclear power is experiencing an upswing worldwide. High prices of conventional fuels, discussions about the long-term continuity of supply, rising energy requirements, and the search for efficient ways of protecting the climate have moved nuclear power back into focus in a positive way. This is also true for Germany. In this country, nuclear power has gone through twelve very successful months since the 2004 Nuclear Technology Conference in Duesseldorf, as is borne out by the performance of all nuclear power plants in Germany. A change of mood towards a positive view of nuclear power is taking place in Germany. It is also seen, however, that the ''problem'' of final storage, which has been solved technically, is in urgent need of a political solution. German know-how in nuclear technology enjoys a high reputation internationally. For manufacturers and the associated supplier industries, this means excellent market opportunities, also for future projects, in view of worldwide demand. Various nuclear projects have progressed at long last: The Heinz Meier-Leibnitz research reactor (FRM-II) has been commissioned; the final stage of expansion of the Urenco uranium enrichment plant in Gronau has been approved; the license for a capacity increase in the ANF fuel fabrication plant in Lingen has been granted. Nuclear power is enjoying a high reputation also in the European Union. Major expansion plans exist in Asia, while increases in power and performance as well as life extensions can be observed in the United States. The world needs a sustainable energy mix - with nuclear power. (orig.)

  18. Decommissioning of nuclear facilities in Korea

    International Nuclear Information System (INIS)

    Hahn, Pil Soo

    2003-01-01

    In 1996, it was concluded that the first Korea research reactor (KRR-1) and the second Korea research reactor (KRR-2) would be shut down and decommissioned. The main reason for the decommissioning was that the facilities became old and has become surrounded by the urbanised community. And many difficulties, including the higher cost, were faced according to the enhanced regulations. Another reason was the introduction of a new research reactor 'HANARO' in 1995. A project to decommission the reactors was launched on January of 1997 with a goal of release of the site and buildings for unrestricted use by 2008. All the radioactive wastes generated are to be transported to the national repository, planned by the Korea Hydro and Nuclear Power Company (KHNP), and the final evaluation of the residual radioactivity will be made before the clearance of the site. As a first step of the project, a decommissioning plan, including the assessment of the environmental impact and the quality assurance program, was prepared and submitted to the government in 1998. It was approved, after its safety evaluation, by the Korea Institute of Nuclear Safety (KINS) in November of 2000. After some preparative works such as documentation of procedures, the decontamination and dismantling works for the laboratories and hot cells of KRR-2 were started in September, 2001 and finished in December, 2002. The spent fuels that had been generated from the reactors were transferred to the United States in 1998 and no spent fuel remained at the site. All the liquid waste, both operational and decommissioning, was very low in its radioactivity and was treated in a natural evaporation facility of 200 m3/year capacity, developed by KAERI. Especially the laundry waste was treated in a membrane filtering unit for the removal of surfactants before being introduced to the natural evaporator. The solid wastes were segregated and packed in the container of 4 m3, designed according to the ISO-1496, and also in

  19. A Swedish nuclear fuel facility and public acceptance

    Energy Technology Data Exchange (ETDEWEB)

    Andersson, Bengt A [ABB Atom (Sweden)

    1989-07-01

    For more than ten years the ABB Atom Nuclear Fuel Facility has gained a lot of public attention in Sweden. When the nuclear power debate was coming up in the middle of the seventies, the Nuclear Fuel Facility very soon became a spectacular object. It provided a possibility to bring factual information about nuclear power to the public. Today that public interest still exists. For ABB Atom the Facility works as a tool of information activities in several ways, as a solid base for ABB Atom company presentations. but also as a very practical demonstration of the nuclear power technology to the public. This is valid especially to satisfy the local school demand for a real life object complementary to the theoretical nuclear technology education. Beyond the fact that the Nuclear Fuel Facility is a very effective fuel production plant, it is not too wrong to see it as an important resource for education as well as a tool for improved public relations.

  20. A Swedish nuclear fuel facility and public acceptance

    International Nuclear Information System (INIS)

    Andersson, Bengt A.

    1989-01-01

    For more than ten years the ABB Atom Nuclear Fuel Facility has gained a lot of public attention in Sweden. When the nuclear power debate was coming up in the middle of the seventies, the Nuclear Fuel Facility very soon became a spectacular object. It provided a possibility to bring factual information about nuclear power to the public. Today that public interest still exists. For ABB Atom the Facility works as a tool of information activities in several ways, as a solid base for ABB Atom company presentations. but also as a very practical demonstration of the nuclear power technology to the public. This is valid especially to satisfy the local school demand for a real life object complementary to the theoretical nuclear technology education. Beyond the fact that the Nuclear Fuel Facility is a very effective fuel production plant, it is not too wrong to see it as an important resource for education as well as a tool for improved public relations

  1. Study on system integration of robots operated in nuclear fusion facility and nuclear power plant facilities

    International Nuclear Information System (INIS)

    Oka, Kiyoshi

    2004-07-01

    A present robot is required to apply to many fields such as amusement, welfare and protection against disasters. The are however only limited numbers of the robots, which can work under the actual conditions as a robot system. It is caused by the following reasons: (1) the robot system cannot be realized by the only collection of the elemental technologies, (2) the performance of the robot is determined by that of the integrated system composed of the complicated elements with many functions, and (3) the respective elements have to be optimized in the integrated robot system with a well balance among them, through their examination, adjustment and improvement. Therefore, the system integration of the robot composed of a large number of elements is the most critical issue to realize the robot system for actual use. In the present paper, I describe the necessary approaches and elemental technologies to solve the issues on the system integration of the typical robot systems for maintenance in the nuclear fusion facility and rescue in the accident of the nuclear power plant facilities. These robots work under the intense radiation condition and restricted space in place of human. In particular, I propose a new approach to realize the system integration of the robot for actual use from the viewpoints of not only the environment and working conditions but also the restructure and optimization of the required elemental technologies with a well balance in the robot system. Based on the above approach, I have a contribution to realize the robot systems working under the actual conditions for maintenance in the nuclear fusion facility and rescue in the accident of the nuclear power plant facilities. (author)

  2. Safety study of fire protection for nuclear fuel cycle facility

    International Nuclear Information System (INIS)

    2013-01-01

    Insufficiencies in the fire protection system of the nuclear reactor facilities were pointed out when the fire occurred due to the Niigata prefecture-Chuetsu-oki Earthquake in July, 2007. This prompted the revision of the fire protection safety examination guideline for nuclear reactors as well as commercial guidelines. The commercial guidelines have been endorsed by the regulatory body. Now commercial fire protection standards for nuclear facilities such as the design guideline and the management guideline for protecting fire in the Light Water Reactors (LWRs) are available, however, those to apply to the nuclear fuel cycle facilities such as mixed oxide fuel fabrication facility (MFFF) have not been established. For the improvement of fire protection system of the nuclear fuel cycle facilities, the development of a standard for the fire protection, corresponding to the commercial standard for LWRs were required. Thus, Japan Nuclear Energy Safety Organization (JNES) formulated a fire protection guidelines for nuclear fuel cycle facilities as a standard relevant to the fire protection of the nuclear fuel cycle facilities considering functions specific to the nuclear fuel cycle facilities. In formulating the guidelines, investigation has been conduced on the commercial guidelines for nuclear reactors in Japan and the standards relevant to the fire protection of nuclear facilities in USA and other countries as well as non-nuclear industrial fire protection standards. The guideline consists of two parts; Equipments and Management, as the commercial guidances of the nuclear reactor. In addition, the acquisition of fire evaluation data for a components (an electric cabinet, cable, oil etc.) targeted for spread of fire and the evaluation model of fire source were continued for the fire hazard analysis (FHA). (author)

  3. Nuclear energy: current situation and prospects to 2020.

    Science.gov (United States)

    Ion, Sue

    2007-04-15

    For close to half a century nuclear fission has been providing reliable supplies of electricity to the UK, with virtually no emissions of carbon dioxide. Over that period, the UK nuclear industry has avoided the emission of over one and a half billion tonnes of CO2. Yet no nuclear plant has been built in the UK for over two decades even though many of the stations in our current fleet are now within a decade or so of the end of their lifetime. Without new plants being ordered soon, the UK's nuclear capacity will decline dramatically, from 23% today to 3% post-2020--just as considerations of supply security and climate change are becoming increasingly important. Elsewhere in the world, many countries such as China, India, Japan, South Korea, Finland and France are building new stations. Other countries such as the USA, South Africa, and some nations that currently do not have nuclear stations (such as Indonesia and Poland) are making preparations for future nuclear stations. Globally capacity factors for nuclear plants are higher than they have ever been, averaging around 85% and with the best stations achieving well over 90%. Lifetime can be 60 years. That the economics of such stations compete well with other technologies is well founded and easily verifiable--especially in the face of rising fossil fuel prices and the pricing in of costs for CO2 emissions--both of which stand to improve the economics of nuclear energy still further. Waste volumes arising from modern plants are just a fraction of those of some earlier stations, and the technologies are in place to deal with them safely and effectively. Following recent reviews and international developments, there is growing confidence that internationally available competitive designs of nuclear plant will provide part of the solution to the UK's long-term energy needs.

  4. Some technical aspects of the nuclear material accounting and control at nuclear fuel cycle facilities

    International Nuclear Information System (INIS)

    Miller, O.A.; Babaev, N.S.; Gryazev, V.M.; Gadzhiev, G.I.; Gabeskiriya, V.Ya.

    1977-01-01

    The possibilities of nuclear material accounting and control are discussed at nuclear facilities of fuel cycle (WWER-type reactor, fuel fabrication plant, reprocessing plant and uranium enrichment facility) and zero energy fast reactor facility. It is shown that for nuclear material control the main method is the accounting with the application isotopic correlations at the reprocessing plant and enrichment facility. Possibilities and limitations of the application of destructive and non-destructive methods are discussed for nuclear material determinations at fuel facilities and their role in the accounting and safeguards systems as well as possibilities of the application of neutron method at a zero energy fast reactor facility [ru

  5. Stochastic Optimization for Nuclear Facility Deployment Scenarios

    Science.gov (United States)

    Hays, Ross Daniel

    Single-use, low-enriched uranium oxide fuel, consumed through several cycles in a light-water reactor (LWR) before being disposed, has become the dominant source of commercial-scale nuclear electric generation in the United States and throughout the world. However, it is not without its drawbacks and is not the only potential nuclear fuel cycle available. Numerous alternative fuel cycles have been proposed at various times which, through the use of different reactor and recycling technologies, offer to counteract many of the perceived shortcomings with regards to waste management, resource utilization, and proliferation resistance. However, due to the varying maturity levels of these technologies, the complicated material flow feedback interactions their use would require, and the large capital investments in the current technology, one should not deploy these advanced designs without first investigating the potential costs and benefits of so doing. As the interactions among these systems can be complicated, and the ways in which they may be deployed are many, the application of automated numerical optimization to the simulation of the fuel cycle could potentially be of great benefit to researchers and interested policy planners. To investigate the potential of these methods, a computational program has been developed that applies a parallel, multi-objective simulated annealing algorithm to a computational optimization problem defined by a library of relevant objective functions applied to the Ver ifiable Fuel Cycle Simulati on Model (VISION, developed at the Idaho National Laboratory). The VISION model, when given a specified fuel cycle deployment scenario, computes the numbers and types of, and construction, operation, and utilization schedules for, the nuclear facilities required to meet a predetermined electric power demand function. Additionally, it calculates the location and composition of the nuclear fuels within the fuel cycle, from initial mining through

  6. Safety of nuclear fuel cycle facilities. Safety requirements

    International Nuclear Information System (INIS)

    2008-01-01

    This publication covers the broad scope of requirements for fuel cycle facilities that, in light of the experience and present state of technology, must be satisfied to ensure safety for the lifetime of the facility. Topics of specific reference include aspects of nuclear fuel generation, storage, reprocessing and disposal. Contents: 1. Introduction; 2. The safety objective, concepts and safety principles; 3. Legal framework and regulatory supervision; 4. The management system and verification of safety; 5. Siting of the facility; 6. Design of the facility; 7. Construction of the facility; 8. Commissioning of the facility; 9. Operation of the facility; 10. Decommissioning of the facility; Appendix I: Requirements specific to uranium fuel fabrication facilities; Appendix II: Requirements specific to mixed oxide fuel fabrication facilities; Appendix III: Requirements specific to conversion facilities and enrichment facilities

  7. The State Surveillance over Nuclear Safety of Nuclear Facilities Act No. 28/1984

    International Nuclear Information System (INIS)

    1995-01-01

    The Act lays down responsibilities of the Czechoslovak Atomic Energy Commission in the field of state surveillance over nuclear safety of nuclear facilities; determines the responsibilities of nuclear safety inspectors in their inspection activities; specifies duties of bodies and corporations responsible for nuclear safety of nuclear facilities; stipulates the obligation to set up emergency plans; and specifies penalties imposed on corporations and individuals for noncompliance with nuclear safety provisions. The Act entered into force on 4 April 1984. (J.B.)

  8. The concept of the double-purpose electro-nuclear facility

    Energy Technology Data Exchange (ETDEWEB)

    Bergelson, B.P.; Balyuk, S.A. [Institute of theoretical and experimental physics, Moscow (Russian Federation)

    1995-10-01

    The parameters have been determined on a conceptual level of the electro-nuclear facility intended for electric power generation and minor actinide transmutation. Electro-nuclear facilities (ENFs) have been developed without apparent success for many years. The main difficulties are associated with high accelerator cost and absence of their own clearly defined place for ENFs in the nuclear-power complex. In recent years, however, the situation has changed in many aspects in connection with the rise in safety requirements for nuclear power industry and because of the necessity to decrease the equilibrium level of the long-lived radiotoxicity in particular. In the authors opinion double-purpose ENFs designed for power generation and tansmutation of minor actinides are promising. The results of conceptual investigations for such a facility being operated on liquid fuel in the condition of a uranium-plutonium fuel cycle are given here.

  9. A Review of Quantitative Situation Assessment Models for Nuclear Power Plant Operators

    International Nuclear Information System (INIS)

    Lee, Hyun Chul; Seong, Poong Hyun

    2009-01-01

    Situation assessment is the process of developing situation awareness and situation awareness is defined as 'the perception of the elements in the environment within a volume of time and space, the comprehension of their meaning and the projection of their status in the near future.' Situation awareness is an important element influencing human actions because human decision making is based on the result of situation assessment or situation awareness. There are many models for situation awareness and those models can be categorized into qualitative or quantitative. As the effects of some input factors on situation awareness can be investigated through the quantitative models, the quantitative models are more useful for the design of operator interfaces, automation strategies, training program, and so on, than the qualitative models. This study presents the review of two quantitative models of situation assessment (SA) for nuclear power plant operators

  10. Nuclear orientation facility at Charles University in Prague

    International Nuclear Information System (INIS)

    Rotter, M.; Trhlik, M.; Hubalovsky, S.; Srnka, A.; Dupak, J.; Ota, J.; Pari, P.

