Statement of nuclear incidents at nuclear installations. Third quarter 2001

International Nuclear Information System (INIS)

2002-01-01

A statement of nuclear incidents at nuclear installations in Britain during the third quarter of 2001 is published today by the Health and Safety Executive (copy attached). It covers the period 1 July to 30 September 2001. The statement is published under arrangements that came into effect from the first quarter of 1993, derived from the Health and Safety Commission's powers under section 11 of the Health and Safety at Work, etc. Act 1974. Normally each incident mentioned in HSE's Quarterly Incident Statements will already have been made public by the licensee or site operator either through a press statement or by inclusion in the newsletter for the site concerned. The locations of the installations mentioned in the statement are as follows: Heysham 1 (British Energy Generation plc), Sellafield (British Nuclear Fuels plc), Chapelcross (British Nuclear Fuels plc)

Statement of nuclear incidents at nuclear installations: first quarter 1994

International Nuclear Information System (INIS)

1994-06-01

As a requirement of the 1974 Health and Safety at Work Act, the United Kingdom Health and Safety Inspectorate is required to publish reports of nuclear incidents at nuclear installations. This report covers the period 1st January to 31st March 1994. Two incidents are reported for Dungeness A Power Station, one at the Amersham International building on site at Harwell Laboratory, one at AEA Technology's Windscale Plant and one at British Nuclear Fuels Limited's Sellafield site. (UK)

Nuclear Installations Act 1965

International Nuclear Information System (INIS)

1965-01-01

This Act governs all activities related to nuclear installations in the United Kingdom. It provides for the licensing procedure for nuclear installations, the duties of licensees, the competent authorities and carriers of nuclear material in respect of nuclear occurrences, as well as for the system of third party liability and compensation for nuclear damage. The Act repeals the Nuclear Installations (Licensing and Insurance) Act 1959 and the Nuclear Installations (Amendment Act) 1965 except for its Section 17(2). (NEA) [fr

The Management System for Nuclear Installations. Safety Guide (Spanish Edition)

International Nuclear Information System (INIS)

2017-01-01

This Safety Guide is applicable throughout the lifetime of a nuclear installation, including any subsequent period of institutional control, until there is no significant residual radiation hazard. For a nuclear installation, the lifetime includes site evaluation, design, construction, commissioning, operation and decommissioning. These stages in the lifetime of a nuclear installation may overlap. This Safety Guide may be applied to nuclear installations in the following ways: (a) To support the development, implementation, assessment and improvement of the management system of those organizations responsible for research, site evaluation, design, construction, commissioning, operation and decommissioning of a nuclear installation; (b) As an aid in the assessment by the regulatory body of the adequacy of the management system of a nuclear installation; (c) To assist an organization in specifying to a supplier, via contractual documentation, any specific element that should be included within the supplier's management system for the supply of products. This Safety Guide follows the structure of the Safety Requirements publication on The Management System for Facilities and Activities, whereby: (a) Section 2 provides recommendations on implementing the management system, including recommendations relating to safety culture, grading and documentation. (b) Section 3 provides recommendations on the responsibilities of senior management for the development and implementation of an effective management system. (c) Section 4 provides recommendations on resource management, including guidance on human resources, infrastructure and the working environment. (d) Section 5 provides recommendations on how the processes of the installation can be specified and developed, including recommendations on some generic processes of the management system. (e) Section 6 provides recommendations on the measurement, assessment and improvement of the management system of a nuclear

Nuclear steam supply system and method of installation

International Nuclear Information System (INIS)

Tower, S.N.; Christenson, J.A.; Braun, H.E.

1989-01-01

This patent describes a method of providing a nuclear reactor power plant at a predetermined use site accessible by predetermined navigable waterways. The method is practiced with apparatus including a nuclear reactor system. The system has a nuclear steam-supply section. The method consists of: constructing a nuclear reactor system at a manufacturing site remote from the predetermined use site but accessible to the predetermined waterways for transportation from the manufacturing site to the predetermined use site, the nuclear reactor system including a barge with the nuclear steam supply section constructed integrally with the barge. Simultaneously with the construction of the nuclear reactor system, constructing facilities at the use site to be integrated with the nuclear reactor system to form the nuclear-reactor power plant; transporting the nuclear reactor system along the waterways to the predetermined use site; at the use site joining the removal parts of the altered nuclear reactor system to the remainder of the altered nuclear reactor system to complete the nuclear reactor system; and installing the nuclear reactor system at the predetermined use site and integrating the nuclear reactor system to interact with the facilities constructed at the predetermined use site to form the nuclear-reactor power plant

The dismantling of nuclear installations

International Nuclear Information System (INIS)

Lacoste, A.C.; Duthe, M.; Mignon, H.; Lambert, F.; Pradel, Ph.; Hillewaere, J.P.; Dupre la Tour, St.; Mandil, C.; Weil, L.; Eickelpasch, N.; Finsterwalder, L.

1997-01-01

for nuclear installations, the dismantling is an important part of their exploitation. The technology of dismantling is existing and to get a benefit from the radioactive decay, it seems more easy for operating company such E.D.F. to wait for fifty years before dismantling. But in order to get the knowledge of this operation, the Safety Authority wanted to devote this issue of 'Controle'to the dismantling method. This issue includes: the legal aspects, the risks assessment, the dismantling policy at E.D.F., the site of Brennilis (first French experience of dismantling), the dismantling techniques, the first dismantling of a fuel reprocessing plant, comparison with classical installations, economic aspect, some German experiences, the cleansing of the american site of Handford. (N.C.)

Code on the safety of civilian nuclear fuel cycle installations

International Nuclear Information System (INIS)

1996-01-01

The 'Code' was promulgated by the National Nuclear Safety Administration (NSSA) on June 17, 1993, which is applicable to civilian nuclear fuel fabrication, processing, storage and reprocessing installations, not including the safety requirements for the use of nuclear fuel in reactors. The contents of the 'Code' involve siting, design, construction, commissioning, operation and decommissioning of fuel cycle installation. The NNSA shall be responsible for the interpretation of this 'Code'

Feasible research on VLLW disposal in control area of nuclear installation

International Nuclear Information System (INIS)

Kong Jinsong; Guo Weiqun

2013-01-01

Based on the basic requirements on the VLLW landfill disposal specified by the national codes and standards, a on-site disposal of VLLW in the control area of nuclear installation was proposed. A detail analysis of the advantages and disadvantages about the disposal method and the problem to be solved were described. Results showed that the on-site disposal of VLLW in the control area of nuclear installation was feasible in practice. (authors)

The control of base nuclear installations; Le controle des installations nucleaires de base (INB)

Energy Technology Data Exchange (ETDEWEB)

Anon

2009-04-15

The Authority of Nuclear Safety ( A.S.N). presents in this column the current events of the control of the nuclear base installations during november, december 2008 and january 2009, classified by nuclear site. This information is also available in real-time on the A.S.N. web site, www.asn.fr, in the column 'news'. We can consult all the notices of significant incident published as well as the following letters of inspection, the notices of information about the reactors shutdown, press releases and the A.S.N. information notes. (N.C.)

Childhood cancer and nuclear installations: a review

International Nuclear Information System (INIS)

Muirhead, C.R.

1998-01-01

Many epidemiological studies of childhood cancer around nuclear installations have been conducted in recent years. This article reviews results from Great Britain and elsewhere. Geographical studies have indicated raised risks of childhood leukaemia around some British nuclear installations. However, environmental assessments suggest that the findings are unlikely to be due to radioactive releases from the sites. Case-control studies have allowed more detailed investigation of putative risk factors than is possible from geographical studies. In particular, a recent national study in Britain does not support the hypothesis raised by an earlier study in West Cumbria that paternal radiation exposure prior to conception may increase the risk of leukaemia and non-Hodgkin's lymphoma in offspring. Other studies suggest that childhood leukaemia may have an infective basis, although there is still uncertainty about whether this would explain the findings around nuclear installations. The UK Childhood Cancer Study may provide more information on the causes of these diseases. (author)

Opinion on the radio-ecological monitoring of waters around nuclear installations and on the management of old nuclear waste warehousing sites: 18 recommendations to improve information, transparency and dialogue with involved parties

International Nuclear Information System (INIS)

2008-01-01

After a presentation of the different actors (agencies, institutions, companies) involved in the activities of the various French nuclear installations (base nuclear installations and those concerning the national defence), this report describes the radio-ecological monitoring performed around these nuclear sites: water surveillance on these sites and within their environment, regulatory requirements on effluents and surveillance, information provided by operators and by institutional organisations, assessment of the radio-ecological status of nuclear sites and of potential environmental and health impacts. It describes regulatory obligation in terms of public information, information and communication actions, and gives an assessment of the High committee about public information quality. It discusses ways to improve this quality for a higher transparency, to reinforce the role of local information commissions (CLI), and improve site monitoring. All these aspects are grouped in 18 recommendations

Public information on nuclear safety and incidents at nuclear installations in the UK

International Nuclear Information System (INIS)

Gausen, R.; Gronow, W.S.

