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Sample records for french nuclear plants

  1. French nuclear power plants. Results and outlooks

    International Nuclear Information System (INIS)

    Serres, S.; Carbonnier, D.

    1999-01-01

    Operating results were good in 1997 for French nuclear power plants: safety levels were perfectly satisfactory; operating expenses continued to decrease (by 2% per annum from 1992 to 1997); there were spectacular results in radiation protection; and they had one of the world's highest availability rates (nearly 83%). (orig.) [de

  2. French nuclear power plants for heat generation

    International Nuclear Information System (INIS)

    Girard, Y.

    1984-01-01

    The considerable importance that France attributes to nuclear energy is well known even though as a result of the economic crisis and the energy savings it is possible to observe a certain downward trend in the rate at which new power plants are being started up. In July 1983, a symbolic turning-point was reached - at more than 10 thousand million kW.h nuclear power accounted, for the first time, for more than 50% of the total amount of electricity generated, or approx. 80% of the total electricity output of thermal origin. On the other hand, the direct contribution - excluding the use of electricity - of nuclear energy to the heat market in France remains virtually nil. The first part of this paper discusses the prospects and realities of the application, at low and intermediate temperatures, of nuclear heat in France, while the second part describes the French nuclear projects best suited to the heat market (excluding high temperatures). (author)

  3. Psychological empowerment in French nuclear power plants

    International Nuclear Information System (INIS)

    Fillol, Charlotte

    2011-01-01

    Since the eighties, nuclear safety has been discussed in organizational studies and constitutes nowadays a specific stream with several standpoints. Regarding the reliability of nuclear plants, the nuclear safety literature has emphasized on the crucial role of individuals and human factors. Especially, some researchers have noticed rule breaking behavior and the impact of individual self-confidence on the behavior; but without deepening their analyses. As high self-esteem and confidence, i.e. psychological empowerment, naturally lead to innovation and rule breaking, the behavior can be analyzed, in such a regulated industry, as opposite to safety. Thus, this article aims at explaining the roots and discernable features of the observed psychological empowerment. Methods include an in-depth qualitative study in 4 nuclear power plants owned by Electricite de France (EDF), the French national nuclear power operator. Focused on the leading team of the plant, the set of data is composed of 35 interviews, 6 weeks of non-participant observation and internal documents. The content analysis has revealed two main pillars of psychological empowerment. On the first hand, the strong professional identity developed at the opening of the plants is based on initiative and risk-taking. In some ways, this professional identify fostered by commitment to a demanding job and the team, influences behavior more than do professional rules. On the second hand, the management discourse is perceived as ambiguous towards the strict application of the rules and tacitly legitimizes rule breaking behavior. This article details and exemplifies these phenomena and discusses the implications. (author)

  4. French effort in field NDT nuclear plant

    International Nuclear Information System (INIS)

    Saglio, R.

    1983-12-01

    For the in-service inspection of nuclear generating stations, the French Atomic Commission has built up a program first to increase the defect detection probability, secondly to increase the reliability and recently to improve the characterization of defects. Focused Ultrasound and multiple frequency eddy current techniques, developped by French Atomic Energy Commission are well known. In this paper we will present the latest developments made in relation with defect characterization

  5. Seismic re-evaluation of French nuclear power plants

    International Nuclear Information System (INIS)

    Andrieu, R.

    1995-01-01

    After a presentation of the seismic inputs which have been taken into account in the design of the French Nuclear Power Plants, the re-assessed values of these inputs are shown. Some considerations about the specificity of the French PWR program with regard to the standardisation of plants are given together with the present objectives of seismic re-evaluations. Finally the main results of the seismic re-analysis being performed for the Phenix Fast Reactor are considered. (author)

  6. 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

  7. Internal exposure in French nuclear power plants : 10 years on

    International Nuclear Information System (INIS)

    Chevalier, C.; Gonin, M.

    1992-01-01

    Collectively speaking, internal exposure in French nuclear power plants is negligible. However, some quite high individual doses have been recorded. The details of cases of significant contamination are presented here in table form. A brief discussion of a few particular cases underscores the problems involved. (author)

  8. Protection against fire hazards in French nuclear power plants

    International Nuclear Information System (INIS)

    Chapus, J.

    2000-01-01

    The prevention of fire in French nuclear power plants has followed the evolution of safety regulations. Today fire hazards are no longer considered as classical industrial risks but as specific risks that deserve to be studied thoroughly and in a more formalized form. In the beginning of the eighties EDF was committed to the redaction of a technical referential against fire gathering all the directives applicable to the N4-type plant (1450 MW). In 1994 this technical referential was reconsidered and enlarged in order to involve 900 MW and 1300 MW units. In each nuclear power plant a PAI (plan against fire) has been elaborated so that the installation can be progressively upgraded according to the last standard defined by the technical referential. (A.C.)

  9. Operating nuclear plant feedback to ASME and French codes

    International Nuclear Information System (INIS)

    Journet, J.; O'Donnell, W.J.

    1996-01-01

    The French have an advantage in nuclear plant operating experience feedback due to the highly centralized nature of their nuclear industry. There is only one utility in charge of design as well as operations (EDF) and only one reactor vendor (Framatome). The ASME Code has played a key role in resolving technical issues in the design and operation of nuclear plants since the inception of nuclear power. The committee structure of the Code brings an ideal combination of senior technical people with both broad and specialized experience to bear on complex how safe is safe enough technical issues. The authors now see an even greater role for the ASME Code in a proposed new regulatory era for the US nuclear industry. The current legalistic confrontational regulatory era has been quite destructive. There now appears to be a real opportunity to begin a new era of technical consensus as the primary means for resolving safety issues. This change can quickly be brought about by having the industry take operating plant problems and regulatory technical issues directly to the ASME Code for timely resolution. Surprisingly, there is no institution in the US nuclear industry with such a mandate. In fact, the industry is organized to feedback through the Nuclear Regulatory Commission issues which could be far better resolved through the ASME Code. Major regulatory benefits can be achieved by closing this loop and providing systematic interaction with the ASME Code. The essential elements of a new regulatory era and ideas for organizing US institutional industry responsibilities, taken from the French experience, are described in this paper

  10. Complementary assessment of the safety of French nuclear power plants

    International Nuclear Information System (INIS)

    Camarcat, N.; Pouget-Abadie, X.

    2011-01-01

    As an immediate consequence of the Fukushima accident the French nuclear safety Authority (ASN) asked EDF to perform a complementary safety assessment for each nuclear power plant dealing with 3 points: 1) the consequences of exceptional natural disasters, 2) the consequences of total loss of electrical power, and 3) the management of emergency situations. The safety margin has to be assessed considering 3 main points: first a review of the conformity to the initial safety requirements, secondly the resistance to events overdoing what the facility was designed to stand for, and the feasibility of any modification susceptible to improve the safety of the facility. This article details the specifications of such assessment, the methodology followed by EDF, the task organization and the time schedule. (A.C.)

  11. French-Finnish colloquium on safety of French and Russian type nuclear power plants

    International Nuclear Information System (INIS)

    Lukka, M.; Jaervinen, M.; Minkkinen, P.; Ukkola, A.; Levomaeki, L.

    1994-01-01

    The French-Finnish Colloquium on Safety of French and Russian Type Nuclear Power Plants was held in June, 14th - 16th, 1994, in Lappeenranta, Finland. The main topics of the colloquium were: VVER and RBMK reactors; Industrial safety studies for VVER's in FRAMATOME; Structural safety analysis of Ignalina NPP; Thermalhydraulic system (BETHSY) and analytical experiments for French NPP; Test facilities simulating VVER plants during accidents; PACTEL - facility for VVER thermal hydraulics; High burn-up fuel and reactivity accidents; Overview of severe accident research at Nuclear Protection and Safety Institute of CEA; Research of severe accidents in Finland; Review of main activities concerning computer codes used for VVER thermal-hydraulic safety analysis in OKB Gidropress; CATHARE code; APROS computer code, new developments; TRIO and TOLBIAC computer codes; ESTET and N3S softwares; HEXTRAN - 3D reactor dynamics code for VVER accident analysis; An overview the boron dilution issue in PWRs; Boron mixing transients in a 900 MW PWR vessel for a reactor start-up operation; and Problem of boric acid dilution in IVO

  12. Experience of load following in French nuclear power plants

    International Nuclear Information System (INIS)

    Miossec, C.

    1989-01-01

    The relative importance of the French nuclear programme has reached such a scale that nuclear power stations can no longer be operated in the base load mode: their capacity exceeded the network demands for 1200 hours in 1983 and it is estimated that this figure will move to 5200 hours in 1990; their power should be able to vary flexibly. These figures illustrate the policy of substituting nuclear power plants for fossil-fired plants and explain the need for nuclear units to provide a quality of service at least equal to that of their ''elders'', which, for several years, have regularly participated in load following. Electricite de France (EDF) therefore had to perform the studies and work necessary to provide nuclear units with the required modulation capacity. There are several grid requirements and three types of flexibility are to be distinguished. The first, load follow, is fundamental when adapting to demand. The second type of flexibility, frequency adjustment, is another important factor in the quality of the product delivered to the consumer. The third type of flexibility is participation in the spinning reserve. When automatic operations are inadequate, available power reserves must be used to support the gird. Load following operations are performed. The operating mode with load modulation is subject to authorisations issued by the governmental organisations responsible for nuclear safety. EDF and the manufacturers have had to prove that such operations remain compatible with safety under normal operating conditions and, in the event of incidents, modulation should be capable of considerably modifying the initial conditions. (5 figures). (Author)

  13. Chemistry evaluation in French EDF Nuclear Power Plants

    International Nuclear Information System (INIS)

    Jacquier, Hervé

    2014-01-01

    The Nuclear Production Division of EDF is comprised of 19 power stations (58 PWR reactors) and 2 national engineering organisations. Nuclear Inspection (IN) is an internal assessment unit of the EDF Nuclear Production Directorate. At the request of the Directorate, it carries out periodic evaluations of all the units of the division. The evaluation of the nuclear sites (EGE: Overall Excellence Assessment) is carried out every 4 years, an intermediate evaluation is also carried out between each EGE. These evaluations are independent of the WANO and IAEA evaluations. Exchanges are carried out between Nuclear Inspection and the other international operators (for example, USA (INPO), England, China...) to share site evaluation methods. These evaluations are carried out by a team of 30 inspectors, reinforced during each evaluation by 10 peers who come from the various French nuclear sites. Nuclear Inspection produces a performance standards document for each FUNCTIONAL AREA, which is based on the requirements of the company. On the whole, 13 areas are evaluated during each inspection, in particular: Management, Operations, Maintenance, Engineering and Chemistry. The area of reactor plant chemistry has been evaluated since 2009. The Chemistry performance standards document is written from the EDF internal requirements and international references. During site evaluations, all the performance standards are assessed for compliance. The Chemistry performance standards document is comprised of 3 topics: Management of plant chemistry, The respect of the chemical and radiochemical specifications, The condition of the laboratories and the sampling lines, measuring equipment, and chemical products. The evaluations carried out make it possible to define strengths and weaknesses which the sites must address. After each evaluation, the assessment is presented to the site management and to the director of EDF Nuclear Production. For 4 years these evaluations have allowed progress to

  14. Protection of French nuclear power plants against flooding risks - 15307

    International Nuclear Information System (INIS)

    Barbaud, J.

    2015-01-01

    In France, the flooding risk has been taken into account since the beginning of the nuclear program and has been reinforced following operating feedback from French and international power plants. The main events which led to reinforcement were the partial flooding in the Blayais NPP that occurred in 1999 and the Fukushima accident in 2011. The current French fleet is composed of 58 PWR reactors located on 19 sites: 4 sites are sea side, 1 side is located on an estuary and all other are located on river side. The lessons learned from the Blayais event are: -) an update of the hazard evaluation of the risks, -) a new assessment of the sufficiency of the protective measures, and -) the taking into account of aggravating risks associated to support functions such as site inaccessibility, loss of off-site power, etc. The lessons learned from the Fukushima accident have confirmed and enhanced lessons from the Blayais event. In addition the Fukushima accident has underlined the need to have sufficient margins beyond the design to avoid cliff edge effects. The improvements implemented on the Blayais and the Belleville sites are detailed

  15. French nuclear plants PWR vessel integrity assessment and life management

    Energy Technology Data Exchange (ETDEWEB)

    Bezdikian, G. [Electricite de France (EDF), Div. Production Nucleaire, 93 - Saint-Denis (France); Quinot, P. [FRAMATOME, Dept. Bloc Reacteur et Boucles Primaires, 92 - Paris-La-Defence (France); Faidy, C.; Churier-Bossennec, H. [Electricite de France (EDF), Div. Ingenierie et Service, 69 - Villeurbanne (France)

    2001-07-01

    The Reactor Pressure Vessel life management of 56 PWR 3 loop and 4 loop reactors units was engaged by the French Utility EDF (Electricite de France) a few years ago and is yet on going on. This paper will present the work carried out within the framework of justifying why the 34 three loop reactor vessels will remain acceptable for operation for a lifetime of at least 40-years. A summary of the measures will be given. An overall review of actions will be presented describing the French approach, using important existing databases, including studies related to irradiation surveillance monitoring program and end of life fluence assessment. The last results obtained are based on generic integrity analyses for all categories of situations (normal upset emergency and faulted conditions) until the end of lifetime, postulating circumferential an radial kinds of flaw located in the stainless steel cladding or shallow sub-cladding area. The results of structural integrity analyses beginning with elastic computations and completed with three-dimensional finite element elastic plastic computations for envelope cases, are compared with code criteria for operating plants. The objective is to evaluate the margins on different parameters as RTNDT (Reference Nil Ductility Transition Temperature), toughness or crack size, to justify the global fitness for service of all these Reactor Pressure Vessels. The paper introduces EDF's maintenance strategy, related to integrity assessment, for those nuclear power plants under operation, based on NDE in-service inspection of the first thirty millimeters in the thickness of the wall and major surveillance programs of the vessels. (author)

  16. French nuclear plants PWR vessel integrity assessment and life management

    International Nuclear Information System (INIS)

    Bezdikian, G.; Quinot, P.; Faidy, C.; Churier-Bossennec, H.

    2001-01-01

    The Reactor Pressure Vessel life management of 56 PWR 3 loop and 4 loop reactors units was engaged by the French Utility EDF (Electricite de France) a few years ago and is yet on going on. This paper will present the work carried out within the framework of justifying why the 34 three loop reactor vessels will remain acceptable for operation for a lifetime of at least 40-years. A summary of the measures will be given. An overall review of actions will be presented describing the French approach, using important existing databases, including studies related to irradiation surveillance monitoring program and end of life fluence assessment. The last results obtained are based on generic integrity analyses for all categories of situations (normal upset emergency and faulted conditions) until the end of lifetime, postulating circumferential an radial kinds of flaw located in the stainless steel cladding or shallow sub-cladding area. The results of structural integrity analyses beginning with elastic computations and completed with three-dimensional finite element elastic plastic computations for envelope cases, are compared with code criteria for operating plants. The objective is to evaluate the margins on different parameters as RTNDT (Reference Nil Ductility Transition Temperature), toughness or crack size, to justify the global fitness for service of all these Reactor Pressure Vessels. The paper introduces EDF's maintenance strategy, related to integrity assessment, for those nuclear power plants under operation, based on NDE in-service inspection of the first thirty millimeters in the thickness of the wall and major surveillance programs of the vessels. (author)

  17. French nuclear plant safeguard pump qualification testing: EPEC test loop

    International Nuclear Information System (INIS)

    Guesnon, H.

    1985-01-01

    This paper reviews the specifications to which nuclear power plant safeguard pumps must be qualified, and surveys the qualification methods and program used in France to verify operability of the pump assembly and major pump components. The EPEC test loop is described along with loop capabilities and acheivements up to now. This paper shows, through an example, the Medium Pressure Safety Injection Pump designed for service in 1300 MW nuclear power plants, and the interesting possibilities offered by qualification testing

  18. Childhood leukaemia incidence below the age of 5 years near French nuclear power plants

    International Nuclear Information System (INIS)

    Laurier, D; Hemon, D; Clavel, J

    2008-01-01

    A recent study indicated an excess risk of leukaemia among children under the age of 5 years living in the vicinity of nuclear power plants in Germany. We present results relating to the incidence of childhood leukaemia in the vicinity of nuclear power plants in France for the same age range. These results do not indicate an excess risk of leukaemia in young children living near French nuclear power plants. (note)

  19. The new operating conditions of French nuclear power plants

    International Nuclear Information System (INIS)

    Leclercq, J.

    1986-01-01

    Six themes are examined: France's unique position in view of the size of its nuclear operating plant, the role of nuclear power in matching electricity supply to demand, the excellent flexibility provided by PWR facilities in operation, the approaches used in the field of automatic operational control systems, the systematic use of data processing for maintenance and generation and the gains in productivity that can be gained as a result of improving fuel use [fr

  20. Safety of Nuclear Power Plants: Commissioning and Operation (French Edition)

    International Nuclear Information System (INIS)

    2012-01-01

    This publication is a revision of Safety Requirements No. NS-R-2, Safety of Nuclear Power Plants: Operation, and has been extended to cover the commissioning stage. It describes the requirements to be met to ensure the safe operation of nuclear power plants. Over recent years there have been developments in areas such as long term operation, plant ageing, periodic safety review, probabilistic safety analysis and risk informed decision making processes. It became necessary to revise the IAEA's safety requirements in these areas and to correct and/or improve the publication on the basis of feedback from its application by both the IAEA and its Member States. In addition, the requirements are governed by, and must apply, the safety objective and safety principles that are established in the Fundamental Safety Principles. Contents: 1. Introduction; 2. Safety objectives and principles; 3. The management and organizational structure of the operating organization; 4. Management of operational safety; 5. Operational safety programmes; 6. Plant commissioning; 7. Plant operations; 8. Maintenance, testing, surveillance and inspection; 9. Preparation for decommissioning.

  1. A human factors data bank for French nuclear power plants

    International Nuclear Information System (INIS)

    Villemeur, A.; Mosneron-Dupin, F.; Bouissou, M.; Meslin, T.

    1986-01-01

    CONFUCIUS is a computerized data bank developed by Electricite de France to study human factors in nuclear power plants. A detailed and homogeneous grouping of described operation and maintenance errors as well as of performance times is possible with CONFUCIUS. It also incorporates a selection of statistical treatment softwares. Readily usable and modifiable, the system can easily evolve. It allows a wide range of applications (safety analysis, event analysis, training, human factors engineering, probabilistic analysis). Data derived from the analysis of significant events reported in power plants and from the analysis of simulator tests are used as inputs into this data bank

  2. An example of the use of robotics in French nuclear power plants the ISIS robot

    International Nuclear Information System (INIS)

    Seguy, J.; Thirion, H.

    1988-01-01

    The authors report how Robotics in French nuclear power plants (NPP) is used to solve maintenance problems. One of the most typical example of the use of robotics in French NPP is the ISIS robot. The first generation of this robot has performed the repair of corroded upper internal structures in Chinon A3 gaz cooled reactor. Two robots of this type have successfully welded more than 200 repair parts in the core without major failure during more than 12,000 hours

  3. Life cycle management of french operating nuclear power plants

    International Nuclear Information System (INIS)

    Valibus, L.; Loriette, Ph.

    1998-01-01

    The PWR units of the EDF generation capacity in operation are young. They represent a technical and financial asset with a strategic significance both for the company and for France. According to regulations, even if the safety reports take into account a 40-year lifetime for the NSSS, the French regulations do not specify a time limit for the operation of the facilities according to the plant authorization decree. The Safety Authorities may, at any time require another safety re-examination. In fact, it was decided to carry out unit safety periodic reviews according to types of series. A program was set up in order to achieve regular assessments on the aging of the facilities. This program, combining all the skills within EDF and the manufacturers, is a guarantee for the coherence and the exhaustivity of the consideration as it relies on a great number of evaluation areas. It seems to day that under operational conditions, an appropriate surveillance and maintenance of components the 900 and 1300 MWe units should be able to fulfill the expected duty for a 40-year design life and very likely even longer. (author)

  4. Severe Accidents: French Regulatory Practice for Nuclear Power Plants

    International Nuclear Information System (INIS)

    Colin, M.

    1997-01-01

    In the framework of a continuous and iterative process, the French Safety Authority asks the utility EDF to implement equipment and procedure modifications on the operating reactors, in order to cope with the most likely Severe Accident sequences. As a result of Probabilistic Safety Assessments published in 1990, important equipment and procedure modifications are being implemented on the French PWRs to improve the safety in shutdown states. The implementation of another set of modifications against some reactivity accident sequences is also in progress. More recently, the Safety Authority expressed specific Severe Accident requirements in terms of instrumentation, equipment qualification, high pressure core melt accidents and hydrogen risk prevention. In that respect, EDF was asked to implement hydrogen recombiners on its reactors. On the other hand, the French Safety authority is involved with its German counterpart in the assessment process of the European Pressurized Water Reactor Project. In consistency with the common recommendations of the Safety Authorities involved, Severe Accident provisions for this reactor are being taken into account at the design stage

  5. Oracle as a tool for monitoring data management in French nuclear power plants

    International Nuclear Information System (INIS)

    Joussellin, A.; Tarteret, P.; Gal, A.

    1996-05-01

    On-line monitoring of the main components of the French nuclear power plants is performed using an integrated system called PSAD (Poste de Surveillance et d'Aide au Diagnostic). In real-time, physical measurement data are continuously acquired, computed and stored in an ORACLE database. All measurement data are dated and represent a wide range of physical variables (temperatures, vibrations, acoustic waves,...). Then, millions of measurements are available to the operator for diagnostic. (author)

  6. Oracle as a tool for monitoring data management in French nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Joussellin, A.; Tarteret, P.; Gal, A.

    1996-05-01

    On-line monitoring of the main components of the French nuclear power plants is performed using an integrated system called PSAD (Poste de Surveillance et d`Aide au Diagnostic). In real-time, physical measurement data are continuously acquired, computed and stored in an ORACLE database. All measurement data are dated and represent a wide range of physical variables (temperatures, vibrations, acoustic waves,...). Then, millions of measurements are available to the operator for diagnostic. (author).

  7. Graphical analysis of French nuclear power plant production date

    Energy Technology Data Exchange (ETDEWEB)

    Jourdan, J.P. [Electricite de France (EDF), Projet Production EPR 1, 93 - Saint-Denis (France)

    2001-07-01

    The analysis of values of plant production uses here an original method of graphical analysis. This method clarifies various difficulties of analysing big experience feedback databases among which the language interpretation and distinctions between scarce events and multi-annual events. In general, the method shows the logical processes that production values obey (pure chance logic, administrative logic, and willpower) This method of graphical analysis provides a tool to observe and question in a concrete way so that each person involved can put the events in which he played a role into the general context of other plants. It is a deductible method to improve this big and complex system. (author)

  8. Graphical analysis of French nuclear power plant production date

    International Nuclear Information System (INIS)

    Jourdan, J.P.

    2001-01-01

    The analysis of values of plant production uses here an original method of graphical analysis. This method clarifies various difficulties of analysing big experience feedback databases among which the language interpretation and distinctions between scarce events and multi-annual events. In general, the method shows the logical processes that production values obey (pure chance logic, administrative logic, and willpower) This method of graphical analysis provides a tool to observe and question in a concrete way so that each person involved can put the events in which he played a role into the general context of other plants. It is a deductible method to improve this big and complex system. (author)

  9. On the safety of French nuclear power plants. Zur Sicherheit der franzoesischen Kernkraftwerke

    Energy Technology Data Exchange (ETDEWEB)

    Anon,

    1990-04-01

    An allegedly secret report by the inspector general for nuclear safety, of EDF, has recently been unearthed and published by the French weekly 'Le Canard Enchaine, and the response in France, and very soon after also in West Germany, has been a number of alarming reports and articles in the press. Readers in West Germany have been stirred up by press reports that made French nuclear power plants appear to be a herd of hazards, which of course again added fuel to the feeling of fear of nuclear power already existing in the population. A copy of the internal report in question was sent without any fuss upon request by the atw editorial office who was preparing the interview. The report is a sober account of the state and operating behaviour of French nuclear power plants, also stating weak points seen by the safety expert that need particular attention. Materials are a main aspect in this context, particularly the materials behaviour in steam raising units. The problems have been spotted, and are given due attention. (orig./HP).

  10. Remote dismantling of the French Brennilis nuclear power plant

    International Nuclear Information System (INIS)

    Studenski, Joerg

    2009-01-01

    The paper deals with the remote dismantling of the decommissioned EL4 prototype power plant Brennilis in France. The block contains the reactor pressure vessel including internals and biological shield, the piping and the control systems. The authors describe the general operation principle of the reactor to illustrate the peculiarities of the dismantling concept and the concept-related challenges. Detailed information is given concerning the following issues: creation of an access to the reactor block, the used remote technology, dismantling of the coolant piping and the axial shield, dismantling of the reactor pressure vessel and the lateral shield. Special attention is given on the minimization of the produced radioactive waste.

  11. Remote dismantling of the French Brennilis nuclear power plant

    Energy Technology Data Exchange (ETDEWEB)

    Studenski, Joerg [NUKEM Technologies GmbH (Germany)

    2009-07-01

    The paper deals with the remote dismantling of the decommissioned EL4 prototype power plant Brennilis in France. The block contains the reactor pressure vessel including internals and biological shield, the piping and the control systems. The authors describe the general operation principle of the reactor to illustrate the peculiarities of the dismantling concept and the concept-related challenges. Detailed information is given concerning the following issues: creation of an access to the reactor block, the used remote technology, dismantling of the coolant piping and the axial shield, dismantling of the reactor pressure vessel and the lateral shield. Special attention is given on the minimization of the produced radioactive waste.

  12. Nuclear power plant performance and mechanical design - French experience

    International Nuclear Information System (INIS)

    Leclercq, J.

    1986-01-01

    The fact that users of nuclear boilers of proved types are no longer troubled by the mechanical structure behaviour of reactors is due to the sustained efforts of construction engineers during the past ten or twenty years to perfect, and incorporate in their equipment studies, the latest developments which have emerged from the expert engineering community of the world, which you represent here today. The presentation is divided into five parts. Firstly, two parts will be devoted to showing how and why the past twenty years have enabled us to achieve our present results which can objectively be regarded as excellent. Thirdly, it is explained why we believe that it is reasonable to assume that our power stations will have an effective life of up to 40 years. In the fourth part I shall revert to more immediate preoccupations and tackle the subject of the desirable optimisation of in service inspection programmes in the light of what we have learnt from modern design studies. (orig./GL)

  13. Ingredients of success in the design and construction of the french nuclear power plants

    International Nuclear Information System (INIS)

    Bacher, P.; Panossian, J.; Riollet, G.

    1989-01-01

    A nuclear program can be compared to a pastry. There are many ingredients, a lot of know-how, an adequate cooking and some good luck to achieve success or back luck to fail. The French nuclear program has had all the ingredients of success and the necessary luck. The present paper presents the major ingredients: strong and well defined policies, an adapted industrial organization, original management methods, dedicated men, political and popular support. The main results of the French program, well known today, are only briefly be presented. The last part of the paper show the very strong interactions between operation and design, and how experience is fed back into the design both of new and of older plants. The conclusion calls for new ingredients for future success

  14. French lessons in nuclear power

    International Nuclear Information System (INIS)

    Valenti, M.

    1991-01-01

    In stark contrast to the American atomic power experience is that of the French. Even the disaster at Chernobyl in 1986, which chilled nuclear programs throughout Western Europe, did not slow the pace of the nuclear program of the state-owned Electricite de France (EDF), based in Paris. Another five units are under construction and are scheduled to be connected to the French national power grid before the end of 1993. In 1989, the EDF's 58 nuclear reactors supplied 73 percent of French electrical needs, a higher percentage than any other country. In the United States, for example, only about 18 percent of electrical power is derived from the atom. Underpinning the success of nuclear energy in France is its use of standardized plant design and technology. This has been an imperative for the French nuclear power industry since 1974, when an intensive program of nuclear power plant construction began. It was then, in the aftermath of the first oil embargo, that the French government decided to reduce its dependence on imported oil by substituting atomic power sources for hydrocarbons. Other pillars supporting French nuclear success include retrofitting older plants with technological or design advances, intensive training of personnel, using robotic and computer aids to reduce downtime, controlling the entire nuclear fuel cycle, and maintaining a comprehensive public information effort about the nuclear program

  15. The French nuclear programme

    International Nuclear Information System (INIS)

    Bacher, Pierre

    1987-01-01

    France has a civil nuclear power generation programme second only to the USA with 49 nuclear units in operation and 13 under construction. The units in service are described. These include 33 PWR 900 MW and 9 PWR 1300 MW units. The electricity consumption and generation in France is illustrated. The absence of a powerful anti-nuclear lobby and two main technical options have contributed to the success of the French nuclear programme. These are the PWR design and the plant standardization policy which allows the setting up of an effective industrial complex (eg for analysis of operating conditions and of safety and reliability information). The programme and the reasons for its success are reviewed. Research programmes and future plans are also discussed. (UK)

  16. Complementary safety assessments of the French nuclear power plants (European 'stress tests'). Report by the French nuclear safety authority - December 2011

    International Nuclear Information System (INIS)

    2011-12-01

    After having recalled the organisation of nuclear safety and radiation protection regulation in France, presented the French nuclear safety regulations (acts, decrees, orders, ASN decisions, rules and guides), described the nuclear safety approach in France (the 'defense in depth' concept), and ASN's sanctions powers, this report presents the French approach to complementary safety assessments (CSAs) with their different types of specifications (those consistent with European specification, those broader than the European specifications, and those which take into account some situations resulting from a malevolent act), and with the different categories of facilities concerned by these CSAs. It presents the organisation of the targeted inspections and outlines the transparency of this action and public information. Then, after an overview of the French nuclear power plant fleet, it discusses how earthquakes, flooding, and other extreme natural phenomena related to flooding are taken into account in the design of facilities and in terms of evaluation of safety margins. It describes the consequences of some critical situations (loss of electrical power supplies and cooling systems) and how they could be dealt with. It also addresses the different aspects of a severe accident management (organisation, measures, and actions to be performed) and the conditions related to the use of outside contractors

  17. The French nuclear context

    International Nuclear Information System (INIS)

    Havard, J.; Israel, M.

    1977-01-01

    The mean- and longer-range energy needs, that can be now forecasted in France, are analyzed, together with the special character of the French energy market. A resort to nuclear power is first shown to be necessary to limit the increase in the demand for imported fossil fuels, then this resort is shown to offer some real possibilities. The energy balance proves that the industrial stage of power plant construction is reached. The conditions of realization of the program have been settled with a set of provisions that render the risk and environmental impact as negligible as possible [fr

  18. French codes and standards for design, construction and in-service inspection of nuclear power plants

    International Nuclear Information System (INIS)

    Hugot, G.; Grandemange, J. M.

    1995-01-01

    In 1970, France decided that its future power plants would be of the Pressurized Water Reactor type. This choice proved to be successful since it resulted in more than 60 PWR units in operation or under construction in France and abroad. At the beginning of such a program, the French engineering and manufacturing industry, the national electrical utility and the Safety Authorities had to face the many challenges imposed by the implementation of an imported technology. The government reorganised the licensing process. FRAMATOME, the NSSS vendor, and EDF (Electricite de France), the national utility, decided to create 'AFCEN', the French Association for Design and Construction Rules for Nuclear Island Components. These rules, the RCC's (Regles de Construction et de conception), which are approved by French Safety Authorities deal with mechanical and electrical equipment as well as with nuclear fuel and civil works. They are now being supplemented by in service inspection rules, the RSE's (Regles d'inspection en Service). The paper presents these Codes and their main updating following experience of application, technical progress and evolution of standards. Status of discussion concerning reference to European standardisation and developments of rules applicable to the EPR project will also be discussed

  19. Review of annual radioecological studies carried out since 1991 in the French nuclear power plants environment

    International Nuclear Information System (INIS)

    Duffa, C.; Gontier, G.; Renaud, P.

    2004-01-01

    Since 1991, the IRSN carries out annual radioecological studies in the environment of the French Nuclear Power Plants. More than 5,000 samples, collected in terrestrial and aquatic ecosystems around the 20 studied plants, have been analysed by low-level gamma spectrometry. This paper presents the main goals and methods for such studies, and the lessons learnt from 11 years results. The French NPP routine atmospheric releases do not lead to detectable radioactive inputs into their surroundings. For this reason, IRSN decided to reduce the number of analysis concerning terrestrial samples since 2000. On the other hand, NPP liquid discharges into rivers are responsible for the presence of low 60 Co, 58 Co, 110m Ag and 54 Mn activities and significant difference in 137 Cs/ 134 Cs activity ratios measured in aquatic compartments. Radioactive discharges of artificial gamma emitters are also detectable in the Channel marine environment around NPP. Nevertheless, this influence is often concealed by radionuclides released by COGEMA-La Hague nuclear reprocessing plant. Beyond important evaluations concerning the presence of artificial radionuclides in NPP's environment, studies conducted since 1991 give us an important database that can be used for a better knowledge of transfers and distribution of radioactivity through the environment. (author)

  20. French nuclear organization

    International Nuclear Information System (INIS)

    Naudet, G.

    1993-01-01

    The French nuclear organization is characterized by two main features: the small number of firms involved and the role of the Government. In this text we give the French organization for nuclear industry and the role of Government and public authorities. 7 figs

  1. The French nuclear law

    International Nuclear Information System (INIS)

    Ito, Hiroshi

    2013-01-01

    The nuclear law had been out of the environmental law. The act on the transparency and the security of the nuclear matter was enacted in 2006 and set in the code of the environment in 2012. It means that the nuclear law is part of the environmental law and that it is advanced. I will report the French nuclear law. (author)

  2. Design of test and emergency procedures to improve operator behaviour in French nuclear power plants

    International Nuclear Information System (INIS)

    Griffon-Fouco, M.; Gomolinski, M.

    1982-09-01

    The incident analyses performed in French nuclear power plants high-lighted that deficiencies in the design of procedures are frequent causes of human errors. The process for developing new guidelines for the writing of test and emergency procedures is presented: this process is based on operators interviews and observations at the plants or at simulators. The main principles for the writing of procedures are developed. For example: - the elaboration of a procedure for action and of a separate educational procedure, - the coordination of crew responses, - the choice of vocabulary, graphs, flow charts and so on as regards the format. Other complementary actions, such as the training of operators in the use of procedures, are described

  3. Design of test and emergency procedures to improve operator behavior in French nuclear power plants

    International Nuclear Information System (INIS)

    Griffon-Fouco, M.; Gomolinski, M.

    1983-01-01

    The incident analyses performed in French nuclear power plants high-lighted that deficiencies in the design of procedures are frequent causes of human errors. The process for developing new guidelines for the writing of test and emergency procedures is presented: this process is based on operators interviews and observations at the plants or at simulators. The main principles for the writing of procedures are developed. For example: the elaboration of a procedure for action and of separate educational procedure; the coordination of crew responses; and the choice of vocabulary, graphs, flow charts and so on as regards the format. Other complementary actions, such as the training of operators in the use of procedures, are described

  4. Broader utilization of programmable automation equipment in French nuclear power plants: Reflections on the choices made by Electricite de France and French designers

    International Nuclear Information System (INIS)

    Baudry, Y.; Varaldi, G.

    1983-01-01

    More than 1000 microprocessors and more than 10,000 data memories in each of the twenty or so 1300 MW units in the French nuclear programme: that was the decision taken by Electricite de France (EDF) in conjunction with the designers in 1974, with the intention of introducing programmable automata on a wide scale in French nuclear power plants. This programme was carried out with the assistance of advanced research services such as the universities, the Commissariat a l'energie atomique (CEA), EDF's design and research service and the designers, most of whom were already EDF suppliers for the 900 MW range. Having used computers for linking sequences (themselves carried out with electromagnetic technology) for its latest natural-uranium gas-cooled graphite-moderated power plants, EDF decided to call a temporary halt, in the case of its 900 MW light-water range, to the use of digital techniques for the control and automation of power plants although it continued to employ such techniques widely in data processing. Thus, the widespread introduction of programmable automata, which was decided upon in 1974/75 at a time when no equivalent existed at the international level, led EDF and French designers to undertake a major development effort in order to meet the requirements - particularly safety and reliability requirements - for such automata to be incorporated into the nuclear field. How does this choice fit in with the logical evolution of the digitalization of French nuclear power plants. What problems has it caused for EDF and French industry. How have these problems been tackled. How have they been overcome. These are the questions dealt with in this paper. (author)

  5. Unplanned unavailability of the French nuclear plants. Evolution. Outstanding facts applications

    International Nuclear Information System (INIS)

    Coppe, P.

    2001-01-01

    The presentation gives a description of the unplanned unavailability of the whole French nuclear units on the aspect performance. The French fleet comprises 58 nuclear units including 34 from the series 900 MW, 20 from the stage 1300 MW and 4 units from the new series N4 of 1450 MW recently commissioned. Because of this width, even if the unavailability of the park remains on a low level on average, the experience feedback on this parameter gives very a rich lesson. The general evolution of unavailability over the last years is the subject of the first part of the talk. Several modes of analysis are examined: by year on the whole of the units, for the various series, by order of age of the various units. The different modes of gathering are examined and others are evoked, in order to reveal those which allow an optimal use of the experience feedback. The outstanding facts are then presented: the principal causes of unavailability are raised and examined. Certain equipment stand out particularly: the reasons of these singularities are exposed as well as the lesson and the modifications brought, the committed actions. Finally the applications resulting from the studies of the unplanned unavailability of the nuclear units are developed. Of course they relate in the forefront to the field of maintenance with the use of these studies within the framework of optimized and adapted programs of maintenance. The contributions are examined. The aging evolution of the plants is also analyzed starting from these studies. The stress is put however on a less obvious application: this one of the future units in design. (author)

  6. Improvements in Defense in Depth in French Nuclear Power Plants Following Fukushima Accidents

    Energy Technology Data Exchange (ETDEWEB)

    Barbaud, J. [EDF SEPTEN, Villeurbanne Cedex (France); Pouget-Abadie, X., E-mail: jean.barbaud@edf.fr [EDF DIN Headquarters, Saint-Denis (France)

    2014-10-15

    The accidents which occurred in the nuclear power plants in Fukushima-Daiichi resulted in a complementary safety assessment (CSA or stress-tests) of all French NPPs to confirm their compliance with their design bases and to evaluate their behaviour beyond it. They have shown that nuclear facilities have a satisfactory level of safety, but it had been decided to significantly improve their robustness to extreme situations, beyond the safety margins they have already. Planned improvements include several parts, where the main ones are the implementation of a hardened safety core (HSC) of key components for the management of extreme situations resulting from a hazard beyond the design and deployment of a nuclear rapid response force (FARN). The hardened safety core aims to avoid massive releases and lasting effects in the environment. It relies on existing or new components designed or verified to hazards with significant margins compared to the design levels of NPP beyond. It also includes provisions allowing crisis management, including crisis centre and communication means. The FARN complements the HSC and the crisis organization to bring from off-site sufficient human and material resources to increase the autonomy of the site. All these improvement contribute to a better defence in depth. (author)

  7. Public perceptions of the iodine tablets distribution around French nuclear power plants

    International Nuclear Information System (INIS)

    Charron, S.; Morin, D.; Brenot, J.

    2000-01-01

    In April 1996 the French ministry of health took the decision to distribute iodine tablets to the population surrounding all nuclear power plants in France. In case of a severe accident the absorption of stable iodine would prevent irradiation of the thyroid by radioactive iodine released by the plant. This preventive distribution was initiated at the end of 1996 around 4 pilot sites, and then spread to all sited in 1997. During this period, the large public sample surveys conducted by IPSN for its barometer contained questions on counter-measures in case of a nuclear accident and more specifically on the distribution of iodine tablets. The aim of this polls was to find out if the general public had known about this decision and to get some feedback on its reactions. The work presented in this paper is the detailed analysis of the two sets of data obtained by the answers to the polls. Some numerical treatments and tests were performed to compare the data, evaluate their consistency and analyse the relation between the distance to a nuclear site and the perception of the public. The main conclusions are that people living close to nuclear sites knew more about the on-going action of the ministry of health, and appreciated it more than the general population but in the same time, many people (70% of interviewed people) are quite reluctant to have tablets in their home; and 65% of the population directly concerned with the distribution did not know where to get their tablets. It is now intended to follow the potential evolution of this results in year 2000 when public authorities have to organise a new distribution of iodine tablets. (author)

  8. French nuclear experience

    International Nuclear Information System (INIS)

    Reynolds, M.; Barre, B.

    1984-01-01

    The French nuclear attache at the French Embassy in Washington discusses his country's energy program and his role at the embassy as a representative of the French nuclear industry. He reviews the nuclear program's growth since it began in 1945, and the impetus of the OPEC oil embargo to accelerate the program since 1973. The success of France's nuclear program is due to a convergence of reasons that include incentive, the existence of a single utility that could design and manage a project of this magnitude, and the decision to focus on the pressurized water reactor (PWR) built by a single supplier and offering the benefits of standardization. Controlling the fuel cycle is the basic philosophy of both the PWR and the breeder program. Barre recommends policies of pre-approved sites, standardization, and licensing reform for the US

  9. Application of fire models for risk analysis in french nuclear power plants

    International Nuclear Information System (INIS)

    Brauns, P.

    1989-04-01

    Numerical simulations of compartment fires have been carried out in the French 900 MW and 1 300 MW nuclear power plants, to obtain quantitative data about this particular kind of risk: characteristic spreading times from one redundant electrical train to the other one, behaviour of important electrical components... The main stages of both studies were the following: selection of rooms, the location or function of which are essential for the plant safety in case of fire, on-site inspections to collect information about these rooms (amount of fuel, openings...), definition of fire scenarios, improvement of the fire model VESTA-PLUS, and, finally calculations using this computer code. The simulations have shown two major trends: i) the spreading times, without taking into account any external intervention, are always greater than half an hour, and ii) the specific design of the 1 300 MW power plants generally prevents one of the redundant train from being damaged due to a fire occurring in a room containing the other one. Examples of typical results obtained are given, showing the capability of application of the improved fire model to complex problems

  10. Improving plant performance through efficient nuclear waste management - The French experience

    International Nuclear Information System (INIS)

    Peterson, C.H.

    1986-01-01

    This paper discusses high and low level waste management and its effect on Plant Performance. In France, high level waste policy is an improtant factor in plant performance. The LLW section of the paper discusses the role of French Industry organization as well as the benefits of standard plants with standard practices. The regulation of the production of waste and the waste processing by utilities is covered

  11. IRSN's viewpoint on the safety and radiation protection of French nuclear power plants in 2007

    International Nuclear Information System (INIS)

    2009-01-01

    This report presents the viewpoint of the IRSN on the safety and radiation protection of EDF's nuclear power plants (NPPs) in operation during 2007. It does not aim to be exhaustive but rather to highlight the points the IRSN considers important for safety. Contributing to maintaining a high level of safety and radiation protection in nuclear facilities in service is one of the seven challenges of the objectives contract signed between the French Government and the IRSN. Safety demands constant vigilance on the part of all the players involved. It is never definitively acquired and must remain a priority and continuously progress, with the plant operator remaining the first entity responsible for the safety of its facility. For the IRSN, part of this mission firstly involves carefully examining and taking into consideration national and international experience feedback, and new scientific knowledge resulting from research. The implementation of improvements, whether technical or organizational or relating to human skills, then comes secondly. This report comprises four sections. In the first section, the IRSN presents the main trends that emerged from its overall review of the safety of the in-service nuclear power plants. The second section addresses the events that have marked the year due to their impact on safety. It also presents a synthesis of the radiation protection events. The third section is devoted to anomalies displaying a generic nature for several power plants. The last section covers the significant changes implemented or scheduled. These are generally modifications or plans of action intended to improve safety performance in the operation or design of the facilities. In spite of sometimes significant disparities in the results between power plants, the IRSN draws the following conclusions from its global review of the year 2007. First of all, no event had serious consequences in the fields of either safety or radioprotection. This good result must

  12. IAEA Team Reviews Safety Progress at French Nuclear Power Plant 19-23 May 2014

    International Nuclear Information System (INIS)

    2014-01-01

    An international team of nuclear installation safety experts led by the International Atomic Energy Agency (IAEA) has evaluated the Gravelines Nuclear Power Plant (NPP) in France to assess how the station has followed up on an Operational Safety Review Team (OSART) mission undertaken in 2012. The IAEA assembled a team of experts at the request of the Government of France to conduct the follow-up OSART mission at Gravelines NPP from 19 to 23 May 2014. Follow-up missions are standard components of the OSART programme; they are typically conducted 15-24 months after the initial OSART mission. The IAEA mission in 2012 made a number of recommendations and suggestions for consideration by the Gravelines NPP operators. The station thoroughly analyzed the OSART recommendations and suggestions and developed corrective action plans. In 18 months, the Gravelines plant has achieved the level ''resolved;; or ''satisfactory progress'' in almost all of the recommendations and suggestions made by the OSART in November 2012. During the follow-up mission, the team assessed that the operators have resolved the issues in several areas, including: Undertaking initiatives to improve fire prevention; Reinforcing contamination control practices; and Enhancing capabilities to protect emergency workers in the event of a release of radioactivity. The team identified some issues which have achieved satisfactory progress toward resolution, but need further work, including: Further improvement of measures to preventing the ingress of items or chemicals into circuits and equipment; Comprehensive application of the corrective actions programme; and Reinforcement of the containment protection system in the event of an extremely adverse situation. The team identified the following issue as one which has made insufficient progress toward resolution and needs further work: Emergency response arrangements do not follow current IAEA safety standards recommending that the plant should have a person on

  13. Radioecological monitoring of the environment of a French nuclear power plant after 12 years in operation

    International Nuclear Information System (INIS)

    Foulquier, L.; Descamps, B.; Roussel, S.

    1992-01-01

    Taking Fessenheim Nuclear Power Plant as an example, this paper gives a description of various types of environmental test carried out under the responsibility of the Operator of Nuclear Power Plants in France: permanent monitoring of radioactivity, periodic radioecological assessments. The main results of measurements taken, show the effect of the Plant to be negligible. 8 refs., 1 fig., 4 tabs

  14. Action taken by the french safety authorities for fire protection and fire fighting in basic nuclear plants

    International Nuclear Information System (INIS)

    Savornin, J.; Gibault, M.; Berger, R.; Kaluzny, Y.; Wallard, H.E.; Winter, D.

    1989-03-01

    The safety goal for nuclear installations is to prevent the dispersal of radioactive substances, both in the work area and outside the buildings into the environment. It is therefore at the design stage, then during construction and subsequent operation that it is necessary to take preventive measures against the outbreak of fire, and to take precautions to ensure that the consequences will always be limited. The paper describes the arrangements made by the French safety authorities to provide protection against fire in both nuclear plants and nuclear fuel cycle installations at all these stages

  15. French nuclear energy policy

    International Nuclear Information System (INIS)

    Ferrari, A.; Bertel, E.

    1980-11-01

    The French energy policy is supported by a lucid view of the situation of our country and the constraints linked to the international context. This statement implies, the definition of a French policy or energy production essentially based on national resources, uranium, and especially for long term, technical know how which allows using plutonium in breeder reactors. This policy implies an effort in R and D, and industrial development of nuclear field, both in reactor construction and at all levels of fuel cycle. This coherent scientific and financial effort has been pursued since the beginning of years 60, and has placed France among the first nuclear countries in the world. Now this effort enables the mastership of a strong nuclear industry capable to assure the energy future of the country [fr

  16. Decision no. 2011-DC-0224 of the French nuclear safety authority from May 5, 2011, ordering the French atomic energy and alternative energies commission (CEA) to proceed to a complementary safety evaluation of some of its basic nuclear facilities in the eyes of the Fukushima Daiichi nuclear power plant accident

    International Nuclear Information System (INIS)

    2011-01-01

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

  17. Development of control room design in French PWR nuclear power plants

    International Nuclear Information System (INIS)

    Guesnier, G.

    1996-01-01

    The layouts of the control rooms of the French nuclear power stations have undergone great development in the period 1970-1990. The control rooms, with an architecture similar to that of the oil fired power stations, were similar to those of the 1300 MW blocks in which the human factor was emphasised. For the selection of a computerised control room for the N4 series, comprehensive functional and ergonomical validation on a full simulator was required. (author) 3 figs., 7 refs

  18. Safety of Nuclear Power Plants: Design. Specific Safety Requirements (French Ed.)

    International Nuclear Information System (INIS)

    2012-01-01

    On the basis of the principles included in the Fundamental Safety Principles, IAEA Safety Standards Series No. SF-1, this Safety Requirements publication establishes requirements applicable to the design of nuclear power plants. It covers the design phase and provides input for the safe operation of the power plant. It elaborates on the safety objective, safety principles and concepts that provide the basis for deriving the safety requirements that must be met for the design of a nuclear power plant. Contents: 1. Introduction; 2. Applying the safety principles and concepts; 3. Management of safety in design; 4. Principal technical requirements; 5. General plant design; 6. Design of specific plant systems.

  19. French experience on renewing I and C systems in NPPs. Feedback from assessing nuclear instrumentation system (RPN) refurbishment at French CP0-series plants

    International Nuclear Information System (INIS)

    Elsensohn, O.; Fradet, F.; Peron, J.C.; Soubies, B.

    2003-01-01

    In 1996, the utility operating France's nuclear power plants launched feasibility studies for the refurbishment of the nuclear instrumentation system (RPN classed category A) installed in its CPO-series (900 MWe) units. The system was ultimately upgraded with digital I and C system, using a SPINLINE 3 platform. This article describes feedback from an evaluation conducted on the refurbishment by the Institute of Radiological Protection and Nuclear Safety (IRSN), technical support arm of the Directorate General for Nuclear Safety and Radiological Protection (DGSNR). The study begins with a historical overview of the refurbishing operation, then discusses the IRSN assessment method and the lessons learned from this first major revamp of an I and C system in the French nuclear reactor series. Based on its previous experience in evaluating I and C systems for P4/P'4 (1300 MWe) and N4 (1450 MWe) plants and to account for the first-ever aspect of such an upgrade, IRSN partitioned its assessment into four phases. This approach enabled taking into account the impact of RPN refurbishment at every level - system, hardware and qualification, software, operation, onsite requalification, health physics, fire protection and human factors. All six units in the CPO series have now been equipped with the new digital RPN. (authors)

  20. Safety of Nuclear Power Plants: Design. Specific Safety Requirements (French Edition)

    International Nuclear Information System (INIS)

    2017-01-01

    This publication establishes requirements applicable to the design of nuclear power plants and elaborates on the safety objective, safety principles and concepts that provide the basis for deriving the safety requirements that must be met for the design of a nuclear power plant. It will be useful for organizations involved in design, manufacture, construction, modification, maintenance, operation and decommissioning of nuclear power plants, as well as for regulatory bodies. A review of Safety Requirements publications was commenced in 2011 following the accident in the Fukushima Daiichi nuclear power plant in Japan. The review revealed no significant areas of weakness and resulted in just a small set of amendments to strengthen the requirements and facilitate their implementation, which are contained in the present publication.

  1. Germany surrounded by ionizing radiation sources from aging nuclear power plants. Update of French data 2012-2014

    International Nuclear Information System (INIS)

    Scherb, Hagen; Voigt, Kristina

    2016-01-01

    The detrimental genetic impact of nuclear facilities has been an important research issue in the past. We studied the birth sex ratio, technically sex odds, near nuclear facilities including all nuclear power plants in France, Germany, and Switzerland. We found evidence for an increase in the birth sex odds for distances of up to 40 km from nuclear facilities. Here, we update our analysis of the French data from 1968 to 2011 with most recent data from 2012 to 2014. Within 20 km from the considered 28 pertinent nuclear facilities in France we see a pronounced increasing sex ratio trend compared to the rest of France where the well-known highly significant global sex ratio decrease prevails. Correspondingly, within the 20 km minimum distance from nuclear facilities in France, the sex odds is elevated, relative to the rest of France, with a sex odds ratio (SOR) of 1.0063 (95%CI: 1.0031, 1.0095) p<0.0001. Therefore, the new French data corroborate our previous findings.