    2000-01-01

    A low temperature nuclear orientation facility was installed at Charles University in the laboratory of the Department of Low Temperature Physics on the Faculty of Mathematics and Physics in Prague. The solid state as well as nuclear physics research is pursued on this facility. (author)

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

    International Nuclear Information System (INIS)

    Alengry, P.

    1989-03-01

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

  12. Dealing with the Y2K problem in German nuclear facilities

    International Nuclear Information System (INIS)

    Hagemann, A.

    1999-01-01

    General situation concerning Y2K problem related to german nuclear facilities is presented. Nuclear material used i Germany is owned by EURATOM and Germany is responsible to EURATOM as well as IAEA inspections. Systems of concern are monitoring and control systems, safety related systems and physical protection systems. Present situation is as follows: responsible project teams are formed, Y2K sensitive equipment is identified, designers are contacted, compliance tests specified and schedule of the proof established as of end of August 1999. Experiences obtained in overcoming the Y2K risks are cited

  13. On-site habitability in the event of an accident at a nuclear facility

    International Nuclear Information System (INIS)

    1989-01-01

    This publication is intended to provide technical guidance and a methodology for regulatory bodies, designers, constructors and operators of nuclear facilities to assist them in assessing the current situation as regards on-site habitability for their specific nuclear facilities. Initially, the aim will be to ensure that the ''vital areas'' of the facility which are necessary for the safe operation and shutdown of the facility will remain habitable, in some cases continuously and in others transiently, in the event of an accident inside or outside the installation. The assessment procedure can be used not only for potential radiation accidents but also to consider the effects on habitability of those probable non-radiological events which, if not correctly and effectively countered, could lead to the development of potentially unsafe conditions in the facility itself. 30 refs, 4 figs, 8 tabs

  14. Nuclear safety and radiation protection report of the Saint-Alban Saint-Maurice nuclear facilities - 2014

    International Nuclear Information System (INIS)

    2015-01-01

    This safety report was established in accordance with articles L. 125-15 and L. 125-16 of the French environmental code. It presents, first, the NPPs (INBs no. 119 and 120). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2014, if any, are reported as well as the radioactive and non-radioactive effluents discharge in the environment. Finally, the radioactive materials and wastes generated by the facility are presented (type of waste, quantities, conditioning process). The document concludes with a presentation of the actions of communication and public information made by the direction of the facility. A glossary and the list of recommendations from the Committees for health, safety and working conditions are given in appendix

  15. Nuclear safety and radiation protection report of the Saint-Alban Saint-Maurice nuclear facilities - 2013

    International Nuclear Information System (INIS)

    2014-01-01

    This safety report was established in accordance with articles L. 125-15 and L. 125-16 of the French environmental code. It presents, first, the NPPs (INBs no. 119 and 120). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2013, if any, are reported as well as the radioactive and non-radioactive effluents discharge in the environment. Finally, the radioactive materials and wastes generated by the facility are presented (type of waste, quantities, conditioning process). The document concludes with a presentation of the actions of communication and public information made by the direction of the facility. A glossary and the list of recommendations from the Committees for health, safety and working conditions are given in appendix

  16. Decommissioning of nuclear fuel cycle facilities. Safety guide

    International Nuclear Information System (INIS)

    2001-01-01

    The objective of this Safety Guide is to provide guidance to regulatory bodies and operating organizations on planning and provision for the safe management of the decommissioning of non-reactor nuclear fuel cycle facilities. While the basic safety considerations for the decommissioning of nuclear fuel cycle facilities are similar to those for nuclear power plants, there are important differences, notably in the design and operating parameters for the facilities, the type of radioactive material and the support systems available. It is the objective of this Safety Guide to provide guidance for the shutdown and eventual decommissioning of such facilities, their individual characteristics being taken into account

  17. Decommissioning of nuclear facilities involving operations with uranium and thorium

    International Nuclear Information System (INIS)

    Shum, E.Y.; Neuder, S.M.

    1990-01-01

    When a licensed nuclear facility ceases operation, the U.S. Nuclear Regulatory Commission (NRC) ensures that the facility and its site are decontaminated to acceptable levels so they may safely be released for unrestricted public use. Because specific environmental standards or broad federal guidelines governing release of residual radioactive contamination have not been issued, NRC has developed ad hoc cleanup criteria for decommissioning nuclear facilities that involved uranium and thorium. Cleanup criteria include decontamination of buildings, equipment, and land. We will address cleanup criteria and their rationale; procedures for decommissioning uranium/thorium facilities; radiological survey designs and procedures; radiological monitoring and measurement; and cost-effectiveness to demonstrate compliance

  18. Emission of Tc-99 from nuclear facilities

    International Nuclear Information System (INIS)

    Luxenburger, H.J.; Schuettelkopf, H.; Bohn, B.

    1984-11-01

    No noticeable Tc-activities are emitted from nuclear power stations. The emissions with the gaseous effluents exceed but rarely the detection limit of 25 nCi/h. Likewise, the emission with the liquid effluents remains below the detection limit of about 0.5 nCi/m 3 . Neither can a remarkable emission be recorded from the facilities of the Central Decontamination Services Department (HDB) of KfK. The emissions from the evaporation system for low level solutions and from the evaporation system for low level solutions and from the incineration facility for solid wastes do not exceed or rarely exceed to a minor extent the detection limit of 0.3 pCi/m 3 waste air. Also with the liquid effluents only minor Tc-amounts are discharged of 0.3 nCi/m 3 at the maximum. In the distillate of the medium level solutions discharged from the Karlsruhe Reprocessing Plant (WAK) to HDB as so-called tritiated water 2 nCi/m 3 Tc-99 at the maximum are contained. Only in the gaseous effluents from the evaporation system for medium level solutions emissions of up to 14 pCi/m 3 can be detected. The detection limits are almost permanently exceeded by the gaseous effluents from WAK. Small amounts of Tc-99 of 7 pCi/m 3 exhaust air at the maximum are released to the environment. However, the amount of Tc accumulated over the sampling period is insignificant from the radioecological point of view. (orig./HP) [de

  19. Final report on DOE nuclear facilities

    International Nuclear Information System (INIS)

    1991-11-01

    Risk analysis policy and guidance should be developed, especially for the non-DOE nuclear facilities. Minimum standards should be set on issues including risk management, the scope and depth of risk analysis (e.g., site-wide analysis, worker risk), and approaches to treatment of external events. Continued vigilance is required in maintaining operation staffing levels at the DOE research and testing reactors. Safety Analysis Reports should be updated to reflect the evolving configurations of the facilities and the current safety analysis requirements. The high-level waste storage programs at Hanford, Savannah River and INEL were evaluated. The Department of Energy has not adopted a cleanup policy with specific, clear objectives. DOE should define the respective roles of Headquarters, the field offices, and the M ampersand O contractors. The proposed budget priority setting system should not be implemented. The plan to develop a nation-wide programmatic environmental impact statement (PEIS) should be rethought. An environmental impact statement on the total cleanup program is inconsistent with the localized nature of cleanup decisionmaking. DOE must provide for significant improvements in its radiation protection and safety programs to meet current, and future, technical, engineering, and scientific procedures and practices for controlling sources and contamination, performing external and internal dosimetry, and implementing incident response plans, including applicable protective action guides. The culture of safety is not yet well established at Rocky Flats. The philosophy of the Department of Energy and the management of Rocky Flats is not understood, accepted and believed by the work force. The Advisory Committee has serious concerns about whether DOE's current program at WIPP will be able to demonstrate, in a timely manner, compliance with EPA's proposed long-term performance and human intrusion requirements for disposal of TRU and high-level radioactive wastes

  20. World situation of atomic energy and nuclear fuel cycle

    International Nuclear Information System (INIS)

    Szili, G.

    1978-01-01

    At the International Conference organized by the IAEA in May 1976, several sections dealt with problems of the production of atomic energy and of the nuclear fuel cycle. However, the whole spectrum of these problems was discussed including problems of economic policy, politics and ethical problems, too. Reports were presented on trends of the development of atomic energy in developed and developing countries. Besides the systems of nuclear power plants and the trends of their development, the Conference attached prominent importance to the supply of nuclear fuels and to the fuel cycle, respectively. Owing to important factors, the reprocessing of the spent nuclear fuel was emphasized. The problem area of the treatment of radioactive wastes, the protection of workers in immediate contact and of environment against radiations, the possibilities of ensuring nuclear safety, the degrees of hazards and the methods of protection of fast breeder reactors and up-to-date equipments were discussed. In contrast to earlier conferences the complex problem of the correlation of atomic energy to public opinion played an important role, too. (P.J.)

  1. European Nuclear Decommissioning Training Facility II

    International Nuclear Information System (INIS)

    Demeulemeester, Y.

    2005-01-01

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

  2. Modern tornado design of nuclear and other potentially hazardous facilities

    International Nuclear Information System (INIS)

    Stevenson, J.D.; Zhao, Y.

    1996-01-01

    Tornado wind loads and other tornado phenomena, including tornado missiles and differential pressure effects, have not usually been considered in the design of conventional industrial, commercial, or residential facilities in the United States; however, tornado resistance has often become a design requirement for certain hazardous facilities, such as large nuclear power plants and nuclear materials and waste storage facilities, as well as large liquefied natural gas storage facilities. This article provides a review of current procedures for the design of hazardous industrial facilities to resist tornado effects. 23 refs., 19 figs., 13 tabs

  3. Remote intelligent nuclear facility monitoring in LabVIEW

    International Nuclear Information System (INIS)

    Kucewicz, J.C.; Argo, P.E.; Caffrey, M.; Loveland, R.C.; McNeil, P.J.

    1996-01-01

    A prototype system implemented in LabVIEW for the intelligent monitoring of the movement of radioactive' material within a nuclear facility is presented. The system collects and analyzes radiation sensor and video data to identify suspicious movement of material within the facility. The facility system also transmits wavelet- compressed data to a remote system for concurrent monitoring. 2 refs., 2 figs

  4. Energy supply, nuclear power, and the international energy situation

    International Nuclear Information System (INIS)

    Pierer, H. von

    1991-01-01

    The Chernobyl accident has greatly intensified the readiness for international cooperation on problems of reactor safety and for exchanges of operating experience. That accident was more than a regional event. If all psychological and political consequences are taken into account, its international significance is apparent. In principle, it demonstrated not the lack of safety of nuclear power plants generally, but rather that of the Soviet RBMK reactor line, which would not have been licensed in any Western country because of its inherent unsafety. In the long run, the worldwide acceptance of nuclear power can be regained and stabilized only by an open dialog and by international exchanges of experience. The pronounced growth of the world's population requires energy policy to think beyond national frontiers. The rising energy requirement permits of no other decision than to exploit all technically feasible and economically viable as well as ecologically tolerable sources of energy. This includes nuclear power as well as solar energy. (orig.) [de

  5. PRTR/309 building nuclear facility preliminary

    International Nuclear Information System (INIS)

    Cornwell, B.C.

    1994-01-01

    The hazard classification of the Plutonium Recycle Test Reactor (PRTR)/309 building as a ''Radiological Facility'' and the office portions as ''Other Industrial Facility'' are documented by this report. This report provides: a synopsis of the history and facility it's uses; describes major area of the facility; and assesses the radiological conditions for the facility segments. The assessment is conducted using the hazard category threshold values, segmentation methodology, and graded approach guidance of DOE-STD-1027-92

  6. Seismic safety assessment of nuclear facilities other than NPPs

    International Nuclear Information System (INIS)

    Coman, O.; Dragomirescu, A.; Kope, F.; Zemtev, N.

    2003-01-01

    Many research nuclear facilities are much simpler as compared with a Nuclear Power Plant (NPP) and the accident scenarios corresponding to an external initiating events and the relevant shutdown paths are much easier to be identified. Therefore, simpler methods than an EE-PSA can be often involved in the evaluation of the overall risk associated to such nuclear facilities in respect to External Event Hazards. (author)

  7. Environmental radiation monitoring around the nuclear facilities

    International Nuclear Information System (INIS)

    Lee, H.D.; Lee, Y.B.; Lee, W.Y.; Park, D.W.; Chung, B.G.

    1980-01-01

    For the KAERI site, various environmental samples were collected three times a month, and the natural environmental radiation levels were also measured at each sampling point. Measurements for gross alpha and beta radioactivities of the samples were routinely measured for all samples. Strontium-90 concentrations were also analysed for the fallout and air samples collected daily basis on the roof of the main building. Accumulated exposure including the possibility of determination of low level environmental radiation field by employing thermoluminescent dosimeter, CaSO 4 : Dsub(y)-0.4 teflon disc type, at 6 posts in on-site of the KAERI. As for Kori site, at 19 points of ON, OFF-site, and at the same time the environmental radiation exposure rate at each sampling point were measured. Several environmental samples such as surface soil, pine needles, water samples, milk sample and pasture samples were collected and analysed on a quarterly basis. As a result of the survey it can be said that no significant release of radiation to the environment due to the operations of nuclear facilities including research reactor at the KAERI and power reactor at the Kori has been found during the period of the survey and monitoring. (author)

  8. Water intaking facility of nuclear power plant

    International Nuclear Information System (INIS)

    Koyama, Kazuhito; Iwata, Nobukatsu; Ochiai, Kanehiro.

    1994-01-01

    In a water intaking facility of a nuclear power plant, a dam is disposed at a position near a sea shore for preventing sea water introduced in open conduit from flowing to the outer sea upon ebbing of tsunamis. The upper end of the dam is set lower than the lower end of a water-intake pipe of a sea water pump of an ordinary system. A water-intake pipe is disposed to such a length that a sea water pump of an emergency system continues to suck the sea water when the water level of the introduced sea water is lowered than the upper end of the dam during the ebb tide. In addition, a means for stopping the operation of the sea water pump of the ordinary system upon starting of the ebb is disposed. Upon reactor scram for occurrence of earthquakes and the like, either the sea water pump in the ordinary system or the seawater pump in the emergency system operates to ensure required amount of sea water for cooling the reactor. In addition, even if the level of the sea water is lowered than the upper end of the dam, since the sea water pump in the emergency system continues to suck sea water, unnecessary suction for sea water by the ordinary sea water pumps can be eliminated. (N.H.)

