WorldWideScience

Sample records for french nuclear plants

  1. 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)

  2. 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)

  3. 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

  4. 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)

  5. 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)

  6. Operational modes of french 900 MW nuclear power plant

    International Nuclear Information System (INIS)

    Shen Rugang

    1991-01-01

    The operational safety criteria of the PWR French 900 MW nuclear power plant and their operational modes: Mode A and Mode G is briefly introduced. The principle of the basic control, the operational performance, the advantages and the shortcomings of two modes are compared

  7. 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.)

  8. 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

  9. 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

  10. Maintenance operations and radiation protection in french nuclear power plants

    International Nuclear Information System (INIS)

    Godin, R.; Stricker, L.

    1990-01-01

    In the field of radiation protection, the Service de la Production thermique (the Thermal and fossil generation division, SPT) at EDF aims at being among the best and at keeping for EDF agents an exposure potential allowing them to act in an emergency case. Doses to EDF or subcontractors' workers must therefore be optimized during maintenance operations. These aims can be reached through special techniques and by a know-how of the actors at several levels: 1) upstream, operating the plant with a clean primary circuit (which limits dose rates) and solubilizing corrosion products during reactor cooling and primary circuit drainage; 2) before the intervention, thorough preparation of the work and operation of protection means suited to each site; 3) during the intervention, the actors' know-how requires suitable training and qualification of the operation leader, awareness of all the actors and, sometimes training on mockup; 4) finally, for special operations on account of their repetitiveness or because they take place in hostile places, special tools are developed. The techniques thus developed, the systematic use of feedback have made it possible to reach a most acceptable result. Radiation protection proceeds from the maintenance operation quality and thus shares in improving the operation safety of the french nuclear power plants. 5 figs.; 3 refs [fr

  11. 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)

  12. 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

  13. 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)

  14. 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)

  15. 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)

  16. 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

  17. 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

  18. 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)

  19. 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

  20. 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

  1. 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)

  2. 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)

  3. 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

  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. 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

  6. 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)

  7. 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

  8. 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

  9. Progressive decommissioning of French nuclear power plants: economic and geopolitical impacts

    International Nuclear Information System (INIS)

    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.)

  10. 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.)

  11. 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

  12. 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

  13. 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

  14. 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.

  15. 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)

  16. 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

  17. 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)

  18. 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

  19. 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)

  20. 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

  1. 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

  2. Decommissioning of French nuclear submarines

    International Nuclear Information System (INIS)

    Robin, B.; Buzonniere, A. de; Chenais, J.

    2003-01-01

    Since the beginning of the sixties, France has developed a fleet of nuclear powered vessels. Insofar as the ships of the 2. generation are being built, the older ones are decommissioned and enter the dismantling process. The average rate is presently one submarine decommissioned every two or three years. The overall strategy for the decommissioning of French nuclear submarines can be brought down to 3 phases: 1. Level 1 dismantling which essentially consists in: - unloading the spent fuel and storing it in a pool ; - possibly emptying the circuits which contain radioactive liquids. The level 1 is easily achieved, as it is not very different from the plant situation during ship overhaul or major refits. 2. Level 2 dismantling which consists in isolating the nuclear reactor compartment from the rest of the submarine and conditioning it for interim storage on a ground facility located inside Cherbourg Naval Dockyard. The rest of the ship is decontaminated, controlled and set for scrap like any conventional submarine. Up to now, the policy has been to keep the reactor compartment in this intermediate storage facility for at least 20 years, a duration calculated to allow enough time for short life corrosion products to disappear and hence, reduce the radioactive dose to workers during the level 3 dismantling operations. 3. Level 3 dismantling of the nuclear reactor compartment after a storage period. These operations consist in cutting into pieces all remaining structures and equipment, conditioning and sending them to ANDRA for disposal. The SSBN Le Redoutable, first French nuclear submarine which was removed from active service en 1991, underwent the first two phases but, forward and stern parts after cutting of the reactor compartment have been sealed and turned into a museum which is now part of 'La Cite de la Mer' in Cherbourg. Among the three other SSBNs removed from active service, two are at the end of phase 1 just before the separation of the reactor

  3. 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.)

  4. 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)

  5. 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

  6. 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)

  7. 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)

  8. 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.)

  9. 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.)

  10. 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.)

  11. Nuclear energy: French government policy

    International Nuclear Information System (INIS)

    1998-01-01

    This report presents the French government policy concerning nuclear energy and alternative sources of energy for the next 10 years. This report overviews the situation of Super-Phenix fast reactor and presents the implications of the 30/12/1999 decree (Bataille's law) about the management of radioactive wastes

  12. Cleaning chemical and mechanical of heat exchangers in french nuclear plants; Limpieza mecanica y quimica de intercambiadores de calor en centrales nucleares francesas

    Energy Technology Data Exchange (ETDEWEB)

    Ruiz, J. t.; Guerra, P.; Carreres, C.

    2013-03-01

    This project was carried out under the frame of the approval of LAINSA as a supplier of EDF in France. The inspection performed on systems called the moisture separator reheaters (GSS) of CPO series reactor of EDF nuclear power plants has shown evidence of significant clogging due to deposits of magnetite inside the tubes of tube bundle. The pressure drop between inlet and outlet of the heating was close to maximum design criterion. This effect could result in equipment damage and loss of plant productivity. The aim of the work was the design, development, approval and implementation of a procedure for un blocking the tubes of the GSS respecting the integrity of materials and ensuring the harmlessness of cleaning procedures. The procedure used was to completely remove magnetite deposits in order to recover a passage diameter and a surface finish equivalent to the origin, thus avoiding the replacement of the GSS and obtaining a considerable reduction of costs. The achieve these objectives we have developed a procedure that is basically a mechanical pre-cleaning of all tubes of the GSS in order to unblock tem, followed by a chemical cleaning where magnetite is dissolved and crawled out of the tube bundle. The main results were: -Corrosion less than 10 microns. 100-110 Kg of magnetite removed by heat exchanger. -Final pressure drop similar to that of new equipment. -Waste water: 70 m{sup 3} per exchanger, which were managed by an authorized waste management company. This procedure has been applied successfully in 14 GSS type heat exchangers in Fessenheim and Bugey nuclear power plants in France between 2009 and 2011. This project demonstrates that the long experience of LAINSA in the Spanish nuclear industry along with the knowledge and experience in chemical cleaning of SOLARCA, have served to successfully work demanding and mature markets such as the French nuclear market, solving the problem of deposits of magnetite with an effective and safe method for the treated

  13. 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.)

  14. 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.)

  15. 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.)

  16. 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.)

  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. 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

  19. Prospects for the French nuclear fuel management

    International Nuclear Information System (INIS)

    Presta, M.; Guiheux, J.M.

    1990-01-01

    In France, the present share of nuclear electricity generation is about 70 percent. In order to reduce fuel costs, EDF, the French utility, is dedicated to improve the management of the reloads for the 50 reactors it has to manage. Several decisions are now on the way. They affect the adjustment of the reloads to the situation of electricity consumption, the development of higher burn-up fuels and 1/4 reloads, and the recycling of reprocessing materials. It results that some new features in the management of the fuel cycle have been developed. That is why, COGEMA and other French fuel cycle companies have prepared some new processes to bring new solutions to the utility needs. First, new flexibilities have been created in the enrichment and fabrication management system in order to procure assemblies to EDF according to its needs with both right enrichment levels and fuel capabilities. Second, the recycling of reprocessing materials has been largely studied and large industrial facilities are now either operating or planned: they deal with conversions in UREP plants, enrichment of reprocessed uranium in EURODIF or by laser process, fabrication for REPU fuels by FRAGEMA or for MOX fuels by COMMOX. COGEMA relies on its experience acquired during the large French nuclear program development that let the company to adapt flexibly to the various EDF fuel management improvements. With this background, COGEMA offers services to foreign customers as well. With all these new features, the French nuclear system is now on a good way to ensure a good transition from the phase of building and development to a phase of sophisticated management and optimized use of French nuclear industrial facilities in the next 20 years. (author). 3 figs

  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. 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

  2. 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

  3. 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

  4. Voluntary Health Registry of French Nationals after the Great East Japan Earthquake, Tsunami, and Fukushima Daiichi Nuclear Power Plant Accident: Methods, Results, Implications, and Feedback.

    Science.gov (United States)

    Motreff, Yvon; Pirard, Philippe; Lagrée, Céline; Roudier, Candice; Empereur-Bissonnet, Pascal

    2016-06-01

    feasible and does not raise adverse side effects in involved people. Motreff Y , Pirard P , Lagrée C , Roudier C , Empereur-Bissonnet P . Voluntary health registry of French nationals after the Great East Japan Earthquake, tsunami, and Fukushima Daiichi Nuclear Power Plant accident: methods, results, implications, and feedback. Prehosp Disaster Med. 2016;31(3):326-329.

  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 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.)

  8. The black book of the French nuclear industry

    International Nuclear Information System (INIS)

    Laurent, J.

    2011-01-01

    Pro-nuclear lobbies, industrialists and politicians have claim for years that nuclear energy is the safest and most ecological energy source. In this book the author reveals the real hazards and the darkest side of the French nuclear industry: cancers and malformations or mutations risks, hidden by government authorities, serious problems due to power plants aging, impact on the environment with the reprocessing of toxic wastes

  9. 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)

  10. Nuclear power plant exports

    International Nuclear Information System (INIS)

    Degot, D.

    1987-01-01

    Framatome export expertise is discussed. Framatome can accept different types of contracts - for the supply of nuclear steam supply systems or for nuclear islands (both of which can be produced solely by Framatome) or for complete plants. Cooperation with the local industry is possible -this can involve technology transfer. Examples of exports in the following countries are given; Belgium (where there is close cooperation between Framatome and two major companies), South Africa (where Framatome has been involved in the building of a two-992 MWe unit at Koeberg), South Korea (where Framatome is building two-900 MWe nuclear islands in cooperation with Korean industry, Knu 9 and Knu 10) and China (where Framatome is to build two-1000 MWe class pressurized water reactors at Daya Bay). As well as supplying the French domestic nuclear market Framatome is a major force in the future of nuclear power in the world. (UK)

  11. 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%

  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. 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

  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. 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.)

  16. 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)

  17. 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

  18. 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

  19. 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.

  20. 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.)

  1. 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.)

  2. 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

  3. The fate of the French civil nuclear

    International Nuclear Information System (INIS)

    Marti, Claude

    2013-01-01

    The author first outlines the importance of improving the control processes and procedures for the whole civil nuclear sector (from construction to dismantling). He identifies the consequences of this requirement for the French control authorities. Then, he discusses the assessment of the useful, needed or unavoidable share of nuclear energy with respect to various challenges: climate change, energy production requirements (how to produce energy at the right place and at the right time). The author finally outlines the importance of efforts to be made in research and development

  4. 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

  5. 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

  6. 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

  7. 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)

  8. 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.)

  9. 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

  10. 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

  11. Nuclear plants: France and the export market

    International Nuclear Information System (INIS)

    Economic contingencies are causing the French industry to expand its activity abroad. After a review of the nuclear industry in France: uranium extraction, enrichment, irradiated fuel reprocessing and France's present programme; the competitive market among countries exporting and countries interested in importing nuclear power plants are examined. Finally France's position in the world nuclear power plant market is outlined with that of its foreign competitors [fr

  12. 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

  13. 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

  14. 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)

  15. 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.)

  16. 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

  17. 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

  18. Submarine nuclear power plants

    International Nuclear Information System (INIS)

    Horton, C.C.

    1984-01-01

    The submarine nuclear power plant has revolutionised the strategy and tactics of under-sea warfare. Present day submarine nuclear power plants are discussed, as well as future developments. The endurance, speed, noise and diving depth of nuclear submarines are also outlined. (U.K.)

  19. 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.)

  20. 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)

  1. 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

  2. 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

  3. 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

  4. 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)

  5. 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…

  6. 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

  7. 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

  8. 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

  9. French statutory approach of the evaluation of the safety level of old nuclear divisions

    International Nuclear Information System (INIS)

    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)

  10. 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.)

  11. 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.)

  12. 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.)

  13. 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

  14. 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

  15. 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

  16. 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)

  17. 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

  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. 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)

  20. 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

  1. 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

  2. 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?.

  3. 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.

  4. 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

  5. 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

  6. 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

  7. 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

  8. 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.

  9. 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)

  10. 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.)

  11. 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)

  12. 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

  13. 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

  14. 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)

  15. 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

  16. 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

  17. 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

  18. 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.)

  19. 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

  20. 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%

  1. 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)

  2. 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

  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. Dictionary of nuclear engineering. English-German-French-Russian

    International Nuclear Information System (INIS)

    Sube, R.

    1985-01-01

    This volume contains nearly 30,000 entries from all branches of nuclear engineering excluding biological aspects, health physics, and isotope applications in medicine and agriculture. The therminology used in the International Nuclear Information System (INIS) of the IAEA has been completely taken into account. Each English entry is numbered and is followed by corresponding terms in the other languages. Alphabetical indexes of the German, French, and Russian terms are included. At the end of the volume, there is a section devoted to the transliteration of place-names between the English names and their Cyrillic equivalents, and vice versa

  5. The 'humane performance' project for the French nuclear power plants; Le projet performance humaine au sein du parc nucleaire francais

    Energy Technology Data Exchange (ETDEWEB)

    Theurier, J.P. [Electricite de France (EDF/DPN/UNIE), 93 - Saint-Denis (France)

    2010-05-15

    In 2006 EDF launched a project called 'human performance' whose aim was to make work practices of 37.000 nuclear workers evolve towards more efficiency and more rigor. In fact the aim is to break the professional routines that are often sources of mistakes and make workers more able to summon up all their capabilities during an intervention. The most innovative step in this project is the implementation of the 'reliability path'. This path is in fact a mental preparation before the intervention and an acute awareness of what is being done during the intervention. A debriefing phase follows the intervention in which the worker reviews the intervention and suggests the points to improve. (A.C.)

  6. 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

  7. Floating nuclear power plants

    International Nuclear Information System (INIS)

    Kindt, J.W.

    1983-01-01

    This article examines the legal regime for floating nuclear power plants (FNPs), in view of the absence of specific US legislation and the very limited references to artificial islands in the Law of the Sea Convention. The environmental impacts of FNPs are examined and changes in US regulation following the Three Mile Island accident and recent US court decisions are described. References in the Law of the Sea Convention relevant to FNPs are outlined and the current status of international law on the subject is analysed. (author)

  8. Obrigheim nuclear power plant

    International Nuclear Information System (INIS)

    1976-05-01

    The gross output of the 345MWe pressurized water nuclear power station at Obrigheim, operation on base load, amounted to about 2.57TWh in 1974, the net power fed to the grid being about 2.44TWh. The core was used to its full capacity until 10 May 1974. Thereafter, the reactor was on stretch-out operation with steadily decreasing load until refuelled in August 1974. Plant availability in 1974 amounted to 92.1%. Of the 7.9% non-availability, 7.87% was attributable to the refuelling operation carried out from 16 August to 14 September and to the inspection, overhaul and repair work and the routine tests performed during this period. The plant was in good condition. Only two brief shutdowns occurred in 1974, the total outage time being 21/2 hours. From the beginning of trial operation in March 1969 to the end of 1974, the plant achieved an availability factor of 85.2%. The mean core burnup at the end of the fifth cycle was 19600 MWd/tonne U, with one fuel element that had been used for four cycles achieving a mean burnup of 39000 MWd/tonne U. The sipping test on the fuel elements revealed defective fuel-rods in a prototype plutonium fuel element, a high-efficiency uranium fuel element and a uranium fuel element. The quantities of radioactive substances released to the environment in 1974 were far below the officially permitted values. In july 1974, a reference preparation made up in the nuclear power station in October 1973 was discovered by outsiders on the Obrigheim municipality rubbish tip. The investigations revealed that this reference preparation had very probably been abstracted from the plant in October 1973 and arrived at the rubbish tip in a most irregular manner shortly before its discovery

  9. 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

  10. 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.

  11. 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

  12. French achievements in the field of nuclear electronics

    International Nuclear Information System (INIS)

    Doireau, M.; Fabre, R.; Guillon, H.; Guyot, C.

    1958-01-01

    Nuclear electronic equipment used by the french Atomic Energy Commission has been developed, with an increasing participation of the radioelectric industry (manufacture under AEC license, contracts for prototypes). The equipment for general use has been standardized and satisfies the technical specification sheets in which are specified more particularly, the conditions for construction, the choice of the spare parts and the conditions for acceptance by the french AEC at factory. The electronic equipment is classified in nine classes, and a brief description of the principal instruments is given in each class. The reliability of the equipment in use is satisfactory, as it is shown by the mean frequency of faults per 1000 hours operation. (author) [fr

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-07-01

    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: 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.)

  14. 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.)

  15. 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.)

  16. 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

  17. 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.)

  18. 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

  19. 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.)

  20. Nuclear power fleet replacement: an opportunity for the French energy mix?

    OpenAIRE

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

    2015-01-01

    International audience; – In France, 27% of the electricity is to be produced by renewable resources by 2020. This share is intended to grow continuously 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 po...

  1. A prospective scenario of the French nuclear fleet growth based on sodium cooled fast reactor technology

    International Nuclear Information System (INIS)

    Garzenne, Claude; Le Mer, Joel; Lemasson, David; Hoang, Manh-Hung

    2011-01-01

    Generation IV Sodium cooled Fast Reactors (SFR) deployment would allow to optimize the use of the various available resources (natural, reprocessed and depleted uranium, plutonium) thanks to breeding capacities featuring a valuable advantage with respect to the fuel cycle flexibility and fissile material management. The complete replacement of the 60 GWe French nuclear fleet by GEN IV SFRs in 2100 would require around 1000 tons of plutonium. An accurate simulation of this prospective scenario shows that the amount of plutonium issued from the French PWRs spent fuel reprocessing would not be enough. The lacking amount of plutonium could be produced with fertile blankets during the transient SFR deployment phase. A more ambitious research scenario, aimed at doubling the nuclear French fleet installed power in 2100, would require to use SFRs at their maximum breeding capacity. However, it is not possible to deploy more than about 100 GWe of SFRs in 2100, meaning that the fleet growth would have to be partially supported by GEN III PWRs. Using the scenario simulation code TIRELIRE-STRATEGIE, we have optimized the main scenario parameters: the capacities of the fuel cycle facilities, the proportion of PWRs necessary for supporting the growth phase, the kinetics of SFRs deployment compatible with the plutonium build-up, etc., while respecting industrial constraints such as a realistic cooling time before reprocessing, a fuel cycle plants utilization rate constant over several decades, etc.. We illustrate the impact of this French fleet growth scenario over the nuclear material fluxes in the fuel cycle plants, the uranium consumption, and the waste production. (author)

  2. 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

  3. Nuclear Power Plant

    Directory of Open Access Journals (Sweden)

    Analia Bonelli

    2012-01-01

    Full Text Available A description of the results for a Station Black-Out analysis for Atucha 2 Nuclear Power Plant is presented here. Calculations were performed with MELCOR 1.8.6 YV3165 Code. Atucha 2 is a pressurized heavy water reactor, cooled and moderated with heavy water, by two separate systems, presently under final construction in Argentina. The initiating event is loss of power, accompanied by the failure of four out of four diesel generators. All remaining plant safety systems are supposed to be available. It is assumed that during the Station Black-Out sequence the first pressurizer safety valve fails stuck open after 3 cycles of water release, respectively, 17 cycles in total. During the transient, the water in the fuel channels evaporates first while the moderator tank is still partially full. The moderator tank inventory acts as a temporary heat sink for the decay heat, which is evacuated through conduction and radiation heat transfer, delaying core degradation. This feature, together with the large volume of the steel filler pieces in the lower plenum and a high primary system volume to thermal power ratio, derives in a very slow transient in which RPV failure time is four to five times larger than that of other German PWRs.

  4. 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

  5. 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

  6. 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.)

  7. The French nuclear program: national prospects, international cooperation; Le programme nucleaire francais: perspectives nationales, cooperations internationales

    Energy Technology Data Exchange (ETDEWEB)

    Lacoste, A. [Direction de la Surete des Installations Nucleaires (DSIN), 75 - Paris (France); Joint-Lambert, V.; Breard, G.; Jolly, B. [FRAMATOME, 92 - Paris-La-Defense (France); Durret, L.F.; Capus, G.; Lebastard, G. [Cogema, 78 - Velizy-Villacoublay (France); Ouzounian, G. [Agence Nationale pour la Gestion des Dechets Nucleaire, ANDRA, 92 - Chatenay-Malabry (France); Bouteille, F. [Nuclear Power International, (Country Unknown); Appell, B. [Electricite de France (EDF), 92 - Courbevoie (France). Service Etudes et Projets Thermiques et Nucleaires; Baret, J.P.; Esteve, B. [Electricite de France (EDF), 75 - Paris (France); Peyran, J.C. [Fragema, 69 - Lyon (France); Monnet, F. [Technicatome, Centre d`Etudes Nucleaires de Saclay, 91 - Gif-sur-Yvette (France); Caoul, A. [CNESTEN, (Morocco)

    1998-08-01

    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)

  8. 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.)

  9. 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

  10. 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.

  11. 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

  12. 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.)

  13. 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)

  14. 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

  15. The French civilian nuclear: connections and stakes; Le nucleaire civil francais: filieres et enjeux

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2010-07-01

    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

  16. 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)

  17. Systematic evaluation of safety in old nuclear power plants

    International Nuclear Information System (INIS)

    Dredemis, G.; Fourest, B.

    1984-11-01

    A systematic evaluation program of the early nuclear power plant has been conducted by the French safety authorities. This examination is concerned with the remodelling of safety documents (safety reports, operation general regulations, incident and accident procedures, internal emergency plans and organization manuals for quality), with an analysis of the operating experience in frequently utilized circuits and with a systematic analysis of safeguards circuits. These evaluations are based on the experience of the Ardennes nuclear power plant, operating 15 years. This paper also describes the main studies and modifications undertaken in this power plant [fr

  18. Systematic safety analysis of old nuclear power plants

    International Nuclear Information System (INIS)

    Dredemis, G.

    1985-11-01

    A program of systematic safety analysis of old nuclear power plants has been engaged by French safety authorities. Beyond the reshaping of safety documents (safety reports, general rules of operation, incidental and accidental procedures, internal emergency plan and manual of quality organization), this examination consisted of an analysis of the operation experience of circuits frequently actuated and a systematic analysis of safety circuits. This paper is based on the presentation of the exercise carried out at the Ardennes nuclear power plant operating for 15 years. This paper reviews also the main studies and modifications engaged on this power plant [fr

  19. 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.)

  20. 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

  1. 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)

  2. 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

  3. 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.)

  4. 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

  5. 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.

  6. 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

  7. 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

  8. 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.)

  9. [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.

  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. 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

  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. 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.)

  14. Robots for nuclear power plants

    International Nuclear Information System (INIS)

    Moore, T.

    1985-01-01

    In many industrial applications of robots, the objective is to replace human workers with machines that are more productive, efficient, and accurate. But for nuclear applications, the objective is not so much to replace workers as it is to extend their presence - for example, to project their reach into areas of a nuclear plant where the thermal or radiation environment prohibits or limits a human presence. The economic motivation to use robots for nuclear plant inspection and maintenance is centered on their potential for improving plant availability; a by-product is the potential for reducing the occupational radiation exposure of plant personnel. Robotic equipment in nuclear applications may be divided into two broad categories: single-purpose devices with limited ability to perform different operations, and reprogrammable, multi-purpose robots with some degree of computer-based artificial intelligence. Preliminary assessments of the potential for applying robotics in nuclear power plants - mainly at surveillance and inspection tasks - have been carried out. Future developments are considered

  15. 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

  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. 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

  19. 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

  20. 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)

  1. Future of nuclear power plants and reactor dismantling

    International Nuclear Information System (INIS)

    Tanguy, P.; Cregut, A.

    1994-01-01

    After some considerations on dismantling experience, technology, legislation and costs, the various causes for dismantling a reactor are reviewed (research program termination, plant obsolescence, ageing and safety problems) and the present and future situation concerning the French nuclear park is examined. The various tools, equipment and techniques for reactor dismantling and the related researches are presented: cutting techniques, decontamination techniques, remote control, robotics and automation, waste processing and conditioning

  2. 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)

  3. 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)

  4. The French nuclear development program a success today, an asset for the future

    International Nuclear Information System (INIS)

    Guilhamon, J.