1977-01-01

In recent years public interest in the safety aspects of the use of nuclear energy has been increasing in the UK as in other countries. The Government considers public involvement on this subject to be important and has taken action to promote and encourage public debate. As a result of a Government requirement, the Health and Safety Executive (HSE) now publish a quarterly statement which gives particulars of incidents at nuclear installations reported to the HSE under the Nuclear Installations Act 1965, Dangerous Occurrences Regulations and under conditions attached to nuclear site licences granted that Act. The range of incidents covered in the quarterly statement and the present state and background of the public debate on nuclear energy in the UK are described. (author)

Memorandum of Understanding on cooperation and consultation on nuclear installations near borders

International Nuclear Information System (INIS)

1977-01-01

This Agreement signed on 27 September 1977 lays down that the Contracting Parties will inform each other about all nuclear installations constructed along the common border. Nuclear installations within the meaning of the Agreement are installations for the production, processing, reprocessing, manufacture or fission of nuclear fuels and radioactive waste storage. The information to be communicated includes plans and decisions on siting, construction and operation of such installations and relevant documents. The Agreement provides for consultation between the Parties on safety aspects and lays down in detail all the conditions for communication of information. (NEA) [fr

The insurance of nuclear installations

International Nuclear Information System (INIS)

Francis, H.W.

1977-01-01

A brief account is given of the development of nuclear insurance. The subject is dealt with under the following headings: the need for nuclear insurance, nuclear insurance pools, international co-operation, nuclear installations which may be insured, international conventions relating to the liability of operators of nuclear installations, classes of nuclear insurance, nuclear reactor hazards and their assessment, future developments. (U.K.)

Nuclear installations

International Nuclear Information System (INIS)

1998-01-01

This document presents the fulfilling of the Brazilian obligations under the Convention on Nuclear Safety. The Chapter 2 of the document contains some details about the existing Brazilian nuclear installations. Also, safety improvements at Angra 1 and aspects of Angra 2 and 3 are reported

Nuclear installations

International Nuclear Information System (INIS)

2001-01-01

This document presents the fulfilling of the Brazilian obligations under the Convention on Nuclear Safety. The Chapter 2 of the document contains some details about the existing Brazilian nuclear installations. Also, safety improvements at Angra 1 and aspects of Angra 2 and 3 are reported

Risks due to industrial activities and to transports around nuclear installations sites

International Nuclear Information System (INIS)

Doumenc, A.; Faure, J.

1988-01-01

In order to verify that the human activities around a site under consideration are not incompatible with the installation conception, they should be analyzed before the definitive site selection, then watched over and if necessary limited during the installation construction and operation. Taking account of the aggression sources diversity, there is to consider different distances according to the risks. 6 tabs., 5 refs. (F.M.)

Nuclear law and environmental law in the licensing of nuclear installations

International Nuclear Information System (INIS)

Raetzke, Christian

2013-01-01

Large nuclear installations can have a considerable impact on the environment, both in actual terms, due to the construction and operation of the plant and in potential terms, related to the risk of an accident. A considerable part of the multiple authorisation processes required to develop a large nuclear project is devoted to addressing the possible impact on the environment. Accordingly, environmental protection is not only warranted by requirements and processes arising out of what is generally considered 'environmental law', but also by laws governing the design, siting, construction and operation of nuclear installations. By ensuring prevention and control of radiation releases to the environment, the aspects of nuclear law governing the design, construction, operation and decommissioning of nuclear facilities pertain to the field of environmental protection just like other fields of environmental law. The perception of the public that nuclear energy is 'anti-environmental' and the generally antinuclear stance of environmental non-governmental organisations (NGOs) should not deflect attention from the fact that protection of the environment is one of the main functions of the body of nuclear law. In this article, the general relationship between the law governing civil nuclear installations and environmental law will be analysed. The subsequent chapters will deal with environmental requirements and procedures as part of the authorisation process for a nuclear installation. The role of public participation and the involvement of neighbouring states in the licensing process will also be investigated, as they are today mainly based on environmental law. Some other aspects which may also have some relation to environmental protection, such as waste management, emergency planning, multinational early notification and assistance in the case of an accident and nuclear liability, have been omitted from discussion as they lie outside the focus of this article

Ecological and radioecological studies of nuclear installation sites

International Nuclear Information System (INIS)

Caries, J. C.; Hugon, J.; Grauby, A.

1988-01-01

The site study method consists of a dynamic and estimated analysis and of following up the release impact on all natural or non natural media compartments that take a part in the protection of man and his environment. The stages of knowing a nuclear site include the site preliminary radioecological evaluation, diffusion parameters evaluation, the quantification of factors of radioelements transfer to man, the ecological baseline carrying out, the radioactive baseline establishment, the radioecological synthesis of the results, the site radioactive and ecological control. This method applys to selection and detailed study of site. 1 tab., 7 refs. (F.M.)

Statement of nuclear incidents: statement of incidents at nuclear installations: third quarter 1990

International Nuclear Information System (INIS)

1990-01-01

A summary of nuclear incidents occuring at nuclear installations in Britain between 1st July 1990 and 30th September 1990 is presented here, as published by the Health and Safety Executive, two occurring at Harwell Laboratory and one at Winfrith. None of the incidents caused danger to the public, and doses to site workers were not significant. (UK)

Professional operation and management of nuclear island installation

International Nuclear Information System (INIS)

Ma Limin

2011-01-01

As an important part of nuclear power plant construction, nuclear island installation mainly involves main equipment installation, pipeline installation, associated procedure examination and other important tasks. However, due to the nuclear island installation management changing from single project to multi-projects, the problems such as professional management of nuclear island installation and the lack of technical staff become more and more prominent and become one of the key restricts to the work of nuclear island installation. Based on analysis of the single project, single-base nuclear island installation management and practice, combined with the current situation that multi-project and multi-base construction of nuclear power are carrying out at the same time, this paper proposes a new management model of nuclear island installation. (author)

Regulatory Aspects for Site Selection for Radiological and Nuclear Installations

International Nuclear Information System (INIS)

Sirag, N.M.

2016-01-01

The purpose of this research is to check in one of the considerations necessary for any new nuclear facility. A previous study that was conducted using a questionnaire reported that general admission to the public, aesthetic considerations, and characteristics associated with the site are able to adequately accept the existence of new nuclear facilities. The findings of this research revealed that public involvement in the process of site selection and in the design of nuclear power plants, an understanding of their point of view is an important aspect of a participatory approach. An important factor for any new nuclear program is to improve confidence in the energy choices in the future. A survey was conducted on 1304 adults to, to get the main goal. The study concluded showed that the prevalence of culture of safety reflected on the public acceptance of the site, especially if it takes into account the aesthetic and environmental considerations.

Conflict management in the planning of nuclear installations

International Nuclear Information System (INIS)

Pfeifer, M.

1989-01-01

Subsequent to the decision of the Bavarian Higher Administrative Court, which after judicial review declared the development plan for the Wackersdorf site and the reprocessing facility there to be void, the author analyses the situation with regard to the tasks to be accomplished by an installation-specific planning management for coping with arising conflicts - and nuclear hazards in particular -, and for coming to a reconciliation of interests. The author agrees with the decision of the Lueneburg Higher Administrative Court which stated that, in view of the subsequent licensing procedure provided by the law, the development plans need not specify any regulations concerning the specific nuclear hazards or radiological consequences of installations of this type, so that development plans within the meaning of sec. 1, sub-sec. (3) BauGB do not necessarily have to consider nuclear risks or dose limits. (orig./HP) [de

Chapter 4. Assessment and inspection of nuclear installations

International Nuclear Information System (INIS)

2001-01-01

inspections: (1) Routine inspections performed mainly by site inspectors. They look whether the nuclear safety conditions and requirements are met. They also examine technical condition of nuclear equipment, performing surveillance testing of nuclear safety related equipment, observation of fulfilment of approved limits and conditions, selected operating procedures and programmes of quality assurance during construction and commissioning, operation and maintenance as well as in decommissioning nuclear installations. (2) Special inspections are focused on specific profession areas (such as fire safety, qualification and training of NPP personnel, etc.), especially on inspection of meeting specific requirements of nuclear safety. Team inspections are aimed at complex inspection of relevant nuclear equipment safety and they usually are being conducted simultaneously in several professional areas. The inspection of readiness of the nuclear installation for individual phases of commissioning is a typical example of a team inspection. This is the inspection of fulfilment of conditions imposed by UJD to the licensee to operate the nuclear power plant for issuing an approval to start up the unit after refuelling. Team inspections during operation are normally oriented to the areas, which are set based on long-term evaluation of results of nuclear installation's operator. (3) Extraordinary inspections are unplanned, evoked by unexpected operational events on nuclear installations, or the regulator responds by them to the situation in the organisation under supervision. In compliance with the 'Atomic Act' UJD performs inspections also during construction, reconstruction, repair and maintenance of nuclear installations in a form of participation of UJD inspectors at tests of selected equipment after its assembly is completed. The inspection activity of UJD has been performed by nuclear safety inspectors, the most of them having long-term experience in the relevant area. Inspectors

Civilian protection and Britain's commercial nuclear installations

International Nuclear Information System (INIS)

1981-01-01

The subject is treated as follows: initial conclusions (major nuclear attack on military installations; nuclear attack including civil nuclear targets; conventional attack on civil nuclear installations); nature of nuclear weapons explosions and power reactor releases (general; dose effects and biologically significant isotopes; nuclear weapon effects; effect of reactors and other fuel-cycle installations in a thermonuclear area; implications of reactor releases due to conventional attack, sabotage, civil disorder or major accident). (U.K.)