  9. Westinghouse Savannah River Company (WSRC) approach to nuclear facility maintenance

    International Nuclear Information System (INIS)

    Harrison, D.W.

    1991-01-01

    The Savannah River Site (SRS) in South Carolina is a 300+ square mile facility owned by the US Department of Energy (DOE) and operated by Westinghouse Savannah River Company (WSRC), the prime contractor; Bechtel Savannah River, Incorporated (BSRI) is a major subcontractor. The site has used all of the five nuclear reactors and it has the necessary nuclear materials processing facilities, as well as waste management and research facilities. The site has produced materials for the US nuclear arsenal and various isotopes for use in space research and nuclear medicine for more than 30 years. In 1989, WSRC took over as prime contractor, replacing E.I. du Pont de Nemours and Company. At this time, a concentrated effort began to more closely align the operating standards of this site with those accepted by the commercial nuclear industry of the United States. Generally, this meant acceptance of standards of the Institute of Nuclear Power Operations (INPO) for nuclear-related facilities at the site. The subject of this paper is maintenance of nuclear facilities and, therefore, excludes discussion of the maintenance of non-nuclear facilities and equipment

  10. Regulatory control of nuclear facility valves and their actuators

    International Nuclear Information System (INIS)

    1993-01-01

    The methods and procedures by which the Finnish Centre for Radiation and Nuclear Safety (STUK) regulates valves and their actuators in nuclear power plants and in other nuclear facilities are specified in the guide. The scope of regulation depends on the Safety Class of the valve and the actuator in question. The Safety Classification principles for the systems, structures and components of the nuclear power plants are described in the guide YVL 2.1 and the regulatory control of the nuclear facility safety valves is described in the guide YVL 5.4

  11. Report on operation of nuclear facilities in Slovenia in 1991

    International Nuclear Information System (INIS)

    1992-11-01

    Slovenian Nuclear Safety Administration (SNSA) is responsible for: nuclear safety, transport of nuclear and radioactive materials, safeguarding nuclear materials, and conducting regulatory process related to liability for nuclear damage, qualification and training of operators at nuclear facilities, quality assurance and inspection of nuclear facilities. The major nuclear facility supervised by SNSA is the Nuclear Power Plant in Krsko with a pressurized water reactor of 632 MW electric power. Beside the nuclear power plant, TRIGA Mark 11 Research Reactor of 250 kW thermal power operates within the Reactor Center of Jozef Stefan Institute. There is an interim storage of low and medium radioactive waste at the Reactor Center. Also the Uranium mine Zirovski Vrh was supervised by SNSA. All the nuclear power facilities in Republic of Slovenia were operating safely in 1991. There were no significant events that could be evaluated as a safety problem or a breach of technical specifications. A great part of activities of SNSA was focused on the next visit of the IAEA OSART team (Operational Safety Assessment Review Team) in Krsko Nuclear Power Plant and on the visit of the INSARR mission (Integrated Safety Assessment of Research Reactors) for the TRIGA Mark 11 Research Reactor. (author)

  12. Data bank for nuclear-physical studies in educational facilities

    International Nuclear Information System (INIS)

    Boboshin, I.N.; Varlamov, V.V.; Ishkhanov, B.S.; Kapitonov, I.M.; Lenskaya, N.A.; Surgutanov, V.V.; Khoronenko, A.A.; Chernyaev, A.P.

    1986-01-01

    Purposes and tasks of nuclear data Centers of the USSR Ministry of Education are discussed in short. Files of both bibliographic and factographic nuclear-physical data widely used with the Centres to provide the state organizations and scientists, first of all educational facilities, with nuclear data to increase effectiveness of fundamental and applied investigations and educational process are described

  13. The impact of social and economical situation on nuclear knowledge management in Serbia

    International Nuclear Information System (INIS)

    Pesic, M.; Nikolic, D.

    2004-01-01

    The former Yugoslavia nuclear programs had been supported by comprehensive research and development, educational programs and pertinent training in country and abroad. Three research reactors and one nuclear power plant (NPP) were constructed and operated with significant participation of domestic experts. Since 1989, the nuclear expertise has been deteriorated considerably in Serbia due to adopted law on ban for NPP construction, isolation of the country due to the UN sanctions and weak economical situation. Major research and development programs were cancelled, nuclear courses at the University revoked, many professionals left the country, and the loss of nuclear knowledge and expertise was inevitable. A new nuclear program related to remediation of nuclear and radiation safety in Serbia has been launched two years ago. This paper, beside overview of past nuclear knowledge management programs, emphasizes the need for nuclear expertise and the lack of nuclear professionals to carry out new program. (authors)

  14. A study on domino effect in nuclear fuel cycle facilities

    International Nuclear Information System (INIS)

    Bozzolan, Jean-Claude

    2006-01-01

    Accidents caused by domino effect are among the most severe accidents in the chemical and process industry. Although the destructive potential of these accidental scenarios is widely known, little attention has been paid to this problem in the technical literature and a complete methodology for quantitative assessment of domino accidents contribution to industrial risk is still lacking. The present study proposed a systematic procedure for the quantitative assessment of the risk caused by domino effect in chemical plants that are part of nuclear fuel cycle plants. This work is based on recent advances in the modeling of fire and explosion damage to process equipment due to different escalation vectors (heat radiation, overpressure and fragment projection). Available data from literature and specific vulnerability models derived for several categories of process equipment had been used in the present work. The proposed procedure is applied to a typical storage area of a reconversion plant situated in a complex that shelters other nuclear fuel cycle facilities. The top-events and escalation vectors are identified, their consequences estimated and credible domino scenarios selected on the basis of their frequencies. (author)

  15. Childhood leukemia around five nuclear facilities in Canada

    International Nuclear Information System (INIS)

    Elaguppillai, V.

    1992-05-01

    As a result of public concern over the incidence of leukemia around the Sellafield nuclear fuel reprocessing plant, the Canadian Atomic Energy Control Board commissioned a study to test for similar clustering around licensed nuclear facilities in Ontario. In this study the incidence and mortality of leukemia among children up to the age of 14 years born within a radius of about 25 km from five different types of facilities were compared to the provincial average. The facilities considered were the Pickering Nuclear Generating Station, the Bruce Nuclear Power Development, the uranium conversion facility at Port Hope, the uranium mine and mill facilities in Elliot Lake, and the Chalk River Laboratories. The ratio of observed to expected childhood leukemias was around unity at the 95 percent confidence level, indicating that the occurrence of the disease is not significantly different from the provincial average. The sample size is not large enough to distinguish between a change occurrence and a true excess or deficit. (table)

  16. STACY and TRACY: nuclear criticality experimental facilities under construction

    International Nuclear Information System (INIS)

    Kobayashi, I.; Takeshita, I.; Yanagisawa, H.; Tsujino, T.

    1992-01-01

    Japan Atomic Energy Research Institute is constructing a Nuclear Fuel Cycle Safety Engineering Research Facility, NUCEF, where the following research themes essential for evaluating safety problems relating to back-end technology in nuclear fuel cycle facilities will be studied: nuclear criticality safety research; research on advanced reprocessing processes and partitioning; and research on transuranic waste treatment and disposal. To perform nuclear criticality safety research related to the reprocessing of light water reactor spent fuels, two criticality experimental facilities, STACY and TRACY, are under construction. STACY (Static Criticality Facility) will be used for the study of criticality conditions of solution fuels, uranium, plutonium and their mixtures. TRACY (Transient Criticality Facility) will be used to investigate criticality accident phenomena with uranium solutions. The construction progress and experimental programmes are described in this Paper. (author)

  17. Research and test facilities required in nuclear science and technology

    International Nuclear Information System (INIS)

    2009-01-01

    Experimental facilities are essential research tools both for the development of nuclear science and technology and for testing systems and materials which are currently being used or will be used in the future. As a result of economic pressures and the closure of older facilities, there are concerns that the ability to undertake the research necessary to maintain and to develop nuclear science and technology may be in jeopardy. An NEA expert group with representation from ten member countries, the International Atomic Energy Agency and the European Commission has reviewed the status of those research and test facilities of interest to the NEA Nuclear Science Committee. They include facilities relating to nuclear data measurement, reactor development, neutron scattering, neutron radiography, accelerator-driven systems, transmutation, nuclear fuel, materials, safety, radiochemistry, partitioning and nuclear process heat for hydrogen production. This report contains the expert group's detailed assessment of the current status of these nuclear research facilities and makes recommendations on how future developments in the field can be secured through the provision of high-quality, modern facilities. It also describes the online database which has been established by the expert group which includes more than 700 facilities. (authors)

  18. General problems specific to hot nuclear materials research facilities

    International Nuclear Information System (INIS)

    Bart, G.

    1996-01-01

    During the sixties, governments have installed hot nuclear materials research facilities to characterize highly radioactive materials, to describe their in-pile behaviour, to develop and test new reactor core components, and to provide the industry with radioisotopes. Since then, the attitude towards the nuclear option has drastically changed and resources have become very tight. Within the changed political environment, the national research centres have defined new objectives. Given budgetary constraints, nuclear facilities have to co-operate internationally and to look for third party research assignments. The paper discusses the problems and needs within experimental nuclear research facilities as well as industrial requirements. Special emphasis is on cultural topics (definition of the scope of nuclear research facilities, the search for competitive advantages, and operational requirements), social aspects (overageing of personnel, recruitment, and training of new staff), safety related administrative and technical issues, and research needs for expertise and state of the art analytical infrastructure

  19. Space Nuclear Thermal Propulsion (SNTP) Air Force facility

    Science.gov (United States)

    Beck, David F.

    The Space Nuclear Thermal Propulsion (SNTP) Program is an initiative within the US Air Force to acquire and validate advanced technologies that could be used to sustain superior capabilities in the area or space nuclear propulsion. The SNTP Program has a specific objective of demonstrating the feasibility of the particle bed reactor (PBR) concept. The term PIPET refers to a project within the SNTP Program responsible for the design, development, construction, and operation of a test reactor facility, including all support systems, that is intended to resolve program technology issues and test goals. A nuclear test facility has been designed that meets SNTP Facility requirements. The design approach taken to meet SNTP requirements has resulted in a nuclear test facility that should encompass a wide range of nuclear thermal propulsion (NTP) test requirements that may be generated within other programs. The SNTP PIPET project is actively working with DOE and NASA to assess this possibility.

  20. [Assessment of modern radioecological situation at nuclear explosion "Chagan" (Balapan Site, Semipalatinsk Nuclear Test Site, Kazakhstan)].

    Science.gov (United States)

    Evseeva, T I; Maĭstrenko, T A; Geras'kin, S A; Belykh, E S; Umarov, M A; Sergeeva, I Iu; Sergeev, V Iu

    2008-01-01

    Results on estimation of modern radioecological situation at nuclear explosion "Chagan" based on large-scale cartographic studies (1:25000) of a test area (4 km2) are presented. Maximum gamma-irradiation doses were observed at bulk of ground surrounded a crater and at radioactive fall-outs extended to the North-East and to the SouthWest from the crater. Based on data on artificial radionuclide specific activity most part of soil samples were attributed to radioactive wastes according to IAEA (1996) and OSPORB (1999). Natural decrease of soil radioactivity up to safety level due to 60Co, 137Cs, 90Sr, 152Eu, 154Eu radioactive decay and 241Am accumulation-decay will not take place within the next 60 years at the studied area.

  1. Discharges of [sup 14]C from nuclear facilities; Implication in environmental science

    Energy Technology Data Exchange (ETDEWEB)

    Iwakura, Tetsuo (Japan Chemical Analysis Center, Chiba (Japan))

    1993-10-01

    At present as C-14 existing in environment, there are that formed by cosmic ray in nature, by nuclear explosion experiment and released from nuclear facilities. As for the former two, the actual situation has been grasped, but the last one lacks the sure information as the range of its influence is local. In this study, the actual situation was explored based on the numerical evaluation of the amount generated in nuclear facilities and the investigative and analytical data by actual measurement. The rate of formation of natural C-14 is closely related to the variation of cosmic ray intensity and energy spectra. The specific radioactivity is 12.9 - 15.3 dpm/g, and it lowers due to the Suess effect, namely the increase of dead carbon. The C-14 due to nuclear explosion experiment reached the highest level of twice as much as the natural level in 1963, but thereafter, it decreased, and at present, it is 15-20% more than the natural level. The nuclear reaction and the reaction cross section of C-14 formation in LWRs, LMFBRs and HTGRs are shown. The formation of C-14 in fuel, core structures and cooling water of LWRs and in other types of reactors, and the examples of C-14 measurement around nuclear facilities are reported. (K.I.).

  2. Criteria, standards and policies regarding decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    Detilleux, E.; Lennemann, W.L.

    1977-01-01

    At the end of this century, there will probably be around 2500 operating nuclear power reactors, along with all the other nuclear fuel cycle facilities supporting their operation. Eventually these facilities, one by one, will be shut down and it will be necessary to dispose of them as with any redundant industrial facility or plant. Some parts of a nuclear fuel cycle facility can be dismantled by conventional methods, but those parts which have become contaminated with radioactive nuclear products or induced radioactivity must be subject to rigid controls and restrictions and handled by special dismantling and disposal procedures. In many cases, the resulting quantity of radioactive waste is likely to be relatively large and dismantling quite costly. Decommissioning nuclear facilities is a multifaceted problem involving planners, design engineers, operators, waste managers and regulatory authorities. Preparation for decommissioning should begin as early as site selection and plant design. The corner stone for the preparation of a decommissioning programme is the definition of its extent, meeting the requirements for public and environmental protection during the period that the radioactive material is of concern. The paper discusses the decontamination and decommissioning experience at the Eurochemic fuel reprocessing plant, the implications and the knowledge gained from this experience. It includes the results of technical reviews made by the Nuclear Energy Agency of OECD and the International Atomic Energy Agency regarding decommissioning nuclear facilities. The paper notes the special planning that should be arranged between those responsible for the nuclear facility and competent public authorities who should jointly make a realistic determination of the eventual disposition of the nuclear facility, even before it is built. Recommendations cover the responsibilities of nuclear plant entrepreneurs, designers, operators, and public and regulatory authorities

  3. Ground test facility for nuclear testing of space reactor subsystems

    International Nuclear Information System (INIS)

    Quapp, W.J.; Watts, K.D.