    1986-10-01

    The two oil crises induced France to take up a triple challenge: limiting the cost of the country's energy supply, reducing its dependency on foreign energy supplies and diversifying its sources of supply. From this triple point of view, nuclear electricity rapidly emerged as a key factor in the French energy policy. In that consideration, France has been making a major effort in restructuring its electricity supply system since 1974. Its effort is now bearing fruit. From a technical standpoint, 40 GWe of nuclear power are already commissioned, accounting for 65% of the electricity generated. As for power plants themselves or the fuel cycle, the results, relating to the management of costs, availability and environmental preservation confirm the validity of the general orientations taken. Since electricity in France relies, to a large extent on nuclear energy, it is available, competitive and entails foreign currency savings. The future development of nuclear power in the electricity generation system is basically dependent on domestic demand for electricity. This trend will be mainly based on electricity penetration in different economic energy sectors as a substitute for imported fuels. A study of past and present trends illustrate the potential of nuclear electricity and the problems related to its output. The successful implementation of a major programme necessitates mastering the technology by undertaking research and development work at the proper time. Design requires a long period of time, and planning should be carried out on a long-term basis. Research undertaken today relating to fast breeder reactors which could do away with uranium supply constraints, plays a determinant role in the future of the system. The assertion and extension of the role played by nuclear electricity necessitates the follow up of research and development programmes for improving the present systems, especially the PWR, developing fuel cycle plants and designing new systems

  5. 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

  6. 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

  7. 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)

  8. Nuclear power plant

    International Nuclear Information System (INIS)

    Amamiya, Shu; Inagaki, Shuichi; Suzuki, Yasuhiro.

    1992-01-01

    The plant of the present invention can suppress the amount of clad in feedwater when drains of a moisture content separation heater or a high pressure feedwater heater are recovered. That is, the moisture content separation heater has ferrite or austenite type stainless steel heat transfer pipes. A chromium-enriched layer is formed on the surface of the heat transfer pipe by chromizing treatment or flame spraying. Then, a stainless steel heat transfer pipe having chromium-enriched layer is incorporated to at least one of the moisture content separation heater or the high pressure feedwater heater. During plant operation, the temperature of heated steams is as high as 235 to 282degC. Accordingly, this is a severe corrosion region for ferrite or austenite stainless steel. However, the chromium-enriched layer of excellent corrosion resistance is formed on the surface of the heat transfer pipe. Accordingly, metal ingredients are less leached. As a result, even if the drains are recovered to feedwater, increase of concentration of the clads in the feedwater can be prevented. (I.S.)

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

    International Nuclear Information System (INIS)

    Bitsch, D.

    1985-01-01

    Improvement of nuclear island design to facilitate maintenance and working conditions during plant shutdown has been a subject of particular attention in the French PWR programme. Standardization and industrial concentration created an unusually favourable situation for approaching this objective. Progress efforts supported by the feedback of actual operating experience were pursued in areas of plant layout equipment installation, and on the design and technology of the components themselves. When compared with units of the three-loop series currently in operation, the evolution of the latest nuclear island designs covers such layout features as better segregation and separation between systems, easier access in special areas, installation of new cleaning systems, etc. Progress efforts on the design and technology of components were pursued along several paths including: (a) the increase in resistance of specific parts submitted to various forms of in-service degradation, for example, steam generator tubes, reactor coolant pump seals, reactor control cluster drive lines and some auxiliary equipment; (b) reduction of the extent and duration of work during plant outages (fuel handling, in-service inspection, maintenance) by facilitating disassembly, removal, handling and storage of equipment parts; (c) reduction of occupational radiation exposure, one of the most important axes of development, by the appropriate selection of less activity-releasing materials such as Inconel 690 for the steam generator tubes, implementation of more efficient decontamination systems and use of robots. (author)

  10. 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

  11. Current status of the EPR (european pressurized reactor) program developed jointly by german and French nuclear industry

    International Nuclear Information System (INIS)

    Pouget-abadie, X.; Lallier, M.; Lauret, P.; Schneider, D.

    2000-01-01

    The Basic Design of the EPR is now completed and all the tasks, which were foreseen as part of this franco-german cooperation, came to a conclusion. At the origin of this project was the common decision in 1989 of Framatome and Siemens to cooperate through NPI, to design the Nuclear Island which meets the future needs of utilities. EDF and a group of the main German Utilities joined this cooperation in 1991 and since then have been totally involved to the progress of the the work. In addition, all the process was backed up to the end of 1998 by the strong cooperation between the French and the German Safety Authorities which have a long lasting cooperation to define common requirements which have to be applied to future Nuclear Power Plant. end of 2000, the French Safety Authorities are expected to issue their final recommendations

  12. The Next Generation Nuclear Plant

    Energy Technology Data Exchange (ETDEWEB)

    Dr. David A. Petti

    2009-01-01

    The Next Generation Nuclear Plant (NGNP) will be a demonstration of the technical, licensing, operational, and commercial viability of High Temperature Gas-Cooled Reactor (HTGR) technology for the production of process heat, electricity, and hydrogen. This nuclear- based technology can provide high-temperature process heat (up to 950°C) that can be used as a substitute for the burning of fossil fuels for a wide range of commercial applications (see Figure 1). The substitution of the HTGR for burning fossil fuels conserves these hydrocarbon resources for other uses, reduces uncertainty in the cost and supply of natural gas and oil, and eliminates the emissions of greenhouse gases attendant with the burning of these fuels. The HTGR is a passively safe nuclear reactor concept with an easily understood safety basis that permits substantially reduced emergency planning requirements and improved siting flexibility compared to other nuclear technologies.

  13. BWR type nuclear plant

    International Nuclear Information System (INIS)

    Fujita, Yoshio; Okano, Kimifumi; Sasaki, Hiroshi; Okura, Minoru

    1998-01-01

    The present invention provides a BWR plant capable of reducing the size of the reactor building while maintaining reliability of a pool water cooling and cleaning facility even when two fuel storage pools are disposed in the reactor building. Namely, in the reactor building, two fuel storage pools, a temporality storing pool for temporary storing incore structures and a suppression pool are disposed. A primary cleaning facility for cooling and cleaning pool water for each of fuel storage pools comprises a serge tank, a pump, a heat exchanger and a filtration desalting device. A secondary cleaning facility for cleaning pool water in the suppression pool comprises a pump and a filtration desalting device. The first cleaning facility can be switched to be used for the secondary cleaning facility. Specifically, upstream and downstream of the pump of the primary cleaning facility and those of the pump of the secondary cleaning facility are connected by communication pipelines. (I.S.)

  14. French Nuclear Power Generation Program: The Industrial Achievements; Le Programme Electronucleaire Francais: Realisations industrielles

    Energy Technology Data Exchange (ETDEWEB)

    Dupraz, B. [Societe Francaise d' Energie Nucleaire (SFEN), 75 - Paris (France); Lacoste, A.C. [Direction de la Surete des Installations Nucleaires (DSIN), 75 - Paris (France); Merle, P. [Bureau de Controle des Chaudieres Nucleaires (BCCN), 75 - Paris (France); Scherrer, J. [Commission Centrale des Appareils a Pression (CCAP), 75 - Paris (France); Stricker, L. [Electricite de France (EDF), 75 - Paris (France). Div. Production Nucleaire; Joint-Lambert, V. [FRAMATOME, 92 - Paris-La-Defense (France); Montalembert, A. de [Cogema, 78 - Velizy-Villacoublay (France); Flament, T.A.; Hubert, X. [Numatec Hanford Corporation (NHC), Richland-Washington (United States); Zaccai, H. [SGN Reseau Eurisys, 78 - Saint Quentin (France); Ouzounian, G. [Agence Nationale pour la Gestion des Dechets Nucleaires (ANDRA), 92 - Chatenay-Malabry (France); Voin, R. [Groupe Intersyndical de l' Industrie Nucleaire (GIIN), 75 - Paris (France)

    1999-09-01

    The 're-opening' issue (no 4) of RGN is devoted, each year, to the situation of the French nuclear power generation program under several aspects (achievements, operation, safety, maintenance, fuel cycle, waste management, etc.). This issue is very similar, but more particularly dedicated to the industrial aspects of the program. Thus, in parallel with scientific and technical topics, the issue deals with several subjects (nuclear competitiveness, plutonium management, cleanup of nuclear sites, etc.) from the economic and industrial standpoint, and with the situation of medium- and small-size French nuclear companies. (author)

  15. Proposition of resolution aiming at the creation of an inquiry commission relative to the safety of the french nuclear installations and the protection of inhabitants face to the risks of radioactive contaminations coming to uranium leakages or any other product used in the nuclear power plants and the radioactive waste storage facilities

    International Nuclear Information System (INIS)

    2007-01-01

    This commission will have for mission to establish the facts relative to the Tricastin accident and the previous pollutions around this site; to appreciate the delay, the transparency and the public information modalities, both by the company and by the authorities; to establish a systematic and precise statement of the radioactive contaminations on the sites and around the french nuclear facilities ( included the waste storage sites); to measure the ecological damages on the ecosystems and the sanitary risks for the populations; to evaluate the prevention programmes management and the safety of these facilities; to identify the dysfunctions of the french nuclear sector and give propositions to improve the safety of these facilities. (N.C.)

  16. 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)

  17. Nuclear power plants: structure and function

    International Nuclear Information System (INIS)

    Hendrie, J.M.

    1983-01-01

    Topics discussed include: steam electric plants; BWR type reactors; PWR type reactors; thermal efficiency of light water reactors; other types of nuclear power plants; the fission process and nuclear fuel; fission products and reactor afterheat; and reactor safety

  18. 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

  19. 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)

  20. 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.

  1. 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

  2. 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)

  3. 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

  4. 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

  5. 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

  6. 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

  7. 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

  8. 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.)

  9. 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

  10. 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)

  11. 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.

  12. 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

  13. 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

  14. 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

  15. 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)

  16. 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

  17. 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

  18. International geomechanical commission. Underground nuclear testing in French Polynesia: stability and hydrology issues

    International Nuclear Information System (INIS)

    1999-01-01

    The International Geomechanical Commission is an independent group of experts in rock mechanics and hydrology. This commission has carried out a study on the rocks stability and hydrology of the atolls of Mururoa and Fangataufa (French Polynesia) after the stoppage of the French underground nuclear tests (147 tests all of all, from which 6 took place in 1995 and 1996). This book presents the results of this study. (J.S.)

  19. 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

  20. 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

  1. 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

  2. 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.)

  3. 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.)

  4. Nuclear power plants in the world

    International Nuclear Information System (INIS)

    2007-01-01

    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 2005 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; 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.)

  5. 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.)

  6. 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)

  7. 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.)

  8. Licensing of nuclear power plants

    International Nuclear Information System (INIS)

    Witt, S. de.

    1984-01-01

    De Witt, who as an advocate represents the interests of citizen's initiatives in lawsuits concerning nuclear power plants, contests an independent scope of discretion of the administration and criticizes the reduction of the control density of courts which can be noticed recently. The shift of emphasis from the courts to the administration would not only change the balance within the constitutional separation of powers but could also lead to a weakening of the protection of fundamental rights. When assessing the technical risks he wants above all to take into account the possible extent of the damage. De Witt also shows that - beyond the discretion of refusal according to section 7 of the Atomic Energy Act and the exertion of influence of the executive on public utilities - it could be possible to develop means - not used until now - to control the social impacts of nuclear energy. (orig./HSCH) [de

  9. 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.)

  10. 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

  11. 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.

  12. 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

  13. 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

  14. All nuclear: a French exception; Tout nucleaire: une exception francaise

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-07-01

    This little book, written by a nuclear opponent, explains how and why France has become one of the only European countries that has developed nuclear energy as the main energy source for power generation. It denounces the hypocrisy of the official talk, the economical logics, the political manipulation and the lack of information about the real risks linked with nuclear wastes.

  15. 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.)

  16. 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

  17. 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)

  18. Assessment of hydrogen risk in French pressurized water nuclear reactors

    International Nuclear Information System (INIS)

    Duco, J.; Rousseau, L.; Evrard, J.M.

    1983-12-01

    During the course of a severe core accident, hydrogen evolving, mainly due to zircaloy cladding-steam reaction, may form early a flammable mixture in the containment. The risk of a short-term containment failure due to a hydrogen explosion, which would result in a large radioactivity release into the environment, is currently being assessed for the various types of large dry containments existing for French PWRs. In this framework, comparisons between pressure peaks, due to the most severe conceivable hydrogen deflagration, and the realistic ultimate strength of French containment buildings have led to the conclusion that containment integrity should not be questioned. However the problem of the likehood of local detonations and of their impact on structures is still examined. Another aspect of the hydrogen risk is the possible impairment of safety-related equipment in the containment during an eventual hydrogen combustion or explosion. Information coming from the EPRI research program on hydrogen combustion and control, in which the safety body (CEA/IPSN) and the utility (EDF) jointly took a participation, is to back up our own studies on hydrogen risk analysis. Up to now all the results gathered as regards the integrity of the large, dry containments of the French PWRs against hydrogen explosion tend to relegate such a risk to the level of a residual risk. Although the studies are going on a drastic change of this trend in the future is not expected. Therefore no hydrogen specific design modification is presently required by the safety authorities

  19. 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.

  20. 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

  1. 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.)

  2. 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

  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. 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

  5. Nuclear energy: French government policy; Politique nucleaire et diversification energetique: orientations gouvernementales

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-02-02

    This report presents the French government policy concerning nuclear energy and alternative sources of energy for the next 10 years. This report overviews the situation of Super-Phenix fast reactor and presents the implications of the 30/12/1999 decree (Bataille's law) about the management of radioactive wastes.

  6. 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

  7. 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

  8. 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

  9. 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

  10. 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.)

  11. 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.)

  12. 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

  13. Appraisal of nuclear power plant reliability

    International Nuclear Information System (INIS)

    Applegren, G.H.; Beckwith, R.; Jakubowski, C.L.; Whysong, J.L.; Rossin, A.D.

    1975-01-01

    The performance of large power plants at Commonwealth Edison is evaluated. There are seven nuclear units with a total capacity of about 5500 MW(e); six of the units are 800 MW(e) in size or larger. Fossil-fired capacity totals about 10,600 MW, primarily coal-fired. There are five coal-fired units 600 MW in size or larger. All large units have been installed since 1964. It is found that the nuclear plants in the system are more economical than coal-fired plants even at capacity factors well below 65 percent; that the nuclear plants have slightly better availability than the fossil plants; and that system characteristics have a strong influence on the performance of all of the plants. A cost comparison is shown of electric power generation from nuclear, a combination of Illinois and Western coal, and Western coal plants. (U.S.)

  14. 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

  15. 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

  16. 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

  17. Preventive fire protection in nuclear power plants

    International Nuclear Information System (INIS)

    Kordina, K.; Dobbernack, R.

    1988-01-01

    Fire risk considerations in nuclear power plants and questions of preventive fire protection have so far not been dealt with sufficient attention. For this reason a research program was proposed and financed by the government of the Federal Republic of Germany in order to clarify these questions and to optimise preventive fire protection measures especially in nuclear power plants. (orig.)

  18. 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.)

  19. 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)

  20. 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

  1. 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)

  2. Handbook on Nuclear Law: Implementing Legislation (French Edition)

    International Nuclear Information System (INIS)

    Stoiber, C.; Cherf, A.; Tonhauser, W.; Vez Carmona, Maria de Lourdes

    2011-01-01

    In 2003, the IAEA published the Handbook on Nuclear Law (the 2003 Handbook), which emphasized that the safe and peaceful uses of nuclear energy in any State can only be ensured with the promulgation and implementation of an effective national legal framework to govern this technology. The IAEA has long been involved in providing assistance to its Member States in developing these frameworks, and demand for such assistance has increased dramatically. Since publication of the 2003 Handbook, requests for IAEA legislative assistance have - if anything - been even more numerous, in large part due to the fact that over sixty Member States that currently do not utilize nuclear energy for the production of electrical power have recently expressed interest in pursuing this option. The current nuclear laws in many of these States are limited to non-power uses of ionizing radiation, such as those utilizing radiation sources for medical, agricultural and industrial purposes. If these States move toward nuclear power development, they will need to adopt legislation consistent with the various relevant international legal instruments covering the field (such as the Convention on Nuclear Safety and the Convention on the Physical Protection of Nuclear Material, among others) and with relevant voluntary guidance documents developed under the aegis of the IAEA. The 2003 Handbook has already made an important contribution to enhancing national capabilities to develop the necessary legal frameworks by setting out the general scheme of nuclear law. However, a number of important developments in nuclear law have occurred since its publication. These developments are discussed in the present volume. Also, over the past six years, representatives of many Member States receiving IAEA legislative assistance have suggested that it would be valuable to develop model texts of legislative provisions covering the key elements needed in a national nuclear law. The present volume provides such

  3. Nuclear power plants in electric power system

    International Nuclear Information System (INIS)

    Leicman, J.; Vokurka, F.

    1985-01-01

    The paper analyzes the demands placed by the power system on operating qualities of nuclear power plants with regard to the prospective tasks of nuclear power in the Czechoslovak power system. The characteristics of the operation of Czechoslovak nuclear plants are given taking into account the frequency and voltage deviations of the network, operating and control properties of nuclear power plants with WWER-440 and WWER-1000 reactors considering the technical conditions of operation, the required operating schedule of a nuclear power plant unit. For comparison, the demands are summed up of foreign power systems as are the control properties of foreign nuclear power units in regulating output, regulating delivered electric power and in emergency states of the system. Recommendations for further research and development are drawn from the data. (author)

  4. 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

  5. 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.

  6. 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)

  7. Draft Revised Agreement Between the Government of the French Republic and the European Organization for Nuclear Research concerning the Legal Status of the Said Organization in France - Changes to be made to the English and French Texts of the Draft

    CERN Document Server

    1972-01-01

    Draft Revised Agreement Between the Government of the French Republic and the European Organization for Nuclear Research concerning the Legal Status of the Said Organization in France - Changes to be made to the English and French Texts of the Draft

  8. 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

  9. 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

  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. 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. 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)

  13. Effects of nuclear electromagnetic pulse (EMP) on nuclear power plants

    International Nuclear Information System (INIS)

    Barnes, P.R.; Manweiler, R.W.; Davis, R.R.

    1977-09-01

    The electromagnetic pulse (EMP) from a high-altitude nuclear detonation consists of a transient pulse of high intensity electromagnetic fields. These intense fields induce current and voltage transients in electrical conductors. Although most nuclear power plant cables are not directly exposed to these fields, the attenuated EMP fields that propagate into the plant will couple some EMP energy to these cables. The report predicts the probable effects of the EMP transients that could be induced in critical circuits of safety-related systems. It was found that the most likely consequence of EMP for nuclear plants is an unscheduled shutdown. EMP could prolong the shutdown period by the unnecessary actuation of certain safety systems. In general, EMP could be a nuisance to nuclear power plants, but it is not considered a serious threat to plant safety

  14. 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

  15. 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)

  16. Uranium contamination due to nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Martin Sanchez, A.; Vera Tome, F.; Diaz Bejarano, J.; Garcia Aparicio, A. (Univ. de Extremadura, Badajoz (Spain). Dept. de Fisica)

    1992-01-01

    Measurements of uranium isotopes and their daughters in the natural series were performed in the cooling reservoirs and their neighborhood of two nuclear power plants, [alpha] and [gamma] spectrometry of samples were used to measure the natural and artificial radionuclides. The nuclear power plants are in the southwest of Spain and one of them has been in operation since 1982, the other plant is in the construction phase. We compare the results obtained for the two sites. (orig.).

  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. 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

  19. 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)

  20. Nuclear Power Plants in the World

    International Nuclear Information System (INIS)

    2000-01-01

    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 'Developmental trends on nuclear power plants in the world'. In this report, some data at the end of 1999 was made up on bases of answers on questionnaires from 72 electric companies in 31 nations and regions in 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; location of the plants; the plants in the world; and so forth. And, it also has some survey results on the 'Liberalization of electric power markets and nuclear power generation' such as some 70% of respondents in nuclear power for future option, gas-thermal power seen as power source with most to gain from liberalization, merits on nuclear power generation (environmental considerations and supply stability), most commonly voiced concern about new plant orders in poor economy, and so forth. (G.K.)

  1. Seismic reevaluation of existing nuclear power plants

    International Nuclear Information System (INIS)

    Hennart, J.C.

    1978-01-01

    The codes and regulations governing Nuclear Power Plant seismic analysis are continuously becoming more stringent. In addition, design ground accelerations of existing plants must sometimes be increased as a result of discovery of faulting zones or recording of recent earthquakes near the plant location after plant design. These new factors can result in augmented seismic design criteria. Seismic reanalysius of the existing Nuclear Power Plant structures and equipments is necessary to prevent the consequences of newly postulated accidents that could cause undue risk to the health or safety of the public. This paper reviews the developments of seismic analysis as applied to Nuclear Power Plants and the methods used by Westinghouse to requalify existing plants to the most recent safety requirements. (author)

  2. Nuclear plant data systems - some emerging directions

    International Nuclear Information System (INIS)

    Johnson, R.D.; Humphress, G.B.; McCullough, L.D.; Tashjian, B.M.

    1983-01-01

    Significant changes have occurred in recent years in the nuclear power industry to accentuate the need for data systems to support information flow and decision making. Economic conditions resulting in rapid inflation and larger investments in new and existing plants and the need to plan further ahead are primary factors. Government policies concerning environmental control, as well as minimizing risk to the public through increased nuclear safety regulations on operating plants are additional factors. The impact of computer technology on plant data systems, evolution of corporate and plant infrastructures, future plant data, system designs and benefits, and decision making capabilities and data usage support are discussed. (U.K.)

  3. Surveillance system for nuclear power plants

    International Nuclear Information System (INIS)

    Mizeracki, M.T.

    1981-01-01

    This paper describes an integrated surveillance system for nuclear power plant application. The author explores an expanded role for closed circuit television, with remotely located cameras and infrared scanners as the basic elements. The video system, integrated with voice communication, can enhance the safe and efficient operation of the plant, by improving the operator's knowledge of plant conditions. 7 refs

  4. Seismic detectors for nuclear power plant

    International Nuclear Information System (INIS)

    Sumida, Susumu; Matsumoto, Takuji; Gunyasu, Kenzo; Tanabe, Akira.

    1979-01-01

    Purpose: To improve the safety of a nuclear power plant by placing seismic detectors in the periphery of the nuclear power plant at the position capable of sensing the seismic waves at least 2 seconds before they arrive at the power plant, and reducing the reactor power by a scram setter upon reception of the seismic waves. Constitution: Seismic detectors are plated on a same circle around the nuclear power plant at a distance capable of detecting seismic waves before they arrive at the power plant, and they are connected to a scram setter. When the detectors detect the seismic waves, which exceeds a predetermined set value for the scram, the scram setter actuated control rod drives, by which control rods are inserted in the nuclear reactor to reduce its output power, as well as prevents external disturbances such as turbine trips. (Yoshino, Y.)

  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. Nuclear power plant's safety and risk

    International Nuclear Information System (INIS)

    Franzen, L.F.

    1975-01-01

    Starting with a comprehensive safety strategy as evolved over the past years and the present legal provisions for the construction and operation of nuclear power plants, the risk of the intended operation, of accidents and unforeseen events is discussed. Owing to the excellent safety record of nuclear power plants, main emphasis in discussing accidents is given to the precautionary analysis within the framework of the licensing procedure. In this context, hypothetical accidents are mentioned only as having been utilized for general risk comparisons. The development of a comprehensive risk concept for a completely objective safety assessment of nuclear power plants remains as a final goal. (orig.) [de

  7. Safety assessment principles for nuclear plants

    International Nuclear Information System (INIS)

    1992-01-01

    The present Safety Assessment Principles result from the revision of those which were drawn up following a recommendation arising from the Sizewell-B enquiry. The principles presented here relate only to nuclear safety; there is a section on risks from normal operation and accident conditions and the standards against which those risks are assessed. A major part of the document deals with the principles that cover the design of nuclear plants. The revised Safety assessment principles are aimed primarily at the safety assessment of new nuclear plants but they will also be used in assessing existing plants. (UK)

  8. Methods of assessing nuclear power plant risks

    International Nuclear Information System (INIS)

    Skvarka, P.; Kovacz, Z.

    1985-01-01

    The concept of safety evalution is based on safety criteria -standards or set qualitative values of parameters and indices used in designing nuclear power plants, incorporating demands on the quality of equipment and operation of the plant, its siting and technical means for achieving nuclear safety. The concepts are presented of basic and optimal risk values. Factors are summed up indispensable for the evaluation of the nuclear power plant risk and the present world trend of evaluation based on probability is discussed. (J.C.)