Nuclear installations and their environment

International Nuclear Information System (INIS)

Rieu, Ch.; Berge-Thierry, C.; Duval, C.; Bonnet, Ch.; Gaubert, B.; Riffard, Th.; Greffier, G.; Cervantes, J.C.; Le Breton, F.; Clement, C.; Charbonnier, R.; Andreani, A.M.; Maubert, H.; Maisonneuve, A.

2002-01-01

This dossier deals with protection of nuclear installations against external risks. The articles come from the presentations of the Conference on 'Nuclear installations and their environment', held by the 'Safety and Environment Protection' Section of the French Nuclear Energy Society on October 15, 2002. Floods, earthquakes, winter cold, snow-falls, wind, fires are the main natural risks taken into account. Risks from industrial environment and communication lines are also considered. (authors)

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

International Nuclear Information System (INIS)

Takahashi, Reiko; Nakagome, Yoshihiro

2004-01-01

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

The safety of nuclear installations

International Nuclear Information System (INIS)

1993-01-01

This Safety Fundamental publication sets out basic objectives, concepts and principles for ensuring safety that can be used both by the IAEA in its international assistance operations and by Member States in their national nuclear programmes. These Safety Fundamentals apply primarily to those nuclear installations in which the stored energy developed in certain situations could potentially results in the release of radioactive material from its designated location with the consequent risk of radiation exposure of people. These principles are applicable to a broad range of nuclear installations, but their detailed application will depend on the particular technology and the risks posed by it. In addition to nuclear power plants, such installations may include: research reactors and facilities, fuel enrichment, manufacturing and reprocessing plants; and certain facilities for radioactive waste treatment and storage

Regulatory requirements and administrative practice in safety of nuclear installations

International Nuclear Information System (INIS)

Servant, J.

1977-01-01

This paper reviews the current situation of the France regulatory rules and procedures dealing with the safety of the main nuclear facilities and, more broadly, the nuclear security. First, the author outlines the policy of the French administration which requires that the licensee responsible for an installation has to demonstrate that all possible measures are taken to ensure a sufficient level of safety, from the early stage of the project to the end of the operation of the plant. Thus, the administration performs the assessment on a case-by-case basis, of the safety of each installation before granting a nuclear license. On the other hand, the administration settles overall safety requirements for specific categories of installations or components, which determine the ultimate safety performances, but avoid, as far as possible, to detail the technical specifications to be applied in order to comply with these goals. This approach, which allows the designers and the licensees to rely upon sound codes and standards, gains the advantage of a great flexibility without imparing the nuclear safety. The author outlines the licensing progress for the main categories of installations: nuclear power plants of the PWR type, fast breeders, uranium isotope separation plants, and irradiated fuel processing plants. Emphasis is placed on the most noteworthy points: standardization of projects, specific risks of each site, problems of advanced type reactors, etc... The development of the technical regulations is presented with emphasis on the importance of an internationally concerned action within the nuclear international community. The second part of this paper describes the France operating experience of nuclear installations from the safety point of view. Especially, the author examines the technical and administrative utilization of data from safety significant incidents in reactors and plants, and the results of the control performed by the nuclear installations

Safety of nuclear installations

International Nuclear Information System (INIS)

1991-01-01

In accordance with the Nuclear Energy Act, a Licence may only be issued if the precautions required by the state of the art have been taken to prevent damage resulting from the construction and operation of the installation. The maximum admissible body doses in the area around the installation which must be observed in planning constructional and other technical protective measures to counter accidents in or at a nuclear power station (accident planning values, are established). According to the Radiological Protection Ordinance the Licensing Authority can consider these precautions to have been taken if, in designing the installation against accidents, the applicant has assumed the accidents which, according to the Safety Criteria and Guidelines for Nuclear Power Stations published in the Federal Register by the Federal Minister of the Interior after hearing the competent senior state authorities, must determine the design of a nuclear power station. On the basis of previous experience from safety analysis, assessment and operation of nuclear power stations, the accident guidelines published here define which accidents are determinative for the safety-related design of PWR power stations and what verification -particularly with regard to compliance with the accident planning values of the Radiological Protection Ordinance -must be provided by the applicant. (author)

Decommissioning and dismantling of nuclear installations

International Nuclear Information System (INIS)

Pelzer, N.

1993-01-01

The German law governing decommissioning and dismantling of nuclear installations can be called to be embryonic as compared to other areas of the nuclear regulatory system, and this is why the AIDN/INLA regional meeting organised by the German national committee in July 1992 in Schwerin has been intended to elaborate an assessment of the current legal situation and on this basis establish proposals for enhancement and development, taking into account the experience reported by experts from abroad. The proceedings comprise the paper of the opening session, 'Engineering and safety aspects of the decommissioning of nuclear installations', and the papers and discussions of the technical sessions entitled: - Comparative assessment of the regulatory regimes. - Legislation governing the decommissioning of nuclear installations in Germany. - Analysis of the purpose and law making substance of existing regulatory provisions for the decommissioning of nuclear installations. All seventeen papers of the meeting have been prepared for separate retrieval from the database. (orig./HSCH) [de

Development regulation regarding with licensing of nuclear installation

International Nuclear Information System (INIS)

Bambang Riyono; Yudi Pramono; Dahlia Cakrawati Sinaga

2011-01-01

Provisions of Article 17 paragraph (3) of Law Number 10 Year 1997 on Nuclear cleary mandates for the establishment of government regulations (GR) on Nuclear licensing containing the requirements and procedure, both from the standpoint of their utilization and installation. To use has been rising GR No.29 Year 2008 on the Use of Ionizing Radiation Sources and Nuclear Materials, while for the installation has been published PP No.43 Year 2006 on Nuclear Reactor Licensing, and BAPETEN Chairman Decree No.3 Year 2006 on Non-reactor Nuclear Installation Licensing. Based on the background of the preparation of both the aforementioned are just regulate the reactor and utilization, not yet fully meet the mandate of Article 17 paragraph (3) of Law No.10 of 1997 on Nuclear, including other nuclear installations. For these reasons, it initiated the need for a separate regulation containing provisions concerning licensing of non-reactor nuclear installations. On the other side from the understanding the legal aspects and interpretations of the Law No.10 of 2004 on the Establishment Regulation Legislation, should be in single mandate of Article 17 paragraph (3) of Law No.10 of 1997 on Nuclear would only produce one of the requirements and procedure for the use or installation, or a maximum of two (2) GR related licensing the use and installation. This is encourages conducted the assessing or studies related to how possible it is according to the legal aspect is justified to combine in one Nuclear licensing regulations regarding both the use and installation, by looking at the complexity of installation and wide scope of utilization of nuclear energy in Indonesia. The results of this paper is expected to provide input in the preparation of GR on licensing of nuclear installations. (author)

The Swiss nuclear installations annual report 1992

International Nuclear Information System (INIS)

1993-06-01

This report concerns the safety of the Swiss nuclear installations in the period of 1992. Surveillance of these installations with regard to nuclear safety, including radiation protection, is among the tasks of the Swiss Federal Nuclear Safety Inspectorate (HSK). In Switzerland five nuclear power plants are operational: Beznau I and II, Muehleberg, Goesgen and Leibstadt. Research reactors of thermal capacities below 10 MWth are operational at the Paul Scherrer Institute (PSI), at the Swiss Federal Institute of Technology Lausanne and at the University of Basle. Further subject to HSK's supervision are all activities at PSI involving nuclear fuel or ionizing radiation, the shut down experimental reactor of Lucens, the exploration in Switzerland of final disposal facilities for radwaste and the interim radwaste storage facilities. The present report first deals with the nuclear power plants and covers, in individual sections, the aspects of installation safety, radiation protection as well as personnel and organization, and the resulting overall impression from the point of view of HSK (chapters 1-4). In chapter 5, the corresponding information is given for the research installations. Chapter 6 on radwaste disposal is dedicated to the waste treatment, waste from reprocessing, interim storage and exploration by the NAGRA. In chapter 7, the status of emergency planning in the nuclear power plants' vicinity is reported. Certificates issued for the transport of radioactive materials are dealt with in chapter 8. Finally chapter 9 goes into some general questions relating to the safety of nuclear installations, and in particular covers important events in nuclear installations abroad. In all, the operation of the Swiss nuclear installations in the period of 1992 is rated safe by HSK. (author) 7 figs., 13 tabs

Protocol between the Nuclear Protection and Safety Bureau of Portugal and the Nuclear Energy Commission of Spain on Technical Information concerning Nuclear Installations in Border Areas

International Nuclear Information System (INIS)

1980-01-01

This Protocol was concluded under the Agreement of the same date on the safety of nuclear installations in border areas. Its purpose is to prescribe the type of information referred to in the Agreement. It lays down in detail all the documents to be supplied concerning the siting, construction, operation and decommissioning of nuclear installations, including the geological, seismological, meteorological, hydrological and ecological aspects of the sites concerned, for purposes of environmental protection; the characteristics of the projected installations and emergency plans must also be provided. Similarly to the Agreement, this Protocol will remain in force for a period of ten years. (NEA) [fr

Safety culture in nuclear installations - The role of the regulator

International Nuclear Information System (INIS)

Karigi, Alice W.