  2. Germany surrounded by ionizing radiation sources from aging nuclear power plants. Update of French data 2012-2014

    Energy Technology Data Exchange (ETDEWEB)

    Scherb, Hagen; Voigt, Kristina [Helmholtz Zentrum Muenchen Deutsches Forschungszentrum fuer Gesundheit und Umwelt GmbH, Neuherberg (Germany)

    2016-07-01

    The detrimental genetic impact of nuclear facilities has been an important research issue in the past. We studied the birth sex ratio, technically sex odds, near nuclear facilities including all nuclear power plants in France, Germany, and Switzerland. We found evidence for an increase in the birth sex odds for distances of up to 40 km from nuclear facilities. Here, we update our analysis of the French data from 1968 to 2011 with most recent data from 2012 to 2014. Within 20 km from the considered 28 pertinent nuclear facilities in France we see a pronounced increasing sex ratio trend compared to the rest of France where the well-known highly significant global sex ratio decrease prevails. Correspondingly, within the 20 km minimum distance from nuclear facilities in France, the sex odds is elevated, relative to the rest of France, with a sex odds ratio (SOR) of 1.0063 (95%CI: 1.0031, 1.0095) p<0.0001. Therefore, the new French data corroborate our previous findings.

  3. Safety of Nuclear Power Plants: Commissioning and Operation. Specific Safety Requirements (French Edition)

    International Nuclear Information System (INIS)

    2016-01-01

    This publication describes the requirements to be met to ensure the safe operation of nuclear power plants. It takes into account developments in areas such as long term operation of nuclear power plants, plant ageing, periodic safety review, probabilistic safety analysis and risk informed decision making processes. In addition, the requirements are governed by, and must apply, the safety objective and safety principles that are established in the IAEA Safety Standards Series No. SF-1, Fundamental Safety Principles. A review of Safety Requirements publications was commenced in 2011 following the accident in the Fukushima Daiichi nuclear power plant in Japan. The review revealed no significant areas of weakness and resulted in just a small set of amendments to strengthen the requirements and facilitate their implementation, which are contained in the present publication.

  4. Harmonization of French and German calculation procedures for atmospheric dispersion following accidental releases from nuclear power plants

    International Nuclear Information System (INIS)

    Crabol, B.; Romeo, E.; Nester, K.

    1992-01-01

    In case of an accident in a nuclear power plant near the French-German border different schemes for dispersion calculations in both countries will currently be applied. An intercomparison of these schemes initiated from the German-French Commission for the safety of nuclear installations (DFK) revealed in some meteorological situations large differences in the resulting concentrations for radionuclides. An ad hoc working group was installed by the DFK with the mandate to analyse the reasons for the different model results and also to consider new theoretical concepts. The working group has agreed to apply a Gaussian puff model for emergency response calculations. The results of the model based on turbulence parameterization via similarity approach or spectral theory - have been compared with tracer experiments for different emission heights and atmospheric stability regimes. As a reference the old modelling approaches have been included in the study. The simulations with the similarity approach and the spectral theory show a slightly better agreement to the measured concentration data than the schemes used in the past. Instead of diffusion categories both new approaches allow a continuous characterization of the atmospheric dispersion conditions. Because the spectral approach incorporates the sampling time of the meteorological data as an adjustable parameter thereby offering the possibility to adjust the dispersion model to different emission scenarios this turbulence parameterization scheme will be foreseen as the basis for a joint French-German puff model

  5. IRSN-ANCCLI partnership. Information day: Childhood leukaemia around French nuclear power plants - April 2012

    International Nuclear Information System (INIS)

    Clavel, Jacqueline; Laurier, Dominique; Sommelet, Daniele; Chantal Bardelay

    2012-04-01

    As an epidemiological study performed by the INSERM highlighted an excess of childhood leukaemia within 5 km around nuclear power plants during the 2002-2007 period, this meeting has been organised to discuss this issue. After a presentation of these results, a contribution discusses the context and research perspectives on the relationship between childhood leukaemia and nuclear sites. After the reported debate, a contribution presents the conclusion of a work-group on childhood leukaemia and ASN works, and a last one presents the activities of a work-group gathering the ANCCLI, IRSN and InVS on the health impact of nuclear installations. A debate on these issues is reported

  6. The French nuclear programme

    International Nuclear Information System (INIS)

    Feger, M.

    1990-01-01

    EDF has long been interested in the use of nuclear energy for thermal power generation. After a period of apprenticeship and experiments, EDF launched a major PWR plant programme so as to reduce France's energy dependence and master generation costs. This programme, based on standardization, has achieved the desired results. It must now be adapted to suit the needs of the 21st century. For this programme, all those involved (Governmental authorities, EDF, manufacturers) were mobilized to an unprecedented extent and rigorous working methods were imposed. Experience feedback has been used to make improvements both to the installations themselves and to procedures. Results have proved satisfactory as regards nuclear safety but vigilance must be maintained. Public opinion on nuclear power is reserved we are sentenced to achieving a 'fault-free' track record, all the while mastering costs, so as to ensure the continuing use of nuclear energy. (author)

  7. The French nuclear programme

    Energy Technology Data Exchange (ETDEWEB)

    Feger, M [Ecole Nationale Superieure d' Electrotechnique de Grenoble, Institute National des Sciences et Techniques Nucleaires (Saclay), Gif-sur-Yvette, Electricite de France (France)

    1990-06-01

    EDF has long been interested in the use of nuclear energy for thermal power generation. After a period of apprenticeship and experiments, EDF launched a major PWR plant programme so as to reduce France's energy dependence and master generation costs. This programme, based on standardization, has achieved the desired results. It must now be adapted to suit the needs of the 21st century. For this programme, all those involved (Governmental authorities, EDF, manufacturers) were mobilized to an unprecedented extent and rigorous working methods were imposed. Experience feedback has been used to make improvements both to the installations themselves and to procedures. Results have proved satisfactory as regards nuclear safety but vigilance must be maintained. Public opinion on nuclear power is reserved we are sentenced to achieving a 'fault-free' track record, all the while mastering costs, so as to ensure the continuing use of nuclear energy. (author)

  8. Operating reliability of valves in French pressurized water nuclear power plants

    International Nuclear Information System (INIS)

    Conte

    1986-10-01

    Taking into account the large numbers of valves (about 10000) of a PWR nuclear power plant, the importance of some valves in the safety functions and the cost resulting from their unavailability, the individual operability of these equipments has to be ensured at a high reliability level. This assurance can be obtained by means of an effort at all the stages which contribute to the quality of the product: design, qualification tests, fabrication, tests at the start-up stage, maintenance and tests during the power plant operation, experience feedback. This paper emphasizes more particularly on the tests carried out on loops of qualification [fr

  9. What the French think about the operational life of nuclear power plants

    International Nuclear Information System (INIS)

    Suteau, R.

    2014-01-01

    A recent opinion survey has been organized to assess how the issue of the lifetime extension of nuclear power plants was understood by the man on the street in France. 20 people have been interviewed after participating to a meeting in which 3 experts from different opinions on nuclear energy have shared their vision of lifetime extension. It appears that lifetime extension is not considered as an issue in itself but belongs to a more important issue that is the future of nuclear energy. Most people do not disagree with the idea of lifetime extension if this extension does not go beyond 10 years and their agreement is strongly correlated with other issues like the management of radioactive waste, the quality and follow-up of sub-contractors and the real alternatives to nuclear energy. 5 profile types have been identified from the most reluctant to the use of nuclear energy who consider lifetime extension as a leap forward in the bad direction to the most confident who agree with both nuclear energy and lifetime extension strategy. (A.C.)

  10. Properties of a large carbon steel casting used in French PWR nuclear plant

    International Nuclear Information System (INIS)

    Benhamou, C.; Roux, F.; Nectoux, G.; Delorme, A.

    1980-09-01

    To introduce a large casting in a PWR nuclear plant migh appear detrimental to its safety when comparing with forgings or rollings. In this paper we would like to show the constant efforts of the founder in providing a product with reproducible and high quality. Furthermore a program test covering a complete investigation of a real channel head is presented; the three following aspects have been studied: characterisation of cast flaws by non destructive and destructive examination, homogeneity of casting and fatigue and use properties

  11. Ecology of Legionella within water cooling circuits of nuclear power plants along the French Loire River

    International Nuclear Information System (INIS)

    Jakubek, Delphine

    2012-01-01

    The cooling circuits of nuclear power plants, by their mode of operating, can select thermophilic microorganisms including the pathogenic organism Legionella pneumophila. To control the development of this genus, a disinfection treatment of water cooling systems with monochloramine can be used. To participate in the management of health and environmental risks associated with the physico-chemical and microbiological modification of water collected from the river, EDF is committed to a process of increasing knowledge about the ecology of Legionella in cooling circuits and its links with its environment (physical, chemical and microbiological) supporting or not their proliferation. Thus, diversity and dynamics of culturable Legionella pneumophila were determined in the four nuclear power plants along the Loire for a year and their links with physico-chemical and microbiological parameters were studied. This study revealed a high diversity of Legionella pneumophila subpopulations and their dynamic seems to be related to the evolution of a small number of subpopulations. Legionella subpopulations seem to maintain strain-specific relationships with biotic parameters and present different sensitivities to physico-chemical variations. The design of cooling circuits could impact the Legionella community. The use of monochloramine severely disrupts the ecosystem but does not select biocide tolerant subpopulations. (author)

  12. Preventive acid chemical cleaning operation (PACCO) on steam generator in French nuclear power plants

    International Nuclear Information System (INIS)

    Traino, Jules; Ruiz Martinez, Jose Thomas; Rottner, Bernard; Vedova, Eric

    2014-01-01

    Steam Generators (SG) usually present important deposit loading and Tube Support Blockage, resulting from Secondary Side corrosion products. These phenomena modify SG behavior which can lead to safety, heat exchange performance and lifetime problems. In this context, a Chemical Cleaning Process (PACCO) was designed to solve the issue. After almost two years of intensive lab tests, pilot simulation and mock-ups, the chemical process was finally qualified by EDF. The aim of the work was firstly the development in laboratory of a chemical process that could eliminate partially the deposit loading, respecting the integrity of materials and gas emission limits. Secondly, the objective was the design and the implementation of the process on-site. The process has been applied successfully in 3 SG in Dampierre nuclear power plant in France on July 2013. The main results were: - Corrosion < 100 μm. - 40% of the initial deposit loading, removed by SG. (authors)

  13. The human factor in the design and operation of french light water nuclear power plants

    International Nuclear Information System (INIS)

    Gomolinski, M.

    1986-10-01

    The accident which occurred at Three Mile Island (TMI 2) on March 28, 1979 is considered rightfully as the outset of the approach taking the human factor explicitly into account in nuclear safety, both in the design of the plants and in their operational use. In this paper, we shall endeavour to explain how this human factor has been taken into account in France. For this purpose, in the first part, we shall define the requirements, i.e. describe the sectors in which improvements were deemed necessary. In the second part, we shall describe the structures set up both at EDF and at the CEA to handle these problems. Lastly, in the third part, we shall describe the principal actions taken or in progress [fr

  14. Decommissioning of nuclear reprocessing plants French past experience and approach to future large scale operations

    International Nuclear Information System (INIS)

    Jean Jacques, M.; Maurel, J.J.; Maillet, J.

    1994-01-01

    Over the years, France has built up significant experience in dismantling nuclear fuel reprocessing facilities or various types of units representative of a modern reprocessing plant. However, only small or medium scale operations have been carried out so far. To prepare the future decommissioning of large size industrial facilities such as UP1 (Marcoule) and UP2 (La Hague), new technologies must be developed to maximize waste recycling and optimize direct operations by operators, taking the integrated dose and cost aspects into account. The decommissioning and dismantling methodology comprises: a preparation phase for inventory, choice and installation of tools and arrangement of working areas, a dismantling phase with decontamination, and a final contamination control phase. Detailed description of dismantling operations of the MA Pu finishing facility (La Hague) and of the RM2 radio metallurgical laboratory (CEA-Fontenay-aux-Roses) are given as examples. (J.S.). 3 tabs

  15. DIVA and DIAPO: two diagnostic knowledge based systems used for French nuclear power plants

    International Nuclear Information System (INIS)

    Porcheron, M.; Ricard, B.; Joussellin, A.

    1997-01-01

    In order to improve monitoring and diagnosis capabilities in nuclear power plants, Electricite de France (EDF) has designed an integrated monitoring and diagnosis assistance system: PSAD-Poste de Surveillance et d'Aide au Diagnostic. The development of such a sophisticated monitoring and data processing systems has emphasized the need for the addition of analysis and diagnosis assistance capabilities. Therefore, diagnostic knowledge based systems have been added to the functions monitored in PSAD: DIVA for turbine generators, and DIAPO for reactor coolant pumps. These systems were designed from a representation of the diagnostic reasoning process of experts and of the supporting knowledge. Diagnosis in both systems relies on an abduction reasoning process applied to component fault models and observations derived from their actual behavior, as provided by the monitoring functions. The basic theoretical elements of this diagnostic model are summarized in a first part. In a second part, DIVA and DIAPO specific elements are described

  16. Evolution of the feedback from experience on degradations of French nuclear power plants condensers and foreseen solutions

    Energy Technology Data Exchange (ETDEWEB)

    Mayos, M.; Chanel, F.; Copin, E.; Carlier, L. [EDF/DIN/CEIDRE, Saint-Denis (France); Coquio, N.; Garbay, E. [EDF/DIN/CEIDRE, Avoine (France); Bastian, C. [EDF/DPN/UNIE, Saint-Denis (France)

    2011-07-01

    The materials constituting the condenser tubes of French nuclear power plants display a great diversity and are subject to different degradations, known from the operational feedback from experience. Copper alloys (mainly brass), which were bound to disappear in renovated condensers, are still significantly present, due to their unique bacteriostatic ability. Brass tubes lifetime is still governed in general by steady abrasion, as evaluated by eddy current nondestructive testing. However, an atypical NDE (non-destructive evaluation) behavior has led to spot a new damage: localized under-deposit pitting corrosion on the raw water side, caused by the particular quality of water chemistry and heavy scaling of the tube surface. This damage is likely to overcome steady abrasion for tube life prediction. Prevention includes a tighter look at NDE indications and improved descaling solutions (chemical or mechanical). Other specific damages have been reported from operation feedback: the main one was accidental stress corrosion cracking, which has occurred on some recently renovated brass condenser tube bundles. Thanks to a metallurgical and mechanical study, its cause was found in the manufacturing process. This experience has resulted in tightened specifications for brass tubes manufacturing. Stainless steel and titanium still appear more damage-resistant and represent a safe solution when no microorganism issue is present. The degradation feedback, confirmed by NDE inspections, is very low in French power plants. However, titanium hydriding still represents an issue when cathodic protection is present. Furthermore, some other damages have been reported on titanium, like isolated steam erosion. Vibration fatigue damage has been observed on stainless steel tubes, but it is more in relationship with the condenser design than with the material itself. (authors)

  17. Probabilistic safety assessment of French 900 and 1,300 MWe nuclear plants

    International Nuclear Information System (INIS)

    Brisbois, J.; Lanore, J.M.

    1991-08-01

    Although reactor design is mainly governed by deterministic principles in France, the probabilistic approach has been considered an important aid to safety analysis since the early seventies. Various partial probabilistic studies have been performed by Electricite de France, by IPSN and by Framatome, for various types of reactor. In particular, these studies have made it possible to assess the reliability and availability of nuclear power plants safety systems as well as the probability of accident scenarios and have helped to define technical specifications (especially, allowed operating times in the event of a partial unavailability of safety systems). Simultaneously, evaluation methods and corresponding software have been widely developed. Besides. EDF has implemented the Systeme de Recueil de Donnees de Fiabilite - SRDF (Reliability Data Collection System) which allows follow-up of equipment behaviour on all the operating units, and has led to a particularly representative data base. In 1982 the decision was taken at IPSN to carry out a complete PSA for a standard reactor of the 900 MWe type, and in 1986 EDF launched an equivalent study on a 1,300 MWe reactor, taking Unit 3 Paluel as reference. These PSAs were terminated in the course of the first quarter of 1990

  18. Probabilistic safety assessment of French 900 and 1,300 MWe nuclear plants

    International Nuclear Information System (INIS)

    Brisbois, J.; Lanore, J.M.

    1991-01-01

    Although reactor design is mainly governed by deterministic principles in France, the probabilistic approach has been considered an important aid to safety analysis since the early seventies. Various partial probabilistic studies have been performed by Electricite de France, by IPSN and by Framatome, for various types of reactor. In particular, these studies have made it possible to assess the reliability and availability of nuclear power plants safety systems as well as the probability of accident scenarios and have helped to define technical specifications (especially, allowed operating times in the event of a partial unavailability of safety systems). Simultaneously, evaluation methods and corresponding software have been widely developed. Besides. EDF has implemented the Systeme de Recueil de Donnees de Fiabilite - SRDF (Reliability Data Collection System) which allows follow-up of equipment behaviour on all the operating units, and has led to a particularly representative data base. In 1982 the decision was taken at IPSN to carry out a complete PSA for a standard reactor of the 900 MWe type, and in 1986 EDF launched an equivalent study on a 1,300 MWe reactor, taking Unit 3 Paluel as reference. These PSAs were terminated in the course of the first quarter of 1990. (author)

  19. Decision no. 2011-DC-0219 of the French nuclear safety authority from May 5, 2011, ordering the SOCATRI company to proceed to a complementary safety evaluation of some of its basic nuclear facilities in the eyes of the Fukushima Daiichi nuclear power plant accident

    International Nuclear Information System (INIS)

    2011-01-01

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

  20. French PWR nuclear power plants: Probabilistic studies of accident sequences and related findings

    International Nuclear Information System (INIS)

    Villemeur, A.; Moroni, J.M.; Berger, J.P.; Meslin, T.

    1987-01-01

    This paper presents the major studies performed in France by EDF in the framework of probabilistic studies. It describes the part played by these studies especially as regards: the assessment of the allowed outage time in the event of a safety component unavailability, the risk assessment in the event of a total loss of system (heat sink, electric power supplies, etc.). The specific features of the French 'living' PSA, now still in progress, are also presented. (orig./HSCH)

  1. Directory of the French nuclear industry

    International Nuclear Information System (INIS)

    2002-10-01

    This directory includes data sheets on the French companies operating in the nuclear industry. It begins with an introduction containing information on the French nuclear industry: 1 - nuclear power development in France (national energy plan, history, organization, economic advantages, reactors); 2 - French operator: Electricite de France (EdF); 3 - the industry (Areva, Cogema, mining activities, uranium chemistry and enrichment, processing, recycling, engineering, services, Framatome ANP); 4 - R and D and knowledge dissemination: French atomic energy commission (CEA); 5 - nuclear safety, security, control and regulation: nuclear safety authority (ASN), general direction of nuclear safety and radioprotection (DGSNR), institute of radioprotection and nuclear safety (IRSN), radioactive wastes, ANDRA's role; 6 - associations: French atomic forum (FAF), French nuclear industry trade association (GIIN), French nuclear energy society (SFEN), French radiation protection society (SFRP). Then, the data sheets of the directory follows. (J.S.)

  2. IRSN's viewpoint on the safety and radiation protection of French nuclear power plants in 2007

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2009-07-01

    This report presents the viewpoint of the IRSN on the safety and radiation protection of EDF's nuclear power plants (NPPs) in operation during 2007. It does not aim to be exhaustive but rather to highlight the points the IRSN considers important for safety. Contributing to maintaining a high level of safety and radiation protection in nuclear facilities in service is one of the seven challenges of the objectives contract signed between the French Government and the IRSN. Safety demands constant vigilance on the part of all the players involved. It is never definitively acquired and must remain a priority and continuously progress, with the plant operator remaining the first entity responsible for the safety of its facility. For the IRSN, part of this mission firstly involves carefully examining and taking into consideration national and international experience feedback, and new scientific knowledge resulting from research. The implementation of improvements, whether technical or organizational or relating to human skills, then comes secondly. This report comprises four sections. In the first section, the IRSN presents the main trends that emerged from its overall review of the safety of the in-service nuclear power plants. The second section addresses the events that have marked the year due to their impact on safety. It also presents a synthesis of the radiation protection events. The third section is devoted to anomalies displaying a generic nature for several power plants. The last section covers the significant changes implemented or scheduled. These are generally modifications or plans of action intended to improve safety performance in the operation or design of the facilities. In spite of sometimes significant disparities in the results between power plants, the IRSN draws the following conclusions from its global review of the year 2007. First of all, no event had serious consequences in the fields of either safety or radioprotection. This good result

  3. Progress of French nuclear programme

    International Nuclear Information System (INIS)

    Pierrard, J.-H.

    1981-02-01

    The aims of the French nuclear programme launched in 1974 are briefly recalled to mind, as are the projects completed at the end of 1980. The operating results mentioned, particularly concern the new PWR units brought into commercial service in 1980 [fr

  4. Decision no. 2011-DC-0222 of the French nuclear safety authority from May 5, 2011, ordering the Comurhex company to proceed to a complementary safety evaluation of some of its basic nuclear facilities in the eyes of the Fukushima Daiichi nuclear power plant accident

    International Nuclear Information System (INIS)

    2011-01-01

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

  5. Decision no. 2011-DC-0223 of the French nuclear safety authority from May 5, 2011, ordering the MELOX SA company to proceed to a complementary safety evaluation of some of its basic nuclear facilities in the eyes of the Fukushima Daiichi nuclear power plant accident

    International Nuclear Information System (INIS)

    2011-01-01

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

  6. Decision no. 2011-DC-0218 of the French nuclear safety authority from May 5, 2011, ordering the EURODIF SA company to proceed to a complementary safety evaluation of some of its basic nuclear facilities in the eyes of the Fukushima Daiichi nuclear power plant accident

    International Nuclear Information System (INIS)

    2011-01-01

    As a consequence of the accident of the Fukushima Daiichi nuclear power plant (Japan), the French Prime Minister entrusted the French nuclear safety authority (ASN) with the mission to carry out a safety analysis re-evaluation of the French nuclear facilities, and in particular the nuclear power plants. A decision has been addressed by the ASN to each nuclear operator with the specifications of this safety re-evaluation analysis and the list of facilities in concern. This document is the decision addressed to the EURODIF SA company, operator of the George Besse I uranium enrichment plant of the Tricastin site (France). (J.S.)

  7. Generic results and conclusions of re-evaluating the flooding protection in French Nuclear Power Plants

    International Nuclear Information System (INIS)

    Vial, E.; Rebour, V.; Mattei, J.; Gprbatchev, A.

    2002-01-01

    The partial flooding of the Blayais site, occurred on December 1999 has led to a large scale re-examination of the measures to prevent and limit the consequences associated with all contingencies or combinations of them, which could lead to external flooding of any of the 19 French sites, equipped with pressurized water reactors. An Action Program has been launched by Electricite de France and a methodology has been approved, consisting of: defining of principles for re-evaluating external flooding risks together with the relevant arrangements; applying the principles to each site and showing that the margins adopted are sufficient for achieving an acceptable safety level. The implementation of the program throughout all sites with PWR in France will extend to 2005

  8. Short-circuit tests of 1650 and 96 MVA transformers for 1300 MW french nuclear power plants

    International Nuclear Information System (INIS)

    Mailhot, M.

    1989-01-01

    Power evacuation and feeding of the auxiliaries directly from the 400 kV grid are sensitive points governing the security of 1300 MW PWR Nuclear Power Plants of the French Program. These two different functions are provided by two specific types of transformers. - Banks of 3 single-phase 550 MVA - 400 kV/20 kV transformers. - Three-phase 96 MVA - 400 kV / 3 x 6.8 kV transformers. These passive elements must have a never failing reliability and assure a continuous service in spite of electric, thermal and mechanical stresses that may occur during the lifetime of the power plant. Dielectric and thermal tests carried out in the manufacturers test floors insure these stresses withstand capabilities of transformers. In France, high short-circuit power for the 400 kV network added to often low impedance voltages for transformers impose on them very high stresses during short-circuits. Calculation and experimentation on scale or partial models are not sufficient to insure short-circuit currents withstand capabilities of transformers. The margin of uncertainty dependent on obligatory extrapolations for this kind of complex systems [steel, magnetic sheets, copper, oil, paper and transformerboard] can be reduced in a significant way only by real scale tests on prototypes. These tests that need both high power and voltage cannot be performed in manufacturers test floors. So, in France they are carried out at the EDF Les Renardieres Laboratory. Following paper deals with SHELL TYPE TRANSFORMERS which, particularly thanks to their interleaved rectangular windings display a great resistance to short-circuit stresses

  9. Neutron dosimetry in French nuclear power plants. Problems and their solutions in 1995

    International Nuclear Information System (INIS)

    Guibbaud, Y.; Dollo, R.; Rannou, A.

    1996-01-01

    Exposure to neutron radiation in the nuclear industry is normally limited to a small number of workers essentially EDF employees operating in specific areas. Operational collective dose due to neutron exposure is almost negligible compared to the rest of the external doses (less than 2 % in the collective dose equivalent). But this risk represents a significant fraction of the annual dose equivalent of those exposed. Suggest specifications for individual dosemeters which would ideally meet both technical and practical requirements. (author)

  10. Operability of the valves in the french pressurized water nuclear plants

    International Nuclear Information System (INIS)

    Conte, M.; Vrillon, B.

    1986-10-01

    There are about 10 000 valves in a PWR, which must have a high standard of reliability. This confidence can be obtained by a continuous effort at every important stage, in the maintenance of the product's quality: design, loop qualifying tests, manufacture, plant start-up tests, maintenance and periodic tests during operation, feed-back of experience. This paper describes more particularly the loop qualifying tests

  11. French people and nuclear wastes

    International Nuclear Information System (INIS)

    D'Iribarne, Ph.

    2005-01-01

    On March 21, 2005, the French minister of industry gave to the author of this document, the mission to shade a sociological light on the radioactive wastes perception by French people. The objective of this study was to supply an additional information before the laying down in 2006 of the decisions about the management of high-level and long-lived radioactive wastes. This inquiry, carried out between April 2004 and March 2005, stresses on the knowledge and doubts of the questioned people, on the vision they have of radioactive wastes and of their hazards, and on their opinion about the actors in concern (experts, nuclear companies, government, anti-nuclear groups, public). The last two parts of the report consider the different ways of waste management under study today, and the differences between the opinion of people living close to the Bure site and the opinion of people living in other regions. (J.S.)

  12. Decision no. 2011-DC-0216 of the French nuclear safety authority from May 5, 2011, ordering the Laue Langevin Institute to proceed to a complementary safety evaluation of its basic nuclear facility (high flux reactor - INB no. 67) in the eyes of the Fukushima Daiichi nuclear power plant accident

    International Nuclear Information System (INIS)

    2011-01-01

    As a consequence of the accident of the Fukushima Daiichi nuclear power plant (Japan), the French Prime Minister entrusted the French nuclear safety authority (ASN) with the mission to carry out a safety analysis re-evaluation of the French nuclear facilities, and in particular the nuclear power plants. A decision has been addressed by the ASN to each nuclear operator with the specifications of this safety re-evaluation analysis and the list of facilities in concern. This document is the decision addressed to the Laue Langevin Institute, operator of the high flux research reactor (RHF) of Grenoble (France). (J.S.)

  13. Decision no. 2011-DC-0215 of the French nuclear safety authority from May 5, 2011, ordering ITER Organization to proceed to a complementary safety evaluation of its basic nuclear facility in the eyes of the Fukushima Daiichi nuclear power plant accident

    International Nuclear Information System (INIS)

    2011-01-01

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

  14. Decision no. 2011-DC-0214 of the French nuclear safety authority from May 5, 2011, ordering CIS bio international company to proceed to a complementary safety evaluation of its basic nuclear facility in the eyes of the Fukushima Daiichi nuclear power plant accident

    International Nuclear Information System (INIS)

    2011-01-01

    As a consequence of the accident of the Fukushima Daiichi nuclear power plant (Japan), the French Prime Minister entrusted the French nuclear safety authority (ASN) with the mission to carry out a safety analysis re-evaluation of the French nuclear facilities, and in particular the nuclear power plants. A decision has been addressed by the ASN to each nuclear operator with the specifications of this safety re-evaluation analysis and the list of facilities in concern. This document is the decision addressed to CIS bio international company, operator of the radiopharmaceuticals fabrication facility (INB 29) of Saclay (France). (J.S.)

  15. Removal of secondary sludge from steam generators used in French 900 class nuclear power plants

    International Nuclear Information System (INIS)

    Lebouc, B.

    1982-09-01

    The objective is to remove magnetite deposits which have formed on a steam generator tubesheet during plant operation. The deposits are separated from the tubesheet by spraying water at high pressure (about 200 bar at lance nozzle outlets) on each tube bundle ligament, i.e. the spaces between steam generator tubes. The water is recovered in suction lines and then filtered in two seperate units. The residue obtained after settling is removed in the form of solid waste. This paper presents the sludge lancing technique (spray lances, sludge recovery, liquid waste, cooling). A typical operating sequence is detailed (duration, personnel). Specifications for the equipment used are given

  16. Organizations putting in place in case of accident in a french nuclear power plant

    International Nuclear Information System (INIS)

    Noc, B.; Queniart, D.

    1987-01-01

    In case of accident entraining radiological consequences on or near the site of nuclear power reactor, organizations are putting in place. These organizations include as well as side of operating authority (generally Electricite de France) or public organizations including safety organizations (Service Central de Surete des Installations Nucleaires, Institut de Protection et de Surete Nucleaire), one local organization and one centralized national organization. Informations exchange and coordination necessary between these organizations are governed by protocols. These protocols include particularly, the problems of mobilizing experts and of dealing with the saturation of normal telecommunications channels. The lessons acquired during accident simulation exercises carried out in recent years are progressively put in place in these protocols [fr

  17. French opinion on Nuclear Energy

    International Nuclear Information System (INIS)

    Bucaille, A.

    2003-01-01

    Contrary to what many think or say, most French people do not have a clear-cut opinion about nuclear power. And until public opinion can be accurately assessed, we should be worried of speaking on its behalf. More than half the population of France believes that nuclear power is the cheapest option, but 40% of them have no idea what the situation really is. The French are keenly aware of the what is at stake at the international level, and the fact that energy is becoming a worldwide issue. What they are most concerned about is nuclear waste and the possibility of a catastrophe of the Chernobyl type occurring. Disquiet about the first is now dissipating, after having increased. But attitudes about the second are ambivalent. A quarter of the French are very ignorant about radioactivity. 20% of the population complain that not enough information is forthcoming, particularly as concerns advances in technology. As can be anticipated, awareness of the question of climate change is growing year by year, with increased reporting of storms, floods and heat waves

  18. Severity scale for incidents and accidents in French nuclear power plant

    International Nuclear Information System (INIS)

    Dupuis, M.C.; Guimbail, H.; Debes, M.; Roels, C.

    1988-10-01

    All countries operating nuclear power stations have developed systems for declaring and analyzing incidents occurring when the stations are in service. These systems, are inevitably extensive and complex, as the search for perfection in terms of operating safety leads not only to identification and analysis of incidents which are evidenced by their consequences, but also to identification of all those other incidents which have not had repercussions, but which nevertheless constitute precursor events for more serious situations. For example in France, a system based on safety significance criteria has been in service since the early 1980s, and is applied and operated by EDF and the safety authorities. While experts obtain maximum benefit from this system, public opinion and the relay points constituted by the media are somewhat at a loss, being unable to discriminate in the mass of non-hierarchized information which may come their way, between what is genuinely important and what is less important or even totally unimportant. For this reason, the CSSIN recommended examination of a severity scale, simple to understand and easy to use, which could be employed to classify all incidents and which could become, in due course, as familiar to all of us as the Richter seismic scale is today. We will now examine the composition of this scale, applied on an experimental basis by the Minister for Industry for a period of about one and a half years, as from 20th April 1988

  19. Training within the French nuclear power program

    International Nuclear Information System (INIS)

    Jusselin, F.

    1987-01-01

    Training dispensed by the EDF Nuclear and Fossil Generation Division has contributed significantly toward successful startup and operation of French nuclear power plants. In 1986, the time-based availability of 900 MW PWRs totaled 85 %. This is just one example of how EDF training programs have benefited from 150 reactor-years of operating experience and the ensuing opportunities for perfecting and testing of training tool effectiveness. These programs have been adopted by utilities in other countries where suitable local facilities are making advantageous use of EDF training experience and methods. EDF expertise is also transferred to these countries indirectly through the simulator manufacturer

  20. Radioactive waste from nuclear power plants and back end nuclear fuel cycle operations: The French approach to safety

    International Nuclear Information System (INIS)

    Gagner, L.; Voinis, S.; De Franco, M.

    2001-01-01

    The Centre de l'Aube Disposal Facility (Centre de Stockage de l'Aube) is designed to receive a wide variety of waste produced by nuclear power plants, reprocessing, decommissioning, as well as the industry, hospitals and armed forces. Such a variety of wastes incur highly different risks which must be grasped in the safety analysis of the Centre. This article attempts to show how a number of safety analysis tools are used to meet the highly varied needs of the waste producers and guarantee safe disposal. They involve functional analysis, risk analysis and safety calculations. The paper shows that the most important acceptance criteria for the first containment barrier, namely the waste package, are containment, durability, activity limitation and biological shielding. And a method is proposed to determine some of these criteria from safety scenarios (scenarios of accidents in operation, intrusion in the post-institutional control phase). Over the years, however, the waste producers have asked the Agence Nationale pour la Gestion des Dechets Radioactifs (ANDRA) to accept new types of waste not initially anticipated in the design criteria, and the safety analysis must imagine new scenarios and develop new acceptance criteria. The paper gives the example of sealed sources, closure heads of NPP vessels, racks for fuel elements, contaminated manipulators, irradiating waste, etc, which incur specific risks. In fact, some of this waste represent a source of unusual irradiation, a risk of further contamination in an accidental situation, or simply increase the likelihood of occurrence of certain scenarios, such as retrieval in the post-institutional control phase. The safety analysis must adapt and imagine specific scenarios to judge the acceptability of such waste, and must identify the acceptance criteria commensurate with the risks. The paper offers examples of research, some of it still under way at ANDRA. (author)

  1. Living probabilistic safety assessment of French 1300 MWe PWR nuclear power plant unit: methodology, results and teaching

    International Nuclear Information System (INIS)

    Dubreuil Chambardel, A.; Villemeur, A.; Berger, J.P.; Moroni, J.M.

    1991-02-01

    Launched in 1986 by Electricite de France, the Probabilistic Safety Assessment of a French 1300 MWe Pressurized Water Reactor (called PSA 1300) was completed in 1989. The first objective was to assess the annual core damage frequency by identifying all the accident scenarii likely to contribute significantly to this frequency. The second objective of the study was to provide an automated computerized tool (software) for updating the assessment - in order to take new data and knowledge into account - and for performing numerous sensitivity studies easily. Its scope and characteristics render this study unique. Indeed, it required an effort amounting to 50 engineer-years. The results and the first lessons are presented in this paper. The PSA 1300 teachings will be extensively used for the design and operation of existing or future French nuclear power reactors

  2. Industrial aspects of nuclear energy: French experience

    International Nuclear Information System (INIS)

    Lebreton, G.

    1986-11-01

    France decides to develop nuclear energy on a wide scale about 12 years ago. To cope with this ambitious program, the roles have been distributed within a very cohesive organization, as follows: EDF, the french national electricity utility is owner, prime contractor, and plant operator. The Atomic Energy Commission, CEA performs part of the research and development work, and supplies the necessary technical support to the safety authorities. A few leading industrial firms design and build the major parts of the nuclear power plants. Among them is Framatome, which is responsible for the design, manufacture, erection, and startup of nuclear steam supply systems (the NSSSs), and related auxiliaries. Alsthom is responsible for the supply of the turbine and its auxiliaries. It would not be proper to describe the French nuclear industry without focussing our attention on the care given to transfer of technology. Technology transfer agreements can take several forms, but local factors have to be taken into account. These forms are discussed in this paper. A typical and highly significant example (KNU 9-10 project) is given

  3. The French nuclear power programme and energy policy in France

    International Nuclear Information System (INIS)

    Carle, R.

    1988-01-01

    After briefly describing the Chernobyl reactor accident and its consequences in Western Europe, especially its psychological effects, the French nuclear energy programme is presented in detail. The role of standardization and education as well as of construction time and cost is pointed out. Moreover, the results of the programme are given including extension of the capable French nuclear power industry, economical and ecological benefits. Future measures such as increase of the flexibility of nuclear power plants, improved fuel management, reduction of personnel radiation doses and employment of advanced reactors (the reactor system N4) will facilitate French efforts to free the country from mineral oil and coal imports. (author)

  4. Nuclear transparency: the French example

    International Nuclear Information System (INIS)

    Phuc Tran Dai

    2016-01-01

    In France nuclear industry is from far the industrial sector that has set the most numerous commissions that allow a dialogue with the public in order to favor transparency. There are 4 local structures of information: -)there are 38 Local Committees of Information (CLI) associated with nuclear facilities, -) the Information Committees (CI) associated with secret nuclear facilities, -) the Follow-up Committees (CSS) for facilities dedicated to the processing of wastes, and the Committees for the prevention of industrial pollution (SPPPI). These committees involve numerous actors: public service, industrialists, supervisory authorities, elected representatives, employee representatives, members of associations and residents living nearby. Since 2000, 10 national public hearings around the 'atom' have been organized by the CNDP (National Commission for Public Consultation). Most actors of the nuclear industry allow residents living nearby to visit their installations, EDF ranks 3 as the company most visited with 400.000 people a year. Following the nuclear example the French chemical industry progressively moves toward more transparency. (A.C.)

  5. Crisis in the French nuclear industry

    International Nuclear Information System (INIS)

    Nectoux, F.

    1991-02-01

    This report discusses the economics of the French nuclear power industry. It considers the dominant position of nuclear power in the French energy system, stresses the scale and causes of the current (1990) economic crisis and dispels the popular misconceptions on the cost efficiency of the French programme. The evidence is based on widely available French documents and articles. The report begins by looking at the background of nuclear power in France then discusses the problem of overcapacity, the technical problems and fall in load factors, generating costs and electricity prices and finally, strategic issues are considered. (UK)

  6. The French civilian nuclear: connections and stakes

    International Nuclear Information System (INIS)

    2010-01-01

    This document (18 power point slides) gives an overview of the French civilian nuclear industry and research and development: importance of the nuclear power generation in France, excellence of the education in nuclear sciences, organization of the nuclear connection (CEA, Areva, EDF, IRSN), the role of the French International Nuclear Agency (AFNI), the requirements for a renewal of human resources (French and foreign engineers) in the field of nuclear energy, the degree course for a diploma, examples of engineer and university diplomas, the educational networks in various regions of France, presentation of the Institut National des Sciences et Techniques Nucleaires (Nuclear Sciences and Techniques National Institute) and its master degrees, organization of the French education system in nuclear sciences with strong relations with the research and development programs

  7. The yawning chasm of French nuclear power

    International Nuclear Information System (INIS)

    Anon.

    1988-01-01

    This is an account of a paper appeared in Energy Economist, February 1988 and contains a severe critique of the French nuclear power policy, in particular the Electricite de France, Cogema and Framatome. It is argued that the blueprint of the original nuclear power program has not been achieved in many topics. Points of critique to the EdF are: the electricity price, overcapacities and financial indeptedness. The French industries are not flourishing due to ample supply of cheap energy, nor do French nuclear manufacturers sell the fast breeder technology throughout the world. (qui)

  8. The cost of French military nuclear programs

    International Nuclear Information System (INIS)

    Barrillot, B.

    1999-02-01

    The author tries to find out the real cost of French nuclear weaponry. According to this study the total cost of the French military nuclear programs for 1960-1998 period is about 1499 milliard francs (MdF). This cost can be distributed as follows: i) fabrication of the bomb: 690 MdF; ii) display of the bomb: 727 MdF; iii) control of the bomb: 50 Mdf; iv) protection against nuclear attacks: 9 MdF; and v) dismantling of the bomb: 23 MdF. It goes without saying that these figures exceed by far those given by French authorities. (A.C.)

  9. The yawning chasm of French nuclear power

    International Nuclear Information System (INIS)

    Anon.

    1988-01-01

    The financial problems of the nuclear power industry in France are explained. Cogema, the waste reprocessing company ventured into the French financial futures market and lost money. It is trying to sue its brokers over this disaster. Framatome, the State reactor manufacturer is trying to diversify into aeronautics, electronics and foodstuffs. The electric utility EdF is sliding into debt and, with no price rise allowed, this situation will get worse. Theoretically EdF should be delivering cheap electricity from nuclear power stations. However, French electricity prices are not significantly cheaper than those of Germany and the United Kingdom. The generating capacity will increase greatly over the next few years. The availability of existing plants is also improving. In spite of efforts to export its electricity (about 10% is exported) EdF seem unable to make its extra electricity cheaper and is heavily in debt. The fast breeder programme has also not lived up to expectations due to a sodium leak at Superphenix. (U.K.)

  10. Organic tritium in freshwater ecosystems: long-term trends in the environment of French nuclear power plants

    International Nuclear Information System (INIS)

    Gontier, G.; Siclet, F.

    2011-01-01

    From 1977 to 2009, more than 600 measurements of organic tritium were performed on fish, aquatic plants and sediments upstream and downstream of the 15 French NPP located along rivers. Examination of the results shows that organic tritium activities have exponentially decreased over the last thirty years, in all components of aquatic ecosystems. Upstream of all NPP, OBT levels in sediments are higher than in plants and fish, themselves larger than HTO in surface water. The magnitude of these differences and the long-term trends depend on the river basin and can be explained by the varying nature of tritium sources. In river catchment, where atmospheric test fallout is the main source of tritium, the observed levels result from the exposure of aquatic organisms to two distinct tritium pools of different ages: atmospheric tritiated water (representing present fallout), and organic tritium from soils (formed over several decades) which supplies particulate matter to surface waters. In the Rhone and Rhine river basins, an additional source of organic tritium of very low bio-availability, probably originating from the luminescent paint industry, is responsible for the spiking of sediment organic matter up to 100 to 100 000 Bq.L -1 combustion water. The comparison of upstream and downstream NPP tritium levels shows that the influence of tritium discharges is detectable only in rivers, with low background OBT activities, i.e in basins other than the Rhone and Rhine. The observed increase in plant and fish OBT is lower than the added HTO activity in water due to discharge, which supports the absence of bioaccumulation for tritium originating from HTO and the absence of highly bio-available tritiated organic molecules in NPP discharges. (authors)

  11. French nuclear harvest: abundant energy or bitter fruit

    International Nuclear Information System (INIS)

    Bupp, I.C.

    1980-01-01

    In France, the nuclear-development program is a high-priority objective of a strong, centralized government. The administrators responsible for its success can draw on concentrated fiscal and technical resources and are free to take decisive action. A major pillar of the entire French nuclear-development effort is the expectation of significant long-term export markets on all fronts: for nuclear power plants, uranium enrichment, and fuel reprocessing

  12. Nuclear power: which industrial approach will preserve a French asset?

    International Nuclear Information System (INIS)

    Machenaud, H.

    2012-01-01

    France's strategic decision in favor of nuclear energy in the 1970's has given rise to an organization of this industry with clearly defined roles and responsibilities for all parties. This has led to the mastering of industrial production of the whole chain from mining to fuel reprocessing and to waste disposal. Nuclear safety was at any stage of the chain the priority number one. The French nuclear industry is present on the international scene and thus maintain its know-how and capacities despite the ups and downs of the nuclear market. Today 240.000 people work in France in the nuclear sector. France has followed a consistent energy policy during the last 50 years and benefits from an important and homogeneous fleet of reactors which has generated a rich feedback experience on reactor operation. The tasks that face the French nuclear industry are: -) to comply with the requirements of the Complementary Safety Assessments that have been performed on all French nuclear facilities, -) to maintain and upgrade the power plants (most of them are facing their 3. decennial overhaul), -) to prepare the nuclear systems of tomorrow, and -) to export the French know-how

  13. Ardennes nuclear power plant

    International Nuclear Information System (INIS)

    1974-12-01

    The SENA nuclear power plant continued to operate, as before, at authorized rated power, namely 905MWth during the first half year and 950MWth during the second half year. Net energy production:2028GWh; hours phased to the line: 7534H; availability factor: 84%; utilization factor: 84%; total shutdowns:19; number of scrams:10; cost per KWh: 4,35 French centimes. Overall, the plant is performing very satisfactory. Over the last three years net production has been 5900GWh, corresponding to in average utilization factor of 83%

  14. The French Nuclear Safety Authority - ASN

    International Nuclear Information System (INIS)

    2013-01-01

    The ASN (Nuclear Safety Authority) was created by the act of 13 June 2006 concerning the transparency and safety of nuclear activities. The ASN is an independent administrative body that is in charge of controlling nuclear activities in France. The ASN has a workforce of 471 people and a budget of about 76 millions euros. This article details its missions and how it is organized to cover all the French territory. (A.C.)

  15. The French nuclear power plant reactor building containment contributions of prestressing and concrete performances in reliability improvements and cost savings

    International Nuclear Information System (INIS)

    Rouelle, P.; Roy, F.

    1998-01-01

    The Electricite de France's N4 CHOOZ B nuclear power plant, two units of the world's largest PWR model (1450 Mwe each), has earned the Electric Power International's 1997 Powerplant Award. This lead NPP for EDF's N4 series has been improved notably in terms of civil works. The presentation will focus on the Reactor Building's inner containment wall which is one of the main civil structures on a technical and safety point of view. In order to take into account the necessary evolution of the concrete technical specification such as compressive strength low creep and shrinkage, the HSC/HPC has been used on the last N4 Civaux 2 NPP. As a result of the use of this type of professional concrete, the containment withstands an higher internal pressure related to severe accident and ensures higher level of leak-tightness, thus improving the overall safety of the NPP. On that occasion, a new type of prestressing has been tested locally through 55 C 15 S tendons using a new C 1500 FE Jack. These updated civil works techniques shall allow EDF to ensure a Reactor Containment lifespan for more than 50 years. The gains in terms of reliability and cost saving of these improved techniques will be developed hereafter

  16. Nuclear power plants

    International Nuclear Information System (INIS)

    1985-01-01

    Data concerning the existing nuclear power plants in the world are presented. The data was retrieved from the SIEN (Nuclear and Energetic Information System) data bank. The information are organized in table forms as follows: nuclear plants, its status and type; installed nuclear power plants by country; nuclear power plants under construction by country; planned nuclear power plants by country; cancelled nuclear power plants by country; shut-down nuclear power plants by country. (E.G.) [pt

  17. Nuclear deterrence - The French nuclear adventure - The cockerel's spurs

    International Nuclear Information System (INIS)

    Valensi, Edouard

    2013-01-01

    This book reveals the secrets of the French strike force: the formidable adventure which provided France with first ranking strategic forces, the incredible fight given by Europe and the European Commission states to prohibit France from acquiring nuclear weapons, the US ambiguous game of accompanying France in her nuclear adventure in order to better monitor her, the core of deterrence with its doctrine of use, and for the future, the measures which will make French deterrence a decisive tool for worldwide peace

  18. Progressive decommissioning of French nuclear power plants: economic and geopolitical impacts; Declassement progressif du parc nucleaire francais: impacts economiques et geopolitiques

    Energy Technology Data Exchange (ETDEWEB)

    Noel, P

    1998-09-01

    The author analyzes the french energy safety in the next twenty years. The first part is devoted to the electric production park structure in 2020, with a presentation of the electric power economy, the carbon cost introduction and the economic choices in the deregulation system. The second part discusses the economical and geopolitical impacts of a gas-nuclear substitution. (A.L.B.)

  19. Generic results and conclusions of re-evaluating the flooding protection in French and German nuclear power plants

    International Nuclear Information System (INIS)

    Mattei, J.M.; Vial, E.; Rebour, V.

    2001-01-01

    Although the event which occurred at the Blayais site on December 27, 1999 did not lead to a dangerous situation for the local population or the environment, it clearly demonstrated the possible occurrence of modes of degradation of the safety level affecting all the units at a site. As a result, a number of projects were established by the French and German operators that were designed to extract useful lessons concerning the flooding risks at the Blayais site, as well as to upgrade all sites equipped with pressurized water reactors, both in France and Germany. This report presents, on the basis of the circumstances observed at the Blayais site during the course of the flood event of December 27, 1999 (which was the subject of a presentation by IPSN at the Eurosafe 2000 Conference), an evaluation of the initiatives aimed at improving the safety of both the French and the German units from an external flooding risk perspective. The safety approaches used in both countries have not been compared. (authors)

  20. Generic results and conclusions of re-evaluating the flooding protection in French and German nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Mattei, J.M.; Vial, E.; Rebour, V. [CEA Fontenay-aux-Roses, 92 (France). Inst. de Protection et de Surete Nucleaire; Liemersdorf, H.; Tuerschmann, M. [Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) mbH, Garching (Germany)

    2001-07-01

    Although the event which occurred at the Blayais site on December 27, 1999 did not lead to a dangerous situation for the local population or the environment, it clearly demonstrated the possible occurrence of modes of degradation of the safety level affecting all the units at a site. As a result, a number of projects were established by the French and German operators that were designed to extract useful lessons concerning the flooding risks at the Blayais site, as well as to upgrade all sites equipped with pressurized water reactors, both in France and Germany. This report presents, on the basis of the circumstances observed at the Blayais site during the course of the flood event of December 27, 1999 (which was the subject of a presentation by IPSN at the Eurosafe 2000 Conference), an evaluation of the initiatives aimed at improving the safety of both the French and the German units from an external flooding risk perspective. The safety approaches used in both countries have not been compared. (authors)

  1. Elecnuc. Nuclear power plants in the world

    International Nuclear Information System (INIS)

    1998-01-01

    This small booklet summarizes in tables all the numerical data relative to the nuclear power plants worldwide. These data come from the French CEA/DSE/SEE Elecnuc database. The following aspects are reviewed: 1997 highlights; main characteristics of the reactor types in operation, under construction or on order; map of the French nuclear power plants; worldwide status of nuclear power plants at the end of 1997; nuclear power plants in operation, under construction and on order; capacity of nuclear power plants in operation; net and gross capacity of nuclear power plants on the grid and in commercial operation; forecasts; first power generation of nuclear origin per country, achieved or expected; performance indicator of PWR units in France; worldwide trend of the power generation indicator; nuclear power plants in operation, under construction, on order, planned, cancelled, shutdown, and exported; planning of steam generators replacement; MOX fuel program for plutonium recycling. (J.S.)

  2. Population distribution around French nuclear sites

    International Nuclear Information System (INIS)

    Bastien, M.C.

    1985-10-01

    With the help of two files respectively from the Institut geographique national (IGN) containing the geographic reference of all cities in France, and from the Institut national de la statistique et des etudes economiques (INSEE) containing the population figures of the 1982 census, the distribution of the population around a geographic point can be determined according to a given grid. Tables of population distribution around the 30 french nuclear sites were obtained by this method; however, at a short distance from a site, a detailed local examination/survey/investigation is necessary. Data shall have to be collected to estimate the non-french population around frontier sites [fr

  3. Cancer incidence in adults living in the vicinity of nuclear power plants in France, based on data from the French Network of Cancer Registries.