  9. Nuclear power plant cable materials :

    Energy Technology Data Exchange (ETDEWEB)

    Celina, Mathias C.; Gillen, Kenneth T; Lindgren, Eric Richard

    2013-05-01

    A selective literature review was conducted to assess whether currently available accelerated aging and original qualification data could be used to establish operational margins for the continued use of cable insulation and jacketing materials in nuclear power plant environments. The materials are subject to chemical and physical degradation under extended radiationthermal- oxidative conditions. Of particular interest were the circumstances under which existing aging data could be used to predict whether aged materials should pass loss of coolant accident (LOCA) performance requirements. Original LOCA qualification testing usually involved accelerated aging simulations of the 40-year expected ambient aging conditions followed by a LOCA simulation. The accelerated aging simulations were conducted under rapid accelerated aging conditions that did not account for many of the known limitations in accelerated polymer aging and therefore did not correctly simulate actual aging conditions. These highly accelerated aging conditions resulted in insulation materials with mostly inert aging processes as well as jacket materials where oxidative damage dropped quickly away from the air-exposed outside jacket surface. Therefore, for most LOCA performance predictions, testing appears to have relied upon heterogeneous aging behavior with oxidation often limited to the exterior of the cable cross-section a situation which is not comparable with the nearly homogenous oxidative aging that will occur over decades under low dose rate and low temperature plant conditions. The historical aging conditions are therefore insufficient to determine with reasonable confidence the remaining operational margins for these materials. This does not necessarily imply that the existing 40-year-old materials would fail if LOCA conditions occurred, but rather that unambiguous statements about the current aging state and anticipated LOCA performance cannot be provided based on

  10. Accounting for maintenance in the design of nuclear power plants

    International Nuclear Information System (INIS)

    Meuwisse, C.; Martin-Mattei, C.; Hamon, L.

    1997-01-01

    The objective of the CIDEM project (French acronym for Design Integrating Availability, Operating Experience and Maintenance) is to control the per-kW production cost of future Electricite de France REP 2000 nuclear plants. In particular, such cost control requires accounting for maintenance and logistic support from the time of design of the future installations. This technical and economic optimization is based on assessment and comparison of possible choices in terms of materials and maintenance, and on the search for potential improvements. In the Basic Design phase, the method involves identifying reference components which are supposed highly similar to the components to be designed. In the Construction phase, it culminates in the early definition of a detailed maintenance and support plant. To be effective, the approach requires realistic tailoring of the studies to be undertaken, and the participation of multidisciplinary teams working in the framework of concurrent engineering. (author)

  11. 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.)

  12. 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)

  13. Intelligent operation system for nuclear power plants

    International Nuclear Information System (INIS)

    Morioka, Toshihiko; Fukumoto, Akira; Suto, Osamu; Naito, Norio.

    1987-01-01

    Nuclear power plants consist of many systems and are operated by skillful operators with plenty of knowledge and experience of nuclear plants. Recently, plant automation or computerized operator support systems have come to be utilized, but the synthetic judgment of plant operation and management remains as human roles. Toshiba is of the opinion that the activities (planning, operation and maintenance) should be integrated, and man-machine interface should be human-friendly. We have begun to develop the intelligent operation system aiming at reducing the operator's role within the fundamental judgment through the use of artificial intelligence. (author)

  14. Problems facing a first nuclear power plant

    International Nuclear Information System (INIS)

    Diaz, E.

    1986-01-01

    Requirement of nuclear power generation. Reason for considering a nuclear power programme. Decision to 'go nuclear'. Existing antecedents in the country (nuclear research institution, conventional generating plants, other nuclear utilities). - First organizational steps. Feasibility studies. Site selection and power module. Eventual reactor type decision. Site approval. - Pre-purchasing activities. Eventual selection of a consultant. Domestic participation capabilities. Pre-qualification bids. - Definition of contract type and scopes. Turn-key/non-turn-key. Architect Engineer organization. Bidding documentation. Financing. Warranties. Role of the owner. Licensing procedures and regulations. (orig./GL)

  15. Environmental and security challenges of nuclear plants

    International Nuclear Information System (INIS)

    Omar, A.S.

    2014-01-01

    The world population increase, the acceleration of global requirement for development and the need to expand energy production, have led to the depletion of natural resources. The international efforts are increasing to get clean, safe and economical energy sources . The electricity generated from nuclear energy considers less polluting and high economic competitiveness as well as reliability and efficiency. The nuclear power plants projects face significant challenges, especially after two major accidents, in Chernobyl 1986 and Fukushima 2011 including the fears of radiation effects, nuclear waste management and nuclear proliferation issues, as well as the lack of public acceptance. So those bodies interested in operating nuclear power plants work to increase nuclear safety standards, review the nuclear facilities safety, know the strict application of laws, seek to prove the economic competitiveness, maintain environmental security, assist in the nonproliferation regime and gain public acceptance. This article discusses the most important environmental and security challenges of nuclear power plants. It highlights the importance of the peaceful uses of nuclear energy as a source of sustainable development and environmental security. It also offers a number of recommendations to support the Arab countries trend towards the inclusion of nuclear energy option within their national programs to generate electricity. (author)

  16. Training program for nuclear power plant personnel

    International Nuclear Information System (INIS)

    Sugihara, M.; Ikeda, K.; Shinomiya, Y.; Hada, M.

    1987-01-01

    Nuclear power generation in Japan reached 24.7% of its electric power supply with its capacity and time availability factors of 76.2% and 77.1%, respectively (in the calendar year 1986 - as of December 31, 1986). One of the reasons for such high performance is attributable to high quality of operating and maintenance personnel in the nuclear power plants. Ministry of International Trade and Industry of the Japanese Government has an overall responsibility with relation to the safety regulations and supervises all scope of training, while the Thermal and Nuclear Power Engineering Society is authorized to conduct licensing activities to qualify the chief shift supervisor of nuclear power plant operation and individual utility companies are required to train their plant operating and maintenance personnel. General status of training for plant personnel is briefly described in this paper, touching the practical education and training systems of utility companies and operation and maintenance training facilities

  17. Design quality assurance for nuclear power plants

    International Nuclear Information System (INIS)

    1986-07-01

    This Standard contains the requirements for the quality assurance program applicable to the design phase of a nuclear plant, and is applicable to the design of safety-related equipment, systems, and structures, as identified by the owner. 1 fig

  18. Nuclear power plant V-1, V-2

    International Nuclear Information System (INIS)

    2000-01-01

    In this leaflet the principal scheme of the Bohunice V-1 and V-2 nuclear power plants is presented. Thermal scheme of WWER 440-type NPP (primary circuit, secondary circuit, and cooling water circuit) is described

  19. A trend to small nuclear power plants?

    International Nuclear Information System (INIS)

    Lameira, Fernando Soares

    2000-01-01

    The release of fossil fuel greenhouse gases and the depletion of cheap oil reserves outside the Persic Gulf suggest a promising scenario for the future of nuclear power. But the end of the Cold War, the crisis of the state, axiological questions and globalization may lead to a marked for small power plants. The purpose of this paper is to analyze these factors, since they are not always considered all together in the future scenarios for nuclear power. It is concluded that the current evolutionary trend of nuclear power projects toward big plants may become one of the main barriers for the introduction of new plants in the future. It is suggested that a combination of fission reactors with technologies unavailable in the 1950's, when the design characteristics of the current nuclear power plants were established, could be considered to overcome this barrier. (author)

  20. Environmental hazards from nuclear power plants

    International Nuclear Information System (INIS)

    Bockelmann, D.

    1973-04-01

    The article discusses the radiation exposure due to nuclear power stations in normal operation and after reactor incidents. Also mentioned is the radiation exposure to the emissions from fuel reprocessing plants and radioactive waste facilities. (RW/AK) [de

  1. 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.)

  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. 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.)

  4. Seismic instrumentation for nuclear power plants

    International Nuclear Information System (INIS)

    Senne Junior, M.

    1983-07-01

    A seismic instrumentation system used in Nuclear Power Plants to monitor the design parameters of systems, structures and components, needed to provide safety to those plants, against the action of earth quarks is described. The instrumentation is based on the nuclear standards and other components used, as well as their general localization is indicated. The operation of the instrumentation system as a whole and the handling of the recovered data are dealt with accordingly. The accelerometer is described in detail. (Author) [pt

  5. Structural dynamic analysis of nuclear power plants

    International Nuclear Information System (INIS)

    Halbritter, A.L.; Koishi, N.; Prates, C.L.M.

    1986-01-01

    One of the most important items to be considered in order to guarantee the safety conditions of a Nuclear Power Plant is the design of the civil structures, the electrical and mechanical components and piping system taking into account non-conventional loading cases, e.g. earthquakes and explosions pressure waves. The general procedures used in the structural dynamic analysis of Nuclear Power Plants are presented, specially for seismic and explosion loads. (Author) [pt

  6. Risk analyses of nuclear power plants

    International Nuclear Information System (INIS)

    Jehee, J.N.T.; Seebregts, A.J.

    1991-02-01

    Probabilistic risk analyses of nuclear power plants are carried out by systematically analyzing the possible consequences of a broad spectrum of causes of accidents. The risk can be expressed in the probabilities for melt down, radioactive releases, or harmful effects for the environment. Following risk policies for chemical installations as expressed in the mandatory nature of External Safety Reports (EVRs) or, e.g., the publication ''How to deal with risks'', probabilistic risk analyses are required for nuclear power plants

  7. Report concerning Zarnowiec nuclear power plant

    International Nuclear Information System (INIS)

    Albinowski, S.; Dakowski, M.; Downarowicz, M.

    1990-01-01

    Report of the Team of the President of the National Atomic Energy Agency regarding Zarnowiec nuclear power plant contains the analysis of situation in Poland in June 1990, the assessment of public opinion, as well as the description of ecological, technical and economical problems. The team's conclusions are given together with the general conclusion to stop the construction of Zarnowiec nuclear power plant. 5 appendixes, 6 enclosures, 1 documents list, 1 tab. (A.S.)

  8. Quality assurance organization for nuclear power plants

    International Nuclear Information System (INIS)

    1983-01-01

    This Safety Guide provides requirements, recommendations and illustrative examples for structuring, staffing and documenting the organizations that perform activities affecting quality of a nuclear power plant. It also provides guidance on control of organization interfaces, and establishment of lines for direction, communication and co-ordination. The provisions of this Guide are applicable to all organizations participating in any of the constituent areas of activities affecting quality of a nuclear power plant, such as design, manufacture, construction, commissioning and operation

  9. Approval tests in a nuclear power plant

    International Nuclear Information System (INIS)

    Barreto, V.; Rolf, F.

    1984-01-01

    The supplier contract of a Nuclear Power plant establishes the values of Netto electrical Power, specific heat rate and the steam humidity at the outlet of the steam generator. Based on the Nuclear Plant Angra 2 and 3 (1300 MW) the methodology of evaluation and execution of the tests is shown as well as the location of the measuring instruments and the results of the measurements including tolerances. (Author) [pt

  10. Operation reports of nuclear power plants

    International Nuclear Information System (INIS)

    1983-01-01

    The requirements aiming to standardize the program of nuclear power plant operation report, required by Brazilian Energy Commission - CNEN - to evaluate the activities related to the nuclear technical safety and to the radiation protection during the units operational phase, are showed. (E.G.) [pt

  11. Questions and Answers About Nuclear Power Plants.

    Science.gov (United States)

    Environmental Protection Agency, Washington, DC.

    This pamphlet is designed to answer many of the questions that have arisen about nuclear power plants and the environment. It is organized into a question and answer format, with the questions taken from those most often asked by the public. Topics include regulation of nuclear power sources, potential dangers to people's health, whether nuclear…

  12. Selection procedures for nuclear power plant personnel

    International Nuclear Information System (INIS)

    Kuchler, R.

    1976-01-01

    Selection procedures in reference to experience in staffing two Wisconsin Electric Power Company nuclear project offices and the Point Beach Nuclear Power Plant are discussed. Wisconsin Electric has had a great deal of experience in the application of psychological tests and evaluation procedures, and it was natural that a major consideration in staffing these facilities was the selection of testing procedures

  13. Effort on Nuclear Power Plants safety

    International Nuclear Information System (INIS)

    Prayoto.

    1979-01-01

    Prospects of nuclear power plant on designing, building and operation covering natural safety, technical safety, and emergency safety are discussed. Several problems and their solutions and nuclear energy operation in developing countries especially control and permission are also discussed. (author tr.)

  14. PWR reactors for BBR nuclear power plants

    International Nuclear Information System (INIS)

    Structure and functioning of the nuclear steam generator system developed by BBR and its components are described. Auxiliary systems, control and load following behaviour and fuel management are discussed and the main data of PWR given. The brochure closes with a perspective of the future of the Muelheim-Kaerlich nuclear power plant. (GL) [de

  15. MODELLING OF NUCLEAR POWER PLANT DECOMMISSIONING FINANCING

    Czech Academy of Sciences Publication Activity Database

    Bemš, J.; Knápek, J.; Králík, T.; Hejhal, M.; Kubančák, Ján; Vašíček, J.

    2015-01-01

    Roč. 164, č. 4 (2015), s. 519-522 ISSN 0144-8420 Institutional support: RVO:61389005 Keywords : nuclear power plant * methodology * future decommissioning costs Subject RIV: BG - Nuclear, Atomic and Molecular Physics, Colliders Impact factor: 0.894, year: 2015

  16. Architecture and aesthetics of nuclear power plants

    International Nuclear Information System (INIS)

    Andreu, P.

    1977-01-01

    Having first analysed the main aesthetical and architectural problems related to the establishment of nuclear sites, the first results of the description is given of studies undertaken by a group of architects asked by E.D.F. to conceive the main buildings of a nuclear power plant and to imagine their insert in the site [fr

  17. Nuclear power plant safety in Brazil

    International Nuclear Information System (INIS)

    Lederman, L.

    1980-01-01

    The Code of Practice for the Safe Operation of Nuclear Power Plants states that: 'In discharging its responsibility for public health and safety, the government should ensure that the operational safety of a nuclear reactor is subject to surveillance by a regulatory body independent of the operating organization'. In Brazil this task is being carried out by the Comissao Nacional de Energia Nuclear in accordance with the best international practice. (orig./RW)

  18. Cost savings from extended life nuclear plants

    International Nuclear Information System (INIS)

    Forest, L.R. Jr.; Deutsch, T.R.; Schenler, W.W.

    1988-09-01

    This study assesses the costs and benefits of nuclear power plant life extension (NUPLEX) for the overall US under widely varying economic assumptions and compares these with alternative new coal- fired plants (NEWCOAL). It is found that NUPLEX saves future electricity consumers more than 3 cents/-kwh compared with NEWCOAL. The NUPLEX costs and benefits for existing individual US nuclear power plants under base-line, or most likely, assumptions are assessed to determine the effects of the basic plant design and plant age. While benefits vary widely, virtually all units would have a positive benefit from NUPLEX. The study also presents a cost-benefit analysis of the nuclear industry's planned advanced light water reactor (ALWR). It is concluded that ALWR offers electrical power at a substantially lower cost than NEWCOAL. 9 refs., 6 figs

  19. Regulatory requirements for desalination plant coupled with nuclear reactor plant

    International Nuclear Information System (INIS)

    Yune, Young Gill; Kim, Woong Sik; Jo, Jong Chull; Kim, Hho Jung; Song, Jae Myung

    2005-01-01

    A small-to-medium sized reactor has been developed for multi-purposes such as seawater desalination, ship propulsion, and district heating since early 1990s in Korea. Now, the construction of its scaled-down research reactor, equipped with a seawater desalination plant, is planned to demonstrate the safety and performance of the design of the multi-purpose reactor. And the licensing application of the research reactor is expected in the near future. Therefore, a development of regulatory requirements/guides for a desalination plant coupled with a nuclear reactor plant is necessary for the preparation of the forthcoming licensing review of the research reactor. In this paper, the following contents are presented: the design of the desalination plant, domestic and foreign regulatory requirements relevant to desalination plants, and a draft of regulatory requirements/guides for a desalination plant coupled with a nuclear reactor plant

  20. From the 'Le Blayais NPP' flooding in 1999 to the review of French regulation for the protection of nuclear facilities against external flooding

    International Nuclear Information System (INIS)

    Dupuy, P.

    2011-01-01

    On 27 December 1999, a severe storm occurred in the vicinity of the 'Le Blayais' Nuclear Power Plant located on the banks of the Gironde estuary. The severe storm-driven waves coincident with high water levels in the Gironde estuary exceeded the worst-case scenario considered at the design of the site protection against flooding, resulting in the scram of three out of four units and severe nuclear island flooding. Several underground rooms sheltering equipment important to safety were flooded. This partial flooding incident has 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 in particular in terms of flood events and combinations of flood events considered for the design. It has also revealed some weaknesses in the existing measures implemented, especially the site protection dykes, the protection of equipment important to safety, the warning systems and the emergency organization. Following this incident, in addition to the rush through protection measures undertaken on Le Blayais NPP, the utility Electricity De France (EDF) has launched a wide review of the protection of all French NPPs against external flooding. This review is based on a new and more comprehensive methodology for the protection of NPPs against external flooding (called 'REX Blayais methodology'), including a reassessment of flood events and their combinations and of all protection measures. This review has led EDF to carry out a large number of modifications and improvements at all NPP sites. 'REX Blayais methodology' and its application to all French NPPs were submitted to the approval of the French Nuclear Safety Authority (ASN) in 2001 and then in 2007 after being analyzed by its technical support IRSN (French Institute for Radioprotection and Nuclear Safety). The methodology and the level of protection of the NPPs thanks to all the improvements and modifications performed by the utility were

  1. Project of law relative to the sanitary consequences of French nuclear weapons tests

    International Nuclear Information System (INIS)

    2009-05-01

    In order to make easy the indemnifications and to include the persons having participate to nuclear weapons tests (Sahara and French Polynesia) and populations leaving in the concerned areas, the project of law relative to the repair of sanitary consequences of nuclear weapons tests proposes to create a right to integral repair of prejudices for the persons suffering of a radioinduced disease coming from these tests. The American example and the British example are given for comparison. The modalities of financing are detailed as well as the social economic and administrative impacts. (N.C.)

  2. The French Disconnection – Reducing the nuclear share in France’s energy mix

    OpenAIRE

    2014-01-01

    France is debating its energy transition, triggered by President Hollande’s pledge to reduce nuclear power’s dominant share in the country’s electricity mix. The debate has yet to produce a new energy law, but has shaken French complacency that they completed their energy transition years ago by decarbonising their electricity through nuclear power. It has also raised the question of the long term future and replacement of France’s 58 reactors. This paper argues against early closure of react...

  3. The economics of nuclear power plants today

    International Nuclear Information System (INIS)

    Heller, W.

    2004-01-01

    The debate about the use of nuclear power is currently entering a phase of new objectivity, also because of its economic background. A new nuclear power plant is being built by private operators in Finland. That decision was based on important energy policy reasons and on a positive answer to the question of the economic viability of that plant. Studies along these lines were conducted mainly by Professor Risto Tarjanne of the Technical University of Lappeenranta, Finland. In that study, different electricity generating plants were compared with respect to their electricity generating costs. The lowest costs were found for nuclear, gas-fired, and coal-fired power plants, without taking into account the assumed probable costs of emissions trading. When these were included, the electricity costs of fossil-fired plants increased markedly. Changes in the underlying cost assumptions were examined further in a sensitivity analysis. Nuclear power was found to show cost advantages even under conditions of unfavorably high real interest rates. These cost benefits, in addition, were seen to be rather insensitive to increases in fuel costs and capital costs. In gas and coal-fired power plants, on the other hand, generating costs rise significantly as a function of rising fuel costs, among other things. The Finnish studies indicate sound economic reasons for building a new nuclear power plant in Finland. (orig.)

  4. Modifications to nuclear power plants. Safety guide

    International Nuclear Information System (INIS)

    2004-01-01

    This Safety Guide was prepared under the IAEA's programme for safety standards for nuclear power plants. It supplements Section 7 of the Safety Requirements publication on Safety of Nuclear Power Plants: Operation, which establishes the safety requirements for the modification of nuclear power plants. Reasons for carrying out modifications to nuclear power plants may include: (1) maintaining or strengthening existing safety provisions and thus maintaining consistency with or improving on the current design. (2) recovering from plant faults. (3) improving the thermal performance or increasing the power rating of the plant. (4) increasing the maintainability of the plant, reducing the radiation exposure of personnel or reducing the costs of plant maintenance. And (5) extending the design life of the plant. Most modifications, made on the basis of operating experience, are intended to improve on the design or to improve operational performance and flexibility. Some are rendered necessary by new regulatory requirements, ageing of the plant or obsolescence of equipment. However, the benefits of regularly updating the plant design can be jeopardized if modifications are not kept under rigorous control throughout the lifetime of the plant. The need to reduce costs and improve efficiency, in combination with changes to the structure of the electricity generation sector of the economy in many countries, has led many companies to make changes in the structure of the operating organization for nuclear power plants. Whatever the reason for such organizational changes, consideration should be given to the effects of those changes with the aim of ensuring that they would have no impacts that would compromise the safety of the plant. The objective of this Safety Guide is to provide guidance and recommendations on controlling activities relating to modifications at nuclear power plants in order to reduce risk and to ensure that the configuration of the plant is at all times under

  5. Overview of the French offer in nuclear training: 60 years to serve development and knowledge transfer

    International Nuclear Information System (INIS)

    Fanjas, Y.; Navon-Gross, A.; Mougel, B.; Verdier, A.

    2017-01-01

    As early as the beginning of its nuclear program, France has developed a wide range of higher education programs and occupational training in nuclear sciences, nuclear technologies and nuclear engineering. INSTN (Institute for Nuclear Sciences and Nuclear Technologies) was founded in 1956 inside CEA premises at Saclay to issue the diploma of 'ingenieur en genie atomique'. This diploma is still delivered and celebrated its 60. anniversary in 2016. A large course offering has been added to the sole initial INSTN diploma. Throughout France and each year about 2000 students are awarded a diploma opening the gates of nuclear industry or research from vocational baccalaureates (130) to doctoral thesis (200) via engineer/master degrees (1270). Continuous training has also been developed, employees from the nuclear industry benefit from 16 days a year of training in average. French high education systems are open to foreign students and 9 master degrees in nuclear engineering are entirely taught in English. (A.C.)

  6. Extension of the nuclear power plant lifetime

    International Nuclear Information System (INIS)

    Keramsi, Alain

    2011-01-01

    After a presentation of the French nuclear context (history of the reactor fleet, choice of reactor type, PWR operation principle, competitiveness, environmental performance), this Power Point presentation addresses the context and challenges of the operation lifetime (average fleet age in different countries, examples of extensions, case of the United States, what is at stake with lifetime extension, decennial visits, EDF strategy), discusses the EDF's safety objectives (definition of the three main safety functions, impact of the operation duration and of the coexistence of two generations for the safety functions), discusses how to manage the ageing phenomenon for replaceable and non-replaceable components

  7. Quality assurance program for nuclear power plants

    International Nuclear Information System (INIS)

    Gamon, T.H.

    1976-02-01

    The Topical Report presented establishes and provides the basis for the Brown and Root Quality Assurance Program for Nuclear Power Plants from which the Brown and Root Quality Assurance Manual is prepared and implemented. The Quality Assurance Program is implemented by the Brown and Root Power Division during the design, procurement, and construction phases of nuclear power plants. The Brown and Root Quality Assurance Program conforms to the requirements of Nuclear Regulatory Commission Regulation 10 CFR 50, Appendix B; to approved industry standards such as ANSI N45.2 and ''Daughter Standards''; or to equivalent alternatives as indicated in the appropriate sections of the report

  8. Quality assurance program for nuclear power plants

    International Nuclear Information System (INIS)

    Gamon, T.H.

    1976-06-01

    This topical report establishes and provides the basis for the Brown and Root Quality Assurance Program for Nuclear Power Plants from which the Brown and Root Quality Assurance Manual is prepared and implemented. The Quality Assurance Program is implemented by the Brown and Root Power Division during the design, procurement, and construction phases of nuclear power plants. The Brown and Root Quality Assurance Program conforms to the requirements of Nuclear Regulatory Commission Regulation 10 CFR 50, Appendix B; to approved industry standards such as ANSI N45.2 and ''Daughter Standards''; or to equivalent alternatives as indicated in the appropriate sections of this report

  9. How to forecast nuclear plant construction time

    International Nuclear Information System (INIS)

    Bentley, B.W.; Denehy, R.F.

    1980-01-01

    A cumulative probability distribution curve is described which can help planners estimate the construction time for nuclear power plants. Accumulated construction data published by the Nuclear Regulatory Commission in Construction Status Report - Nuclear Power Plants is the basis for the curves. A case for both optimism and pessimism in lead times can be argued, but a probability curve can be drawn by monitoring construction duration trends and forming a histogram on which to base cumulative probability. The curve can be adapted to project the time for a project already in progress. 6 figures

  10. Nuclear material control systems for nuclear power plants

    International Nuclear Information System (INIS)

    1975-06-01

    Paragraph 70.51(c) of 10 CFR Part 70 requires each licensee who is authorized to possess at any one time special nuclear material in a quantity exceeding one effective kilogram to establish, maintain, and follow written material control and accounting procedures that are sufficient to enable the licensee to account for the special nuclear material in his possession under license. While other paragraphs and sections of Part 70 provide specific requirements for nuclear material control systems for fuel cycle plants, such detailed requirements are not included for nuclear power reactors. This guide identifies elements acceptable to the NRC staff for a nuclear material control system for nuclear power reactors. (U.S.)