2002-01-01

Safety culture is an amalgamation of values, standards, morals and norms of acceptable behavior by the licensees, Radiation workers and the Regulator. The role played by a Regulator in establishing safety culture in a nuclear installation is that related to Authorization, review, assessment, inspection and enforcement. The regulator is to follow the development of a facility or activity from initial selection of the site through design, construction, commissioning, radioactive waste management through to decommissioning and closure. He is to ensure safety measures are followed through out the operation of the facility by laying down in the license conditions of controlling construction of nuclear installations and ensuring competence of the operators. (author)

Taking into account chemical safety for French basic nuclear installations

International Nuclear Information System (INIS)

Tabard, Laurence; Conte, Dorothee

2013-01-01

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

Safety of nuclear installations in the Slovak Republic and activities of the Nuclear Regulatory Authority of the Slovak Republic in 2007

International Nuclear Information System (INIS)

Zemanova, D.

2008-01-01

Prepared pursuant to the provisions of the Atomic Act, the report provides information on the safety of nuclear installation in the Slovak Republic and activities of the Nuclear Regulatory Authority of the Slovak Republic ( UJD SR). UJD SR executes its activities in the area of legislation, issuance of authorizations and permissions for the siting, construction, operation and decommissioning of nuclear installations, in the area of reviews, assessments and control of nuclear safety of nuclear installations and emergency planning, in the area of records and accountability of nuclear materials, independent public information and in the area of international co-operation focused on peaceful uses of nuclear power. Based on the results of inspection activities and evaluation of safety indicators, UJD SR assessed the operation of nuclear installations in the Slovak Republic as safe and reliable. No significant event that could have a negative impact on the personnel, population or environment occurred in 2007. (orig.)

Statement of nuclear incidents at nuclear installations

International Nuclear Information System (INIS)

2002-07-01

A statement of nuclear incidents at nuclear installations in Britain during the first quarter of 2002 is published today by the Health and Safety Executive. It covers the period 1 January to 31 March 2002. There are two installations mentioned in the statement: Dungeness B and Heysham 1. The statement is published under arrangements that came into effect from the first quarter of 1993, derived from the Health and Safety Commission's powers under section 11 of the Health and Safety at Work, etc. Act 1974

Importance of human factors on nuclear installations safety

International Nuclear Information System (INIS)

Caruso, G.J.

1990-01-01

Actually, installations safety and, in particular the nuclear installations infer a strong incidence in human factors related to the design and operation of such installations. In general, the experience aims to that the most important accidents have happened as result of the components' failures combination and human failures in the operation of safety systems. Human factors in the nuclear installations may be divided into two areas: economy and human reliability. Human factors treatments for the safety evaluation of the nuclear installations allow to diagnose the weak points of man-machine interaction. (Author) [es

Emergency plans for civil nuclear installations in the United Kingdom

International Nuclear Information System (INIS)

Gronow, W.S.

1984-01-01

The operators of nuclear installations in the United Kingdom have plans to deal with accidents or emergencies at their nuclear sites. These plans provide for any necessary action, both on and off the nuclear site, to protect members of the public and are regularly exercised. The off-site actions involve the emergency services and other authorities which may be called upon to implement measures to protect the public in any civil emergency. In a recent review of these plans by Government Departments and agencies and the nuclear site operators, a number of possible improvements were identified. These improvements are concerned mainly with the provisions made for liaison with local and national authorities and for public information and have been incorporated into existing plans. An outline is given of the most likely consequences of an accidental release of radioactive material and the scope of emergency plans. Details are also provided on the responsibilities and functions of the operator and other organizations with duties under the plans and the arrangements made for public information. (author)

The use of on-site Project Officers by a nuclear regulatory body

International Nuclear Information System (INIS)

Beare, J.W.

1977-01-01

In Canada consideration of applications for licensing nuclear installations is entrusted to the Reactor Safety Advisory Committee within the Atomic Energy Control Board (AECB). The licensing procedure is conducted in three stages (site approval, construction licence, operating licence). In order to control construction and operation of nuclear installations Project Officers are assigned to each particular installation. The policy of AECB is to send these officers on site several months before the reactor reaches criticality; and during reactor operation. This system clearly provides great practical advantages. (NEA) [fr

Recommendations for the hydrogeologic review and assessment of sites for nuclear power installations within the framework of the radiation protection licensing procedure

International Nuclear Information System (INIS)

Adam, C.; Petschel, M.; Koerner, W.

1985-01-01

Article 4 of the Nuclear Facility Licensing Ordinance requires the information to be submitted in support of licensing applications for nuclear power installations to include an expertise on the hydrogeologic characteristics of the site environment with main emphasis on the movement of radionuclides through groundwater in the event of accident conditions, and on measures to protect ground and surface waters. Recommendations are given for the conduct of a hydrogeologic review and assessment process and its timing relative to the individual stages in the licensing procedure. (author)

Virtual dosimetry applied to the physical security of a nuclear installation

Energy Technology Data Exchange (ETDEWEB)

Santo, Andre Cotelli do E.; Mol, Antonio C.A.; Machado, Daniel M.; Chelles, Daniel R.; Goncalves, Deise G.S., E-mail: cotelli.andre@gmail.com, E-mail: mol@ien.gov.br, E-mail: machado.mol@gmail.com, E-mail: daniel.chelles@gmail.com, E-mail: deise.galvao@gmail.com [Instituto de Engenharia Nuclear (IEN/CNEN-RJ), Rio de Janeiro, RJ (Brazil)

2013-07-01

An important activity to be held in radiation protection is the location of radioactive sources. The present work was devoted to the development of a virtual dosimetry tool for locating and detecting such sources. To this end, was created a three-dimensional virtual model of the Instituto de Engenharia Nuclear - IEN, endowed with virtual characters (avatars), capable of move and interact with the environment, radiation detectors (fixed and mobile) and radioactive sources. Aiming to assist in planning physical security of nuclear installations, the tool developed allows the detection simulation of individuals carrying radioactive sources through detectors installed at strategic points of the site. In addition, it is possible to detect and locate sources by handling portable detectors, operated by characters within the virtual environment. The results obtained show the behavior of the radiation detectors on continuous profile of radioactive sources, allowing calculate the dose rate at any position of the virtual environment. Thus, this work can assist in the training of security officers, as well as in evaluating the radiological safety of the nuclear site. (author)

Virtual dosimetry applied to the physical security of a nuclear installation

International Nuclear Information System (INIS)

Santo, Andre Cotelli do E.; Mol, Antonio C.A.; Machado, Daniel M.; Chelles, Daniel R.; Goncalves, Deise G.S.

2013-01-01

An important activity to be held in radiation protection is the location of radioactive sources. The present work was devoted to the development of a virtual dosimetry tool for locating and detecting such sources. To this end, was created a three-dimensional virtual model of the Instituto de Engenharia Nuclear - IEN, endowed with virtual characters (avatars), capable of move and interact with the environment, radiation detectors (fixed and mobile) and radioactive sources. Aiming to assist in planning physical security of nuclear installations, the tool developed allows the detection simulation of individuals carrying radioactive sources through detectors installed at strategic points of the site. In addition, it is possible to detect and locate sources by handling portable detectors, operated by characters within the virtual environment. The results obtained show the behavior of the radiation detectors on continuous profile of radioactive sources, allowing calculate the dose rate at any position of the virtual environment. Thus, this work can assist in the training of security officers, as well as in evaluating the radiological safety of the nuclear site. (author)

Nuclear Installations Act 1969

International Nuclear Information System (INIS)

1969-01-01

The purpose of this Act is to amend the Nuclear Installations Act 1965 to bring it into full compliance with the international conventions on nuclear third party liability to which the United Kingdom is a Signatory, namely, the Paris Convention, the Brussels Supplementary Convention and the Vienna Convention. (NEA) [fr

Information report on nuclear safety and radiation protection of the Tricastin AREVA site - Issue 2014. Figures and information about nuclear safety and radiation protection of the Tricastin AREVA site - Issue 2014

International Nuclear Information System (INIS)

2015-06-01

Published in compliance with the French code of the environment, this report first presents different aspects of the Areva's Tricastin site which comprises five basic nuclear installations or INBs, and seven ICPE (installation classified for environment protection). The activities are dedicated to uranium conversion, uranium enrichment, uranium chemistry, industrial services, and fuel manufacturing. The report presents this important industrial site, describes the various measures regarding nuclear safety and radiation protection, reports nuclear events which occurred on this site and had to be declared, reports the management of releases by this site and the control of the environment. The next part addresses the management of the various wastes produced by the different installations present on this site. The management of other impacts is also reported. The last chapter reviews the actions undertaken in the field of transparency and information

Information report on nuclear safety and radiation protection of the Tricastin AREVA site - Issue 2013. Figures and information about nuclear safety and radiation protection of the Tricastin AREVA site - Issue 2013

International Nuclear Information System (INIS)

2014-06-01

Published in compliance with the French code of the environment, this report first presents different aspects of the Areva's Tricastin site which comprises five basic nuclear installations or INBs, and seven ICPE (installation classified for the protection of the environment). The activities are dedicated to uranium conversion, uranium enrichment, uranium chemistry, industrial services, and fuel manufacturing. The report presents this important industrial site, describes the various measures regarding nuclear safety and radiation protection, reports nuclear events which occurred on this site and had to be declared, reports the management of releases by this site and the control of the environment. The next part addresses the management of the various wastes produced by the different installations present on this site. The management of other impacts is also reported. The last chapter reviews the actions undertaken in the field of transparency and information

Advanced Measuring (Instrumentation Methods for Nuclear Installations: A Review

Directory of Open Access Journals (Sweden)

Wang Qiu-kuan

2012-01-01

Full Text Available The nuclear technology has been widely used in the world. The research of measurement in nuclear installations involves many aspects, such as nuclear reactors, nuclear fuel cycle, safety and security, nuclear accident, after action, analysis, and environmental applications. In last decades, many advanced measuring devices and techniques have been widely applied in nuclear installations. This paper mainly introduces the development of the measuring (instrumentation methods for nuclear installations and the applications of these instruments and methods.