    Science.gov (United States)

    Desbiolles, Alice; Roudier, Candice; Goria, Sarah; Stempfelet, Morgane; Kairo, Cécile; Quintin, Cécile; Bidondo, Marie-Laure; Monnereau, Alain; Vacquier, Blandine

    2018-03-01

    Nuclear power plants (NPPs) release toxic emissions into the environment that may affect neighboring populations. This ecologic study was designed to investigate the possibility of an excess incidence of cancer in the vicinity of French NPPs by examining the incidence by municipality of 12 types of cancer in the population aged 15 years and older during the 1995-2011 period. Population exposure to pollution was estimated on the basis of distance from towns of residence to the NPP. Using regression models, we assessed the risk of cancer in a 20-km zone around NPPs and observed an excess incidence of bladder cancer (Relative Risk (RR), 95% Credibility Interval (95% CI)) in men and women (RR men  = 1.08; 95% CI: 1.00, 1.17 and RR women  = 1.19; 95% CI: 1.02, 1.39). Women living within the 20-km proximity areas had a significantly reduced risk of thyroid cancer (RR women  = 0.86; 95% CI: 0.77, 0.96). No excess risk of hematologic malignancies in either sex was seen. The higher than expected incidence of bladder cancer may be due to an excess incidence localized around the Flamanville NPP and the nearby La Hague nuclear waste treatment center, which is a source of chemical contaminants, many (including arsenic) of them known risk factors for bladder cancer. Differences in medical practices could explain the reduced risk of thyroid cancer. In this first study of adults living near NPPs in France, cancer incidence is significantly higher than in the references populations for one of the cancer types studied: bladder cancer. © 2017 UICC.

  4. The cyber security of French nuclear installations: stakes and opportunities

    International Nuclear Information System (INIS)

    Marquez, Thierry

    2016-01-01

    Notably due to the development of the number of connected objects, nuclear installations, their supply chain and all the actors of the chain value are exposed to cyber risks, even if a recent study noticed that successful cyber attacks involving nuclear plants are rare, but real. Thus, the threat is actual and growing, and the IAEA is already working with Interpol on this issue. The author then describes how French actors (EDF, Areva, CEA) have introduced cyber-resilience to better anticipate and identify actual threats and critical vulnerabilities in order to protect infrastructures. He comments some strengthened regulatory measures introduced for the French nuclear sector, and continuous improvements brought in the field of cyber security. He shows that handling these risks is also an opportunity to develop crisis management tools through the development of a specific know-how which also has an industrial value

  5. Elecnuc. Nuclear power plants in the world

    International Nuclear Information System (INIS)

    2003-01-01

    This 2003 version of Elecnuc contents information, data and charts on the nuclear power plants in the world and general information on the national perspectives concerning the electric power industry. The following topics are presented: 2002 highlights; characteristics of main reactor types and on order; map of the French nuclear power plants; the worldwide status of nuclear power plants on 2002/12/3; units distributed by countries; nuclear power plants connected to the Grid by reactor type groups; nuclear power plants under construction; capacity of the nuclear power plants on the grid; first electric generations supplied by a nuclear unit; electrical generation from nuclear plants by country at the end 2002; performance indicator of french PWR units; trends of the generation indicator worldwide from 1960 to 2002; 2002 cumulative Load Factor by owners; nuclear power plants connected to the grid by countries; status of license renewal applications in Usa; nuclear power plants under construction; Shutdown nuclear power plants; exported nuclear power plants by type; exported nuclear power plants by countries; nuclear power plants under construction or order; steam generator replacements; recycling of Plutonium in LWR; projects of MOX fuel use in reactors; electricity needs of Germany, Belgium, Spain, Finland, United Kingdom; electricity indicators of the five countries. (A.L.B.)

  6. French Regulatory Framework for the Recycling/Reuse of Nuclear Waste and the Dismantling of George Besse Gaseous Diffusion Plant

    Energy Technology Data Exchange (ETDEWEB)

    Themines, R., E-mail: robert.themines@areva.com [AREVA (France)

    2011-07-15

    The regulatory framework in France governing the management of materials containing low levels of radionuclides is described. The plans for the management of the materials arising from the dismantling of the Georges Besse Gaseous Diffusion Plant are described as an example of the application of the regulations. (author)

  7. The new French uranium refining plant at Narbonne

    International Nuclear Information System (INIS)

    Roux, J.

    1961-01-01

    In 1957 the Commissariat l'Energie Atomique in collaboration with two French industrial firms, the Compagnie de Saint-Gobain and the Societe Potasse et Engrais chimique, undertook the construction of a plant for the production of refined uranium on an industrial scale. This plant, which forms part of the French nuclear equipment programme and which works at a capacity of 1000 tons/year, was put into operation in July 1959. First of all the principles on which this under-taking is based are outlined. This is followed by a more detailed account of the construction, including the improvements brought to the process developed at the C.E.A. plant at le Bouchet when it was carried over to the industrial stage by the uranium branch of the Societe d'Etudes et de Travaux. (author) [fr

  8. French public opinion and nuclear energy

    International Nuclear Information System (INIS)

    Le Ngoc, B.

    2016-01-01

    Since the beginning of the year French media have dealt with a lot of negative information concerning nuclear industry: the dire financial situation of AREVA, the questioning about the state of the pressure vessel of the Flamanville EPR or the EDF and Chinese investments in the british Hinkley point project. All these issues have impacted the opinion of the French people about nuclear energy: more people are against nuclear energy but nuclear accident appears to be only the tenth source of concern after unemployment (first) and terrorism. The debate about the energetic transition that will lead to the decrease of the nuclear share in the production of electricity marks the end of a political consensus in favour of the atom. Solar energy is the favorite energy source, more than 55% of the population wish solar energy to achieve a bigger share in the 15 next years while only 32% wish the same thing for wind energy. For most people nuclear energy appears to be necessary to complement renewable energies for at least the next 15-30 years. (A.C.)

  9. Nuclear. Areva, a French fission

    International Nuclear Information System (INIS)

    Dupin, Ludovic

    2015-01-01

    This article comments the difficulties and problems faced by Areva for its activity of nuclear reactor construction, and which leaded to the transfer of this activity from Areva to EDF while Areva will keep its uranium providing and fuel enrichment activities. These difficulties and problems concern the Flamanville EPR (the construction is 5 years late, vessel defects have just been identified, cost overruns), the Finnish EPR (7 years late, a 5 billions cost overrun), the Jules Horowitz research reactor (5 years late, cost overrun), and strategic choices (notably with respect to the post-Fukushima context). The article also outlines that other activities (mining, enrichment, reactor maintenance) are still doing well, and then briefly discusses the future of Areva NP

  10. French nuclear industry exportations: companies and organisations, achievements and projects

    International Nuclear Information System (INIS)

    Faudon, V.; Pailler, S.; Miniere, D.; Pouget-Abadie, X.; Journes, F.; Ouali, F.; Brochard, D.; Choho, T.; Lagarde, D.; Anglaret, P.; Kottman, G.; Mockly, D.; Ouzounian, G.; Cordier, P.Y.; Prenez, J.C.; Arpino, J.M.; Jaouen, C.; Jolly, B.

    2013-01-01

    This document gathers a series of short articles in which the following players: French Nuclear Safety Authority (ASN), Electricity of France (EdF), French Alternative Energies and Atomic Energy Commission (CEA), AREVA, ALSTOM, the Association of French Nuclear Industry Exporters (AIFEN), the National Radioactive Waste Management Agency (ANDRA) and the French Society of Nuclear Energy (SFEN) present their competencies in their respective fields and their strategies and commercial offers for exports. 2 articles are dedicated to the achievements of the French nuclear industry in China and another details the cooperation between SFEN and its foreign counterparts. Another article briefly presents the EPR and ATMEA reactors. (A.C.)

  11. Operation results of the secondary circuits of the French PWR type power plant park

    International Nuclear Information System (INIS)

    Mercier, J.P.

    1984-01-01

    Global results of performances realized since 1981 by the French PWR 900 MW power plants (installed power, availability, casual or planned shutdowns); analysis of the behaviour (casual unavailability) comparing together the performances of the different components in the secondary circuit; behaviour of the principal materials of the secondary circuit and their weight in the unavailabilities of the whole French nuclear park [fr

  12. French nuclear power experience with public opinion

    International Nuclear Information System (INIS)

    Havlicek, R.

    1990-01-01

    Establishing information centres proved to be advantageous in France. In this way, about 300 000 people visit nuclear power plants annually. EdF staff members periodically supply information to media people. Emphasis is also laid on good contacts with Members of Parliament, physicians, clergymen, teachers and politicians. The strategy of indirect communication is recognized: the utilities should not speak for themselves, it is better for somebody else to say the thing. No debates are organized with Greenpeace, who are too militant, irrational and untrustworthy. Municipalities where nuclear power plants are sited receive tax money from the plants (as from any other industrial plant), so that if the power plant is shut down, the population often demands that a new nuclear power plant be built there. Absolute transparency, openness and immediate response are vital in contacts with the public. (M.D.). 1 fig

  13. Nuclear: the decline of the French empire

    International Nuclear Information System (INIS)

    2011-01-01

    This issue first proposes critical articles which address the stumped revival of the world nuclear energy: overview of the world nuclear industry, a critic of the IAEA and NEA predictions, discussion of the financial risk, consequences of Chernobyl. A second set of articles comments the role and position of the French nuclear industry in the world. The authors outline the strong but fragile position of this self-declared leader (overview of the activities, abroad interests, mining activities abroad, and the end of foreign fuel processing activities) and discuss the diplomatic and commercial policy. Then, several articles discuss different aspects of the nuclear program in France: a climatic and energy policy transition impeded by the nuclear, an electric system under the nuclear constraint, an industrial policy characterized by an EPR monomania and stake holder concurrence, a nuclear safety put into question again, an always heavier weight of waste management, a dismantling industrialization which is a long time coming, the bad example of proliferation, and the secrets, uncertainty and spiral of the nuclear costs

  14. The French nuclear safety authority's experience with radioactive transport inspection

    International Nuclear Information System (INIS)

    Jacob, E.; Aguilar, J.

    2004-01-01

    About 300,000 radioactive material packages are transported annually in France. Most consist of radioisotopes for medical, pharmaceutical or industrial use. On the other hand, the nuclear industry deals with the transport of fuel cycle materials (uranium, fuel assemblies, etc.) and waste from power plants, reprocessing plants and research centers. France is also a transit country for shipments such as spent fuel packages from Switzerland or Germany, which are bound for Sellafield in Great Britain. The French nuclear safety authority (DGSNR: Directorate General for Nuclear Safety and Radioprotection) has been responsible since 1997 for the safety of radioactive material transport. This paper presents DGNSR's experience with transport inspection: a feedback of key points based on 300 inspections achieved during the past five years is given

  15. Climate Change and Nuclear Power (French Edition)

    International Nuclear Information System (INIS)

    2015-08-01

    Ahead of the UN Climate Change Conference, including COP 21, to be held in Paris from 30 November to 11 December 2015, the IAEA released the French version of its scientific assessment of nuclear power’s role in meeting the climate–energy challenge: Changements Climatiques et Énergie Nucléaire. The report reiterates the fact that nuclear power is the second lowest CO2 emitter, considering emissions through entire life cycles, after hydro but ahead of wind and solar-based electricity. It also examines broader issues relevant to the climate change–nuclear energy nexus, such as costs, investments, financing, safety, waste management and non-proliferation. Recent developments in resource supply, changes in energy markets and technological developments are also presented

  16. Population around the French nuclear power plant sites: a key-parameter for crisis management and safety economics; La population autour des sites nucleaires francais: un parametre determinant pour la gestion de crise et l'analyse economique des accidents nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    PASCAL, A. [IRSN, Laboratoire d' economie de la surete, DSDP/SPIIC/LAERN, BP 17, 92262 Fontenay-aux-Roses (France)

    2012-01-15

    This paper undertakes an analysis of population around the French nuclear power plant sites, tackles the problem of evacuation planning and provides a glimpse into ongoing research at the Laboratory of Nuclear Safety Economics of the IRSN, about the cost assessment of a nuclear accident and long-term land contamination. (author)

  17. Saudi Arabia: the French nuclear sector mobilized

    International Nuclear Information System (INIS)

    Cheikh-Ali, A.

    2016-01-01

    Saudi Arabia is preparing itself to replace half fossil energies by a mix of nuclear and renewable energies. Although the nuclear program is not yet well implemented, Saudi Arabia and France have signed an agreement to develop cooperation in the nuclear sector. A joint committee was created to give a frame to assess the best practices in terms of nuclear regulations, waste management, scientific cooperation and training. Concerning nuclear regulations, waste management and scientific cooperation the French contacts of KACARE (King Abdullah City for Atomic and Renewable Energy) are respectively IRSN, ANDRA and CEA. Concerning scholar and professional training, a cooperation involving I2EN (International Institute for Nuclear Energy), EDF and AREVA on one side and the King Saud University, the Prince Mohammad University, the EFFAT University and the Dar Al Hekma College on the other side, has been set to develop training in nuclear engineering in Saudi Arabia. In parallel, AREVA and EDF have developed a program to find and qualify local subcontractors. (A.C.)

  18. Planning and developing the French nuclear programme

    International Nuclear Information System (INIS)

    Carle, R.

    1983-01-01

    Since France has been compelled to free itself from the domination of oil, it has undertaken a nuclear programme capable of providing for nearly one third of its energy needs by 1990. Some years after the first oil crisis, a good part of the battle has already been won: 22 reactor units of 900 MW each have been connected to the grid and account for 40% of the electricity produced in France, while 12 other 900 MW units, together with the first 1300 MW units, are under construction. Nuclear power has thus become an industrial reality possessed of the tools appropriate for the whole fuel cycle, which has managed to cope with costs and meet deadlines, and has developed a safe and reliable product. With these positive results despite inevitable incidents the French nuclear industry has come of age. There are, however, handicaps which remain to be overcome: high investment costs, operating constraints and continuing doubt on the part of the public. The efforts deployed in these three spheres are beginning to bear fruit. As a result, implementation of the French nuclear programme is being continued, albeit at a slower rate, for the aim is no longer to replace oil by nuclear power as soon as possible, but rather to keep up with the rise in consumption. In pursuing its nuclear efforts, France will henceforth be stressing progress in terms of quality, which can still be achieved in terms of increased reliability (incorporation of feedback), better economic return (initiation of a new series known as ''N4''), easier operation (improvement of the man-machine interface) and also more independence. The ''frenchification'' of the light-water reactor has from the beginning been seen as one of the means of achieving this independence. This also applies to mastery of the whole fuel cycle. And finally, fast breeders represent the next stage

  19. Ranking French nuclear industry on international market

    International Nuclear Information System (INIS)

    Labbe, B.

    1987-01-01

    Based on the success of its own ambitious nuclear power station program, France has been able to export its technology to many parts of the world, providing everything from individual components to complete power stations on a turnkey basis. Industrial partners who regurarly work together have set up the necessary structures to ensure the dovetailing of their activities during joint operations on the foreign market. These structures are matched to the needs of individual clients, and can be dispensed with completely in cases where a sole supplier is involved. Not one single unit under construction has been halted and no contract cancelled after the Chernobyl accident. France, like Japan and the USSR, is pressing on with its nuclear power program. China has ordered two PWR units for Daya Bay, while Britain has decided to construct its first PWR at Sizewell. Although a number of countries have deferred decisions in this field, this has been mainly on financial grounds. The French nuclear power industry has demonstrated its mastery of the technology, which can now be placed at the disposal of countries wishing to build nuclear power units, to improve their existing nuclear capacity, to develop parts of this future-oriented industry, or to supply their power stations with advanced nuclear fuel

  20. The French nuclear program: national prospects, international cooperation

    International Nuclear Information System (INIS)

    Lacoste, A.; Joint-Lambert, V.; Breard, G.; Jolly, B.; Durret, L.F.; Capus, G.; Lebastard, G.; Ouzounian, G.; Bouteille, F.; Appell, B.; Peyran, J.C.; Monnet, F.; Caoul, A.

    1998-01-01

    This issue, with a foreword by Christian Pierret, the French Secretary of State of Industry, is bilingual (French/English). It gives a thorough overview of the French nuclear industry: present situation, expected evolutions; some typical cooperations with others countries throughout the world. It contains a leaflet in which advertisers give some information about their products and services. (author)

  1. French lessons - can they help the US nuclear industry?

    International Nuclear Information System (INIS)

    Jasper, J.M.

    1987-01-01

    Many analyses of the politics and economics of nuclear energy in the United States rely on comparisons of US reactor programs with those of France, which have proven to be more successful. The kernel of the comparison is that France has a large and growing nuclear system that produces most of the country's electricity, little political resistance, electric rates that are among the lowest in Europe, and independence from the vicissitudes of the oil markets. By contrast, in the US there are widespread political resistance and unfavorable public opinion, uncertainty about future plans for nuclear energy, and a generally costly set of reactors that produce about 15% of the country's electricity. What is more, the relatively expensive American plants are often thought of to be less safe than their cheaper French counterparts. In attempting to explain the French success and the US failure, observers have been all too prone to single out as the root cause a particular political or economic factor that differs between the two countries. One of the major shortcomings of this approach is that there are a number of relevant differences, any of which could play a part in affecting the countries' nuclear programs and which may not be easily changed. Moreover, implicit in each explanation is a prescription for how to aid the ailing nuclear industry in the United States--a prescription that may well be questionable

  2. French case law and the use of nuclear energy

    International Nuclear Information System (INIS)

    Hebert, Jean

    1980-01-01

    This Article which covers the most representative examples of French case-law in the nuclear field, analyses the cases involved and the relevant court decisions. It describes the evolution of the nuclear debate in France, the progressive constitution of anti-nuclear associations and their fight against nuclear energy development in the courts in the context of the licensing procedures for nuclear installations. The author analyses French law and the legal basis for the courts' decisions. (NEA) [fr

  3. Forbidden love. A French position on the future of nuclear energy

    International Nuclear Information System (INIS)

    Jaureguy-Naudin, Maite

    2013-01-01

    The French electricity supply system is based on nuclear energy, with three quarters of total electricity production originating from nuclear power plants. The sector has grown continuously over a period of 60 years. For a long time the realms of politics and science were in consensus about the use of nuclear energy for civil purposes, but now the French nuclear dogma is increasingly being called into question as a result of the disaster in Fukushima, the German decision to phase out nuclear energy and European energy policy in general. How will France shape its future energy policy given these altered framework conditions?

  4. Determination of {sup 90}Sr, {sup 63}Ni and {sup 55}Fe activities by liquid scintillation counting in the environmental samples close to French nuclear power plants located on Loire and Garonne rivers

    Energy Technology Data Exchange (ETDEWEB)

    Rousseau, G.; Mokili, M.B.; Le Roy, C.; Deniau, I. [SUBATECH, IN2P3 (France); Gontier, G.; Boyer, C. [EDF-DPI-DIN-CIDEN (France); Hemidy, P.Y. [EDF-DPN-UNIE-GPRE-IEV (France); Chardon, P. [CNRS/IN2P3 (France)

    2014-07-01

    The protection of the aquatic and terrestrial environment from a wide range of radioactive contaminants released by nuclear industry requires continuous monitoring of radionuclides released into the environment. Specific measurement methods depending of the radionuclide are used to determinate this contribution. A lot of radionuclide can easily be measured at low level by gamma spectrometry, like {sup 137}Cs, {sup 60}Co..., but others like {sup 90}Sr, {sup 63}Ni or {sup 55}Fe require prior specific radiochemical separations. Activity of {sup 90}Sr values in environmental samples are available but only few measurements of {sup 63}Ni and {sup 55}Fe activities have been carried out in samples collected in the environment close to French nuclear power plants located on the Loire and Garonne rivers despite they represent 12% to 24% for {sup 63}Ni activity and <1% for {sup 55}Fe + other minor radionuclides of total activity of their liquid effluent discharges. {sup 90}Sr is not rejected by the liquid effluent discharges of Nuclear Power Plants and can be found in the environmental samples because of thermonuclear test and subsequently after the Chernobyl nuclear power plant accident. Considering the French Nuclear Power Plant located on Loire and Garonne rivers, the determination of {sup 90}Sr, {sup 63}Ni and {sup 55}Fe levels in the environmental samples around French nuclear power plants is carried out to detect the traces of these radionuclides originating from nuclear technology activities. The environment around five French nuclear Power Plants was investigated for 4 years between 2009 and 2014. The radionuclide activities determined by liquid scintillation counting after chemical steps were performed on a large set of various matrix samples likely to be encountered in environmental monitoring as soils, sediments, terrestrial and aquatic bio-indicators. It was found that the mean activity concentration of the most frequently detected was for the radionuclide {sup 90

  5. The partnership with other nuclear industries is important for the French industry

    International Nuclear Information System (INIS)

    Le Ngoc, B.

    2016-01-01

    After the French bid for the construction of a nuclear power plant in the United Arab Emirates (AE) failed in 2011, Assystem, a French engineering company decided to develop in the Middle-East and now has become one of the most important partners of KEPCO, the company in charge of constructing the Barakah plant in AE. In Turkey, Assystem has bought a Turkish enterprise to back the Franco-Japanese SINOP project and to initiate a partnership with Rosatom building the Akkuyu plant. Today Assystem has become an important player in nuclear industry and has been able to bring back to French nuclear industry its experience of different practices and know-how in international nuclear markets. Assystem employs 12.200 staff worldwide and realized a 908 Meuros turnover in 2015. (A.C.)

  6. the french nuclear bet: political history of the main decisions

    International Nuclear Information System (INIS)

    Taccoen, L.

    2003-01-01

    The double french nuclear bet was an ultimate political choice of an old nation which did not wanted to renounce its glamour. but the world had changed. Is it always possible to conceive a national energy policy, knowing that the french military nuclear strategy is opposed to the rules of the next International Penal Court? (A.L.B.)

  7. Creation, organizing and development of the French nuclear documentation network

    International Nuclear Information System (INIS)

    Vergnes, Gisele; Cheron, Christiane; Guilloux, Raymond

    1974-01-01

    This historical account covers the creation of the French nuclear documentation network, the preliminary research, aims, structures and first accomplishments of the Association Francaise de Documentation et d'Information Nucleaire (AFDIN) (French Association of Nuclear Documentation and Information) and its relations with the international system INIS [fr

  8. G2 - G3 inventive properties, the first french nuclear plants; Caracteristiques generales et aspects originaux des reacteurs G2 et G3

    Energy Technology Data Exchange (ETDEWEB)

    Pascal,; Horowitz,; Bussac,; Joatton,; de Meux, De Lagge; Martin, [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1958-07-01

    This paper points out the inventive properties of the frenchctors G2 and G3. These are dual purpose reactors, i.e. designed for the production of both plutonium and energy (30 electrical MW); in this respect, they can be considered as the start point of the french electrical energy produced from nuclear fuel. The following points are specially discussed in this paper: the choice of the prestressed concrete pressure vessel, the horizontal arrangement of the channels, the interest of neutron flux flattening, the advantages of the charging and discharging device working during pile operation. (author)Fren. [French] Les caracteres originaux des reacteurs fran is G2 et G3 sont decrits dans ce rapport. Ce sont des reacteurs a double fin, plutonigenes et aussi producteurs d'energie (30 MW electriques); ils constituent a ce titre le point de depart de la production fran ise d'electricite d'origine nucleaire. Sont discutes, en particulier, dans ce rapport: le choix du caisson en beton precontraint pour tenir la pression, la disposition horizontale des canaux, l'interet de l'aplatissement du flux neutronique, les avantages de l'appareil permettant le chargement et le dechargement du combustible sans arreter la pile. (auteur)

  9. Scaling back French nuclear generation poses risk to trade deficit

    International Nuclear Information System (INIS)

    Mavroleon, Beatrice

    2013-01-01

    Increasing electricity costs weigh on the performance of France's exports, and this should lead to 'prudence' regarding the rate at which France's nuclear plants are taken out of service, says a report from the council of economic analysis (CAE), an economic think tank that advises the French prime minister. Reducing the proportion of nuclear energy in the country's generation mix was part of French president Francois Hollande's agreement with the country's green parties during his election campaign and is one of the key issues being discussed in France's energy transition debate. The government has said that nuclear energy's share in the generation mix should be reduced from 75% to 50% by 2025. The only nuclear plant the government has committed to closing is France's oldest, the 1.8 GW Fessenheim plant. It is scheduled to close at the end of 2016, but the move has generated much debate. 'Nobody knows why Fessenheim should be closed. Because it is old? So what?' said a legal source close to the French energy market who asked to remain anonymous. 'It's a shame that the French energy transition debate is not dealing with fundamental questions. It's too political', said the source. Low electricity prices are a key factor in maintaining France's economic competitiveness in relation to other European countries, said the CAE report, which was published on 16 May. A 10% increase in power prices paid by industrial consumers would lead to a 1.9% average reduction in the value of France's exports, it said. The market share of France's exports fell 19% in 2005-10, one of the largest slumps in Europe, according to a report published last summer by the European Commission. The country's current account recorded a growing deficit from 2005 onwards, reaching -2.2% in 2011, with the trade balance for goods accounting for most of this deterioration, said the report. Although France's trade deficit improved in 2012, driven by aerospace sector sales and weak domestic demand, the

  10. Nuclear power plant operational data compilation system

    International Nuclear Information System (INIS)

    Silberberg, S.

    1980-01-01

    Electricite de France R and D Division has set up a nuclear power plant operational data compilation system. This data bank, created through American documents allows results about plant operation and operational material behaviour to be given. At present, French units at commercial operation are taken into account. Results obtained after five years of data bank operation are given. (author)

  11. The French A.E.C. nuclear robotic program

    International Nuclear Information System (INIS)

    Foult, T.

    1991-01-01

    The new French nuclear robotic program launched by the CEA was started at the beginning of 1988 for the duration of two years and with the total subsidy of about 130 million French franc. This program includes the following four steps: the definition of model missions dedicated to inspection and intervention in nuclear environment, the system analysis to define the systems, functions and specifications required to perform these model missions, the technological development required to achieve these systems, and the design of demonstration models with the partial integration of the above developments. The whole program including these four steps is called SYROCO (modular SYstem for RObots COoperating in radioactive environment). The repair of leak in a pipe in a reprocessing cell, the model mission in a PWR nuclear power plant, autonomous load bearing mobile robots, squirrel concept light modular carrier concept, radiation hardening, mechanic, perception of environment, communication, control and simulation and the demonstration models are described. SHERPA project, perception management, force controlled manipulator, squirrel project, light modular carrier, processes and NAB model mission simulation are particularly mentioned

  12. Elecnuc. Nuclear power plants in the world

    International Nuclear Information System (INIS)

    2005-01-01

    This 2005 edition of the Elecnuc booklet summarizes in tables all numerical data relative to the nuclear power plants worldwide. These data come from the PRIS database managed by the IAEA. The following aspects are reviewed: 2004 highlights; main characteristics of reactor types; map of the French nuclear power plants on 2005/01/01; worldwide status of nuclear power plants at the end of 2004; units distributed by countries; nuclear power plants connected to the grid by reactor-type group; nuclear power plants under construction on 2004; evolution of nuclear power plant capacities connected to the grid; first electric generations supplied by a nuclear unit; electrical generation from nuclear power plants by country at the end 2004; performance indicator of PWR units in France; trend of the generation indicator worldwide; 2004 load factor by owners; units connected to the grid by countries at 12/31/2004; status of licence renewal applications in USA; nuclear power plants under construction at 12/31/2004; shutdown reactors; exported nuclear capacity in net MWe; exported and national nuclear capacity connected to the grid; exported nuclear power plants under construction or order; exported and national nuclear capacity under construction or order; recycling of plutonium in LWR; Mox licence plant projects; Appendix - historical development; acronyms, glossary

  13. French ESPN order, codes and nuclear industry requirements

    International Nuclear Information System (INIS)

    Laugier, C.; Grandemange, J.M.; Cleurennec, M.

    2010-01-01

    Work on coding safety regulations applicable to large equipment was undertaken in France as of 1978 to accompany the construction of a French nuclear plant. The needs of manufacturers were threefold: translate the design rules from the American licensor, meet the safety objectives expressed in French regulations published at that time through coding of industrial practices (order of February 26, 1974) and stabilize the work reference system between the operator - consultant - and the manufacturer responsible for applying technical recommendations. Significant work was carried out by AFCEN (the French Association for the Design, Construction and Operating Supervision of the equipment for Electronuclear boilers), an association created for this purpose, leading to the publication of a collection of rules related to mechanical equipment for pressurised water reactors, RCC-M and RSE-M, which will be discussed later, and also in several other technical fields: particularly mechanical equipment in fast neutron reactors, RCC-MR, electricity (RCC-E), and fuel (RCC-C). (authors)

  14. Nuclear Power and Sustainable Development (French Edition)

    International Nuclear Information System (INIS)

    2008-01-01

    Any discussion of 21st century energy trends must take into account the global energy imbalance. Roughly 1.6 billion people still lack access to modern energy services, and few aspects of development - whether related to living standards, health care or industrial productivity - can take place without the requisite supply of energy. As we look to the century before us, the growth in energy demand will be substantial, and 'connecting the unconnected' will be a key to progress. Another challenge will be sustainability. How can we meet these growing energy needs without creating negative side effects that could compromise the living environment of future generations? Nuclear power is not a 'fix-all' option. It is a choice that has a place among the mix of solutions, and expectations for the expanding use of nuclear power are rising. In addition to the growth in demand, these expectations are driven by energy security concerns, nuclear power's low greenhouse gas emissions, and the sustained strong performance of nuclear plants. Each country must make its own energy choices; one size does not fit all. But for those countries interested in making nuclear power part of their sustainable development strategies, it is important that the nuclear power option be kept open and accessible [fr

  15. The French electromechanical industry in the nuclear sector

    International Nuclear Information System (INIS)

    Barrau, M. de.

    1981-02-01

    A brief paper recounting the extensive changes brought about in electromechanics further to the implementation of the large French nuclear programme and the experience that its implementation has given to this industry, in particular at ALSTHOM-ATLANTIQUE, the only French manufacturer of high power turbo-generating units rated among the big world manufacturers [fr

  16. Management of waste from french nuclear fuel cycle: what are the key issues?

    International Nuclear Information System (INIS)

    Londres, V.; Do Quang, R.; Fournier, P.

    2000-01-01

    Like any other industry, the nuclear industry generates waste. This waste arises in the different successive stages of the fuel cycle, including nuclear power plants, and its physical and chemical properties vary greatly. What is special about it is the radioactivity it contains. Management of waste generated by spent fuel conditioning in nuclear reprocessing facilities, and which cannot be stored in surface repositories, according to current French regulations (ILW and HLW), is specifically discussed in this paper. (authors)

  17. Elecnuc. Nuclear power plants in the world

    International Nuclear Information System (INIS)

    2000-01-01

    This small booklet summarizes in tables all the numerical data relative to the nuclear power plants worldwide. These data come from the French CEA/DSE/SEE Elecnuc database. The following aspects are reviewed: 1999 highlights; main characteristics of the reactor types in operation, under construction or on order; map of the French nuclear power plants; worldwide status of nuclear power plants at the end of 1999; nuclear power plants in operation, under construction and on order; capacity of nuclear power plants in operation; net and gross capacity of nuclear power plants on the grid and in commercial operation; grid connection forecasts; world electric power market; electronuclear owners and share holders in EU, capacity and load factor; first power generation of nuclear origin per country, achieved or expected; performance indicator of PWR units in France; worldwide trend of the power generation indicator; 1999 gross load factor by operator; nuclear power plants in operation, under construction, on order, planned, cancelled, shutdown, and exported; planning of steam generators replacement; MOX fuel program for plutonium recycling. (J.S.)

  18. Poisoned reign: French nuclear colonialism in the Pacific. Revised ed.

    International Nuclear Information System (INIS)

    Danielsson, Bengt; Danielsson, Marie-Therese.

    1986-01-01

    Since 1966, France has used Moruroa, a small atoll in the Pacific, as the testing site for its nuclear bombs - despite opposition from both the Polynesian people and nations throughout the world. Levels of radioactive fallout and sea contamination, and the extent of damage to Moruroa itself have remained a closely-guarded military secret. This book traces the history of French nuclear involvement in the Pacific and shows how the tests have been used to strengthen colonial rule in French Polynesia

  19. Nuclear power plants

    International Nuclear Information System (INIS)

    Margulova, T.Ch.

    1976-01-01

    The textbook focuses on the technology and the operating characteristics of nuclear power plants equiped with pressurized water or boiling water reactors, which are in operation all over the world at present. The following topics are dealt with in relation to the complete plant and to economics: distribution and consumption of electric and thermal energy, types and equipment of nuclear power plants, chemical processes and material balance, economical characteristics concerning heat and energy, regenerative preheating of feed water, degassing and condenser systems, water supply, evaporators, district heating systems, steam generating systems and turbines, coolant loops and pipes, plant siting, ventilation and decontamination systems, reactor operation and management, heat transfer including its calculation, design of reactor buildings, and nuclear power plants with gas or sodium cooled reactors. Numerous technical data of modern Soviet nuclear power plants are included. The book is of interest to graduate and post-graduate students in the field of nuclear engineering as well as to nuclear engineers

  20. Nuclear power plant outages

    International Nuclear Information System (INIS)

    1998-01-01

    The Finnish Radiation and Nuclear Safety Authority (STUK) controls nuclear power plant safety in Finland. In addition to controlling the design, construction and operation of nuclear power plants, STUK also controls refuelling and repair outages at the plants. According to section 9 of the Nuclear Energy Act (990/87), it shall be the licence-holder's obligation to ensure the safety of the use of nuclear energy. Requirements applicable to the licence-holder as regards the assurance of outage safety are presented in this guide. STUK's regulatory control activities pertaining to outages are also described

  1. Integrated Nuclear Recycle Plant

    International Nuclear Information System (INIS)

    Patodi, Anuj; Parashar, Abhishek; Samadhiya, Akshay K.; Ray, Saheli; Dey, Mitun; Singh, K.K.

    2017-01-01

    Nuclear Recycle Board (NRB), Tarapur proposes to set up an 'Integrated Nuclear Recycle Plant' at Tarapur. This will be located in the premises of BARC facilities. The project location is at coastal town of Tarapur, 130 Km north of Mumbai. Project area cover of INRP is around 80 hectares. The plant will be designed to process spent fuel received from Pressurized Heavy Water Reactors (PHWRs). This is the first large scale integrated plant of the country. INRP will process spent fuel obtained from indigenous nuclear power plants and perform left over nuclear waste disposal

  2. Exploiting nuclear plants in time

    International Nuclear Information System (INIS)

    Tran, Lionel

    2011-02-01

    This document outlines that the French fleet of 58 reactors is only 25 year old in average, and that nuclear safety is strongly regulated, and notably relies on improved indicators and on a decennial re-assessment. It outlines that nuclear energy is a response to energy challenges and that it is therefore relevant to operate the nuclear fleet beyond the initially foreseen lifetime (40 years). Due to maintenance and renewal activities, plants are supposed to be safer and more efficient. To guarantee an always safer and more efficient operation in time, five actions are highlighted: decennial controls, installation and equipment modifications, control and anticipation of installation and equipment wear, competencies and ability renewal, better knowledge of techniques and technologies

  3. Maintenance of French 900 MW PWR plants

    International Nuclear Information System (INIS)

    Anon.

    1985-01-01

    This paper presents the doctrine and the aims of maintenance of EDF in the next few years. With an average age of 3.5 years, France's 900 MW PWRs, which now total 31, have overcome their growing pains. During the next few years EDF is aiming for a sharp increase in the availability factor of these plants which make up most of its nuclear thermal capacity, a reduction in the number of emergency outages, as great a cut back as possible in the period of programmed outages and the bringing down of the doses received by staff to the lowest possible level. Eventually the idea is to extend the operating life of plants as much as possible, perhaps to 40 or 50 years [fr

  4. Nuclear safety and human factors: the French factory of expertise

    International Nuclear Information System (INIS)

    Rolina, G.

    2009-01-01

    The French regulation of the nuclear safety is based on the maintaining of a deep technical dialogue between the nuclear safety authority, the I.R.S.N. (Institute of radiation protection and nuclear safety) and the nuclear operators. This type of risk management is called 'french coking' by the Anglo-Saxons, followers of stricter regulatory approach, more readable by the civil society. This technical dialogue is not without quality, especially in the field of human and organizational factors where it allows to improve the know how situation that stays incomplete. (N.C.)

  5. Complementary safety assessments - Report by the French Nuclear Safety Authority

    International Nuclear Information System (INIS)

    2011-12-01

    As an immediate consequence of the Fukushima accident, the French Authority of Nuclear Safety (ASN) launched a campaign of on-site inspections and asked operators (mainly EDF, AREVA and CEA) to make complementary assessments of the safety of the nuclear facilities they manage. The approach defined by ASN for the complementary safety assessments (CSA) is to study the behaviour of nuclear facilities in severe accidents situations caused by an off-site natural hazard according to accident scenarios exceeding the current baseline safety requirements. This approach can be broken into 2 phases: first conformity to current design and secondly an approach to the beyond design-basis scenarios built around the principle of defence in depth. 38 inspections were performed on issues linked to the causes of the Fukushima crisis. It appears that some sites have to reinforce the robustness of the heat sink. The CSA confirmed that the processes put into place at EDF to detect non-conformities were satisfactory. The complementary safety assessments demonstrated that the current seismic margins on the EDF nuclear reactors are satisfactory. With regard to flooding, the complementary safety assessments show that the complete reassessment carried out following the flooding of the Le Blayais nuclear power plant in 1999 offers the installations a high level of protection against the risk of flooding. Concerning the loss of electrical power supplies and the loss of cooling systems, the analysis of EDF's CSA reports showed that certain heat sink and electrical power supply loss scenarios can, if nothing is done, lead to core melt in just a few hours in the most unfavourable circumstances. As for nuclear facilities that are not power or experimental reactors, some difficulties have appeared to implement the CSA approach that was initially devised for reactors. Generally speaking, ASN considers that the safety of nuclear facilities must be made more robust to improbable risks which are not

  6. French nuclear dissuasion after the cold war: continuity, ruptures, questions

    International Nuclear Information System (INIS)

    Tertrais, B.

    2000-01-01

    Nuclear dissuasion is a slow and permanent process of adjustment to the strategic environment. French dissuasion adaptation to the new international environment covers a full decade, starting in the 1989-1992 era with a re-evaluation of defense programs. It has been followed by the 1994 defense white book which opens up the European perspective and reaches its peak in 1996 with a series of major decisions: renouncement of surface-to-surface missiles, launching of the M51 program, end of nuclear tests and shift towards simulation, dismantling of fissile materials production facilities etc. This process shows up two logics: the one of continuity with the confirmation of the bases of the French nuclear doctrine, and the one of discontinuity with significant changes in the general domain of the French nuclear policy. It also opens up questions about the field of application of dissuasion and the future of the nuclear consensus. (J.S.)

  7. The role of research in nuclear regulation: A French perspective

    International Nuclear Information System (INIS)

    Livolant, M.

    1997-01-01

    Roughly speaking, the French Nuclear Protection and Safety Institute's role is similar in the French situation to the NRC administration role but with less authority role, which corresponds to another body in France. They define themselves as a technical support of the safety authorities. On the other hand, they have their own research laboratories. Among them, the most famous are the Phebus reactor and the Cabri reactor about which we have heard a lot these two days. They work on safety but also on protection of man and environment, management of accident conditions, security of transport, and safeguards. They have a relationship with utilities and with government authorities. With the utilities they have two types of technical evaluations. They make detailed technical studies of the safety reports presented to the authorities by the utility. On the research side, they participate in common research programs to resolve issues and to increase knowledge and understanding about safety related questions. With the governmental authorities, their role is to give advice on safety reports of existing or being-built installations and on more general policy questions like, for example, the safety principle to apply to the next generation of power plants. The decisions are left to the safety authorities, but they give a lot of advice and detailed studies about questions of safety

  8. Evaluation of PWR's operating experience. Significant events which influenced French nuclear power program

    International Nuclear Information System (INIS)

    Dupuis, M.C.

    1986-10-01

    This report discusses developments or changes in safety policy (whether statutory or otherwise) and in plant design and operation, which, in many cases, correlate. When considering these events, it is important to bear in mind the standardization policy characterizing the French nuclear power program, and implying central decision-making, both for the safety authorities and the operating utility [fr

  9. Plant biodiversity in French Mediterranean vineyards

    Science.gov (United States)

    Cohen, Marianne; Bilodeau, Clelia; Alexandre, Frédéric; Godron, Michel; Gresillon, Etienne

    2017-04-01

    In a context of agricultural intensification and increasing urbanization, the biodiversity of farmed plots is a key to improve the sustainability of farmed landscapes. The medium life-duration of the vineyards as well as their location in Mediterranean region are favorable to plant biodiversity. We studied 35 vineyards and if present, their edges, located in three French Mediterranean terroirs: Bandol, Pic Saint Loup and Terrasses du Larzac. We collected botanical information (floral richness et diversity, biological traits), and analyzed their relationships with different factors: social (management, heritage or professional concern), environmental (slope, exposition, geology), spatial (edges, surrounding landscape in a 500 meters radius, distance to the nearest large city). Vineyards are generally heavily disturbed by intensive practices like tilling and application of herbicides, and for this reason their floral diversity is low. This is particularly true in Bandol terroir, in accordance with the standards of the Bandol PDO wine sector. Farmed landscapes and proximity to a large town impact on functional groups, generalist species being overrepresented. If vineyards are surrounded with natural edges, it doubles the floral richness at the plot and edges scale. Species present in vineyards edges are perennial herbaceous species with Euro- Asian and Mediterranean distribution ranges characteristic of prairie and wasteland stages, increasing the functional diversity of vineyards (generalist species). Environmental factors have a lower influence: vineyards are generally located on flat lands. These results suggest that some practices should be encouraged to avoid the biological degradation of vineyards: conservation of tree-lined edges and their extensive management, reduction of chemical weeding, grass-growing using non-cosmopolitan species. These recommendations should also contribute to soil conservation.

  10. Nuclear Power Plants. Revised.

    Science.gov (United States)

    Lyerly, Ray L.; Mitchell, Walter, III

    This publication is one of a series of information booklets for the general public published by the United States Atomic Energy Commission. Among the topics discussed are: Why Use Nuclear Power?; From Atoms to Electricity; Reactor Types; Typical Plant Design Features; The Cost of Nuclear Power; Plants in the United States; Developments in Foreign…

  11. Are the French authorities beginning to prepare for nuclear accident?

    International Nuclear Information System (INIS)

    Autret, J.C.

    2008-01-01

    This article, published in issue 80 of 'l'ACROnique du nucleaire', aims to retrace the early steps in the consideration of the possibility of a nuclear accident in France, with the inclusion of 'non-institutional' participants and applying the lessons learned in Belarus in the contaminated territories around the Chernobyl nuclear power plant. After a review of the origin of the involvement of the Association pour le Controle de la Radioactivite dans l'Ouest (ACRO) in addressing post-accident issues alongside the populations living in an environment polluted by radioactivity, it discusses, from the critical viewpoint of an NGO, the context and the working method adopted for this examination. This is followed by some key elements of the programme and unresolved questions about the available body of knowledge which motivates research and about the method adopted for the work. The conclusion, moderately optimistic, highlights some advances and limits arising during this exercise in a French nuclear scene which remains characterised by a centralized mode of management. (author)

  12. Nuclear power plants in the world - 2010 edition

    International Nuclear Information System (INIS)

    2010-01-01

    This small booklet summarizes in tables all data relative to the nuclear power plants worldwide. These data come from the IAEA's PRIS and AREVA-CEA's GAIA databases. The following aspects are reviewed: 2009 highlights, Main characteristics of reactor types, Map of the French nuclear power plants on 2010/01/01, Worldwide status of nuclear power plants (12/31/2009), Units distributed by countries, Nuclear power plants connected to the Grid- by reactor type groups, Nuclear power plants under construction on 2009, Evolution of nuclear power plants capacities connected to the grid, First electric generations supplied by a nuclear unit in each country, Electrical generation from nuclear power plants by country at the end 2009, Performance indicator of french PWR units, Evolution of the generation indicators worldwide by type, Nuclear operator ranking according to their installed capacity, Units connected to the grid by countries at 12/31/2009, Status of licence renewal applications in USA, Nuclear power plants under construction at 12/31/2009, Shutdown reactors, Exported nuclear capacity in net MWe, Exported and national nuclear capacity connected to the grid, Exported nuclear power plants under construction, Exported and national nuclear capacity under construction, Nuclear power plants ordered at 12/31/2009, Long term shutdown units at 12/31/2009, COL applications in the USA, Recycling of Plutonium in reactors and experiences, Mox licence plants projects, Appendix - historical development, Meaning of the used acronyms, Glossary

  13. Elecnuc - Nuclear power plants in the world - 2009 edition

    International Nuclear Information System (INIS)

    2009-01-01

    This small booklet summarizes in tables all data relative to the nuclear power plants worldwide. These data come from the IAEA's PRIS and AREVA-CEA's GAIA databases. The following aspects are reviewed: 2008 highlights, Main characteristics of reactor types, Map of the French nuclear power plants on 2008/01/01, Worldwide status of nuclear power plants (12/31/2008), Units distributed by countries, Nuclear power plants connected to the Grid- by reactor type groups, Nuclear power plants under construction on 2008, Evolution of nuclear power plants capacities connected to the grid, First electric generations supplied by a nuclear unit in each country, Electrical generation from nuclear powe plants by country at the end 2008, Performance indicator of french PWR units, Evolution of the generation indicators worldwide by type, Nuclear operator ranking according to their installed capacity, Units connected to the grid by countries at 12/31/2008, Status of licence renewal applications in USA, Nuclear power plants under construction at 12/31/2008, Shutdown reactors, Exported nuclear capacity in net MWe, Exported and national nuclear capacity connected to the grid, Exported nuclear power plants under construction, Exported and national nuclear capacity under construction, Nuclear power plants ordered at 12/31/2008, Long term shutdown units at 12/31/2008, COL applications in the USA, Recycling of Plutonium in reactors and experiences, Mox licence plants projects, Appendix - historical development, Meaning of the used acronyms, Glossary

  14. ELECNUC Nuclear power plants in the world - 2013 edition

    International Nuclear Information System (INIS)

    2013-01-01

    This small booklet summarizes in a series of tables the figures relative to the nuclear power plants worldwide. Data come from the IAEA's PRIS database and from specific I-tese studies. The following aspects are reviewed: 2012 highlights; Main characteristics of reactor types; Map of the French nuclear power plants on 2012/01/01; Worldwide status of nuclear power plants (12/31/2012); Units distributed by countries; Nuclear power plants connected to the Grid- by reactor type groups; Nuclear power plants under construction on 2012; Evolution of nuclear power plants capacities connected to the grid; First electric generations supplied by a nuclear unit in each country; Electrical generation from nuclear power plants by country at the end 2012; Performance indicator of french PWR units; Evolution of the generation indicators worldwide by type; Nuclear operator ranking according to their installed capacity; Units connected to the grid by countries at 12/31/2012; Status of licence renewal applications in USA; Nuclear power plants under construction at 12/31/2012; Shutdown reactors; Exported nuclear capacity in net MWe; Exported and national nuclear capacity connected to the grid; Exported nuclear power plants under construction; Exported and national nuclear capacity under construction; Nuclear power plants ordered at 12/31/2012; Long term shutdown units at 12/31/2012; COL (Combined Licence) applications in the USA; Recycling of Plutonium in reactors and experiences; Mox licence plants projects; Appendix - historical development; Meaning of the used acronyms; Glossary

  15. The future of the French civil nuclear sector. Report synthesis

    International Nuclear Information System (INIS)

    2010-01-01

    Considering the evolution of the French civil nuclear industry by 2030, this study examines its different dimensions: energy policy, safety and security of uranium supplies, nuclear competitiveness, environmental and safety issues, public acceptance, consequences of non proliferation international and French policies, industrial, human and research capacities, and so on. Thus, this report presents the actors involved in the French civil nuclear sector, gives an overview of the reactor market, highlights the main aspects of the fuel cycle and of the waste management, stresses the need of a new organisation for this sector to face the domestic as well as the international challenges. It discusses the possible ways for a wider financing and a higher competitiveness. It identifies new means for an ambitious civil nuclear policy. Fifteen recommendations are proposed

  16. The french nuclear industry is looking for an american partner

    International Nuclear Information System (INIS)

    2001-01-01

    In the same time of the nuclear industry revival in USA by the President Bush, TOPCO the holding society which is going to group the main french nuclear society, is looking for an american partner. This report deals with the economic and political aspects of the situation. (A.L.B.)

  17. The French experience in nuclear energy: Reasons for success

    International Nuclear Information System (INIS)

    Plante, J.

    2000-01-01

    Nuclear energy for France represents a viable option in meeting energy demands in the near and medium terms due to few energy resources and dependency on imported oil. Basic decisions to launch the French nuclear program, successive series of PWRs installed and standardization due to technical progress are highlighted in this paper. (author)

  18. Assessment of the impacts of the french nuclear program on the environment

    International Nuclear Information System (INIS)

    Naudet, G.

    1991-01-01

    The assessment of the impacts of the French nuclear program on atmosphere pollution is based on a macroeconomic long term model MELODY particularly detailed for the energy sector. The French energy strategy, characterized by its nuclear program, is compared with an alternative coal strategy based on coal-fired power plants. The coal strategy would have entailed different economic performances, a different energy balance, and, consequently, a different quality of air. For instance, by 1990, carbon emissions would have been 60% higher with the coal strategy; actually, they are 27% lower today than their 1973 level. The French nuclear program resulted both in a carbon emission reduction similar to the Toronto Conference target, and in a significant improvement of economic performances. 4 refs.; 10 figs.; 1 tab

  19. French Nuclear Forces in the 1980s and 1990s

    Science.gov (United States)

    1983-08-01

    the mid-1990s, the new force structure will be theoretically capable of inflicting massive destruc- tion against the Soviet Union as well as...capacity which turns national territory into a sanctuary. The current French nuclear force structure is shown in table 1 below. -2- TABLE 1 FRENCH...out in favor of the M-2 in 1974 which by 1977 had itself been supplanted by the M-20. The first Sous-marin Nucleaire Lanceur d’Engins I (SNLE) or

  20. French policy in the nuclear industry and last governmental decisions

    International Nuclear Information System (INIS)

    Maillard, Dominique

    1999-01-01

    In the wake of the first oil shock, France embarked on an energy policy aimed at strengthening the long-term security of its supplies. French Government has confirmed the continuation of the nuclear power option as an essential component of French energy policy and in the interests of energy self-sufficiency and environmental concerns. The Government is also ready to work actively and seriously on diversifying France's electricity supply

  1. More child leukemia near nuclear power plants

    International Nuclear Information System (INIS)

    Anon.

    2012-01-01

    A French study shows that there are more cases of child leukemia near nuclear power plants but the statistics is low: only 14 cases detected. The same study shows that the excess is not due to the releases of gaseous effluents from the plant, there is no relationship between the excess and a particular type of plant or even a particular plant. Some experts suggest that it might be the movement and intermingling of populations in the plant area that ease the propagation of infectious agents involved in child acute leukemia. A similar result was obtained in Germany a few years ago. (A.C.)

  2. Nuclear power plant siting

    International Nuclear Information System (INIS)

    Sulkiewicz, M.; Navratil, J.

    The construction of a nuclear power plant is conditioned on territorial requirements and is accompanied by the disturbance of the environment, land occupation, population migration, the emission of radioactive wastes, thermal pollution, etc. On the other hand, a nuclear power plant makes possible the introduction of district heating and increases the economic and civilization activity of the population. Due to the construction of a nuclear power plant the set limits of negative impacts must not be exceeded. The locality should be selected such as to reduce the unfavourable effects of the plant and to fully use its benefits. The decision on the siting of the nuclear power plant is preceded by the processing of a number of surveys and a wide range of documentation to which the given criteria are strictly applied. (B.H.)