  11. Operations quality assurance for nuclear power plants

    International Nuclear Information System (INIS)

    1987-01-01

    This standard covers the quality assurance of all activities concerned with the operation and maintenance of plant equipment and systems in CANDU-based nuclear power plants during the operations phase, the period between the completion of commissioning and the start of decommissioning

  12. Drought prompts government to close nuclear plant

    CERN Multimedia

    2003-01-01

    "A nuclear power plant was shut down Sunday because a record drought left insufficient water to cool down the reactor. The plant supplies more than 10 percent of Romania's electricity and closure prompted fears of a price hike" (1/2 page).

  13. Maintenance welding technology in nuclear power plant

    International Nuclear Information System (INIS)

    Matsuda, Fukuhisa

    1999-01-01

    Welding technology used for a nuclear power plant greatly differs depending on either when the plant is being constructed or when the plant is in operation. Welding used in plant construction does not much differ, in method and technology, from that used in ordinary thermal power, chemical or other plants. On the other hand, repair welding technology for the reactor section of a nuclear power plant in operation greatly differs from that used for those plants. The recent requests for the prolongation of the life of nuclear power plants have remarkably improved welding technology for maintenance and repair in the nuclear field. Thus, the existing welding technology has been improved and new advanced welding technologies have been created one after another. Problems with the reactor section and welding technology for its maintenance and repair are presented. The temper bead method and the laser beam cladding and modification method for reactor pressure vessels, SCC and irradiation-assisted SCC measures for vessel structures, and SCC measures for heat-exchange tubes and the overall replacement of a steam generator are presented. (N.H.)

  14. 77 FR 28407 - Special Nuclear Material Control and Accounting Systems for Nuclear Power Plants

    Science.gov (United States)

    2012-05-14

    ... COMMISSION Special Nuclear Material Control and Accounting Systems for Nuclear Power Plants AGENCY: Nuclear...-5028, ``Special Nuclear Material Control and Accounting Systems for Nuclear Power Plants.'' In DG-5028... Control and Accounting Systems for Nuclear Power Plants.'' DATES: Submit comments by July 16, 2012...

  15. Close down nuclear power plants. Materials for nuclear power phaseout

    International Nuclear Information System (INIS)

    1986-07-01

    This is a brochure presented by the Greens in the Parliament of Baden-Wuerttemberg, Stuttgart, to document that it is possible for Baden-Wuerttemberg and, moreover, the entire Federal Republic of Germany to opt out of nuclear power immediately, and to show how this can be done. Most prominent in this context is a study worked out in connection with the bill for the nuclear-test ban. That study calculates the figures for two scenarios: scenario A is based on the immediate close-down of all nuclear power plants in 1986/87; the concept of scenario B is the immediate close-down of all nuclear power plants put into operation in 1980 at the latest, as well as the speedy closing-down step-by-step of all the remaining nuclear power plants until the beginning of the nineties. Opting out of nuclear energy must be accompanied also by changes in the energy economy in legal and structural regards. For that purpose, the programme for 'democratization and recommunalization of the energy economy' was designed. Opting out of nuclear energy finally presupposes a commitment to energy conservation techniques and to non-polluting, renewable energy sources. (orig./HSCH) [de

  16. Holographic inspection of nuclear plant

    International Nuclear Information System (INIS)

    Gordon, A.L.; Armour, I.A.; Glanville, R.; Malcolm, G.J.; Wright, D.G.

    1988-01-01

    The high resolution, enormous depth of field and high tolerance to radiation of holography mean that it has great potential as an inspection tool in the nuclear industry. In addition, the ability of double-pulse holography to yield detailed information on vibration over the whole field of both large and small structures provides measurements that often cannot be obtained in any other way. This paper reviews the development of equipment for the holographic inspection of nuclear fuel elements; a portable holocamera for use inside reactors; and the application of holographic techniques for vibration measurements in a nuclear power station. (author)

  17. Academic training for nuclear power plant operators

    International Nuclear Information System (INIS)

    Jones, D.W.

    1982-01-01

    In view of the increasing emphasis being placed upon academic training of nuclear power plant operators, it is important that institutions of higher education develop and implement programs which will meet the educational needs of operational personnel in the nuclear industry. Two primary objectives must be satisfied by these programs if they are to be effective in meeting the needs of the industry. One objective is for academic quality. The other primary objective is for programs to address the specialized needs of the nuclear plant operator and to be relevant to the operator's job. The Center for Nuclear Studies at Memphis State University, therefore, has developed a total program for these objectives, which delivers the programs, and/or appropriate parts thereto, at ten nuclear plant sites and with other plants in the planning stage. The Center for Nuclear Studies program leads to a Bachelor of Professional Studies degree in nuclear industrial operations, which is offered through the university college of Memphis State University

  18. Nuclear power plants 1995 - a world survey

    International Nuclear Information System (INIS)

    Anon.

    1996-01-01

    The atw Statistics Report compiled by atw lists 428 nuclear power plants with 363 397 gross MWe in operation in 30 countries in late 1995. Another 62 units with 55 180 gross MWe were under construction in 18 countries. This adds up to a total of 490 units with an aggregate 418 577 MWe. In the course of 1995 four units in four countries started commercial operation. In the survey of electricity generation in 1995 for which no information was made available from China and Kasachstan, a total of 417 nuclear power plants were covered. In the year under review they generated an aggregate 2 282 614 GWH, which is 3.4% more than in the previous year. The highest nuclear generation again was recorded in the USA with 705 771 GWh, followed by France with 377 021 GWh. The Grohnde power station in Germany attained the maximum annual production figure of 11 359 GWh. The survey includes nine tables indicating the generating performance of each nuclear power plant, the development of electricity generation in nuclear plants, and status of nuclear power plants at the end of 1995 arranged by countries, types of reactors, and reactor manufacturers. (orig.) [de

  19. Dose reduction at nuclear power plants

    International Nuclear Information System (INIS)

    Baum, J.W.; Dionne, B.J.

    1983-01-01

    The collective dose equivalent at nuclear power plants increased from 1250 rem in 1969 to nearly 54,000 rem in 1980. This rise is attributable primarily to an increase in nuclear generated power from 1289 MW-y to 29,155 MW-y; and secondly, to increased average plant age. However, considerable variation in exposure occurs from plant to plant depending on plant type, refueling, maintenance, etc. In order to understand the factors influencing these differences, an investigation was initiated to study dose-reduction techniques and effectiveness of as low as reasonably achievable (ALARA) planning at light water plants. Objectives are to: identify high-dose maintenance tasks and related dose-reduction techniques; investigate utilization of high-reliability, low-maintenance equipment; recommend improved radioactive waste handling equipment and procedures; examine incentives for dose reduction; and compile an ALARA handbook

  20. How to manage flexible nuclear power plants in a deregulated electricity market from the point of view of social welfare?

    International Nuclear Information System (INIS)

    Lykidi, Maria; Gourdel, Pascal

    2015-01-01

    Flexible nuclear power plants can adjust their electricity production to the predicted evolution of demand. Under certain conditions, flexible operation is necessary to ensure the stability of the electricity system. However, despite the potential advantages of nuclear energy including the flexibility of nuclear reactors, the social acceptance of nuclear has reduced after the Fukushima accident, leading some countries to reduce or even phase out nuclear (e.g. Germany). So, a question that arises is how flexible nuclear power plants have to be operated in order to maximize social welfare. The French nuclear fleet gives an illustration of flexible management while social acceptance of nuclear is questioned; this was reflected in the new French Energy Transition law. Theoretically and numerically, we found that the production behavior that maximizes social welfare is characterized by a constant thermal production and a totally flexible nuclear production given sufficient nuclear capacity. - Highlights: • We determine the management of flexible nuclear plants to maximize social welfare. • We model the nuclear fuel stock as a “reservoir” of energy. • Social optimum is given by a totally flexible management of the nuclear production. • The level of thermal production of the optimal solution is always constant. • We need to invest in nuclear energy to ensure social optimum within our model

  1. Human factors in nuclear power plants

    International Nuclear Information System (INIS)

    Hennig, J.; Bohr, E.

    1976-04-01

    This annotated bibliography is a first attempt to give a survey of the kind of literature which is relevant for the ergonomic working conditions in nuclear power plants. Such a survey seems to be useful in view of the fact that the 'factor human being' comes recently more and more to the fore in nuclear power plants. In this context, the necessity is often pointed out to systematically include our knowledge of the performance capacity and limits of human beings when designing the working conditions for the personnel of nuclear power plants. For this reason, the bibliography is so much intended for the ergonomics experts as for the experts of nuclear engineering. (orig./LN) [de

  2. Investigation of human system interface design in nuclear power plant

    International Nuclear Information System (INIS)

    Feng Yan; Zhang Yunbo; Wang Zhongqiu

    2012-01-01

    The paper introduces the importance of HFE in designing nuclear power plant, and introduces briefly the content and scope of HFE, discusses human system interface design of new built nuclear power plants. This paper also describes human system interface design of foreign nuclear power plant, and describes in detail human system interface design of domestic nuclear power plant. (authors)

  3. Availability Improvement of German Nuclear Power Plants

    International Nuclear Information System (INIS)

    Wilhelm, Oliver

    2008-01-01

    High availability is important for the safety and economical performance of Nuclear Power Plants (NPP). The strategy for availability improvement in a typical German PWR shall be discussed here. Key parameters for strategy development are plant design, availability of safety systems, component reliability, preventive maintenance and outage organization. Plant design, availability of safety systems and component reliability are to a greater extent given parameters that can hardly be influenced after the construction of the plant. But they set the frame for maintenance and outage organisation which have shown to have a large influence on the availability of the plant. (author)

  4. Operation of Finnish nuclear power plants

    International Nuclear Information System (INIS)

    Reponen, H.; Viitasaari, O.

    1985-09-01

    These general reviews of the operation of the Finnish nuclear power plants concentrate on such events and discoveries related to reactor and radiation safety that the regulatory body, the Finnish Centre for Radiation and Nuclear Safety, regards as significant. In the report period, no event essentially degraded plant safety nor posed a radiation hazard to the personnel or the environment. The report also includes a summary of the radiation safety of the personnel and the environment and tabulated data on the production and capacity factors of the plants. (author)

  5. Operation of Finnish nuclear power plants

    International Nuclear Information System (INIS)

    Lehtinen, P.

    1985-11-01

    These general reviews of the operation of the Finnish nuclear power plants concentrate on such events and discoveries related to reactor and radiation safety that the regulatory body, the Finnish Centre for Radiation and Nuclear Safety, regards as noteworthy. The report also includes a summary of the radiation safety of the personnel and the environment and tabulated data on the production and load factors of the plants. In the report period, no event essentially degraded plant safety nor posed a radiation hazard to the personnel or the environment. (author)

  6. Safety design of Qinshan Nuclear Power Plant

    International Nuclear Information System (INIS)

    Ouyang Yu; Zhang Lian; Du Shenghua; Zhao Jiayu

    1984-01-01

    Safety issues have been greatly emphasized through the design of the Qinshan Nuclear Power Plant. Reasonable safety margine has been taken into account in the plant design parameters, the design incorporated various safeguard systems, such as engineering safety feature systems, safety protection systems and the features to resist natural catastrophes, e. g. earthquake, hurricanes, tide and so on. Preliminary safety analysis and environmental effect assessment have been done and anti-accident provisions and emergency policy were carefully considered. Qinshan Nuclear Power Plant safety related systems are designed in accordance with the common international standards established in the late 70's, as well as the existing engineering standard of China

  7. Operation of Finnish nuclear power plants

    International Nuclear Information System (INIS)

    Reponen, H.; Viitasaari, O.

    1985-05-01

    This general review of the operation of the Finnish nuclear power plants in the third quarter of the year 1984 concentrates on such events and discoveries related to reactor and radiation safety that the regulatory body, the Finnish Centre for Radiation and Nuclear Safety, regards as significant. In the report period, no event essentially degraded plant safety nor posed a radiation hazard to the personnel or the environment. The report also includes a summary of the radiation safety of the personnel and the environment and tabulated data on the production and capacity factors of the plants. (author)

  8. Safety Assessment - Swedish Nuclear Power Plants

    International Nuclear Information System (INIS)

    Kjellstroem, B.

    1996-01-01

    After the reactor accident at Three Mile Island, the Swedish nuclear power plants were equipped with filtered venting of the containment. Several types of accidents can be identified where the filtered venting has no effect on the radioactive release. The probability for such accidents is hopefully very small. It is not possible however to estimate the probability accurately. Experiences gained in the last years, which have been documented in official reports from the Nuclear Power Inspectorate indicate that the probability for core melt accidents in Swedish reactors can be significantly larger than estimated earlier. A probability up to one in a thousand operating years can not be excluded. There are so far no indications that aging of the plants has contributed to an increased accident risk. Maintaining the safety level with aging nuclear power plants can however be expected to be increasingly difficult. It is concluded that the 12 Swedish plants remain a major threat for severe radioactive pollution of the Swedish environment despite measures taken since 1980 to improve their safety. Closing of the nuclear power plants is the only possibility to eliminate this threat. It is recommended that until this is done, quantitative safety goals, same for all Swedish plants, shall be defined and strictly enforced. It is also recommended that utilities distributing misleading information about nuclear power risks shall have their operating license withdrawn. 37 refs

  9. Linguistic control of a nuclear power plant

    International Nuclear Information System (INIS)

    Feeley, J.J.; Johnson, J.C.

    1987-01-01

    A multivariable linguistic controller based on fuzzy set theory is discussed and its application to a pressurized water nuclear power plant control is illustrated by computer simulation. The nonlinear power plant simulation model has nine states, two control inputs, one disturbance input, and two outputs. Although relatively simple, the model captures the essential coupled nonlinear plant dynamics and is convenient to use for control system studies. The use of an adaptive version of the controller is also demonstrated by computer simulation

  10. SWOT of nuclear power plant sustainable development

    International Nuclear Information System (INIS)

    Abbaspour, M.; Ghazi, S.

    2008-01-01

    SWOT Analysis is a Useful tool that can he applied to most projects or business ventures. In this article we are going to examine major strengths, weaknesses, opportunities and threats of nuclear power plants in view of sustainable development. Nuclear power plants have already attained widespread recognition for its benefits in fossil pollution abatement, near-zero green house gas emission, price stability and security of energy supply. The impressive new development is that these virtues are now a cost -free bonus, because, in long run, nuclear energy has become an inexpensive way to generate electricity. Nuclear energy's pre-eminence economically and environmentally has two implications for government policy. First, governments should ensure that nuclear licensing and safety oversight arc not only rigorous but also efficient in facilitating timely development of advanced power plants. Second, governments should be bold incentivizing the transformation to clean energy economics, recognizing that such short-term stimulus will, in the case of nuclear plants, simply accelerate desirable changes that now have their own long-term momentum. The increased competitiveness of nuclear power plant is the result of cost reductions in all aspects of nuclear economics: Construction, financing, operations, waste management and decommissioning. Among the cost-lowering factors are the evolution to standardized reactor designs, shorter construction periods, new financing techniques, more efficient generation technologies, higher rates of reactor utilization, and longer plant lifetimes. U.S World Nuclear Association report shows that total electricity costs for power plant construction and operation were calculated at two interest rates. At 10%, midrange generating costs per kilowatt-hour are nuclear at 4 cents, coal at 4.7 cents and natural gas at 5.1 cent. At a 5% interest rate, mid-range costs per KWh fall to nuclear at 2.6 cents, coal at 3.7 cents and natural gas at 4.3 cents

  11. Cell fusion and nuclear fusion in plants.

    Science.gov (United States)

    Maruyama, Daisuke; Ohtsu, Mina; Higashiyama, Tetsuya

    2016-12-01

    Eukaryotic cells are surrounded by a plasma membrane and have a large nucleus containing the genomic DNA, which is enclosed by a nuclear envelope consisting of the outer and inner nuclear membranes. Although these membranes maintain the identity of cells, they sometimes fuse to each other, such as to produce a zygote during sexual reproduction or to give rise to other characteristically polyploid tissues. Recent studies have demonstrated that the mechanisms of plasma membrane or nuclear membrane fusion in plants are shared to some extent with those of yeasts and animals, despite the unique features of plant cells including thick cell walls and intercellular connections. Here, we summarize the key factors in the fusion of these membranes during plant reproduction, and also focus on "non-gametic cell fusion," which was thought to be rare in plant tissue, in which each cell is separated by a cell wall. Copyright © 2016 Elsevier Ltd. All rights reserved.

  12. Problems of nuclear power plant safety evaluation

    International Nuclear Information System (INIS)

    Suchomel, J.

    1977-01-01

    Nuclear power plant safety is discussed with regard to external effects on the containment and to the human factor. As for external effects, attention is focused on shock waves which may be due to explosions or accidents in flammable material transport and storage, to missiles, and to earthquake effects. The criteria for evaluating nuclear power plant safety in different countries are shown. Factors are discussed affecting the reliability of man with regard to his behaviour in a loss-of-coolant accident in the power plant. Different types of PWR containments and their functions are analyzed, mainly in case of accident. Views are discussed on the role of destructive accidents in the overall evaluation of fast reactor safety. Experiences are summed up gained with the operation of WWER reactors with respect to the environmental impact of the nuclear power plants. (Z.M.)

  13. Nuclear power plant transients: where are we

    International Nuclear Information System (INIS)

    Majumdar, D.

    1984-05-01

    This document is in part a postconference review and summary of the American Nuclear Society sponsored Anticipated and Abnormal Plant Transients in Light Water Reactors Conference held in Jackson, Wyoming, September 26-29, 1983, and in part a reflection upon the issues of plant transients and their impact on the viability of nuclear power. This document discusses state-of-the-art knowledge, deficiencies, and future directions in the plant transients area as seen through this conference. It describes briefly what was reported in this conference, emphasizes areas where it is felt there is confidence in the nuclear industry, and also discusses where the experts did not have a consensus. Areas covered in the document include major issues in operational transients, transient management, transient events experience base, the status of the analytical tools and their capabilities, probabilistic risk assessment applications in operational transients, and human factors impact on plant transients management

  14. French practices concerning quantitative evaluation of potential atmospheric pollution connected to nuclear activities

    International Nuclear Information System (INIS)

    Doury, A.

    1980-10-01

    Since 1945, French nuclear development has been accompanied, in the field of prevention and control of atmospheric pollution, by special efforts which were significantly stepped up after the accident that occurred at Reactor no.1, Windscale, Great Britain, in October 1957. With a view to quantitative evaluation of concentrations and doses, a first stage has been undertaken which consisted in rapidly setting up practical abacuses without mathematical support directly deduced from full-scale tests by means of tracers on various French sites. Then, from approximately 1970 onwards, partly in answer to new necessities and new problems related to the radiological security of the Pacific atomic tests, one has been striving-through necessary reliance on data obtained from different occasional or concerted 'traced' tests, both French and foreign, to develop a scale reduction having general, yet sufficiently simple characteristics to allow for practicality and efficiency, while being capable of processing as many concrete problems as possible, in particular by overstepping the rather restrictive operating limitations of previous abacuses. The two procedures, the first of which is still being used in an old version, by the nuclear sector of Electricite de France, while the second one begins to be applied by the Technical Support of the Public Authority, are presented and discussed. They are then compared, both as regards their respective performance and complementarity, and from the viewpoint of numerical results, especially in the light of corresponding results obtained with foreign methods [fr

  15. Advancements in nuclear plant maintenance programs

    International Nuclear Information System (INIS)

    Meligi, A.E.; Maras, M.C.

    1993-01-01

    The viability of the nuclear option as a technology choice for present and future electricity generation will be decided primarily on the basis of operating cost to achieve plant performance objectives. In a nuclear plant, performance is judged not only on availability and output rate but also on safety risk and radiation exposure. Operating, cost is essentially made up of the fuel cost and operation and maintenance (O and M) cost. Over the past decade, the industry average nuclear plant performance has improved significantly; however, this improvement was accompanied by rising O and M cost. The net result was that the nuclear option lost its long-standing economic advantage over the coal option, based on the industry average comparison, around 1987 - with the gap narrowing slightly in the last 2 years. In recent times, gas-fired plants have also become a basis for comparison. The electric generation cost comparisons of various fuel options has led to even greater scrutiny of nuclear plant performance, with the poorer performing plants facing the risk of shutdown. While effective O and M programs improve plant performance, present industry data show that there is no direct correlation between the cost of a plant O and M program and its associated performance. There is a significant number of existing tools and techniques in the O and M area that have proved to be successful and have resulted in significant benefits and payback. This paper presents an overview of the nuclear industry efforts to improve the conduct of O and M activities, describes the basic elements of an effective O and M program, and addresses some of the state-of-the-art tools and techniques to enhance maintenance work planning, training, and procedures

  16. CRISTAL: a french criticality code package to assess nuclear installation criticality safety

    International Nuclear Information System (INIS)

    Michel, E Doucet; Comte, N.; Jean Michel Gomit; Eric Letang; Chrsitine Magnaud; Christophe Venard; Herve Toubon; Cogema

    2005-01-01

    For more than thirty years, CEA, IRSN and the French nuclear industry have been combining their efforts to finance, develop and validate computer codes to assess the criticality safety concerns of nuclear installations, transport casks, and reprocessing facilities. As one of the major world fuel vendors, Framatome ANP is deeply involved in defining code developments which incorporate feedback from both users and customers. The result of these continuous efforts is the evolutionary CRISTAL code. The CRISTAL package was developed as an easy-to-use system using cross-section libraries (JEF 2.2 and CEA93), well-established computer codes (APOLLO2, MORET 4 and TRIPOLI-4) and including a Graphical User-Friendly Interface. The APOLLO2 computer code, a spectral code used for evaluating the basic characteristics of fuel assemblies, has been upgraded to perform criticality safety calculations. The MORET 4 computer code is a neutron simulation code in three dimensions which uses the multigroup formalism for cross-sections and the Monte Carlo method to solve the Boltzmann equation. Through the years, the CRISTAL package has been improved to take into account both the growth of its validation database and the increasing user requirements. Today, CRISTAL V0 is an up-to-date computational tool incorporating the comprehensive APOLLO2 and MORET 4 computer codes; CRISTAL V0 is the result of more than five years of development work focusing on theoretical approaches and on the implementation of user-friendly graphical interfaces. Thanks to its broad validation database, CRISTAL V0 provides outstanding accuracy of criticality evaluation for configurations covering the entire fuel cycle life (i.e. from fuel enrichment, pellet/assembly fabrication and transport casks to fuel reprocessing). With more than a thousand benchmark/calculation comparisons, uncertainties can be deduced for various file media, fissile shapes, fissile process interactions, neutron-poisoning screens and material

  17. 76 FR 39908 - Calvert Cliffs Nuclear Power Plant, LLC; Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2...

    Science.gov (United States)

    2011-07-07

    ... Nuclear Power Plant, LLC; Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2; Calvert Cliffs.... DPR-53 and DPR-69, for the Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2 (CCNPP), respectively... (ISFSI), currently held by Calvert Cliffs Nuclear Power Plant, LLC as owner and licensed operator...

  18. 75 FR 66802 - Calvert Cliffs Nuclear Power Plant, LLC; Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2...

    Science.gov (United States)

    2010-10-29

    ... Nuclear Power Plant, LLC; Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2; Notice of Withdrawal of...) has granted the request of Calvert Cliffs Nuclear Power Plant, LLC, the licensee, to withdraw its... for the Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2, located in Calvert County, MD. The...

  19. Revised inspection program for nuclear power plants

    International Nuclear Information System (INIS)

    1978-01-01

    The United States Nuclear Regulatory Commission (NRC) regulates nuclear power plants to assure adequate protection of the public and the environment from the dangers associated with nuclear materials. NRC fulfills this responsibility through comprehensive safety reviews of nuclear facilities, licensing of organizations that use nuclear materials, and continuing inspection. The NRC inspection program is currently conducted from the five regional offices in or near Philadelphia, Atlanta, Chicago, Dallas and San Francisco. Inspectors travel from the regional offices to nuclear power plants in various phases of construction, test and operation in order to conduct inspections. However, in June 1977 the Commission approved a revision to the inspection program that will include stationing inspectors at selected plants under construction and at all plants in operation. In addition, the revised program provides for appraising the performance of licensees on a national basis and involves more direct measurement and observation by NRC inspectors of work and tests in progress. The program also includes enhanced career management consisting of improved training and career development for inspectors and other professionals. The report was requested in the Conference Report on the NRC Authorization for Appropriations for Fiscal Year 1978. The report provides a discussion of the basis for both the current and revised inspection programs, describes these programs, and shows how the NRC inspection force will be trained and utilized. In addition, the report includes a discussion of the actions that will be taken to assure the objectivity of inspectors

  20. Elecnuc. Nuclear power plants in the world. 1997; Elecnuc. Les centrales nucleaires dans le monde. 1997

    Energy Technology Data Exchange (ETDEWEB)

    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.)