Nuclear installations inspectorate a public opinion survey

International Nuclear Information System (INIS)

Lennie, S.E.; Davies, A.G.

2001-01-01

HM Nuclear Installations Inspectorate (HMNII) is the regulator responsible for the safety of licensed nuclear sites in the UK. Recognizing the need for public approval on future policy with respect to nuclear waste management, the NII commissioned a public opinion research programme amongst the UK general public. Opinion was sought on a number of issues including attitudes towards the industry in general, perception of nuclear waste and its management, tolerability of risk and attitudes towards current decommissioning plans. In response to the primary objectives of the survey the main findings are: current spontaneous level of concern over the industry in general is low (7%), and lower still for nuclear waste (3%). However, on prompting, 47% of respondents were very concerned about nuclear waste. Top of mind issues of concern about the industry are: nuclear waste; risk of accidents; health risks. Personal risk from nuclear waste is not of overt concern and is significantly less worrisome to respondents than risk from diseases like meningitis or cancer, smoking or road accidents. On being presented with a statement describing current UK decommissioning plans, the sample was generally in favour. However, this issue will require further research. (authors)

Culture safety in the nuclear installation

International Nuclear Information System (INIS)

Benar Bukit

2008-01-01

Culture safety is aimed to empower all the personnel to contribute and responsible to the installation safety where they work in. Culture safety is important as there were so many accidents happened due to the little attention given to the safety, take as examples of what happened in Three Mille Island installation (1979) and Chernobyl (1986). These remind us that human factor gives a significant contribution to the failure of operational system which influences the safety. Therefore, as one of institutions which has nuclear installation. National Nuclear Energy Agency must apply the culture safety to guarantee the safety operation of nuclear installation to protect the personnel, community and environment from the hazard of radioactive radiation. Culture safety has two main components. The first component under the management responsibility is a framework needed in an organisation. The second component is the personnel attitude in al/ levels to respond and optimize those framework. (author)

Managing for safety at nuclear installations

International Nuclear Information System (INIS)

1996-01-01

This publication, by the Health and Safety Executive's (HSE's) Nuclear Safety Division (NSD), provides a statement of the criteria the Nuclear Installations Inspectorate (NII) uses to judge the adequacy of any proposed or existing system for managing a nuclear installation in so far as it affects safety. These criteria have been developed from the basic HSE model, described in the publication Successful health and safety management that applies to industry generally, in order to meet the additional needs for managing nuclear safety. In addition, the publication identifies earlier studies upon which this work was based together with the key management activities and outputs. (Author)

Geological Mapping and Identification of Active Fault in Site Candidate of Nuclear Power Plant Installation at Ketapang Area and Its Surroundings, Madura

International Nuclear Information System (INIS)

Ngadenin; Lilik-Subiantoro; Kurnia-Setiawan-W; Agus-Sutriyono; P Widito

2004-01-01

The result of economical study about demand of electric and water supply in Madura Island in 2015 will increase double for domestic or support industry in Madura Island which have to be solved sooner. One way which is considered to solve the problem is Desalination with nuclear electrical plant. In order to support the installation of nuclear Desalination plant, it is needed site free or far from active fault. Active fault is mainly factor to reject the area on site selection process. Aim of the research is to get geological information and identify of active fault in the site candidate of nuclear Desalination plant at Ketapang area and its surrounding by interpretation of air photos and Landsat imagery, geological and structure geological mapping as well as trenching. The lithology of Ketapang and Sokobana site candidate consists of reef and chalky limestone with form of morphology is undulating hills. Structurally, research areas forms a mono cline with east-westerly trending axis, plunging 10 o to E, the direction of strike is W-E, dip 10 o -30 o to the north. This research concludes that an active fault was not found in the area. (author)

Decree No 74-945 of 6 November 1974 concerning gaseous radioactive effluent releases from large nuclear installations and nuclear installations located on the same site

International Nuclear Information System (INIS)

1974-01-01

This Decree prescribes the licensing for the release of gaseous wastes from nuclear installations as well as the technical supervision of such operations. It does not apply to the transport of radioactive effluents which is governed by the regulations on the transport of dangerous goods. (NEA) [fr

The Dismantling of Nuclear Installations in France

International Nuclear Information System (INIS)

Bonnaure, P.

2011-01-01

As we saw in the previous article by Pierre Bonnaure, though it has long been decried for the dangers inherent in its production structures and the very long-lived waste that it generates, nuclear power may yet recover its credibility, particularly in France. However, on close examination, we see that the nuclear industry is beset by a number of unresolved questions, beginning with the dismantling of installations that have become obsolete or are set to become so. Nuclear power took off after the Second World War, but several generations of technology have been developed since then, and most currently functioning power-stations - mainly second-generation installations - are theoretically nearing the end of their useful lives, at least in terms of what was said when they were being built. The problem therefore arises of their dismantling and the clean-up of the sites on which they were built, a thorny question on which Pierre Bonnaure casts light in this article (prospects, strategies, financing, management of waste etc.). Unfortunately, it emerges that in France nothing has really been resolved, that public debate on the matter is decidedly limited and that investment (both financial investment and research) is not commensurate with the needs of a sector which is, after all, the source of three quarters of national electricity production. (author)

The Swiss nuclear installations. Annual report 1993

International Nuclear Information System (INIS)

1994-08-01

Surveillance of the Swiss nuclear installations with regard to nuclear safety, including radiation protection, is among the tasks of the Swiss Federal Nuclear Safety Inspectorate (HSK). Five nuclear power plants are operational in Switzerland: the three units Beznau I and II and Muehleberg with electrical capacities in the range of 300 to 400 MWe, and the two units Goesgen and Leibstadt with capacities between 900 and 1200 MWe. These are light water reactors; at Beznau and Goesgen of the PWR type, and at Muehleberg and Leibstadt of the BWR type. Research reactors of thermal capacities below 10 MWth are operational at the Paul Scherrer Institute (PSI), at the Swiss Federal Institute of Technology Lausanne and at the University of Basel. Further subject to HSK's supervision are all activities at PSI involving nuclear fuel or ionizing radiation, the shut-down experimental reactor of Lucens, the exploration of final disposal facilities for radwaste and the interim radwaste storage facilities in Switzerland. The report first deals with the nuclear power and covers, in individual sections, the aspects of installation safety, radiation protection as well as personnel and organization, and the resulting overall impression from the point of view of HSK. In chapter 5, the corresponding information is given for research installations. Chapter 6, on radwaste disposal, is dedicated to the treatment of waste, waste from reprocessing, interim storage and exploration by NAGRA. In chapter 7, the status of emergency planning in the nuclear power plants' proximity is reported. Certificates issued for the transport of radioactive materials are dealt with in chapter 8. Finally chapter 9 goes into general questions relating to the safety of nuclear installations. All in all, the safety of operation of the Swiss nuclear installations, in the period of 1993, is judged as good by HSK. (author) 10 figs., 11 tabs

The Swiss nuclear installations. Annual report 1994

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-06-01

Surveillance of the Swiss nuclear installations with regard to nuclear safety, including radiation protection, is among the tasks of the Swiss Federal Nuclear Safety Inspectorate (HSK). Five nuclear power plants are operational in Switzerland: the three units Beznau I and II and Muehleberg with electrical capacities in the range of 300 to 400 MWe, and the two units Goesgen and Leibstadt with capacities between 900 and 1200 MWe. These are light water reactors; at Beznau and Goesgen of the PWR type, and at Muehleberg and Leibstadt of the BWR type. Research reactors of thermal capacities below 10 MWth are operational at the Paul Scherrer Institute (PSI), at the Swiss Federal Institute of Technology Lausanne and at the University of Basel. Further subject to HSK`s supervision are all activities at PSI involving nuclear fuel or ionizing radiation, the shut-down experimental reactor of Lucens, the exploration, in Switzerland, of final disposal facilities for radwaste and the interim radwaste storage facilities. The report first deals with the nuclear power and covers, in individual sections, the aspects of installation safety, radiation protection as well as personnel and organization, and the resulting overall impression from the point of view of HSK. In chapter 5, the corresponding information is given for research installations. Chapter 6, on radwaste disposal, is dedicated to the treatment of waste, waste from reprocessing, interim storage and exploration by NAGRA. In chapter 7, the status of emergency planning in the nuclear power plants` proximity is reported. Certificates issued for the transport of radioactive materials are dealt with in chapter 8. Finally chapter 9 goes into general questions relating to the safety of nuclear installations. All in all, the safety of operation of the Swiss nuclear installations, in the period of 1994, is judged as good by HSK. (author) 11 figs., 13 tabs.