  3. Power generation by nuclear power plants

    International Nuclear Information System (INIS)

    Bacher, P.

    2004-01-01

    Nuclear power plays an important role in the world, European (33%) and French (75%) power generation. This article aims at presenting in a synthetic way the main reactor types with their respective advantages with respect to the objectives foreseen (power generation, resources valorization, waste management). It makes a fast review of 50 years of nuclear development, thanks to which the nuclear industry has become one of the safest and less environmentally harmful industry which allows to produce low cost electricity: 1 - simplified description of a nuclear power generation plant: nuclear reactor, heat transfer system, power generation system, interface with the power distribution grid; 2 - first historical developments of nuclear power; 3 - industrial development and experience feedback (1965-1995): water reactors (PWR, BWR, Candu), RBMK, fast neutron reactors, high temperature demonstration reactors, costs of industrial reactors; 4 - service life of nuclear power plants and replacement: technical, regulatory and economical lifetime, problems linked with the replacement; 5 - conclusion. (J.S.)

  4. The nuclear instrumentation system of the French 1400 MWe reactors

    International Nuclear Information System (INIS)

    Bourgerette, A.; Mauduit, J.P.

    1993-01-01

    The nuclear instrumentation systems in power reactors in France have made considerable advances thanks to technological progress. The appearance of an integrated digital protection system (SPIN) and the extension of digital techniques have considerably improved performance and operating flexibility. Working on the basis of technology developed jointly with the Nuclear Electronics and Instrumentation Department at the French Atomic Energy Commission (CEA), Framatome and Merlin Gerin have designed the new nuclear instrumentation system for 1400 MW reactors. (authors). 4 figs

  5. Forbidden love. A French position on the future of nuclear energy; Verbotene Liebe. Eine franzoesische Position zur Zukunft der Kernenergie

    Energy Technology Data Exchange (ETDEWEB)

    Jaureguy-Naudin, Maite [Institut Francais des Relations Internationales (Ifri), Paris (France). Centre Energie

    2013-03-15

    The French electricity supply system is based on nuclear energy, with three quarters of total electricity production originating from nuclear power plants. The sector has grown continuously over a period of 60 years. For a long time the realms of politics and science were in consensus about the use of nuclear energy for civil purposes, but now the French nuclear dogma is increasingly being called into question as a result of the disaster in Fukushima, the German decision to phase out nuclear energy and European energy policy in general. How will France shape its future energy policy given these altered framework conditions?.

  6. The nuclear inspections in Brazil and a french public urinal

    International Nuclear Information System (INIS)

    Silva, Othon L.P. da

    2004-01-01

    The article approaches the political aspects concerning to the nuclear energy, specifically the commercial contracts with Germany for acquisition of nuclear power plants and the entire nuclear fuel cycle, and the considerations of the IAEA

  7. Quality assurance during operation of a nuclear power plant

    International Nuclear Information System (INIS)

    Stolz, J.

    1980-01-01

    The lecture provides a description of the QA manual as operated in French nuclear power plants. Oral comments will include discussion of some difficulties in actual implementation. Also examples will be given of incidents in nuclear plants, which could have been mitigated or fully prevented by QA attitude. (orig./RW)

  8. Nuclear power plant equipment design and construction rules

    International Nuclear Information System (INIS)

    Boiron, P.

    1983-03-01

    Presentation of the AFCEN (French association for nuclear power plant equipment design and construction rules) working, of its edition activity and of somes of its edited documents such as RCC-C (design and construction rules for PWR power plant fuel assemblies) and RCC-E (design and construction rules for nuclear facility electrical equipments) [fr

  9. Nuclear power plant construction

    International Nuclear Information System (INIS)

    Lima Moreira, Y.M. de.

    1979-01-01

    The legal aspects of nuclear power plant construction in Brazil, derived from governamental political guidelines, are presented. Their evolution, as a consequence of tecnology development is related. (A.L.S.L.) [pt

  10. 22. French language symposium on nuclear medicine

    International Nuclear Information System (INIS)

    1981-01-01

    The 80 papers presented in summary form at the Congress are given. These papers cover three main topics: broncho-pulmonary investigation with radioaerosols; role of nuclear medicine in pharmacokinetics; role of Nuclear Medicine in metabolic investigations [fr

  11. The struggle of the veterans of the French nuclear tests

    International Nuclear Information System (INIS)

    2005-01-01

    The question debated in this article concerns the demand of compensation and recognition of the impact on their health of nuclear tests. The military personnel that worked during nuclear tests in French Polynesia and the Sahara sites, but also the inhabitants of the atolls of Moruroa and Fangataufa equally in French Polynesia. An observatory of the veterans health has been created in order to improve the medical management of military personnel and former military personnel. An association 'Moruroa e tatou' contains the Polynesian former workers of the Nuclear tests of the Pacific and the association A.V.E.N. contains the veterans of nuclear tests. numerous examples are detailed. The question is tackled too for the consequences on health of the British nuclear tests, in Australia, Christmas Islands, and New Zealand. (N.C.)

  12. 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

  13. Maintenance of nuclear power plants

    International Nuclear Information System (INIS)

    Migaud, D.; Hutin, J.P.; Jouette, I.; Eymond, P.; Devie, P.; Cudelou, C.; Magnier, S.; Frydman, M.

    2016-01-01

    This document gathers different articles concerning the maintenance of the French nuclear power plants. The first article analyses the impact of the recent law on the energetic transition that sets the share of nuclear power at 50% of the electricity produced by 2025. A consequence may be the decommissioning of 17 to 20 reactors by 2025 and the huge maintenance program called 'Grand Carenage' whose aim is to extend operating life over 40 years will have to be re-considered in order to avoid useless expenses. The second article shows that in 2015 the French nuclear reactor fleet got very good results in terms of availability and safety. There were 49 scheduled outages and among them some ended ahead of time. The third article describes the specificities of the maintenance of a nuclear power plant, for instance the redundancy of some systems implies that maintenance has to deal with systems that have never functioned but must be ready to operate at any moment. Another specificity is the complexity of a nuclear power plant that implies an essential phase of preparation for maintenance operations. Because of safety requirements any maintenance operation has to be controlled, checked and may provide feedback. The fourth article presents the 'Grand Carenage' maintenance program that involves the following operations: the replacement of steam generators, the re-tubing of condensers, the replacement of the filtering drums used for cooling water, the testing of the reactor building, the hydraulic test of the primary circuit and the inspection of the reactor vessel. The fifth article focuses on the organization of the work-site for maintenance operations and the example of the Belleville-sur-Loire is described in the sixth article. Important maintenance operations like 'Grand Carenage' requires a strong collaboration with a network of specialized enterprises and as no reactor (except Flamanville EPR) is being built in France, maintenance

  14. Nuclear Power Plant Technician

    Science.gov (United States)

    Randall, George A.

    1975-01-01

    The author recognizes a body of basic knowledge in nuclear power plant technoogy that can be taught in school programs, and lists the various courses, aiming to fill the anticipated need for nuclear-trained manpower--persons holding an associate degree in engineering technology. (Author/BP)

  15. NUCLEAR POWER PLANT

    Science.gov (United States)

    Carter, J.C.; Armstrong, R.H.; Janicke, M.J.

    1963-05-14

    A nuclear power plant for use in an airless environment or other environment in which cooling is difficult is described. The power plant includes a boiling mercury reactor, a mercury--vapor turbine in direct cycle therewith, and a radiator for condensing mercury vapor. (AEC)

  16. Review of the French environmental nuclear toxicology programme

    International Nuclear Information System (INIS)

    Leguay, J.J.; Menager, M.T.; Ansoborlo, E.

    2005-01-01

    Full text of publication follows: The fate of radionuclides in the geosphere and in particular their transfer in the biosphere constitutes an essential key point in relation with environmental issues as well as their effects on living organisms. In order to answer to such issues, an Environmental Nuclear Toxicology Programme (a French national programme) has been launched in 2001 for a period of 5 years. It is a resolutely forward-looking programme gathering all the main research institutes (CEA, CNRS, Inserm and Inra) and comprising 15 projects that pool the expertise of physicians, biologists, chemists, physicists... The programme's central thrust is the study of the biological effects of nuclear toxics, i.e., most part of the compounds encountered in the nuclear industry ( 3 H, Co, Cd, Se, Sr, Tc, I, Cs, Pb U, Pu) that may have a chemical and (or) radiological toxicity towards living organisms. Its objectives are to study the toxicology of the materials used, in particular in nuclear fuels, to analyse the biological effects of radionuclides (naturally-occurring or artificial) that may be present in the environment, and to examine the effects of chemically toxic metals, particularly the heavy metals, used in nuclear and medical research and industrial activities. For the radionuclides, the aim is to determine the potential health consequences of exposure to these materials and to make realistic estimates of exposure to the corresponding risks incurred. The main research topics concern three types of mechanisms in bacteria, plants and animals: - Mechanisms by which elements are transferred and transported from cell to cell; - Mechanisms by which toxics accumulate in cell compartment and organs; - Specific detoxification mechanisms. In all cases, special emphasis is placed on work that makes possible to compare the toxicity of different elements relative to a better known toxic chemical, such as cadmium or cobalt, and also, for as many elements as possible, work to

  17. The French Nuclear Safety Authority (ASN)

    International Nuclear Information System (INIS)

    Alloso, Ph.

    2011-01-01

    This article presents the statutes, the organization and the missions of the Nuclear Safety Authority (ASN) whose scope includes radiation protection since 2002. Globally ASN is in charge of: -) participating to the making of laws and regulations, -) delivering administrative authorizations, -) controlling the conformity of nuclear installations and activities with the laws and regulations, -) informing the public, and -) reporting on the state of nuclear safety and radiation protection each year. (A.C.)

  18. Nuclear power plants maintenance

    International Nuclear Information System (INIS)

    Anon.

    1988-01-01

    Nuclear power plants maintenance now appears as an important factor contributing to the competitivity of nuclea energy. The articles published in this issue describe the way maintenance has been organized in France and how it led to an actual industrial activity developing and providing products and services. An information note about Georges Besse uranium enrichment plant (Eurodif) recalls that maintenance has become a main data not only for power plants but for all nuclear industry installations. (The second part of this dossier will be published in the next issue: vol. 1 January-February 1989) [fr

  19. Electricity supplies in a French nuclear power station

    International Nuclear Information System (INIS)

    2011-01-01

    As the operation of a nuclear power station requires a power supply system enabling this operation as well as the installation safety, this document describes how such systems are designed in the different French nuclear power stations to meet the requirements during a normal operation (when the station produces electricity) or when it is stopped, but also to ensure power supply to equipment ensuring safety functions during an incident or an accident occurring on the installation. More precisely, these safety functions are provided by two independent systems in the French nuclear power stations. Their operation is briefly described. Two different types of nuclear reactors are addressed: pressurised water reactors (PWR) of second generation, EPR (or PWR of third generation)

  20. KWU Nuclear Plant Analyzer

    International Nuclear Information System (INIS)

    Bennewitz, F.; Hummel, R.; Oelmann, K.

    1986-01-01

    The KWU Nuclear Plant Analyzer is a real time engineering simulator based on the KWU computer programs used in plant transient analysis and licensing. The primary goal is to promote the understanding of the technical and physical processes of a nuclear power plant at an on-site training facility. Thus the KWU Nuclear Plant Analyzer is available with comparable low costs right at the time when technical questions or training needs arise. This has been achieved by (1) application of the transient code NLOOP; (2) unrestricted operator interaction including all simulator functions; (3) using the mainframe computer Control Data Cyber 176 in the KWU computing center; (4) four color graphic displays controlled by a dedicated graphic computer, no control room equipment; and (5) coupling of computers by telecommunication via telephone

  1. Nuclear Power Plants (Rev.)

    Energy Technology Data Exchange (ETDEWEB)

    Lyerly, Ray L.; Mitchell III, Walter [Southern Nuclear Engineering, Inc.

    1973-01-01

    Projected energy requirements for the future suggest that we must employ atomic energy to generate electric power or face depletion of our fossil-fuel resources—coal, oil, and gas. In short, both conservation and economic considerations will require us to use nuclear energy to generate the electricity that supports our civilization. Until we reach the time when nuclear power plants are as common as fossil-fueled or hydroelectric plants, many people will wonder how the nuclear plants work, how much they cost, where they are located, and what kinds of reactors they use. The purpose of this booklet is to answer these questions. In doing so, it will consider only central station plants, which are those that provide electric power for established utility systems.

  2. The power of the will and the French nuclear programme

    International Nuclear Information System (INIS)

    Boureille, P.

    2010-01-01

    Using certain key episodes in the development of the French nuclear deterrent as examples, the author illustrates the extent to which boldness of decision-making, combined with far-thinking and resolute vision, is the foundation of any international defence policy built for the long term. (author)

  3. Nuclear power plant safety

    International Nuclear Information System (INIS)

    Otway, H.J.

    1974-01-01

    Action at the international level will assume greater importance as the number of nuclear power plants increases, especially in the more densely populated parts of the world. Predictions of growth made prior to October 1973 [9] indicated that, by 1980, 14% of the electricity would be supplied by nuclear plants and by the year 2000 this figure would be about 50%. This will make the topic of international co-operation and standards of even greater importance. The IAEA has long been active in providing assistance to Member States in the siting design and operation of nuclear reactors. These activities have been pursued through advisory missions, the publication of codes of practice, guide books, technical reports and in arranging meetings to promote information exchange. During the early development of nuclear power, there was no well-established body of experience which would allow formulation of internationally acceptable safety criteria, except in a few special cases. Hence, nuclear power plant safety and reliability matters often received an ad hoc approach which necessarily entailed a lack of consistency in the criteria used and in the levels of safety required. It is clear that the continuation of an ad hoc approach to safety will prove inadequate in the context of a world-wide nuclear power industry, and the international trade which this implies. As in several other fields, the establishment of internationally acceptable safety standards and appropriate guides for use by regulatory bodies, utilities, designers and constructors, is becoming a necessity. The IAEA is presently planning the development of a comprehensive set of basic requirements for nuclear power plant safety, and the associated reliability requirements, which would be internationally acceptable, and could serve as a standard frame of reference for nuclear plant safety and reliability analyses

  4. The French nuclear team ready to conquer new market shares

    International Nuclear Information System (INIS)

    Levy, J.B.; Varin, P.; Verwaerde, D.

    2016-01-01

    In order to reinforce their partnership, EDF, CEA and AREVA have founded the France Nuclear Platform (FNP). FNP is a tripartite body that will allow EDF, CEA and AREVA to build a consistent common position to respond to the worldwide demand in terms of nuclear reactors, fuel cycle or spent fuel processing. Potential clients and particularly first-time buyers want to buy far more than nuclear reactors, they want to buy the whole experience of the most important nuclear operator in the world which is a guarantee of success, safety and security. In order to stay ahead of the competition, the French nuclear industry can rely on high quality standards, a policy of innovation and a well-developed safety culture. Today's promising markets for nuclear energy are concentrated in Asia: in China a growth rate of 60% over the next 15 years is expected for nuclear power, in India projects for the construction of several EPR are ongoing. (A.C.)

  5. Nuclear power fleet replacement: an opportunity for the French energy mix? - 5044

    International Nuclear Information System (INIS)

    Cany, C.; Mansilla, C.; Mathonniere, G.; Duquesnoy, T.; Baschwitz, A.; Da Costa, P.

    2015-01-01

    In France, 27% of the electricity is to be produced by renewable resources by 2020. This share is intended to grow up to 2050. The recent European agreement and the French 'energy transition law' will promote such a development. The French power system is characterized by high nuclear penetration and nuclear power is meant to remain a significant contributor in the medium and long term, as a low-carbon power source. More than half the French nuclear power fleet was installed in the late seventies / early eighties. Thus, the issue of its replacement is at the core of the French power mix issue. The objective of this paper is to provide some insights about the opportunity it enables for the energy mix. Two plausible replacement scenarios are developed and analyzed as regards to the energy cost provided by nuclear power. For a given target level of nuclear installed capacities, the penetration of non-dispatchable renewable energies with dispatch priority will increase the need for nuclear power modulation at reduced average load factor. The impact of modulation on the nuclear levelized cost of electricity is assessed, according to the considered replacement scenario and for different renewable and nuclear energy penetration scenarios. Results show that, according to the selected assumptions, implementing a progressive shut-down (based on an increased operation lifetime of Nuclear Power Plants) appears a relevant choice since it both provides a lowest power production cost even at reduced average load factor to participate to load following and allows the possibility of 'waiting' for choosing most sustainable technologies. (authors)

  6. Nuclear plant life extension

    International Nuclear Information System (INIS)

    Negin, C.A.

    1989-01-01

    The nuclear power industry's addressing of life extension is a natural trend in the maturation of this technology after 20 years of commercial operation. With increasing emphasis on how plants are operated, and less on how to build them, attention is turning on to maximizing the use of these substantial investments. The first studies of life extension were conducted in the period from 1978 and 1982. These were motivated by the initiation, by the Nuclear Regulatory Commission (NRC), of studies to support decommissioning rulemaking. The basic conclusions of those early studies that life extension is feasible and worth pursuing have not been changed by the much more extensive investigations that have since been conducted. From an engineering perspective, life extension for nuclear plants is fundamentally the same as for fossil plants

  7. French administrative practice and design codes for nuclear vessels

    International Nuclear Information System (INIS)

    Roche, R.L.

    1987-07-01

    French regulations on boilers and pressure vessels have prevailed for a very long time, the first measure having been promulgated on 29 October 1823. Restraining the attention to nuclear pressure vessels it must be pointed out regulations and enforcement by public authorities are more stringent than they are for conventional pressure vessels. The first part of this paper will be devoted to regulations with a special attention to the decree of 26 February 1974 and to the practice of public authorities in this field with special attention given to the Bureau de Controle de la Construction Nucleaire (BCCN = Bureau of Inspection of Nuclear Design and Manufacturing). The second part of this paper will deal with the French construction codes for nuclear components RCC-M (water reactors) and RCC-MR (elevated temperature design)

  8. The perception of nuclear risks on French sites: social actors and rumors

    International Nuclear Information System (INIS)

    Timbal-Duclaux, L.

    1983-01-01

    This study summarizes the main French researchs on people living close to nuclear plants and their perception of nuclear risks. The ethnological approach was utilized, consisting in an observer living long periods of time on the site. It shows the existence of a ''psychogeographical'' zone in which people fell concerned by the building of the plant. This event reinforce the existing tensions between the social actors in the field of the site. The plant is seen as a ''big work'' ''eating'' land from agriculture and recreation, mixed with a nuclear thing mysterious and dangerous. Perceptions and rumors are greatly varying depending time and space. These results may be applied to a better siting of the plants [fr

  9. Benchmarking Nuclear Power Plants

    International Nuclear Information System (INIS)

    Jakic, I.

    2016-01-01

    One of the main tasks an owner have is to keep its business competitive on the market while delivering its product. Being owner of nuclear power plant bear the same (or even more complex and stern) responsibility due to safety risks and costs. In the past, nuclear power plant managements could (partly) ignore profit or it was simply expected and to some degree assured through the various regulatory processes governing electricity rate design. It is obvious now that, with the deregulation, utility privatization and competitive electricity market, key measure of success used at nuclear power plants must include traditional metrics of successful business (return on investment, earnings and revenue generation) as well as those of plant performance, safety and reliability. In order to analyze business performance of (specific) nuclear power plant, benchmarking, as one of the well-established concept and usual method was used. Domain was conservatively designed, with well-adjusted framework, but results have still limited application due to many differences, gaps and uncertainties. (author).

  10. Nuclear power plant decommissioning

    International Nuclear Information System (INIS)

    Yaziz Yunus

    1986-01-01

    A number of issues have to be taken into account before the introduction of any nuclear power plant in any country. These issues include reactor safety (site and operational), waste disposal and, lastly, the decommissioning of the reactor inself. Because of the radioactive nature of the components, nuclear power plants require a different approach to decommission compared to other plants. Until recently, issues on reactor safety and waste disposal were the main topics discussed. As for reactor decommissioning, the debates have been academic until now. Although reactors have operated for 25 years, decommissioning of retired reactors has simply not been fully planned. But the Shippingport Atomic Power Plant in Pennysylvania, the first large scale power reactor to be retired, is now being decommissioned. The work has rekindled the debate in the light of reality. Outside the United States, decommissioning is also being confronted on a new plane. (author)

  11. Legal aspects of French nuclear policy

    Energy Technology Data Exchange (ETDEWEB)

    1975-06-01

    By proceeding with underground nuclear tests, France does not intend to abandon its legal position concerning the right to possess nuclear weapons. The author - a specialist on international law in these matters - discusses this position and clarifies its nuances. He goes on to deal with the problem of jus cogens, the restrictive law which certain circles would like to draw from the resolutions of the General Assembly of the United Nations and from common law. France rejects this process as one which opens new possibilities for arguing against its tests, albeit underground.

  12. Legal aspects of french nuclear policy

    International Nuclear Information System (INIS)

    Anon.

    1975-01-01

    By proceeding with underground nuclear tests, France does not intend to abandon its legal position concerning the right to possess nuclear weapons. The author - a specialist on international law in these matters - discusses this position and clarifies its nuances. He goes on to deal with the problem of jus cogens, the restrictive law which certain circles would like to draw from the resolutions of the General Assembly of the United Nations and from common law. France rejects this process as one which opens new possibilities for argueing against its tests, albeit underground [fr

  13. Integrated project management information systems: the French nuclear industry experience

    International Nuclear Information System (INIS)

    Jacquin, J.-C.; Caupin, G.-M.

    1990-01-01

    The article discusses the desirability of integrated project management systems within the French nuclear power industry. Change in demand for nuclear generation facilities over the last two decades has necessitated a change of policy concerning organization, cost and planning within the industry. Large corporate systems can benefit from integrating equipment and bulk materials tracking. Project management for the nuclear industry will, in future, need to incorporate computer aided design tools and project management information systems data bases as well as equipment and planning data. (UK)

  14. Integrated project management information systems: the French nuclear industry experience

    Energy Technology Data Exchange (ETDEWEB)

    Jacquin, J.-C.; Caupin, G.-M.

    1990-03-01

    The article discusses the desirability of integrated project management systems within the French nuclear power industry. Change in demand for nuclear generation facilities over the last two decades has necessitated a change of policy concerning organization, cost and planning within the industry. Large corporate systems can benefit from integrating equipment and bulk materials tracking. Project management for the nuclear industry will, in future, need to incorporate computer aided design tools and project management information systems data bases as well as equipment and planning data. (UK).

  15. What do French people really think of nuclear power?

    International Nuclear Information System (INIS)

    Anon.

    2003-01-01

    According to an opinion poll performed in end 2003: 70% of the French people think that we can not do without nuclear power for the generation of electricity, 28% are for nuclear power, 17% are against and 55% hesitate, 69% agree with a mix between nuclear energy and renewable energies, 20% are missing the lack of information concerning the latest advances in nuclear energy field (safety, management of radioactive wastes). According to another opinion poll performed by Credoc: 44% of the people surveyed think that the production and disposal of radioactive wastes is the main drawback of nuclear power, as for the issue concerning the activity domain where the risk of major accident is the highest: 29% think of nuclear power, 27% think of road transport and 27% think of chemistry industry. (A.C.)

  16. French studies on the thermal effluents of electric power plants

    International Nuclear Information System (INIS)

    Dezes-Cadiere, H.

    1976-01-01

    This report presents a synthesis of studies made in France in the thermal effluent field: thermal power plant cooling systems, transfer and dispersion of thermal effluents in the receptive media, effects of thermal effluents on water physicochemistry and biochemistry, effects of thermal effluents on aquatic ecosystems, and, possibilities of waste heat recovery with the view of utilization in agriculture, aquaculture and district heating. A catalogue of French organizations working or having data on thermal effluents is presented, as also an alphabetical list of the contacted persons. A bibliography of French documents concerning the previously mentioned studies is finally given (193 refs.) [fr

  17. French views on the nuclear fuel cycle

    International Nuclear Information System (INIS)

    Chavardes, D.

    1986-01-01

    Fuel cycle activities are viewed in France as a very important and indissociable part of our nuclear program. Supply of material and services are firmly assured for domestic needs and overcapacities provide opportunities for industry to compete on the international market. A permanent and consistent R and D effort is continuously undertaken, aiming to apply new advanced technologies improving safety, economy and reliability of fuel cycle installations

  18. Nuclear power plant analyzer

    International Nuclear Information System (INIS)

    Stritar, A.

    1986-01-01

    The development of Nuclear Power Plant Analyzers in USA is described. There are two different types of Analyzers under development in USA, the forst in Idaho and Los Alamos national Lab, the second in brookhaven National lab. That one is described in detail. The computer hardware and the mathematical models of the reactor vessel thermalhydraulics are described. (author)

  19. Nuclear plant scram reduction

    International Nuclear Information System (INIS)

    Wiegle, H.R.

    1986-01-01

    The Nuclear Utility Management and Human Resources Committee (NUMARC) is a confederation of all 55 utilities with nuclear plants either in operation or under construction. NUMARC was formed in April 1984 by senior nuclear executives with hundreds of man-years of plant experience to improve (plant) performance and resolve NRC concerns. NUMARC has adopted 10 commitments in the areas of management, training, staffing and performance. One of these commitments is to strive to reduce automatic trips to 3 per year per unit for calendar year 1985 for plants in commercial operation greater than 3 years (with greater than 25% capacity factor). This goal applies to any unplanned automatic protection system trips at any time when the reactor is critical. Each utility has committed to develop methods to thoroughly evaluate all unplanned automatic trips to identify the root causes and formulate plans to correct the root causes thus reducing future unplanned scrams. As part of this program, the Institute of Nuclear Power Operations (INPO) collects and evaluates information on automatic reactor trips. It publishes the results of these evaluations to aid the industry to identify root causes and corrective actions

  20. Nuclear plant license renewal

    International Nuclear Information System (INIS)

    Gazda, P.A.; Bhatt, P.C.

    1991-01-01

    During the next 10 years, nuclear plant license renewal is expected to become a significant issue. Recent Electric Power Research Institute (EPRI) studies have shown license renewal to be technically and economically feasible. Filing an application for license renewal with the Nuclear Regulatory Commission (NRC) entails verifying that the systems, structures, and components essential for safety will continue to perform their safety functions throughout the license renewal period. This paper discusses the current proposed requirements for this verification and the current industry knowledge regarding age-related degradation of structures. Elements of a license renewal program incorporating NRC requirements and industry knowledge including a schedule are presented. Degradation mechanisms for structural components, their significance to nuclear plant structures, and industry-suggested age-related degradation management options are also reviewed

  1. PWR heavy equipments manufacture for nuclear power plants

    International Nuclear Information System (INIS)

    Boury, C.; Terrien, J.F.

    1983-10-01

    The manufacture of boilers has been imported by the French nuclear program to the societe FRAMATOME. FRAMATOME, because of the size of this market, has constructed two special plants for manufacturing of nuclear components (vapor generators, reactor tanks, pressurizers); these two high technical facilities are presented: production, staff training, technical overseas assistance, and technical and economical repercussions on the industrial vicinity [fr

  2. Labour inspection in nuclear power plant

    International Nuclear Information System (INIS)

    Vallet, J.; Polge, Ch.

    2009-01-01

    The French nuclear safety authority is in charge of labour inspection in nuclear power plants due to historical reasons. Thus, fifteen agents of ASN are acting simultaneously as nuclear inspectors and labour inspectors: they fulfill in the fifty eight reactor operated by EDF. ASN labour inspectors have the same rights ant duties than labour inspectors who fulfill in other French administrations. The regulatory domain is exactly the same. The work of ASN labour inspectors is divided in two main parts checking, on the one hand health and safety regulation requirements and on the other hand, social laws requirements. ASN labour inspectors assume, on their own, most of the decision they have to bring out. Nevertheless, ASN labour inspectors meet each other four times a year in order to share experiences. ASN labour inspectors and nuclear safety inspectors work together in the nuclear power plant. Its the principal benefit of this organisation. A high nu-clear safety level can not be reach without a good work conditions and social dialogue with labour unions. (author)

  3. New French guide for the protection of nuclear facilities against external flooding

    International Nuclear Information System (INIS)

    Duluc, Claire-Marie; Bardet, Lise; Guimier, Laurent; Rebour, Vincent

    2014-01-01

    On 27 December 1999, more than ten years before the tsunami of 11 March 2011, a severe storm occurred in the vicinity of the 'Le Blayais' Nuclear Power Plant (NPP) located in the Gironde estuary. This partial flooding called into question the design bases defined in the French Basic Safety Rule (BSR) I.2.e for the protection of French NPPs against external flooding. Following an initial improvement of protections of nuclear installations against external flooding, the French Nuclear Safety Authority (ASN) and the Institute for Radioprotection and Nuclear Safety (IRSN) initiated the elaboration a new safety rule for the protection of nuclear facilities against external flooding. In order to prepare the technical basis of the new safety rule, IRSN conducted a hydrologic working group. This technical group gathered experts from universities or research organisms, government departments or agencies and operators. After a long process, the guide for protection of basic nuclear installations against external flooding was published by the French Nuclear Safety Authority in April, 2013. The purpose of this guide is to i) define the situations to consider when evaluating the flood hazard for a given site ii) propose an acceptable method of quantifying them, iii) list recommendations for defining means of protection adapted to the specificities of the hazard of flooding. A specificity of external flooding is that many different sources have to be considered. Consequently, a list of 11 'Reference Flood Situation' (RFS) is defined. Each of them is based on a single event or on a conjunction of events whose characteristics may be increased if necessary. The RFS are defined with a probability target of 10-4 per year, taking into account uncertainties. This article presents the guide process of development, the method applied to define the reference flood situations (RFS) and the treatment of uncertainties. The last part of the article presents the RFS defined for local rainfall

  4. US-French nuclear cooperation: its past, present and future

    International Nuclear Information System (INIS)

    Lewis, Jeffrey; Tertrais, Bruno

    2015-10-01

    It is now a matter of public record that France and the United States conducted in-depth cooperation on ballistic missiles and, later, on nuclear weapons safety and security starting with the Nixon and Pompidou Administrations. The existence of a deep France-US strategic nuclear cooperation exists as a historical counter-narrative to the notion of France as a fully independent nuclear power, but also as a reluctant US strategic partner. Today, both countries conceive of their interests globally, and share similar outlooks regarding strategic challenges from countries such as Russia, China, Pakistan, Iran and North Korea. The United States and France have worked particularly closely in the P5+1 context to reach a diplomatic solution to Iran's growing nuclear capabilities. As permanent members of the United Nations Security Council, they are key partners on crisis management, regarding Libya, Syria, or Ukraine. Cooperation on counter-terrorism has been stepped up since the events of January 2015 in France. The two countries cooperate closely in Sahel and in Iraq. This short briefing provides new information on past nuclear cooperation and seeks to address the following question: given the existence of deep US-UK and UK-French nuclear ties, would enhanced US-French cooperation - the 'third side of the triangle' - be useful either strategically, in terms of enhancing the stability of deterrence, or financially? (authors)

  5. Nuclear plant safety

    International Nuclear Information System (INIS)

    Anon.

    1980-01-01

    The four-member New York Power Pool Panel concluded that, for a number of reasons, no nuclear power plant in New York State is prone to the type of accident that occurred at Three Mile Island (TMI). The Panel further concluded that changes in operating practices, both regulatory and voluntary, and heightened sensitivity to reactor-core-cooling requirements will substantially reduce the chances for another such accident anywhere. Panel members found that New York State utilities have taken a responsible attitude with regard to requirements set forth by the Nuclear Regulatory Commission (NRC) as a result of the TMI accident. In a cover letter that accompanied the report to Federal and New York state officials, New York Power Pool Executive Committee Chairman Francis E. Drake, Jr. expressed hope that the report will alleviate public fears of nuclear reactors and promote wider acceptance of nuclear energy as an economic and safe means of power production. 17 references

  6. Nuclear plants - military hostages

    International Nuclear Information System (INIS)

    Ramberg, B.

    1986-01-01

    Recent events suggest that nuclear reactors could make tempting military or terrorist targets. Despite the care with which most reactors are built, studies document their vulnerability to willful destruction through disruption of coolant mechanisms both inside and outside the containment building. In addition to reactors, such nuclear support facilities as fuel fabrication, reprocessing, and waste storage installations may be attractive military targets. A nuclear bomb which exploded in the vicinity of a reactor could increase its lethal effects by one-third. The implications of this is vulnerability for Middle East stability as well as to other volatile regions. The author suggests several avenues for controlling the dangers: international law, military and civil defense, facility siting, increasing plant safety, and the international management of nuclear energy. 21 references

  7. Decree nr 2017-1271 of 9 August 2017 bearing publication of the agreement under the form of an exchange of letters between the Government of the French Republic and the Swiss Federal Council concerning the scope and modalities of alert and/or transmission of information in case of minor event or accidental situation in the French Bugey nuclear plant or in the Swiss Beznau, Goegen, Leibstadt and Muehleberg nuclear plants (together an appendix) signed in Bern on 22 February 2017 and in Bourg-en-Bresse on 28 March 2017

    International Nuclear Information System (INIS)

    Macron, Emmanuel; Philippe, Edouard; Le Drian, Jean-Yves; Cochet, Arnaud; Buehlmann, Benno

    2017-01-01

    After the decree text which formalises the implementation of the agreement between France and Switzerland about alert and information modalities in case of minor events or accidental situations occurring in French and Swiss nuclear power plants located near the border, this document contains the agreement text which specifies these modalities, notably by specifying involved public bodies and authorities in charge of implementation of these modalities in the different concerned cases (minor event, accidental situation), and actions these bodies and authorities are supposed to undertake in terms of reciprocal information

  8. Renewal of the French fleet of nuclear reactors

    International Nuclear Information System (INIS)

    Nifenecker, Herve

    2012-01-01

    While supposing the lifetime of all present PWR reactors would be extended to sixty years, the author compares two scenarios regarding the renewal of the French fleet of nuclear reactors: the first one over 40 years and the second one over 20 years. This renewal is based on the construction of EPR reactors at different rhythms. The author compares the associated production costs and assesses the exploitation costs. A renewal scenario over 40 years seems to give better results

  9. Pulsed nuclear power plant

    International Nuclear Information System (INIS)

    David, C.V.

    1986-01-01

    This patent describes a nuclear power plant. This power plant consists of: 1.) a cavity; 2.) a detonatable nuclear device in a central region of the cavity; 3.) a working fluid inside of the cavity; 4.) a method to denote a nuclear device inside of the cavity; 5.) a mechanical projection from an interior wall of the cavity for recoiling to absorb a shock wave produced by the detonation of the nuclear device and thereby protecting the cavity from damage. A plurality of segments defines a shell within the cavity and a plurality of shock absorbers, each connecting a corresponding segment to a corresponding location on the wall of the cavity. Each of these shock absorbers regulate the recoil action of the segments; and 6.) means for permitting controlled extraction of a quantity of hot gases from the cavity produced by the vaporization of the working fluid upon detonation of the nuclear device. A method of generating power is also described. This method consists of: 1.) introducing a quantity of water in an underground cavity; 2.) heating the water in the cavity to form saturated steam; 3.) detonating a nuclear device at a central location inside the cavity; 4.) recoiling plate-like elements inside the cavity away from the central location in a mechanically regulated and controlled manner to absorb a shock wave produced by the nuclear device detonation and thereby protect the underground cavity against damage; 5.) extracting a quantity of superheated steam produced by the detonation of the nuclear device; and 6.) Converting the energy in the extracted superheated steam into electrical power

  10. Glossary of nuclear power plant ageing

    International Nuclear Information System (INIS)

    1999-01-01

    A glossary is presented of the terminology for understanding and managing the ageing of nuclear power plant systems, structures and components. This glossary has been published by NEA, in cooperation with CEC and IAEA, as a handy reference to facilitate and encourage use of common ageing terminology. The main benefits are improved reporting and interpretation of plant data on SSC degradation and failure, and improved interpretation and compliance with codes, regulations and standards related to nuclear plant ageing. The goal is to provide plant personnel with a common set of terms that have uniform, industry-wide meanings, and to facilitate discussion between experts from different countries. The glossary is in five languages: English, French, German, Spanish and Russian. In each language section terms are listed alphabetically, with sequential members which are repeated in the English section thus allowing cross-reference between al languages. (R.P.)

  11. Beloyarsk Nuclear Power Plant

    International Nuclear Information System (INIS)

    1997-01-01

    The Beloyarsk Nuclear Power Plant (BNPP) is located in Zarechny, approximately 60 km east of Ekaterinberg along the Trans-Siberian Highway. Zarechny, a small city of approximately 30,000 residents, was built to support BNPP operations. It is a closed city to unescorted visitors. Residents must show identification for entry. BNPP is one of the first and oldest commercial nuclear power plants in Russia and began operations in 1964. As for most nuclear power plants in the Russian Federation, BNPP is operated by Rosenergoatom, which is subordinated to the Ministry of Atomic Energy of the Russian Federation (Minatom). BNPP is the site of three nuclear reactors, Units 1, 2, and 3. Units 1 and 2, which have been shut-down and defueled, were graphite moderated reactors. The units were shut-down in 1981 and 1989. Unit 3, a BN-600 reactor, is a 600 MW(electric) sodium-cooled fast breeder reactor. Unit 3 went on-line in April 1980 and produces electric power which is fed into a distribution grid and thermal power which provides heat to Zarechny. The paper also discusses the SF NIKIET, the Sverdiovsk Branch of NIKIET, Moscow, which is the research and development branch of the parent NIKEIT and is primarily a design institute responsible for reactor design. Central to its operations is a 15 megawatt IVV research reactor. The paper discusses general security and fissile material control and accountability at these two facilities

  12. The French regime of civil liability for nuclear

    International Nuclear Information System (INIS)

    Leger, Marc

    2013-01-01

    As civil liability for nuclear is a matter of discussion and initiatives at the European and international levels, the author proposes an overview of the legal framework of the French regime of civil liability for nuclear which is a combination of two international treaties (Paris and Brussels conventions) and a national arrangement (a 1968 law). He presents and comments the main characteristics of this regime (geographical scope of application, concerned activities, excluded events, covered damages, principles regarding operator's liability) and the improvements brought by Paris and Brussels convention review protocols

  13. Nuclear Plant Data Bank

    International Nuclear Information System (INIS)

    Booker, C.P.; Turner, M.R.; Spore, J.W.

    1986-01-01

    The Nuclear Plant Data Bank (NPDB) is being developed at the Los Alamos National Laboratory to assist analysts in the rapid and accurate creation of input decks for reactor transient analysis. The NPDB will reduce the time and cost of the creation or modification of a typical input deck. This data bank will be an invaluable tool in the timely investigation of recent and ongoing nuclear reactor safety analysis. This paper discusses the status and plans for the NPDB development and describes its anticipated structure and capabilities

  14. Ardennes nuclear power plant. Annual report 1975

    International Nuclear Information System (INIS)

    1977-05-01

    At the beginning of the year 1975 the nominal power of the nuclear plant of the Ardennes was brought from 950 up to 1040 MWth, after a positive decision of the official safety organizations. Net energy produced: 2016 GWh, number of coupled hours: 6832 h, coefficient of availability: 75%, total number of standstills: 25. The functioning of the installations is, on the whole, very satisfying. Liquid wastes are clearly inferior to admissible maximum limits. The cost per KWh of the plant amounts to 5.57 French centimes. For the last 5 years net production has reached 9375 GWh, which means an average coefficient of availability of 76.7%

  15. Nuclear power plant

    International Nuclear Information System (INIS)

    Orlov, V.V.; Rineisky, A.A.

    1975-01-01

    The invention is aimed at designing a nuclear power plant with a heat transfer system which permits an accelerated fuel regeneration maintaining relatively high initial steam values and efficiency of the steam power circuit. In case of a plant with three circuits the secondary cooling circuit includes a steam generator with preheater, evaporator, steam superheater and intermediate steam superheater. At the heat supply side the latter is connected with its inlet to the outlet of the evaporator and with its outlet to the low-temperature side of the secondary circuit

  16. Nuclear power plant

    International Nuclear Information System (INIS)

    Aisaka, Tatsuyoshi; Kamahara, Hisato; Yanagisawa, Ko.

    1982-01-01

    Purpose: To prevent corrosion stress cracks in structural materials in a BWR type nuclear power plant by decreasing the oxygen concentration in the reactor coolants. Constitution: A hydrogen injector is connected between the condensator and a condensate clean up system of a nuclear power plant. The injector is incorporated with hydrogenated compounds formed from metal hydrides, for example, of alloys such as lanthanum-nickel alloy, iron titanium alloy, vanadium, palladium, magnesium-copper alloy, magnesium-nickel alloy and the like. Even if the pressure of hydrogen obtained from a hydrogen bomb or by way of water electrolysis is changed, the hydrogen can always be injected into a reactor coolant at a pressure equal to the equilibrium dissociation pressure for metal hydride by introducing the hydrogen into the hydrogen injector. (Seki, T.)

  17. Third generation nuclear plants

    Science.gov (United States)

    Barré, Bertrand

    2012-05-01

    After the Chernobyl accident, a new generation of Light Water Reactors has been designed and is being built. Third generation nuclear plants are equipped with dedicated systems to insure that if the worst accident were to occur, i.e. total core meltdown, no matter how low the probability of such occurrence, radioactive releases in the environment would be minimal. This article describes the EPR, representative of this "Generation III" and a few of its competitors on the world market.

  18. Nuclear power plant

    International Nuclear Information System (INIS)

    Schabert, H.P.; Laurer, E.

    1976-01-01

    The invention concerns a quick-acting valve on the main-steam pipe of a nuclear power plant. The engineering design of the valve is to be improved. To the main valve disc, a piston-operated auxiliary valve disc is to be assigned closing a section of the area of the main valve disc. This way it is avoided that the drive of the main valve disc has to carry out different movements. 15 sub-claims. (UWI) [de

  19. French nuclear doctrine: in keeping with continuity and orthodoxy

    International Nuclear Information System (INIS)

    Sitt, Bernard

    2012-09-01

    Debate surrounding French nuclear doctrine was lively last July, and the noted opponents of the French deterrent, such as General Norlain and Paul Quiles, took the opportunity provided by the election of a new French President to speak out in favour of reviving the debate in favour of nuclear disarmament on the grounds that nuclear weapons have become ineffectual since the end of the Cold War, even though this argument was dealt with in detail in the White Paper on Defence publishing during the spring of 1994. Yet the President's choices suggest an unequivocal policy direction: The President boarded SSBN le Terrible on the 4 July, something none of his predecessors has done since Valery Giscard d'Estaing in 1974. As the Elysee Palace underlined, this gesture was meant to 'reaffirm French commitment to its deterrent'. It also follows on from the positions Mr Hollande adopted in December 2011 and March 2012 during the electoral campaign. During a simultaneous visit to the Ile Longue base, the Defence Minister made it clear that the French position revolved around sufficiency, thereby reiterating the previous posture, following President Sarkozy's announcement that the aerial component would be reduced by one third and the overall warheads capped at 300. On the 13 July, at the launch of the commission tasked with drafting a new White Paper on defence and security, the President confirmed from the outset 'the preservation of the nuclear deterrence strategy', thereby defining an unambiguous conceptual framework for this important exercise of strategic reflection. In his speech to open the Conference of the Ambassadors on the 27 August, he did not fail to recall that France is a permanent member of the Security Council Nuclear-Weapon State, following on from the tradition established by his predecessors. The continuation of the French deterrent thus appears fairly certain, even if the White Paper committee will also be tasked with formulating the best course between

  20. Nuclear energy. The post-Fukushima situation, debate about the French exception, the energy transition

    International Nuclear Information System (INIS)

    Bezat, J.M.; Tazieff, H.; Morin, H.; Le Hir, P.; Vincent, C.; Labbe, M.H.; Viansson-Ponte, P.; Saint-James, D.; Tatu, M.; Pons, P.; Kempf, H.; Lemaitre, F.; Baudet, M.B.; Armagnac, B. d'; Allix, G.; Foucart, S.; Barroux, R.

    2011-01-01

    Published 8 months after the Fukushima Dai-ichi accident, this special issue of Le Monde newspaper takes stock of the nuclear question. Prior to the Fukushima accident, the civil nuclear industry experienced two other major accidents: Three Miles Island (US, 1979) with limited and controlled impacts, and Chernobyl (USSR, 1986) with enormous impacts. The recent Japanese catastrophe has revived the questions concerning this risky technology. However, according to the IAEA, the civil nuclear energy should continue to develop in the future but in a more moderate way. Germany announced in June 2011 the shutdown of its last reactor by 2022, while France remained an exception until the Fukushima accident with a large political consensus among the general public in favor of nuclear energy. The nuclear phasing out or the energy transition is a complex question which is explored in this special issue. Content: 1 - The nuclear world: a moderate growth of the nuclear industry; interview of Mohamed ElBaradei, former head of IAEA; 441 reactors in operation in the world in January 2011; France has chosen the all-nuclear option; critics: a 'costly, unadapted, useless' nuclear program; interview of Valery Giscard d'Estaing, former French President; the nuclear industry actors; nuclear dismantling: a what cost?; how to manage the 250.000 tons of spent fuels; 2 - A risky technology: radioactivity measurement and effects; how to manage contaminations; four generations of reactors; ITER: a solar project; imagining the unimaginable and anticipating the worse; the wake up of a dozed off fear; the most important accidents: the progress of the three main nuclear catastrophes, the human mistake of Three Mile Island, the days after the Chernobyl accident, in the dead cities around Fukushima; interview of Kenzaburo Oe (Japanese writer); the Blayais power plant to the test; 3 - The energy transition: is France capable to abandon nuclear energy?; Germany is going to re-launch gas- and coal

  1. The French nuclear sector. Situation and predictions 2018 - Sectoral and competitive analysis

    International Nuclear Information System (INIS)

    2017-01-01

    This document comprises two reports. A first one, published and updated three times a year, and a second one which is a yearly publication. The first one, based on an analysis of market perspectives and of actor strategies, proposes a synthesis on the consequences of the evolution of the economic environment, on major trends noticed for the nuclear sector, and on predictable evolutions. It proposes the most recent data regarding the activities of more than 100 firms belonging to the sector (notably in terms of electric power production, of turnover for firms specialised in nuclear maintenance or in the fuel cycle). It highlights recent events for companies of the sector: takeovers, investments, restructuring, introduction of new products, and so on. It proposes a sector-based dashboard which contains all the critical figures useful to analyse the sector situation (activity determining factors, key figures for the sector and its environment). The annual report proposes a general presentation of the sector (determining factors of the activity, operated nuclear plants in the world, nuclear power production in the world, uranium production and consumption in the world, maintenance and improvement expenses on nuclear plants, electric power consumption and shares in power generation by different sources in France), an analysis of the evolution of the sector activity (trends, indicators, financial performance of actors in the maintenance of nuclear plants), an overview of important issues for the profession (growth issue despite the maturity of the French market, implications of intensification of foreign competition, of higher safety requirements, and of a decrease of nuclear energy profitability), and an analysis of the sector economic structure (turnovers, personnel, position of France among world exporters, equipment export structure, key figures for nuclear maintenance). The last part proposes presentations of 20 French actors and data and information sheets for 10

  2. The N4 plant: culmination of French PWR experience

    International Nuclear Information System (INIS)

    Bellet, J.; Houyez, A.; Journet, J.; Pierrard, J.H.

    1985-01-01

    The model N4 series of 1400MWe class PWR plants has been developed in France from a unique base of technical and operating experience. It meets the French government's requirement for a reactor free of constraints due to licensing agreements with overseas companies, with enhanced safety features and incorporating the lessons of Three Mile Island. In particular, improvements have been made to the reactor vessel, the steam generators, the primary pumps and control systems. The units are capable of daily load following and extended operation between refuelling. The N4 plant includes a new design of turbine-generator. (author)

  3. On nuclear power plant uprating

    International Nuclear Information System (INIS)

    Ho, S. Allen; Bailey, James V.; Maginnis, Stephen T.

    2004-01-01

    Power uprating for commercial nuclear power plants has become increasingly attractive because of pragmatic reasons. It provides quick return on investment and competitive financial benefits, while involving low risks regarding plant safety and public objection. This paper briefly discussed nuclear plant uprating guidelines, scope for design basis analysis and engineering evaluation, and presented the Salem nuclear power plant uprating study for illustration purposes. A cost and benefit evaluation of the Salem power uprating was also included. (author)

  4. The year 2000 and the French nuclear facilities

    International Nuclear Information System (INIS)

    Henry, Jean Yves; Regnier, Pascal; Daumas, Frederic; Manners, Simeon

    1999-03-01

    This report deals with the millennium problem from the point of view of French Nuclear Activities. The paper presents the millennium problem and its causes as well as the difficulties in achieving millennium compliance. The relationship between the computer systems and the safety of nuclear installations is addressed and, in this respect, the question of determining the analysis strategy at the IPSN is discussed. The necessity to set up a specific organisational system having tasks related to analysis of installation sensitivity, study of resources, tests, and contingency measures is maintained. Particularly, an analysis of PWR of EDF and other nuclear installations is presented. Also mentioned are the IPSN initiatives in support of its assessment as well as the IPSN's international actions to cope with the millennium bug challenge

  5. Nuclear Power Plant 1996

    International Nuclear Information System (INIS)

    1997-01-01

    Again this year, our magazine presents the details of the conference on Spanish nuclear power plant operation held in February and that was devoted to 1996 operating results. The Protocol for Establishment of a New Electrical Sector Regulation that was signed last December will undoubtedly represent a new challenge for the nuclear industry. By clearing stating that current standards of quality and safety should be maintained or even increased if possible, the Protocol will force the Sector to improve its productivity, which is already high as demonstrated by the results of the last few years described during this conference and by recent sectorial economic studies. Generation of a nuclear kWh that can compete with other types of power plants is the new challenge for the Sector's professionals, who do not fear the new liberalization policies and approaching competition. Lower inflation and the resulting lower interest rates, apart from being representative indices of our economy's marked improvement, will be very helpful in facing this challenge. (Author)

  6. Siting nuclear power plants

    International Nuclear Information System (INIS)

    Yellin, J.; Joskow, P.L.

    1980-01-01

    The first edition of this journal is devoted to the policies and problems of siting nuclear power plants and the question of how far commercial reactors should be placed from urban areas. The article is divided into four major siting issues: policies, risk evaluation, accident consequences, and economic and physical constraints. One concern is how to treat currently operating reactors and those under construction that were established under less-stringent criteria if siting is to be used as a way to limit the consequences of accidents. Mehanical cost-benefit analyses are not as appropriate as the systematic use of empirical observations in assessing the values involved. Stricter siting rules are justified because (1) opposition because of safety is growing: (2) remote siting will make the industry more stable; (3) the conflict is eliminated between regulatory policies and the probability basis for nuclear insurance; and (4) joint ownership of utilities and power-pooling are increasing. 227 references, 7 tables

  7. French Senate debate on nuclear deterrence; Dissuasion nucleaire francaise

    Energy Technology Data Exchange (ETDEWEB)

    Vincon, S. [UMP Cher (France); Bentegeat, H. [Cema, 75 - Paris (France); Verwaerde, D. [CEA Bruyeres le Chatel, 91 (France); Quinlan, M. [IISS, Londre (United Kingdom); Tertrais, B. [Fondation pour la Recherche Strategique (FRS), 75 - Paris (France)

    2006-07-15

    The Senate committee on foreign affairs, defence and the Armed Forces met at a round table session on 14 June 2006 to discuss French nuclear deterrence. Serge Vincon presided the discussion, which covered three aspects of the subject: first, an analysis of the current and medium-term future strategic contexts and their consequences for the role of deterrence, and thus whether or not current doctrine is matched to current and future threats; second, the assets dedicated to deterrence, how well they reflect doctrine and how they fit in with other defence priorities; and finally an examination of Britain position within NATO along with future possibilities arising from closer European defence cooperation. (author)

  8. Nuclear safety: economic analysis of American, French and Japanese regulations

    International Nuclear Information System (INIS)

    Leveque, Francois

    2013-05-01

    While discussing and comparing the American, Japanese and French approaches and practices, and identifying the strengths and weaknesses of each of them, the author discusses why self-regulation and civil responsibility cannot guarantee a sufficient nuclear safety level, why the safety regulation authority must be independent from industry and government, whether a figure must be put to the safety objective (for example with a risk threshold), whether it is better to define detailed standards to be applied by manufacturers and operators or to define general performance criteria to be reached

  9. Nuclear power plant disasters

    International Nuclear Information System (INIS)

    Trott, K.R.