    1985-01-01

    Two major reactor facilities at the INEL have been identified as easily adaptable for supporting the nuclear testing of the SP-100 reactor subsystem. They are the Engineering Test Reactor (ETR) and the Loss of Fluid Test Reactor (LOFT). In addition, there are machine shops, analytical laboratories, hot cells, and the supporting services (fire protection, safety, security, medical, waste management, etc.) necessary to conducting a nuclear test program. This paper presents the conceptual approach for modifying these reactor facilities for the ground engineering test facility for the SP-100 nuclear subsystem. 4 figs

  4. Design aspects of radiological safety in nuclear facilities

    International Nuclear Information System (INIS)

    Patkulkar, D.S.; Purohit, R.G.; Tripathi, R.M.

    2014-01-01

    In order to keep operational performance of a nuclear facility high and to keep occupational and public exposure ALARA, radiological safety provisions must be reviewed at the time of facility design. Deficiency in design culminates in deteriorated system performance and non adherence to safety standards and could sometimes result in radiological incident. Important radiological aspects relevant to safety were compiled based on operating experiences, design deficiencies brought out from past nuclear incidents, experience gained during maintenance, participation in design review of upcoming nuclear facilities and radiological emergency preparedness

  5. Training of nuclear facility personnel: boon or boondoggle

    International Nuclear Information System (INIS)

    Remick, F.J.

    1975-01-01

    The training of nuclear facility personnel has been a requirement of the reactor licensing process for over two decades. However, the training of nuclear facility personnel remains a combination of boon and boondoggle. The opportunity to develop elite, well trained, professionally aggressive reactor operation staffs is not being realized to its full potential. Improvements in the selection of personnel, training programs, operational tools and professional pride can result in improved plant operation and contribute to improved plant capacity factors. Industry, regulatory agencies, professional societies and universities can do much to improve standards and quality of the training of nuclear facility personnel and to improve the professional level of plant operation

  6. History of health studies around nuclear facilities: a methodologival consideration

    International Nuclear Information System (INIS)

    Tokuhata, G.K.; Smith, M.W.

    1981-01-01

    A brief historical review was made of low-level radiation studies for general populations living around nuclear facilities. In addition, technical and methodological problems were identified and discussed which often arise in all epidemiological studies designed to determine the possible health effects of low-level radiation released from nuclear facilities. Need for extremely large populations for prospective cancer studies was discussed, but accompanying ascertainment difficulties were also emphasized. More epidemiological studies are needed to provide adequate assessment of the potential health hazards of nuclear facilities

  7. Criteria, standards and policies regarding decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    Detilleux, E.; Lennemann, W.

    1977-01-01

    The paper discusses the decontamination and decommissioning experiences encountered at the Eurochemic fuel reprocessing plant, their implications and the knowledge gained from these experiences. It includes the results of technical reviews made by the Nuclear Energy Agency of OECD and the International Atomic Energy Agency regarding decommissioning nuclear facilities. The conlusions which are presented should weigh heavily in the considerations of the national authorities involved in regulating nuclear power programmes. The paper notes the special planning that should be arranged between those responsible for the nuclear facility and competent public authorities who jointly should make a realistic determination of the eventual disposition of the nuclear facility, even before it is built. Recommendations cover the responsibilities of nuclear plant entrepreneurs, designers, operators, and public and regulatory authorities [fr

  8. Development situation about the Canadian CANDU Nuclear Power Generating Stations

    Energy Technology Data Exchange (ETDEWEB)

    Jeon, Yu Mi; Kim, Yong Hee; Park, Joo Hwan

    2009-07-15

    The CANDU reactor is the most versatile commercial power reactor in the world. The acronym 'CANDU', a registered trademark of Atomic Energy of Canada Limited, stands for 'CANada Deuterium Uranium'. CANDU uses heavy water as moderator and uranium (originally, natural uranium) as fuel. All current power reactors in Canada are of the CANDU type. Canada exports CANDU type reactor in abroad. CANDU type is used as the nuclear power plants to produce electrical. Today, there are 41 CANDU reactors in use around the world, and the design has continuously evolved to maintain into unique technology and performance. The CANDU-6 power reactor offers a combination of proven, superior and state-of-the-art technology. CANDU-6 was designed specifically for electricity production, unlike other major reactor types. One of its characteristics is a very high operating and fuel efficiency. Canada Nuclear Power Generating Stations were succeeded in a commercial reactor of which the successful application of heavy water reactor, natural uranium method and that on-power fuelling could be achieved. It was achieved through the joint development of a major project by strong support of the federal government, public utilities and private enterprises. The potential for customization to any country's needs, with competitive development and within any level of domestic industrial infrastructure, gives CANDU technology strategic importance in the 21st century.

  9. Development situation about the Canadian CANDU Nuclear Power Generating Stations

    International Nuclear Information System (INIS)

    Jeon, Yu Mi; Kim, Yong Hee; Park, Joo Hwan

    2009-07-01

    The CANDU reactor is the most versatile commercial power reactor in the world. The acronym 'CANDU', a registered trademark of Atomic Energy of Canada Limited, stands for 'CANada Deuterium Uranium'. CANDU uses heavy water as moderator and uranium (originally, natural uranium) as fuel. All current power reactors in Canada are of the CANDU type. Canada exports CANDU type reactor in abroad. CANDU type is used as the nuclear power plants to produce electrical. Today, there are 41 CANDU reactors in use around the world, and the design has continuously evolved to maintain into unique technology and performance. The CANDU-6 power reactor offers a combination of proven, superior and state-of-the-art technology. CANDU-6 was designed specifically for electricity production, unlike other major reactor types. One of its characteristics is a very high operating and fuel efficiency. Canada Nuclear Power Generating Stations were succeeded in a commercial reactor of which the successful application of heavy water reactor, natural uranium method and that on-power fuelling could be achieved. It was achieved through the joint development of a major project by strong support of the federal government, public utilities and private enterprises. The potential for customization to any country's needs, with competitive development and within any level of domestic industrial infrastructure, gives CANDU technology strategic importance in the 21st century

  10. Beneficial Re-use of Decommissioned Former Nuclear Facilities

    International Nuclear Information System (INIS)

    Boing, L.E.

    1997-01-01

    With the decision to decommission a nuclear facility, it is necessary to evaluate whether to fully demolish a facility or to re-use the facility in some capacity. This evaluation is often primarily driven by both the past mission of the site and the facility and the site's perceived future mission. In the case where the facility to be decommissioned is located within a large research or industrial complex and represents a significant resource to the site's future mission, it may be a perfect candidate to be re-used in some fashion. However, if the site is a rather remote older facility with little chance of being modified to today's standards for its re-use, the chances for its re-use will be substantially reduced. In this presentation, some specific cases of former nuclear facilities being decommissioned and re-used will be reviewed and some factors required to be considered in making this decision will be reviewed

  11. Situation of the radioactive waste management and the employee radiation exposure in commercial power generation reactor facilities in fiscal 1980

    International Nuclear Information System (INIS)

    1981-01-01

    (1) Situation of the radioactive waste management in commercial power generating reactor facilities: The owners of power generation reactor facilities are obligated not to exceed the target dose around the sites by law in the radioactive waste management. The release of radioactive gaseous and liquid wastes and the storage of radioactive solid wastes in respective reactor facilities in fiscal 1980 are presented in tables (for the former, the data since 1971 are also given). The release control values were satisfied in all the facilities. (2) Situation of employe radiation exposure in commercial power generating reactor facilities: The owners of power generation reactor facilities are obligated not to exceed the permissible exposure doses by law. The Employe exposure doses in respective reactor facilities in fiscal 1980 are given in tables. All exposure doses were below the permissible levels. (J.P.N.)

  12. The optimization of nuclear power plants operation modes in emergency situations

    Science.gov (United States)

    Zagrebayev, A. M.; Trifonenkov, A. V.; Ramazanov, R. N.

    2018-01-01

    An emergency situations resulting in the necessity for temporary reactor trip may occur at the nuclear power plant while normal operating mode. The paper deals with some of the operation c aspects of nuclear power plant operation in emergency situations and during threatened period. The xenon poisoning causes limitations on the variety of statements of the problem of calculating characteristics of a set of optimal reactor power off controls. The article show a possibility and feasibility of new sets of optimization tasks for the operation of nuclear power plants under conditions of xenon poisoning in emergency circumstances.

  13. Decommissioning of nuclear facilities: Decontamination, disassembly and waste management

    International Nuclear Information System (INIS)

    1983-01-01

    The term 'decommissioning', as used within the nuclear industry, means the actions taken at the end of a facility's useful life to retire the facility from service in a manner that provides adequate protection for the health and safety of the decommissioning workers, the general public, and for the environment. These actions can range from merely closing down the facility and a minimal removal of radioactive material coupled with continuing maintenance and surveillance, to a complete removal of residual radioactivity in excess of levels acceptable for unrestricted use of the facility and its site. This latter condition, unrestricted use, is the ultimate goal of all decommissioning actions at retired nuclear facilities. The purpose of this report is to provide an information base on the considerations important to decommissioning, the methods available for decontamination and disassembly of a nuclear facility, the management of the resulting radioactive wastes, and the areas of decommissioning methodology where improvements might be made. Specific sections are devoted to each of these topics, and conclusions are presented concerning the present status of each topic. A summary of past decommissioning experience in Member States is presented in the Appendix. The report, with its discussions of necessary considerations, available operational methods, and waste management practices, together with supporting references, provides an appreciation of the activities that comprise decommissioning of nuclear facilities. It is anticipated that the information presented in the report should prove useful to persons concerned with the development of plans for the decommissioning of retired nuclear facilities

  14. Supervision of the safety culture in nuclear facilities

    International Nuclear Information System (INIS)

    2014-11-01

    This brochure issued by the Swiss Federal Nuclear Safety Inspectorate ENSI reports on safety culture aspects in nuclear facilities and ENSI’s activities as a supervisory instance. ENSI is the independent supervisory authority for the nuclear sector in Switzerland. A definition of safety culture is presented and the development of the concepts used in its monitoring are discussed. The main attributes of a good safety culture are discussed. Further, the conceptual basics and principles of such monitoring are looked at and the methods used for the supervision of safety culture in nuclear facilities are described

  15. Nuclear Science: a survey of funding, facilities, and manpower

    International Nuclear Information System (INIS)

    1975-01-01

    In 1973 the Committee on Nuclear Science of the National Research Council initiated a re-examination of aspects (funding, manpower, and facilities) of the organization and operation of nuclear science research in order to evaluate any changes in the preceding four years and implications of such changes. The reports of the three ad hoc panels established for this purpose (funding and level of effort, nuclear facilities, manpower and education) are presented. Although they identify current problems in nuclear science, these reports do not provide simple solutions; rather, they attempt to provide updated information for use as background for continuing decisions

  16. Situation awareness and trust in computer-based procedures in nuclear power plant operations

    Energy Technology Data Exchange (ETDEWEB)

    Throneburg, E. B.; Jones, J. M. [AREVA NP Inc., 7207 IBM Drive, Charlotte, NC 28262 (United States)

    2006-07-01

    Situation awareness and trust are two issues that need to be addressed in the design of computer-based procedures for nuclear power plants. Situation awareness, in relation to computer-based procedures, concerns the operators' knowledge of the plant's state while following the procedures. Trust concerns the amount of faith that the operators put into the automated procedures, which can affect situation awareness. This paper first discusses the advantages and disadvantages of computer-based procedures. It then discusses the known aspects of situation awareness and trust as applied to computer-based procedures in nuclear power plants. An outline of a proposed experiment is then presented that includes methods of measuring situation awareness and trust so that these aspects can be analyzed for further study. (authors)

  17. Situation awareness and trust in computer-based procedures in nuclear power plant operations

    International Nuclear Information System (INIS)

    Throneburg, E. B.; Jones, J. M.

    2006-01-01

    Situation awareness and trust are two issues that need to be addressed in the design of computer-based procedures for nuclear power plants. Situation awareness, in relation to computer-based procedures, concerns the operators' knowledge of the plant's state while following the procedures. Trust concerns the amount of faith that the operators put into the automated procedures, which can affect situation awareness. This paper first discusses the advantages and disadvantages of computer-based procedures. It then discusses the known aspects of situation awareness and trust as applied to computer-based procedures in nuclear power plants. An outline of a proposed experiment is then presented that includes methods of measuring situation awareness and trust so that these aspects can be analyzed for further study. (authors)

  18. Status of the support researches for the regulation of nuclear facilities decommissioning in Japan

    International Nuclear Information System (INIS)

    Masuda, Yusuke; Iguchi, Yukihiro; Kawasaki, Satoru; Kato, Masami

    2011-01-01

    In Japan, 4 nuclear power stations are under decommissioning and some nuclear fuel cycle facilities are expected to be decommissioned in the future. On the other hand, the safety regulation of decommissioning of nuclear facilities was changed by amending act in 2005. An approval system after review process of decommissioning plan was adopted and applied to the power stations above. In this situation, based on the experiences of the new regulatory system, the system should be well established and moreover, it should be improved and enhanced in the future. Nuclear Industry and Safety Agency (NISA) is in charge of regulation of commercial nuclear facilities in Japan and decommissioning of them is included. Japan Nuclear Energy Safety Organization (JNES) is in charge of technical supports for NISA as a TSO (Technical Support Organization) also in this field. As for decommissioning, based on regulatory needs, JNES has been continuing research activities from October 2003, when JNES has been established. Considering the 'Prioritized Nuclear Safety Research Plan (August 2009)' of the Nuclear Safety Commission of Japan and the situation of operators facilities, 'Regulatory Support Research Plan between FY 2010-2014' was established in November 2009, which shows the present regulatory needs and a research program. This program consists of researches for 1. review process of decommissioning plan of power reactors, 2. review process of decommissioning plan of nuclear fuel cycle facilities, 3. termination of license at the end of decommissioning and 4. management of decommissioning waste. For the item 1, JNES studied safety assessment methods of dismantling, e.g. obtaining data and analysis of behavior of dust diffusion and risk assessment during decommissioning, which are useful findings for the review process. For the item 2, safety requirements for the decommissioning of nuclear fuel cycle facilities was compiled, which will be used in the future review. For the item 3

  19. Agricultural Aspects of Nuclear and/or Radiological Emergency Situations

    International Nuclear Information System (INIS)

    1997-01-01

    This document contains the Proceedings of the NEA/OECD Workshop held at Fontenay-aux-Roses on 12-14 June 1995. The Workshop discussions (20 contributions) were grouped in the following six sessions: 1.Introduction (3 papers); 2. Evaluation and management of agricultural questions (8 papers); 3. Economical and social aspects of the agricultural questions (1 paper); 4. Information exchange mechanisms (3 papers); 5. National strategies in agricultural emergency situations (4 papers); 6. Conclusions and recommendations (1 paper). Summarizing, conclusions were drawn to the following issues: public reaction to foodstuffs containing radioisotope concentrations under the danger standards, possible non-adherence of manufacturers, processors, distributors, et al, to the instructions and guidance from radiation protection specialists, integration of all the food chain factors in the elaboration of the emergency intervention programs, etc. As significant recommendations the following may be mentioned: 1. Differences between different intervention levels and the maximum admissible levels agreed upon by national, regional or international nutrition authorities should be further studied; 2. Problems created by the Chernobyl accident (as for instance, the methods of treatment of food chain products containing unacceptable radioactivity concentrations) are still present and must be solved; 3. Further studies should be done on the socio-cultural aspects of the communication, particularly on the information in rural environment; 4. The preventive measures in agriculture should be implemented as rapidly as possible; 5. In elaborating programmes of agriculture countermeasures, the management of contaminated media, particularly of forests and their effect on agriculture

  20. Decontamination and decommissioning of nuclear facilities: a literature search

    International Nuclear Information System (INIS)

    Sande, W.E.; Freeman, H.D.; Hanson, M.S.; McKeever, R.