The nuclear installations face to their environment

International Nuclear Information System (INIS)

Rieu, Ch.; Berge-Thierry, C.; Duval, C.; Bonnet, Ch.; Gaubert, B.; Riffard, Th.; Greffier, G.; Cervantes, J.C.; Le Breton, F.; Clement, C.; Charbonnier, R.; Andreani, A.M.; Maubert, H.; Maisonneuve, A.

2002-01-01

This dossier deals with protection of nuclear installations against external risks. The articles come from the presentations of the Conference on 'Nuclear installations and their environment', held by the 'Safety and Environment Protection' Section of the French Nuclear Energy Society on October fifteenth 2002. Floods, earthquakes, winter cold, snow-falls, wind, fires are the main natural risks taken into account. Risks from industrial environment and communication lines are also considered. (author)

Nuclear installations and childhood cancer in the UK

International Nuclear Information System (INIS)

Goldsmith, J.R.

1992-01-01

Data on cancer incidence and mortality near nuclear installations in England and Wales have been published, covering the period 1959-1980. Several age classes and a number of cancer sites have been included. Systematic analysis has so far been limited to cancer mortality. This suggests that childhood leukemia is unusually frequent near some types of installations and the excess is greater for years 0-9 than for later ages. In the earlier decade, 1959-1969, there was questionable consistency of incidence reporting. This report uses the incidence and mortality data only for the period 1971-1980; leukemia and non-leukemia cancer data for those 0-9 years are analyzed, and consistency of incidence reporting is evaluated by comparing incidence and mortality. For comparison with reported data for grouped local authority areas (LAAs) near to 21 different installations, 2 sources of expected incidence are used. The first is based on regional data, and the second is based on a group of LAAs similar in location, urban/rural character and population size. The results of this study confirm Cook-Mozaffari et al.'s findings by mortality analysis for the group of installations involved in non-power producing nuclear technology. This study sheds no light on the possible basis for the association, which remains to be clarified. Initial steps have been taken by Gardner et al. using case-referent methods. (author). 15 refs., 3 figs., 7 tabs

The population distribution near the sites of nuclear facilities in the FRG

International Nuclear Information System (INIS)

Gutschmidt, W.D.

1975-11-01

This report is a compilation of relevant data concerning population distribution near the site of nuclear installations in the Federal Republic of Germany. The 'Site Evaluation Data', a guideline approved by the Laender Committee on Nuclear Energy, is dealt with, and a classification of German nuclear sites with respect to the population distribution is presented. In addition, German and US nuclear sites are compared with the aid of the Site Population Factor, and in respect to population density values as given in WASH-1400. (orig.) [de

Information report on nuclear safety and radiation protection of the Tricastin AREVA site - Issue 2012

International Nuclear Information System (INIS)

2013-06-01

Published in compliance with the French code of the environment, this report first presents different aspects of the Areva's Tricastin site which comprises five basic nuclear installations or INBs, and seven ICPE (installation classified for the protection of the environment). The activities are dedicated to uranium conversion, uranium enrichment, uranium chemistry, industrial services, and fuel manufacturing. The report presents this important industrial site, describes the various measures regarding nuclear safety and radiation protection, reports nuclear events which occurred on this site and had to be declared, reports the management of releases by this site and the control of the environment. The next part addresses the management of the various wastes produced by the different installations present on this site. The management of other impacts is also reported. The last chapter reviews the actions undertaken in the field of transparency and information

Interpretation of the concepts of ALARA and bat for radioactive effluent releases from nuclear installation

International Nuclear Information System (INIS)

Chen Xiaoqiu

2009-01-01

Based on the understanding of the important concepts of both ALARA and BAT associated with the characteristics of effluent releases from the existing nuclear installations and the abatement techniques for effluents, this paper elaborates the principle of controlling radioactive effluent concentration from nuclear installation, that is based on the BAT focusing on the abatement techniques for effluents, introduces the good practice in the projects, and optimize the effluent releases with account taken of external factors such as the site condition. (authors)

Arrangements for dealing with emergencies at civil nuclear installations

International Nuclear Information System (INIS)

Turner, M.J.; Robinson, I.F.

1989-01-01

This paper covers arrangements for dealing with nuclear emergencies at sites licensed by the Health and Safety Executive/Nuclear Installations Inspectorate. Such arrangements are over and above the contingency plans required for radiation incidents as required by the Ionising Radiations Regulations. The statutory position of the NII is described and, although the NII is limited to regulating the activities of the operator, the functions of the other organisations that could be involved in dealing with an emergency are briefly covered in order to give as complete a picture as possible. The basis for emergency planning is given together with the consequences and countermeasures for mitigation of a nuclear emergency, including the use of ERLs. The requirements for emergency exercises are explained. (author)

Nuclear electronic equipment for control and monitoring panel. Procedure guide for on-site tests of nuclear reactor instruments

International Nuclear Information System (INIS)

1975-10-01

By the use of a procedure for on-site testing of nuclear reactor instruments it should be possible to judge their ability to guarantee the reactor safety and availability at the moment of divergence or during operation. Such a procedure must therefore be created as a work implement for the quick and reliable installation of electronic devices necessary for nuclear reactor control and supervision. A standard document is proposed for this purpose, allowing a ''test programme'' to be set up before the equipment is installed on the site [fr

Sites for locations of nuclear reactors

International Nuclear Information System (INIS)

Balcazar, M.; Huerta, M.; Lopez, A.

2014-10-01

A restriction on sites of nuclear energy is the history of seismic activity, in its magnitude (Richter) and intensity (Mercalli). This article delimits the areas of greatest magnitude and national seismic intensity, with restrictions of ground acceleration; the supplement areas with a low magnitude of seismic activity are shown. Potential sites for the location of these sites are introduced into a geographic information system. The set of geo-referenced data contains the location of the active volcanic manifestations; the historical record of earthquake epicenters, magnitudes and intensities; major geological faults; surface hydrology and water bodies; location of population density; protected areas; contour lines; the rock type or geology. The geographic information system allows entering normative criteria and environmental restrictions that correlate with geo-referenced data described above, forms both probable and exclusion areas for the installation of nuclear sites. (Author)

Seismic evaluation of nuclear installations

International Nuclear Information System (INIS)

Mattar Neto, Miguel

1997-01-01

Some considerations regarding extreme external events, natural or man-induce, such as earthquakes, floods, air crashes, etc, shall be done for nuclear facilities to minimizing the potential impact of the installation on the public and the environment. In this paper the main aspects of the seismic evaluation of nuclear facilities (except the nuclear power reactors) will be presented based on different codes and standards. (author). 7 refs., 2 tabs

Construction for Nuclear Installations. Specific Safety Guide

International Nuclear Information System (INIS)

2015-01-01

This Safety Guide provides recommendations and guidance based on international good practices in the construction of nuclear installations, which will enable construction to proceed with high quality. It can be applied to support the development, implementation and assessment of construction methods and procedures and the identification of good practices for ensuring the quality of the construction to meet the design intent and ensure safety. It will be a useful tool for regulatory bodies, licensees and new entrant countries for nuclear power plants and other nuclear installations

Geological and geotechnical investigations for nuclear power plants sites

International Nuclear Information System (INIS)

Alves, P.R.R.

1984-09-01

This dissertation presents a general methodology for the tasks of geological and geotechnical investigations, to be performed in the proposed sites for construction of nuclear Power Plants. In this work, items dealing with the standards applied to licensing of Nuclear Power Plants, with the selection process of sites and identification of geological and geotechnical parameters needed for the regional and local characterization of the area being studied, were incorporated. This dissertation also provides an aid to the writing of Technical Reports, which are part of the documentation an owner of a Nuclear Power Plant needs to submit to the Comissao Nacional de Energia Nuclear, to fulfill the nuclear installation licensing requirements. Moreover, this work can contribute to the planning of field and laboratory studies, needed to determine the parameters of the area under investigation, for the siting of Nuclear Power Plants. (Author) [pt

Decommissioning of nuclear installations - regulations - financing - responsibility - insurance

International Nuclear Information System (INIS)

Hubert, E.H.; Andersson, C.; Deprimoz, J.; Mayoux, J.C.; Richard, M.; Sartorelli, C.; Nocera, F.

1983-01-01

This paper highlights three aspects of decommissioning of nuclear installations which relate, more or less directly, to legal options already applied or advocated. It reviews the regulatory conditions for decommissioning a nuclear installation and indicates legal provisions for financing decommissioning expenditures. It also describes the legal provisions to determine liabilities in case of nuclear damage and the assistance which insurers may provide to cover the consequences of such liabilities. (NEA) [fr

Statement of nuclear incidents at nuclear installations

International Nuclear Information System (INIS)

2001-07-01

A statement of nuclear incidents at nuclear installations in Britain during the first quarter of 2001 is published today by the Health and Safety Executive. It covers the period 1 January to 31 March 2001. The statement is published under arrangements that came into effect from the first quarter of 1993, derived from the Health and Safety Commission's powers under section 11 of the Health and Safety at Work, etc. Act 1974

Regulatory Safety Requirements for Operating Nuclear Installations

International Nuclear Information System (INIS)

Gubela, W.