    1979-01-01

    The possibility of a nuclear power plant disaster is small but not excluded: in its event, assistance to the affected population mainly depends on local practitioners. Already existing diseases have to be diagnosed and treated; moreover, these physicians are responsible for the early detection of those individuals exposed to radiation doses high enough to induce acute illness. Here we present the pathogenesis, clinical development and possible diagnostic and therapeutical problems related to acute radiation-induced diseases. The differentiation of persons according to therapy need and prognosis is done on the sole base of the clinical evidence and the peripheral blood count. (orig.) [de

  10. Nuclear reactor plant

    International Nuclear Information System (INIS)

    Schabert, H.P.; Laurer, E.

    1977-01-01

    The invention is concerned with a quick-closing valve on the main-steam pipe of a nuclear reactor plant. The quick-closing valve serves as isolating valve and as safety valve permitting depressurization in case of an accident. For normal operation a tube-shaped gate valve is provided as valve disc, enclosing an auxiliary valve disc to be used in case of accidents and which is opened at increased pressure to provide a smaller flow cross-section. The design features are described in detail. (RW) [de

  11. Garigliano nuclear power plant

    International Nuclear Information System (INIS)

    1976-03-01

    During the period under review, the Garigliano power station produced 1,028,77 million kWh with a utilization factor of 73,41% and an availability factor of 85,64%. The disparity between the utilization and availability factors was mainly due to a shutdown of about one and half months owing to lack of staff at the plant. The reasons for nonavailability (14.36%) break down as follows: nuclear reasons 11,49%; conventional reasons 2,81%; other reasons 0,06%. During the period under review, no fuel replacements took place. The plant functioned throughout with a single reactor reticulation pump and resulting maximum available capacity of 150 MWe gross. After the month of August, the plant was operated at levels slightly below the maximum available capacity in order to lengthen the fuel cycle. The total number of outages during the period under review was 11. Since the plant was brought into commercial operation, it has produced 9.226 million kWh

  12. Nuclear and intermittent renewables: Two compatible supply options? The case of the French power mix

    International Nuclear Information System (INIS)

    Cany, Camille; Mansilla, Christine; Costa, Pascal da; Mathonnière, Gilles; Duquesnoy, Thierry; Baschwitz, Anne

    2016-01-01

    The complementary features of low-carbon power sources are a central issue in designing energy transition policies. The French current electricity mix is characterised by a high share of nuclear power which equalled 76% of the total electric production in 2015. With the increase in intermittent renewable sources, nuclear flexibility is examined as part of the solution to balance electricity supply and demand. Our proposed methodology involves designing scenarios with nuclear and intermittent renewable penetration levels, and developing residual load duration curves in each case. The load modulation impact on the nuclear production cost is estimated. This article shows to which extent the nuclear annual energy production will decrease with high shares of intermittent renewables (down to load factors of 40% for proactive assumptions). However, the production cost increase could be compensated by progressively replacing the plants. Moreover, incentives are necessary if nuclear is to compete with combined-cycle gas turbines as its alternative back-up option. In order to reconcile the social planner with plant operator goals, the solution could be to find new outlets rather than reducing nuclear load factors. Nuclear flexibility could then be considered in terms of using its power to produce heat or hydrogen. - Highlights: •Nuclear flexibility is examined to balance the system with high renewables share. •Impacts of wind and solar shares on the nuclear load factor and LCOE are assessed. •Nuclear fleet replacement must be progressive to ensure competitive load-following. •Incentives are needed for nuclear to compete with CCGT gas back-up. •We recommend considering nuclear flexibility through the power use.

  13. Nuclear power plant emergency preparedness

    International Nuclear Information System (INIS)

    2005-01-01

    The guide sets forth detailed requirements on how the licensee of a nuclear power plant shall plan, implement and maintain emergency response arrangements. The guide is also applied to nuclear material and nuclear waste transport in situations referred to in guide YVL 6.5. Requirements on physical protection are presented in a separate guide of Finnish Radiation and Nuclear Safety Authority (STUK)

  14. Affective imagery and acceptance of replacing nuclear power plants.

    Science.gov (United States)

    Keller, Carmen; Visschers, Vivianne; Siegrist, Michael

    2012-03-01

    This study examined the relationship between the content of spontaneous associations with nuclear power plants and the acceptance of using new-generation nuclear power plants to replace old ones. The study also considered gender as a variable. A representative sample of the German- and French-speaking population of Switzerland (N= 1,221) was used. Log-linear models revealed significant two-way interactions between the association content and acceptance, association content and gender, and gender and acceptance. Correspondence analysis revealed that participants who were opposed to nuclear power plants mainly associated nuclear power plants with risk, negative feelings, accidents, radioactivity, waste disposal, military use, and negative consequences for health and environment; whereas participants favoring nuclear power plants mainly associated them with energy, appearance descriptions of nuclear power plants, and necessity. Thus, individuals opposing nuclear power plants had both more concrete and more diverse associations with them than people who were in favor of nuclear power plants. In addition, participants who were undecided often mentioned similar associations to those participants who were in favor. Males more often expressed associations with energy, waste disposal, and negative health effects. Females more often made associations with appearance descriptions, negative feelings, and negative environmental effects. The results further suggest that acceptance of replacing nuclear power plants was higher in the German-speaking part of the country, where all of the Swiss nuclear power plants are physically located. Practical implications for risk communication are discussed. © 2011 Society for Risk Analysis.

  15. Digital nuclear instrumentation application to nuclear power plant

    International Nuclear Information System (INIS)

    Burel, J.-P.; Fanet, H.

    1993-01-01

    The use of digital techniques for the control of nuclear reactors offers an interesting prospect in the improvement of the operation and safety of reactors. Thanks to close collaboration between Merlin Gerin and the French Atomic Energy Commission, a new piece of technology for nuclear instrumentation systems has been developed in order to meet the needs of different types of reactors. The principles of measurement are presented and the technology used is described. Other interesting points of this technology in addition to installation, operation and safety are examined. The digital neutron measurements are already operating in research reactors in France and will be installed in a different configuration in the new 1400 MW nuclear power plant. Integration into different designs is easily attainable by adapting the information transmission mode according to the technology present in the protection system and the treatment and visualization systems. (author)

  16. Leak before break application in French PWR plants under operation

    Energy Technology Data Exchange (ETDEWEB)

    Faidy, C. [EDF SEPTEN, Villeurbanne (France)

    1997-04-01

    Practical applications of the leak-before break concept are presently limited in French Pressurized Water Reactors (PWR) compared to Fast Breeder Reactors. Neithertheless, different fracture mechanic demonstrations have been done on different primary, auxiliary and secondary PWR piping systems based on similar requirements that the American NUREG 1061 specifications. The consequences of the success in different demonstrations are still in discussion to be included in the global safety assessment of the plants, such as the consequences on in-service inspections, leak detection systems, support optimization,.... A large research and development program, realized in different co-operative agreements, completes the general approach.

  17. The consequences of underground nuclear testing in French Polynesia

    International Nuclear Information System (INIS)

    Brown, E.T.

    1998-01-01

    France began atmospheric nuclear testing at Mururoa and Fangataufa atolls in the South Pacific in July 1966. Following international protest, atmospheric testing ceased in August 1970. In late 1995, an International Geomechanical Commission (IGC) was created to assess the short- and long-term effects of underground nuclear testing on the stability and hydrology of Mururoa and Fangataufa. With the aid of its consultants, the Commission sought to develop its own understanding of the mechanics and consequences of the underground nuclear tests. It carried out extensive numerical analyses of shock wave effects, seismic wave propagation, slope stability and pre- and post-test hydrology. However, in its studies, the IGC was constrained to use the data made available to it by the French authorities. The Commission's report (International Geomechanical Commission 1998) has been submitted to the French Government. This article draws heavily on parts of that report. The Commission's observations and analyses show that there has been no apparent change, on the atoll scale, to the overall mechanical stability of either atoll as a consequence of the underground nuclear tests. The main observable consequences of the tests are underwater slope failures, open fractures on the rim surface and surface settlements. The fractures visible on the surface are generally associated with subsurface slope displacements and occur only in the carbonates. There is no evidence that slope failures or settlements have occurred in the underlying volcanics. There has been no significant change in the long-term (beyond 500 years) hydrology of either atoll. The IGC estimates that the long-term change in the natural groundwater flow will be no more than 1%. There are, however, significant short-term changes locally around the test sites, which are briefly outlined

  18. Report on the behalf of the inquiry commission related to past, present and future costs of the nuclear sector, to the reactor exploitation duration, and to various economic and financial aspects of production and commercialization of nuclear electricity within the frame of the French and European electric mix, as well as to the consequences of the shutting down and dismantling of nuclear reactors, notably the Fessenheim power plant - Nr 2007

    International Nuclear Information System (INIS)

    Brottes, Francois; Baupin, Denis

    2014-01-01

    This official report first describes the role of nuclear energy in the European electric system: economic context (pricing mode, interconnection leading to a European price), similar situations and different policies in Germany, Belgium and UK. It proposes the contribution of the inquiry commission: a constrained energy transition, a shared diagnosis on the status of the European electric system but two possible solutions, nuclear as an economy on its own requiring a strong commitment of public authorities. The next part addresses the front end of the nuclear cycle, i.e. how to ensure the supply of the French nuclear fleet (world resources, demand-supply balance, weak relationship between uranium price and nuclear electricity price). The inquiry commission outlines and discusses the roles of AREVA for the front end, EDF which tries to be less vulnerable, and the State (EDF's regulator and Areva's support). The third part addresses the maintenance and subcontracting expenses: maintenance as a major challenge to control costs, subcontracting as a choice of industrial policy. The inquiry commission notices that EDF has not yet reached a full control of maintenance and that subcontracting remains a matter of controversy. The fourth part discusses the fleet evolution: entry in the fourth decade, a life extension project which requires safety improvement. The inquiry commission discusses the numerous uncertainties of the industrial project, outlines that the construction of a new fleet requires huge investments, that the future of the nuclear fleet requires a global approach, and that shutting down nuclear plants requires support. The fifth part discusses the correct assessment of the amount of future expenses and how to secure their funding: the main future expenses are those related to installation dismantling and to nuclear wastes. The inquiry commission outlines the uncertainties about this funding. The sixth chapter addresses reprocessing activities, MOX fuel and

  19. Qualification of electric equipments for nuclear power plants

    International Nuclear Information System (INIS)

    Chauvin, G.; Raimondo, E.

    1983-03-01

    Description of the testing equipment, testing methods and standards of the resistance to seisms of electrical equipments (switches, pump motors, electrovalves, ...) for electronuclear power plants in France. Presentation of the French design and construction rules for electrical devices in the domestic and export nuclear market (resistance to thermodynamical and chemical stresses, to seisms, etc...) [fr

  20. Nuclear power plant operator licensing

    International Nuclear Information System (INIS)

    1997-01-01

    The guide applies to the nuclear power plant operator licensing procedure referred to the section 128 of the Finnish Nuclear Energy Degree. The licensing procedure applies to shift supervisors and those operators of the shift teams of nuclear power plant units who manipulate the controls of nuclear power plants systems in the main control room. The qualification requirements presented in the guide also apply to nuclear safety engineers who work in the main control room and provide support to the shift supervisors, operation engineers who are the immediate superiors of shift supervisors, heads of the operational planning units and simulator instructors. The operator licensing procedure for other nuclear facilities are decided case by case. The requirements for the basic education, work experience and the initial, refresher and complementary training of nuclear power plant operating personnel are presented in the YVL guide 1.7. (2 refs.)

  1. Images of nuclear power plants

    International Nuclear Information System (INIS)

    Hashiguchi, Katsuhisa; Misumi, Jyuji; Yamada, Akira; Sakurai, Yukihiro; Seki, Fumiyasu; Shinohara, Hirofumi; Misumi, Emiko; Kinjou, Akira; Kubo, Tomonori.

    1995-01-01

    This study was conducted to check and see, using Hayashi's quantification method III, whether or not the respondents differed in their images of a nuclear power plant, depending on their demographic variables particularly occupations. In our simple tabulation, we compared subject groups of nuclear power plant employees with general citizens, nurses and students in terms of their images of a nuclear power plant. The results were that while the nuclear power plant employees were high in their evaluations of facts about a nuclear power plant and in their positive images of a nuclear power plant, general citizens, nurses and students were overwhelmingly high in their negative images of a nuclear power plant. In our analysis on category score by means of the quantification method III, the first correlation axis was the dimension of 'safety'-'danger' and the second correlation axis was the dimension of 'subjectivity'-'objectivity', and that the first quadrant was the area of 'safety-subjectivity', the second quadrant was the area of 'danger-subjectivity', the third quadrant as the area of 'danger-objectivity', and the forth quadrant was the area of 'safety-objectivity'. In our analysis of sample score, 16 occupation groups was compared. As a result, it was found that the 16 occupation groups' images of a nuclear power plant were, in the order of favorableness, (1) section chiefs in charge, maintenance subsection chiefs, maintenance foremen, (2) field leaders from subcontractors, (3) maintenance section members, operation section members, (4) employees of those subcontractors, (5) general citizens, nurses and students. On the 'safety-danger' dimension, nuclear power plant workers on the one hand and general citizens, nurses and students on the other were clearly divided in terms of their images of a nuclear power plant. Nuclear power plant workers were concentrated in the area of 'safety' and general citizens, nurses and students in the area of 'danger'. (J.P.N.)

  2. Wuergassen nuclear power plant

    International Nuclear Information System (INIS)

    Anon.

    1989-01-01

    The decision of the Federal Court of Administration concerns an application for immediate decommissioning of a nuclear power plant (Wuergassen reactor): The repeal of the permit granted. The decision dismisses the appeal for non-admission lodged by the plaintiffs against the ruling of the Higher Court of Administration (OVG) of North-Rhine Westphalia of December 19th 1988 (File no. 21 AK 8/88). As to the matter in dispute, the Federal Court of Administration confirms the opinion of the Higher Court of Administration. As to the headnotes, reference can be made to that decision. Federal Court of Administration, decision of April 5th 1989 - 7 B 47.89. Lower instance: OVG NW, Az.: 21 AK 8/88. (orig./RST) [de

  3. Nuclear power plant

    International Nuclear Information System (INIS)

    Uruma, Hiroshi

    1998-01-01

    In the first embodiment of the present invention, elements less activated by neutrons are used as reactor core structural materials placed under high neutron irradiation. In the second embodiment of the present invention, materials less activated by neutrons when corrosive materials intrude to a reactor core are used as structural materials constituting portions where corrosion products are generated. In the third embodiment, chemical species comprising elements less activated by neutrons are used as chemical species to be added to reactor water with an aim of controlling water quality. A nuclear power plant causing less radioactivity can be provided by using structural materials comprising a group of specific elements hardly forming radioactivity by activation of neutrons or by controlling isotope ratios. (N.H.)

  4. Nuclear power plant

    International Nuclear Information System (INIS)

    Schabert, H.P.

    1976-01-01

    A nuclear power plant is described which includes a steam generator supplied via an input inlet with feedwater heated by reactor coolant to generate steam, the steam being conducted to a steam engine having a high pressure stage to which the steam is supplied, and which exhausts the steam through a reheater to a low pressure stage. The reheater is a heat exchanger requiring a supply of hot fluid. To avoid the extra load that would be placed on the steam generator by using a portion of its steam output as such heating fluid, a portion of the water in the steam generator is removed and passed through the reheater, this water having received at least adequate heating in the steam generator to make the reheater effective, but not at the time of its removal being in a boiling condition

  5. An Information Building on Radioactivity and Nuclear Energy for the French CEA Cadarache Research Center - 13492

    Energy Technology Data Exchange (ETDEWEB)

    Brunel, Guy; Denis, Dominique; Boulet, Alain [Commissariat a l' energie Atomique et aux Energies Alternatives - CEA-Cadarache, DEN/CEACAD/UCAP, 13108 Saint Paul lez Durance Cedex (France)

    2013-07-01

    The CEA Cadarache research center is one of the 10 research centers of the French Alternative Energies and Atomic Energy Commission (CEA). Distributed throughout various research platforms, it focuses on nuclear fission, nuclear fusion, new energy technologies (hydrogen, solar, biomass) and fundamental research in the field of vegetal biology. It is the most important technological research and development centers for energy in Europe. Considering the sensitive nature of nuclear activities, the questions surrounding the issue of radioactive waste, the nuclear energy and the social, economic and environmental concerns for present and future generations, the French Government asked nuclear actors to open communication and to give all the information asked by the Local Information Commission (CLI) and the public [1]. In this context, the CEA Cadarache has decided to better show and explain its expertise and experience in the area of nuclear energy and nuclear power plant design, and to make it available to stakeholders and to the public. CEA Cadarache receives each year more than 9000 visitors. To complete technical visits of the research facilities and laboratories, a scientific cultural center has been built in 2011 to inform the public on CEA Cadarache research activities and to facilitate the acceptance of nuclear energy in a way suited to the level of knowledge of the visitors. A modern interactive exhibition of 150 m{sup 2} allows visitors to find out more about energy, CEA Cadarache research programs, radioactive waste management and radiological impact on the research center activities. It also offers an auditorium for group discussions and for school groups to discover science through enjoyment. This communication center has received several thousand visitors since its opening on October 2011; the initial results of this experience are now available. It's possible to explain the design of this exhibition, to give some statistics on the number of the

  6. An Information Building on Radioactivity and Nuclear Energy for the French CEA Cadarache Research Center - 13492

    International Nuclear Information System (INIS)

    Brunel, Guy; Denis, Dominique; Boulet, Alain

    2013-01-01

    The CEA Cadarache research center is one of the 10 research centers of the French Alternative Energies and Atomic Energy Commission (CEA). Distributed throughout various research platforms, it focuses on nuclear fission, nuclear fusion, new energy technologies (hydrogen, solar, biomass) and fundamental research in the field of vegetal biology. It is the most important technological research and development centers for energy in Europe. Considering the sensitive nature of nuclear activities, the questions surrounding the issue of radioactive waste, the nuclear energy and the social, economic and environmental concerns for present and future generations, the French Government asked nuclear actors to open communication and to give all the information asked by the Local Information Commission (CLI) and the public [1]. In this context, the CEA Cadarache has decided to better show and explain its expertise and experience in the area of nuclear energy and nuclear power plant design, and to make it available to stakeholders and to the public. CEA Cadarache receives each year more than 9000 visitors. To complete technical visits of the research facilities and laboratories, a scientific cultural center has been built in 2011 to inform the public on CEA Cadarache research activities and to facilitate the acceptance of nuclear energy in a way suited to the level of knowledge of the visitors. A modern interactive exhibition of 150 m 2 allows visitors to find out more about energy, CEA Cadarache research programs, radioactive waste management and radiological impact on the research center activities. It also offers an auditorium for group discussions and for school groups to discover science through enjoyment. This communication center has received several thousand visitors since its opening on October 2011; the initial results of this experience are now available. It's possible to explain the design of this exhibition, to give some statistics on the number of the visitors

  7. Nuclear power plants

    International Nuclear Information System (INIS)

    Kiyokawa, Teruyuki; Soman, Yoshindo.

    1985-01-01

    Purpose: To constitute a heat exchanger as one unit by integrating primary and secondary coolant circuits with secondary coolant circuit and steam circuit into a single primary circuit and steam circuit. Constitution: A nuclear power plant comprises a nuclear reactor vessel, primary coolant pipeways and a leakage detection system, in which a dual-pipe type heat exchanger is connected to the primary circuit pipeway. The heat conduction tube of the heat exchanger has a dual pipe structure, in which the inside of the inner tube is connected to the primary circuit pipeway, the outside of the outer tube is connected to steam circuit pipeway and a fluid channel is disposed between the inner and outer tubes and the fluid channel is connected to the inside of an expansion tank for intermediate heat medium. The leak detection system is disposed to the intermediate heat medium expansion tank. Sodium as the intermediate heat medium is introduced from the intermediate portion (between the inner and outer tubes) by way of inermediate heat medium pipeways to the intermediate heat medium expansion tank and, further, to the intermediate portion for recycling. (Kawakami, Y.)

  8. Elecnuc. Nuclear power plants in the world; Elecnuc. Les centrales nucleaires dans le monde

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2003-07-01

    This 2003 version of Elecnuc contents information, data and charts on the nuclear power plants in the world and general information on the national perspectives concerning the electric power industry. The following topics are presented: 2002 highlights; characteristics of main reactor types and on order; map of the French nuclear power plants; the worldwide status of nuclear power plants on 2002/12/3; units distributed by countries; nuclear power plants connected to the Grid by reactor type groups; nuclear power plants under construction; capacity of the nuclear power plants on the grid; first electric generations supplied by a nuclear unit; electrical generation from nuclear plants by country at the end 2002; performance indicator of french PWR units; trends of the generation indicator worldwide from 1960 to 2002; 2002 cumulative Load Factor by owners; nuclear power plants connected to the grid by countries; status of license renewal applications in Usa; nuclear power plants under construction; Shutdown nuclear power plants; exported nuclear power plants by type; exported nuclear power plants by countries; nuclear power plants under construction or order; steam generator replacements; recycling of Plutonium in LWR; projects of MOX fuel use in reactors; electricity needs of Germany, Belgium, Spain, Finland, United Kingdom; electricity indicators of the five countries. (A.L.B.)

  9. Continuous improvement of operation and maintenance conditions of french PWR nuclear islands

    International Nuclear Information System (INIS)

    Bitsch, D.

    1985-05-01

    Improvement of the nuclear island design, to facilitate maintenance and working conditions during plant shutdown, has been a subject of particular attention within the French PWR program. Standardization and industrial concentration created an unusually favourable context for approaching this objective. Progress efforts supported by the feedback of actual operating experience were pursued in the areas of plant layout-equipment installation, and on the design and technology of the component themselves. The progress efforts on the design and technology of the components were pursued along several paths including: - the resistance increase of specific parts submitted to various forms of in-service damage, - the reduction of the extent and duration of work during plant outages and - the reduction of the Occupational Radiation Exposure (ORE), one of the most important axes of development, through the appropriate selection of less releasing materials, the implementation of more efficient decontamination systems and by the use of robots

  10. Perspectives of nuclear power plants

    International Nuclear Information System (INIS)

    Vajda, Gy.

    2001-01-01

    In several countries the construction of nuclear power plants has been stopped, and in some counties several plants have been decommissioned or are planned to. Therefore, the question arises: have nuclear power plants any future? According to the author, the question should be reformulated: can mankind survive without nuclear power? To examine this challenge, the global power demand and its trends are analyzed. According to the results, traditional energy sources cannot be adequate to supply power. Therefore, a reconsideration of nuclear power should be imminent. The economic, environmental attractions are discussed as opposite to the lack of social support. (R.P.)

  11. Owners of nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Hudson, C.R.; White, V.S.

    1996-11-01

    Commercial nuclear power plants in this country can be owned by a number of separate entities, each with varying ownership proportions. Each of these owners may, in turn, have a parent/subsidiary relationship to other companies. In addition, the operator of the plant may be a different entity as well. This report provides a compilation on the owners/operators for all commercial power reactors in the United States. While the utility industry is currently experiencing changes in organizational structure which may affect nuclear plant ownership, the data in this report is current as of July 1996. The report is divided into sections representing different aspects of nuclear plant ownership.

  12. Elecnuc. Nuclear power plants in the world; Elecnuc. Les centrales nucleaires dans le monde

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2008-07-01

    This small booklet summarizes in tables all data relative to the nuclear power plants worldwide. These data come from the IAEA's PRIS and AREVA-CEA's GAIA databases. The following aspects are reviewed: 2007 highlights; Main characteristics of reactor types; Map of the French nuclear power plants on 2007/01/01; Worldwide status of nuclear power plants (12/31/2007); Units distributed by countries; Nuclear power plants connected to the Grid- by reactor type groups; Nuclear power plants under construction on 2007; Evolution of nuclear power plants capacities connected to the grid; First electric generations supplied by a nuclear unit in each country; Electrical generation from nuclear power plants by country at the end 2007; Performance indicator of French PWR units; Evolution of the generation indicators worldwide by type; Nuclear operator ranking according to their installed capacity; Units connected to the grid by countries at 12/31/2007; Status of licence renewal applications in USA; Nuclear power plants under construction at 12/31/2007; Shutdown reactors; Exported nuclear capacity in net MWe; Exported and national nuclear capacity connected to the grid; Exported nuclear power plants under construction; Exported and national nuclear capacity under construction; Nuclear power plants ordered at 12/31/2007; Long term shutdown units at 12/31/2007; COL (combined licences) applications in the USA; Recycling of Plutonium in reactors and experiences; Mox licence plants projects; Appendix - historical development; Meaning of the used acronyms; Glossary.

  13. ELECNUC. Nuclear power plants in the world - 2012 edition, Status on 2011-12-31

    International Nuclear Information System (INIS)

    2012-01-01

    This small booklet summarizes in tables all data relative to the nuclear power plants worldwide. Data come from the IAEA's PRIS database and from specific I-tese studies. The following aspects are reviewed: 2011 highlights; Main characteristics of reactor types; Map of the French nuclear power plants on 2011/01/01; Worldwide status of nuclear power plants (12/31/2011); Units distributed by countries; Nuclear power plants connected to the Grid- by reactor type groups; Nuclear power plants under construction on 2011; Evolution of nuclear power plants capacities connected to the grid; First electric generations supplied by a nuclear unit in each country; Electrical generation from nuclear powe plants by country at the end 2011; Performance indicator of french PWR units; Evolution of the generation indicators worldwide by type; Nuclear operator ranking according to their installed capacity; Units connected to the grid by countries at 12/31/2011; Status of licence renewal applications in USA; Nuclear power plants under construction at 12/31/2011; Shutdown reactors; Exported nuclear capacity in net MWe; Exported and national nuclear capacity connected to the grid; Exported nuclear power plants under construction; Exported and national nuclear capacity under construction; Nuclear power plants ordered at 12/31/2011; Long term shutdown units at 12/31/2011; COL (Combined Licence) applications in the USA; Recycling of Plutonium in reactors and experiences; Mox licence plants projects; Appendix - historical development; Meaning of the used acronyms; Glossary

  14. The 36. French Language Colloquium on Nuclear Medicine

    International Nuclear Information System (INIS)

    Bourguet, P.

    1997-01-01

    This issue of the journal 'Medecine Nucleaire - Imagerie Fonctionnelle et Metabolique' contains the short communications, abstracts of the poster communications and lectures presented in the 36. French Language Colloquium on Nuclear Medicine held at Rennes - Saint-Malo on 1 to 3 October, 1997. According to their content the communications were bunched in the following sessions: Radioprotection-Environment, Cardiology-Pneumology, Endocrinology, Oncology-Diagnosis, Oncology-Therapy, Neurology, Radiobiology, Radioprotection, Osteo-articulary, Uro-Nephrology, Hepato-Gastroenterology, Radiopharmaceuticals, Immuno-analysis, Instrumentation-Image Processing. The overwhelming majority of the papers presented dealt with the use of radioisotopes and radiolabelled complexes in diagnosis and therapy especially, by means of PET and SPECT techniques. The colloquium proceedings are completed by two lectures on Radioimmunotherapy of lymphomas and use of PET in tumor imaging considered from the cost efficiency

  15. Proposal of resolution to create an inquiry commission on the french nuclear power plants reliability in case or earthquakes and on the safety, information and warning procedures in case of incidents

    International Nuclear Information System (INIS)

    2003-01-01

    This short paper presents the reasons of the creation of parliamentary inquiry commission of 30 members, on the reliability of the nuclear power plants in France in case of earthquakes and on the safety, information and warning procedures in case of accidents. (A.L.B.)

  16. Nuclear Security for Floating Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Skiba, James M. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Scherer, Carolynn P. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2015-10-13

    Recently there has been a lot of interest in small modular reactors. A specific type of these small modular reactors (SMR,) are marine based power plants called floating nuclear power plants (FNPP). These FNPPs are typically built by countries with extensive knowledge of nuclear energy, such as Russia, France, China and the US. These FNPPs are built in one country and then sent to countries in need of power and/or seawater desalination. Fifteen countries have expressed interest in acquiring such power stations. Some designs for such power stations are briefly summarized. Several different avenues for cooperation in FNPP technology are proposed, including IAEA nuclear security (i.e. safeguards), multilateral or bilateral agreements, and working with Russian design that incorporates nuclear safeguards for IAEA inspections in non-nuclear weapons states

  17. Elecnuc. Nuclear power plants worldwide

    International Nuclear Information System (INIS)

    1998-01-01

    This small folder presents a digest of some useful information concerning the nuclear power plants worldwide and the situation of nuclear industry at the end of 1997: power production of nuclear origin, distribution of reactor types, number of installed units, evolution and prediction of reactor orders, connections to the grid and decommissioning, worldwide development of nuclear power, evolution of power production of nuclear origin, the installed power per reactor type, market shares and exports of the main nuclear engineering companies, power plants constructions and orders situation, evolution of reactors performances during the last 10 years, know-how and development of nuclear safety, the remarkable facts of 1997, the future of nuclear power and the energy policy trends. (J.S.)

  18. Owners of nuclear power plants

    International Nuclear Information System (INIS)

    Wood, R.S.

    1991-07-01

    This report indicates percentage ownership of commercial nuclear power plants by utility companies. The report includes all plants operating, under construction, docketed for NRC safety and environmental reviews, or under NRC antitrust review, but does not include those plants announced but not yet under review or those plants formally cancelled. Part 1 of the report lists plants alphabetically with their associated applicants or licensees and percentage ownership. Part 2 lists applicants or licensees alphabetically with their associated plants and percentage ownership. Part 1 also indicates which plants have received operating licenses (OLS)

  19. Nuclear power plant

    Energy Technology Data Exchange (ETDEWEB)

    Urata, Hidehiro; Oya, Takashi

    1996-11-05

    The present invention provides a highly safe light water-cooled type nuclear power plant capable of reducing radiation dose by suppressing deposition of activated corrosion products by a simple constitution. Namely, equipments and pipelines for fluid such as pumps at least in one of fluid systems such as a condensate cleanup system are constituted by a material containing metal species such as Zn having an effect of suppressing deposition of radioactivity. Alternatively, the surface of these equipments and pipelines for fluids on which water passes is formed by a coating layer comprising a material containing a metal having a radiation deposition suppressing effect. As a result, radioactivity deposited on the equipments and pipelines for fluids is reduced. In addition, since the method described above may be applied only at least to a portion of the members constituting at least one of the systems for fluids, it is economical. Accordingly, radiation dose upon inspection of equipments and pipelines for fluids can be reduced simply and reliably. (I.S.)

  20. Nuclear power plant

    International Nuclear Information System (INIS)

    Urata, Hidehiro; Oya, Takashi.

    1996-01-01

    The present invention provides a highly safe light water-cooled type nuclear power plant capable of reducing radiation dose by suppressing deposition of activated corrosion products by a simple constitution. Namely, equipments and pipelines for fluid such as pumps at least in one of fluid systems such as a condensate cleanup system are constituted by a material containing metal species such as Zn having an effect of suppressing deposition of radioactivity. Alternatively, the surface of these equipments and pipelines for fluids on which water passes is formed by a coating layer comprising a material containing a metal having a radiation deposition suppressing effect. As a result, radioactivity deposited on the equipments and pipelines for fluids is reduced. In addition, since the method described above may be applied only at least to a portion of the members constituting at least one of the systems for fluids, it is economical. Accordingly, radiation dose upon inspection of equipments and pipelines for fluids can be reduced simply and reliably. (I.S.)

  1. Nuclear power plants

    International Nuclear Information System (INIS)

    Ushijima, Susumu.

    1984-01-01

    Purpose: To enable to prevent the degradation in the quality of condensated water in a case where sea water leakage should occur in a steam condenser of a BWR type nuclear power plant. Constitution: Increase in the ion concentration in condensated water is detected by an ion concentration detector and the leaking factor of sea water is calculated in a leaking factor calculator. If the sea water leaking factor exceeds a predetermined value, a leak generation signal is sent from a judging device to a reactor power control device to reduce the reactor power. At ehe same tiem, the leak generation signal is also sent to a steam condenser selection and isolation device to interrupt the sea water pump of a specified steam condenser based on the signal from the ion concentration detector, as well as close the inlet and outlet valves while open vent and drain valves to thereby forcively discharge the sea water in the cooling water pipes. This can keep the condensate desalting device from ion breaking and prevent the degradation in the quality of the reactor water. (Horiuchi, T.)

  2. Underground nuclear power plant

    International Nuclear Information System (INIS)

    Takahashi, Hideo.

    1997-01-01

    In an underground-type nuclear power plant, groups of containing cavities comprising a plurality of containing cavities connected in series laterally by way of partition walls are disposed in parallel underground. Controlled communication tunnels for communicating the containing cavities belonging to a control region to each other, and non-controlled communication tunnels for communicating containing cavities belonging to a non-controlled area to each other are disposed underground. A controlled corridor tunnel and a non-controlled corridor tunnel extended so as to surround the containing cavity groups are disposed underground, and the containing cavities belonging to the controlled area are connected to the controlled corridor tunnel respectively, and the containing cavities belonging to the non-controlled area are connected to the non-controlled corridor tunnel respectively. The excavating amount of earth and sand upon construction can be reduced by disposing the containing cavity groups comprising a plurality of containing cavities connected in series laterally. The time and the cost for the construction can be reduced, and various excellent effects can be provided. (N.H.)

  3. Systematic safety evaluation of old nuclear power plants

    International Nuclear Information System (INIS)

    Dredemis, G.; Fourest, B.

    1984-01-01

    The French safety authorities have undertaken a systematic evaluation of the safety of old nuclear power plants. Apart from a complete revision of safety documents (safety analysis report, general operating rules, incident and accident procedures, internal emergency plan, quality organisation manual), this examination consisted of analysing the operating experience of systems frequently challenged and a systematic examination of the safety-related systems. This paper is based on an exercise at the Ardennes Nuclear Power Plant which has been in operation for 15 years. This paper also summarizes the main surveys and modifications relating to this power plant. (orig.)

  4. Public regulation of nuclear plants

    International Nuclear Information System (INIS)

    Burtheret, M.; Cormis, de

    1980-01-01

    The construction and operation of nuclear plants are subject to a complex system of governmental administration. The authors list the various governmental authorisations and rules applicable to these plants. In the first part, they describe the national regulations which relate specifically to nuclear plants, and emphasize the provisions which are intended to ensure the safety of the installations and the protection of the public against ionizing radiation. However, while the safety of nuclear plants is a major concern of the authorities, other interests are also protected. This is accomplished by various laws or regulations which apply to nuclear plants as well as other industrial installations. The duties which these texts, and the administrative practice based thereon, impose on Electricite de France are covered in the second part [fr

  5. Nuclear power plant diagnostic system

    International Nuclear Information System (INIS)

    Prokop, K.; Volavy, J.

    1982-01-01

    Basic information is presented on diagnostic systems used at nuclear power plants with PWR reactors. They include systems used at the Novovoronezh nuclear power plant in the USSR, at the Nord power plant in the GDR, the system developed at the Hungarian VEIKI institute, the system used at the V-1 nuclear power plant at Jaslovske Bohunice in Czechoslovakia and systems of the Rockwell International company used in US nuclear power plants. These diagnostic systems are basically founded on monitoring vibrations and noise, loose parts, pressure pulsations, neutron noise, coolant leaks and acoustic emissions. The Rockwell International system represents a complex unit whose advantage is the on-line evaluation of signals which gives certain instructions for the given situation directly to the operator. The other described systems process signals using similar methods. Digitized signals only serve off-line computer analyses. (Z.M.)

  6. Nuclear material discovery or loss: the French experience

    International Nuclear Information System (INIS)

    Zanetti, S.H.

    2006-01-01

    In a nuclear facility, when a difference between the physical inventory listing and accountancy records is discovered, the French law (Article 11 of the 'Decret 81-512') requires a declaration to the High Civil Servant for Defence of the Ministry in charge of Industry. Moreover, according to article L.1333-13 of the Defence Code, in case of a suspicion of loss, theft or diversion of nuclear material, the licensee has to declare this event to the police. In the meantime, an investigation is carried out in the facility, and in cooperation with other facilities if necessary. These measures are aimed at: - Finding the lost nuclear material (if any), - Understand the causes of the problem, - Solve the differences by acting on the PIL or/and accountancy records, - Act to prevent any other occurrence of this kind of event. These actions can take place in the general field of a police investigation. After all these facts and information have been gathered, the licensee writes down a complete file which is transferred to the High Civil Servant for Defence of the Ministry in charge of Industry, in order to be analysed by his technical support body (IRSN). Thus, the IRSN is able to give its conclusion to the authority about this event, especially regarding: - The causes of the event, - Relevance and completeness of investigations, - Pertinence of the corrections, - Relevance of corrective actions, - Probability of another occurrence. This system is useful to ensure a complete follow-up of the events occurring in the various nuclear facilities in France, to have an extensive overview of the problems on a national scale. If an item is found in a facility A, numerous questions must be answered: - Where does it come from? - Since when is it in facility A? - How did it happened that this item has been transferred from facility B to facility A without the transfer of information? - We will consider these issues through examples. This kind of event can be potentially very rich in

  7. Deterrence at Three: US, UK and French Nuclear Cooperation

    International Nuclear Information System (INIS)

    Lewis, Jeffrey; Tertrais, Bruno

    2016-01-01

    Following Russia's annexation of Crimea and aggression against Ukraine, members of NATO are again pondering the strength of Western deterrence. Over the course of the Ukraine crisis, President Vladimir Putin has repeatedly emphasised the potency of Russian nuclear weapons, announced new nuclear-weapons programmes and brushed off accusations that Russia is cheating on a number of arms-control agreements. Most ominously, Putin has declared that he would have been prepared to place Russian nuclear forces on alert - which implies threatening their use - had the annexation of Crimea met with serious resistance. The three NATO nuclear-weapons states - the United States, United Kingdom and France - must again contemplate how best to ensure that their very different nuclear forces strengthen NATO's nuclear deterrence against Russian aggression. There is a tendency among Western defence analysts to assume that, in the event of a major crisis, the three NATO nuclear-weapons states would be able to effectively coordinate their deterrence policies and communications. The stakes are so high, so the thinking goes, that the three parties would find a way to successfully manage the crisis together. Yet, recent experience in terms of trilateral crisis management and strategic communications is not encouraging. In 2013, the United States, the United Kingdom and France attempted to deter Syria from using chemical weapons. This ended up being one of the biggest deterrence fiascos in recent memory - a textbook example of how not to prevent adversaries from embarking on large-scale aggression. The president of the United States announced a 'red line' regarding Syrian use of chemical weapons. Although the red line was apparently drawn extemporaneously, at a press conference on 20 August 2012, London and Paris presumed that Washington was committed to the red line and followed suit with their own statements. Over the course of several months, Syria appears to have

  8. Nuclear power plant V-1

    International Nuclear Information System (INIS)

    1998-01-01

    The nuclear power plant Bohunice V -1 is briefly described. This NPP consists from two reactor units. Their main time characteristics are (Reactor Unit 1, Reactor Unit 2): beginning of construction - 24 April 1972; first controlled reactor power - 27 November 1978, 15 March 1980; connection to the grid - 17 December 1978, 26 March 1980; commercial operation - 1 April 1980, 7 January 1981. This leaflet contains: NPP V-1 construction; Major technological equipment (Primary circuit: Nuclear reactor [WWER 440 V230 type reactor];Steam generator; Reactor Coolant Pumps; Primary Circuit Auxiliary Systems. Secondary circuit: Turbine generators, Nuclear power plant electrical equipment; power plant control) and technical data

  9. Historical seismicity in France. Its role in the assessment of seismic risk on French nuclear sites

    International Nuclear Information System (INIS)

    Levret, A.

    1987-11-01

    Since 1975 in order to be in conformity with the requirements of the French nuclear program, a review of historical seismicity was undertaken in France. The assessment of seismic hazard for the safety of nuclear plants is in fact based upon a seismotectonic approach which needs to take into account the seismic activity over as long a period of time as possible. The method adopted for reviewing historical earthquakes entails a systematic consultation of the original sources and a critical analysis there of in the light of the historical, geographical and political contexts of the time. The same standards apply where the acquisition of new elements of information is involved. Each item of information is assigned a degree of reliability, then compiled in a computer file, up-dated annually; this file currently contains more than 4.500 events covering a period of time of about a millenary

  10. [Recommendations for inspections of the French nuclear safety authority].

    Science.gov (United States)

    Rousse, C; Chauvet, B

    2015-10-01

    The French nuclear safety authority is responsible for the control of radiation protection in radiotherapy since 2002. Controls are based on the public health and the labour codes and on the procedures defined by the controlled health care facility for its quality and safety management system according to ASN decision No. 2008-DC-0103. Inspectors verify the adequacy of the quality and safety management procedures and their implementation, and select process steps on the basis of feedback from events notified to ASN. Topics of the inspection are communicated to the facility at the launch of a campaign, which enables them to anticipate the inspectors' expectations. In cases where they are not physicians, inspectors are not allowed to access information covered by medical confidentiality. The consulted documents must therefore be expunged of any patient-identifying information. Exchanges before the inspection are intended to facilitate the provision of documents that may be consulted. Finally, exchange slots between inspectors and the local professionals must be organized. Based on improvements achieved by the health care centres and on recommendations from a joint working group of radiotherapy professionals and the nuclear safety authority, changes will be made in the control procedure that will be implemented when developing the inspection program for 2016-2019. Copyright © 2015. Published by Elsevier SAS.

  11. Man and nuclear power plants

    International Nuclear Information System (INIS)

    Anon.

    1978-01-01

    According to the Inst. fuer Unfallforschung/TUeV Rheinland, Koeln, the interpretation of empirical data gained from the operation of nuclear power plants at home and abroad during the period 1967-1975 has shown that about 38% of all reactor accidents were caused by human failures. These occured either during the design and construction, the commissioning, the reconditioning or the operation of the plants. This very fact stresses human responsibility for the safety of nuclear power plants, in spite of those plants being automated to a high degree and devices. (orig.) [de

  12. The role of the operator of nuclear power plants in disposal of nuclear waste

    International Nuclear Information System (INIS)

    Chaussade, J.P.

    1995-01-01

    Public opinion polls show that the French have largely understood the importance of our nuclear programme in maintaining French independence with regard to power supply and its security and that they have confidence in the technicians for the proper construction and operation of these power plants, but that they retain many questions concerning the disposal of nuclear waste. They have the impression that solutions remain to be found, and especially that the Electricite de France (EDF) devised the nuclear power programme without concern for the disposal of waste. This lack of information is fortunately far from reality, EDF, under the supervision of the security authorities, manages the waste produced in the nuclear power plants. Final stocking of waste is handled by a body that is independent of the waste producer, the ''Agence nationale pour la gestion des dechets radioactifs'' (Andra) (National Agency for the Management of Radioactive Waste). (author). 7 refs., 1 tab

  13. Radiochemistry in nuclear power plants

    International Nuclear Information System (INIS)

    Schwarz, W.

    2007-01-01

    Radiochemistry is employed in nuclear power plants not as an end in itself but, among other things, as a main prerequisite of optimum radiation protection. Radiochemical monitoring of various loops provides important information about sources of radioactivity, activity distribution in the plant and its changes. In the light of these analytical findings, plant crews are able to take measures having a positive effect on radiation levels in the plant. The example of a BWR plant is used to show, among other things, how radiochemical analyses helped to reduce radiation levels in a plant and, as a consequence, to decrease clearly radiation exposure of the personnel despite higher workloads. (orig.)

  14. Nuclear Power Plant Simulation Game.

    Science.gov (United States)

    Weiss, Fran

    1979-01-01

    Presents a nuclear power plant simulation game which is designed to involve a class of 30 junior or senior high school students. Scientific, ecological, and social issues covered in the game are also presented. (HM)

  15. Robotics for nuclear power plants

    International Nuclear Information System (INIS)

    Shiraiwa, Takanori; Watanabe, Atsuo; Miyasawa, Tatsuo

    1984-01-01

    Demand for robots in nuclear power plants is increasing of late in order to reduce workers' exposure to radiations. Especially, owing to the progress of microelectronics and robotics, earnest desire is growing for the advent of intellecturized robots that perform indeterminate and complicated security work. Herein represented are the robots recently developed for nuclear power plants and the review of the present status of robotics. (author)

  16. Robotics for nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Shiraiwa, Takanori; Watanabe, Atsuo; Miyasawa, Tatsuo

    1984-10-01

    Demand for robots in nuclear power plants is increasing of late in order to reduce workers' exposure to radiations. Especially, owing to the progress of microelectronics and robotics, earnest desire is growing for the advent of intellecturized robots that perform indeterminate and complicated security work. Herein represented are the robots recently developed for nuclear power plants and the review of the present status of robotics.

  17. Decommissioning of nuclear power plants

    International Nuclear Information System (INIS)

    Vollradt, J.

    1977-01-01

    A survey of the main questions of decommissioning of nuclear power plants will be given in the sight of German utilities (VDEW-Working group 'Stillegung'). The main topics are: 1) Definitions of decommissioning, entombment, removal and combinations of such alternatives; 2) Radioactive inventory (build up and decay); 3) Experience up to now; 4) Possibilities to dismantle are given by possibility to repair nuclear power plants; 5) Estimated costs, waste, occupational radiation dose; 6) German concept of decommissioning. (orig./HK) [de

  18. Organizing nuclear power plant operation

    International Nuclear Information System (INIS)

    Adams, H.W.; Rekittke, K.

    1987-01-01

    With the preliminary culmination in the convoy plants of the high standard of engineered safeguards in German nuclear power plants developed over the past twenty years, the interest of operators has now increasingly turned to problems which had not been in the focus of attention before. One of these problems is the organization of nuclear power plant operation. In order to enlarge the basis of knowledge, which is documented also in the rules published by the Kerntechnischer Ausschuss (Nuclear Technology Committee), the German Federal Minister of the Interior has commissioned a study of the organizational structures of nuclear power plants. The findings of that study are covered in the article. Two representative nuclear power plants in the Federal Republic of Germany were selected for the study, one of them a single-unit plant run by an independent operating company in the form of a private company under German law (GmbH), the other a dual-unit plant operated as a dependent unit of a utility. The two enterprises have different structures of organization. (orig.) [de

  19. Partner of nuclear power plants

    International Nuclear Information System (INIS)

    Gribi, M.; Lauer, F.; Pauli, W.; Ruzek, W.

    1992-01-01

    Sulzer, the Swiss technology group, is a supplier of components and systems for nuclear power plants. Important parts of Swiss nuclear power stations, such as containments, reactor pressure vessels, primary pipings, are made in Winterthur. Sulzer Thermtec AG and some divisions of Sulzer Innotec focus their activities on servicing and backfitting nuclear power plants. The European market enjoys priority. New types of valves or systems are developed as economic solutions meeting more stringent criteria imposed by public authorities or arising from operating conditions. (orig.) [de

  20. Integrated project-management information systems: the French nuclear industry experience

    Energy Technology Data Exchange (ETDEWEB)

    Jacquin, J.C.; Capuin, G.M.

    1988-01-01

    In the early eighties, and in the French case from 1985, the development of the data-processing industry has made the real integration of project-management information systems feasible, and the data-base administration function has been extended to all facets of the engineering process. The new systems had to take into account the existing ones which were still operating efficiently and the new problems encountered due to the changes in the environment. One of these new problems was equipment and materials management, as the period of plants built in series had vanished, and the industry was obliged to build plants individually. The challenge encountered by the French nuclear industry in terms of the project-management information systems was to adapt efficiently to the new situation, and the purpose of this paper is to describe the most-significant elements of this adaptation. The authors review: (2) the objectives established by the company's general management; (2) the organization put into place to reach these objectives; (3) the main choices made; and (4) the economics. 3 references, 1 figure, 1 table.

  1. Integrated project-management information systems: the French nuclear industry experience

    International Nuclear Information System (INIS)

    Jacquin, J.C.; Capuin, G.M.

    1988-01-01

    In the early eighties, and in the French case from 1985, the development of the data-processing industry has made the real integration of project-management information systems feasible, and the data-base administration function has been extended to all facets of the engineering process. The new systems had to take into account the existing ones which were still operating efficiently and the new problems encountered due to the changes in the environment. One of these new problems was equipment and materials management, as the period of plants built in series had vanished, and the industry was obliged to build plants individually. The challenge encountered by the French nuclear industry in terms of the project-management information systems was to adapt efficiently to the new situation, and the purpose of this paper is to describe the most-significant elements of this adaptation. The authors review: (2) the objectives established by the company's general management; (2) the organization put into place to reach these objectives; (3) the main choices made; and (4) the economics. 3 references, 1 figure, 1 table

  2. Operation and maintenance of nuclear power plants

    International Nuclear Information System (INIS)

    Ackermann, G.

    1987-01-01

    This textbook gives a systematic introduction into the operational and maintenance activities in nuclear power plants with pressurized water reactors. Subjects: (1) Setup and operational behaviour of power reactors, (2) setup of nuclear power plants, (3) radiation protection and nuclear safety, (4) nuclear fuel, (5) constructional layout of nuclear power plants, (6) management, and (7) maintenance. 158 figs., 56 tabs

  3. Environmental monitoring associated with nuclear testing in French Polynesia

    International Nuclear Information System (INIS)

    Coulon, R.; Arnould, C.; Bory, P.; Ducousso, R.; Sarbach, J.

    2009-01-01

    The realization of the programme of nuclear experiments in French Polynesia was accompanied by the installation by a radiological monitoring device of the environment, either the physical environment or biological, continental or marine, vegetable or animal, in order to make sure of the absence of risk for the populations. This device took all its importance with the tests carried out in the atmosphere between 1966 and 1974. Its implementation required important means in hardware and manpower with the intervention of civil and military or sometimes mixed organizations. The monitoring was naturally done in a very complete way in the zones close to the sites of tests, but also on the whole of the Polynesian territory, in particular the most populated atolls. It also carried, but in a less extended way, on remote zones, like the Andean countries, because of their geographical location. The results obtained by the various involved laboratories were gathered and interpreted in order to ensure information of the persons in charge and the authorities, in particular in Polynesia and through them the population. They were each year transmitted to the scientific committee of the United Nations for the study of the effects of ionizing radiations (UNSCEAR). The surveillance device is thus described, apart from the zones close to the zones of testing, with the presentation of the various implied organizations and the various monitoring programs. (authors)

  4. Loviisa nuclear power plant analyzer

    International Nuclear Information System (INIS)

    Porkholm, K.; Nurmilaukas, P.; Tiihonen, O.; Haenninen, M.; Puska, E.