    1975-05-01

    is bibliography includes 429 unclassified references to the decontamination and decommissioning of nuclear facilities. The references are arranged in chronological order and cover the period from 1944 through 1974. Subject and author indexes are e provided. (U.S.)

  1. Ensuring the safety of nuclear facilities located in large cities

    International Nuclear Information System (INIS)

    Ryazantsev, E.P.; Kolyadin, V.I.; Bylkin, B.K.; Zverkov, Yu.A.

    2002-01-01

    The problems of ensuring the safety of nuclear facilities and other facilities representing a radiation hazard (hereinafter referred to as 'nuclear facilities') which are located in large cities are considered in the light of the experience with the 'Kurchatov Institute' Russian Research Centre. The accumulation of substantial quantities of spent nuclear fuel and radwaste at the Centre was an inevitable consequence of the military and civilian nuclear research programmes which started there in 1943. A comprehensive programme has been developed for reducing the impact of ionizing radiation on the Centre's personnel, the population living near the Centre and the local environment. The authors describe the basic elements of a programme for decommissioning reactor facilities and eliminating spent fuel and radwaste storage sites and also describe how the programme is progressing. (author)

  2. Energy situation in Latin America and nuclear power

    International Nuclear Information System (INIS)

    Jinchuk, D.; Deluchi, F.

    2006-01-01

    Greenhouse Gas emission levels. As an example, C02 emission levels in South America were dominated by a 38% increase in Brazil in the period of 1990-2003. Regarding Nuclear Power generation, at present, only Mexico (1.300 MWe), Brazil (1.900 MWe) and Argentina (950 MWe) have NPP's in operation, representing 5%, 3% and 8% of total electricity generation share respectively. Argentina has 1 reactor (750 MWe) under construction, while Brazil has 1 (1.200 MWe) planned. In the near future Argentina is planning to finish its Third Nuclear Power Plant Atucha 2 for 2010, to extend the life of the CANDU type Embalse NPP for another 20 years and start studies for a future fourth plant in 2015

  3. Office of Nuclear Energy Knowledge Management Program Situational Analysis Report

    Energy Technology Data Exchange (ETDEWEB)

    Kimberlyn C. Mousseau

    2011-12-01

    Knowledge management (KM) has been a high priority for the Department of Energy (DOE) Office of Nuclear Energy (NE) for the past several years. NE Programs are moving toward well-established knowledge management practices and a formal knowledge management program has been established. Knowledge management is being practiced to some level within each of the NE programs. Although it continues to evolve as NE programs evolve, a formal strategic plan that guides the implementation of KM has been developed. Despite the acceptance of KM within DOE NE, more work is necessary before the NE KM program can be considered fully successful. Per Dr. David J. Skyrme[1], an organization typically moves through the following evolutionary phases: (1) Ad-hoc - KM is being practiced to some level in some parts of the organization; (2) Formal - KM is established as a formal project or program; (3) Expanding - the use of KM as a discipline grows in practice across different parts of the organization; (4) Cohesive - there is a degree of coordination of KM; (5) Integrated - there are formal standards and approaches that give every individual access to most organizational knowledge through common interfaces; and (6) Embedded - KM is part-and-parcel of everyday tasks; it blends seamlessly into the background. According to the evolutionary phases, the NE KM program is operating at the two lower levels, Ad-hoc and Formal. Although KM is being practiced to some level, it is not being practiced in a consistent manner across the NE programs. To be fully successful, more emphasis must be placed on establishing KM standards and processes for collecting, organizing, sharing and accessing NE knowledge. Existing knowledge needs to be prioritized and gathered on a routine basis, its existence formally recorded in a knowledge inventory. Governance to ensure the quality of the knowledge being used must also be considered. For easy retrieval, knowledge must be organized according to a taxonomy that

  4. Childhood leukaemia around Canadian nuclear facilities. Phase 1

    International Nuclear Information System (INIS)

    Clarke, E.A.; McLaughlin, J.; Anderson, T.W.

    1989-05-01

    A ninefold excess risk of leukaemia, as observed in vicinity of the Sellafield facility, was not observed amongst children born to mothers residing in the areas around nuclear research facilities and uranium mining, milling and refining facilities in Ontario. In the vicinity of nuclear research facilities, the rate of leukaemia was, in fact, less than expected. In the areas around the uranium mining, milling and refining facilities; leukaemia occurred slightly more frequently than expected; however, due to small frequencies these results may have risen by chance. A slightly greater than expected occurrence of leukaemia was also detected, which may well have been due to chance, in an exploratory study of the areas around nuclear power generating stations in Ontario

  5. Regulatory system for control of nuclear facilities in Bangladesh

    International Nuclear Information System (INIS)

    Mollah, A.S.

    2005-01-01

    All human activities have associated risks. Nuclear programme is no exception. The Bangladesh Atomic Energy Commission (BAEC), constituted in February 1973 through the promulgation of the Presidential order 15 of 1973. Functions of BAEC include research and development in peaceful application of atomic energy, generation of electricity and promotion of international relations congenial to implementation of its programmes and projects. In 1993 the Government of Bangladesh promulgated the law on Nuclear Safety and Radiation Control. Considering the human resources, expertise and facilities needed for implementation of the provisions of the NSRC law, BAEC was entrusted with the responsibility to enforce it. The responsibilities of the BAEC cover nuclear and radiological safety within the installations of BAEC and radiological safety in the manifold applications of radioisotopes and radiation sources within the country. An adequate and competent infrastructure has been built to cater to the diverse nuclear and radiation protection requirements of all nuclear facilities in Bangladesh, arising at different stages from site selection to day-to-day operation. In addition, periodic inspections of the nuclear facilities are carried out. The licensing and regulatory inspection systems for controlling of nuclear installations and radiation sources are established. The paper describes the legal provisions, responsibilities and organization of BAEC with special emphasis on nuclear safety and radiation protection of nuclear facilities in Bangladesh. (author)

  6. INTEGRATION OF FACILITY MODELING CAPABILITIES FOR NUCLEAR NONPROLIFERATION ANALYSIS

    Energy Technology Data Exchange (ETDEWEB)

    Gorensek, M.; Hamm, L.; Garcia, H.; Burr, T.; Coles, G.; Edmunds, T.; Garrett, A.; Krebs, J.; Kress, R.; Lamberti, V.; Schoenwald, D.; Tzanos, C.; Ward, R.

    2011-07-18

    Developing automated methods for data collection and analysis that can facilitate nuclear nonproliferation assessment is an important research area with significant consequences for the effective global deployment of nuclear energy. Facility modeling that can integrate and interpret observations collected from monitored facilities in order to ascertain their functional details will be a critical element of these methods. Although improvements are continually sought, existing facility modeling tools can characterize all aspects of reactor operations and the majority of nuclear fuel cycle processing steps, and include algorithms for data processing and interpretation. Assessing nonproliferation status is challenging because observations can come from many sources, including local and remote sensors that monitor facility operations, as well as open sources that provide specific business information about the monitored facilities, and can be of many different types. Although many current facility models are capable of analyzing large amounts of information, they have not been integrated in an analyst-friendly manner. This paper addresses some of these facility modeling capabilities and illustrates how they could be integrated and utilized for nonproliferation analysis. The inverse problem of inferring facility conditions based on collected observations is described, along with a proposed architecture and computer framework for utilizing facility modeling tools. After considering a representative sampling of key facility modeling capabilities, the proposed integration framework is illustrated with several examples.

  7. Development of simplified decommissioning cost estimation code for nuclear facilities

    International Nuclear Information System (INIS)

    Tachibana, Mitsuo; Shiraishi, Kunio; Ishigami, Tsutomu

    2010-01-01

    The simplified decommissioning cost estimation code for nuclear facilities (DECOST code) was developed in consideration of features and structures of nuclear facilities and similarity of dismantling methods. The DECOST code could calculate 8 evaluation items of decommissioning cost. Actual dismantling in the Japan Atomic Energy Agency (JAEA) was evaluated; unit conversion factors used to calculate the manpower of dismantling activities were evaluated. Consequently, unit conversion factors of general components could be classified into three kinds. Weights of components and structures of the facility were necessary for calculation of manpower. Methods for evaluating weights of components and structures of the facility were studied. Consequently, the weight of components in the facility was proportional to the weight of structures of the facility. The weight of structures of the facility was proportional to the total area of floors in the facility. Decommissioning costs of 7 nuclear facilities in the JAEA were calculated by using the DECOST code. To verify the calculated results, the calculated manpower was compared with the manpower gained from actual dismantling. Consequently, the calculated manpower and actual manpower were almost equal. The outline of the DECOST code, evaluation results of unit conversion factors, the evaluation method of the weights of components and structures of the facility are described in this report. (author)

  8. Integration of facility modeling capabilities for nuclear nonproliferation analysis

    International Nuclear Information System (INIS)

    Garcia, Humberto; Burr, Tom; Coles, Garill A.; Edmunds, Thomas A.; Garrett, Alfred; Gorensek, Maximilian; Hamm, Luther; Krebs, John; Kress, Reid L.; Lamberti, Vincent; Schoenwald, David; Tzanos, Constantine P.; Ward, Richard C.

    2012-01-01

    Developing automated methods for data collection and analysis that can facilitate nuclear nonproliferation assessment is an important research area with significant consequences for the effective global deployment of nuclear energy. Facility modeling that can integrate and interpret observations collected from monitored facilities in order to ascertain their functional details will be a critical element of these methods. Although improvements are continually sought, existing facility modeling tools can characterize all aspects of reactor operations and the majority of nuclear fuel cycle processing steps, and include algorithms for data processing and interpretation. Assessing nonproliferation status is challenging because observations can come from many sources, including local and remote sensors that monitor facility operations, as well as open sources that provide specific business information about the monitored facilities, and can be of many different types. Although many current facility models are capable of analyzing large amounts of information, they have not been integrated in an analyst-friendly manner. This paper addresses some of these facility modeling capabilities and illustrates how they could be integrated and utilized for nonproliferation analysis. The inverse problem of inferring facility conditions based on collected observations is described, along with a proposed architecture and computer framework for utilizing facility modeling tools. After considering a representative sampling of key facility modeling capabilities, the proposed integration framework is illustrated with several examples.

  9. Integration Of Facility Modeling Capabilities For Nuclear Nonproliferation Analysis

    International Nuclear Information System (INIS)

    Gorensek, M.; Hamm, L.; Garcia, H.; Burr, T.; Coles, G.; Edmunds, T.; Garrett, A.; Krebs, J.; Kress, R.; Lamberti, V.; Schoenwald, D.; Tzanos, C.; Ward, R.

    2011-01-01

    Developing automated methods for data collection and analysis that can facilitate nuclear nonproliferation assessment is an important research area with significant consequences for the effective global deployment of nuclear energy. Facility modeling that can integrate and interpret observations collected from monitored facilities in order to ascertain their functional details will be a critical element of these methods. Although improvements are continually sought, existing facility modeling tools can characterize all aspects of reactor operations and the majority of nuclear fuel cycle processing steps, and include algorithms for data processing and interpretation. Assessing nonproliferation status is challenging because observations can come from many sources, including local and remote sensors that monitor facility operations, as well as open sources that provide specific business information about the monitored facilities, and can be of many different types. Although many current facility models are capable of analyzing large amounts of information, they have not been integrated in an analyst-friendly manner. This paper addresses some of these facility modeling capabilities and illustrates how they could be integrated and utilized for nonproliferation analysis. The inverse problem of inferring facility conditions based on collected observations is described, along with a proposed architecture and computer framework for utilizing facility modeling tools. After considering a representative sampling of key facility modeling capabilities, the proposed integration framework is illustrated with several examples.

  10. Childhood leukaemia around Canadian nuclear facilities. Phase 2

    International Nuclear Information System (INIS)

    Clarke, E.A.; McLaughlin, J.; Anderson, T.W.

    1991-06-01

    Prompted by findings of increased occurrence of childhood leukaemia in the vicinity of some nuclear facilities in the United Kingdom, this study aimed to investigate whether the frequency of leukaemia among children born to mothers living near nuclear facilities in Ontario differed from the provincial average. The Ontario Cancer Registry was used to identify 1894 children aged 0 to 14 years who died from leukaemia between 1950 and 1987, and 1814 children who were diagnosed with leukaemia between 1964 and 1986. Residence at birth and death was obtained from birth and death certificates. Analyses were performed separately for nuclear research and development facilities; uranium mining, milling and refining facilities; and, nuclear generating stations; and for areas within the same county as the facility and 'nearby' - within a 25-km radius of the facility. Risk estimates were calculated as the ratio of the observed (O) number of events over the expected (E) number. In the vicinity of nuclear research and development facilities the rate of leukaemia was less than expected and within the bound of chance variation. In the areas around the uranium mining, milling and refining facilities and nuclear power plants leukaemia occurred slightly more frequently than expected, but due to small frequencies these differences may have arisen due to chance. Large differences between observed and expected rates were not detected around any of the Ontario facilities. This study was large enough to detect excess risks of the magnitude reported in the United Kingdom, but it was not large enough to discriminate between the observed relative risks and a chance finding. Levels of leukaemia detected near nuclear generating stations indicate the need for further investigation. (20 tabs., 15 figs., 32 refs.)