2017-01-01

The National Nuclear Regulator (NNR) is established in terms of the National Nuclear Regulator Act (Act No 47 of 1999) and its mandate and authority are conferred through sections 5 and 7 of this Act, setting out the NNR's objectives and functions, which include exercising regulatory control over siting, design, construction etc of nuclear installations through the granting of nuclear authorisations. The NNR's responsibilities embrace all those actions aimed at providing the public with confidence and assurance that the risks arising from the production of nuclear energy remain within acceptable safety limits -> Therefore: Set fundamental safety standards, conducting pro-active safety assessments, determining licence conditions and obtaining assurance of compliance. The promotional aspects of nuclear activities in South Africa are legislated by the Nuclear Energy Act (Act No 46 of 1999). The NNR approach to regulations of nuclear safety and security take into consideration, amongst others, the potential hazards associated with the facility or activity, safety related programmes, the importance of the authorisation holder's safety related processes as well as the need to exercise regulatory control over the technical aspects such as of the design and operation of a nuclear facility in ensuring nuclear safety and security. South Africa does not have national nuclear industry codes and standards. The NNR is therefore non-prescriptive as it comes to the use of industry codes and standards. Regulatory framework (current) provide for the protection of persons, property, and environment against nuclear damage, through Licensing Process: Safety standards; Safety assessment; Authorisation and conditions of authorisation; Public participation process; Compliance assurance; Enforcement

Days of dismantling activities of installations and rehabilitation of contaminated sites in France; Demantelement des installations et rehabilitation de sites contamines

Energy Technology Data Exchange (ETDEWEB)

NONE

2008-07-01

The objective of these days, organized by the section environment of the French society of radiation protection, is to present a panorama of the activities of nuclear installations dismantling and contaminated sites rehabilitation in France, by leaning in the same time on practical cases and by stating the French rule and the national and international recommendations on the subject. These days have also for object to approach the stakes associated with the sectors of waste management and the materials generated by these activities and in a more general way, the stakes to come for the different actors of the dismantling and the rehabilitation. (N.C.)

Meteorological characteristics of nuclear installations sites

International Nuclear Information System (INIS)

Doumenc, A.

1988-01-01

The atmosphere is the most propitious medium to a rapid transport and diffusion of a pollutant. So, it is important to know its local characteristics which is decisive for every evaluation of radioactive release consequences using transfer models. It is also the siege of intense sudden hazardous phenomena, as tornados and typhoons, that should be taken into account in the installation conception. 1 tab., 6 refs. (F.M.)

The dismantling of CEA nuclear installations

International Nuclear Information System (INIS)

Piketty, Laurence

2016-03-01

After having indicated locations of French nuclear installations which are currently being dismantled (about 30 installations), and recalled the different categories of radioactive wastes with respect to their activity level and the associated storage options, this article gives an overview of various aspects of dismantling, more precisely in the case of installations owned and managed by the CEA. These operations comprise the dismantling itself, the recovery and packaging of wastes, old effluents and spent fuels. The organisation and responsible departments within the CEA are presented, and the author outlines some operational problematic issues met due to the age of installations (traceability of activities, regulation evolutions). The issue of financing is then discussed, and its uncertainties are outlined. The dismantling strategy within the CEA-DEN is described, with reference to legal and regulatory frameworks. The next parts of the article address the organisation and the economic impact of these decontamination and dismantling activities within the CEA-DEN, highlight how R and D and advanced technology are a support to this activities as R and D actions address all scientific and technical fields of nuclear decontamination and dismantling. An overview of three important dismantling works is proposed: Fontenay-aux-Roses, the Marcoule CEA centre (a reference centre in the field of nuclear dismantling and decontamination) and the Grenoble CEA centre (reconversion in R and D activities in the fields of technologies of information, of communication, technologies, for health, and in renewable energies). The last part addresses the participation to the Strategic Committee of the Nuclear Sector (CSFN)

From nuclear installation to greenfield site. SCK-CEN develops a new measurement method

International Nuclear Information System (INIS)

2014-01-01

The article discusses a new measurement method that has been developed by the Belgian Nuclear Research Center SCK-CEN in conjunction with the decommissioning of nuclear facilities. This measurement technique is based on on-site gamma ray spectrometry in combination with modelling and is employed for directing the flow of demolition materials in the decommissioning of nuclear facilities.

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

International Nuclear Information System (INIS)

Orr, Peter; Mitchell, Nick; Mobbs, Shelly; Bennest, Terry; Abu-Eid, Rateb-Boby; Berton, Marie-Anne; Dehaye, Catherine Ollivier; Pellenz, Gilles; Cruikshank, Julian; Diaz Arocas, Paloma; Garcia Tapias, Ester; Hess, Norbert; Hong, Sam-Bung; Miller, Susan; Monken-Fernandes, Horst; ); Morse, John; Nitzsche, Olaf; Ooms, Bart; Osimani, Celso; Stuart Walker

2014-01-01

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

Risk of childhood leukaemia in the vicinity of nuclear installations: Findings and recent controversies

International Nuclear Information System (INIS)

Dominique Laurier; Bernd Grosche; Hall, Per

2002-01-01

The identification of a local excess of cancer cases, possibly associated with ionizing radiation, always receives substantial media coverage and communication about clusters is difficult. We reviewed studies that examined the risk of leukaemia among young people near nuclear installations. An excess of leukaemia exists near some nuclear installations, at least for the reprocessing plants at Sellafield and Dounreay and the nuclear power plant Kruemmel. Nonetheless, the results of multi-site studies invalidate the hypothesis of an increased risk of leukaemia related to nuclear discharge. Up until now, analytic studies have not found an explanation for the leukaemia clusters observed near certain nuclear installations. The hypothesis of an infectious aetiology associated with population mixing has been proposed, but needs to be investigated further. The review illustrates two recent examples in France (La Hague reprocessing plant) and in Germany (Kruemmel power plant), where controversies developed after reports of increased leukaemia risks. These examples show the importance of recalling the current epidemiological knowledge and of using systematic recording of cases to replace the alleged excesses in a more general framework. Some elements should also be suggested from the recent French and German experiences to reinforce credibility in the results

Questions for the nuclear installations inspectorate

International Nuclear Information System (INIS)

Conroy, C.; Flood, M.; MacRory, R.; Patterson, W.C.

1976-01-01

The responsibilities of the Nuclear Installations Inspectorate are considered, and the responsibilities of other bodies for (a) reprocessing and enrichment, and (b) security. Questions for the Nuclear Installations Inspectorate are then set out under the following heads: general (on such topics as vandalism, sabotage, threats, security, reactor incidents); magnox reactors; corrosion; advanced gas-cooled reactor; steam generating heavy water reactor; fast breeder reactor; reproces-sing and waste. Most of the questions are concerned with technical problems that have been reported or might possibly arise during construction or operation, affecting the safety of the reactor or process. (U.K.)

State fund of decommissioning of nuclear installations and handling of spent nuclear fuels and nuclear wastes (Slovak Republic)

International Nuclear Information System (INIS)

Kozma, Milos

2006-01-01

State Fund for Decommissioning of Nuclear Installations and Handling of Spent Nuclear Fuels and Nuclear Wastes was established by the Act 254/1994 of the National Council of the Slovak Republic as a special-purpose fund which concentrates financial resources intended for decommissioning of nuclear installations and for handling of spent nuclear fuels and radioactive wastes. The Act was amended in 2000, 2001 and 2002. The Fund is legal entity and independent from operator of nuclear installations Slovak Power Facilities Inc. The Fund is headed by Director, who is appointed and recalled by Minister of Economy of the Slovak Republic. Sources of the Fund are generated from: a) contributions by nuclear installation operators; b) penalties imposed by Nuclear Regulatory Authority of the Slovak Republic upon natural persons and legal entities pursuant to separate regulation; c) bank credits; d) interest on Fund deposits in banks; e) grants from State Budget; f) other sources as provided by special regulation. Fund resources may be used for the following purposes: a) decommissioning of nuclear installations; b) handling of spent nuclear fuels and radioactive wastes after the termination of nuclear installation operation; c) handling of radioactive wastes whose originator is not known, including occasionally seized radioactive wastes and radioactive materials stemming from criminal activities whose originator is not known, as confirmed by Police Corps investigator or Ministry of Health of the Slovak Republic; d) purchase of land for the establishment of nuclear fuel and nuclear waste repositories; e) research and development in the areas of decommissioning of nuclear installations and handling of nuclear fuels and radioactive wastes after the termination of the operation of nuclear installations; f) selection of localities, geological survey, preparation, design, construction, commissioning, operation and closure of repositories of spent nuclear fuels and radioactive wastes

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

International Nuclear Information System (INIS)

Lareyne, O.; Marugan Tovar, I.; Martinez Moreno, M.; Sanz Alduan, M. T.