  1. Countermeasures to earthquakes in nuclear plants

    International Nuclear Information System (INIS)

    Sato, Kazuhide

    1979-01-01

    The contribution of atomic energy to mankind is unmeasured, but the danger of radioactivity is a special thing. Therefore in the design of nuclear power plants, the safety has been regarded as important, and in Japan where earthquakes occur frequently, the countermeasures to earthquakes have been incorporated in the examination of safety naturally. The radioactive substances handled in nuclear power stations and spent fuel reprocessing plants are briefly explained. The occurrence of earthquakes cannot be predicted effectively, and the disaster due to earthquakes is apt to be remarkably large. In nuclear plants, the prevention of damage in the facilities and the maintenance of the functions are required at the time of earthquakes. Regarding the location of nuclear plants, the history of earthquakes, the possible magnitude of earthquakes, the properties of ground and the position of nuclear plants should be examined. After the place of installation has been decided, the earthquake used for design is selected, evaluating live faults and determining the standard earthquakes. As the fundamentals of aseismatic design, the classification according to importance, the earthquakes for design corresponding to the classes of importance, the combination of loads and allowable stress are explained. (Kako, I.)

  2. Plant Design Nuclear Fuel Element Production Capacity Optimization to Support Nuclear Power Plant in Indonesia

    International Nuclear Information System (INIS)

    Bambang Galung Susanto

    2007-01-01

    The optimization production capacity for designing nuclear fuel element fabrication plant in Indonesia to support the nuclear power plant has been done. From calculation and by assuming that nuclear power plant to be built in Indonesia as much as 12 NPP and having capacity each 1000 MW, the optimum capacity for nuclear fuel element fabrication plant is 710 ton UO 2 /year. The optimum capacity production selected, has considered some aspects such as fraction batch (cycle, n = 3), length of cycle (18 months), discharge burn-up value (Bd) 35,000 up 50,000 MWD/ton U, enriched uranium to be used in the NPP (3.22 % to 4.51 %), future market development for fuel element, and the trend of capacity production selected by advances country to built nuclear fuel element fabrication plant type of PWR. (author)

  3. French PWR Safety Philosophy

    International Nuclear Information System (INIS)

    Conte, M. M.

    1986-01-01

    The first 900 MWe units, built under the American Westinghouse licence and with reference to the U. S. regulation, were followed by 28 standardized units, C P1 and C P2 series. 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. As early as 1976, this experience was taken into account by French Safety organisms to discuss, with Electricite de France, the safety options for the planned 1300 MWe units, P4 and P4 series. In 1983, the new reactor scheduled, Ni4 series 1400 MWe, is a totally French design which satisfies the French regulations and other French standards and codes. Based on a deterministic approach, the French safety analysis was progressively completed by a probabilistic approach each of them having possibilities and limits. Increasing knowledge and lessons learned from operating experience have contributed to the French safety philosophy improvement. The methodology now applied to safety evaluation develops a new facet of the in depth defense concept by taking highly unlikely events into consideration, by developing the search of safety consistency of the design, and by completing the deterministic approach by the probabilistic one

  4. Revisiting the cost escalation curse of nuclear power. New lessons from the French experience

    International Nuclear Information System (INIS)

    Escobar Rangel, Lina; Leveque, Francois

    2012-01-01

    Since the first wave of nuclear reactors in 1970 to the construction of Generation III+ reactors in Finland and France in 2005 and 2007 respectively, nuclear power seems to be doomed to a cost escalation curse. In this paper we reexamine this issue for the French nuclear power fleet. Using the construction costs from the Cour des Comptes report, that was publicly available in 2012, we found that previous studies overestimated the cost escalation. Although, it is undeniable that the scale-up ended up in more costly reactors, we found evidence of a learning curve within the same size and type of reactors. This result confirms that standardization is a good direction to look, in order to overcome the cost escalation curse. (authors)

  5. French diagnostic reference levels in diagnostic radiology, computed tomography and nuclear medicine: 2004-2008 Review

    International Nuclear Information System (INIS)

    Roch, P.; Aubert, B.

    2013-01-01

    After 5 y of collecting data on diagnostic reference levels (DRLs), the Nuclear Safety and Radiation Protection French Inst. (IRSN) presents the analyses of this data. The analyses of the collected data for radiology, computed tomography (CT) and nuclear medicine allow IRSN to estimate the level of regulatory application by health professionals and the representativeness of current DRL in terms of relevant examinations, dosimetric quantities, numerical values and patient morphologies. Since 2004, the involvement of professionals has highly increased, especially in nuclear medicine, followed by CT and then by radiology. Analyses show some discordance between regulatory examinations and clinical practice. Some of the dosimetric quantities used for the DRL setting are insufficient or not relevant enough, and some numerical values should also be reviewed. On the basis of these findings, IRSN formulates recommendations to update regulatory DRL with current and relevant examination lists, dosimetric quantities and numerical values. (authors)

  6. French diagnostic reference levels in diagnostic radiology, computed tomography and nuclear medicine: 2004-2008 review.

    Science.gov (United States)

    Roch, P; Aubert, B

    2013-04-01

    After 5 y of collecting data on diagnostic reference levels (DRLs), the Nuclear Safety and Radiation Protection French Institute (IRSN) presents the analyses of this data. The analyses of the collected data for radiology, computed tomography (CT) and nuclear medicine allow IRSN to estimate the level of regulatory application by health professionals and the representativeness of current DRL in terms of relevant examinations, dosimetric quantities, numerical values and patient morphologies. Since 2004, the involvement of professionals has highly increased, especially in nuclear medicine, followed by CT and then by radiology. Analyses show some discordance between regulatory examinations and clinical practice. Some of the dosimetric quantities used for the DRL setting are insufficient or not relevant enough, and some numerical values should also be reviewed. On the basis of these findings, IRSN formulates recommendations to update regulatory DRL with current and relevant examination lists, dosimetric quantities and numerical values.

  7. Modifications at operating nuclear power plants

    International Nuclear Information System (INIS)

    Duffy, T.J.; Gazda, P.A.

    1985-01-01

    Modifications at operating nuclear power plants offer the structural engineer many challenges in the areas of scheduling of work, field adjustments, and engineering staff planning. The scheduling of structural modification work for operating nuclear power plants is normally closely tied to planned or unplanned outages of the plant. Coordination between the structural engineering effort, the operating plant staff, and the contractor who will be performing the modifications is essential to ensure that all work can be completed within the allotted time. Due to the inaccessibility of some areas in operating nuclear power plants or the short time available to perform the structural engineering in the case of an unscheduled outrage, field verification of a design is not always possible prior to initiating the construction of the modification. This requires the structural engineer to work closely with the contractor to promptly resolve problems due to unanticipated interferences or material procurement problems that may arise during the course of construction. The engineering staff planning for structural modifications at an operating nuclear power plant must be flexible enough to permit rapid response to the common ''fire drills,'' but controlled enough to ensure technically correct designs and to minimize the expenditure of man-hours and the resulting engineering cost

  8. Thoughts on nuclear power plants

    International Nuclear Information System (INIS)

    Rouze, Michel

    1996-01-01

    In this article published before the Chernobyl accident (and the greenhouse effect issue), the author comments the evolution of the perception people have on nuclear energy: it was supposed to be the beginning of a golden age, and is finally perceived as a source of thermal and radioactive pollution and a major industrial risk. He outlines and criticizes the various and more or less violent reactions and debates about the fact that choosing nuclear energy means choosing a certain type of society. He considers that this point of view refuses reality. He states that the emerging new and renewable energies cannot be the solution. He comments the emergence of an energy crisis after the first oil crisis, and the associated questions about a possible reduction of consumption, the replacement of oil, the potential of renewable energies. He criticizes the excessive fear about nuclear materials and energy, discusses the actual risks associated with electronuclear production, and discusses the energy issue in the international context to outline the importance of nuclear energy. He finally addresses issues related to the definition and implementation of an energy policy, with EDF as a major actor

  9. The maintenance optimization of structural components in nuclear power plants

    International Nuclear Information System (INIS)

    Bryla, P.; Ardorino, F.; Aufort, P.; Jacquot, J.P.; Magne, L.; Pitner, P.; Verite, B.; Villain, B.; Monnier, B.

    1997-10-01

    An optimization process, called 'OMF-Structures', is developed by Electricite de France (EDF) in order to extend the current 'OMF' Reliability Centered Maintenance to piping structural components. The Auxiliary Feedwater System of a 900 MW French nuclear plant has been studied in order to lay the foundations of the method. This paper presents the currently proposed principles of the process. The principles of the OMF-Structures process include 'Risk-Based Inspection' concepts within an RCM process. Two main phases are identified: The purpose of the first phase is to select the risk-significant failure modes and associated elements. This phase consists of two major steps: potential consequences evaluation and reliability performance evaluation. The second phase consists of the definition of preventive maintenance programs for piping elements that are associated with risk-significant failure modes. (author)

  10. Nuclear power plant outage optimisation strategy

    International Nuclear Information System (INIS)

    2002-10-01

    Competitive environment for electricity generation has significant implications for nuclear power plant operations, including among others the need of efficient use of resources, effective management of plant activities such as on-line maintenance and outages. Nuclear power plant outage management is a key factor for good, safe and economic nuclear power plant performance which involves many aspects: plant policy, co-ordination of available resources, nuclear safety, regulatory and technical requirements and, all activities and work hazards, before and during the outage. This technical publication aims to communicate these practices in a way they can be used by operators and utilities in the Member States of the IAEA. It intends to give guidance to outage managers, operating staff and to the local industry on planning aspects, as well as examples and strategies experienced from current plants in operation on the optimization of outage period. This report discusses the plant outage strategy and how this strategy is actually implemented. The main areas identified as most important for outage optimization by the utilities and government organizations participating in this report are: organization and management; outage planning and preparation, outage execution, safety outage review, and counter measures to avoid extension of outages and to easier the work in forced outages. This report was based on discussions and findings by the authors of the annexes and the participants of an Advisory Group Meeting on Determinant Causes for Reducing Outage Duration held in June 1999 in Vienna. The report presents the consensus of these experts regarding best common or individual good practices that can be used at nuclear power plants with the aim to optimize

  11. Control and management of the chemical risk linked with hydrazine hydrate storage, unloading and injection across French nuclear fleet

    International Nuclear Information System (INIS)

    Spahic, Mersiha; Dzemidzic Aida; Dijoux, Michel; Pages, Danielle; Rigal, Jean-Francois; Boize, Magali

    2012-09-01

    Across the EDF nuclear fleet, the chemical risk linked with hydrazine hydrate storage, unloading and injection has received much attention in the past decades. Since 1997, continuous investigation into the substitution of dangerous and carcinogenic chemicals has been conducted and regularly updated by EDF. As a downstream user of hydrazine hydrate, EDF is concerned by REACH legislation, in force since 1 June 2007. As part of the compliance process with REACH, EDF provided its hydrazine hydrate suppliers with information regarding the uses of the chemical. This was done by the end of 2008, as per REACH deadline. On the other hand, EDF contributed throughout European Chemicals Agency consultation phase by submitting data relating to hydrazine hydrate uses across nuclear sites. The absence of a suitable hydrazine hydrate replacement product, able to satisfy the entirety of technical requirements, entails rigorous arrangements to be implemented in order to segregate the zones where use of hydrazine is made and therefore eradicate the risk to personnel regarding hydrazine effects. Consequently, a number of engineering changes and modifications are to be carried out on the chemical injection systems of 58 French nuclear power plants over the next few years as part of the EDF Hydrazine Fleet Programme. (authors)

  12. Explicatory Dictionary for Exact Sciences. Nuclear Energy, EN2. Nuclear Power. Romanian/English/French

    International Nuclear Information System (INIS)

    Dragan, Gleb; Rapeanu, S.N.; Comsa, Olivia

    2002-01-01

    The explicative dictionary for nuclear power, accomplished in the frame of the Commission for Scientific Terminology of the Romanian Academy, represents the second issue in a series running from Nuclear Energy EN 1 through Nuclear Energy EN 10 covering the following fields: EN 1. General terminology; EN 2. Nuclear power; EN 3. Physical protection and nuclear safeguards; EN 4. Nuclear fuel cycle; EN 5. Radioactive wastes; EN 6. Safety of nuclear facilities and materials; EN 7. Radioprotection and dosimetry; EN 8. Nuclear reactors; EN 9. Nuclear sciences and engineering; EN 10. Nuclear law and legislation. The main body of the dictionary's contents was selected by specialists working with the Center of Technology and Engineering for Nuclear Projects - CITON, based on their experience of more than 20 years in introducing and implementing nuclear power in Romania, as well as, on collaboration with nuclear physics and engineering research institutes and physics departments of Romanian universities. The project of a nuclear dictionary in 10 issues aims at supporting the program of nuclear power development in Romania and is at the same time part of nuclear knowledge management policy boosted by IAEA which encourages publication of informative materials highly specialized but also accessible to the public at large. The project aims also to establish the Romanian standardized terminology in the nuclear domain as much in line as possible with the terminologies of the largest communities worldwide most active in nuclear science and technology. Under the guidance of continuos build-up and evolution of nuclear knowledge the present work is intended to be upgraded permanently. The explanation of the terms was based on SR ISO standards, terminology adopted by Organization for Economic and Cooperation Development, OECD/NEA, and IAEA. This series is targeting translators, specialists, students, and the public at large

  13. Nuclear power plant in whose backyard

    International Nuclear Information System (INIS)

    Cooper, W.

    1981-01-01

    The authority to regulate the nuclear power industry resides largely with the federal government. But states have the responsibility to protect the health and safety of their citizens and to regulate land use within their borders. The siting of nuclear power plants can engender conflicts between these jurisdictions that are usually resolved in the courts. Most state challenges to federal control of nuclear power have been struck down or severely weakened by the preemption doctrine contained in the supremacy clause of Article VI of the Constitution, which provides for the preemption of federal law over state law in the event of direct conflict. The existing avenues for state control over siting and operation of nuclear power plants can be greatly strengthened while avoiding direct conflict with federal jurisdiction

  14. A nuclear power plant system engineering workstation

    International Nuclear Information System (INIS)

    Mason, J.H.; Crosby, J.W.

    1989-01-01

    System engineers offer an approach for effective technical support for operation and maintenance of nuclear power plants. System engineer groups are being set up by most utilities in the United States. Institute of Nuclear Power operations (INPO) and U.S. Nuclear Regulatory Commission (NRC) have endorsed the concept. The INPO Good Practice and a survey of system engineer programs in the southeastern United States provide descriptions of system engineering programs. The purpose of this paper is to describe a process for developing a design for a department-level information network of workstations for system engineering groups. The process includes the following: (1) application of a formal information engineering methodology, (2) analysis of system engineer functions and activities; (3) use of Electric Power Research Institute (EPRI) Plant Information Network (PIN) data; (4) application of the Information Engineering Workbench. The resulting design for this system engineer workstation can provide a reference for design of plant-specific systems

  15. Ground acceleration in a nuclear power plant

    International Nuclear Information System (INIS)

    Pena G, P.; Balcazar, M.; Vega R, E.

    2015-09-01

    A methodology that adopts the recommendations of international organizations for determining the ground acceleration at a nuclear power plant is outlined. Systematic presented here emphasizes the type of geological, geophysical and geotechnical studies in different areas of influence, culminating in assessments of Design Basis earthquake and the earthquake Operating Base. The methodology indicates that in regional areas where the site of the nuclear power plant is located, failures are identified in geological structures, and seismic histories of the region are documented. In the area of detail geophysical tools to generate effects to determine subsurface propagation velocities and spectra of the induced seismic waves are used. The mechanical analysis of drill cores allows estimating the efforts that generate and earthquake postulate. Studies show that the magnitude of the Fukushima earthquake, did not affect the integrity of nuclear power plants due to the rocky settlement found. (Author)

  16. Review of nuclear power plant systems

    International Nuclear Information System (INIS)

    Doehler

    1980-01-01

    This presentation starts with a brief description of the Technischer Ueberwachungs-Verein (TUeV) and its main activities in the field of technical assessments. The TUeV-organisation is in general the assessor who performs the review if nuclear power plant systems, structures and equipment. All aspects relating to the safe operation of nuclear power plants are assessed by the TUeV. This paper stresses the review of the design of nuclear power plant systems and structures. It gives an outline on the procedure of an assessment, starting with the regulatory requirements, going into the papers of the applicant and finally ending with the TUeV-appraisal. This procedure is shown using settlement measuring requirements as an example. The review of the design of mechanical structures such as pipes, valves, pump and vessels is shown in detail. (RW)

  17. Closures for underground nuclear power plants

    International Nuclear Information System (INIS)

    1981-10-01

    This study demonstrates that, with the appropriate selection of an access concept on the underground nuclear power plant, it is possible to design a gate complying with the increased requirements of the construction of an underground nuclear power plant. The investigations revealed that a comparison leakage of 42 mm in diameter for the failure of seals is too conservative. When selecting suitable seals a leakage being more extensive than the above mentioned one can be prevented even in case of disturbance lasting several months. The closure structures of the personnel and material accesses do not represent any weak point within the concept of the construction method for underground nuclear power plants. (orig./HP)

  18. Construct ability Improvement for Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Dae Soo; Lee, Jong Rim; Kim, Jong Ku [Korea Electric Power Research Institute, Taejon (Korea, Republic of)

    1997-12-31

    The purpose of this study was to identify methods for improving the construct ability of nuclear power plants. This study reviewed several references of current construction practices of domestic and overseas nuclear plants in order to identify potential methods for improving construct ability. The identified methods for improving construct ability were then evaluated based on the applicability to domestic nuclear plant construction. The selected methods are expected to reduce the construction period, improve the quality of construction, cost, safety, and productivity. Selection of which methods should be implemented will require further evaluation of construction modifications, design changes, contract revisions. Among construction methods studied, platform construction methods can be applied through construction sequence modification without significant design changes, and Over the Top construction method of the NSSS, automatic welding of RCL pipes, CLP modularization, etc., are considered to be applied after design modification and adjustment of material lead time. (author). 49 refs., figs., tabs.

  19. Wireless Technology Application to Nuclear Power Plants

    International Nuclear Information System (INIS)

    Lee, Jeong Kweon; Jeong, See Chae; Jeong, Ki Hoon; Oh, Do Young; Kim, Jae Hack

    2009-01-01

    Wireless technologies are getting widely used in various industrial processes for equipment condition monitoring, process measurement and other applications. In case of Nuclear Power Plant (NPP), it is required to review applicability of the wireless technologies for maintaining plant reliability, preventing equipment failure, and reducing operation and maintenance costs. Remote sensors, mobile technology and two-way radio communication may satisfy these needs. The application of the state of the art wireless technologies in NPPs has been restricted because of the vulnerability for the Electromagnetic Interference and Radio Frequency Interference (EMI/RFI) and cyber security. It is expected that the wireless technologies can be applied to the nuclear industry after resolving these issues which most of the developers and vendors are aware of. This paper presents an overview and information on general wireless deployment in nuclear facilities for future application. It also introduces typical wireless plant monitoring system application in the existing NPPs

  20. Nuclear plant cancellations: causes, costs, and consequences

    International Nuclear Information System (INIS)

    1983-04-01

    This study was commissioned in order to help quantify the effects of nuclear plant cancellations on the Nation's electricity prices. This report presents a historical overview of nuclear plant cancellations through 1982, the costs associated with those cancellations, and the reasons that the projects were terminated. A survey is presented of the precedents for regulatory treatment of the costs, the specific methods of cost recovery that were adopted, and the impacts of these decisions upon ratepayers, utility stockholders, and taxpayers. Finally, the report identifies a series of other nuclear plants that remain at risk of canellation in the future, principally as a result of similar demand, finance, or regulatory problems cited as causes of cancellation in the past. The costs associated with these potential cancellations are estimated, along with their regional distributions, and likely methods of cost recovery are suggested

  1. The french nuclear industry is looking for an american partner; Le nucleaire francais cherche un allie americain

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-07-01

    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.)

  2. Design concepts of nuclear desalination plants

    International Nuclear Information System (INIS)

    2002-11-01

    Interest in using nuclear energy for producing potable water has been growing worldwide in the past decade. This has been motivated by a variety of factors, including economic competitiveness of nuclear energy, the growing need for worldwide energy supply diversification, the need to conserve limited supplies of fossil fuels, protecting the environment from greenhouse gas emissions, and potentially advantageous spin-off effects of nuclear technology for industrial development. Various studies, and at least one demonstration project, have been considered by Member States with the aim of assessing the feasibility of using nuclear energy for desalination applications under specific conditions. In order to facilitate information exchange on the subject area, the IAEA has been active for a number of years in compiling related technical publications. In 1999, an inter regional technical co-operation project on Integrated Nuclear Power and desalination System Design was launched to facilitate international collaboration for the joint development by technology holders and potential end users of an integrated nuclear desalination system. This publication presents material on the current status of nuclear desalination activities and preliminary design concepts of nuclear desalination plants, as made available to the IAEA by various Member States. It is aimed at planners, designers and potential end-users in those Member States interested in further assessment of nuclear desalination. Interested readers are also referred to two related and recent IAEA publications, which contain useful information in this area: Introduction of Nuclear Desalination: A Guidebook, Technical Report Series No. 400 (2000) and Safety Aspects of Nuclear Plants Coupled with Seawater Desalination Units, IAEA-TECDOC-1235 (2001)

  3. Nuclear fuel production at BNFL plants

    International Nuclear Information System (INIS)

    Petritskij, E.P.

    1994-01-01

    The structure of nuclear fuel production at BNFL plants is described, as well as basic technological processes of UO 2 powder production including IDR process for automatic fabrication of fuel elements and fuel assemblies. Physical and chemical properties of UO 2 powder, fuel pellet sintering parameters, data on in-reactor operation of nuclear fuels fabricated from pellets of controlled porosity with CONPOR additives, are presented. 8 refs.; 2 figs.; 3 tabs

  4. Safety targets for nuclear power plants

    International Nuclear Information System (INIS)

    Herttrich, P.M.

    1985-01-01

    By taking as an example the safety targets of the American nuclear energy authority US-NRC, this paper explains what is meant by global, quantitative safety targets for nuclear power plants and what expectations are associated with the selecton of such safety targets. It is shown how probabilistic methods can be an appropriate completion of proven deterministic methods and what are the sectors where their application may become important in future. (orig./HP) [de

  5. Investment issues in nuclear plant license renewal

    International Nuclear Information System (INIS)

    Eynon, R.T.

    1999-01-01

    A method that determines the operating lives for existing nuclear power plants is discussed. These assumptions are the basis for projections of electricity supply through 2020 reported in the Energy Information Administration's (EIA's) Annual Energy Outlook 1999. To determine if plants will seek license renewal, one must first determine if they will be operating to the end of their current licenses. This determination is based on an economic test that assumes an investment of $150/kW will be required after 30 yr of operation for plants with older designs. This expenditure is intended to be equivalent to the cost that would be associated with any of several needs such as a one0time investment to replace aging equipment (steam generators), a series of investments to fix age-related degradation, increases in operating costs, or costs associated with decreased performance. This investment is compared with the cost of building and operating the lowest-cost new plant over the same 10-yr period. If a plant fails this test, it is assumed to be retired after 30 yr of service. All other plants are then considered candidates for license renewal. The method used to determine if it is economic to apply for license renewal and operate plants for an additional 20 yr is to assume that plants face an investment of $250 million after 40 yr of operation to refurbish aging components. This investment is compared with the lowest-cost new plant alternative evaluated over the same 20 yr that the nuclear plant would operate. If the nuclear plant is the lowest cost option, it is projected to continue to operate. EIA projects that it would be economic to extend the operating licenses for 3.7 GW of capacity (6 units)

  6. Child leukemias around nuclear power plants: what can we learn from epidemiologic surveys?

    International Nuclear Information System (INIS)

    Esteve, J.; Hubert, D.; Le Guen, B.

    2012-01-01

    A recent study has shown an excess of child leukemias around the French nuclear power plants. This result contradicts a previous study based on data collected between 1990 and 1998. The new study differs on 2 points: first only data from nuclear power plants have been taken into account and a new factor called 'distance to pollution sources' has been defined. This new approach allows us to take into account health hazards due to the presence of high roads, of high voltage power lines, of gas stations and of the level of natural radioactivity in the vicinity of the plants. Studies performed in foreign countries show also an excess of child leukemias in a few cases but with radiation doses so weak that a viral origin of the disease is suspected. The hypothesis of the viral origin of the leukemia could be comforted or invalidated by surveys involving other industrial facilities than nuclear power plants. (A.C.)