  11. Validity evaluation of internal exposure in nuclear facility decommission

    International Nuclear Information System (INIS)

    Wang Xiaoli; Chen Dahua; You Zeyun

    2012-01-01

    During nuclear facility decommission under construction, it is very important for workers to wear respirator to avoid harm of Am aerosols. So the protection effect of respirator is very important. The protection effect of respirator was calculated and evaluated according to the data achieved from engineering practice. The result shows that the protection effect is better than target management value and the respirator is effective to protect workers from harm of Am aerosols. The respirator is applied to other nuclear facility decommission. (authors)

  12. Safety study of fire protection for nuclear fuel cycle facility

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2013-08-15

    Based on the investigation of fire protection standards for domestic and foreign nuclear facilities, the fire protection guideline for nuclear fuel cycle facility has been completed. In 2012, trial operation is started by private company using the guideline. In addition, the acquisition of fire evaluation data for a components (electric cable) targeted for spread of fire and the evaluation model of fire source were continued for the fire hazard analysis (FHA). (author)

  13. Deactivation and Storage Issues Shared by Fossil and Nuclear Facilities

    International Nuclear Information System (INIS)

    Thomas S. LaGuardia

    1998-01-01

    The deactivation of a power plant, be it nuclear or fossil fueled, requires that the facility be placed in a safe and stable condition to prevent unacceptable exposure of the public or the environment to hazardous materials until the facility can be decommissioned. The conditions at two Texas plants are examined. These plants are fossil fueled, but their conditions might be duplicated at a nuclear plant

  14. A Regulators Systematic Approach to Physical Protection for Nuclear Facilities

    International Nuclear Information System (INIS)

    Bayer, Stephan; Doulgeris, Nicholas; Leask, Andrew

    2004-01-01

    This paper outlines the framework for a physical protection regime which needs to be incorporated into the design and construction phases of nuclear facility. The need for physical protection considerations at the outset of the design of nuclear facilities is explained. It also discusses about the consequences of malicious activity and the management of risk. Various risk and consequences evaluations are undertaken, notably using design basis threat methodology. (author)

  15. Physical protection of facilities and special nuclear materials in france

    International Nuclear Information System (INIS)

    Jeanpierre, G.

    1980-01-01

    Physical protection of nuclear facilities and special nuclear materials is subject in France to a national governmental regulation which provides for the basic principles to be taken into account and the minimal level of protection deemed necessary. But the responsibility of implementation is left to the facility management and the resulting decentralization allows for maximum efficiency. All safeguards measures comply with the commitments taken at the international level by the French government

  16. Safety study of fire protection for nuclear fuel cycle facility

    International Nuclear Information System (INIS)

    2013-01-01

    Based on the investigation of fire protection standards for domestic and foreign nuclear facilities, the fire protection guideline for nuclear fuel cycle facility has been completed. In 2012, trial operation is started by private company using the guideline. In addition, the acquisition of fire evaluation data for a components (electric cable) targeted for spread of fire and the evaluation model of fire source were continued for the fire hazard analysis (FHA). (author)

  17. Security Culture in Physical Protection of Nuclear Material and Facility

    International Nuclear Information System (INIS)

    Susyanta-Widyatmaka; Koraag, Venuesiana-Dewi; Taswanda-Taryo

    2005-01-01

    In nuclear related field, there are three different cultures: safety, safeguards and security culture. Safety culture has established mostly in nuclear industries, meanwhile safeguards and security culture are relatively new and still developing. The latter is intended to improve the physical protection of material and nuclear facility. This paper describes concept, properties and factors affecting security culture and interactions among these cultures. The analysis indicates that anybody involving in nuclear material and facility should have strong commitment and awareness of such culture to establish it. It is concluded that the assessment of security culture outlined in this paper is still preliminary for developing and conduction rigorous security culture implemented in a much more complex facility such as nuclear power plant

  18. The cost of decommissioning nuclear facilities

    International Nuclear Information System (INIS)

    1993-01-01

    This report sets out the results of a National Audit Office investigation to determine the extent of the potential Government liability for nuclear decommissioning, how this is to be financed and the possible implications for the taxpayer. Further effort are needed to improve the nuclear industry's estimates, improve efficiency and face up to the costs of decommissioning. This should also ensure that the full cost of nuclear energy is identified. (author)

  19. Nuclear Security Recommendations on Physical Protection of Nuclear Material and Nuclear Facilities (INFCIRC/225/Revision 5): Recommendations

    International Nuclear Information System (INIS)

    2011-01-01

    This publication, Revision 5 of Physical Protection of Nuclear Material and Nuclear Facilities (INFCIRC/225), is intended to provide guidance to States and their competent authorities on how to develop or enhance, implement and maintain a physical protection regime for nuclear material and nuclear facilities, through the establishment or improvement of their capabilities to implement legislative and regulatory programmes. The recommendations presented in this publication reflect a broad consensus among IAEA Member States on the requirements which should be met for the physical protection of nuclear materials and nuclear facilities.

  20. A study on the operator's communication pattern characteristics under abnormal operating situation of nuclear power plants

    International Nuclear Information System (INIS)

    Kim, S. H.; Park, J.

    2008-01-01

    The quality of a probabilistic safety assessment (PSA) has become more important and a human reliability analysis (HRA) is known as a major contributor to the uncertainty of a PSA. As a part of enhancing the HRA quality, a study was initiated to find out characteristics of communication pattern and to evaluate communication quality of the operators of nuclear power plants. Korea Atomic Energy Research Institute (KAERI) is developing evaluation methods for the effect of human-induced events on risk/performance. This paper describes a study on the operator's communication pattern characteristics under abnormal operating situation of nuclear power plants. The study was carried out in four stages; 1) Video recording 2) Audio scripting 3) Message Classification 4) Communication Pattern Analysis. We recorded eight abnormal simulator training programs from Younggwang nuclear power plant training center. After that we performed message classification and carried out communication pattern analysis. We compared communication patterns of abnormal operating situation with emergency operating situation.As results of analysis, the role of SRO (senior reactor operator) under abnormal operating situation was decreased than the activities under emergency operating situation because each operator (reactor operator, turbine operator, safety supervisor) in main control room (MCR) performs the activity to control by himself with corresponding field engineers with his basic knowledge of the system. On the other hand, the operator's decision making processes and activities under abnormal operating situation were dramatically increased than the emergency operating situation. (authors)

  1. Analysis of general specifications for nuclear facilities environmental monitoring vehicles

    International Nuclear Information System (INIS)

    Xu Xiaowei

    2014-01-01

    At present, with the nuclear energy more increasingly extensive application, the continuous stable radiation monitoring has become the focus of the public attention. The main purpose of the environmental monitoring vehicle for the continuous monitoring of the environmental radiation dose rate and the radionuclides concentration in the medium around nuclear facilities is that the environmental radiation level and the radioactive nuclides activity in the environment medium are measured. The radioactive pollution levels, the scope contaminated and the trends of the pollution accumulation are found out. The change trends for the pollution are observed and the monitoring results are explained. The domestic demand of the environmental monitoring for the nuclear facilities is shown in this report. The changes and demands of the routine environmental monitoring and the nuclear emergency monitoring are researched. The revision opinions for EJ/T 981-1995 General specifications for nuclear facilities environmental monitoring vehicles are put forward. The purpose is to regulate domestic environmental monitoring vehicle technical criterion. The criterion makes it better able to adapt and serve the environmental monitoring for nuclear facilities. The technical guarantee is provided for the environmental monitoring of the nuclear facilities. (authors)

  2. Status of ANSI standards on decommissioning of nuclear reprocessing facilities

    International Nuclear Information System (INIS)

    Graham, H.B.

    1975-01-01

    A definition of decommissioning is given, and the preparation of ANSI Standard, ''General Design Criteria for Nuclear Reprocessing Facilities'' (N101.3) is discussed. A Eurochemic report, entitled ''The Shutdown of Reprocessing Facilities--Results of Preliminary Studies on the Installations Belonging to Eurochemic,'' was used in the preparation of this standard. (U.S.)

  3. Safety of Nuclear Fuel Cycle Facilities. Safety Requirements (Arabic Edition)

    International Nuclear Information System (INIS)

    2015-01-01

    This publication covers the broad scope of requirements for fuel cycle facilities that, in light of the experience and present state of technology, must be satisfied to ensure safety for the lifetime of the facility. Topics of specific relevance include aspects of nuclear fuel generation, storage, reprocessing and disposal

  4. Decommissioning of nuclear facilities: Feasibility, needs and costs

    International Nuclear Information System (INIS)

    DeLaney, E.G.; Mickelson, J.R.

    1985-01-01

    The Nuclear Energy Agency's Working Group on Decommissioning is preparing a study entitled ''Decommissioning of Nuclear Facilities: Feasibility, Needs and Costs.'' The study addresses the economics, technical feasibility and waste management aspects of decommissioning larger commercial reactors and nuclear support facilities. Experience on decommissioning small reactors and fuel cycle facilities shows that current technology is generally adequate. Several major projects that are either underway or planned will demonstrate decommissioning of the larger and more complex facilities. This experience will provide a framework for planning and engineering the decommissioning of the larger commercial reactors and fuel cycle facilities. Several areas of technology development are desired for worker productivity improvement, occupational exposure reduction, and waste volume reduction. In order to assess and plan for the decommissioning of large commercial nuclear facilities, projections have been made of the capacity of these facilities that may be decommissioned in the future and the radioactive waste that would be produced from the decommissioning of these facilities. These projections through the year 2025 are based on current data and the OECD reactor capacity forecast through the year 2000. A 25-year operating lifetime for electrical power generation was assumed. The possibilities of plant lifetime extension and the deferral of plant dismantlement make this projection very conservative

  5. Present radiological situation at the Semipalatinsk nuclear test site

    International Nuclear Information System (INIS)

    Stegar, P.

    1996-01-01

    pathways were taken into account in assessing the doses to people in the identified settlements and the other areas. For the assessment of current doses it was assumed that people lived all year round in the settlements, that those in the vicinity of Lake Balapan spent one hour per day close to the lake and that those in the vicinity of Ground Zero spent one hour per day at the location. The preliminary conclusions are: No more detailed assessment of the radiological situation is required, because the doses today to local populations in the settlements are very low; Access to land with high dose rates within the polygon, namely Lake Balapan and Ground Zero, should be restricted in order to prevent reoccupation; Further specific and systematic studies are needed on the plutonium levels in the soil around Lake Balapan and Ground Zero, and on the levels of radionuclides in drinking water sources of the settlements outside the polygon

  6. Uranium Mining and Nuclear Facilities (Prohibitions) Act 1986 No. 194

    International Nuclear Information System (INIS)

    1986-01-01

    The purpose of this Act is to protect the health and safety of the people of New South Wales and its environment. Accordingly it prohibits prospecting or mining for uranium and the construction and operation of nuclear reactors and other facilities in the nuclear fuel cycle. (NEA) [fr

  7. Safety Analysis of Spent Nuclear Fuel and Radwaste Facilities

    International Nuclear Information System (INIS)

    Poskas, P.; Ragaisis, V.

    2001-01-01

    The overview of the activities in the Laboratory of Heat Transfer in Nuclear Reactors related with the assessment of thermal, neutronic and radiation characteristics in spent nuclear fuel and radwaste facilities are performed. Activities related with decommissioning of Ignalina NPP are also reviewed. (author)

  8. The decommissioning concept for nuclear facilities in Ukraine

    International Nuclear Information System (INIS)

    Yaroslavtsev, G.F.; Korchagin, P.A.

    2000-01-01

    The basic task of the conception is a formulation of the basic directions and priorities, terms of schedules and plans, calculation of costs of works on endurance, preservations, dismantlement of nuclear facilities and returning of territories in the unlimited usage. Independent of the development rate of nuclear energy in Ukraine, this problem must now be solved. (author)

  9. Safety requirements and safety experience of nuclear facilities in the Federal Republic of Germany

    International Nuclear Information System (INIS)

    Schnurer, H.L.

    1977-01-01

    Peaceful use of nuclear energy within the F.R.G. is rapidly growing. The Energy Programme of the Federal Government forecasts a capacity of up to 50.000 MW in 1985. Whereas most of this capacity will be of the LWR-Type, other activities are related to LMFBR - and HTGR - development, nuclear ships, and facilities of the nuclear fuel cycle. Safety of nuclear energy is the pacemaker for the realization of nuclear programmes and projects. Due to a very high population - and industrialisation density, safety has the priority before economical aspects. Safety requirements are therefore extremely stringent, which will be shown for the legal, the technical as well as for the organizational area. They apply for each nuclear facility, its site and the nuclear energy system as a whole. Regulatory procedures differ from many other countries, assigning executive power to state authorities, which are supervised by the Federal Government. Another particularity of the regulatory process is the large scope of involvement of independent experts within the licensing procedures. The developement of national safety requirements in different countries generates a necessity to collaborate and harmonize safety and radiation protection measures, at least for facilities in border areas, to adopt international standards and to assist nuclear developing countries. However, different nationally, regional or local situations might raise problems. Safety experience with nuclear facilities can be concluded from the positive construction and operation experience, including also a few accidents and incidents and the conclusions, which have been drawn for the respective factilities and others of similar design. Another tool for safety assessments will be risk analyses, which are under development by German experts. Final, a scope of future problems and developments shows, that safety of nuclear installations - which has reached a high performance - nevertheless imposes further tasks to be solved

  10. Emergency preparedness and response plan for nuclear facilities in Indonesia

    International Nuclear Information System (INIS)

    Nur Rahmah Hidayati; Pande Made Udiyani

    2009-01-01

    All nuclear facilities in Indonesia are owned and operated by the National Nuclear Energy Agency (BATAN). The programs and activities of emergency planning and preparedness in Indonesia are based on the existing nuclear facilities, i.e. research reactors, research reactor fuel fabrication plant, radioactive waste treatment installation and radioisotopes production installation. The assessment is conducted to learn of status of emergency preparedness and response plan for nuclear facilities in Indonesia and to support the preparation of future Nuclear Power Plant. The assessment is conducted by comparing the emergency preparedness and response system in Indonesia to the system in other countries such as Japan and Republic of Korea, since the countries have many Nuclear Power Plants and other nuclear facilities. As a result, emergency preparedness response plan for existing nuclear facility in Indonesia has been implemented in many activities such as environmental monitoring program, facility monitoring equipment, and the continuous exercise of emergency preparedness and response. However, the implementation need law enforcement for imposing the responsibility of the coordinators in National Emergency Preparedness Plan. It also needs some additional technical support systems which refer to the system in Japan or Republic of Korea. The systems must be completed with some real time monitors which will support the emergency preparedness and response organization. The system should be built in NPP site before the first NPP will be operated. The system should be connected to an Off Site Emergency Center under coordination of BAPETEN as the regulatory body which has responsibility to control of nuclear energy in Indonesia. (Author)

  11. National policies and regulations for decommissioning nuclear facilities

    International Nuclear Information System (INIS)

    1993-07-01

    This report, though produced as a follow-up to Safety Series No. 105, The Regulatory Process for the Decommissioning of Nuclear Facilities, is not primarily intended as guidance. Rather, its objective is to provide an overview of national decommissioning policies and regulatory practices as part of the background knowledge which is an essential precondition for good decision making. It discusses the reasons for the similarities and differences in national approach using specific examples but without giving preference to any particular scheme; it aims rather to provide factual, general information on the choices that have been or are being made, and why. As many Member States are in a transient situation between the case-by-case approach to decommissioning and the establishment of national policies, strategies and regulations, this seems the right moment to assess existing national practices worldwide and that is the purpose for which the document is issued at this time. The information gathered in this report is based on submissions by Member States which have developed or are in the process of developing decommissioning oriented policies and regulations. 29 refs

  12. Technical requirement of experiments and facilities for fusion nuclear technology

    International Nuclear Information System (INIS)

    Abdou, M.; Tillak, M.; Gierszwski, P.; Grover, J.; Puigh, R.; Sze, D.K.; Berwald, D.