    1992-12-01

    The APROS Simulation Environment has been developed since 1986 by Imatran Voima Oy (IVO) and the Technical Research Centre of Finland (VTT). It provides tools, solution algorithms and process components for use in different simulation systems for design, analysis and training purposes. One of its main nuclear applications is the Loviisa Nuclear Power Plant Analyzer (LPA). The Loviisa Plant Analyzer includes all the important plant components both in the primary and in the secondary circuits. In addition, all the main control systems, the protection system and the high voltage electrical systems are included. (orig.)

  5. Exchange of information between nuclear safety authorities: Policy of the French regulator

    International Nuclear Information System (INIS)

    Asty, Michel

    2000-01-01

    Full text: The decree setting up the Nuclear Safety Authority in 1973 entrusted it with international assignments whose objectives are still valid: - develop exchanges of information with foreign counterparts on regulatory systems and practices, on problems encountered in the nuclear safety field and on provisions made, with a view to enhancing its approach, and - becoming better acquainted with the actual operating practice of these Safety Authorities from which lessons could be learned for its own working procedures; - improving its position in the technical discussions with the French operators, since its arguments would be strengthened by practical knowledge of conditions abroad; - make known and explain the French approach and practices in the nuclear safety field and provide information on measures taken to deal with the problems encountered. This approach has several objectives: - promote the circulation of information on French positions on certain issues, such as very low level waste, for instance; - assist some countries wishing to create or modify their Nuclear Safety Authority, such as countries of the former USSR, the Central and Eastern European countries, and emerging countries on other continents; - help, when requested, foreign Safety Authorities required to issue permits for nuclear equipment of French origin; - provide the countries concerned with all relevant information on French nuclear installations located near their frontiers. Examples are given on the way the French Nuclear Safety Authority implements these objectives. (author)

  6. Building of nuclear power plant

    International Nuclear Information System (INIS)

    Saito, Takashi.

    1997-01-01

    A first nuclear plant and a second nuclear power plant are disposed in adjacent with each other in a building for a nuclear reactor. A reactor container is disposed in each of the plants, and each reactor container is surrounded by a second containing facility. A repairing chamber capable of communicating with the secondary containing facilities for both of the secondary containing facilities is disposed being in contact with the second containing facility of each plant for repairing control rod driving mechanisms or reactor incorporated-type recycling pumps. Namely, the repairing chamber is in adjacent with the reactor containers of both plants, and situated between both of the plants as a repairing chamber to be used in common for both plants. Air tight inlet/exit doors are formed to the inlets/exits of both plants of the repairing chamber. Space for the repairing chamber can be reduced to about one half compared with a case where the repairing chamber is formed independently on each plant. (I.N.)

  7. TVA's nuclear power plant experience

    International Nuclear Information System (INIS)

    Willis, W.F.

    1979-01-01

    This paper reviews TVA's nuclear power plant design and construction experience in terms of schedule and capital costs. The completed plant in commercial operation at Browns Ferry and six additional plants currently under construction represent the nation's largest single commitment to nuclear power and an ultimate investment of $12 billion by 1986. The presentation is made in three separate phases. Phase one will recapitulate the status of the nuclear power industry in 1966 and set forth the assumptions used for estimating capital costs and projecting project schedules for the first TVA units. Phase two describes what happened to the program in the hectic early 1979's in terms of expansion of scope (particularly for safety features), the dramatic increase in regulatory requirements, vendor problems, stretchout of project schedules, and unprecedented inflation. Phase three addresses the assumptions used today in estimating schedules and plant costs for the next ten-year period

  8. French experience in using programmable systems for the control and the protection of nuclear reactors

    International Nuclear Information System (INIS)

    Jover, P.

    1986-01-01

    The paper presents the results obtained in the use of two automated systems important to safety in 1300 MWE French nuclear reactors: the numerical integrated protection system (SPIN) and the logical control system (CONTROBLOC)

  9. Elecnuc. Nuclear power plants in the world. 1997

    International Nuclear Information System (INIS)

    Maubacq, F.; Tailland, C.

    1997-04-01

    This small booklet provides information about all type of nuclear power plants worldwide. It is based on the data taken from the CEA/DSE/SEE Elecnuc database. The content comprises: the 1996 highlights, the main characteristics of the different type of reactors in operation or under construction, the map of the French nuclear power plant sites, the worldwide status of nuclear power plants at the end of 1996, the nuclear power plants in operation, under construction or on order (by groups of reactor-types), the power capacity evolution of power plants in operation, the net and gross capacity of the power plants on the grid, the commercial operation and grid connection forecasts, the first achieved or expected power generation supplied by a nuclear reactor for each country and the power generation from nuclear reactors, the performance indicator of the PWR units in France, the trends of the power generation indicator worldwide, the nuclear power plants in operation, under construction, on order, planned, cancelled, decommissioned and exported worldwide, the schedule of steam generator replacements, and the MOX fuel plutonium recycling programme. (J.S.)

  10. Nuclear plant simulation using the Nuclear Plant Analyzer

    International Nuclear Information System (INIS)

    Beelman, R.J.; Laats, E.T.; Wagner, R.J.

    1984-01-01

    The Nuclear Plant Analyzer (NPA), a state-of-the-art computerized safety analysis and engineering tool, was employed to simulate nuclear plant response to an abnormal transient during a training exercise at the US Nuclear Regulatory Commission (USNRC) in Washington, DC. Information relative to plant status was taken from a computer animated color graphics display depicting the course of the transient and was transmitted to the NRC Operations Center in a manner identical to that employed during an actual event. Recommendations from the Operations Center were implemented during on-line, interactive execution of the RELAP5 reactor systems code through the NPA allowing a degree of flexibility in training exercises not realized previously. When the debriefing was conducted, the RELAP5 calculations were replayed by way of the color graphics display, adding a new dimension to the debriefing and greatly enhancing the critique of the exercise

  11. The nuclear power stations of the French atomic energy programme (1960)

    International Nuclear Information System (INIS)

    Leduc, C.

    1960-01-01

    After recalling the entry of nuclear energy into energy production in France, the paper emphasizes the evolution of techniques applied in the designing of French nuclear power plants and describes the means employed for reducing costs per kWh of EDF2 and EDF3 compared with EDF1: the electric power per ton of uranium varies from 493 kW/t for EDF1 to 970 kW/t for EDF3. For this purpose the thermal power and electric power of units are changed respectively from 290 MWt for EDF1 to 1200 or 1600 MWt for EDF3 and from 28 to 250 MW. The results are obtained by an improvement in neutronic characteristics, developments in nuclear fuel technology, and simplification of the system of charging the reactor, whose means of maintenance are increased; the EDF2 heat-exchangers have been so designed as to increase the unit power of the elements, which will attain 9 MWt, as against 3 for EDF1. For EDF3 an advance project forecasts a thermodynamic layout with only one pressure stage. The paper ends with a description of the burst-slug detection systems, and an appendix gives a detailed comparative table of EDF1, EDF2 and EDF3 plant characteristics. (author) [fr

  12. Heat recovery from nuclear power plants

    International Nuclear Information System (INIS)

    Safa, H.

    2012-01-01

    The thermodynamic efficiency of a standard Nuclear Power Plant (NPP) is around 33%. Therefore, about two third of the heat generated by the nuclear fuel is literally wasted in the environment. Given the fact that the steam coming out from the high pressure turbine is superheated, it could be advantageously used for non electrical applications, particularly for district heating. Considering the technological improvements achieved these last years in heat piping insulation, it is now perfectly feasible to envisage heat transport over quite long distances, exceeding 200 km, with affordable losses. Therefore, it could be energetically wise to revise the modifications required on present reactors to perform heat extraction without impeding the NPP operation. In this paper, the case of a French reactor is studied showing that a large fraction of the wasted nuclear heat can be actually recovered and transported to be injected in the heat distribution network of a large city. Some technical and economical aspects of nuclear district heating application are also discussed. (author)

  13. ALARA at nuclear power plants

    International Nuclear Information System (INIS)

    Baum, J.W.

    1991-01-01

    Implementation of the ALARA principle at nuclear power plants presents a continuing challenge for health physicists at utility corporate and plant levels, for plant designers, and for regulatory agencies. The relatively large collective doses at some plants are being addressed through a variety of dose reduction techniques. Initiatives by the ICRP, NCRP, NRC, INPO, EPRI, and BNL ALARA Center have all contributed to a heightened interest and emphasis on dose reduction. The NCRP has formed Scientific Committee 46-9 which is developing a report on ALARA at Nuclear Power Plants. It is planned that this report will include material on historical aspects, management, valuation of dose reduction ($/person-Sv), quantitative and qualitative aspects of optimization, design, operational considerations, and training. The status of this work is summarized in this report

  14. World nuclear power plant capacity

    International Nuclear Information System (INIS)

    1991-01-01

    This report provides the background information for statistics and analysis developed by NUKEM in its monthly Market Report on the Nuclear Fuel Cycle. The assessments in this Special Report are based on the continuous review of individual nuclear power plant projects. This Special Report begins with tables summarizing a variety of nuclear power generating capacity statistics for 1990. It continues with a brief review of the year's major events regarding each country's nuclear power program. The standard NUKEM Market Report tables on nuclear plant capacity are given on pages 24 and 25. Owing to space limitations, the first year shown is 1988. Please refer to previous Special Reports for data covering earlier years. Detailed tables for each country list all existing plants as well as those expected by NUKEM to be in commercial operation by the end of 2005. An Appendix containing a list of abbreviations can be found starting on page 56. Only nuclear power plants intended for civilian use are included in this Special Report. Reactor lifetimes are assumed to be 35 years for all light water reactors and 30 years for all other reactor types, unless other data or definite decommissioning dates have been published by the operators. (orig./UA) [de

  15. French perspectives for production of hydrogen using nuclear energy

    International Nuclear Information System (INIS)

    Vitart, Xavier; Yvon, Pascal; Carles, Philippe; Naour, Francois Le

    2009-01-01

    The demand for hydrogen, driven by classical applications such as fertilizers or oil refining a well as new applications (synthetic fuels, fuel cells ... ) is growing significantly. Presently, most of the hydrogen produced in the world uses methane or another fossil feedstock, which is not a sustainable option, given the limited fossil resources and need to reduce CO 2 emissions. This stimulates the need to develop alternative processes of production which do not suffer from these drawbacks. Water decomposition combined with nuclear energy appears to be an attractive option. Low temperature electrolysis, even if it is used currently for limited amounts is a mature technology which can be generalized in the near future. However, this technology, which requires about 4 kWh of electricity per Nm 3 of hydrogen produced, is energy intensive and presents a low efficiency. Therefore the French Atomic Energy Commission (CEA) launched an extensive research and development program in 2001 in order to investigate advanced processes which could use directly the nuclear heat and present better economic potential. In the frame of this program, high temperature steam electrolysis along with several thermochemical cycles has been extensively studied. HTSE offers the advantage of reducing the electrical energy needed by substituting thermal energy, which promises to be cheaper. The need for electricity is also greatly reduced for the leading thermochemical cycles, the iodine-sulfur and the hybrid sulfur cycles, but they require high temperatures and hence coupling to a gas cooled reactor. Therefore interest is also paid to other processes such as the copper-chlorine cycle which operates at lower temperatures and could be coupled to other generation IV nuclear systems. The technical development of these processes involved acquisition of basic thermodynamic data, optimization of flowsheets, design and test of components and lab scale experiments in the kW range. This will demonstrate

  16. Medium-size nuclear plants

    International Nuclear Information System (INIS)

    Vogelweith, L.; Lavergne, J.C.; Martinot, G.; Weiss, A.

    1977-01-01

    CEA (TECHNICATOME) has developed a range of pressurized water reactors of the type ''CAS compact'' which are adapted to civil ship propulsion, or to electric power production, combined possibly with heat production, up to outputs equivalent to 125 MWe. Nuclear plants equipped with these reactors are suitable to medium-size electric networks. Among the possible realizations, two types of plants are mentioned as examples: 1) Floating electron-nuclear plants; and 2) Combined electric power and desalting plants. The report describes the design characteristics of the different parts of a 125 MWe unit floating electro-nuclear plant: nuclear steam system CAS 3 G, power generating plant, floating platform for the whole plant. The report gives attention to the different possibilities according to site conditions (the plant can be kept floating, in a natural or artificial basin, it can be put aground, ...) and to safety and environment factors. Such unit can be used in places where there is a growing demand in electric power and fresh water. The report describes how the reactor, the power generating plant and multiflash distillation units of an electric power-desalting plant can be combined: choice of the ratio water output/electric power output, thermal cycle combination, choice of the gain ratio, according to economic considerations, and to desired goal of water output. The report analyses also some technical options, such as: choice of the extraction point of steam used as heat supply of the desalting station (bleeding a condensation turbine, or recovering steam at the exhaust of a backpressure turbine), design making the system safe. Lastly, economic considerations are dealt with: combining the production of fresh water and electric power provides usually a much better energy balance and a lower cost for both products. Examples are given of some types of installations which combine medium-size reactors with fresh water stations yielding from 10000 to 120000 m 3 per day

  17. Owners of nuclear power plants

    International Nuclear Information System (INIS)

    Wood, R.S.

    1979-12-01

    The following list indicates percentage ownership of commercial nuclear power plants by utility companies as of December 1, 1979. The list includes all plants licensed to operate, under construction, docketed for NRC safety and envionmental reviews, or under NRC antitrust review. It does not include those plants announced but not yet under review or those plants formally cancelled. In many cases, ownership may be in the process of changing as a result of antitrust license conditions and hearings, altered financial conditions, changed power needs, and other reasons. However, this list reflects only those ownership percentages of which the NRC has been formally notified

  18. French statutory approach of the evaluation of the safety level of old nuclear divisions; Approche reglementaire francaise de l`appreciation du niveau de surete des tranches anciennes

    Energy Technology Data Exchange (ETDEWEB)

    Delage, M

    1994-06-01

    The legal French procedures include three steps which have to be followed during the exam of the safety in nuclear plants (creation authorization, loading authorization, actual running of the plant). After listing the different types of evaluation of safety in fraction of plants, this report presents the main themes encountered during the safety assessment: state of the reactor, maintenance, tracking of the incidents, personnel training, radioprotection, radioactive releases. The Fessenheim and Bugey list of reevaluation themes is also given. (TEC).

  19. Qualification by analogy of the functional valving of French pressurized water nuclear power stations

    International Nuclear Information System (INIS)

    Grenet, M.

    1991-01-01

    In certain postulated accidental conditions (loss of coolant accident or secondary pipe rupture, earthquake, high energy pipe rupture) plant valving is called on the important functions to bring the reactor to and maintain it at a safe shutdown condition. ELWCTRICITE DE FRANCE has completed qualification tests of about forty valves to assure their operability. However, taking into account the costs and time required to obtain this qualification and the number of valves to be qualified, this method alone is not sufficient. For this reason, Electricite de France has developed the alternative qualification methodology by analogy for each postulated accidental situation. Feedback experience of these methods today is such that it can be they have achieved their objective; namely, to improve the safety of French pressurized water nuclear power stations, while at the same time avoiding the two dangers represented by excessive complexity resulting in unsatisfactory operation, and insufficient thoroughness not providing any real increase in safety. (author)

  20. Latina nuclear power plant

    International Nuclear Information System (INIS)

    1976-03-01

    In the period under review, the Latina power plant produced 1009,07 million kWh with a utilization factor of 72% and an availability factor of 80,51%. The disparity between the utilization and availability factors was mainly due to the shutdown of the plant owing to trade union strife. The reasons for non-availability (19,49%) were almost all related to the functioning of the conventional part and the general servicing of the plant (18 September-28 October). During the shutdown for maintenance, an inspection of the steel members and parts of the core stabilizing structure was made in order to check for the familiar oxidation phenomena caused by CO 2 ; the results of the inspection were all satisfactory. Operation of the plant during 1974 was marked by numerous power cutbacks as a result of outages of the steam-raising units (leaks from the manifolds) and main turbines (inspection and repairs to the LP rotors). Since it was first brought into commercial operation, the plant has produced 13,4 thousand million kWh

  1. The performance trends of nuclear power plants worldwide

    Energy Technology Data Exchange (ETDEWEB)

    Glorian, D. [Electricite de France (EDF), 93 - Saint-Denis (France)

    2001-07-01

    Looking back to the worldwide operating experience feedback, which performance trends and conclusions could be drawn up? What is the specific situation of the French nuclear units, in comparison with the average worldwide performance? The performance of a unit or group of facilities is measured not only in technical terms (safety, availability, load control capability), but also from an economic and financial standpoint (operating and maintenance costs, fuel costs, etc). Performance in terms of radiological protection and on-the-job safety, as well as environmental protection, is also monitored in order to give the broadest possible overview of nuclear power plant performance. The main technical results are presented on the basis of selected performance indicators. The results obtained by French units are benchmarked against those of other PWR facilities in operation around the world, in accordance with comparisons made by the World Association of Nuclear Operators (WANO). (author)

  2. The performance trends of nuclear power plants worldwide

    International Nuclear Information System (INIS)

    Glorian, D.

    2001-01-01

    Looking back to the worldwide operating experience feedback, which performance trends and conclusions could be drawn up? What is the specific situation of the French nuclear units, in comparison with the average worldwide performance? The performance of a unit or group of facilities is measured not only in technical terms (safety, availability, load control capability), but also from an economic and financial standpoint (operating and maintenance costs, fuel costs, etc). Performance in terms of radiological protection and on-the-job safety, as well as environmental protection, is also monitored in order to give the broadest possible overview of nuclear power plant performance. The main technical results are presented on the basis of selected performance indicators. The results obtained by French units are benchmarked against those of other PWR facilities in operation around the world, in accordance with comparisons made by the World Association of Nuclear Operators (WANO). (author)

  3. Maintenance of nuclear power plants

    International Nuclear Information System (INIS)

    Lashgari, Farbod.

    1995-01-01

    This paper is about maintenance of nuclear power plants. In part one, the outage management of nuclear power plants has described. Meaning of the outage and objectives of outage management is given in introduction. The necessity of a long-term outage strategy is shown in chapter one. The main parts of an outage are as follows: Planning; Preparation; Execution, Each of them and also post-outage review have been explained in the followed chapters. Part two deals with technical details of main primary components of nuclear power plant type WWER. After an introduction about WWER reactors, in each chapter first the general and detailed description of main primary components has given and then their maintenance schedules and procedures. Chapter about reactor and steam generator is related to both types of WWER-440 and WWER-1000, but chapter about reactor coolant pump has specified to WWER-1000 to be more in details.(author)

  4. Cancer mortality among two different populations of French nuclear workers

    Energy Technology Data Exchange (ETDEWEB)

    Samson, Eric; Telle-Lamberton, Maylis; Caer-Lorho, Sylvaine [Institut de Radioprotection et de Surete Nucleaire (IRSN), Fontenay-aux-Roses (France). DRPH, SRBE, LEPID; and others

    2011-08-15

    The aim of this paper is to study the effect of external photon radiation on the mortality of two populations of French nuclear workers: workers exposed only to external photon radiation and workers potentially exposed also to internal contamination or to neutrons. External photon radiation has been measured through individual dosimeters. Potential exposure to internal contamination or to neutrons has been assessed by experts on the basis of quantitative measurements or of worksite and type of activity. The mortality observed in each population was compared with that expected from national mortality statistics, by computing standardized mortality ratios. Dose-effect relationships were analyzed through trend tests and log-linear Poisson regressions. 14,796 workers were exposed only to external photon radiation; 14,408 workers were also potentially exposed to internal radiation or to neutrons. Between 1968 and 1994, the number of deaths is respectively, 645 and 1,197. The mean external photon dose was respectively, 3.7 and 12.9 mSv. Similar Healthy Worker Effects were observed in the two populations (SMR = 0.59). SMR of 2.41 90% CI [1.39-3.90] was observed for malignant melanoma among workers of the second population. Significant dose-effect relationships were observed: among workers exposed only to external photon radiation for leukemia except CLL and in the other population, for cancers and other diseases related to tobacco or alcohol consumption. Results differed between the two populations. The increase in leukemia risk with dose in the first population will have to be confirmed with extended follow-up. In the other population, results may have been confounded by alpha-emitters inhalation, tobacco, or alcohol consumption.

  5. Cancer mortality among two different populations of French nuclear workers

    International Nuclear Information System (INIS)

    Samson, Eric; Telle-Lamberton, Maylis; Caer-Lorho, Sylvaine

    2011-01-01

    The aim of this paper is to study the effect of external photon radiation on the mortality of two populations of French nuclear workers: workers exposed only to external photon radiation and workers potentially exposed also to internal contamination or to neutrons. External photon radiation has been measured through individual dosimeters. Potential exposure to internal contamination or to neutrons has been assessed by experts on the basis of quantitative measurements or of worksite and type of activity. The mortality observed in each population was compared with that expected from national mortality statistics, by computing standardized mortality ratios. Dose-effect relationships were analyzed through trend tests and log-linear Poisson regressions. 14,796 workers were exposed only to external photon radiation; 14,408 workers were also potentially exposed to internal radiation or to neutrons. Between 1968 and 1994, the number of deaths is respectively, 645 and 1,197. The mean external photon dose was respectively, 3.7 and 12.9 mSv. Similar Healthy Worker Effects were observed in the two populations (SMR = 0.59). SMR of 2.41 90% CI [1.39-3.90] was observed for malignant melanoma among workers of the second population. Significant dose-effect relationships were observed: among workers exposed only to external photon radiation for leukemia except CLL and in the other population, for cancers and other diseases related to tobacco or alcohol consumption. Results differed between the two populations. The increase in leukemia risk with dose in the first population will have to be confirmed with extended follow-up. In the other population, results may have been confounded by alpha-emitters inhalation, tobacco, or alcohol consumption.

  6. Recent advances in nuclear power plant simulation

    International Nuclear Information System (INIS)

    Zerbino, H.; Plisson, P.; Friant, J.Y.

    1997-01-01

    The field of industrial simulation has experienced very significant progress in recent years, and power plant simulation in particular has been an extremely active area. Improvements may be recorded in practically all simulator subsystems. In Europe, the construction of new full- or optimized-scope nuclear power plant simulators during the middle 1990's has been remarkable intense. In fact, it is possible to identify a distinct simulator generation, which constitutes a new de facto simulation standard. Thomson Training and Simulation has taken part in these developments by designing, building, and validation several of these new simulators for Dutch, German and French nuclear power plants. Their characteristics are discussed in this paper. The following main trends may be identified: Process modeling is clearly evolving towards obtaining engineering-grade performance, even under the added constraints of real-time operation and a very wide range of operating conditions to be covered; Massive use of modern graphic user interfaces (GUI) ensures an unprecedented flexibility and user-friendliness for the Instructor Station; The massive use of GUIs also allows the development of Trainee Stations (TS), which significantly enhance the in-depth training value of the simulators; The development of powerful Software Development Environments (SDE) enables the simulator maintenance teams to keep abreast of modifications carried out in the reference plants; Finally, simulator maintenance and its compliance with simulator fidelity requirements are greatly enhanced by integrated Configuration Management Systems (CMS). In conclusion, the power plant simulation field has attained a strong level of maturity, which benefits its approximately forty years of service to the power generation industry. (author)

  7. Space nuclear reactor power plants

    International Nuclear Information System (INIS)

    Buden, D.; Ranken, W.A.; Koenig, D.R.

    1980-01-01

    Requirements for electrical and propulsion power for space are expected to increase dramatically in the 1980s. Nuclear power is probably the only source for some deep space missions and a major competitor for many orbital missions, especially those at geosynchronous orbit. Because of the potential requirements, a technology program on space nuclear power plant components has been initiated by the Department of Energy. The missions that are foreseen, the current power plant concept, the technology program plan, and early key results are described

  8. Pumps in nuclear power plants

    International Nuclear Information System (INIS)

    Kim, J.H.

    1991-01-01

    This paper reports that pumps play an important role in nuclear plant operation. For instance, reactor coolant pumps (RCPs) should provide adequate cooling for reactor core in both normal operation and transient or accident conditions. Pumps such as Low Pressure Safety Injection (LPSI) pump in the Emergency Core Cooling System (ECCS) play a crucial role during an accident, and their reliability is of paramount importance. Some key issues involved with pumps in nuclear plant system include the performance of RCP under two-phase flow conditions, piping vibration due to pump operating in two-phase flows, and reliability of LPSI pumps

  9. Nuclear power plant V-2

    International Nuclear Information System (INIS)

    1998-01-01

    The nuclear power plant Bohunice V -2 is briefly described. This NPP consists from two reactor units. Their main time characteristics are (Reactor Unit 1, Reactor Unit 2): beginning of construction - December 1976; first controlled reactor power - 7 August 1984, 2 August 1985; connection to the grid - 20 August 1984, 9 August 1985; commercial operation - 14 February 1985, 18 December 1985. This leaflet contains: NPP V-2 construction; Major technological equipment [WWER 440 V230 type reactor; Nuclear Power plant operation safety (Safety barriers; Safety systems [Active safety systems, Passive safety systems]); Centralized heat supply system; Scheme of Bohunice V-2 NPP and technical data

  10. Nuclear power plant

    International Nuclear Information System (INIS)

    Wieser, R.

    1979-01-01

    The reactor pressure vessel consists of two parts. A cylindrical lower part with a hemispherical steel roof is placed at some distance within an equally shaped pressure vessel of concrete. Both vessels are standing on a common bottom plate. The interspace is kept at subpressure. It serves to contain ring galleries, elevator shafts, and power plant components. (GL) [de

  11. Nuclear plant undergrounding

    International Nuclear Information System (INIS)

    Brown, R.C.; Bastidas, C.P.

    1978-01-01

    Under Section 25524.3 of the Public Resources Code, the California Energy Resources Conservation and Development Commission (CERCDC) was directed to study ''the necessity for '' and the effectiveness and economic feasibility of undergrounding and berm containment of nuclear reactors. The author discusses the basis for the study, the Sargent and Lundy (S and L) involvement in the study, and the final conclusions reached by S and L

  12. Challenges for new nuclear plants

    International Nuclear Information System (INIS)

    Bruschi, H.J.

    2000-01-01

    In the past 20 years, numerous new nuclear plant designs have been introduced in the hope of generating a mixture of features and benefits that generated enough enthusiasm amongst the utility industry decision makers to move forward with a new nuclear generation. Not only has there not been enough enthusiasm, there has been little interest in building new plants with advanced features, especially in the U.S. Compounding this predicament are the changing paradigms to which a new plant would be measured. The near hiatus on new plant orders is the clear cause of the significant consolidation in the nuclear industry. Regardless whether the disappearance of old-line nuclear companies is over or not, some paradigms for new generation designs are unmovable, while others are still under discussion as to their role in future plant designs. This paper will address those design goals that Westinghouse deems already having earned the rank of exemplar, and those still open to debate. Because it is my hope that this paper will lead to a fruitful discussion period, I will provide a list of what I feel are the champion design requirements, and those I consider the contenders. (author)

  13. Robotics for nuclear power plants

    International Nuclear Information System (INIS)

    Nakayama, Ryoichi; Kimura, Motohiko; Abe, Akira

    1993-01-01

    A continuing need exists for automatic or remote-controlled machines or robots which can perform inspection and maintenance tasks in nuclear power plants. Toshiba has developed several types of monofunctional and multi- functional robots for such purposes over the past 20 years, some of which have already been used in actual plants. This paper describes new multifunctional robots for inspection and maintenance. An inspection robot has been applied in an actual plant for two years for performance testing. Maintenance robots for grinding tasks have also been developed, which can be easily teleoperated by the operator using automatic control. These new robots are expected to be applied to actual inspection and maintenance work in nuclear power plants. (author)

  14. Submarine nuclear power plant

    International Nuclear Information System (INIS)

    Enohara, Masami; Araragi, Fujio.

    1980-01-01

    Purpose: To provide a ballast tank, and nuclear power facilities within the containment shell of a pressure resistance structure and a maintenance operator's entrance and a transmission cable cut-off device at the outer part of the containment shell, whereby after the construction, the shell is towed, and installed by self-submerging, and it can be refloated for repairs by its own strength. Constitution: Within a containment shell having a ballast tank and a pressure resisting structure, there are provided nuclear power facilities including a nuclear power generating chamber, a maintenance operator's living room and the like. Furthermore, a maintenance operator's entrance and exit device and a transmission cable cut-off device are provided within the shell, whereby when it is towed to a predetermined a area after the construction, it submerges by its own strength and when any repair inspection is necessary, it can float up by its own strength, and can be towed to a repair dock or the like. (Yoshihara, H.)

  15. Management of nuclear power plants lifetime

    International Nuclear Information System (INIS)

    Hutin, J.P.

    2006-01-01

    The factors influencing the management of the service life of nuclear power plants can be of various types and the 'heaviest' ones have to be managed through robust and explicit approaches involving all actors. However, the mastery of the service life starts with the mastery of the technical problems, in particular the physical aging of the facilities. This mastery requires to foresee and anticipate the problems and thus a good understanding of the phenomena involved. This article presents: 1 - the general problem of service life management: lifetime concept, situation of French power plants, service life management policy; 2 - aging mechanisms: embrittlement of steel under irradiation, swelling of materials, thermal aging, fatigue, stress corrosion, aqueous corrosion of metals, corrosion-erosion, mechanisms of concrete degradation, mechanisms of elastomers and polymers degradation, wear; 3 - non-replaceable parts: reactor vessel, containment building; 4 - replaceable parts: cables, instrumentation and control system, core internals, primary loop piping, auxiliary primary piping, pressurizer, primary pump, steam generator tubes, other Ni-Cr-Fe alloy parts, secondary loop piping, turbine, alternator; 5 - non-technical aspects: perenniality of the industrial support, evolution of safety requirements, public acceptance, economical aspects, knowledge and information systems; 6 - situation in foreign countries: status of the world nuclear park, lifetime notion in foreign countries, situation in the USA. (J.S.)

  16. Worldwide nuclear-plant performance

    International Nuclear Information System (INIS)

    Surrey, J.; Thomas, S.

    1980-01-01

    The authors compare the performance of different reactor systems to identify the determinants of plant performance, to examine the evidence of technological maturation, and to discover the principal causes of outage or unavailability. In the light of the findings, they discuss the implications for the UK regarding reactor choice and technology development. They make no judgements about the relative merits of nuclear and fossil-fuel plants, or about safety. (author)

  17. Decommissioning of nuclear power plants

    International Nuclear Information System (INIS)

    Friske, A.; Thiele, D.

    1988-01-01

    The IAEA classification of decommissioning stages is outlined. The international development hitherto observed in decommissioning of nuclear reactors and nuclear power stations is presented. The dismantling, cutting and decontamination methods used in the decommissioning process are mentioned. The radioactive wastes from decommissioning are characterized, the state of the art of their treatment and disposal is given. The radiation burdens and the decommissioning cost in a decommissioning process are estimated. Finally, some evaluation of the trends in the decommissioning process of nuclear power plants is given. 54 refs. (author)

  18. Nuclear power plant diagnostics

    International Nuclear Information System (INIS)

    Hollo, E.; Siklossy, P.

    1982-01-01

    The cooling circuit vibration diagnostic system of the Block 1 of the Paks nuclear power station is described. The automatic online vibration monitoring system consisting presently of 42 acceleration sensors and 9 pressure fluctuation sensors, which could be extended, performs both global and local inspection of the primary cooling circuit and its components. The offline data processing system evaluates the data for failure mode analysis. The software under development will be appropriate for partial preliminary identification of failure reasons during their initial phases. The installation experiences and the preliminary results during the hot operational testing of Block 1 are presented. (Sz.J.)

  19. French nuclear safety authorities: for a harmonization of nuclear safety at the European level

    International Nuclear Information System (INIS)

    Anon.

    2004-01-01

    The European Commission is working on 2 directives concerning nuclear energy: the first one is dedicated to nuclear safety and the second to the management of radioactive wastes and spent fuels. In the context of the widening of the European Union and of the inter-connection of the different electric power grids throughout Europe, the harmonization of the rules in the nuclear safety field is seen by manufacturers as a mean to achieve a fair competition between nuclear equipment supplying companies and by the French nuclear safety authorities (FNSA) as a mean to keep on improving nuclear safety and to be sure that competitiveness does not drive safety standards down. According to FNSA the 2 European directives could give a legal framework to the harmonization and should contain principles that reinforce the responsibility of each state. FNSA considers that the EPR (European pressurized water reactor) may be an efficient tool for the harmonization because of existing industrial cooperation programs between France and Germany and between France and Finland. (A.C.)

  20. Nuclear test - The French nuclear strike force in the 21. century: challenges, ambitions and strategy

    International Nuclear Information System (INIS)

    Wodka-Gallien, Philippe

    2014-01-01

    This bibliographical note presents a book in which the author, after having recalled the history of the French nuclear force since the first nuclear test in 1960, and outlined the fact that France has been living under the protection of its own nuclear deterrence force since that date, presents the components of this nuclear strike force with its four nuclear submarines equipped to launch new generation missiles, its fifty fighter bomber aircraft equipped with the ASMP-A missile. He presents and discusses the mission of this nuclear force, discusses the relevancy of the deterrence strategy in the present context, and the significance of such a strategy for a European country like France. He wanders whether this strike force is still affordable for our country, which can be its benefits, whether this arsenal remains useful as it has been designed in the Cold War context. He also discusses the disarmament perspectives in an unsteady international environment where power and arms race logics prevail again

  1. French experience in transient data collection and fatigue monitoring of PWR's nuclear steam supply system

    International Nuclear Information System (INIS)

    Sabaton, M.; Morilhat, P.; Savoldelli, D.; Genette, P.

    1995-10-01

    Electricite de France (EDF), the french national electricity company, is operating 54 standardized pressurizer water reactors. This about 500 reactor-years experience in nuclear stations operation and maintenance area has allowed EDF to develop its own strategy for monitoring of age-related degradations of NPP systems and components relevant for plant safety and reliability. After more than fifteen years of experience in regulatory transient data collection and seven years of successful fatigue monitoring prototypes experimentation, EDF decided to design a new system called SYSFAC (acronym for SYsteme de Surveillance en FAtigue de la Chaudiere) devoted to transient logging and thermal fatigue monitoring of the reactor coolant pressure boundary. The system is fully automatic and directly connected to the on-site data acquisition network without any complementary instrumentation. A functional transient detection module and a mechanical transient detection module are in charge of the general transient data collection. A fatigue monitoring module is aimed towards a precise surveillance of five specific zones particularly sensible to thermal fatigue. After the first step of preliminary studies, the industrial phase of the SYSFAC project is currently going on, with hardware and software tests and implementation. The first SYSFAC system will be delivered to the pilot power plant by the beginning of 1996. The extension to all EDF's nuclear 900 MW is planned after one more year of feedback experience. (authors). 12 refs., 3 figs

  2. Nuclear plant aging research program

    International Nuclear Information System (INIS)

    Eissenberg, D.M.

    1987-01-01

    The U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, has established the Nuclear Plant Aging Research (NPAR) program in its Division of Engineering Technology. Principal contractors for this program include Oak Ridge National Laboratory, Brookhaven National Laboratory, Idaho National Engineering Laboratory, and Pacific Northwest Laboratory. The program goals are: to identify and characterize time-dependent degradation (aging) of nuclear plant safety-related electrical and mechanical components which could lead to loss of safety function; to identify and recommend methods for detecting and trending aging effects prior to loss of safety function so that timely maintenance can be implemented; and to recommend maintenance practices for mitigating the effects of aging. Research activities include prioritization of system and component aging in nuclear plants, characterization of aging degradation of specific components including identification of functional indicators useful for trending degradation, and testing of practical methods and devices for measuring the functional indicators. Aging assessments have been completed on electric motors, snubbers, motor-operated valves, and check valves. Testing of trending methods and devices for motor-operated valves and check valves is in progress

  3. More than 30 years of opinion of French people on nuclear risks - Special release of the 2012 IRSN opinion survey

    International Nuclear Information System (INIS)

    El Jammal, Marie-Helene; Rollinger, Francois; Mur, Emmanuelle; Schuler, Matthieu; Tchernia, Jean-Francois

    2013-01-01

    Illustrated by many graphs and tables, this report comments and discusses the evolution of opinion surveys performed in France on the perception of nuclear risks through thirty annual IRSN opinion surveys. It appears that the opinion on nuclear is rather steady, and that French people have a rather rational perception of risk hierarchy. The first part outlines that unemployment is the main concern for French people, and that environmental concerns depend on current events. The second part analyses the perception of the nuclear risk with respect to other societal concerns and to other risks, and discusses the evolution of opinion from a quantitative to a qualitative sensitivity. The third part addresses the representations people have of nuclear activities and how they challenge the reality: perception of nuclear plants and of radioactive wastes, fear of a serious accident. The last part deals with issues related to responsibilities, abilities and governance: how actors of nuclear risk management are perceived, and expectations in terms of transparency and opinion plurality

  4. Underwater nuclear power plant structure

    International Nuclear Information System (INIS)

    Severs, S.; Toll, H.V.

    1982-01-01

    A structure for an underwater nuclear power generating plant comprising a triangular platform formed of tubular leg and truss members upon which are attached one or more large spherical pressure vessels and one or more small cylindrical auxiliary pressure vessels. (author)

  5. Would the re-structuration of the French nuclear industry be necessary?

    International Nuclear Information System (INIS)

    Finon, D.

    2011-04-01

    In this paper we analyze the recent propositions to reorganize the French industry of reactors in view to increase its efficiency on the export markets. Based on a critic of the choices of reactor technologies offered to export market, the Roussely report published on June 2010 recommends to crown the French electricity utility as the leader of a so-called 'French team' and to let him free to negotiate the sale of reactor of any technology that it would prefer as a Gen-2 reactor for example, and to place the French nuclear reactor constructor in a position of sub-contractor. The government has not followed this recommendation rightly. Based on an analysis of the changing world market of reactors, we defuse the criticism addressed to Areva on his choice, as well as the recommendation to open the present catalog of reactors to other models. The analysis leads to underline the importance of Areva's technological and industrial resources and the limited advantages of the EDF's skills in matter of architect-engineering and nuclear operation for winning export contracts. At the end of the day the mercantile approach which motivates the promoters of this tentative reform for competing with entrants prosing low cost nuclear reactors has been disapproved by the government, and that before the Fukushima accidents. We conclude by observing that only a flexible coordination between French industrial players would be useful for improving export performances of the French nuclear industry. (author)

  6. Nuclear power plant

    International Nuclear Information System (INIS)

    Igarashi, Yoko; Kato, Naoyoshi.

    1982-01-01

    Purpose: To decrease the reducing speed of nuclear reactor water level after the water level has reached a turbine trip level to trip the turbine thereby preventing cooling systems or the likes from undesired operation upon separation caused by the reduction of the reactor water level to a low water level before the water level control is switched to the manual control. Constitution: Two feedwater pumps arranged in parallel are operated in usual operation to feedwater to a BWR type reactor. If a trouble should occur in a feedwater controller to increase the feedwater rate and the reactor water level, one of the feedwater pumps is tripped by a signal from a feedwater pump trip device. Then, when the trip level is reached again the remaining pump is tripped. In this way, the sudden decrease in the feedwater rate and the reactor water level can be prevented. (Yoshino, Y.)

  7. Physical protection concepts of nuclear materials. The French experience

    International Nuclear Information System (INIS)

    Arnaud, G.; Artaud, R.

    1995-01-01

    As the nuclear energy was being developed, it appeared necessary to set up protections against its potential hazards, that should be more complete and elaborate than those implemented on the other industrial installations. This had to be done both in the safety field to prevent the environment and the populations from the consequences of severe casualties, and in the security field to avoid the risk of proliferation and limit to an acceptable level the results of voluntarily provoked accidents and sabotages. Taking advantage of the gathered experience, this document gives consideration to the concepts used in France in order to ensure the physical protection of the nuclear materials. The following topics are tackled: context inside which are envisaged the specific measures, coherence with the general dispositions taken to protect industrial installations, importance and limitations of the part played by the regulations, respective responsibilities of the plant operators and the public authorities, compromise between objectives in view and means to implement, adjustment between the physical protection system and the operating requirements. In addition, the ways in which these systems should be implemented are discussed, underlining the necessity to make progressive steps under a permanent will, in order, first, to update and bring under conformity the old installations, and second, to ensure the maintenance of the systems, taking account of the evolutions of needs and techniques. Those points are commented on examples taken among the different types of installations to be found in France, showing the differences in approach coming from the type and the age of the facilities, and giving the present trends for the new plants. (authors). 1 annexe

  8. Index of French nuclear literature: IBM 360 programmes for preparing the permuted index of French titles

    International Nuclear Information System (INIS)

    Chonez, Nicole

    1968-12-01

    This report contains the assembly list, the flow chart and some comments about each of the IBM 360 assembler language programmes used for preparing one of the subject indexes contained in the bibliographical bulletin entitled: 'Index de la Litterature nucleaire francaise'; this bulletin has been produced by the French C.E.A. since 1968. Only the processing phases from the magnetic tape file of the bibliographical references, assumed correct, to the printing out of the permuted index obtained with the French titles of the documents on the tape are considered here. This permuted index has the peculiarity of automatically regrouping synonyms and certain grammatical variations of the words. (author) [fr

  9. Quantitative assessment of the environmental footprint of the French nuclear fuel cycle by life cycle assessment

    International Nuclear Information System (INIS)

    Poinssot, Christophe; Bourg, Stephane; Ouvrier, Noel; Serp, Jerome

    2015-07-01

    Full text of publication follows: Nuclear energy contributes to most than 75% of the French electricity thanks to the operation of 58 generation 2 reactors located on 19 sites built from the 70's to the end of the 90's. France also developed for a long time a fully integrated nuclear industry covering the whole nuclear fuel cycle, from the ore mining to the fabrication of the fuel for the front-end, from the reprocessing up to the MOX fuel fabrication and storage facility and in the near-future geological repository for the back-end. This investment allows France to produce a low-carbon electricity with the second lowest GHG emissions intensity, in the range of 90 g CO 2 /KWh. Such a very beneficial figure is directly related to the high contribution of nuclear in the electricity mix combined with renewables energies, in particular hydro. Greenhouse gases emissions are very relevant to assess the respective influence on the global climate change, but they do not address the whole potential environmental impact of any activity. However, such a question is crucial for assessing the respective sustainability of such an activity, in particular nuclear energy which is thought to be very detrimental by a large part of the public opinion. In order to address this question, we developed a dedicated life cycle assessment (LCA) tools referred to as NELCAS, the specificity of which is to focus on the first order parameters and avoiding any 'black-box' effect which can exist in commercial LCA tool. Thanks to the recent transparency and nuclear safety law (2006), in- and out- fluxes of matter and energy for any of the fuel cycle facilities are now publicly available. We hence used this significant set of measured data to feed our model and assess the most usual environmental indicators such as land use, different types of atmospheric emissions (GHG, SOx, NOx, particles...) and aqueous release (chemical effluents, eutrophication potential,...)... We also

  10. French PWR safety philosophy

    International Nuclear Information System (INIS)

    Conte, M.

    1986-05-01

    Increasing knowledge and lessons learned from starting and operating experience of French nuclear power plants, completed by the experience learned from the operation of foreign reactors, has contributed to the improvement of French PWR design and safety philosophy. Based on a deterministic approach, the French safety analysis was progressively completed by a probabilistic approach, each of them having possibilities and limits. As a consequence of the global risk objective set in 1977 for nuclear reactors, safety analysis was extended to the evaluation of events more complex than the conventional ones, and later to the evaluation of the feasibility of the offsite emergency plans in case of severe accidents

  11. Nuclear power plant

    International Nuclear Information System (INIS)

    Nishio, Masahide

    1986-01-01

    Purpose: To provide a constitution capable of previously and reliably preventing radioactivity from releasing into the atmosphere upon occurrence of main steam pipe rupture accidents in a main steam tunnel chamber. Constitution: The outer circumference at the penetration portion of a nuclear reactor container is tightly closed and the main steam tunnel chamber has a tightly closed vessel structure, which is cooled by a local cooler during normal operation. The main steam tunnel chamber is in communication with a pressure control chamber by way of a release line and a releaf valve is disposed at the midway of the release line. Upon occurrence of rupture accident to the main steam pipes in the main steam tunnel chamber, while steams are issued from the ruptured portion, they are discharged through the release line to the suppression chamber and condensated. As a result, excess pressure in the main steam tunnel can be prevented and when the rupture accident is detected, the main steam isolation valve is closed rapidly to interrupt the steam feeding, whereby the steam released from the ruptured pipeways is stopped to avoid the radioactivity release to the atmosphere. (Kamimura, M.)

  12. Passive Nuclear Plants Program (UPDATE)

    International Nuclear Information System (INIS)

    Chimeno, M. A.

    1998-01-01

    The light water passive plants program (PCNP), today Advanced Nuclear Power Plants Program (PCNA), was constituted in order to reach the goals of the Spanish Electrical Sector in the field of advanced nuclear power plants, optimize the efforts of all Spanish initiatives, and increase joint presence in international projects. The last update of this program, featured in revision 5th of the Program Report, reflects the consolidation of the Spanish sector's presence in International programs of the advanced power plants on the basis of the practically concluded American ALWR program. Since the beginning of the program , the PCNP relies on financing from the Electrical sector, Ocide, SEPI-Endesa, Westinghouse, General Electric, as well as from the industrial cooperators, Initec, UTE (Initec- Empresarios Agrupados), Ciemat, Enusa, Ensa and Tecnatom. The program is made up of the following projects, already concluded: - EPRI's Advanced Light Water Plants Certification Project - Westinghouse's AP600 Project - General Electric's SBWR Project (presently paralyzed) and ABWR project Currently, the following project are under development, at different degrees of advance: - EPP project (European Passive Plant) - EBWR project (European Advanced Boiling Water Reactor)

  13. French research in the field of nuclear agronomy

    International Nuclear Information System (INIS)

    Guerin De Montgareuil, P.

    1964-01-01

    This report presents a survey of the most important work in the field of nuclear agronomy carried out in France since the second international conference, ranging from pure research to the most direct application. As the programmes develop, so to an ever decreasing degree does this differentiation cover the distinction made in the report between the biological radiations effects and the other uses of nuclear techniques. Thus research on agricultural radio-genetics is carried on in two directions: from the theoretical and methodological angle, with comparative studies of the action of various types of radiation, the influence of dose rate and temperature, the action of chemical mutation agents, the production of chimera by gamma irradiation; and on the practical side, leading to the creation of new, hardier or earlier varieties (rice, millet, ground-nuts). Problems of pest destruction (eradication) and the preservation of foodstuffs by irradiation are also tackled by widely varied means and for totally different purposes. One operation consisting of a simple irradiation (moist seeds, potatoes...) will sometimes be associated with original studies of a biochemical or microbiological nature (for example: decomposition of starch, glucide metabolism of irradiated tubers, radiation resistance of yeasts). The nuclear technique side is represented mainly by radioisotopes (carbon 14, phosphorus 32, sulphur 35, calcium 45, potassium 42, copper 64, gold 198) and stable isotopes analysed by mass spectrometer (nitrogen 15, oxygen 18) or by neutron activation (boron 10). The studies mentioned refer to problems on different levels concerning plant physiology, agrology, agricultural entomology and zootechny. Results obtained from measurements of the humidity (neutron thermalization) and density (gamma diffusion) of a soil are also given. Numerous organisations take part in these various research programmes, each according to its speciality: cooperative private enterprise

  14. Relative costs to nuclear plants: international experience

    International Nuclear Information System (INIS)

    Souza, Jair Albo Marques de

    1992-03-01

    This work approaches the relative costs to nuclear plants in the Brazil. It also presents the calculation methods and its hypothesis to determinate the costs, and the nacional experience in costs of investment, operating and maintenance of the nuclear plants

  15. Cooling water recipients for nuclear power plants

    International Nuclear Information System (INIS)

    Dahl, F.-E.; Saetre, H.J.

    1971-10-01

    The hydrographical and hydrological conditions at 17 prospective nuclear power plant sites in the Oslofjord district are evaluated with respect to their suitability as recipients for thermal discharges from nuclear power plants. No comparative evaluations are made. (JIW)

  16. Quality assurance of the French nuclear market - IAEA code and standardization

    International Nuclear Information System (INIS)

    Pavaux, F.

    1980-06-01

    The fact that Quality Assurance was imported from abroad and our reticence to reach agreement on single and accurate texts explain, if not excuse, the abundance of reference requirements existing on the French nuclear market with respect to Quality Assurance Programmes. But all is not lost, since the IAEA Good Practice Code is perhaps the solution that, in a few years time, will enable all French industrialists to work and be assessed by their customers, according to the same reference text [fr

  17. Nuclear power plant

    International Nuclear Information System (INIS)

    Inami, Ichiro; Kobayashi, Minoru.

    1995-01-01

    In a condensate cleanup system and a reactor water cleanup system of a BWR-type reactor, in which primary coolants flow, there is disposed a filtering and desalting device using hollow thread membrane filter and ion exchange resin for a condensate cleanup system, and using a high temperature filter made of a metal, a metal oxide or ceramics as a filtering material and a precoat filter made of a powdery ion exchange resin as a filtering material for a reactor water cleanup system. This can completely remove cruds generated in the condensate system. Since the reactor water cleanup system comprises the powdery resin precoat-type filtering and desalting device and the high temperature filter using ceramics, ionic impurities such as radioactive materials can be removed. Accordingly, cruds are not carried into the inside of the reactor, and since the radioactive concentration in the reactor water is reduced, radiation exposure upon periodical inspection can be minimized almost to zero, to attain a clean plant. (T.M.)

  18. Safety evaluation of the nuclear power plant at Cattenom

    International Nuclear Information System (INIS)

    Anon.

    1987-01-01

    This is a systematic compilation of the material which was dealt with at the level of the German-French Commission (on questions of the safety of nuclear installations) in this discussions about the nuclear power plant at Cattenom. As a supplement to the report published already in 1982, the Commission has officially released its deliberation results on the subjects constructive safety measures, radiological effects, and precautions in case of an emergency. The allegations according to which the installation is wanting in safety are countered by the joint statement of the chairmen of GPR (Permanent Group on Reactors) and RSK (German Commission on Reactor Safety) of August 29, 1986. (HSCH) [de

  19. Incidence of childhood leukemia around French nuclear sites between 1990 and 1998

    International Nuclear Information System (INIS)

    White-Koning, M.; Hemon, D.; Goubin, A.; Clavel, J.; Laurier, D.; Tirmarche, M.; Jougla, E.

    2006-01-01

    The works presented here constitute the first systematic study of the incidence of childhood leukemia around the whole of French nuclear facilities. Globally, the incidence of childhood leukemia does not diverge significantly of the expected incidence during the period 1990-1998. It does not show a decrease of S.I.R. (standardized incidence ratio) in function of the distance from child's home to the nuclear site whatever be the age. This study represents the first analysis of the incidence of leukemia focusing on 29 French nuclear sites, including the whole of the 19 C.N.P.E. ( nuclear power plants that produce electric power), and is based on incidence data rather than mortality. The period, the age groups and the studied area have been all chosen a priori, that gives a statistical validity to the results. The estimation of population at risk have been made with several different methods of interpolation in order to check the stability of estimations. The different methods of statistical analysis used have lead to extremely close results, reinforcing our confidence in the reliability of our estimations. The excess of leukemia incidence observed at Chinon and Civaux and the deficit observed at Bruyere/Saclay/Fontenay loose their statistical significance when the correction of Bonferroni is applied. So, the global analysis of the 29 sites and the analysis by site have not shown statistically significant difference between the numbers of observed and expected cases. The study of the 19 C.N.P.E. gave same results, even in taken into account their electric power or their year of service. The possibility of confounding factors has been excluded. The power of the study to detect excess incidence and a decrease of S.I.R. with distance from the site was examined under different alternative hypotheses through simulation methods. For values of S.I.R. near the site (0-5 km) between 1.5 and 2 and a risk of error of 5%, the power of the study is between 96% and 100% depending

  20. Advanced nuclear plant control complex

    International Nuclear Information System (INIS)

    Scarola, K.; Jamison, S.; Manazir, R.M.; Rescorl, R.L.; Harmon, D.L.