  7. Barsebaeck nuclear plant February-99

    International Nuclear Information System (INIS)

    Buch, Ann-Christin

    1999-01-01

    Barsebaeck should, according to the government decision, have been closed before the 1st of July 1998, but the Supreme Administrative Court ruled on Stay of Execution, after Barsebaeck Kraft had applied for judicial review. The Threat of a Phase out of Barsebaeck 1 started in 1980, due to the accident at Three Mile Island. Swedish opinion Opinion polls (Nov 97, March 98 and May 98) shows that about 80 percent of the Swedish population want to use nuclear power until the existing reactors have to be stopped for safety or economical reasons. About 20 percent of these want to develop nuclear power. Average or high confidence in Barsebaeck has 94 percent on the Swedish side and 74 percent in Copenhagen 1998. From February 1997 till August 1998 Barsebaeck personnel have executed several information activities to stress our message that Barsebaeck is necessary for the environment, the jobs and the economy

  8. G. Nuclear power plant siting

    International Nuclear Information System (INIS)

    1976-01-01

    The selection of a site for a nuclear power site is a complex process involving considerations of public health and safety, engineering design, economics, and environmental impact. Although policies adopted in various countries differ in some details, a common philosophy usually underlies the criteria employed. The author discusses the basic requirements, as they relate to New Zealand, under the headings: engineering and economics; health and safety; environmental factors

  9. Nuclear power plants; security strategy

    International Nuclear Information System (INIS)

    Sidorenko, V.A.

    1989-01-01

    Safety standards and approaches to NPPs safety resulting from multilayer experience are presented. It is stressed that sufficiency and efficiency of reactor safety measures should be payed constant attention. Real evolution of accidents reqires unlimited development of new safety means. It is evident that in nuclear power there should exist high s afety culture . NPPs safety should be guaranteed by joint measures of both specialists ans public

  10. A nuclear power plant status monitor

    International Nuclear Information System (INIS)

    Chu, B.B.; Conradi, L.L.; Weinzimmer, F.

    1986-01-01

    Power plant operation requires decisions that can affect both the availability of the plant and its compliance with operating guidelines. Taking equipment out of service may affect the ability of the plant to produce power at a certain power level and may also affect the status of the plant with regard to technical specifications. Keeping the plant at a high as possible production level and remaining in compliance with the limiting conditions for operation (LCOs) can dictate a variety of plant operation and maintenance actions and responses. Required actions and responses depend on the actual operational status of a nuclear plant and its attendant systems, trains, and components which is a dynamic situation. This paper discusses an Electric Power Research Institute (EPRI) Research Project, RP 2508, the objective of which is to combine the key features of plant information management systems with systems reliability analysis techniques in order to assist nuclear power plant personnel to perform their functions more efficiently and effectively. An overview of the EPRI Research Project is provided along with a detailed discussion of the design and operation of the PSM portion of the project

  11. Operation of Finnish nuclear power plants

    International Nuclear Information System (INIS)

    Tossavainen, K.

    1992-03-01

    The Finnish nuclear power plant units Loviisa 1 and 2 as well as TVO I and II were in operation for almost the whole third quarter of 1991. Longer interruptions in electricity generation were caused by the annual maintenances of the Loviisa plant units. The load factor average was 81.7 %. In a test conducted during the annual maintenance outage of Loviisa 1 it was detected that the check valve of the discharge line of one pressurized emergency make-up tank did not open sufficiently at the tank's hydrostatic pressure. In connection with a 1988 modification, a too tightly dimensioned bearing had been mounted on the valve's axle rod and the valve had not been duly tested after the operation. The event is classified as Level 1 on the International Nuclear Event Scale. Other events in this quarter which are classified according to the International Nuclear Event Scale are Level Zero (Below Scale). Occupational radiation doses and releases of radioactive material off-site were below authorised limits in this quarter. Only small amounts of radioactive materials originating in nuclear power plants were detected in samples taken in the vicinity of nuclear power plants

  12. Seismic analysis of nuclear power plants

    International Nuclear Information System (INIS)

    Halbritter, A.L.

    1984-01-01

    Nuclear Power Plants require exceptional safety guarantees which are reflected in a rigorous control of the employed materials, advanced construction technology, sophisticated methods of analysis and consideration of non conventional load cases such as the earthquake loading. In this paper, the current procedures used in the seismic analysis of Nuclear Power Plants are presented. The seismic analysis of the structures has two objectives: the determination of forces in the structure in order to design it against earthquakes and the generation of floor response spectra to be used in the design of mechanical and electrical components and piping systems. (Author) [pt

  13. Virtual environments for nuclear power plant design

    International Nuclear Information System (INIS)

    Brown-VanHoozer, S.A.; Singleterry, R.C. Jr.; King, R.W.

    1996-01-01

    In the design and operation of nuclear power plants, the visualization process inherent in virtual environments (VE) allows for abstract design concepts to be made concrete and simulated without using a physical mock-up. This helps reduce the time and effort required to design and understand the system, thus providing the design team with a less complicated arrangement. Also, the outcome of human interactions with the components and system can be minimized through various testing of scenarios in real-time without the threat of injury to the user or damage to the equipment. If implemented, this will lead to a minimal total design and construction effort for nuclear power plants (NPP)

  14. Seismic instrumentation for nuclear power plants

    International Nuclear Information System (INIS)

    Senne Junior, M.

    1983-01-01

    A seismic instrumentation system used in Nuclear Power Plants to monitor the design parameters of systems, structures and components, needed to provide safety to those Plants, against the action of earthquakes is described. The instrumentation described is based on the nuclear standards in force. The minimum amount of sensors and other components used, as well as their general localization, is indicated. The operation of the instrumentation system as a whole and the handling of the recovered data are dealt with accordingly. The various devices used are not covered in detail, except for the accelerometer, which is the seismic instrumentation basic component. (Author) [pt

  15. Nuclear power plant siting: Hydrogeologic aspects

    International Nuclear Information System (INIS)

    1984-01-01

    This Safety Guide gives guidelines and methods for determining the ground water concentration of radionuclides that could result from postulated releases from nuclear power plants. The Guide gives recommendations on the data to be collected and the investigations to be performed at various stages of nuclear power plant siting in relation to the various aspects of the movement of accidentally released radioactive material through the ground water, the selection of an appropriate mathematical or physical model for the hydrodynamic dispersion even two-phase distribution of the radioactive material and an appropriate monitoring programme

  16. Fire protection in nuclear power plants

    International Nuclear Information System (INIS)

    1991-01-01

    This translation of an IAEA publication (Safety Series No. 50-SD-D2, Rev.1) is a safety guide for fire protection of above-ground nuclear power plants equipped with reactors working with thermal neutrons. It is aimed at designers and surveillance bodies as an aid for setting up the fire protection concept in the design of the nuclear power plant and in its operation. The publication defines generic requirements and aims of fire protection, prevention and extinguishing, gives hints for reducing the secondary impacts of fires, and lays down requirements for quality assurance and basic principles of fire protection. (M.D.). 9 figs., 1 tab

  17. Studies in training nuclear plant personnel

    International Nuclear Information System (INIS)

    Hamlin, K.W.

    1987-01-01

    One of the lessons learned from the Three Mile Island (TMI) accident was that the nuclear industry was ineffective in learning from previous events at other plants. As training programs and methods have improved since TMI, the nuclear industry has searched for effective methods to teach the lessons learned from industry events. The case study method has great potential as a solution. By reviewing actual plant events in detail, trainees can be challenged with solving actual problems. When used in a seminar or discussion format, these case studies also help trainees compare their decision-making processes with other trainees, the instructor, and the personnel involved in the actual case study event

  18. Virtual environments for nuclear power plant design

    Energy Technology Data Exchange (ETDEWEB)

    Brown-VanHoozer, S.A.; Singleterry, R.C. Jr.; King, R.W. [and others

    1996-03-01

    In the design and operation of nuclear power plants, the visualization process inherent in virtual environments (VE) allows for abstract design concepts to be made concrete and simulated without using a physical mock-up. This helps reduce the time and effort required to design and understand the system, thus providing the design team with a less complicated arrangement. Also, the outcome of human interactions with the components and system can be minimized through various testing of scenarios in real-time without the threat of injury to the user or damage to the equipment. If implemented, this will lead to a minimal total design and construction effort for nuclear power plants (NPP).

  19. Site survey for nuclear power plants

    International Nuclear Information System (INIS)

    1984-01-01

    This Safety Guide describes the first stage of the siting process for nuclear power plants - the site survey to select one or more preferred candidate sites. Its purpose is to recommend procedures and provide information for use in implementing a part of the Code of Practice on Safety in Nuclear Power Plant Siting (IAEA Safety Series No.50-C-S). The organization, procedures, methodologies, guidance for documenting the site survey process and examples of detailed procedures on some safety-related site characteristics are given in the Guide

  20. Construction plant requirements for nuclear sites

    International Nuclear Information System (INIS)

    Tatum, C.B.; Harris, J.A.

    1981-01-01

    Planning and developing the temporary construction plant facilities for a nuclear project is equivalent to providing utility services for a small city. Provision of adequate facilities is an important factor in the productivity of both the manual and non-manual work force. This paper summarizes construction facility requirements for a two unit (1300 MWe each) nuclear project. Civil, mechanical and electrical facilities are described, including design, installation and operation. Assignment of responsibility for specific work tasks regarding the construction plant is also discussed. In presenting this data, the authors seek to transfer experience and assist in the provision of adequate facilities on future projects

  1. Summary revaluation of energetic start-up of the unit 1 of nuclear power plant Mochovce

    International Nuclear Information System (INIS)

    Sarvaic, I.; Miskolci, M.

    1998-01-01

    The document contents stage revaluation of energetic start-up of the unit 1 of nuclear power plant Mochovce. Test results of the stage of energetic start-up are summarized in the document, valuation of important systems and block devices as well as fulfilling the operation limits and conditions has been performed. On that base conclusions and recommendations for start-up the unit 2 and for commercial operation of the unit 1 are elaborated. The valuation has been elaborated by a scientific management for start-up nuclear power plant Mochovce of nuclear safety of nuclear power facilities. Scientific management for start-up of nuclear power plant Mochovce performed continuous valuation of individual power levels after ending of each individual level and it gave its valuation to energy power level with recommendations and conditions for further start-up process and operation. Scientific management finished its activity at the unit 1 of nuclear power plant Mochovce according to a statute of scientific management for start-up after successful completion of conclusive block run. Scientific management group was founded in February 1998 at nuclear power plant Mochovce. Its members are experts from Slovak, Czech, Russian and French organizations which are participating in power plant completion. Members are listed in a supplement No. 2

  2. Seismic safety of nuclear power plants

    International Nuclear Information System (INIS)

    Guerpinar, A.; Godoy, A.

    2001-01-01

    This paper summarizes the work performed by the International Atomic Energy Agency in the areas of safety reviews and applied research in support of programmes for the assessment and enhancement of seismic safety in Eastern Europe and in particular WWER type nuclear power plants during the past seven years. Three major topics are discussed; engineering safety review services in relation to external events, technical guidelines for the assessment and upgrading of WWER type nuclear power plants, and the Coordinated Research Programme on 'Benchmark study for the seismic analysis and testing of WWER type nuclear power plants'. These topics are summarized in a way to provide an overview of the past and present safety situation in selected WWER type plants which are all located in Eastern European countries. Main conclusion of the paper is that although there is now a thorough understanding of the seismic safety issues in these operating nuclear power plants, the implementation of seismic upgrades to structures, systems and components are lagging behind, particularly for those cases in which the re-evaluation indicated the necessity to strengthen the safety related structures or install new safety systems. (author)

  3. VISIT - Virtual visits to nuclear power plants

    International Nuclear Information System (INIS)

    Mollaret, Jean-Christophe

    2001-01-01

    For more than twenty years, EDFs Communication Division has conducted a policy of opening its generation sites to the general public. Around 300,000 people visit a nuclear power plant every year. However, for the security of persons and the safety of facilities, those parts of the plant situated in controlled areas are not accessible to visitors. For the sake of transparency, EDF has taken an interest in the technologies offered by virtual reality to show the general public what a nuclear power plant is really like, so as to initiate dialogue on nuclear energy, particularly with young people. Visit has been developed with virtual reality technologies. It serves to show the invisible (voyage to the core of fission), the inaccessible and to immerse the visitors in environments which are usually closed to the general public (discovery of the controlled area of a nuclear power plant). Visit is used in Public Information Centres which receive visitors to EDF power plants and during international exhibitions and conferences. Visit allows a virtual tour of the following controlled areas: locker room hot area/cold area, a necessary passage before entering the controlled areas; reactor building; fuel building; waste auxiliary building (liquid, solid and gaseous effluents). It also includes a tour of the rooms or equipment usually accessible to the general public: control room, turbine hall, transformer, air cooling tower

  4. Turbines for nuclear power plants. 2.ed.

    International Nuclear Information System (INIS)

    Troyanovskij, B.M.

    1978-01-01

    In the second edition of the book considered are practically all the main problems of calculation and operation of turbines and turbine installations of nuclear power plants. As compared to the first edition, essentially addes is the reproduction of the problem on combined generation of heat and electric energy. Also represented is detailed material on methods of preliminary evaluation of turbine effectiveness. Considered are peculiarities of turbine operation on wet steam and the basis of their thermal calculation. Much attention is payed to the problem of wet stream current in the turbine elements and wetness effect on their characteristics. Problems of wetness separation and moving blade erosion as well as other turbine elements are extracted in a special section. Given are structural schemes of different methods of innerchannel and periphery wet removal as well as experimental materials on their effectiveness. Given are descriptions and critical analysis of a great number of typical constructions of nuclear power plant steam turbines, produced by native plants as well as by the main foreign firms. Considered also are constructions of outside separators and steam superheaters. Separately given is the problem of rotation frequency choise of nuclear power plant wet steam turbines. Represented are materials on turbine installation tests, considered are the problems of turbine starting and manoeuvrability, analyzed are their typical jailures and damages. One of the sections of the book is devoted to gas turbine installations of nuclear power plants. Different material on this theme scattered before in various sources is summarized in the book

  5. Classification of nuclear plant cost to energy

    International Nuclear Information System (INIS)

    Long, G.A.

    1983-01-01

    In order to understand why the fixed-cost/variable-cost method of classifying nuclear plant costs can lead to rate discontinuities, the author must examine the factors which lead to the decision to build a nuclear power plant and the interrelationship between demand (KW) and energy (KWH). The problems and inequities associated with the nuclear plants can be avoided by recognizing that fixed costs are related to both demand and energy and by using a costing methodology which closely relates to the functional purpose of the plant. Generally, this leads to classifying fixed costs of nuclear plants primarily to the energy function in an embedded cost-of-service study and through either implicit or explicit recognition of fuel savings in a marginal cost study. The large rate discontinuities which occurred in the scenario can be resolved. Costs associated with demand or energy charges remain relatively stable compared to actual capacity costs and customers would not experience large changes in their bills due solely to a particular costing convention

  6. 78 FR 55118 - Seismic Instrumentation for Nuclear Power Plants

    Science.gov (United States)

    2013-09-09

    ... NUCLEAR REGULATORY COMMISSION [NRC-2013-0202] Seismic Instrumentation for Nuclear Power Plants... Reports for Nuclear Power Plants: LWR Edition,'' Section 3.7.4, ``Seismic Instrumentation.'' DATES: Submit... Nuclear Power Plants: LWR Edition'' (SRP, from the current Revision 2 to a new Revision 3). The proposed...

  7. 76 FR 75771 - Emergency Planning Guidance for Nuclear Power Plants

    Science.gov (United States)

    2011-12-05

    ... Guidance for Nuclear Power Plants AGENCY: Nuclear Regulatory Commission. ACTION: Issuance of NUREG... Support of Nuclear Power Plants;'' NSIR/DPR-ISG-01, ``Interim Staff Guidance Emergency Planning for Nuclear Power Plants;'' and NUREG/CR-7002, ``Criteria for Development of Evacuation Time Estimate Studies...

  8. The atolls of Mururoa and Fangataufa (French Polynesia). The nuclear testings. Radiological aspects

    International Nuclear Information System (INIS)

    Martin, G.

    2007-01-01

    This report provides a review of the radiological measures implemented during the thirty year period of French nuclear tests in Polynesian atolls of Mururoa and Fangataufa. It presents full details of the practices deployed throughout these tests, including, in particular, aspects concerning radiological protection for the population and the environment. It contains all the scientific results and measurements of radioactivity performed during this period, providing concrete facts that can be used to assess the consequences these tests have had on the personnel involved, the population and the environment. (author)

  9. Maintenance of nuclear power plants

    International Nuclear Information System (INIS)

    1982-01-01

    This Guide covers the organizational and procedural aspects of maintenance but does not give detailed technical advice on the maintenance of particular plant items. It gives guidance on preventive and remedial measures necessary to ensure that all structures, systems and components important to safety are capable of performing as intended. The Guide covers the organizational and administrative requirements for establishing and implementing preventive maintenance schedules, repairing defective plant items, providing maintenance facilities and equipment, procuring stores and spare parts, selecting and training maintenance personnel, reviewing and controlling plant modifications arising from maintenance, and for generating, collecting and retaining maintenance records. Maintenance shall be subject to quality assurance in all aspects important to safety. Because quality assurance has been dealt with in detail in other Safety Guides, it is only included here in specific instances where emphasis is required. Maintenance is considered to include functional and performance testing of plant, surveillance and in-service inspection, where these are necessary either to support other maintenance activities or to ensure continuing capability of structures, systems and components important to safety to perform their intended functions

  10. Managing the first nuclear power plant project

    International Nuclear Information System (INIS)

    2007-05-01

    Energy is essential for national development. Nearly every aspect of development - from reducing poverty and raising living standards to improving health care, industrial and agricultural productivity - requires reliable access to modern energy resources. States may have different reasons for considering starting a nuclear power project to achieve their national energy needs, such as: lack of available indigenous energy resources, the desire to reduce dependence upon imported energy, the need to increase the diversity of energy resources and/or mitigation of carbon emission increases. The start of a nuclear power plant project involves several complex and interrelated activities with long duration. Experience shows that the time between the initial policy decision by a State to consider nuclear power up to the start of operation of its first nuclear power plant is about 10 to 15 years and that before specific project management can proceed, several key infrastructure issues have to be in place. The proper management of the wide scope of activities to be planned and implemented during this period represents a major challenge for the involved governmental, utility, regulatory, supplier and other supportive organizations. The main focus is to ensure that the project is implemented successfully from a commercial point of view while remaining in accordance with the appropriate engineering and quality requirements, safety standards and security guides. This publication is aimed at providing guidance on the practical management of a first nuclear power project in a country. There are many other issues, related to ensuring that the infrastructure in the country has been prepared adequately to ensure that the project will be able to be completed, that are only briefly addressed in this publication. The construction of the first nuclear power plant is a major undertaking for any country developing a nuclear power programme. Worldwide experience gained in the last 50 years

  11. Nuclear plant construction and investment risk

    International Nuclear Information System (INIS)

    Studness, C.M.

    1984-01-01

    Escalated cost estimations, delays and cancellations in nuclear construction have caused a preoccupation with the risks of nuclear power plant construction that dominates utility stock investment, overshadowing increased earnings per share and recent growth in production. The issue will be resolved when increased power demand requires new construction, but the effect has so far been to erode the economic advantage of nuclear power and threaten the ability of utilities to get rate increases high enough to cover their costs. Projected delays and cost escalations and their effects must go into an economic appraisal of the investment risks

  12. Seismic isolation of nuclear power plants - EDF's philosophy

    International Nuclear Information System (INIS)

    Coladant, C.

    1989-01-01

    The elastomer bearing pads used since 1963 as supports for prestressed concrete pressure vessels (PCPVs) was quickly chosen by Electricite de France (ED) to improve the capability of nuclear power plants (NPPs) to withstand strong earthquakes and to reduce the seismic loads on structures and equipment. The standardized units for 900 and 1,300 MW(e) pressurized water reactor (PWR) plants have moderate seismic design loads of 0.2 and 0.15 g, respectively. These design loads were exceeded by the site dependent spectra of Cruas (France) and Koeberg (South Africa). To keep the plant design unchanged and to take the advantages of standardization, these units were put on laminated bearings with or without sliding plates. For the future French 1,500 MW(e) fast breeder reactors (FBRs), which are more sensitive to seismic loads, the base isolation is considered by EDF at the beginning of the design, even for low ground motions of 0.1 g. The buildings are placed on laminated bearings while the reactor block is supported by springs and dampers. The isolated plant has identical costs as a conventional design such as SPX1 at Creys-Malville

  13. The mitigation of the French nuclear option: new industrial realism and technical democracy

    Energy Technology Data Exchange (ETDEWEB)

    Finon, D.

    2002-07-01

    Nuclear phase-out policies and the European obligation to liberalise electricity markets could put the French nuclear option dramatically at risk by influencing social preferences or by constraining power producers' investment choices in the future. So far, the particular institutional set-up which has allowed the efficient buildup and operation of several series of standardised reactors preserves the stability of the main elements of the option. However, important adaptations to the evolving industrial and political environment occur and contribute to changing the option. Some institutional changes (such as local public inquiry, creation of a Parliamentary committee, independence of safety authorities) and divergence between industrial interests already allow debates on internal options such as reprocessing, type of waste management deposits, ordering of an advanced PWR. These changes improve the cost transparency, even if internalisation of nuclear externalities (cost of insurance, provisions for waste management) is still incomplete. However, when effective, this internalisation would not affect definitively the competitive position of the nuclear production because of the parallel internalisation of CO{sub 2} externalities from fossil fuel power generation in the official rationale. Consequently the real issue for the future of the nuclear option in France remains the preservation of social acceptability in the perception of nuclear risks. (author)

  14. Dukovany nuclear power plant in 1993

    International Nuclear Information System (INIS)

    1994-01-01

    Data on the power generation, nuclear safety, and gaseous and liquid releases into the environment were extracted from the 1993 annual report of the Dukovany nuclear power plant. Operation of the plant was safe and reliable in 1993. Three events were classed as INES category 1. The plant's Failure Commission dealt with 100 events which brought about a total electricity generation loss of 217,624 MWh, corresponding to about 22 reactor-days. Out of this, 26.8 % was due to human error. Three fires occurred at the power plant site. Releases of radioactive aerosols, tritium, noble gases and radioiodine into air and of tritium, corrosion products, and fission products into the aquatic environment were below annual limits. The collective dose equivalent was 1.78 manSv in 1993. (Z.S.). 2 tabs., 11 figs

  15. Costs of Decommissioning Nuclear Power Plants

    International Nuclear Information System (INIS)

    Neri, Emilio; French, Amanda; Urso, Maria Elena; Deffrennes, Marc; Rothwell, Geoffrey; ); Rehak, Ivan; Weber, Inge; ); Carroll, Simon; Daniska, Vladislav

    2016-01-01

    While refurbishments for the long-term operation of nuclear power plants and for the lifetime extension of such plants have been widely pursued in recent years, the number of plants to be decommissioned is nonetheless expected to increase in future, particularly in the United States and Europe. It is thus important to understand the costs of decommissioning so as to develop coherent and cost-effective strategies, realistic cost estimates based on decommissioning plans from the outset of operations and mechanisms to ensure that future decommissioning expenses can be adequately covered. This study presents the results of an NEA review of the costs of decommissioning nuclear power plants and of overall funding practices adopted across NEA member countries. The study is based on the results of this NEA questionnaire, on actual decommissioning costs or estimates, and on plans for the establishment and management of decommissioning funds. Case studies are included to provide insight into decommissioning practices in a number of countries. (authors)

  16. Improving the knowledge of environment around French nuclear facilities for better dose assessment and post-accidental management

    Energy Technology Data Exchange (ETDEWEB)

    Parache, V.; Renaud, P. [Institut de Radioprotection et de Surete Nucleaire - IRSN (France)

    2014-07-01

    The consequences of an industrial pollution for the population and the environment depend not only on the nature and extent of the pollution, but also of the characteristics of concerned environment: the use that man made of it, and of the man's habits, notably food practices. To improve the consideration of the specificities of territories in its evaluations and its recommendations, in normal operation or in accident and post-accident situations, the Institute for Radioprotection and Nuclear Safety characterizes the environment of the nuclear installations. This standardised measurement of the environmental and population characteristics will be useful in risk assessment and management, and in all the operational stages of a nuclear installation. This characterization concerns the inventory of the main agricultural productions (vegetable and animal), the important agricultural dates (seeding, harvest) and the practices and eating habits of animals, the industry and the local food-processing, as well as on the food practices of the persons which live around the French nuclear power plant. National surveys have identified the major characteristics of French eating habits. Above and beyond the fact that these surveys do not consider local specificities, the use of their results for dosimetric assessments has certain drawbacks: the categories of foodstuffs most vulnerable to contamination in post-accident situations (fresh fruit and vegetables, fresh milk and cheeses) are very rarely described in detail; representation of the eating habits of an 'average' population does not give us as the behaviors of the most sensitive groups. The prime objective of local studies is to describe eating habits (rations and local production rates) of potentially most exposed population around nuclear facilities which may cultivate various foodstuffs. These comparative studies highlighted the important variability of the particular eating habits of the French population

  17. 78 FR 50458 - Entergy Nuclear Operations, Inc., James A. Fitzpatrick Nuclear Power Plant, Vermont Yankee...