    1986-06-01

    The technical issues and requirements of experiments and facilities for fusion nuclear technology (FNT) have been investigated. The nuclear subsystems addressed are: a) blanket, b) radiation shield, c) tritium processing system, and d) plasma interactive components. Emphasis has been placed on the important and complex development problems of the blanket. A technical planning process for FNT has been developed and applied, including four major elements: 1) characterization of issues, 2) quantification of testing requirements, 3) evaluation of facilities, and 4) development of a test plan to identify the role, timing, characteristics and costs of major experiments and facilities

  13. Nuclear safety and radiation protection report of EdF's Tricastin operational hot base nuclear facilities (BCOT) - 2010

    International Nuclear Information System (INIS)

    2011-06-01

    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 2010, 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. (J.S.)

  14. The nuclear safeguards data flow for the item facilities

    International Nuclear Information System (INIS)

    Wang Hongjun; Chen Desheng

    1994-04-01

    The constitution of nuclear safeguards data flow for the item facilities is introduced and the main contents are the data flow of nuclear safeguards. If the data flow moves positively, i.e. from source data →supporting documents→accounting records→accounting reports, the systems of records and reports will be constituted. If the data flow moves negatively, the way to trace inspection of nuclear material accounting quality will be constituted

  15. Test facilities for evaluating nuclear thermal propulsion systems

    International Nuclear Information System (INIS)

    Beck, D.F.; Allen, G.C.; Shipers, L.R.; Dobranich, D.; Ottinger, C.A.; Harmon, C.D.; Fan, W.C.; Todosow, M.

    1992-01-01

    Interagency panels evaluating nuclear thermal propulsion (NTP) development options have consistently recognized the need for constructing a major new ground test facility to support fuel element and engine testing. This paper summarizes the requirements, configuration, and baseline performance of some of the major subsystems designed to support a proposed ground test complex for evaluating nuclear thermal propulsion fuel elements and engines being developed for the Space Nuclear Thermal Propulsion (SNTP) program. Some preliminary results of evaluating this facility for use in testing other NTP concepts are also summarized

  16. A safety decision analysis for Saudi Arabian nuclear research facility

    International Nuclear Information System (INIS)

    Abulfaraj, W.H.; Abdul-Fattah, A.F.

    1985-01-01

    Establishment of a nuclear research facility should be the first step in planning for introducing the nuclear energy to Saudi Arabia. The fuzzy set decision theory is selected among different decision theories to be applied for this analysis. Four research reactors from USA are selected for the present study. The IFDA computer code, based on the fuzzy set theory is applied. Results reveal that the FNR reactor is the best alternative for the case of Saudi Arabian nuclear research facility, and MITR is the second best. 17 refs

  17. Nuclear facilities. Revenue Act for 2000 (no. 99-1172)

    International Nuclear Information System (INIS)

    Anon.

    1999-01-01

    The article no. 43 of the Revenue Act for 2000 modifies the existing system of tax for basic nuclear facilities. The articles no. 17 and no. 121 are abrogated. The basic nuclear facilities subjected to an authorization procedure (article no. 8, act no. 61-842 of the 2. of August 1961 concerning the abatement of air pollution and odors) have to pay an annual tax with effect from January 1. 2000. For nuclear reactors, tax has to be paid for each unit of the plant. (O.M.)

  18. Organization of the internal dosimetry in the Spanish nuclear facilities

    International Nuclear Information System (INIS)

    Manchena, P.; Soliet, E.

    1998-01-01

    From the beginning of the exploitation of the nuclear energy of Espanna, the nuclear facilities have had Services of Personal Dosimetry with the appropriate means to determine the dose. so much internal as external, of the personnel that mentioned facilities works. All the nuclear power stations use advanced systems of teams with object of detecting the radionuclides incorporation in the organism and calculation programs based on the recent recommendations of the International Commission of Radiological Protection (ICRP) for the determination of the derived doses

  19. Technological Advances, Human Performance, and the Operation of Nuclear Facilities

    Science.gov (United States)

    Corrado, Jonathan K.

    Many unfortunate and unintended adverse industrial incidents occur across the United States each year, and the nuclear industry is no exception. Depending on their severity, these incidents can be problematic for people, the facilities, and surrounding environments. Human error is a contributing factor in many such incidents. This dissertation first explored the hypothesis that technological changes that affect how operators interact within the systems of the nuclear facilities exacerbate the cost of incidents caused by human error. I conducted a review of nuclear incidents in the United States from 1955 through 2010 that reached Level 3 (serious incident) or higher on the International Nuclear Events Scale (INES). The cost of each incident at facilities that had recently undergone technological changes affecting plant operators' jobs was compared to the cost of events at facilities that had not undergone changes. A t-test determined a statistically significant difference between the two groups, confirming the hypothesis. Next, I conducted a follow-on study to determine the impact of the incorporation of new technologies into nuclear facilities. The data indicated that spending more money on upgrades increased the facility's capacity as well as the number of incidents reported, but the incident severity was minor. Finally, I discuss the impact of human error on plant operations and the impact of evolving technology on the 21st-century operator, proposing a methodology to overcome these challenges by applying the systems engineering process.

  20. Accident assessment under emergency situation in Daya Bay nuclear power station

    International Nuclear Information System (INIS)

    Yang Ling; Chen Degan; Lin Shumou; Fu Guohui

    2004-01-01

    The accident assessment under emergency situation includes the accident status evaluation and its consequence estimation. This paper introduces evaluation methods for accident status and its assistant computer system (SESAME-GNP) utilized during the emergency situation in Guangdong Daya Bay Nuclear Power Station (GNPS) in detail. At the same time, an improved accident consequence estimation system in GNPS (RACAS-GNP) is briefly described. With the improvement of the accident assessment systems, the capability of emergency response in GNPS is strengthened

  1. Strategy selection for the decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    2004-01-01

    As modern nuclear power programmes mature and large, commercial nuclear power plants and fuel cycle facilities approach the end of their useful life by reason of age, economics or change of policy on the use of nuclear power, new challenges associated with decommissioning and dismantling come to the fore. Politicians and the public may expect there to be a 'right answer' to the choice of strategy for a particular type of facility, or even all facilities. Both this seminar and wider experience show that this is not the case. Local factors and national political positions have a significant input and often result in widely differing strategy approaches to broadly similar decommissioning projects. All facility owners represented at the seminar were able to demonstrate a rational process for strategy selection and compelling arguments for the choices made. In addition to the papers that were presented, these proceedings include a summary of the discussions that took place. (author)

  2. Construction Cost Growth for New Department of Energy Nuclear Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Kubic, Jr., William L. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2014-05-25

    Cost growth and construction delays are problems that plague many large construction projects including the construction of new Department of Energy (DOE) nuclear facilities. A study was conducted to evaluate cost growth of large DOE construction projects. The purpose of the study was to compile relevant data, consider the possible causes of cost growth, and recommend measures that could be used to avoid extreme cost growth in the future. Both large DOE and non-DOE construction projects were considered in this study. With the exception of Chemical and Metallurgical Research Building Replacement Project (CMRR) and the Mixed Oxide Fuel Fabrication Facility (MFFF), cost growth for DOE Nuclear facilities is comparable to the growth experienced in other mega construction projects. The largest increase in estimated cost was found to occur between early cost estimates and establishing the project baseline during detailed design. Once the project baseline was established, cost growth for DOE nuclear facilities was modest compared to non-DOE mega projects.

  3. Nuclear physics at multi-GeV hadron facilities

    International Nuclear Information System (INIS)

    Geesaman, D.F.

    1993-01-01

    The important contributions Multi-GeV hadron beam facilities can make to the field of Nuclear Physics have been recognized by the community for a decade. Such a facility has featured prominently in each NSAC planning exercise in this period. As Nuclear Physicists realize they must become more concerned with the quark structure of nuclei and the applications of Quantum Chromodynamics to many body systems, the need for experiments at such facilities has become more urgent. In this talk, I will present a personal view of some of the significant recent Nuclear Physics results with multi-GeV hadron facilities, the most important opportunities which can open up to us in the future, and demonstrate how our field must take advantage of these opportunities to progress. I will also report on the recent discussions in the community to make this possible

  4. Accidents in nuclear facilities: classification, incidence and impact

    International Nuclear Information System (INIS)

    Galicia A, J.; Paredes G, L. C.

    2012-10-01

    A general analysis of the 146 accidents reported officially in nuclear facilities from 1945 to 2012 is presented, among them some took place in: power or research nuclear reactors, critical and subcritical nuclear assemblies, handling of nuclear materials inside laboratories belonging to institutes or universities, in radiochemistry industrial plants and nuclear fuel factories. In form graph the incidence of these accidents is illustrated classified for; category, decades, geographical localization, country classification before the OECD, failure type, and the immediate or later victims. On the other hand, the main learned lessons of the nuclear accidents of Three Mile Island, Chernobyl and Fukushima are stood out, among those that highlight; the human factors, the necessity of designs more innovative and major technology for the operation, control and surveillance of the nuclear facilities, to increase the criterions of nuclear, radiological and physics safety applied to these facilities, the necessity to carry out probabilistic analysis of safety more detailed for cases of not very probable accidents and their impact, to revalue the selection criterions of the sites for nuclear locations, the methodology of post-accident sites recovery and major instrumentation for parameters evaluation and the radiological monitoring among others. (Author)

  5. Enhancement of safety at nuclear facilities in Pakistan

    International Nuclear Information System (INIS)

    Ahmad, S.A.; Hayat, T.; Azhar, W.

    2006-01-01

    Pakistan is benefiting from nuclear technology mostly in health and energy sectors as well as agriculture and industry and has an impeccable safety record. At the national level uses of nuclear technology started in 1955 resulting in the operation of Karachi Radioisotope Center, Karachi, in December 1960. Pakistan Nuclear Safety Committee (PNSC) was formulated in 1964 with subsequent promulgation of Pakistan Atomic Energy Commission (PAEC) Ordinance in 1965 to cope with the anticipated introduction of a research reactor, namely PARR-I, and a nuclear power plant, namely KANUPP. Since then Pakistan's nuclear program has expanded to include numerous nuclear facilities of varied nature. This program has definite economic and social impacts by producing electricity, treating and diagnosing cancer patients, and introducing better crop varieties. Appropriate radiation protection includes a number of measures including database of sealed radiation sources at PAEC operated nuclear facilities, see Table l, updated during periodic physical verification of these sources, strict adherence to the BSS-115, IAEA recommended enforcement of zoning at research reactors and NPPs, etc. Pakistan is party to several international conventions and treaties, such as Convention of Nuclear Safety and Early Notification, to improve and enhance safety at its nuclear facilities. In addition Pakistan generally and PAEC particularly believes in a blend of prudent regulations and good/best practices. This is described in this paper. (Author)

  6. Environmental licensing of nuclear facilities: compatibility of technical competencies

    International Nuclear Information System (INIS)

    Shu, J.; Paiva, R.L.C. de; Mezrahi, A.; Cardoso, E.M.; Aquino, W.P.; Deppe, A.L.; Menezes, R.M.; Prado, V.; Franco, N.M.F.L.; Nouailhetas, Y.; Xavier, A.M.

    1996-01-01

    The Brazilian Nuclear Energy Commission (CNEN) has the technical competency for diagnosing environmental radiological impacts, as well as evaluating the safety and requiring adequate control of the facilities which, due to their activities, represent a potential risk of radiological contamination for the environment. The institution is responsible for emission of radioprotection guidelines, controls and surveys in nuclear safety according to the country's regulations and international recommendations. The methodology to assure the limitation of radiation exposure is consequence from shared control over the nuclear activities, in special the nuclear facilities. According to the Federal Constitution of 1988, the nuclear activities must be under exclusive control of the Union in special related to the nuclear policies, economical, laboral and nuclear safety aspects, while the health and environmental controls of these activities are shared by the Federation, Union, States, Federal District and Counties. The controls related to specific aspects have to be harmonized in such a way to be optimized and effective. In this paper the results of compatibilization of nuclear legislation and environmental legislation are presented aiming to optimize the licensing of nuclear facilities. (author)

  7. Upgrade and Development of Nuclear Data Production Test Facility

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2007-04-15

    It is necessary to improve the Pohang Neutron Facility (PNF) in order to be used as a nuclear data production facility for users in both domestic and abroad. We improved following items: (1) upgrade the electron linac, (2) collimators inside the TOF beam pipe, (3) the development and installation of an automatic sample changer, (4) the extension of the TOF beam line, and (5) the data acquisition system. We would like to establish a utilization system for users to measure the nuclear data at the PNF. To do this, we made manuals for the accelerator operation and the data acquisition system. We also made an application form to apply for users to measure the nuclear data in both domestic and abroad. The main object of the Pohang Neutron Facility is to measure the nuclear data in the neutron energy region from thermal neutron to few hundreds of eV. In addition to neutron beams produced at the PNF, photon and electron beams are produced in this facility. We thus utilize this facility for other fields, such as test facility for detectors, activation experiments, polarized neutron beam source, and so on. In addition to these, we could use this facility for training students

  8. Upgrade and development of nuclear data production test facility

    Energy Technology Data Exchange (ETDEWEB)

    Namkung, Won; Ko, I. S.; Cho, M. H.; Lee, Y. S.; Kang, H. S. [Pohang Univ. of Science and Technology, Pohang (Korea, Republic of); Kim, G. N. [Kyungpook National Univ., Daegu (Korea, Republic of); Koh, S. K. [Univ. of Ulsan, Ulsan (Korea, Republic of); Ro, T. I. [Donga Univ., Busan (Korea, Republic of); Choi, G. U. [Korea Research Institute of Standards and Science, Daejeon (Korea, Republic of)

    2005-04-15

    It is necessary to improve the Pohang Neutron Facility (PNF) in order to be used as a nuclear data production facility for users in both domestic and abroad. We improved following items: upgrade the electron linac, collimators inside the TOF beam pipe, the development and installation of an automatic sample changer, the extension of the TOF beam line, and the data acquisition system. We would like to establish a utilization system for users to measure the nuclear data at the PNF. To do this, we made manuals for the accelerator operation and the data acquisition system. We also made an application form to apply for users to measure the nuclear data in both domestic and abroad. The main object of the Pohang Neutron Facility is to measure the nuclear data in the neutron energy region from thermal neutron to few hundreds of eV. In addition to neutron beams produced at the PNF, photon and electron beams are produced in this facility. We thus utilize this facility for other fields, such as test facility for detectors, activation experiments, polarized neutron beam source, and so on. In addition to these, we could use this facility for training students.