    1991-01-01

    An advanced control room complex for a nuclear power plant, including a discrete indicator and alarm system which is nuclear qualified for rapid response to changes in plant parameters and a component control system which together provide a discrete monitoring and control capability at a panel in the control room. A separate data processing system, which need not be nuclear qualified, provides integrated and overview information to the control room and to each panel, through CRTs and a large, overhead integrated process status overview board. The discrete indicator and alarm system and the data processing system receive inputs from common plant sensors and validate the sensor outputs to arrive at a representative value of the parameter for use by the operator during both normal and accidental conditions, thereby avoiding the need for him to assimilate data from each sensor individually. The integrated process status board is at the apex of an information hierarchy that extends through four levels and provides access at each panel to the full display hierarchy. The control room panels are preferably of a modular construction, permitting the definition of inputs and outputs, the man machine interface, and the plant specific algorithms, to proceed in parallel with the fabrication of the panels, the installation of the equipment and the generic testing thereof. (author)

  1. Docommissioning of nuclear power plants

    International Nuclear Information System (INIS)

    Essmann, J.

    1981-01-01

    The German utilities operating nuclear power plants have long concerned themselves with aspects of decommissioning and for this purpose an engineering company was given a contract to study the entire spectrum of decommissioning. The results of this study have been available in autumn 1980 and it is possible to discuss all the aspects of decommissioning on a new basis. Following these results no change in the design concept of LWR nuclear power plants in operation or under construction is necessary because the techniques, necessary for decommissioning, are fully available today. The technical feasibility of decommissioning for power plants of Biblis A and KRB type has been shown in detail. The calculations of the quantity of waste produced during removal of a nuclear power plant could be confirmed and it could be determined with high procedure. The radiation dose to the decommissioning personnel is in the range of the radiation protection regulations and is in the same range as the radiation dose to the personnel within a yearly inservice inspection. (AF)

  2. Fire prevention in nuclear plants

    International Nuclear Information System (INIS)

    Cayla, J.P.; Jacquet-Francillon, J.; Matarozzo, F.

    2014-01-01

    About 80 fire starts are reported in EDF nuclear power plants every year but only 3 or 4 turn into a real fire and none has, so far, has led to a major safety failure of a nuclear plant. A new regulation has been implemented in july 2014 that strengthens the concept of defense in depth, proposes an approach that is proportionate to the stakes and risks, this proportionality means that the requirements for a power reactor are not the same as for a nuclear laboratory, and imposes an obligation or result rather than of means. The second article deals with the fire that broke out in the waste silo number 130 at La Hague plant in january 1981. The investigation showed that the flammability of the silo content had been underestimated. The third article presents the consequences of the fire that broke out in a power transformer at the Cattenom plant in june 2013. The fire was rapidly brought under control thanks to the immediate triggering of the emergency plan. The article details also the feedback experience of this event. (A.C.)

  3. SECURE nuclear district heating plant

    International Nuclear Information System (INIS)

    Nilsson; Hannus, M.

    1978-01-01

    The role foreseen for the SECURE (Safe Environmentally Clean Urban REactor) nuclear district heating plant is to provide the baseload heating needs of primarily the larger and medium size urban centers that are outside the range of waste heat supply from conventional nuclear power stations. The rationale of the SECURE concept is that the simplicity in design and the inherent safety advantages due to the use of low temperatures and pressures should make such reactors economically feasible in much smaller unit sizes than nuclear power reactors and should make their urban location possible. It is felt that the present design should be safe enough to make urban underground location possible without restriction according to any criteria based on actual risk evaluation. From the environmental point of view, this is a municipal heat supply plant with negligible pollution. Waste heat is negligible, gaseous radioactivity release is negligible, and there is no liquid radwaste release. Economic comparisons show that the SECURE plant is competitive with current fossil-fueled alternatives. Expected future increase in energy raw material prices will lead to additional energy cost advantages to the SECURE plant

  4. Atucha I nuclear power plant transients analysis

    International Nuclear Information System (INIS)

    Castano, J.; Schivo, M.

    1987-01-01

    A program for the transients simulation thermohydraulic calculation without loss of coolant (KWU-ENACE development) to evaluate Atucha I nuclear power plant behaviour is used. The program includes systems simulation and nuclear power plants control bonds with real parameters. The calculation results show a good agreement with the output 'protocol' of various transients of the nuclear power plant, keeping the error, in general, lesser than ± 10% from the variation of the nuclear power plant's state variables. (Author)

  5. Safety in nuclear power plants

    International Nuclear Information System (INIS)

    Koeberlein, K.

    1987-01-01

    In nuclear power plants large amounts of radioactive fission products ensue from the fission of uranium. In order to protect the environment, the radioactive material is confined in multiple 'activity barriers' (crystal matrix of the fuel, fuel cladding, coolant boundary, safety containment, reactor building). These barriers are protected by applying a defense-in-depth concept (high quality requirements, protection systems which recognize and terminate operational incidents, safety systems to cope with accidents). In spite of a favorable safety record of German nuclear power plants it is obvious - and became most evident by the Chernobyl accident - that absolute safety is not achievable. At Chernobyl, however, design disadvantages of that reactor type (like positive reactivity feedback of coolant voiding, missing safety containment) played an important role in accident initiation and progression. Such features of the Russian 'graphite-moderated pressure tube boiling water reactor' are different from those of light water reactors operating in western countries. The essential steps of the waste management of the nuclear fuel cycle ('Entsorgung') are the interim storage, the shipment, and the reprocessing of the spent fuel and the final repository of radioactive waste. Reprocessing means the separation of fossil material (uranium, plutonium) from radioactive waste. Legal requirements for radiological protection of the environment, which are identical for nuclear power plants and reprocessing plant, are complied with by means of comprehensive filter systems. Safety problems of a reprocessing plant are eased considerably by the fact that system pressures, process temperatures and energy densities are low. In order to confine the radioactive waste from the biosphere for a very long period of time, it is to be discarded after appropriate treatment into the deep geological underground of salt domes. (orig./HP) [de

  6. Fighting fires in nuclear plants

    International Nuclear Information System (INIS)

    Fantom, L.F.; Weldon, G.E.

    1978-01-01

    Since the Browns Ferry incident, the specter of fires at nuclear plants has been the focus of attention by NRC, the utilities, and the public. There are sophisticated hardware and software available - in the form of fire-protection systems and equipment and training and fire-protection programs. Potential fire losses at nuclear faclities can be staggering. Thus, it behooves all those involved to maximize fire-protection security while simultaneously minimizing the chance of human error, which cancels out the effectiveness of the most up-to-date protective systems and devices

  7. The operation of contractors on nuclear sites: French regulations

    International Nuclear Information System (INIS)

    Mayoux, J.C.; Derche, B.

    1985-01-01

    The first purpose of this paper is to show how the French common law -as it results from the code of labour and holdings of the courts- deals with the intervention of contractors. The second part analyses the special regulations in force to ensure radiation protection [fr

  8. QA programs in nuclear power plants

    International Nuclear Information System (INIS)

    Ellingson, A.C.

    1976-01-01

    As an overview of quality assurance programs in nuclear power plants, the energy picture as it appears today is reviewed. Nuclear power plants and their operations are described and an attempt is made to place in proper perspective the alleged ''threats'' inherent in nuclear power. Finally, the quality assurance programs being used in the nuclear industry are described

  9. 4. Nuclear power plant component failures

    International Nuclear Information System (INIS)

    1990-01-01

    Nuclear power plant component failures are dealt with in relation to reliability in nuclear power engineering. The topics treated include classification of failures, analysis of their causes and impacts, nuclear power plant failure data acquisition and processing, interdependent failures, and human factor reliability in nuclear power engineering. (P.A.). 8 figs., 7 tabs., 23 refs

  10. Maintenance of Nuclear Power Plants

    International Nuclear Information System (INIS)

    Quintana, J. M.; Sanchez, J. T.

    2002-01-01

    With this article about the Maintenance in nuclear power plants we will try to give to see the importance of this kind of installations but the problems found by the clients and contractors to face it, and some possible solutions to improve it. It is necessary to understand this problem like something inner to the installation and must be considerate like a benefit for the same. Of course, there must be adequate Sevices Companies in direct relation with the installation that take the responsibility of assuming and understanding the correct fulfillment of the fixed milestones to get the optimal working of the whole plant systems. (Author)

  11. Nuclear power plant life management

    International Nuclear Information System (INIS)

    Rorive, P.; Berthe, J.; Lafaille, J.P.; Eussen, G.

    1998-01-01

    Several definitions can be given to the design life of a nuclear power plant just as they can be attributed to the design life of an industrial installation: the book-keeping life which is the duration of the provision for depreciation of the plant, the licensed life which corresponds to the duration for which the plant license has been granted and beyond which a new license should be granted by the safety authorities, the design life which corresponds to the duration specified for ageing and fatigue calculations in the design of some selected components during the plant design phase, the technical life which is the duration of effective technical operation and finally the economic life corresponding to the duration of profitable operation of the plant compared with other means of electricity production. Plant life management refers to the measures taken to cope with the combination of licensed, design, technical and economical life. They can include repairs and replacements of components which have arrived to the end of their life due to known degradation processes such as fatigue, embrittlement, corrosion, wear, erosion, thermal ageing. In all cases however, it is of great importance to plan the intervention so as to minimise the economic impact. Predictive maintenance is used together with in-service inspection programs to fulfil this goal. The paper will go over the methodologies adopted in Belgium in all aspects of electrical, mechanical and civil equipment for managing plant life. (author)

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

    International Nuclear Information System (INIS)

    Borotra, F.; Lepage, C.

    1996-01-01

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

  13. Expert robots in nuclear plants

    International Nuclear Information System (INIS)

    Byrd, J.S.; Fisher, J.J.; DeVries, K.R.; Martin, T.P.

    1987-01-01

    Expert robots enhance a safety and operations in nuclear plants. E.I. du Pont de Nemours and Company, Savannah River Laboratory, is developing expert mobile robots for deployment in nuclear applications at the Savannah River Plant. Knowledge-based expert systems are being evaluated to simplify operator control, to assist in navigation and manipulation functions, and to analyze sensory information. Development work using two research vehicles is underway to demonstrate semiautonomous, intelligence, expert robot system operation in process areas. A description of the mechanical equipment, control systems, and operating modes is presented, including the integration of onboard sensors. A control hierarchy that uses modest computational methods is being used to allow mobile robots to autonomously navigate and perform tasks in known environments without the need for large computer systems

  14. Expert robots in nuclear plants

    International Nuclear Information System (INIS)

    Byrd, J.S.; Fisher, J.J.; DeVries, K.R.; Martin, T.P.

    1987-01-01

    Expert robots will enhance safety and operations in nuclear plants. E. I. du Pont de Nemours and Company, Savannah River Laboratory, is developing expert mobile robots for deployment in nuclear applications at the Savannah River Plant. Knowledge-based expert systems are being evaluated to simplify operator control, to assist in navigation and manipulation functions, and to analyze sensory information. Development work using two research vehicles is underway to demonstrate semiautonomous, intelligent, expert robot system operation in process areas. A description of the mechanical equipment, control systems, and operating modes is presented, including the integration of onboard sensors. A control hierarchy that uses modest computational methods is being used to allow mobile robots to autonomously navigate and perform tasks in known environments without the need for large computer systems

  15. Nuclear power plants and environment

    International Nuclear Information System (INIS)

    Agudo, E.G.; Penteado Filho, A.C.

    1980-01-01

    The question of nuclear power plants is analysed in details. The fundamental principles of reactors are described as well as the problems of safety involved with the reactor operation and the quantity and type of radioactive released to the environment. It shows that the amount of radioactive is very long. The reactor accidents has occurred, as three mile island, are also analysed. (M.I.A.)

  16. Operation of nuclear power plants

    International Nuclear Information System (INIS)

    Severa, P.

    1988-04-01

    The textbook for training nuclear power plant personnel is centred on the most important aspects of operating modes of WWER-440 reactors. Attention is devoted to the steady state operation of the unit, shutdown, overhaul with refuelling, physical and power start-up. Also given are the regulations of shift operation and the duties of individual categories of personnel during the shift and during the change of shifts. (Z.M.). 3 figs., 1 tab

  17. The French nuclear policy. A model for security policy in North-East Asia

    International Nuclear Information System (INIS)

    Choe, K.

    1998-01-01

    Between the end of the second world war and the collapse of the Berlin wall, the French diplomacy was based on the nuclear policy in a solid and coherent way. This nuclear policy was an 'incarnation' of the national security conception, allowing France to recover its political, military and economical rank on the international scene. The most important characteristic of the French nuclear policy concerns the commercialization of the nuclear energy which aims to ensuring the national security through the building up of a financial, technological and political 'reserve'. In front of the domination of the USA and USSR during the cold war era, NE Asia had a similar geostrategic configuration as Western Europe. It concerns in particular the massive application of nuclear energy for both military and industrial purposes. The bases of the security policy in this region refers to the real use of the nuclear weapon by the USA against Japan in 1945. The French nuclear policy may be considered as a model for the building of the security policy of NE Asia, in particular through the commercialization of the nuclear technology between the countries in concern. This nuclear approach would allow the countries of these region to change their present day national defense policy into an economical and military cooperation. (J.S.)

  18. Nuclear power plants - Quality assurance

    International Nuclear Information System (INIS)

    1980-01-01

    This International Standard defines principles for the establishment and implementation of quality assurance programmes during all phases of design, procurement, fabrication, construction, commissioning, operation, maintenance and decommissioning of structures, systems and components of nuclear power plants. These principles apply to activities affecting the quality of items, such as designing, purchasing, fabricating, handling, shipping, storing, cleaning, erecting, installing, testing, commissioning, operating, inspecting, maintaining, repairing, refuelling and modifying and eventually decommissioning. The manner in which the principles described in this document will be implemented in different organizations involved in a specific nuclear power project will depend on regulatory and contractual requirements, the form of management applied to a nuclear power project, and the nature and scope of the work to be performed by different organizations

  19. Community attitudes toward nuclear plants

    International Nuclear Information System (INIS)

    Peelle, E.

    1982-01-01

    Among the many effects of the accident at Three Mile Island are impacts upon other communities that currently host nuclear-power reactors. Because studies on communities' reactions not immediately available, this chapter reviews existing studies and speculates about possible effects. The patterns and variations in impacts on and responses of nuclear host communities have been the subject of studies at Oak Ridge National Laboratory (Oak Ridge, Tennessee) since 1972. This essay presents results from four post-licensing studies of host communities - Plymouth, Massachusetts, and Waterford, Connecticut (PL-1), and Brunswick, North Carolina, and Appling-Toombs counties, Georgia (PL-2) - along with case study and attitude survey information from two additional communities in which reactors are under construction: Hartsville, Tennessee, and Cherokee County, South Carolina. Differences and similarities between the sites have been assessed in terms of differences in input and social structure; factors affecting the generally favorable attitudes toward local nuclear plants are discussed

  20. Nuclear plant analyzer desktop workstation

    International Nuclear Information System (INIS)

    Beelman, R.J.

    1990-01-01

    In 1983 the U.S. Nuclear Regulatory Commission (USNRC) commissioned the Idaho National Engineering Laboratory (INEL) to develop a Nuclear Plant Analyzer (NPA). The NPA was envisioned as a graphical aid to assist reactor safety analysts in comprehending the results of thermal-hydraulic code calculations. The development was to proceed in three distinct phases culminating in a desktop reactor safety workstation. The desktop NPA is now complete. The desktop NPA is a microcomputer based reactor transient simulation, visualization and analysis tool developed at INEL to assist an analyst in evaluating the transient behavior of nuclear power plants by means of graphic displays. The NPA desktop workstation integrates advanced reactor simulation codes with online computer graphics allowing reactor plant transient simulation and graphical presentation of results. The graphics software, written exclusively in ANSI standard C and FORTRAN 77 and implemented over the UNIX/X-windows operating environment, is modular and is designed to interface to the NRC's suite of advanced thermal-hydraulic codes to the extent allowed by that code. Currently, full, interactive, desktop NPA capabilities are realized only with RELAP5

  1. Occupational dose control in Nuclear Power Plants

    International Nuclear Information System (INIS)

    Viktorsson, C.; Lochard, J.; Benedittini, M.; Baum, J.; Khan, T.A.

    1990-01-01

    Reduction in occupational exposure at nuclear power plants is desirable not only in the interest of the health and safety of plant personnel, but also because it enhances the safety and reliability of the plants. This report summarises the current trends of doses to workers at nuclear power plants and the achievements and developments regarding methods for their reduction

  2. Sabotage at Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Purvis, James W.

    1999-07-21

    Recently there has been a noted worldwide increase in violent actions including attempted sabotage at nuclear power plants. Several organizations, such as the International Atomic Energy Agency and the US Nuclear Regulatory Commission, have guidelines, recommendations, and formal threat- and risk-assessment processes for the protection of nuclear assets. Other examples are the former Defense Special Weapons Agency, which used a risk-assessment model to evaluate force-protection security requirements for terrorist incidents at DOD military bases. The US DOE uses a graded approach to protect its assets based on risk and vulnerability assessments. The Federal Aviation Administration and Federal Bureau of Investigation conduct joint threat and vulnerability assessments on high-risk US airports. Several private companies under contract to government agencies use formal risk-assessment models and methods to identify security requirements. The purpose of this paper is to survey these methods and present an overview of all potential types of sabotage at nuclear power plants. The paper discusses emerging threats and current methods of choice for sabotage--especially vehicle bombs and chemical attacks. Potential consequences of sabotage acts, including economic and political; not just those that may result in unacceptable radiological exposure to the public, are also discussed. Applicability of risk-assessment methods and mitigation techniques are also presented.

  3. Nuclear plant life cycle costs

    International Nuclear Information System (INIS)

    Durante, R.W.

    1994-01-01

    Life cycle costs of nuclear power plants in the United States are discussed. The author argues that these costs have been mishandled or neglected. Decommissioning costs have escalated, e.g. from $328 per unit in 1991 to $370 in 1993 for the Sacramento Municipal Utility District, though they still only amount to less than 0.1 cent per kWh. Waste management has been complicated in the U.S. by the decision to abandon civilian reprocessing; by the year 2000, roughly 30 U.S. nuclear power units will have filled their storage pools; dry storage has been delayed, and will be an expense not originally envisaged. Some examples of costs of major component replacement are provided. No single component has caused as much operational disruption and financial penalties as the steam generator. Operation and maintenance costs have increased steadily, and now amount to more than 70% of production costs. A strategic plan by the Nuclear Power Oversight Committee (of U.S. utilities) will ensure that the ability to correctly operate and maintain a nuclear power plant is built into the original design. 6 figs

  4. Sabotage at Nuclear Power Plants

    International Nuclear Information System (INIS)

    Purvis, James W.

    1999-01-01

    Recently there has been a noted worldwide increase in violent actions including attempted sabotage at nuclear power plants. Several organizations, such as the International Atomic Energy Agency and the US Nuclear Regulatory Commission, have guidelines, recommendations, and formal threat- and risk-assessment processes for the protection of nuclear assets. Other examples are the former Defense Special Weapons Agency, which used a risk-assessment model to evaluate force-protection security requirements for terrorist incidents at DOD military bases. The US DOE uses a graded approach to protect its assets based on risk and vulnerability assessments. The Federal Aviation Administration and Federal Bureau of Investigation conduct joint threat and vulnerability assessments on high-risk US airports. Several private companies under contract to government agencies use formal risk-assessment models and methods to identify security requirements. The purpose of this paper is to survey these methods and present an overview of all potential types of sabotage at nuclear power plants. The paper discusses emerging threats and current methods of choice for sabotage--especially vehicle bombs and chemical attacks. Potential consequences of sabotage acts, including economic and political; not just those that may result in unacceptable radiological exposure to the public, are also discussed. Applicability of risk-assessment methods and mitigation techniques are also presented

  5. Raison d'etat and popular response: the resumption of French nuclear testing in the South Pacific

    International Nuclear Information System (INIS)

    Wooler, Derek.

    1995-01-01

    This Current Issues Brief highlights the issues surrounding several aspects of resumed French nuclear testing series. The French perspective, and the nature of French nuclear weapons program, are discussed, as is the impact of test explosions on the ecology of the Mururoa test site. Also discussed are the development of testing, the pressures that have led to its resumption following the suspension in 1992 and the French position regarding the nuclear weapons control regime; the development of attitudes to French testing in regional countries and the response of their governments to the resumption; the scope for, and restrictions on, as well as the use of trade sanctions as a response in the regulatory environment under the World Trade Organisation. The two appendices give a summary of all known nuclear tests since 1945 as well as details of all French tests. 36 refs., 1 tab

  6. Status of the French nuclear high level waste disposal

    International Nuclear Information System (INIS)

    Sombret, C.

    1985-09-01

    French research on high level waste processing has led to the development of industrial vitrification facilities. Borosilicate glass is still being investigated for its long-term storage properties, since it is itself a component of the containment system. The other constituents of this system, the engineered barriers, are also being actively investigated. The geological barrier is now being assessed using a methodology applicable to various types of geological formations, and final site qualification should be possible before the end of 1992

  7. To benefit from the market opportunities, the French nuclear sector must accelerate its change

    International Nuclear Information System (INIS)

    Therond-Koos, C.

    2016-01-01

    An independent think-tank gives its meaning on the future of nuclear energy and on the assets of the French nuclear industry to obtain contracts and tenders in international markets. Nuclear power appears to be a necessary passage for a quick transition towards a no-carbon emitting power production. Between 2006 and 2015 the construction of about 80 reactors was launched and IAEA expects a growth rate of nuclear power production somewhere between +50 and +100% by 2030. 6 countries: United States, Russia, France, Japan, China and South-Korea have developed a nuclear industry and are able to export reactor technology. Concerning reactor construction, France's share of the world market is about 10% and France ranks third behind Russia (33%) and American-Japanese companies (33%). China will be soon a reactor supplier. On the nuclear fuel business, AREVA is also a major player. At the world scale only a few companies operate in the reactor construction field because of technological, industrial but also regulation challenges. The Hinkley Point C project is crucial for the French nuclear industry because of the attractiveness of the contract and mainly because it is an opportunity to show the ability of the French nuclear enterprises to end projects on time and it may be considered a reference to win other export contracts. (A.C.)

  8. The safety of nuclear power plants during the year 2000 transition

    International Nuclear Information System (INIS)

    1999-01-01

    The French nuclear power plants had to face two main type of problems during the year 2000 transition: a generalized power grid incident and a dysfunction of computer-based or automated systems in nuclear installations. This dossier analyzes both possible incidents and describes the evaluation made by the French Institute of Nuclear Protection and Safety (IPSN) of the different incident scenarios elaborated by Electricite de France (EdF) for its installations in anticipation of the transition. The problem of the year 2000 transition in other countries is briefly evoked. (J.S.)

  9. Nuclear Power Plants in the World

    International Nuclear Information System (INIS)

    2003-01-01

    The Japan Atomic Industrial Forum (JAIF) used every year to summarize a trend survey on the private nuclear power plants in the world in a shape of the 'Nuclear power plants in the world'. In this report, some data at the end of 2002 was made up on bases of answers on questionnaires from 65 electric power companies and other nuclear organizations in 28 countries and regions around the world by JAIF. This report is comprised of 19 items, and contains generating capacity of the plants; current status of Japan; trends of generating capacity of operating the plants, the plant orders and generating capacity of the plants; world nuclear capacity by reactor type; status of MOX use in the world; location of the plants; the plants in the world; directory of the plants; nuclear fuel cycle facilities; and so forth. (J.P.N.)

  10. Nuclear power plants in the world

    International Nuclear Information System (INIS)

    2008-01-01

    The Japan Atomic Industrial Forum, Inc. (JAIF) used every year to summarize a trend survey on the private nuclear power plants in the world in a shape of the 'Nuclear power plants in the world'. In this report, some data at the end of 2007/2008 was made up on bases of answers on questionnaires from electric power companies and other nuclear organizations around the world by JAIF. This report is comprised of 18 items, and contains generating capacity of the plants; effect of the Niigata-ken chuetsu-oki earthquake; current status of Japan; trends of generating capacity of operating the plants, the plant orders and generating capacity of the plants; world nuclear capacity by reactor type; status of MOX use in the world; location of the plants; the plants in the world; directory of the plants; nuclear fuel cycle facilities, and so forth. (J.P.N.)

  11. Nuclear Power Plants in the World

    International Nuclear Information System (INIS)

    2004-01-01

    The Japan Atomic Industrial Forum, Inc. (JAIF) used every year to summarize a trend survey on the private nuclear power plants in the world in a shape of the 'Nuclear power plants in the world'. In this report, some data at the end of 2003 was made up on bases of answers on questionnaires from 81 electric power companies and other nuclear organizations in 33 countries and regions around the world by JAIF. This report is comprised of 19 items, and contains generating capacity of the plants; current status of Japan; trends of generating capacity of operating the plants, the plant orders and generating capacity of the plants; world nuclear capacity by reactor type; status of MOX use in the world; location of the plants; the plants in the world; directory of the plants; nuclear fuel cycle facilities; and so forth. (J.P.N.)

  12. Nuclear Plant Integrated Outage Management

    International Nuclear Information System (INIS)

    Gerstberger, C. R.; Coulehan, R. J.; Tench, W. A.

    1992-01-01

    This paper is a discussion of an emerging concept for improving nuclear plant outage performance - integrated outage management. The paper begins with an explanation of what the concept encompasses, including a scope definition of the service and descriptions of the organization structure, various team functions, and vendor/customer relationships. The evolvement of traditional base scope services to the integrated outage concept is addressed and includes discussions on changing customer needs, shared risks, and a partnership approach to outages. Experiences with concept implementation from a single service in 1984 to the current volume of integrated outage management presented in this paper. We at Westinghouse believe that the operators of nuclear power plants will continue to be aggressively challenged in the next decade to improve the operating and financial performance of their units. More and more customers in the U. S. are looking towards integrated outage as the way to meet these challenges of the 1990s, an arrangement that is best implemented through a long-term partnering with a single-source supplier of high quality nuclear and turbine generator outage services. This availability, and other important parameters

  13. Simulators for nuclear power plants

    International Nuclear Information System (INIS)

    Ancarani, A.; Zanobetti, D.

    1983-01-01

    The different types of simulator for nuclear power plants depend on the kind of programme and the degree of representation to be achieved, which in turn determines the functions to duplicate. Different degrees correspond to different simulators and hence to different choices in the functions. Training of nuclear power plant operators takes advantage of the contribution of simulators of various degrees of complexity and fidelity. Reduced scope simulators are best for understanding basic phenomena; replica simulators are best used for formal qualification and requalification of personnel, while modular mini simulators of single parts of a plant are best for replay and assessment of malfunctions. Another category consists of simulators for the development of assistance during operation, with the inclusion of disturbance and alarm analysis. The only existing standard on simulators is, at present, the one adopted in the United States. This is too stringent and is never complied with by present simulators. A description of possible advantages of a European standard is therefore offered: it rests on methods of measurement of basic simulator characteristics such as fidelity in values and time. (author)

  14. The making of French nuclear energy policy. Through the relationship between civilian and military use

    International Nuclear Information System (INIS)

    Kimura, Kenji

    2013-01-01

    The French history of nuclear development clearly shows the inseparability of its civilian use from military use. In France, Commissariat a l'Energie Atomique (CEA) and Electricite de France (EDF) have played an important role in research and development of nuclear technology since the postwar period. At first, the two organizations had kept great autonomy, but the government reinforced its control on them because France needed nuclear deterrence against the Soviet Union. France began using plutonium in 1952, and the Suez crisis in 1956 showed the need for nuclear force to ensure its independence. After this event, France managed the first nuclear test using plutonium in 1960. As for enriched uranium, they have long had great difficulty in securing it. The uranium enrichment technology became crucial also in civilian use in this period. EDF proposed the pressurized water reactor (PWR), which requires enriched uranium, as the future reactor type because of its economic advantage, but CEA wanted to continue developing the gas-cooled reactor (GCR) because of its independence in nuclear fuel supply. Finally, they chose PWR because a French enrichment facility was built in 1967. From such French history, we can say that the civilian and military use of nuclear technology are inseparable. (author)

  15. Advanced plant design recommendations from Cook Nuclear Plant experience

    International Nuclear Information System (INIS)

    Zimmerman, W.L.

    1993-01-01

    A project in the American Electric Power Service Corporation to review operating and maintenance experience at Cook Nuclear Plant to identify recommendations for advanced nuclear plant design is described. Recommendations so gathered in the areas of plant fluid systems, instrument and control, testing and surveillance provisions, plant layout of equipment, provisions to enhance effective maintenance, ventilation systems, radiological protection, and construction, are presented accordingly. An example for a design review checklist for effective plant operations and maintenance is suggested

  16. Nuclear power plant V-2

    International Nuclear Information System (INIS)

    1999-01-01

    In this leaflet the short history of commissioning of Bohunice V-2 NPP is reviewed (beginning of construction December 1976; First controlled reactor power, Reactor Unit 1 (RU1): 7 August 1984, Reactor Unit 2 (RU2): 2 August 1985; Connection to the grid: RU1 20 August 1984, RU2 9 August 1985; Commercial operation: RU1 14 February 1985, RU2 18 December 1985. The scheme of the nuclear reactor WWER 440/V213 is depicted. The major technological equipment are described. Principles of nuclear power plant operation safety (safety barriers, active and passive safety systems, centralized heat supply system, as well as technical data of the Bohunice V-2 NPP are presented

  17. Nuclear power plant V-1

    International Nuclear Information System (INIS)

    1999-01-01

    In this leaflet the short history of commissioning of Bohunice V-1 NPP is reviewed (beginning of construction 24 April 1972; First controlled reactor power, Reactor Unit 1 (RU1): 27 November 1978, Reactor Unit 2 (RU2): 15 March 1980; Connection to the grid: RU1 17 December 1978, RU2 26 March 1980; Commercial operation: RU1 1 April 1980, RU2 7 January 1981. The scheme of the nuclear reactor WWER 440/V230 is depicted. The major technological equipment (primary circuit, nuclear reactor, steam generators, reactor coolant pumps, primary circuit auxiliary systems, secondary circuit, turbine generators, NPP electrical equipment, and power plant control) are described. Technical data of the Bohunice V-1 NPP are presented

  18. Slovak Electric, plc, Mochovce Nuclear Power Plant

    International Nuclear Information System (INIS)

    1999-01-01

    In this popular scientific brochure a brief description of construction scheme of Bohunice Nuclear Power Plant is presented. Electricity generation in a nuclear power plant is described. Instrumentation and control system as well as nuclear safety principles applied on the NPP are presented

  19. Nuclear power plants in populated areas

    International Nuclear Information System (INIS)

    Wachsmann, F.

    1973-01-01

    The article first deals with the permanently increasing demand for electical power. Considering the ever growing energy demand which can no longer be covered by conventional power plants, it has become necessary to set up nuclear power plants of larger range. The author presents in a survey the basic function of nuclear power plants as well as the resulting risks and safety measures. The author concludes that according to present knowledge there is no more need to erect nuclear power plants outside densely populated urban areas but there is now the possibility of erecting nuclear power plants in densely populated areas. (orig./LH) [de

  20. Two economic, energetic, and environmental assessments of the French nuclear program

    International Nuclear Information System (INIS)

    Vielle, M.

    1996-01-01

    This paper presents two studies, which try to assess the economic, energy and environmental impact of the French nuclear program. First, the two models used are described briefly and then each study is discussed separately. The main results are summarized in the conclusion. (author). 4 refs., 5 tabs., 8 figs

  1. The power of the will and the French nuclear programme; Volontarisme du programme nucleaire francais

    Energy Technology Data Exchange (ETDEWEB)

    Boureille, P. [Ministre de la Defense, Dept. Marine, Service Historique de la Defense, 75 - Paris (France)

    2010-03-15

    Using certain key episodes in the development of the French nuclear deterrent as examples, the author illustrates the extent to which boldness of decision-making, combined with far-thinking and resolute vision, is the foundation of any international defence policy built for the long term. (author)

  2. Assessment of the impacts of the French nuclear program on the environment

    International Nuclear Information System (INIS)

    Naudet, G.

    1994-01-01

    This paper is an assessment of the impact of the French nuclear program on investments, on electricity price, on electricity and energy demand and especially on environment. The impact on atmosphere pollution which is based on a macro economic long term model (called MELODY), particularly detailed for the energy sector, is outlined. (TEC). 10 figs., 1 tab., 4 refs

  3. Design of nuclear power plants

    International Nuclear Information System (INIS)

    Lobo, C.G.

    1987-01-01

    The criteria of design and safety, applied internationally to systems and components of PWR type reactors, are described. The main criteria of the design analysed are: thermohydraulic optimization; optimized arrangement of buildings and components; low costs of energy generation; high level of standardization; application of specific safety criteria for nuclear power plants. The safety criteria aim to: assure the safe reactor shutdown; remove the residual heat and; avoid the release of radioactive elements for environment. Some exemples of safety criteria are given for Angra-2 and Angra-3 reactors. (M.C.K.) [pt

  4. Off-shore nuclear power plant

    International Nuclear Information System (INIS)

    Nakanishi, T.

    1980-01-01

    In order to avoid losses of energy and seawater pollution an off-shore nuclear power plant is coupled with a power plant which utilizes the temperature difference between seawater and hot reactor cooling water. According to the invention the power plant has a working media loop which is separated from the nuclear power plant. The apparative equipment and the operational characteristics of the power plant are the subject of the patent. (UWI) [de

  5. Industrial organization. The government draws a new french nuclear landscape

    International Nuclear Information System (INIS)

    Foucher, N.

    2000-01-01

    This paper presents and explains the new nuclear industry. In order to rationalize Cogema and Framatome are going to be grouped in an holding called Topco with a nuclear pole and an electronic and new technologies pole. Framatome will be split in two parts and its connector technology subsidiary will be introduced on Change. (A.L.B.)

  6. Nuclear power. Volume 1. Nuclear power plant design

    International Nuclear Information System (INIS)

    Pedersen, E.S.

    1978-01-01

    NUCLEAR POWER PLANT DESIGN is intended to be used as a working reference book for management, engineers and designers, and as a graduate-level text for engineering students. The book is designed to combine theory with practical nuclear power engineering and design experience, and to give the reader an up-to-date view of the status of nuclear power and a basic understanding of how nuclear power plants function. Volume 1 contains the following chapters; (1) nuclear reactor theory; (2) nuclear reactor design; (3) types of nuclear power plants; (4) licensing requirements; (5) shielding and personnel exposure; (6) containment and structural design; (7) main steam and turbine cycles; (8) plant electrical system; (9) plant instrumentation and control systems; (10) radioactive waste disposal (waste management) and (11) conclusion

  7. Nuclear energy is not the prevailing energy in the French energetic mix

    International Nuclear Information System (INIS)

    Destais, G.

    2011-01-01

    The author first shows that the share of nuclear energy in the French electricity production is in fact of 76% (and not 80% as usually said), and that the share of this energy in the final electricity consumption was 69% in 2009. She also outlines that nuclear electricity is only 16,5% of the total final energy consumption in France in 2009, whereas oil still prevails with 42%

  8. French presidential election: nuclear energy in candidates' program

    International Nuclear Information System (INIS)

    Le Ngoc, B.

    2017-01-01

    Generally right candidates consider nuclear energy as a chance for France because it is an industrial asset for the country, it releases no greenhouse gases and has given France its large energy independence. They are ready to reconsider the limitation imposed on the share of nuclear energy in the future energy mix and they want to reinforce research for next generations of reactors. The far-right candidate wishes to use nuclear energy massively to produce hydrogen in order to reduce by half the consumption of fossil energies in 20 years. Generally left candidates back the law on the energy transition that was passed during last legislature and that limits the nuclear power share to 50% while developing green energies. The far-left candidates wish a progressive and complete abandon of nuclear energy. All candidates wish a greater share of renewable energies in the future energy mix. (A.C.)

  9. Nuclear power plant operation 2016. Pt. 1

    Energy Technology Data Exchange (ETDEWEB)

    Anon.

    2017-05-15

    A report is given on the operating results achieved in 2016, events important to plant safety, special and relevant repair, and retrofit measures from nuclear power plants in Germany. Reports about nuclear power plants in Belgium, Finland, the Netherlands, Switzerland, and Spain will be published in a further issue.

  10. Environmental survey around EDF nuclear power plants

    International Nuclear Information System (INIS)

    Foulquier, L.

    1992-01-01

    Description of various types of environmental test carried out under the responsibility of the Operator of nuclear power plants in France, with taking Fessenheim nuclear power plant as an example: permanent monitoring of radioactivity, periodic radioecological assessments, main results of measurements taken, showing that there are no detectable effects of the plant on the environment, policy of openness by publication of these results

  11. Elecnuc. Nuclear power plants in the world; Elecnuc. Les centrales nucleaires dans le monde

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-07-01

    This small booklet summarizes in tables all the numerical data relative to the nuclear power plants worldwide. These data come from the French CEA/DSE/SEE Elecnuc database. The following aspects are reviewed: 1999 highlights; main characteristics of the reactor types in operation, under construction or on order; map of the French nuclear power plants; worldwide status of nuclear power plants at the end of 1999; nuclear power plants in operation, under construction and on order; capacity of nuclear power plants in operation; net and gross capacity of nuclear power plants on the grid and in commercial operation; grid connection forecasts; world electric power market; electronuclear owners and share holders in EU, capacity and load factor; first power generation of nuclear origin per country, achieved or expected; performance indicator of PWR units in France; worldwide trend of the power generation indicator; 1999 gross load factor by operator; nuclear power plants in operation, under construction, on order, planned, cancelled, shutdown, and exported; planning of steam generators replacement; MOX fuel program for plutonium recycling. (J.S.)

  12. Integrated CAD/CAE for nuclear power plants

    International Nuclear Information System (INIS)

    Lecoq, P.; Lachat, J.C.

    1987-01-01

    The size of the French nuclear power program has led both EDF and Framatome to equip themselves progressively with management software, computer-assisted design (CAD) systems, and computer-assisted engineering (CAE) systems. The nature of the projects and of the respective activities of EDF and Framatome determined the essential specifications of these computerized systems. EDF and Framatome have pooled their CAD/CAE efforts in a joint venture (Groupement d'Interet Economique) called GIAO, set up in 1985 by EDF and Aquitaine Systeme (a subsidiary of Framatome and Elf Aquitaine). GIAO's ambition is to become a pole of French CAD/CAE efforts and to foster progress in integrated computer-assisted engineering, by enlarging the synergy of EDF and Framatome in this field to other enterprises that participate in design and construction of complex industrial plants

  13. Study and discussion on management of nuclear island in-service inspection procedure system in nuclear power plant

    International Nuclear Information System (INIS)

    Zhang Xueliang; Fan Yancheng

    2014-01-01

    In-service inspection of nuclear island is the important way for keeping safety operation of nuclear power plant. Taking Daya Bay Nuclear Power Plant as example, the management problems of in-service inspection system was studied and discussed from the angle of references, contents, classifications etc. Based on comparison with French practice, some points of view on perfection of in-service inspection system and improvement of management ability under future multi-bases and multi-units management mode were presented. (authors)

  14. The stake of the French electro-nuclear programme

    International Nuclear Information System (INIS)

    Boiteux, Marcel

    1975-01-01

    At the end of the century, neither classic resources nor so-called ''new'' energies will be able to satisfy France's energetical needs. According to this statement -and taking into account the progressive reduction of the world petroleum resources -it is estimated that industrialized countries have no other choice than developping nuclear energy. What could be then the consequences for France of such an important option. Strengthening of its energetical independence, saving in foreign currencies and a lowering of its financial load, for the ''nuclear'' KWh is about twice cheaper than the ''classic'' one. Beyond arguments often justified but sometimes also unreasoned feeding the discussion about nuclear option validity it is considered that the real choice to which France is confronted is either to have ressort to nuclear energy - with all the unavoidable problems it raises but having nothing to do with the dismaying descriptions having been made - or to endanger seriously its economic and social development [fr

  15. Commercialization of nuclear power plant decommissioning technology

    International Nuclear Information System (INIS)

    Williams, D.H.

    1983-01-01

    The commercialization of nuclear power plant decommissioning is presented as a step in the commercialization of nuclear energy. Opportunities for technology application advances are identified. Utility planning needs are presented

  16. French experience to reduce radiation field build-up and improve nuclear fuel performance

    International Nuclear Information System (INIS)

    Thomazet, J.; Beslu, P.; Noe, M.; Stora, J.P.

    1983-01-01

    Over these last years, considerable information has been obtained on primary coolant chemistry, activity build-up and nuclear fuel behavior. As of December 1982, twenty three 900 MWe type reactors were in operation in France and about 1.3 millions of rods had been loaded in power reactors among which six regions of 17x17 fuel assemblies had completed successfully their third cycle of irradiation with a lead assembly burn-up of 37,000 MWd/MtU. Visual examination shows that crud deposited on fuel clads is mostly thin or inexistent. This result is due to the appropriate B/Li coolant concentration control which is currently applied in French reactors since several years. Correlatively, radiation field build-up is minimized and excessive external corrosion has never been observed. Nevertheless for higher coolant temperature plants, where occurrence of nucleate boiling could increase crud deposition, and for load follow and high burn-up operation, an extensive programme is performed jointly by Commissariat a l'Energie Atomique (CEA), Electricite de France, FRAMATOME and FRAGEMA to reduce even more the radiation field. This programme, described in the paper, includes: loop tests; on site chemical and radiochemical surveys; radiation field measurements; on site fuel examination crud-scrapping, crud analysis and oxide thickness measurements; hot cells examination. Some key results are presented and discussed in this paper. (author)

  17. History: development of civil and military nuclear - the French case

    International Nuclear Information System (INIS)

    Greneche, D.

    2016-01-01

    4 countries: USA, USSR, Great-Britain and France have been pioneers for the development of nuclear energy and the article shows that for the 3 first countries the saga of the atom began with the development of the atomic bomb while for France the works for both the achievement of the bomb and the production of electricity from nuclear energy began at the same period in mid fifties. (A.C.)

  18. Introduction to the French legislation dealing with nuclear financial liabilities

    International Nuclear Information System (INIS)

    Maocec, Ch.; Olivier, M.

    2008-01-01

    This paper aims at describing the new legal frame that has been set in France by law to face the issue of the financial liabilities of the nuclear industry, i.e. financing of the decommissioning and of the long term management of spent fuel and radioactive waste. An Act has been passed, dated 28 June 2006 (waste law), for a sustainable management of radioactive material and waste, which, in particular, implies new financial duties for nuclear operators. (authors)

  19. An evaluation of the production of solid radio-active waste in the Tricastin nuclear power station and, more generally, in the other French nuclear power stations

    International Nuclear Information System (INIS)

    Cuisenier, R.G.

    1986-01-01

    The importance of the effect of processing and packaging of solid radio-active wastes on the necessary staff, on the dosimetry acquired by this personnel and on the running costs will be presented, thus permitting a quantitative evaluation of the different types of waste produced, not only for the Tricastin plant but also for any typical French nuclear plant. Experience in the Tricastin power plant has shown that the volume of solid wastes can vary considerably depending on the different problems which can arise during production (cooling system leaks or less regular incidents). The different techniques used will be relooked at in order to facilitate the explanation of these fluctuations in the volume of waste produced and the measures which can be taken to limit them. The different measures which have been taken to improve performance in this domain will be presented: improvements in equipment, in methods, and in the increased awareness of the personnel concerning these problems

  20. Recent progress in SG level control in French PWR plants

    International Nuclear Information System (INIS)

    Parry, A.; Petetrot, J.F.; Vivier, M.J.

    1985-10-01

    Controlling the steam generator (SG) level is of major importance in a large PWR plant. This has led to extensive work on SG computer models. This paper presents results of the comparison between calculations and tests on the first four-loop plant in France. Four-loop plants started up after 1985 will be equipped with digital instead of analog controllers. A new SG level control has been designed and then optimised using the validated SG model. A prototype of this new system has been successfully tested on a three-loop plant. 4 refs

  1. TOSHIBA CAE system for nuclear power plant

    International Nuclear Information System (INIS)

    Machiba, Hiroshi; Sasaki, Norio

    1990-01-01

    TOSHIBA aims to secure safety, increase reliability and improve efficiency through the engineering for nuclear power plant using Computer Aided Engineering (CAE). TOSHIBA CAE system for nuclear power plant consists of numbers of sub-systems which had been integrated centering around the Nuclear Power Plant Engineering Data Base (PDBMS) and covers all stage of engineering for nuclear power plant from project management, design, manufacturing, construction to operating plant service and preventive maintenance as it were 'Plant Life-Cycle CAE System'. In recent years, TOSHIBA has been devoting to extend the system for integrated intelligent CAE system with state-of-the-art computer technologies such as computer graphics and artificial intelligence. This paper shows the outline of CAE system for nuclear power plant in TOSHIBA. (author)

  2. Operation of Finnish nuclear power plants

    International Nuclear Information System (INIS)

    Tossavainen, K.

    1993-06-01

    Quarterly reports on the operation of Finnish nuclear power plants describe events and observations, relating to nuclear and radiation safety, which the Finnish Centre for Radiation and Nuclear Safety considers significant. Also other events of general interest are reported. The reports also include a summary of the radiation safety of plant personnel and the environment, as well as tabulated data on the plants' production and load factors

  3. Safety culture in nuclear power plants

    International Nuclear Information System (INIS)

    Weihe, G. von; Pamme, H.

    2003-01-01

    Experience shows that German nuclear power plants have always been operated reliably and safely. Over the years, the safety level in these plants has been raised considerably so that they can stand any comparison with other countries. This is confirmed by the two reports published by the Federal Ministry for the Environment on the nuclear safety convention. Behind this, there must obviously stand countless appropriate 'good practices' and a safety management system in nuclear power plants. (orig.) [de

  4. Operation of Finnish nuclear power plants

    International Nuclear Information System (INIS)

    Tossavainen, K.

    1993-03-01

    Quarterly reports on the operation of Finnish nuclear power plants describe events and observations, relating to nuclear and radiation safety, which the Finnish Centre for Radiation and Nuclear Safety considers safety significant. Also other events of general interest are reported. The reports also include a summary of the radiation safety of plant personnel and the environment, as well as tabulated data on the plants' production and load factors

  5. HVDC transmission from nuclear power plant

    International Nuclear Information System (INIS)

    Yoshida, Yukio; Takenaka, Kiyoshi; Taniguchi, Haruto; Ueda, Kiyotaka

    1980-01-01

    HVDC transmission directly from a nuclear power plant is expected as one of the bulk power transmission systems from distant power generating area. Successively from the analysis of HVDC transmission from BWR-type nuclear power plant, this report discusses dynamic response characteristics of HVDC transmission (double poles, two circuits) from PWR type nuclear power plant due to dc-line faults (DC-1LG, 2LG) and ac-line faults (3LG) near inverter station. (author)

  6. Nuclear Power Plant Lifetime Management Study (I)

    Energy Technology Data Exchange (ETDEWEB)

    Hong, Sung Yull; Jeong, Ill Seok; Jang, Chang Heui; Song, Taek Ho; Song, Woo Young [Korea Electric Power Research Institute, Taejon (Korea, Republic of); Jin, Tae Eun [Korea Power Engineering Company Consulting and Architecture Engineers, (Korea, Republic of); Kim, Woo Chul [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1997-12-31

    As the operation-year of nuclear power plant increases and finding sites for new nuclear power plant becomes harder, a comprehensive and systematic nuclear plant lifetime management(PLIM) program including life extension has to be established for stable and safe supply of electricity. A feasibility study was conducted to systematically evaluate technical, economic and regulatory aspect of plant lifetime managements and plant life extension for Kori-1 nuclear power plant. For technical evaluation of nuclear power plant, 13 major components were selected for lifetime evaluation by screening system. structure, and components(SSCs) of the plant. It was found that except reactor pressure vessel, which needs detailed integrity analysis, and low pressure turbine, which is scheduled to be replaced, 11 out of 13 major components have sufficient service life, for more than 40 years. Because domestic rules and regulations related to license renewal has not yet been written, review on the regulatory aspect of life extensions was conducted using US NRC rules and regulations. A cooperative effort with nuclear regulatory body is needed for early completion of license renewal rules and regulations. For economic evaluation of plant lifetime extension, a computer program was developed and used. It was found that 10 to 20 year of extension operation of Kori-1 nuclear power plant was proved. Based on the results, next phase of plant lifetime management program for detailed lifetime evaluation and presenting detailed implementation schedule for plant refurbishment for lifetime extension should be followed. (author). 74 refs., figs.

  7. Summary of nuclear power plant construction

    International Nuclear Information System (INIS)

    Tamura, Saburo

    1973-01-01

    Various conditions for the construction of nuclear power plants in Japan without natural resources were investigated. Expansion of the sites of plants, change of reactor vessels, standardization of nuclear power plants, possiblity of the reduction of construction period, approaching of nuclear power plants to consuming cities, and group construction were studied. Evaluation points were safety and economy. Previous sites of nuclear power plants were mostly on plane ground or cut and enlarge sites. Proposals for underground or offshore plants have been made. The underground plants were made at several places in Europe, and the ocean plant is now approved in U.S.A. as a plant on a man-made island. Vessels for containing nuclear reactors are the last barriers to the leakage of radioactive substance. At the initial period, the vessels were made of steel, which were surrounded by shielding material. Those were dry well type containers. Then, vessel type changed to pressure-suppression type wet containers. Now, it tends to concrete (PC or RC) type containers. There is the policy on the standardization of nuclear power plants by U.S.A.E.C. in recent remarkable activity. The merit and effect of the standardization were studied, and are presented in this paper. Cost of the construction of nuclear power plants is expensive, and interest of money is large. Then, the reduction of construction period is an important problem. The situations of plants approaching to consuming cities in various countries were studied. Idea of group construction is described. (Kato, T.)

  8. Nuclear Power Plant Lifetime Management Study (I)

    Energy Technology Data Exchange (ETDEWEB)

    Hong, Sung Yull; Jeong, Ill Seok; Jang, Chang Heui; Song, Taek Ho; Song, Woo Young [Korea Electric Power Research Institute, Taejon (Korea, Republic of); Jin, Tae Eun [Korea Power Engineering Company Consulting and Architecture Engineers, (Korea, Republic of); Kim, Woo Chul [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1996-12-31

    As the operation-year of nuclear power plant increases and finding sites for new nuclear power plant becomes harder, a comprehensive and systematic nuclear plant lifetime management(PLIM) program including life extension has to be established for stable and safe supply of electricity. A feasibility study was conducted to systematically evaluate technical, economic and regulatory aspect of plant lifetime managements and plant life extension for Kori-1 nuclear power plant. For technical evaluation of nuclear power plant, 13 major components were selected for lifetime evaluation by screening system. structure, and components(SSCs) of the plant. It was found that except reactor pressure vessel, which needs detailed integrity analysis, and low pressure turbine, which is scheduled to be replaced, 11 out of 13 major components have sufficient service life, for more than 40 years. Because domestic rules and regulations related to license renewal has not yet been written, review on the regulatory aspect of life extensions was conducted using US NRC rules and regulations. A cooperative effort with nuclear regulatory body is needed for early completion of license renewal rules and regulations. For economic evaluation of plant lifetime extension, a computer program was developed and used. It was found that 10 to 20 year of extension operation of Kori-1 nuclear power plant was proved. Based on the results, next phase of plant lifetime management program for detailed lifetime evaluation and presenting detailed implementation schedule for plant refurbishment for lifetime extension should be followed. (author). 74 refs., figs.