    Science.gov (United States)

    2013-08-19

    ... Nuclear Operations, Inc., James A. Fitzpatrick Nuclear Power Plant, Vermont Yankee Nuclear Power Station, Pilgrim Nuclear Power Station, Request for Action AGENCY: Nuclear Regulatory Commission. ACTION: Request... that the NRC take action with regard to James A. Fitzpatrick Nuclear Power Plant, Vermont Yankee...

  18. Assessment of nuclear power plant siting methods

    Energy Technology Data Exchange (ETDEWEB)

    Rowe, M.D.; Hobbs, B.F.; Pierce, B.L.; Meier, P.M.

    1979-11-01

    Several different methods have been developed for selecting sites for nuclear power plants. This report summarizes the basic assumptions and formal requirements of each method and evaluates conditions under which each is correctly applied to power plant siting problems. It also describes conditions under which different siting methods can produce different results. Included are criteria for evaluating the skill with which site-selection methods have been applied.

  19. Intelligent maintenance system for nuclear power plant

    International Nuclear Information System (INIS)

    Matsuda, Keiichi; Okano, Hideharu; Kobayashi, Masahiro; Tokura, Takehiko.

    1997-01-01

    An advanced Intelligent Maintenance System has been developed to realize highly reliable and efficient maintenance operation in the future for nuclear power plants. This system is equipped with high level sensing and robotic technologies and is composed of the following 4 systems; (1) Common System of Intellectual Maintenance (2) Inspection System in Operating Plants (3) Underwater Inspection System (4) Full-Automated Welding System. This Project is promoted by MITI from FY 1991 to FY 1995. (author)

  20. Floating nuclear power plant safety assurance principles

    International Nuclear Information System (INIS)

    Zvonarev, B.M.; Kuchin, N.L.; Sergeev, I.V.

    1993-01-01

    In the north regions of the Russian federation and low density population areas, there is a real necessity for ecological clean energy small power sources. For this purpose, floating nuclear power plants, designed on the basis of atomic ship building engineering, are being conceptualized. It is possible to use the ship building plants for the reactor purposes. Issues such as radioactive waste management are described

  1. Steam turbines for nuclear power plants

    International Nuclear Information System (INIS)

    Kosyak, Yu.F.

    1978-01-01

    Considered are the peculiarities of the design and operation of steam turbines, condensers and supplementary equipment of steam turbines for nuclear power plants; described are the processes of steam flow in humid-steam turbines, calculation and selection principles of main parameters of heat lines. Designs of the turbines installed at the Charkov turbine plant are described in detail as well as of those developed by leading foreign turbobuilding firms

  2. Nuclear power plants waste management practices in France

    International Nuclear Information System (INIS)

    Matsuda, Fumio

    1998-01-01

    This survey offers a complete review concerning the nuclear power plants waste management in France from generation to disposal, as well as future evolutions. Fundamental Safety Rule specified by the government defines safety objectives, design bases for surface disposals and preliminary terms for acceptance of waste packages on the surface disposal site. A governmental decree authorizes the creation of CSA (Centre de Stockage de l'Aude; French surface repository), and defines the limits of radiological inventory of the disposal facility. The national waste agency ANDRA was established in 1979 by government (turned into public in 1991), and ANDRA defines the technical specifications involving acceptance criteria of the waste packages. The main feature of the French management includes; Comprehensive quality assurance program that encompasses all area of the management. Centralized installation for the melting of contaminated scrap metals and incineration of low level technological wastes. Mobile unit for common treatment of ion exchange resin. Concrete package assuring the long term containment. Complete tracking system of wastes from generation to disposal. This survey would be useful in the consideration of Japanese waste management including miscellaneous wastes, high βγ wastes, large metallic wastes, etc. (author)

  3. Waste from decommissioning of nuclear power plants

    International Nuclear Information System (INIS)

    Nielsen, P.O.

    1992-05-01

    This report is based on the assumption that all twelve nuclear power plants will be shut down no later than A.D. 2010, as was decided by the parliament after the referendum on the future of nuclear power in Sweden. The recent 'Party agreement on the energy policy' of January 15, 1991 does, indeed, leave the door open for an extension of the operational period for the nuclear reactors. This will, however, not change the recommendations and conclusions drawn in this report. The report consists of two parts. Part 1 discusses classification of waste from decommissioning and makes comparisons with the waste arising from reactor operation. Part 2 discusses the documentation required for decommissioning waste. Also this part of the report draws parallels with the documentation required by the authorities for the radioactive waste arising from operation of the nuclear power plants. To some extent these subjects depend on the future use of the nuclear power plant sites after decommissioning of the plants. The options for future site use are briefly discussed in an appendix to the report. There are many similarities between the waste from reactor operations and the waste arising from dismantling and removal of decommissioned nuclear power plants. Hence it seems natural to apply the same criteria and recommendations to decommissioning waste as those presently applicable to reactor waste. This is certainly true also with respect to documentation, and it is strongly recommended that the documentation requirements on decommissioning waste are made identical, or at least similar, to the documentation requirements for reactor waste in force today. (au)

  4. Management strategies for nuclear power plant outages

    International Nuclear Information System (INIS)

    2006-01-01

    More competitive energy markets have significant implications for nuclear power plant operations, including, among others, the need for more efficient use of resources and effective management of plant activities such as on-line maintenance and outages. Outage management is a key factor for safe, reliable and economic plant performance and involves many aspects: plant policy, coordination of available resources, nuclear safety, regulatory and technical requirements, and all activities and work hazards, before and during the outage. The IAEA has produced this report on nuclear power plant outage management strategies to provide both a summary and an update of a follow-up to a series of technical documents related to practices regarding outage management and cost effective maintenance. The aim of this publication is to identify good practices in outage management: outage planning and preparation, outage execution and post-outage review. As in in the related technical documents, this report aims to communicate these practices in such a way that they can be used by operating organizations and regulatory bodies in Member States. The report was prepared as part of an IAEA project on continuous process improvement. The objective of this project is to increase Member State capabilities in improving plant performance and competitiveness through the utilization of proven engineering and management practices developed and transferred by the IAEA

  5. The French Muséum national d'histoire naturelle vascular plant herbarium collection dataset

    OpenAIRE

    Le Bras, Gwenaël,; Pignal, Marc,; Jeanson, Marc L.; Muller, Serge,; Aupic, Cécile; Carré, Benoît,; Flament, Grégoire; Gaudeul, Myriam,; Gonçalves, Claudia; Invernón, Vanessa R.; Jabbour, Florian,; Lerat, Elodie,; Lowry, Porter P.; Offroy, Bérangère; Pimparé, Eva Pérez

    2017-01-01

    International audience; We provide a quantitative description of the French national herbarium vascular plants collection dataset. Held at the Muséum national d'histoire naturelle, Paris, it currently comprises records for 5,400,000 specimens, representing 90% of the estimated total of specimens. Ninety nine percent of the specimen entries are linked to one or more images and 16% have field-collecting information available. This major botanical collection represents the results of over three ...

  6. Monitoring support system for nuclear power plant

    International Nuclear Information System (INIS)

    Higashikawa, Yuichi; Kubota, Rhuji; Tanaka, Keiji; Takano, Yoshiyuki

    1996-01-01

    The nuclear power plants in Japan reach to 49 plants and supply 41.19 million kW in their installed capacities, which is equal to about 31% of total electric power generation and has occupied an important situation as a stable energy supplying source. As an aim to keeping safe operation and working rate of the power plants, various monitoring support systems using computer technology, optical information technology and robot technology each advanced rapidly in recent year have been developed to apply to the actual plants for a plant state monitoring system of operators in normal operation. Furthermore, introduction of the emergent support system supposed on accidental formation of abnormal state of the power plants is also investigated. In this paper, as a monitoring system in the recent nuclear power plants, design of control panel of recent central control room, introduction to its actual plant and monitoring support system in development were described in viewpoints of improvement of human interface, upgrade of sensor and signal processing techniques, and promotion of information service technique. And, trend of research and development of portable miniature detector and emergent monitoring support system are also introduced in a viewpoint of labor saving and upgrade of the operating field. (G.K.)

  7. Intelligent distributed control for nuclear power plants

    International Nuclear Information System (INIS)

    Klevans, E.H.

    1992-01-01

    This project was initiated in September 1989 as a three year project to develop and demonstrate Intelligent Distributed Control (IDC) for Nuclear Power Plants. The body of this Third Annual Technical Progress report summarizes the period from September 1991 to October 1992. There were two primary goals of this research project. The first goal was to combine diagnostics and control to achieve a highly automated power plant as described by M.A. Schultz. His philosophy, is to improve public perception of the safety of nuclear power plants by incorporating a high degree of automation where a greatly simplified operator control console minimizes the possibility of human error in power plant operations. To achieve this goal, a hierarchically distributed control system with automated responses to plant upset conditions was pursued in this research. The second goal was to apply this research to develop a prototype demonstration on an actual power plant system, the EBR-2 stem plant. Emphasized in this Third Annual Technical Progress Report is the continuing development of the in-plant intelligent control demonstration for the final project milestone and includes: simulation validation and the initial approach to experiment formulation

  8. Periodic safety reviews of nuclear power plants

    International Nuclear Information System (INIS)

    Toth, Csilla

    2009-01-01

    Operational nuclear power plants (NPPs) are generally subject to routine reviews of plant operation and special safety reviews following operational events. In addition, many Member States of the International Atomic Energy Agency (IAEA) have initiated systematic safety reassessment, termed periodic safety review (PSR), to assess the cumulative effects of plant ageing and plant modifications, operating experience, technical developments, site specific, organizational and human aspects. These reviews include assessments of plant design and operation against current safety standards and practices. PSRs are considered an effective way of obtaining an overall view of actual plant safety, to determine reasonable and practical modifications that should be made in order to maintain a high level of safety throughout the plant's operating lifetime. PSRs can be used as a means to identify time limiting features of the plant. The trend is to use PSR as a condition for deciding whether to continue operation of the plant beyond the originally established design lifetime and for assessing the status of the plant for long term operation. To assist Member States in the implementation of PSR, the IAEA develops safety standards, technical documents and provides different services: training courses, workshops, technical meetings and safety review missions for the independent assessment of the PSR at NPPs, including the requirements for PSR, the review process and the PSR final reports. This paper describes the PSR's objectives, scopes, methods and the relationship of PSR with other plant safety related activities and recent experiences of Member States in implementation of PSRs at NPPs. (author)

  9. The challenge of financing nuclear power plants

    International Nuclear Information System (INIS)

    Csik, B.J.

    1999-01-01

    To date, more then 500 nuclear power reactors have been successfully financed and built. Experience in recent nuclear projects confirms that nuclear power will not cease to be a viable option due to a worldwide financing constraint. For financing nuclear plants there are special considerations: large investment; long lead and construction times; complex technology; regulatory risk and political risk. The principal preconditions to financing are a national policy supporting nuclear power; creditworthiness; economic competitiveness; project feasibility; assurance of adequate revenues; acceptability of risks; and no open-ended liabilities. Generally, nuclear power plants are financed conventionally through multi-sources, where a package covers the entire cost. The first source, the investor/owner/operator responsible for building and operating the plant, should cover a sizable portion of the overall investment. In addition, bond issues, domestic bank credits etc. and, in case of State-owned or controlled enterprises, donations and credits from public entities or the governmental budget, should complete the financing. A financially sound utility should be able to meet this challenge. For importing technology, bids are invited. Export credits should form the basis of foreign financing, because these have favorable terms and conditions. Suppliers from several countries may join in a consortium subdividing the scope of supply and involve several Export Credit Agencies (ECAs). There are also innovative financing approaches that could be applied to nuclear projects. Evolutionary Reactors with smaller overall investment, shorter construction times, reliance on proven technology, together with predictable regulatory regimes and reliable long-term national policies favorable to nuclear power, should make it easier to meet the future challenges of financing. (author)

  10. Regional economic impacts of nuclear power plants

    International Nuclear Information System (INIS)

    Isard, W.; Reiner, T.; Van Zele, R.; Stratham, J.

    1976-08-01

    This study of economic and social impacts of nuclear power facilities compares a nuclear energy center (NEC) consisting of three surrogate sites in Ocean County, New Jersey with nuclear facilities dispersed in the Pennsylvania - New Jersey - Maryland area. The NEC studied in this report is assumed to contain 20 reactors of 1200 MW(e) each, for a total NEC capacity of 24,000 MW(e). Following the Introductory chapter, Chapter II discusses briefly the methodological basis for estimating impacts. This part of the analysis only considers impacts of wages and salaries and not purchase of construction materials within the region. Chapters III and IV, respectively, set forth the scenarios of an NEC at each of three sites in Ocean County, N.J. and of a pattern of dispersed nuclear power plants of total equivalent generating capacity. In each case, the economic impacts (employment and income) are calculated, emphasizing the regional effects. In Chapter V these impacts are compared and some more general conclusions are reported. A more detailed analysis of the consequences of the construction of a nuclear power plant is given in Chapter VI. An interindustry (input-output) study, which uses rather finely disaggregated data to estimate the impacts of a prototype plant that might be constructed either as a component of the dispersed scenario or as part of an NEC, is given. Some concluding remarks are given in Chapter VII, and policy questions are emphasized

  11. A PIP chart for nuclear plant safety

    International Nuclear Information System (INIS)

    Suzuki, Tatsujiro; Yamaoka, Taiji

    1992-01-01

    While it is known that social and political aspects of nuclear safety issues are important, little study has been done on identifying the breadth of stakeholders whose policies have important influences over nuclear plant safety in a comprehensive way. The objectives of this study are to develop a chart that visually identifies important stakeholders and their policies and illustrates these influences in a hierarchical representation so that the relationship between stakeholders and nuclear safety will be better understood. This study is based on a series of extensive interviews with major stakeholders, such as nuclear plant managers, corporate planning vice presidents, state regulators, news media, and public interest groups, and focuses on one US nuclear power plant. Based on the interview results, the authors developed a conceptual policy influence paths (PIP) chart. The PIP chart illustrates the hierarchy of influence among stakeholders. The PIP chart is also useful in identifying possible stakeholders who can be easily overlooked without the PIP chart. In addition, it shows that influence flow is circular rather than linear in one direction

  12. Nuclear and non-dispatchable renewables: two compatible supply options? The case of the French power mix

    OpenAIRE

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

    2015-01-01

    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 73% of the total electric production in 2013. With the increase of non-dispatchable renewable resources, nuclear flexibility is examined as part of the solution to balance electricity supply and demand. Our proposed methodology involves designing scenarios of nuclear and non-dispa...

  13. Strengthening of nuclear power plant construction safety management

    International Nuclear Information System (INIS)

    Yu Jun

    2012-01-01

    The article describes the warning of the Fukushima nuclear accident, and analyzes the major nuclear safety issues in nuclear power development in China, problems in nuclear power plants under construction, and how to strengthen supervision and management in nuclear power construction. It also points out that the development of nuclear power must attach great importance to the safety, and nuclear power plant construction should strictly implement the principle of 'safety first and quality first'. (author)

  14. Managing Siting Activities for Nuclear Power Plants

    International Nuclear Information System (INIS)

    2012-01-01

    One of the IAEA's statutory objectives is to ''seek to accelerate and enlarge the contribution of atomic energy to peace, health and prosperity throughout the world''. One way this objective is achieved is through the publication of a range of technical series. Two of these are the IAEA Nuclear Energy Series and the IAEA Safety Standards Series. According to Article III.A.6 of the IAEA Statute, the safety standards establish 'standards of safety for protection of health and minimization of danger to life and property.' The safety standards include the Safety Fundamentals, Safety Requirements and Safety Guides. These standards are written primarily in a regulatory style, and are binding on the IAEA for its own programmes. The principal users are the regulatory bodies in Member States and other national authorities. The IAEA Nuclear Energy Series comprises reports designed to encourage and assist R and D on, and application of, nuclear energy for peaceful uses. This includes practical examples to be used by owners and operators of utilities in Member States, implementing organizations, academia, and government officials, among others. This information is presented in guides, reports on technology status and advances, and best practices for peaceful uses of nuclear energy based on inputs from international experts. The IAEA Nuclear Energy Series complements the IAEA Safety Standards Series. The introduction of nuclear power brings new challenges to States - one of them being the selection of appropriates sites. It is a project that needs to begin early, be well managed, and deploy good communications with all stakeholders; including regulators. This is important, not just for those States introducing nuclear power for the first time, but for any State looking to build a new nuclear power plant. The purpose of the siting activities goes beyond choosing a suitable site and acquiring a licence. A large part of the project is about producing and maintaining a validated

  15. Fuel optimization of Qinshan nuclear power plant

    International Nuclear Information System (INIS)

    Liao Zejun; Li Zhuoqun; Kong Deping; Xue Xincai; Wang Shiwei

    2010-01-01

    Based on the design practice of the fuel replacement of Qin Shan nuclear power plant, this document effectively analyzes the shortcomings of current replacement design of Qin Shan. To address these shortcomings, this document successfully implements the 300 MW fuel optimization program from fuel replacement. fuel improvement and experimentation ,and achieves great economic results. (authors)

  16. Operator support system for nuclear power plants

    International Nuclear Information System (INIS)

    Mori, Nobuyuki; Tai, Ichiro; Sudo, Osamu; Naito, Norio.

    1987-01-01

    The nuclear power generation in Japan maintains the high capacity factor, and its proportion taken in the total generated electric power exceeded 1/4, thus it has become the indispensable energy source. Recently moreover, the nuclear power plants which are harmonious with operators and easy to operate are demanded. For realizing this, the technical development such as the heightening of operation watching performance, the adoption of automation, and the improvement of various man-machine systems for reducing the burden of operators has been advanced by utilizing electronic techniques. In this paper, the trend of the man-machine systems in nuclear power plants, the positioning of operation support system, the support in the aspects of information, action and knowledge, the example of a new central control board, the operation support system using a computer, an operation support expert system and the problems hereafter are described. As the development of the man-machine system in nuclear power plants, the upgrading from a present new central control board system PODIA through A-PODIA, in which the operational function to deal with various phenomena arising in plants and safety control function are added, to 1-PODIA, in which knowledge engineering technology is adopted, is expected. (Kako, I.)

  17. Radiological protection and nuclear power plants

    International Nuclear Information System (INIS)

    Delpla, M.

    Dosimetric results obtained inside and outside nuclear power plants are examined with a review to proposing revision of the radiological protection standards. Dose limits are considered with regard to leukemia and genetic effects. Other topics discussed are: observed collective damage and mean risk; lethal exposure; healing and sign change of additional risk; and genetic effects of radiation on mice

  18. Capital investment costs of nuclear power plants

    International Nuclear Information System (INIS)

    Woite, G.

    1978-01-01

    The purpose of the article is to summarize capital cost experience and estimates in industrialized and developing Member States of the IAEA, and to provide some guidance for cost extrapolation. The relative merits of different types and sizes of nuclear and conventional power plants for an expanding electricity generation system are compared over an adequate planning period

  19. Vibrations in pipelines of nuclear power plants

    International Nuclear Information System (INIS)

    Leal, M.R.L.V.; Bevilacqua, L.

    1984-01-01

    It is presented the main causes of vibrations in nuclear power plants pipelines to allow the identification of critical areas and correct the errors during the specification design. The methods of vibration analysis to give subsidies in the determination of the corrective providences when the problem appears during the commissioning or the generation energy, are also presented. (M.C.K.) [pt

  20. Professional adaptability of nuclear power plant operators

    International Nuclear Information System (INIS)

    He Xuhong; Huang Xiangrui

    2006-01-01

    The paper concerns in the results of analysis for nuclear power plant (NPP) operator job and analysis for human errors related NPP accidents. Based on the principle of ergonomics a full psychological selection system of the professional adaptability of NPP operators including cognitive ability, personality and psychological health was established. The application way and importance of the professional adaptability research are discussed. (authors)

  1. Transient analysis models for nuclear power plants

    International Nuclear Information System (INIS)

    Agapito, J.R.

    1981-01-01

    The modelling used for the simulation of the Angra-1 start-up reactor tests, using the RETRAN computer code is presented. Three tests are simulated: a)nuclear power plant trip from 100% of power; b)great power excursions tests and c)'load swing' tests.(E.G.) [pt

  2. Atucha I nuclear power plant surveillance programme

    International Nuclear Information System (INIS)

    Jinchuk, D.

    1993-01-01

    After a review of the main characteristics of the Atucha I nuclear power plant and its pressure vessel, the embrittlement surveillance capsules and the irradiation conditions are described; Charpy impact tests and tensile tests were performed on the irradiated samples, and results are discussed and compared to theoretical calculations: transition temperature shifts, displacement per atom values. 6 refs., 16 figs., 7 tabs

  3. Dura Seal recommendations for nuclear power plants

    International Nuclear Information System (INIS)

    Anon.

    1980-01-01

    Reactor systems (BWR, PWR and Candu) are briefly reviewed with reference to the pumping services encountered in each system, to indicate the conditions imposed on mechanical seals for nuclear power plant liquid handling equipment. A description of the Dura Seals used in each service is included. (U.K.)

  4. Nuclear power plant piping prefabrication and assembly

    International Nuclear Information System (INIS)

    Schmidt, H.

    1990-01-01

    The piping design for nuclear power plants projects reveals, at the beginning, a modification through the application of new fabrication techniques for prefabrication and assembly. This report presents a fabrication methodology which aims to minimize the fabrication and assembly costs as well as to improve and assure quality. (Author) [es

  5. Programmed system for nuclear power plant protection

    International Nuclear Information System (INIS)

    Jover, Pierre.

    1980-06-01

    The progress in the field of microprocessors and large scale integration circuits, have incited to introduce this new technologies into nuclear power plant protection system. The hardware and software design principles are briefly listed; then, a quad-redundant protection system for 1300 MWe PWR, developed in France is described [fr

  6. Availability estimation of international nuclear power plants

    International Nuclear Information System (INIS)

    Ribeiro, A.A.T.; Muniz, A.A.

    1978-11-01

    Results are presented of investigation on the factors influencing the availability of nuclear power plants of the PWR type; an estimation of expected values for the availability factor and the probability of its having lower values than a certain specified value are given. (Author) [pt

  7. Nuclear plant requirements during power system restoration

    International Nuclear Information System (INIS)

    Adamski, G.; Jenkins, R.; Gill, P.

    1995-01-01

    This paper is one of a series presented on behalf of the System Operation Subcommittee with the intent of focusing industry attention on power system restoration issues. This paper discusses a number of nuclear power plant requirements that require special attention during power system restoration

  8. Evaluation of nuclear power plant operator's ability

    International Nuclear Information System (INIS)

    Wei Li; He Xuhong; Zhao Bingquan

    2004-01-01

    Based on the quantitative research on nuclear power plant (NPP) operator's psychological characteristics and performance, the Borda's method of fuzzy mathematics combined with the character of operator's task is used to evaluate their abilities. The result provides the reference for operator's reliability research and psychological evaluation. (author)

  9. Suicide plane crash against nuclear power plants

    International Nuclear Information System (INIS)

    Richard, A.

    2002-01-01

    Cea (French atomic energy commission) and EDF (Electricity of France) are reassessing their safety standards concerning suicide plane attacks against nuclear facilities. The general idea is to study the non-linear behaviour of reinforced concrete in case of mechanical impact. American studies carried out in 1988 show that a F-14 phantom crashing into a 3,6 meter thick wall at a speed of 774 km/h penetrates only the first 5 cm of the wall. More recent studies performed in Germany and based on computerized simulations show that the reactor containment can sustain impacts from a F15 plane or even from a 747-Boeing but contiguous buildings like the one which houses spent fuels might be more easily damaged because of their metal roofing. (A.C.)

  10. Ageing management in German nuclear power plants

    International Nuclear Information System (INIS)

    Becker, D.E.; Reiner, M.

    1998-01-01

    In Germany, the term 'ageing management' comprises several aspects. A demand for a special ageing monitoring programme is not explicitly contained in the regulations. However, from the Atomic Energy Act and its regulations results the operator's obligation to perform extensive measures to maintain the quality of the plant and the operating personnel working in the plant. From this point of view, comprehensive ageing management in German nuclear power plants has taken place right from the start under the generic term of quality assurance. (author)

  11. Nuclear power plants documentation system

    International Nuclear Information System (INIS)

    Schwartz, E.L.

    1991-01-01

    Since the amount of documents (type and quantity) necessary for the entire design of a NPP is very large, this implies that an overall and detailed identification, filling and retrieval system shall be implemented. This is even more applicable to the FINAL QUALITY DOCUMENTATION of the plant, as stipulated by IAEA Safety Codes and related guides. For such a purpose it was developed a DOCUMENTATION MANUAL, which describes in detail the before mentioned documentation system. Here we present the expected goals and results which we have to reach for Angra 2 and 3 Project. (author)

  12. Constitutional determinants of nuclear power plant upgrading

    International Nuclear Information System (INIS)

    Mann, Thomas

    2013-01-01

    Around half a year ago the European stress test for nuclear power plants, a precautionary measure initiated by the European Council in March 2011 in response to the Fukushima disaster, revealed that while German nuclear power plants show a high degree of robustness compared with those in other European countries, they nevertheless required upgrading in one or the other respect (earthquake warning systems, protection against crashing civil passenger airplanes). The present article investigates whether this upgrading requirement can justify an injunction to carry out structural retrofitting measures or whether obligations to this end can be excluded on grounds of reasonability in view of the recent decision taken by the German parliament to phase out nuclear energy.