  9. Study on archive management for nuclear facility decommissioning projects

    International Nuclear Information System (INIS)

    Huang Ling; Gong Jing; Luo Ning; Liao Bing; Zhou Hao

    2011-01-01

    This paper introduces the main features and status of the archive management for nuclear facility decommissioning projects, and explores and discusses the countermeasures in its archive management. Taking the practice of the archive management system of a reactor decommissioning project as an example, the paper illustrates the establishment of archive management system for the nuclear facility decommissioning projects. The results show that the development of a systematic archive management principle and system for nuclear decommissioning projects and the construction of project archives for the whole process from the design to the decommissioning by digitalized archive management system are one effective route to improve the complete, accurate and systematic archiving of project documents, to promote the standardization and effectiveness of the archive management and to ensure the traceability of the nuclear facility decommissioning projects. (authors)

  10. Nuclear facility safeguards systems modeling using discrete event simulation

    International Nuclear Information System (INIS)

    Engi, D.

    1977-01-01

    The threat of theft or dispersal of special nuclear material at a nuclear facility is treated by studying the temporal relationships between adversaries having authorized access to the facility (insiders) and safeguards system events by using a GASP IV discrete event simulation. The safeguards system events--detection, assessment, delay, communications, and neutralization--are modeled for the general insider adversary strategy which includes degradation of the safeguards system elements followed by an attempt to steal or disperse special nuclear material. The performance measure used in the analysis is the estimated probability of safeguards system success in countering the adversary based upon a predetermined set of adversary actions. An exemplary problem which includes generated results is presented for a hypothetical nuclear facility. The results illustrate representative information that could be utilized by safeguards decision-makers

  11. Nuclear facility projects in Finland: quality of environmental impact assessment (EIA) processes

    International Nuclear Information System (INIS)

    Vaatainen, A.

    2001-01-01

    In Finland, three public EIA hearings arranged by the contact authority concerning nuclear facilities were organised in 1999: the EIAs of two reactors planned to be constructed in Eurajoki (Olkiluoto) and in Loviisa, and the EIA of a final disposal facility of spent nuclear fuel, to be situated either in Olkiluoto, Loviisa, Romuvaara or Kivetty. Additionally, an application for a decision-in-principle concerning a final disposal facility to be constructed in Olkiluoto was submitted. The Ministry of Trade and Industry is the contact authority in all nuclear projects in Finland. Probably due to the simultaneity of the processes and the great importance of nuclear facility projects to the whole of society, the public opinions did not include only views about environmental impacts of each project, but also opposing and overall views about the use of nuclear energy and its safety. As for the final disposal project, alternative methods were introduced and opposition to the project itself was expressed instead of or in addition to the environmental impacts. (author)

  12. Feedback experience from the decommissioning of Spanish nuclear facilities

    International Nuclear Information System (INIS)

    Santiago, J.L.

    2008-01-01

    The Spain has accumulated significant experience in the field of decommissioning of nuclear and radioactive facilities. Relevant projects include the remediation of uranium mills and mines, the decommissioning of research reactors and nuclear research facilities and the decommissioning of gas-graphite nuclear power plants. The decommissioning of nuclear facilities in Spain is undertaken by ENRESA, who is also responsible for the management of radioactive wastes. The two most notable projects are the decommissioning of the Vandellos I nuclear power plant and the decommissioning of the CIEMAT nuclear research centre. The Vandellos I power plant was decommissioned in about five years to what is known as level 2. During this period, the reactor vessel was confined, most plant systems and components were dismantled, the facility was prepared for a period of latency and a large part of the site was restored for subsequent release. In 2005 the facility entered into the phase of dormancy, with minimum operating requirements. Only surveillance and maintenance activities are performed, among which special mention should be made to the five-year check of the leak tightness of the reactor vessel. After the dormancy period (25 - 30 years), level 3 of decommissioning will be initiated including the total dismantling of the remaining parts of the plant and the release of the whole site for subsequent uses. The decommissioning of the CIEMAT Research Centre includes the dismantling of obsolete facilities such as the research reactor JEN-1, a pilot reprocessing plant, a fuel fabrication facility, a conditioning plant for liquid and a liquid waste storage facility which were shutdown in the early eighties. Dismantling works have started in 2006 and will be completed by 2009. On the basis of the experience gained in the above mentioned sites, this paper describes the approaches adopted by ENRESA for large decommissioning projects. (author)

  13. Design requirements for new nuclear reactor facilities in Canada

    International Nuclear Information System (INIS)

    Shim, S.; Ohn, M.; Harwood, C.

    2012-01-01

    The Canadian Nuclear Safety Commission (CNSC) has been establishing the regulatory framework for the efficient and effective licensing of new nuclear reactor facilities. This regulatory framework includes the documentation of the requirements for the design and safety analysis of new nuclear reactor facilities, regardless of size. For this purpose, the CNSC has published the design and safety analysis requirements in the following two sets of regulatory documents: 1. RD-337, Design of New Nuclear Power Plants and RD-310, Safety Analysis for Nuclear Power Plants; and 2. RD-367, Design of Small Reactor Facilities and RD-308, Deterministic Safety Analysis for Small Reactor Facilities. These regulatory documents have been modernized to document past practices and experience and to be consistent with national and international standards. These regulatory documents provide the requirements for the design and safety analysis at a high level presented in a hierarchical structure. These documents were developed in a technology neutral approach so that they can be applicable for a wide variety of water cooled reactor facilities. This paper highlights two particular aspects of these regulatory documents: The use of a graded approach to make the documents applicable for a wide variety of nuclear reactor facilities including nuclear power plants (NPPs) and small reactor facilities; and, Design requirements that are new and different from past Canadian practices. Finally, this paper presents some of the proposed changes in RD-337 to implement specific details of the recommendations of the CNSC Fukushima Task Force Report. Major changes were not needed as the 2008 version of RD-337 already contained requirements to address most of the lessons learned from the Fukushima event of March 2011. (author)

  14. Seismic reevaluation of nuclear facilities worldwide: Overview and status

    International Nuclear Information System (INIS)

    Campbell, R.D.; Hardy, G.S.; Ravindra, M.K.; Johnson, J.J.; Hoy, A.J.

    1995-01-01

    Existing nuclear facilities throughout the world are being subjected to severe scrutiny of their safety in tile event of an earthquake. In the United States, there have been several licensing and safety review issues for which industry and regulatory agencies have cooperated to develop rational and economically feasible criteria for resolving the issues. Currently, all operating nuclear power plants in the United States are conducting an Individual Plant Examination of External Events, including earthquakes beyond tile design basis. About two-thirds of tile operating plants are conducting parallel programs for verifying, tile seismic adequacy of equipment for the design basis earthquake. The U.S. Department of Energy is also beginning to perform detailed evaluations of their facilities, many of which had little or no seismic design. Western European countries also have been reevaluating their older nuclear power plants for seismic events often adapting the criteria developed in the United States. With the change in tile political systems in Eastern Europe, there is a strong emphasis from their Western European neighbors to evaluate and Upgrade tile safely of their operating nuclear power plants. Finally, nuclear facilities in Asia are, also, being evaluated for seismic vulnerabilities. This paper focuses oil tile methodologies that have been developed for reevaluation of existing nuclear power plants and presents examples of the application of these methodologies to nuclear facilities worldwide. (author)

  15. Seismic reevaluation of nuclear facilities worldwide: Overview and status

    Energy Technology Data Exchange (ETDEWEB)

    Campbell, R D; Hardy, G S; Ravindra, M K [EQE International, Irvine, CA (United States); Johnson, J J [EQE International, San Francisco, CA (United States); Hoy, A J [EQE International Ltd., Birchwood, Warrington (United Kingdom)

    1995-07-01

    Existing nuclear facilities throughout the world are being subjected to severe scrutiny of their safety in tile event of an earthquake. In the United States, there have been several licensing and safety review issues for which industry and regulatory agencies have cooperated to develop rational and economically feasible criteria for resolving the issues. Currently, all operating nuclear power plants in the United States are conducting an Individual Plant Examination of External Events, including earthquakes beyond tile design basis. About two-thirds of tile operating plants are conducting parallel programs for verifying, tile seismic adequacy of equipment for the design basis earthquake. The U.S. Department of Energy is also beginning to perform detailed evaluations of their facilities, many of which had little or no seismic design. Western European countries also have been reevaluating their older nuclear power plants for seismic events often adapting the criteria developed in the United States. With the change in tile political systems in Eastern Europe, there is a strong emphasis from their Western European neighbors to evaluate and Upgrade tile safely of their operating nuclear power plants. Finally, nuclear facilities in Asia are, also, being evaluated for seismic vulnerabilities. This paper focuses oil tile methodologies that have been developed for reevaluation of existing nuclear power plants and presents examples of the application of these methodologies to nuclear facilities worldwide. (author)

  16. Automated approach to nuclear facility safeguards effectiveness evaluation

    International Nuclear Information System (INIS)

    1977-01-01

    Concern over the security of nuclear facilities has generated a need for a reliable, time efficient, and easily applied method of evaluating the effectiveness of safeguards systems. Such an evaluation technique could be used (1) by the Nuclear Regulatory Commission to evaluate a licensee's proposal, (2) to assess the security status of a system, or (3) to design and/or upgrade nuclear facilities. The technique should be capable of starting with basic information, such as the facility layout and performance parameters for physical protection components, and analyzing that information so that a reliable overall facility evaluation is obtained. Responding to this expressed need, an automated approach to facility safeguards effectiveness evaluation has been developed. This procedure consists of a collection of functional modules for facility characterization, critical path generation, and path evaluation combined into a continuous stream of operations. The technique has been implemented on an interactive computer-timesharing system and makes use of computer graphics for the handling and presentation of information. Using this technique a thorough facility evaluation can be made by systematically varying parameters that characterize the physical protection components of a facility according to changes in perceived adversary attributes and strategy, environmental conditions, and site status

  17. Standard Guide for Preparing Characterization Plans for Decommissioning Nuclear Facilities

    CERN Document Server

    American Society for Testing and Materials. Philadelphia

    2009-01-01

    1.1 This standard guide applies to developing nuclear facility characterization plans to define the type, magnitude, location, and extent of radiological and chemical contamination within the facility to allow decommissioning planning. This guide amplifies guidance regarding facility characterization indicated in ASTM Standard E 1281 on Nuclear Facility Decommissioning Plans. This guide does not address the methodology necessary to release a facility or site for unconditional use. This guide specifically addresses: 1.1.1 the data quality objective for characterization as an initial step in decommissioning planning. 1.1.2 sampling methods, 1.1.3 the logic involved (statistical design) to ensure adequate characterization for decommissioning purposes; and 1.1.4 essential documentation of the characterization information. 1.2 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate saf...

  18. Applying new safeguards technology to existing nuclear facilities

    International Nuclear Information System (INIS)

    Johnson, C.E.; Wagner, E.P.

    1979-01-01

    The application and operation of safeguards instrumentation in a facility containing special nuclear material is most successful when the installation is designed for the operation of the specific facility. Experience at the Idaho National Engineering Laboratory demonstrates that installation designs must consider both Safeguards and Production requirements of specific facilities. Equipment selection and installation design influenced by the training and experience of production operations and safeguards personnel at a specific facility help assure successful installation, reliable operation, and minimal operator training. This minimizes impacts on existing plant production activities while maximizing utility of the safeguards information obtained

  19. Applying new safeguards technology to existing nuclear facilities

    International Nuclear Information System (INIS)

    Harris, W.J.; Wagner, E.P.

    1979-01-01

    The application and operation of safeguards instrumentation in a facility containing special nuclear material is most successful when the installation is desinged for the operation of the specific facility. Experience at the Idaho National Engineering Laboratory demonstrates that installation designs must consider both safeguards and production requirements of specific facilities. Equipment selection and installation design influenced by the training and experience of production operations and safeguards personnel at a specific facility help assure successful installation, reliable operation, and minimal operator training. This minimizes impacts on existing plant production activities while maximizing utility of the safeguards information obtained

  20. Radiation protection in nuclear facilities. Complexity versus systematic approach; Strahlenschutz in Kernanlagen. Komplexitaet versus Systematik

    Energy Technology Data Exchange (ETDEWEB)

    Jahn, S.G. [Eidgenoessisches Nuklearsicherheitsinspektorat (ENSI), Brugg (Switzerland)

    2016-07-01

    Considering the amount of radiation sources in nuclear power plants, their chemical and physical state, the miscellaneous exposure pathways as well as varying limits, reference values and constraints for the protection of persons, tissues and environment, the number of different exposure situations per year ranges up to several thousands. With this complexity a systematic approach for planning a new facility, modification, decommissioning or operation is necessary to ensure complete radiation protection without gaps. The Swiss federal nuclear safety inspectorate (ENSI) is developing and testing a system of safety objectives, functions and measures, which is complementary to the IAEA fundamental safety objectives and requirements.