  9. The nuclear debate in France: some additional data. A point of view by the French Nuclear Energy Society (SFEN)

    International Nuclear Information System (INIS)

    2011-01-01

    Coming after the Fukushima accident which boosted the debate on nuclear energy in France, this document expresses the opinion of the French Nuclear Energy Society (SFEN). According to it, nuclear energy is an answer to the two main current challenges the World is facing: energy supply and global warming. Perspectives of energy policy should be based on a triptych: energy savings, renewable energies and nuclear energy. The authors also states that uranium reserves are available for centuries and even more, that the nuclear industry has a better record than other sources of production of electricity in terms of safety, and that the problem of nuclear wastes is solved. They consider that, provided that AREVA possesses property rights on important uranium reserves in America, Africa and Asia, the national independence is therefore guaranteed. Moreover, the French nuclear industry is a world leader, and the existence of nuclear energy production in France avoids many expenses. Therefore, the authors assert that giving up nuclear energy would be a triple step backwards

  10. Basic safety principles for nuclear power plant

    International Nuclear Information System (INIS)

    Zhang Shiguan

    1989-01-01

    To ensure the safety operation of nuclear power plant, one should strictly adhere to the implelmentation of safety codes and the establishment of nuclear safety code system, as well as the applicable basic safety principles of nuclear power plants. This article briefly introduce the importance of nuclear codes and its economic benefits and the implementation of basic safety principles to be accumulated in practice for many years by various countries

  11. Implemented organisation for subcontracting companies involved in the maintenance of the French nuclear stock - Sheet nr 39

    International Nuclear Information System (INIS)

    2011-01-01

    Every year, some 20,000 subcontracted salaried employees are mobilised for maintenance operations in the French nuclear reactors. Subcontracting is an answer to different needs: specific abilities, the short delay for maintenance during which a reactor is stopped, and which requires a very important contribution of labour, and specialised labour for some interventions. The document evokes a rigorous selection and certification process, and indicates the different specific training which are organised for anyone intervening in a nuclear power plant. It outlines that radiation protection and safety arrangements are the same for all (dosimetry), and that some measurements are performed on some temporary workers. Some data shows that these controls are efficient and that safety is improving

  12. Guide to robots and remote-controlled tools used in French nuclebar power plants

    International Nuclear Information System (INIS)

    Ferriole, G.

    1987-01-01

    Three types of robots are used in French nuclear plants: 1) Tool carriers for steam generator channel heads 2) Autonomous tool carriers and 3) Multifunctional tool carriers. Tool carriers for steam generator channel heads have been designed to perform only maintenance activities inside the channel head of steam generators and especially on the tubes. The shape and size of these carriers are adapted to the channel heads which is their only application. Autonomous carriers are tank-type vehicles with full tractor treads and their capacity ranges from 20 to 150 kg. These vehicles are used mainly for televisual inspection of the instrumentation penetrations underneath the pressure vessel and the upper pressure vessel internal structures (inspection of control rod guide tube split pins). Multifunctional tool carriers are developed to perform exceptional maintenance tasks of a nongeneric type in an environment with very high irradiation fields, that are inaccessible to a human operator. This means that such tasks are not always clearly defined and their execution is liable to change during the process. The different tasks can be delicate to perform and highly complex, e.g.: recovering a dropped fuel element, underwater measuration, dismantling of mechanical equipment, etc

  13. Decree no. 96-927 from October 16, 1996 giving permission to Electricite de France to operate the Ardennes nuclear power plant including the basic nuclear installations no. 1 (reactor and auxiliary circuits), no. 2 (radioactive effluents processing plant) and no. 3 (fuel storage building), located on the territory of Chooz town (Ardennes)

    International Nuclear Information System (INIS)

    Borotra, F.

    1996-01-01

    This decree from the French ministry of industry and postal services gives to Electricite de France (EDF) the official permission to operate the Chooz nuclear power plant previously operated by the French-Belgium nuclear energy Society of the Ardennes. The operation will follow the conditions previously imposed to this Society. (J.S.)

  14. Qualification of nuclear power plant operations personnel

    International Nuclear Information System (INIS)

    1984-01-01

    With the ultimate aim of reducing the possibility of human error in nuclear power plant operations, the Guidebook discusses the organizational aspects, the staffing requirements, the educational systems and qualifications, the competence requirements, the ways to establish, preserve and verify competence, the specific aspects of personnel management and training for nuclear power plant operations, and finally the particular situations and difficulties to be overcome by utilities starting their first nuclear power plant. An important aspect presented in the Guidebook is the experience in training and qualification of nuclear power plant personnel in various countries: Argentina, Belgium, Canada, Czechoslovakia, France, Federal Republic of Germany, Spain, Sweden, United Kingdom and United States of America

  15. The operation of nuclear power plants

    International Nuclear Information System (INIS)

    Brosche, D.

    1992-01-01

    The duties to be performed in managing the operation of a nuclear power plant are highly diverse, as will be explained in this contribution by the examples of the Grafenrheinfeld Nuclear Power Station. The excellent safety record and the high availabilities of German nuclear power plants demonstrate that their operators have adopted the right approaches. Systematic evaluation of the operating experience accumulated inhouse and in other plants is of great significance in removing weak spots and improving operation. The manifold and complex activities in the structure of organization and of activities in a nuclear power plant require a high degree of division of labor. (orig.) [de

  16. Operation of Finnish nuclear power plants

    International Nuclear Information System (INIS)

    Tossavainen, K.

    1991-02-01

    During the third quarter of 1990 the Finnish nuclear power plant units Loviisa 1 and 2 and TVO I and II were in commercial operation for most of the time. The annual maintenance outages of the Loviisa plant units were held during the report period. All events during this quarter are classified as Level hero (Below Scale) on the International Nuclear Event Scale. Occupational radiation doses and external releases of radioactivity were below authorised limits. Only small amounts of radioactive substances originating in nuclear power plants were detected in samples taken in the vicinity of nuclear power plants

  17. Emergency control centers for nuclear power plants

    International Nuclear Information System (INIS)

    Anon.

    1979-01-01

    Guidance is provided for the development and implementation of emergency control centers for nuclear power plants, including nuclear plant control room, nuclear plant company headquarters, emergency control center, and nuclear plant alternate emergency control center. Requirements and recommendations are presented for the mission, communications, instrumentation and equipment associated with each type of control center. Decisional aids, manning requirements and resources are also given; the decision aids cover both the accident assessment and protective action areas. Both normal and alternate means of communications are considered. Off-site emergency control centers, although not covered in the strict sense by this standard, are considered in an appendix

  18. Electromagnetic compatibility of nuclear power plants

    International Nuclear Information System (INIS)

    Cabayan, H.S.

    1983-01-01

    Lately, there has been a mounting concern about the electromagnetic compatibility of nuclear-power-plant systems mainly because of the effects due to the nuclear electromagnetic pulse, and also because of the introduction of more-sophisticated and, therefore, more-susceptible solid-state devices into the plants. Questions have been raised about the adequacy of solid-state-device protection against plant electromagnetic-interference sources and transients due to the nuclear electromagnetic pulse. In this paper, the author briefly reviews the environment, and the coupling, susceptibility, and vulnerability assessment issues of commercial nuclear power plants

  19. Nuclear accidents and safety measures of domestic nuclear power plants

    International Nuclear Information System (INIS)

    Song Zurong; Che Shuwei; Pan Xiang

    2012-01-01

    Based on the design standards for the safety of nuclear and radiation in nuclear power plants, the three accidents in the history of nuclear power are analyzed. And the main factors for these accidents are found out, that is, human factors and unpredicted natural calamity. By combining the design and operation parameters of domestic nuclear plants, the same accidents are studied and some necessary preventive schemes are put forward. In the security operation technology of domestic nuclear power plants nowadays, accidents caused by human factors can by prevented completely. But the safety standards have to be reconsidered for the unpredicted neutral disasters. How to reduce the hazard of nuclear radiation and leakage to the level that can be accepted by the government and public when accidents occur under extreme conditions during construction and operation of nuclear power plants must be considered adequately. (authors)

  20. Large nuclear steam turbine plants

    International Nuclear Information System (INIS)

    Urushidani, Haruo; Moriya, Shin-ichi; Tsuji, Kunio; Fujita, Isao; Ebata, Sakae; Nagai, Yoji.

    1986-01-01

    The technical development of the large capacity steam turbines for ABWR plants was partially completed, and that in progress is expected to be completed soon. In this report, the outline of those new technologies is described. As the technologies for increasing the capacity and heightening the efficiency, 52 in long blades and moisture separating heaters are explained. Besides, in the large bore butterfly valves developed for making the layout compact, the effect of thermal efficiency rise due to the reduction of pressure loss can be expected. As the new technology on the system side, the simplification of the turbine system and the effect of heightening the thermal efficiency by high pressure and low pressure drain pumping-up method based on the recent improvement of feed water quality are discussed. As for nuclear steam turbines, the actual records of performance of 1100 MW class, the largest output at present, have been obtained, and as a next large capacity machine, the development of a steam turbine of 1300 MWe class for an ABWR plant is in progress. It can be expected that by the introduction of those new technologies, the plants having high economical efficiency are realized. (Kako, I.)

  1. Waste from nuclear power plants

    International Nuclear Information System (INIS)

    1980-01-01

    The report presents proposals for organizing and financing of the treatment and deposition of spent fuel and radioactive waste. Decommissioning of plants is taken into consideration. The proposals refer to a program of twelve reactors. A relatively complete model for the handling of radioactive waste in Sweden is at hand. The cost for the years 1980 to 2000 is estimated at approx 1040 million SKr. Also the expense to dispose of the rest of the waste is calculated up to the year 2060, when the waste is planned to be put into final deposit. The state must have substantial influence over the organization which should be closely connected to the nuclear industry. Three different types of organization are discussed, namely (i) a company along with a newly created authority, (ii) a company along with the existing Nuclear Power Inspectorate or (iii) a company along with a board of experts. The proposals for financing the cost of handling nuclear waste are given in chief outlines. The nuclear industry should reserve means to special funds. The allocations are calculated to 1.4 oere per delivered kWh up to and including the year 1980. The accumulated allocations for 1979 should thus amount to 1310 million SKr. The charge for supervision and for certain research and development is recommended to be 0.1 oere per kWh which corresponds to approx 23 million SKr for 1980. The funds should be assured by binding agreements which must be approved by the state. The amounts are given in the monetary value of the year 1979. (G.B.)

  2. Soil-to-plant, plant-to-milk and plant-to-meat transfers for the Oxi-sols in Tahiti, French Polynesia

    International Nuclear Information System (INIS)

    Descamps, B.

    2006-01-01

    French Polynesia is included in the latitude band 10 -30 degrees S.. In this band the total deposition of 137 Cs is about 1000 Bq.m -2; the French tests represent 13 % of this total deposition. The radiological survey of the French Polynesia environment exists since the beginning of the French nuclear program in 1966.It concerns 7 islands: Hiva Oa in the north (10 degrees S), Tubuai in the south (25 degrees S) and, from east to west, Mangareva, Hao, Rangiroa, Tahiti and Maupiti. Tahiti is a recent, high and volcanic island;it is the largest of the French Polynesia as a whole.Under tropical humid climate with heavy rainfalls, high summer temperatures, and excessive air humidity, the strong relief has been considerably eroded with the formation of particular soils, the oxi-sols.On these soils, in the Taravao peninsula, a cattle breeding farm of about 400 hectares has been studied since more than 30 years. Local milk is an important contributor to the ingestion dose in Tahiti and also an excellent item for the determination of the effective decrease of long -lived radionuclides in the environment. During the 1974 -1994 period the long term decrease for milk shows an effective half-live of 14.8 years and an environmental half-live of 24.8 years.In west european zones the effective half-live is about 5 years. To explain this difference we must mainly consider that the pasture zone in Taravao peninsula is a natural area whereas it is semi-natural in Europe. Moreover we assume that a 137 Cs stocking zone exists with very humic soils in some higher summits; a progressive lixiviation of 137 Cs could take place then. For the 1974 -1994 period the effective half live for the beef meat is about 11.5 years against 18.5 years for the environmental half-live. The difference between effective half-live for milk and meat can be explain by a greater collection zone for meat than for milk. The soil-to-plant transfer factor (F.T.) is about 10 (reporting dry matter) for the genus

  3. Data retrieval techniques for nuclear power plants

    International Nuclear Information System (INIS)

    Sozzi, G.L.; Dahl, C.C.; Gross, R.S.; Voeller, J.G. III

    1995-01-01

    Data retrieval, processing retrieved data, and maintaining the plant documentation system to reflect the as-built condition of the plant are challenging tasks for most existing nuclear facilities. The information management systems available when these facilities were designed and constructed are archaic by today's standards. Today's plant documentation systems generally include hard copy drawings and text, drawings in various CAD formats, handwritten information, and incompatible databases. These existing plant documentation systems perpetuate inefficiency for the plant technical staff in the performance of their daily activities. This paper discusses data retrieval techniques and tools available to nuclear facilities to minimize the impacts of the existing plant documentation system on plant technical staff productivity

  4. Commissioning of the nuclear power plant

    International Nuclear Information System (INIS)

    Furtado, P.M.; Rolf, F.

    1984-01-01

    Nuclear Power Plant Angra 2, located at Itaorna Beach-Angra dos Reis is the first plant of the Brazilian-German Agreement to be commissioned. The Nuclear Power Plant is a pressurized water reactor rated at 3765 Mw thermal/1325 Mw electrical. For commissioning purpose the plant is divided into 110 systems. Plant commissioning objective is to demonstrate the safe and correct operation of each plan component, system and of the whole plant in agreement with design conditions, licensing requirements and contractual obligations. This work gives a description of plant commissioning objectives, activities their time sequence, and documentation. (Author) [pt

  5. Nuclear Power Plant (NPP) safety in Brazil

    International Nuclear Information System (INIS)

    Lederman, L.

    1980-01-01

    The multidisciplinary aspects of the activities involved in the nuclear power plant (NPP) licensing, are presented. The activities of CNEN's technical staff in the licensing of Angra-1 and Angra-2 power plants are shown. (E.G.) [pt

  6. Development of nuclear power plant Risk Monitor

    International Nuclear Information System (INIS)

    Yang Xiaoming; Sun Jinlong; Ma Chao; Wang Lin; Gu Xiaohui; Bao Zhenli; Qu Yong; Zheng Hao

    2014-01-01

    Risk Monitor is a tool to monitor the real-time risk of a nuclear power plant for risk management and comprehensive decision-making, which has been widely used all over the world. The nuclear power plant Risk Monitor applies the real-time risk model with low-complicacy that could reflect the plant's actual configuration, automatically reads the plant's configuration information from the engineering system through the developed interface, and efficiently analyzes the plant's risk Dy the intelligent parallel-computing method in order to provide the risk basement for the safety management of nuclear power plant. This paper generally introduces the background, architecture, functions and key technical features of a nuclear power plant Risk Monitor, and validates the risk result, which could well reflect the plant's risk information and has a significant practical value. (authors)

  7. Taking into account chemical safety for French basic nuclear installations

    International Nuclear Information System (INIS)

    Tabard, Laurence; Conte, Dorothee

    2013-01-01

    Among nuclear installations, some fuel cycle facilities present a high level of chemical hazards. In France, the TSN law of the 13 June 2006 requires taking into account all the risks generated by a basic nuclear installation (BNI). But, as most of the implementing regulatory texts are under development at this time, part of the previous regulation settled down in the 1990's is still applying: the order of the 31 December 1999 concerning technical regulation in order to prevent and to limit hazards generated by nuclear facilities; the decree of the 4 May 1995 and the order of the 26 November 1999 that deal with BNI discharges. Moreover, some parts of BNI or of nuclear sites can be submitted to the general regulation concerning chemical hazards, which is part of the environment code. As a result, even if the TSN law and its implementing decree Nr 2007-1557 of the 2 November 2007 settle clearly that safety of BNI is not only radiological, but must take into account chemical hazards, the latter aspects are still under development. Moreover the application of the existing regulation, even if complex, has helped to assess chemical risks inside BNI and nuclear sites. (authors)

  8. The French nuclear safety authority, an independent administrative body

    International Nuclear Information System (INIS)

    Lacoste, A.C.

    2007-01-01

    The Nuclear Safety Authority (ASN) is officially responsible for controlling safety and radioactivity in France so as to protect wage-earners, patients, the public and the environment from nuclear-related risks. It draws on the work done by the Institute of Radioprotection and Nuclear Safety (IRSN), and provides information to the public on these questions. The Authority's goal is to ensure an effective, legitimate, impartial and creditable control recognized by the public and serving as an international reference mark. ASN is led by a board of 5 commissaries, has a staff of 420 employees most of them civil servants, has an annual budget of 50 million euros and relies on 11 regional departments

  9. Strategy - The after-Fukushima of the French nuclear sector - Nuclear must be an explicit choice - Siemens, leader of a nuclear-free Germany

    International Nuclear Information System (INIS)

    Dupin, L.

    2012-01-01

    A first article comments the consequences of the Fukushima accident for the French nuclear sector: the risk of an extreme accident must be taken into account; this will result in works and investments; the cost of the French nuclear-based electricity will increase; the debate on the dismantling costs will be on again. Despite these problems, the French nuclear industry relies on its development perspectives abroad, notably in China. In an interview, the chairman of Areva discusses his first six months of action, evokes the implementation of the strategic action plan and the consequences of France's financial degradation, evokes the UraMin affair, the consequences of the Fukushima accident on Areva's offer, the costs of works required by the ASN, the perspectives for the EPR reactor, Areva's activities in the renewable energy sector. A last article comments the strategy of the German company Siemens who decided to phase out nuclear, and to focus notably of wind energy

  10. 76 FR 1469 - Calvert Cliffs Nuclear Power Plant, LLC; Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2...

    Science.gov (United States)

    2011-01-10

    ... Nuclear Power Plant, LLC; Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2 Environmental Assessment... Plant, LLC, the licensee, for operation of the Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2... Impact Statement for License Renewal of Nuclear Plants, Calvert Cliffs Nuclear Power Plant (NUREG-1437...

  11. SOFINEL: a new engineering society for nuclear power plant sale to foreign countries

    International Nuclear Information System (INIS)

    Pennec, Claude.

    1978-01-01

    Electricite de France is committed with the French designers to realize nuclear power plants in foreign countries, (South Africa and Iran). It intervenes in this field, in cooperation with industrial firms, through a new created entity: SOFINEL (Societe Francaise d'Ingenierie Electronucleaire et d'assitance pour l'exportation) [fr

  12. Nuclear power plant operating experience, 1976

    International Nuclear Information System (INIS)

    1977-11-01

    This report is the third in a series of reports issued annually that summarize the operating experience of U.S. nuclear power plants in commercial operation. Power generation statistics, plant outages, reportable occurrences, fuel element performance, occupational radiation exposure and radioactive effluents for each plant are presented. Summary highlights of these areas are discussed. The report includes 1976 data from 55 plants--23 boiling water reactor plants and 32 pressurized water reactor plants

  13. How to bring the nuclear share to 50 pc without stopping any reactor, nor increasing CO2 emissions. The issue of renewal of the French nuclear reactor fleet is also part of the debate

    International Nuclear Information System (INIS)

    Nifenecker, Herve

    2013-01-01

    In a first article, after having recalled the present situation of the French energy mix, the author analyses the consequences of the shutting down of 22 nuclear reactors by 2025 to bring the nuclear share down from 75 to 50 per cent. Different options are discussed: fossil energy (but CO 2 emissions would be impacted), renewable energy (hydroelectricity cannot be further developed, biomass can be useful for heat networks, and wind energy is limited). The author examines the possibilities of decreasing electricity consumption, and of a significant contribution of gas plants. He compares direct gas- and fuel oil-based heating with heating with electricity produced by gas plants. A second article addresses the issue of renewal of the French nuclear reactor fleet. It discusses how to choose the right renewal pace, and an assessment of exploitation losses

  14. French people and the nuclear - Detailed results, June 2013. Ifop for Dimanche Ouest France

    International Nuclear Information System (INIS)

    Fourquet, Jerome; Pratviel, Esteban

    2013-06-01

    This document presents the results of a survey performed by IFOP on the perception of the nuclear sector by French people, two years after the Fukushima accident. After a presentation of the adopted methodology (sample, survey mode, error margins), the main lessons of this survey are stated. Results are then presented. They concern the opinion on the use of nuclear energy, on the desirable evolution of the nuclear share in energy production. They presented globally and with respect to various categories (gender, age, profession, status, place of residence, political opinion and vote)

  15. Operation of Finnish nuclear power plants

    International Nuclear Information System (INIS)

    Tossavainen, K.

    1993-09-01

    Quarterly reports on the operation of Finnish nuclear power plants describe events and observations, relating to nuclear safety and radiation protection which the Finnish Centre for Radiation and Nuclear Safety considers safety significant. Safety-enhancing modifications at the nuclear power plants and issues relating to the use of nuclear energy which are of general interest are also reported. The reports include a summary of the radiation safety of plant personnel and the environment, as well as tabulated data on the production and load factors of the plants. In the first quarter of 1993, a primary feedwater system pipe break occurred at Loviisa 2, in a section of piping after a feedwater pump. The break was erosion-corrosion induced. Repairs and inspections interrupted power generation for seven days. On the International Nuclear Event Scale the event is classified as a level 2 incident. Other events in the first quarter of 1993 had no bearing on nuclear safety and radiation protection

  16. Dukovany nuclear power plant safety

    International Nuclear Information System (INIS)

    1999-01-01

    Presentation covers recommended safety issues for the Dukovany NPP which have been solved with satisfactory conclusions. Safety issues concerned include: radiation safety; nuclear safety; security; emergency preparedness; health protection at work; fire protection; environmental protection; chemical safety; technical safety. Quality assurance programs at all stages on NPP life time is described. Report includes description of NPP staff training provision, training simulator, emergency operating procedures, emergency preparedness, Year 2000 problem, inspections and life time management. Description of Dukovany Plant Safety Analysis Projects including integrity of the equipment, modernisation, equipment innovation and safety upgrading program show that this approach corresponds to the actual practice applied in EU countries, and fulfilment of current IAEA requirements for safety enhancement of the WWER 440/213 units in the course of MORAWA Equipment Upgrading program

  17. Nuclear power plants in Germany

    International Nuclear Information System (INIS)

    Hennings, U.; Stuermer, W.

    1993-01-01

    Under the influence of the polarization between belief in progress, on the one hand, and the moral rigorism of our society, on the other hand, the risks of modern large technical systems have helped the highest level of technical safety to be attained in Germany. It has been reached especially by opting for maximum quality, maximum utility and reliability, complete documentation, continuous in-service checks during operation and, last but not least, by including man and human fallibility. Our concern should be that this strategy pursued in the Western industrialized countries becomes the rule, at least in its main characteristics, also in the Eastern countries. The hazards associated with reactors in Eastern countries affect us all, and it is especially the safety of those reactors which is causing concern. The experience accumulated with the 417 nuclear power plants now in operation, especially the incidents and accidents, shows that hazard potential management is admissible only with a highly developed safety strategy. (orig.) [de

  18. Nuclear power plant annunciator systems

    International Nuclear Information System (INIS)

    Rankin, W.L.

    1983-08-01

    Analyses of nuclear power plant annunciator systems have uncovered a variety of problems. Many of these problems stem from the fact that the underlying philosophy of annunciator systems have never been elucidated so as to impact the initial annunciator system design. This research determined that the basic philosophy of an annunciator system should be to minimize the potential for system and process deviations to develop into significant hazards. In order to do this the annunciator system should alert the operators to the fact that a system or process deviation exists, inform the operators as to the priority and nature of the deviation, guide the operators' initial responses to the deviation, and confirm whether operators responses corrected the deviation. Annunciator design features were analyzed to determine to what degree they helped the system meet the functional criteria, the priority for implementing specific design features, and the cost and ease of implementing specific design features

  19. BWR type nuclear power plant

    International Nuclear Information System (INIS)

    Matsumoto, Kosuke.

    1991-01-01

    In a BWR type nuclear power plant in which reactor water in a reactor pressure vessel can be drained to a waste processing system by way of reactor recycling pipeways and remaining heat removal system pipeways, a pressurized air supply device is disposed for supplying air for pressurizing reactor water to the inside of the reactor pressure vessel by way of an upper head. With such a constitution, since the pressurized air sent from the pressurized air supply device above the reactor pressure vessel for the reactor water discharging pressure upon draining, the water draining pressure is increased compared with a conventional case and, accordingly, the amount of drained water is not reduced even in the latter half of draining. Accordingly, the draining efficiency can be improved and only a relatively short period of time is required till the completion of the draining, which can improve safety and save labors. (T.M.)

  20. Nuclear power plant component protection

    International Nuclear Information System (INIS)

    Michel, E.; Ruf, R.; Dorner, H.

    1976-01-01

    Described is a nuclear power plant installation which includes a concrete biological shield forming a pit in which a reactor pressure vessel is positioned. A steam generator on the outside of the shield is connected with the pressure vessel via coolant pipe lines which extend through the shield, the coolant circulation being provided by a coolant pump which is also on the outside of the shield. To protect these components on the outside of the shield and which are of mainly or substantially cylindrical shape, semicylindrical concrete segments are interfitted around them to form complete outer cylinders which are retained against outward separation radially from the components, by rings of high tensile steel which may be interspaced so closely that they provide, in effect, an outer steel cylinder. The invention is particularly applicable to pressurized-water coolant reactor installations

  1. Nuclear Power Plant Module, NPP-1: Nuclear Power Cost Analysis.

    Science.gov (United States)

    Whitelaw, Robert L.

    The purpose of the Nuclear Power Plant Modules, NPP-1, is to determine the total cost of electricity from a nuclear power plant in terms of all the components contributing to cost. The plan of analysis is in five parts: (1) general formulation of the cost equation; (2) capital cost and fixed charges thereon; (3) operational cost for labor,…

  2. The new French uranium refining plant at Narbonne; La nouvelle usine francaise de raffinage d'uranium de Narbonne

    Energy Technology Data Exchange (ETDEWEB)

    Roux, J [Commissariat a l' Energie Atomique, Saclay (France).Centre d' Etudes Nucleaires

    1961-07-01

    In 1957 the Commissariat l'Energie Atomique in collaboration with two French industrial firms, the Compagnie de Saint-Gobain and the Societe Potasse et Engrais chimique, undertook the construction of a plant for the production of refined uranium on an industrial scale. This plant, which forms part of the French nuclear equipment programme and which works at a capacity of 1000 tons/year, was put into operation in July 1959. First of all the principles on which this under-taking is based are outlined. This is followed by a more detailed account of the construction, including the improvements brought to the process developed at the C.E.A. plant at le Bouchet when it was carried over to the industrial stage by the uranium branch of the Societe d'Etudes et de Travaux. (author) [French] Le Commissariat a l'Energie Atomique a entrepris en 1957 a Narbonne avec la collaboration de deux societes francaises, la Compagnie de Saint-Gobain et la Societe Potasse et Engrais Chimiques, la construction d'une usine destinee a assurer la production d'uranium raffine sur un plan industriel. Cette usine d'une capacite de 1000 tonnes/an qui s'insere dans le programme d'equipement nucleaire francais, a ete mise en service en juillet 1959. Nous evoquerons d'abord les principes qui ont ete a la base de cette realisation. Puis nous donnerons quelques details sur la construction et les ameliorations qui ont ete apportees au procede mis au point a l'usine du Bouchet du C.E.A. lors de sa transposition sur un plan industriel par la Societe d'Etudes et de Travaux pour l'uranium. (auteur)

  3. Plant life management optimized utilization of existing nuclear power plants

    International Nuclear Information System (INIS)

    Watzinger, H.; Erve, M.

    1999-01-01

    For safe, reliable and economical nuclear power generation it is of central importance to understand, analyze and manage aging-related phenomena and to apply this information in the systematic utilization and as-necessary extension of the service life of components and systems. An operator's overall approach to aging and plant life management which also improves performance characteristics can help to optimize plant operating economy. In view of the deregulation of the power generation industry with its increased competition, nuclear power plants must today also increasingly provide for or maintain a high level of plant availability and low power generating costs. This is a difficult challenge even for the newest, most modern plants, and as plants age they can only remain competitive if a plant operator adopts a strategic approach which takes into account the various aging-related effects on a plant-wide basis. The significance of aging and plant life management for nuclear power plants becomes apparent when looking at their age: By the year 2000 roughly fifty of the world's 434 commercial nuclear power plants will have been in operation for thirty years or more. According to the International Atomic Energy Agency, as many as 110 plants will have reached the thirty-year service mark by the year 2005. In many countries human society does not push the construction of new nuclear power plants and presumably will not change mind within the next ten years. New construction licenses cannot be expected so that for economical and ecological reasons existing plants have to be operated unchallengeably. On the other hand the deregulation of the power production market is asking just now for analysis of plant life time to operate the plants at a high technical and economical level until new nuclear power plants can be licensed and constructed. (author)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2013-07-01

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

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

    International Nuclear Information System (INIS)

    Mahe, Carole; Leroy, Christine

    2013-01-01

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

  6. Are atomic power plants saver than nuclear power plants

    International Nuclear Information System (INIS)

    Roeglin, H.C.

    1977-01-01

    It is rather impossible to establish nuclear power plants against the resistance of the population. To prevail over this resistance, a clarification of the citizens-initiatives motives which led to it will be necessary. This is to say: It is quite impossible for our population to understand what really heappens in nuclear power plants. They cannot identify themselves with nuclear power plants and thus feel very uncomfortable. As the total population feels the same way it is prepared for solidarity with the citizens-initiatives even if they believe in the necessity of nuclear power plants. Only an information-policy making transparent the social-psychological reasons of the population for being against nuclear power plants could be able to prevail over the resistance. More information about the technical procedures is not sufficient at all. (orig.) [de

  7. Life management plants at nuclear power plants PWR

    International Nuclear Information System (INIS)

    Esteban, G.

    2014-01-01

    Since in 2009 the CSN published the Safety Instruction IS-22 (1) which established the regulatory framework the Spanish nuclear power plants must meet in regard to Life Management, most of Spanish nuclear plants began a process of convergence of their Life Management Plants to practice 10 CFR 54 (2), which is the current standard of Spanish nuclear industry for Ageing Management, either during the design lifetime of the plant, as well as for Long-Term Operation. This article describe how Life Management Plans are being implemented in Spanish PWR NPP. (Author)

  8. The compact simulator for Tihange nuclear plant

    International Nuclear Information System (INIS)

    Gueben, M.

    1982-01-01

    After an introduction about the simulators for nuclear plants, a description is given of the compact simulator for the Tihange nuclear power plant as well as the simulated circuits and equipments such as the primary and secondary coolant circuits. The extent of simulation, the functions used by the instructor, the use of the simulator, the formation programme and construction planning are described. (AF)

  9. Operation of Finnish nuclear power plants

    International Nuclear Information System (INIS)

    Tossavainen, K.

    1994-03-01

    In the third quarter of 1993, all of Finland's four nuclear power plant units were in power operation, with the exception of the annual maintenance outages of the Loviisa units. The load factor average of the plant units was 83.6 %. None of the events which occurred during this annual quarter had any bearing on nuclear or radiation safety. (4 figs., 5 tabs.)

  10. Radiological characterization of nuclear plants under decommissioning

    International Nuclear Information System (INIS)

    Mincarini, M.

    1989-01-01

    In the present work a description of major problems encountered in qualitative and quantitative radiological characterization of nuclear plants for decommissioning and decontamination purpose is presented. Referring to several nuclear plant classes activation and contamination processes, direct and indirect radiological analysis and some italian significant experience are descripted

  11. Accidents with nuclear power plants, ch. 11

    International Nuclear Information System (INIS)

    Anon.

    1976-01-01

    A recalculation of the consequences of nuclear power plant accidents is presented taking into account different parameters or different quantities than those usually accepted. A case study of a nuclear power plant planned for the Eems-river estuary in the Netherlands is presented

  12. Slovak Electric, plc, Mochovce Nuclear Power Plant

    International Nuclear Information System (INIS)

    2000-01-01

    In this popular scientific brochure a brief description of history construction of Bohunice Nuclear Power Plant is presented. The chart of electricity generation in WWER 440/V-213 nuclear power plant is described. Operation and safety improvements at Mochovce NPP as well as environment protection are presented. Basic data of Mochovce NPP are included

  13. Quality assurance in nuclear power plant

    International Nuclear Information System (INIS)

    Magalhaes, M.T. de

    1981-01-01

    The factors related to the licensing procedures of a nuclear power plant (quality assurance and safety analysis) are presented and discussed. The consequences of inadequate attitudes towards these factors are shown and suggestions to assure the safety of nuclear power plants in Brazil are presented. (E.G.) [pt

  14. Medical consequences of a nuclear plant accident

    International Nuclear Information System (INIS)

    Olsson, S.E.; Reizenstein, P.; Stenke, L.

    1987-01-01

    The report gives background information concerning radiation and the biological medical effects and damages caused by radiation. The report also discusses nuclear power plant accidents and efforts from the medical service in the case of a nuclear power plant accident. (L.F.)

  15. HVDC transmission from isorated nuclear power plant

    International Nuclear Information System (INIS)

    Takenaka, Kiyoshi; Takasaki, Masahiro; Ichikawa, Tatemi; Hayashi, Toshiyuki

    1985-01-01

    HVDC transmission directly from nuclear power plant is considered as one of the patterns of long distance and large capacity transmission system. This reports considers two route HVDC transmission from PWR type nuclear power plant, and analyzes dynamic response characteristics due to bus fault, main protection failure and etc. using the AC-DC Power System Simulator. (author)

  16. EPRI nuclear power plant decommissioning technology program

    International Nuclear Information System (INIS)

    Kim, Karen S.; Bushart, Sean P.; Naughton, Michael; McGrath, Richard

    2011-01-01

    The Electric Power Research Institute (EPRI) is a non-profit research organization that supports the energy industry. The Nuclear Power Plant Decommissioning Technology Program conducts research and develops technology for the safe and efficient decommissioning of nuclear power plants. (author)

  17. Slovak Electric, plc, Bohunice Nuclear Power Plant

    International Nuclear Information System (INIS)

    1999-01-01

    A brief account of activities carried out by the Bohunice Nuclear Power Plant in 1998 is presented. These activities are reported under the headings: (1) Operation and electric power generation; (2) Nuclear and radiation safety; (3) Maintenance and scheduled refuelling out-gages; (4) Investment and WWER units upgrading; (5) Power Plants Personnel; (6) Public relations

  18. Aircraft, ships, spacecraft, nuclear plants and quality

    International Nuclear Information System (INIS)

    Patrick, M.G.

    1984-05-01

    A few quality assurance programs outside the purview of the Nuclear Regulatory Commission were studied to identify features or practices which the NRC could use to enhance its program for assuring quality in the design and construction of nuclear power plants. The programs selected were: the manufacture of large commercial transport aircraft, regulated by the Federal Aviation Administration; US Navy shipbuilding; commercial shipbuilding regulated by the Maritime Administration and the US Coast Guard; Government-owned nuclear plants under the Department of Energy; spacecraft under the National Aeronautics and Space Administration; and the construction of nuclear power plants in Canada, West Germany, France, Japan, Sweden, and the United Kingdom

  19. Operation of Finnish nuclear power plants

    International Nuclear Information System (INIS)

    Tossavainen, K.

    1992-09-01

    The Finnish nuclear power plant units Loviisa 1 and 2 as well as TVO I and II were in operation for almost all the time in the first quarter of 1992. The load factor average was 99.8%. All events which are classified on the International Nuclear Event Scale were level 0/below scale on the Scale. Occupational radiation doses and releases of radioactive material off-site remained well below authorised limits. Only quantities of radioactive material insignificant to radiation exposure, originating from the nuclear power plants, were detected in samples collected in the vicinity of the nuclear power plants

  20. Millstone nuclear power plant emergency system assessment

    International Nuclear Information System (INIS)

    Akhmad Khusyairi

    2011-01-01

    U.S.NRC determined an obligation to build a nuclear power plant emergency response organization for both on-site and off-site. Millstone Nuclear Power Plants have 3 nuclear reactors and 2 of 3 still in commercial operation. Reactor unit 1, BWR type has been permanently shut down in 1998, while the two others, units 2 and 3 obtain the extended operating license respectively until 2035 and 2045. As a nuclear installation has the high potential radiological impact, Millstone nuclear power plant emergency response organization must establish both on-site or off-site. Emergency response organization that is formed must involve several state agencies, both state agencies and municipality. They have specific duties and functions in a state of emergency, so that protective measures can be undertaken in accordance with the community that has been planned. Meanwhile, NRC conduct their own independent assessment of nuclear power plant emergencies. (author)

  1. Modelling of nuclear power plant decommissioning financing.

    Science.gov (United States)

    Bemš, J; Knápek, J; Králík, T; Hejhal, M; Kubančák, J; Vašíček, J

    2015-06-01

    Costs related to the decommissioning of nuclear power plants create a significant financial burden for nuclear power plant operators. This article discusses the various methodologies employed by selected European countries for financing of the liabilities related to the nuclear power plant decommissioning. The article also presents methodology of allocation of future decommissioning costs to the running costs of nuclear power plant in the form of fee imposed on each megawatt hour generated. The application of the methodology is presented in the form of a case study on a new nuclear power plant with installed capacity 1000 MW. © The Author 2015. Published by Oxford University Press. All rights reserved. For Permissions, please email: journals.permissions@oup.com.

  2. Cooling towers of nuclear power plants

    International Nuclear Information System (INIS)

    Mikyska, L.

    1986-01-01

    The specifications are given of cooling towers of foreign nuclear power plants and a comparison is made with specifications of cooling towers with natural draught in Czechoslovak nuclear power plants. Shortcomings are pointed out in the design of cooling towers of Czechoslovak nuclear power plants which have been derived from conventional power plant design. The main differences are in the adjustment of the towers for winter operation and in the designed spray intensity. The comparison of selected parameters is expressed graphically. (J.B.)

  3. Company of the month: French EDF opts for nuclear power

    International Nuclear Information System (INIS)

    Jansen, Siw Linnea

    2006-01-01

    EDF is Europe's largest power company with 640 TWh produced in 2005 and 36,7 million customers in Europe. On a global scale the company has more than 40 million customers. EDF has significant positions in the four big energy markets in Europe: Germany, France, Great Britain and Italy. EDF has an ambitious investment program in the area of nuclear power, and holds that increased investments in this sector is the best and most beneficial way of keeping up with Europe's increasing energy demand (ml)

  4. Nuclear power plants and their insurances

    International Nuclear Information System (INIS)

    Schludi, H.N.

    1984-01-01

    From the commencement of building to the time of decommissioning of nuclear power plants, the insurances provide continuous coverage, i.e. for construction, nuclear liability, nuclear energy hazards insurance, fire insurance, machinery insurance. The respective financial security is quantified. (DG) [de

  5. Lifting devices in nuclear power plants

    International Nuclear Information System (INIS)

    Anon.

    1978-01-01

    The regulation applies to lifts, cranes, winches, rail trolleys, load pick-up equipment and fuel charging machines for LWR reactors, as far as these are employed in plants for the production or fission of nuclear fuels or for the reprocessing of spent nuclear fuels or for the storage or other uses of nuclear fuels. (orig.) 891 HP [de

  6. Anatomy of a nuclear power plant

    International Nuclear Information System (INIS)

    Navarro, Q.O.

    1983-01-01

    This paper presents the Q model which attempts to classify arguments for use in the discussion on the pros and cons of nuclear power. The basic principles of nuclear energy production, operation of a nuclear power plant and a comparison with other electric power sources are presented and discussed. (ELC)

  7. French people and nuclear wastes; Les francais et les dechets nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    D' Iribarne, Ph [Centre National de la Recherche Scientifique (CNRS), 75 - Paris (France)

    2005-07-01

    On March 21, 2005, the French minister of industry gave to the author of this document, the mission to shade a sociological light on the radioactive wastes perception by French people. The objective of this study was to supply an additional information before the laying down in 2006 of the decisions about the management of high-level and long-lived radioactive wastes. This inquiry, carried out between April 2004 and March 2005, stresses on the knowledge and doubts of the questioned people, on the vision they have of radioactive wastes and of their hazards, and on their opinion about the actors in concern (experts, nuclear companies, government, anti-nuclear groups, public). The last two parts of the report consider the different ways of waste management under study today, and the differences between the opinion of people living close to the Bure site and the opinion of people living in other regions. (J.S.)

  8. Nuclear reactor kinetics and plant control

    CERN Document Server

    Oka, Yoshiaki

    2013-01-01

    Understanding time-dependent behaviors of nuclear reactors and the methods of their control is essential to the operation and safety of nuclear power plants. This book provides graduate students, researchers, and engineers in nuclear engineering comprehensive information on both the fundamental theory of nuclear reactor kinetics and control and the state-of-the-art practice in actual plants, as well as the idea of how to bridge the two. The first part focuses on understanding fundamental nuclear kinetics. It introduces delayed neutrons, fission chain reactions, point kinetics theory, reactivit

  9. Fire prevention in nuclear power plants

    International Nuclear Information System (INIS)

    1993-01-01

    The causes and frequency of fires at nuclear power plants in various countries are briefly given. Methods are described of fire hazard assessment at nuclear power plants, such as Gretener's method and the probabilistic methods. Approaches to the management of nuclear reactor fire protection in various countries as well as the provisions to secure such protection are dealt with. An overview and the basic characteristics of fire detection and extinguishing systems is presented. (Z.S.). 1 tab

  10. Fire protection at nuclear power plants

    International Nuclear Information System (INIS)

    1999-11-01

    The guide presents specific requirements for the design and implementation of fire protection arrangements at nuclear power plants and for the documents relating to the fire protection that are to be submitted to STUK (Finnish Radiation and Nuclear Safety Authority). Inspections of the fire protection arrangements to be conducted by STUK during the construction and operation of the power plants are also described in this guide. The guide can also be followed at other nuclear facilities

  11. Knowledge preservation strategies for nuclear power plants

    International Nuclear Information System (INIS)

    Koruna, S.; Bachmann, H.

    2004-01-01

    The nuclear industry is currently facing several challenges. An internal threat to the safety and operations of nuclear power plants is the loss of those employees who hold knowledge that is either critical to operations or safety. This report discusses the possibilities to preserve knowledge in nuclear power plants. Dependent on the degree of tacitness two different knowledge preservation strategies can be discerned: personalization and codification. The knowledge preservation activities discussed are valued according to the criteria: cost, immediacy of availability and completeness

  12. Topnux'96 international conference French nuclear energy society

    International Nuclear Information System (INIS)

    Park, S.K.

    1996-01-01

    Here is the opening address of Mr S. Park, vice-president of the Korea Electric Power Corporation, at the opening session of the Topnux'96 conference. The main ideas of his speech are the following: 1)energy is indispensable for maintaining affluent living standards 2)it is the most important requirement for rapid economic growth 3)overall energy consumption of the world is expected to rise continuously in the next century 4)demand for electricity is greater than growth of overall energy consumption 5)burning of large amount of fossil fuels to meet the energy, including electricity, will bring about serious environmental impact such as air pollution and global warming due to emission of toxic chemical and greenhouse gases 6)nuclear power is one of the most effective and practical alternatives available now for solving this global problem 7)energy should be convenient to use, inexpensive, safe, secured and environment friendly; in this respect, electricity is the most desirable type of energy indispensable for modern civilization and nuclear power is surely one of the viable option for producing electricity. (O.M.)

  13. Chemistry management system for nuclear power plants

    International Nuclear Information System (INIS)

    Nagasawa, Katsumi; Maeda, Katsuji

    1998-01-01

    Recently, the chemistry management in the nuclear power plants has been changing from the problem solution to the predictive diagnosis and maintenance. It is important to maintain the integrity of plant operation by an adequate chemistry control. For these reasons, many plant operation data and chemistry analysis data should be collected and treated effectively to evaluate chemistry condition of the nuclear power plants. When some indications of chemistry anomalies occur, quick and effective root cause evaluation and countermeasures should be required. The chemistry management system has been developed as to provide sophisticate chemistry management in the nuclear power plants. This paper introduces the concept and functions of the chemistry management system for the nuclear power plants. (author)

  14. French policy for managing the post-accident phase of a nuclear accident.

    Science.gov (United States)

    Gallay, F; Godet, J L; Niel, J C

    2015-06-01

    In 2005, at the request of the French Government, the Nuclear Safety Authority (ASN) established a Steering Committee for the Management of the Post-Accident Phase of a Nuclear Accident or a Radiological Emergency, with the objective of establishing a policy framework. Under the supervision of ASN, this Committee, involving several tens of experts from different backgrounds (e.g. relevant ministerial offices, expert agencies, local information commissions around nuclear installations, non-governmental organisations, elected officials, licensees, and international experts), developed a number of recommendations over a 7-year period. First published in November 2012, these recommendations cover the immediate post-emergency situation, and the transition and longer-term periods of the post-accident phase in the case of medium-scale nuclear accidents causing short-term radioactive release (less than 24 h) that might occur at French nuclear facilities. They also apply to actions to be undertaken in the event of accidents during the transportation of radioactive materials. These recommendations are an important first step in preparation for the management of a post-accident situation in France in the case of a nuclear accident. © The Chartered Institution of Building Services Engineers 2014.

  15. Operation of Finnish nuclear power plants

    International Nuclear Information System (INIS)

    Tossavainen, K.

    1991-08-01

    In the Quarterly Reports on the operation of the Finnish nuclear power plants such events and observations are described relating to nuclear and radiation safety which the Finnish Centre for Radiation and Nuclear Safety considers safety significant. Also other events of general interest are reported. The report also includes a summary of the radiation safety of the plants' workers and the environment, as well as tabulated data on the production and load factors of the plants. The Finnish nuclear power plant units Loviisa 1 and 2 as well as TVO I and II were in commercial operation during the whole first quarter of 1991. The load factor average was 99.1 %. Failures have been detected in the uppermost spacing lattices of nuclear fuel bundles removed from the Loviisa nuclear reactors. Further investigations into the significance of the failures have been initiated. In this quarter, renewed cooling systems for the instrumentation area were introduced at Loviisa 1. The modifications made in the systems serve to ensure reliable cooling of the area even during the hottest summer months when the possibility exists that the temperature of the automation equipment could rise too high causing malfunctions which could endanger plant safety. Occupational radiation doses and external releases of radioactivity were below prescribed limits in this quarter. Only small amounts of radioactive substances originating in nuclear power plants were detected in samples taken in the vicinity of nuclear power plants

  16. Human factors in nuclear power plants

    International Nuclear Information System (INIS)

    Swain, A.D.

    1981-01-01

    This report describes some of the human factors problems in nuclear power plants and the technology that can be employed to reduce those problems. Many of the changes to improve the human factors in existing plants are inexpensive, and the expected gain in human reliability is substantial. The human factors technology is well-established and there are practitioners in most countries that have nuclear power plants. (orig.) [de

  17. Human factors in nuclear power plant operations

    International Nuclear Information System (INIS)

    Swain, A.D.

    1980-08-01

    This report describes some of the human factors problems in nuclear power plants and the technology that can be employed to reduce those problems. Many of the changes to improve the human factors in existing plants are inexpensive, and the expected gain in human reliability is substantial. The human factors technology is well-established and there are practitioners in most countries that have nuclear power plants

  18. The production costs of the French nuclear fleet. Synthesis and conclusions. Technical note

    International Nuclear Information System (INIS)

    2017-09-01

    Whereas the French Energy Multi-year Programming (PPE) notably aims at preserving the purchasing power of consumers and the competitiveness of energy prices, this note aims at reporting an assessment of the production cost of the French present nuclear fleet, i.e. the electric power cost at the output of the production installation. The authors first discuss the choice for the methodology of 'cash costs' for the decision to continue of not the exploitation of existing units. They propose a mean assessment of about 33 euro/MWh, state that the present nuclear-based power production in France is profitable, and consider that there is no 'investment wall' to be faced in the near future. They also state that nuclear costs are hardly supposed to increase because they are little sensitive to uranium prices. They consider that dismantling and waste costs are covered at more than 100 per cent by dedicated assets. A technical note comes with this discussion. It discusses cost calculation methods, the assessment of the production cost of French existing reactors (second generation), and some additional elements regarding some cost components

  19. French experience in design, operation and revamping of nuclear research reactors, in support of advanced reactors development

    International Nuclear Information System (INIS)

    Barre, B.; Bergeonneau, P.; Merchie, F.; Minguet, J.L.; Rousselle, P.

    1996-01-01

    The French nuclear program is strongly based on the R and D work performed in the CEA nuclear research centers and particularly on the various experimental programs carried out in its research reactors in the frame of cooperative actions between the Commissariat a l'Energie Atomique (CEA), Framatome and Electricite de France (EDF). Several types of research reactors have been built by Technicatome and CEA to carry out successfully this considerable R and D work on fuels and materials, among them the socalled Materials Testing Reactors (MTR) SILOE (35 MW) and OSIRIS (70 MW) which are indeed very well suited for technological irradiations. Their simple and flexible design and the large irradiation space available around the core, the SILOE and OSIRIS reactors can be shared by several types of applications such as fuel and material testings for nuclear power plants, radioisotopes production, silicon doping and fundamental research. It is worthwhile recalling that Technicatome and CEA have also built research reactors fully dedicated to safety experimental studies, such as the CABRI, SCARABEE and PHEBUS reactors at Cadarache, and others dedicated to fundamental research such as ORPHEE (14 MW) and the Reacteur a Haut Flux -High Flux Reactor- (RHF 57 MW). This paper will present some of the most significant conceptual and design features of all these reactors as well as the main improvements brought to most of them in the last years. Based on this wide experience, CEA and Technicatome have specially designed for export a new multipurpose research reactor named SIRIUS, with two versions depending on the utilization spectrum and the power range (5 MW to 30 MW). At last, CEA has recently launched the preliminary project study of a new MTR, the Jules Horowitz Reactor, to meet the future needs of fuels and materials irradiations in the next 4 or 5 decades, in support of the French long term nuclear power program. (J.P.N.)

  20. Nuclear Power Plant Concrete Structures

    Energy Technology Data Exchange (ETDEWEB)

    Basu, Prabir [International Atomic Energy Agency (IAEA); Labbe, Pierre [Electricity of France (EDF); Naus, Dan [Oak Ridge National Laboratory (ORNL)

    2013-01-01

    A nuclear power plant (NPP) involves complex engineering structures that are significant items of the structures, systems and components (SSC) important to the safe and reliable operation of the NPP. Concrete is the commonly used civil engineering construction material in the nuclear industry because of a number of advantageous properties. The NPP concrete structures underwent a great degree of evolution, since the commissioning of first NPP in early 1960. The increasing concern with time related to safety of the public and environment, and degradation of concrete structures due to ageing related phenomena are the driving forces for such evolution. The concrete technology underwent rapid development with the advent of chemical admixtures of plasticizer/super plasticizer category as well as viscosity modifiers and mineral admixtures like fly ash and silica fume. Application of high performance concrete (HPC) developed with chemical and mineral admixtures has been witnessed in the construction of NPP structures. Along with the beneficial effect, the use of admixtures in concrete has posed a number of challenges as well in design and construction. This along with the prospect of continuing operation beyond design life, especially after 60 years, the impact of extreme natural events ( as in the case of Fukushima NPP accident) and human induced events (e.g. commercial aircraft crash like the event of September 11th 2001) has led to further development in the area of NPP concrete structures. The present paper aims at providing an account of evolution of NPP concrete structures in last two decades by summarizing the development in the areas of concrete technology, design methodology and construction techniques, maintenance and ageing management of concrete structures.