  13. Recent Advances in Ocean Nuclear Power Plants

    Directory of Open Access Journals (Sweden)

    Kang-Heon Lee

    2015-10-01

    Full Text Available In this paper, recent advances in Ocean Nuclear Power Plants (ONPPs are reviewed, including their general arrangement, design parameters, and safety features. The development of ONPP concepts have continued due to initiatives taking place in France, Russia, South Korea, and the United States. Russia’s first floating nuclear power stations utilizing the PWR technology (KLT-40S and the spar-type offshore floating nuclear power plant designed by a research group in United States are considered herein. The APR1400 and SMART mounted Gravity Based Structure (GBS-type ONPPs proposed by a research group in South Korea are also considered. In addition, a submerged-type ONPP designed by DCNS of France is taken into account. Last, issues and challenges related to ONPPs are discussed and summarized.

  14. Artificial intelligence in nuclear power plants

    International Nuclear Information System (INIS)

    Haapanen, P.J.

    1990-01-01

    The IAEA Specialists' Meeting on Artificial Intelligence in Nuclear Power Plants was arranged in Helsink/Vantaa, Finland, on October 10-12, 1989, under auspices of the International Working Group of Nuclear Power Plant Control and Instrumentation of the International Atomic Energy Agency (IAEA/IWG NPPCI). Technical Research Centre of Finland together with Imatran Voima Oy and Teollisuuden Voima Oy answered for the practical arrangements of the meeting. 105 participants from 17 countries and 2 international organizations took part in the meeting and 58 papers were submitted for presentation. These papers gave a comprehensive picture of the recent status and further trends in applying the rapidly developing techniques of artificial intelligence and expert systems to improve the quality and safety in designing and using of nuclear power worldwide

  15. Determination of discharge authorizations for French basic nuclear installations 58 and public information

    International Nuclear Information System (INIS)

    Tabard, Laurence; Conte, Dorothee

    2013-01-01

    The determination of discharge authorized limits for a French nuclear site is initiated by the request of the operator, based on the maximum nuclear and chemical inventory that could be released during normal operating conditions, accompanied with justifications. Request and justifications are analyzed and discussed by the ASN and the IRSN, taking into account nuclear and chemical inventories expected inside BNI, current regulations (BNI specific regulation, environment code, public health code), operating feedback (release feedback for an operating BNI, feedback coming from other nuclear sites or installations, etc.) and best available technologies that can be used to treat liquid or gaseous waste before release. After taking into account potential suggestions coming from public information or public enquiry concerning the operator request, the discharge authorized limits are settled down in specific ASN prescriptions that have to be ratified by the State secretaries in charge of nuclear safety. The whole process runs through 2 or 3 years to be achieved. Communication has revealed to be quite an uneasy task, even for administrative procedures. This aspect is mostly tested while communicating about events. Consequences of this communication can hardly be foreseen because of multiple external parameters like: news on the front pages at the same moment; historic communication difficulties still in the public mind; technical vocabulary not easily understood; public fear of things being hidden; power of ecologist or non-governmental associations. (authors)

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

    International Nuclear Information System (INIS)

    2011-06-01

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

  17. Intelligent distributed control for nuclear power plants

    International Nuclear Information System (INIS)

    Klevans, E.H.; Edwards, R.M.; Ray, A.; Lee, K.Y.; Garcia, H.E.: Chavez, C.M.; Turso, J.A.; BenAbdennour, A.

    1991-01-01

    In September of 1989 work began on the DOE University Program grant DE-FG07-89ER12889. The grant provides support for a three year project to develop and demonstrate Intelligent Distributed Control (IDC) for Nuclear Power Plants. The body of this Second Annual Technical Progress report covers the period from September 1990 to September 1991. It summarizes the second year accomplishments while the appendices provide detailed information presented at conference meetings. These are two primary goals of this research. The first is to combine diagnostics and control to achieve a highly automated power plant as described by M.A. Schultz, a project consultant during the first year of the project. This philosophy, as presented in the first annual technical progress report, is to improve public perception of the safety of nuclear power plants by incorporating a high degree automation where greatly simplified operator control console minimizes the possibility of human error in power plant operations. A hierarchically distributed control system with automated responses to plant upset conditions is the focus of our research to achieve this goal. The second goal is to apply this research to develop a prototype demonstration on an actual power plant system, the EBR-II steam plant

  18. Modernization of turbines in nuclear power plants

    International Nuclear Information System (INIS)

    Harig, T.

    2005-01-01

    An ongoing goal in the power generation industry is to maximize the output of currently installed assets. This is most important at nuclear power plants due to the large capital investments that went into these plants and their base loaded service demands. Recent trends in the United States show a majority of nuclear plants are either obtaining, or are in the process of obtaining NRC approvals for operating license extensions and power uprates. This trend is evident in other countries as well. For example, all Swedish nuclear power plants are currently working on projects to extend their service life and maximize capacity through thermal uprate and turbine-generator upgrade with newest technology. The replacement of key components with improved ones is a means of optimizing the service life and availability of power plants. Economic advantages result from increased efficiency, higher output, shorter startup and shutdown times as well as reduced outage times and service costs. The rapid advances over recent years in the development of calculation programs enables adaptation of the latest blading technology to the special requirements imposed by steam turbine upgrading. This results in significant potential for generating additional output with the implementation of new technology, even without increased thermal power. In contrast to maintenance and investment in pure replacement or repair of a component with the primary goal of maintaining operability and reliability, the additional output gained by upgrading enables a return on investment to be reaped. (orig.)

  19. Safety culture in nuclear power plants. Proceedings

    International Nuclear Information System (INIS)

    1994-12-01

    As a consequence of the INSAG-4 report on 'safety culture', published by the IAEA in 1991, the Federal Commission for the Safety of Nuclear Power Plants (KSA) decided to hold a one-day seminar as a first step in this field. The KSA is an advisory body of the Federal Government and the Federal Department of Transport and Energy (EVED). It comments on applications for licenses, observes the operation of nuclear power plants, assists with the preparation of regulations, monitors the progress of research in the field of nuclear safety, and makes proposals for research tasks. The objective of this seminar was to familiarise the participants with the principles of 'safety culture', with the experiences made in Switzerland and abroad with existing concepts, as well as to eliminate existing prejudices. The main points dealt with at this seminar were: - safety culture from the point of view of operators, - safety culture from the point of view of the authorities, - safety culture: collaboration between power plants, the authorities and research organisations, - trends and developments in the field of safety culture. Invitations to attend this seminar were extended to the management boards of companies operating Swiss nuclear power plants, and to representatives of the Swiss authorities responsible for the safety of nuclear power plants. All these organisations were represented by a large number of executive and specialist staff. We would like to express our sincerest thanks to the Head of the Federal Department of Transport and Energy for his kind patronage of this seminar. (author) figs., tabs., refs

  20. The long view for nuclear plant maintenance

    International Nuclear Information System (INIS)

    Moore, T.

    1991-01-01

    This article discusses a strategic, anticipatory approach to maintenance as the key to the long-term viability of today's nuclear power plants. As many as 20 plants around the country now have life-cycle management (LCM) programs in place - integrated, forward-looking preventive maintenance and monitoring programs that preserve the plant's material condition and extend economical operation. Besides reducing the need for 'pounds of cure' decades in the future, LCM programs can produce significant near-term gains in plant performance and are valuable in addressing license renewal concerns. EPRI is supporting the industry's LCM activities with research on age-related degradation mechanisms, development of economic evaluation tools for applying LCM approaches, and assistance with life-cycle evaluations of major plant systems, structures, and components at selected utilities

  1. Regulatory framework for nuclear power plant operation

    International Nuclear Information System (INIS)

    Perez Alcaniz, T.; Esteban Barriendos, M.

    1995-01-01

    As the framework of standards and requirements covering each phase of nuclear power plant project and operation developed, plant owners defined their licensing commitments (codes, rules and design requirements) during the project and construction phase before start-up and incorporated regulatory requirements imposed by the regulatory Body during the licensing process prior to operation. This produces a regulatory framework for operating a plant. It includes the Licensing Basis, which is the starting point for analyzing and incorporating new requirements, and for re-evaluation of existing ones. This presentation focuses on the problems of applying this regulatory framework to new operating activities, in particular to new projects, analyzing new requirements, and reconsidering existing ones. Clearly establishing a plant's licensing basis allows all organizations involved in plant operation to apply the requirements in a more rational way. (Author)

  2. Design of a nuclear steam reforming plant

    International Nuclear Information System (INIS)

    Malherbe, J.

    1980-01-01

    The design of a plant for the steam reforming of methane using a High Temperature Reactor has been studied by CEA in connection with the G.E.G.N. This group of companies (CEA, GAZ DE FRANCE, CHARBONNAGES DE FRANCE, CREUSOT-LOIRE, NOVATOME) is in charge of studying the feasibility of the coal gasification process by using a nuclear reactor. The process is based on the hydrogenation of the coal in liquid phase with hydrogen produced by a methane steam reformer. The reformer plant is fed by a pipe of natural gas or SNG. The produced hydrogen feeds the gasification plant which could not be located on the same site. An intermediate hydrogen storage between the two plants could make the coupling more flexible. The gasification plant does not need a great deal of heat and this heat can be satisfied mostly by internal heat exchanges

  3. IPRDS: component histories and nuclear plant aging

    International Nuclear Information System (INIS)

    Borkowski, R.J.; Kahl, W.K.

    1984-01-01

    A comprehensive assessment of nuclear power plant component operating histories, maintenance histories, and design and fabrication details is essential to understanding aging phenomena. As part of the In-Plant Reliability Data System (IPRDS), an attempt is being made to collect and analyze such information from a sampling of US nuclear power plants. Utilizing the IPRDS, one can reconstruct the failure history of the components and gain new insight into the causes and modes of failures resulting from normal or premature aging. This information assembled from the IPRDS can be combined with operating histories and postservice component inspection results for cradle-to-grave assessments of component aging under operating conditions. A comprehensive aging assessment can then be used to provide guidelines for improving the detection, monitoring, and mitigation of aging-related failures

  4. Development of a nuclear plant analyzer (NPA)

    International Nuclear Information System (INIS)

    De Vlaminck, M.; Mampaey, L.; Vanhoenacker, L.; Bastenaire, F.

    1990-01-01

    A Nuclear Plant Analyzer has been developed by TRACTABEL. Three distinct functional units make up the Nuclear Plant Analyser, a model builder, a run time unit and an analysis unit. The model builder is intended to build simulation models which describe on the one hand the geometric structure and initial conditions of a given plant and on the other hand command control logics and reactor protection systems. The run time unit carries out dialog between the user and the thermal-hydraulic code. The analysis unit is aimed at deep analyzing of the transient results. The model builder is being tested in the framework of the International Standard Problem ISP-26, which is the simulation of a LOCA on the Japanese ROSA facility

  5. LWR nuclear power plant component failures

    International Nuclear Information System (INIS)

    Schmidt, W.H.

    1980-10-01

    An analysis of the most significant light water reactor (LWR) nuclear power plant component failures, from information in the computerized Nuclear Safety Information Center (NSIC) data bank, shows that for both pressurized water reactor (PWR) and boiling water reactor (BWR) plants the component category most responsible for reactor shutdowns is valves. Next in importance for PWR shutdowns is steam generators followed by seals of all kinds. For BWR plants, seals, and pipes and pipe fittings are the second and third most important component failure categories which lead to reactor shutdown. The data are for records extending from early 1972 through September 1978. A list of the most significant component categories and a breakdown of the number of component citations for both PWR and BWR reactor types are presented

  6. Management of delayed nuclear power plant projects

    International Nuclear Information System (INIS)

    1999-09-01

    According to the available information at the IAEA PRIS (Power Reactor Information System) at the end of 1998 there were more than 40 nuclear power plant projects with delays of five or more years with respect to the originally scheduled commercial operation. The degree of conformance with original construction schedules showed large variations due to several issues, including financial, economic and public opinion factors. Taking into account the number of projects with several years delay in their original schedules, it was considered useful to identify the subject areas where exchange of experience among Member States would be mutually beneficial in identification of problems and development of guidance for successful management of the completion of these delayed projects. A joint programme of the IAEA Departments of Nuclear Energy (Nuclear Power Engineering Section) and Technical Co-operation (Europe Section, with additional support from the Latin America and West Asia Sections) was set up during the period 1997-1998. The specific aim of the programme was to provide assistance in the management of delayed nuclear power plants regarding measures to maintain readiness for resuming the project implementation schedule when the conditions permit. The integration of IAEA interdepartmental resources enabled the participation of 53 experts from 14 Member States resulting in a wider exchange of experience and dissemination of guidance. Under the framework of the joint programme, senior managers directly responsible for delayed nuclear power plant projects identified several issues or problem areas that needed to be addressed and guidance on management be provided. A work plan for the development of several working documents, addressing the different issues, was established. Subsequently these documents were merged into a single one to produce the present publication. This publication provides information and practical examples on necessary management actions to preserve

  7. Quality assurance during operation of a nuclear plant

    International Nuclear Information System (INIS)

    Knockaert, Andre; Stolz, Jean

    1977-01-01

    The paper summarizes the actual process followed by Electricite de France since 1974 in the design and implementation of a formal QA system for its new PWR nuclear plants during operation. It covers the approach to the problem, the main characteristics of the QA system, and the set-up of the organization for the first two large PWR plants to be commissioned. Although the EDF QA system during operation is closely related to corresponding systems in other utilities, it takes into account the proper French and EDF organizational and psychological peculiarities. It may be noted also that EDF decided to cover by QA not only the direct operation activities, as is usually done, but also all other plant or headquarters safety related aspects. It finally appears that even in a utility where many of the QA requirements have already been normal practice for years, if not yet strictly formalized, the design and set-up of such a QA system calls for a huge amount of organization and information work. An important condition for success is to show clearly to the involved personnel the benefits of the system and thus obtain their unstinted participation

  8. Radiological protection in nuclear power plants

    International Nuclear Information System (INIS)

    Zorrilla R, S.

    2008-12-01

    This presentation sharing experiences which correspond to the nuclear power plant of Laguna Verde. This nuclear power plant is located at level 2 of four possible, in the classification performance of the World Association of Nuclear Operators (WANO), which means the mexican nuclear power plant is classified in terms of its performance indicators and above the average achieved by their counterparts americans and canadians. In the national context, the nuclear power plant of Laguna Verde has also been honored with several awards such as the National Quality Award, the Clean Industry Certificate, the distinction of Environmental Excellence and others of similar importance. For the standards of WANO, the basic idea is that there are shortcomings in one of nuclear power plant concern to all partners. The indicators used for the classification will always go beyond more compliance with regulations, which are assumed, and rather assume come or a path to excellence. Among the most important indicators are: the collective dose, the percentage of areas declared as contaminated, the number, type and tendency of contamination personal cases, the number of dosimetry alarms, the number of unplanned exposures, loss control of high radiation areas and the release of contaminated material outside the restricted areas. Furthermore, as already indicated, nuclear power plants are of special care situations, such as, carrying out work in areas with radiation fields of more than 15 mSv h -1 , the movement of spent fuel in the reload floor. The consideration of the minimum total effective dose equivalent as a criterion for prescribing tools that reduce exposures, but may increase the external cases of contaminated casualties, the experience in portals such as workers subject to radiology, where exposure in industrial radiography, and so on. Special mention deserve the conditions generated during fuel reload stops, which causes a massive personnel movement, working simultaneously on

  9. Inquiry commission of the consequences of atmospheric nuclear tests performed between 1966 and 1974 in French Polynesia

    International Nuclear Information System (INIS)

    2006-01-01

    After having outlined that the French Polynesia institutions want to make their own assessment of 30 years of nuclear tests, this document presents the inquiry commission set up by the French Polynesia Council, and what this commission has done. It outlines the present consequences of the nuclear tests performed in Polynesia, proposes a summary of the inquiry commission report, and formulates a set of recommendations. Appendices contain a text published by the CRIIRAD after a mission in Polynesia, a reference to an indemnification law in the United States, and a bill proposition

  10. The struggle of the veterans of the French nuclear tests; La lutte des veterans des essais nucleaires francais

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-07-01

    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.)

  11. Nuclear Power Plants | RadTown USA | US EPA

    Science.gov (United States)

    2018-03-12

    Nuclear power plants produce electricity from the heat created by splitting uranium atoms. In the event of a nuclear power plant emergency, follow instructions from emergency responders and public officials.

  12. Special safety requirements applied to Brazilian nuclear power plant

    International Nuclear Information System (INIS)

    Lepecki, W.P.S.; Hamel, H.J.E.; Koenig, N.; Vieira, P.C.R.; Fritzsche, J.C.

    1981-01-01

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

  13. Safety goals for nuclear power plant operation

    International Nuclear Information System (INIS)

    1983-05-01

    This report presents and discusses the Nuclear Regulatory Commission's, Policy Statement on Safety Goals for the Operation of Nuclear Power Plants. The safety goals have been formulated in terms of qualitative goals and quantitative design objectives. The qualitative goals state that the risk to any individual member of the public from nuclear power plant operation should not be a significant contributor to that individual's risk of accidental death or injury and that the societal risks should be comparable to or less than those of viable competing technologies. The quantitative design objectives state that the average risks to individual and the societal risks of nuclear power plant operation should not exceed 0.1% of certain other risks to which members of the US population are exposed. A subsidiary quantitative design objective is established for the frequency of large-scale core melt. The significance of the goals and objectives, their bases and rationale, and the plan to evaluate the goals are provided. In addition, public comments on the 1982 proposed policy statement and responses to a series of questions that accompanied the 1982 statement are summarized

  14. About a hypothetical terrorist attack on a nuclear power plant

    International Nuclear Information System (INIS)

    2001-10-01

    After the terrorism attack on the World Trade Center, a record number ( two thirds) of US citizens favour the use of nuclear energy and consider nuclear plants to be safe. At the same time 59% definitely support building more nuclear plants, less than in March during the Californian crisis, but more than earlier., Most american citizens ( 84%) continue to support licence renewal for nuclear plants and 72 % agree with keeping the option open to build new nuclear plants in the future. The strongest supporters are those who have visited a nuclear plant or information centre. (N.C.)

  15. Taking into account the risk of radioactive material dissemination in French fuel cycle plants

    International Nuclear Information System (INIS)

    Ruiz, J.

    1996-01-01

    This paper presents the design principles for handling the radioactive material dissemination risk in French fuel cycle plants (fuel enrichment and fabrication plants, reprocessing plants, processing and storing facilities). Consideration of the dissemination risk in this type of facilities is made through a deep protection procedure involving the settlement of successive containment systems. These containment systems are dimensioned according to the radioactive material dissemination risk and the external exposure risk. Regulations, standards and guides are first reviewed, followed by a presentation of the various components related to the containment realization in the fuel cycle plants and the way they are realized, the evolutions of methods and designs, the supervision and inspection, and the experience gained

  16. Update on the USNRC's nuclear plant analyzer

    International Nuclear Information System (INIS)

    Laats, E.T.

    1987-01-01

    The Nuclear Plant Analyzer (NPA) is the U.S. Nuclear Regulatory Commission's (NRC's) state-of-the-art nuclear reactor simulation capability. This computer software package integrates high fidelity nuclear reactor simulation codes such as the TRAC and RELAPS series of codes with color graphics display techniques and advanced workstation hardware. An overview of this program was given at the 1984 Summer Computer Simulation Conference (SCSC), with selected topics discussed at the 1985 and 1986 SCSCs. This paper addresses these activities and related experiences. First, The Class VI computer implementation is discussed. The trade-offs between gaining significantly greater computational speed and central memory, with the loss of performance due to many more simultaneous users is shown. Second, the goal of the super-minicomputer implementation is to produce a very cost-effective system that utilizes advanced (multi-dimensional, two-phase coolant) simulation capabilities at real wall-clock simulation times. Benchmarking of the initial super-minicomputer implementation is discussed. Finally, the technical and economic feasibility is addressed for implementing the super-minicomputer version of the NPA with the RELAPS simulation code onto the Black Fox full scope nuclear power plant simulator

  17. Operation of Finnish nuclear power plants

    International Nuclear Information System (INIS)

    Tossavainen, K.

    1992-12-01

    The Finnish nuclear power plant units Loviisa 1 and 2 as well TVO I and II were in operation for almost the whole second quarter of 1992. Longer breaks in production were caused by the annual maintenance of the TVO plant units. The load factor was 87.4 %. At TVO I it was detected during the annual maintenance outage when removing nuclear fuel assemblies from the reactor that one assembly had been loaded into the reactor in an incorrect manner during the previous year's annual maintenance: the assembly was slightly higher than the other assemblies. The water cooling the nuclear fuel partly by-passed the fuel assembly and the coolant flow proper passing through the assembly was below design. The fuel assembly's cooling had been sufficient during the whole operating cycle but could have essentially deteriorated during certain transients with the danger of consequent damage to some fuel rods. On the International Nuclear Event Scale the event is classified as level 1. Other events in this quarter which are classified on the International Nuclear Event Scale were level 0/below scale on the scale

  18. Update on the USNRC's Nuclear Plant Analyzer

    International Nuclear Information System (INIS)

    Laats, E.T.

    1987-01-01

    The Nuclear Plant Analyzer (NPA) is the US Nuclear Regulatory Commission's (NRC's) state-of-the-art nuclear reactor simulation capability. This computer software package integrates high fidelity nuclear reactor simulation codes such as the TRAC and RELAP5 series of codes with color graphics display techniques and advanced workstation hardware. An overview of this program was given at the 1984 Summer Computer Simulation Conference (SCSC), with selected topics discussed at the 1985 and 1986 SCSCs. Since the 1984 presentation, major redirections of this NRC program have been taken. The original NPA system was developed for operation on a Control Data Corporation CYBER 176 computer, technology that is some 10 to 15 years old. The NPA system has recently been implemented on Class VI computers to gain increased computational capabilities, and is now being implemented on super-minicomputers for use by the scientific community and possibly by the commercial nuclear power plant simulator community. This paper addresses these activities and related experiences. First, the Class VI computer implementation is discussed. The trade-offs between gaining significantly greater computational speed and central memory, with the loss of performance due to many more simultaneous users is shown. Second, the goal of the super-minicomputer implementation is to produce a very cost-effective system that utilizes advanced (multi-dimensional, two-phase coolant) simulation capabilities at real wall-clock simulation times. Benchmarking of the initial super-minicomputer implementation is discussed. Finally, the technical and economic feasibility is addressed for implementing the super-minicomputer version of the NPA with the RELAP5 simulation code onto the Black Fox full scope nuclear power plant simulator

  19. Dynamic Simulator for Nuclear Power Plants (DSNP)

    International Nuclear Information System (INIS)

    Saphier, D.

    1976-01-01

    A new simulation language DSNP (Dynamic Simulator for Nuclear Power Plants) is being developed. It is a simple block oriented simulation language with an extensive library of component and auxiliary modules. Each module is a self-contained unit of a part of a physical component to be found in nuclear power plants. Each module will be available in four levels of sophistication, the fourth being a user supplied model. A module can be included in the simulation by a single statement. The precompiler translates DSNP statements into FORTRAN statements, takes care of the module parameters and the intermodular communication blocks, prepares proper data files and I/0 statements and searches the various libraries for the appropriate component modules. The documentation is computerized and all the necessary information for a particular module can be retrieved by a special document generator. The DSNP will be a flexible tool which will allow dynamic simulations to be performed on a large variety of nuclear power plants or specific components of these plants

  20. Quality surveillance at nuclear power plants

    International Nuclear Information System (INIS)

    Deviney, D.E.

    1990-01-01

    Quality surveillance (QS) of nuclear power plants has been occurring for a number of years and is growing in importance as a management tool for assuring that power plants are operated and maintained safely. Quality surveillance can be identified by many terms, such as monitoring, assessment, technical audits, and others. The name given to the function is not important. Quality surveillance at nuclear power plants developed out of a need. Historically, audits were performed to verify compliance to quality program requirements. Verification of day-to-day implementation of activities was not being performed. This left a void in verification activities since inspections were mainly directed at hardware verification. Quality surveillance, therefore, was born out of a need to fill this void in verification. This paper discusses quality surveillance definition; objectives of QS, activities considered for QS, personnel performing QS. As in any human endeavor, people and the attitudes of those people make a program succeed or fail. In the case of QS this is even more critical because of the overview and exposure given to the nuclear industry. Properly trained and experienced personnel performing QS combined with the right attitude contribute to the successful performance of a QS. This is only one side of the success equation, however; acceptance of and actions taken by plant management establish the total success of a QS program