2011-01-01

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

Regulatory oversight report 2016 concerning nuclear safety in Swiss nuclear installations

International Nuclear Information System (INIS)

2017-06-01

packages as well as one cask with the fuel assemblies from the shut down research reactor DIORIT of PSI and six casks with waste from the decommissioning of the experimental nuclear power plant at Lucens. During 2016 only one campaign to incinerate and melt radioactive waste was carried out. ENSI recorded no reportable events at Zwilag during the reporting year. The nuclear facilities at PSI consist of the hot laboratory, the three former research reactors SAPHIR, DIORIT and PROTEUS now in varying phases of decommissioning, the former experimental incineration plant and the facilities for the disposal of radioactive materials including the Federal Government's interim storage facility. During 2016, no events were reported at the PSI, at EPFL or at UniB. In 2016, the amount of radioactive material released into the environment via waste water and exhaust air from the nuclear power plants, Zwilag and the nuclear facilities at PSI, Basel and Lausanne was significantly less than the limits specified in the operating licenses. Analyses showed that the maximum dose for persons in the immediate vicinity of a plant was less than 1% of the annual exposure to natural radiation. The waste produced during reprocessing at the reprocessing facilities of La Hague (France) and Sellafield (United Kingdom) must be returned to Switzerland. In the reporting year, compacted, metallic, intermediate level waste and intermediate level vitrified residue packets were transported to Zwilag. All nuclear waste from Swiss fuel assemblies sent abroad for reprocessing is now stored at Zwilag. During 2016, all transports of radioactive substances to and from Swiss nuclear installations took place without any incidents. The site selection procedure for the storage of radioactive waste has been running since 2008. ENSI bears overall responsibility for the safety assessment of the geological site areas. The National Cooperative for the Disposal of Radioactive Waste (Nagra) submitted its suggestion for

The decommissioning of nuclear facilities; Le demantelement des installations nucleaires de base

Energy Technology Data Exchange (ETDEWEB)

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

2008-11-15

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

Nuclear installations abroad the accident risks and their potential consequences

Energy Technology Data Exchange (ETDEWEB)

Turvey, F J [Radiological Protection Inst. of Ireland (Ireland)

1996-10-01

This paper endeavors to assess the threat to Ireland from severe accidents at civil nuclear installations. Among the various types of nuclear installations worldwide, reactors and reprocessing plants are considered to be the most threatening and so the paper focuses on these. The threat is assumed to be a function of the risk of severe accidents at the above types of installations and the probability of unfavourable weather conditions carrying the radioactive releases to Ireland. Although nuclear installations designed in eastern Europe and Asia are less safe than others, the greatest threat to Ireland arises from nearby installations in the UK. The difficulty of measuring the probabilities and consequences of severe nuclear accidents at nuclear installations in general is explained. In the case of the UK installations, this difficulty is overcome to some degree by using values of `tolerable` risk adopted by the national nuclear regulator to define the radiotoxic releases from nuclear accidents. These are used as input to atmospheric dispersion models in which unfavourable weather conditions for Ireland are assumed and radiation doses are calculated to members of the Irish public. No countermeasures, such as sheltering, are assumed. In the worst cast scenario no deaths would be expected in Ireland in the immediate aftermath of the accident however, an increase in cancers over a period of 25 years or so would be expected assuming present-day models for the effect of low level radiation are valid.

Nuclear installations abroad the accident risks and their potential consequences

International Nuclear Information System (INIS)

Turvey, F.J.

1996-01-01

This paper endeavors to assess the threat to Ireland from severe accidents at civil nuclear installations. Among the various types of nuclear installations worldwide, reactors and reprocessing plants are considered to be the most threatening and so the paper focuses on these. The threat is assumed to be a function of the risk of severe accidents at the above types of installations and the probability of unfavourable weather conditions carrying the radioactive releases to Ireland. Although nuclear installations designed in eastern Europe and Asia are less safe than others, the greatest threat to Ireland arises from nearby installations in the UK. The difficulty of measuring the probabilities and consequences of severe nuclear accidents at nuclear installations in general is explained. In the case of the UK installations, this difficulty is overcome to some degree by using values of 'tolerable' risk adopted by the national nuclear regulator to define the radiotoxic releases from nuclear accidents. These are used as input to atmospheric dispersion models in which unfavourable weather conditions for Ireland are assumed and radiation doses are calculated to members of the Irish public. No countermeasures, such as sheltering, are assumed. In the worst cast scenario no deaths would be expected in Ireland in the immediate aftermath of the accident however, an increase in cancers over a period of 25 years or so would be expected assuming present-day models for the effect of low level radiation are valid

Information report on nuclear safety and radiation protection of the Romans site - Issue 2014

International Nuclear Information System (INIS)

2015-06-01

In compliance with the French Code of the Environment, this annual document describes the arrangements regarding nuclear safety and radiation protection, reports incidents and accidents of nuclear safety and radiation protection which must be declared according to this Code and which occurred within the installation, as well as the actions undertaken to limit their development and the consequences for people health for the environment, describes the nature and results of measurements of radioactive and not radioactive releases by the installation in the environment, describes the nature and quantities of radioactive wastes which are warehoused on the installation site as well as measures to limit their volume and their impact on health and on the environment, notably in soils and waters. After a presentation of the AREVA plant located in Romans-sur-Isere which comprises two basic nuclear installations (INB) and where fuel assemblies are manufactured, the different parts of this report address the measures regarding nuclear safety and radiation protection, nuclear events according to the INES scale, the management of releases by the different installations of this site and the control of the environment, the management of radioactive wastes, and the actions undertaken regarding information and transparency. Recommendations of the CHSCT are also reported

Information report on nuclear safety and radiation protection of the Romans site - Issue 2012

International Nuclear Information System (INIS)

2013-06-01

In compliance with the French Code of the Environment, this annual document describes the arrangements regarding nuclear safety and radiation protection, reports incidents and accidents of nuclear safety and radiation protection which must be declared according to this Code and which occurred within the installation, as well as the actions undertaken to limit their development and the consequences for people health for the environment, describes the nature and results of measurements of radioactive and not radioactive releases by the installation in the environment, describes the nature and quantities of radioactive wastes which are warehoused on the installation site as well as measures to limit their volume and their impact on health and on the environment, notably in soils and waters. After a presentation of the AREVA plant located in Romans-sur-Isere which comprises two basic nuclear installations (INB) and where fuel assemblies are manufactured, the different parts of this report address the measures regarding nuclear safety and radiation protection, nuclear events according to the INES scale, the management of releases by the different installations of this site and the control of the environment, the management of radioactive wastes, and the actions undertaken regarding information and transparency. Recommendations of the CHSCT are also reported

Information report on nuclear safety and radiation protection of the Romans site - Issue 2013

International Nuclear Information System (INIS)

2014-06-01

In compliance with the French Code of the Environment, this annual document describes the arrangements regarding nuclear safety and radiation protection, reports incidents and accidents of nuclear safety and radiation protection which must be declared according to this Code and which occurred within the installation, as well as the actions undertaken to limit their development and the consequences for people health for the environment, describes the nature and results of measurements of radioactive and not radioactive releases by the installation in the environment, describes the nature and quantities of radioactive wastes which are warehoused on the installation site as well as measures to limit their volume and their impact on health and on the environment, notably in soils and waters. After a presentation of the AREVA plant located in Romans-sur-Isere which comprises two basic nuclear installations (INB) and where fuel assemblies are manufactured, the different parts of this report address the measures regarding nuclear safety and radiation protection, nuclear events according to the INES scale, the management of releases by the different installations of this site and the control of the environment, the management of radioactive wastes, and the actions undertaken regarding information and transparency. Recommendations of the CHSCT are also reported

The importante of physical and mathematical models for nuclear power plants site selection

International Nuclear Information System (INIS)

Rios, J.L.P.

1989-01-01

The importance of the release of effluents from nuclear installations for the site selection of nuclear power plants is discussed. The main available analysis methods, physical and mathematical, is presented [pt

Radiation exposure as a result of radioactivity in the vicinity of nuclear installations

International Nuclear Information System (INIS)

Van As, Deodandus.

1975-11-01

The nuclear industry in South Africa is expected to expand dramatically and, as a result, the effects of radioactive effluent from these installations on the environment will be of great practical and scientific importance. The long-term effects of low-level radiation cannot be clinically predicted; physical determination and prediction is therefore the accepted measure of radiation exposure. This study includes a survey of all forms of natural and man-made radiation to which the general public is constantly exposed. An intensive study was made of radioactive fallout over South Africa from nuclear bomb tests. From this the general radiation exposure of the South African public could be calculated. It also led to valuable scientific information on mesometeorology and health physics. The latter includes the relationship between air concentration and deposition, the transfer of airborne iodine-131 to milk, and the accumulation of strontium-90 and cesium-137 in human beings as a result of their diets. Thorough environmental studies were conducted at existing nuclear installation sites i.e. Pelinbada which is the site of the National Nuclear Research Centre and Dynefontein which is the proposed site of South Africa's first nuclear power station. These included meso-meteorology, atmospheric dispersion by means of neutron-activable tracers, accumulation factors for important radionuclides in edible marine species by means of stable element tracers, population surveys, background radioactivity surveys etc. From these results critical exposure pathways were established for both sites and the relationship between effluent release and radiation dose to the public was determined. This has lead to the establishment of maximum permissible releases for the operation of the SAFARI-1 research reactor by the Atomic Energy Board and for the specifications of the proposed Koeberg power reactors to be operated by the Electricity Supply Commission at Dynefontein [af

Licensing procedure for the construction and operation of nuclear installations within the EEC member states

International Nuclear Information System (INIS)

Didier, J.M.

1976-08-01

For Belgium and Luxembourg, the authorization procedure varies according to the Class in which the installation concerned falls (assigned according to the degree of hazard involved: Classes I, II or III). Moreover, separate authorizations are needed, one for construction and another for operation of Class I and II installations. With respect to Germany also, two such separate authorization are needed, but there is no specific procedure relating to the potential extent of hazard involved in the installation concerned. In France, the 'basic' nuclear installations are subject to a special procedure. Furthermore, the construction and operation of these installations are also subject to two separate authorizations. While the latter two authorizations are required in Italy for the main nuclear installations, no system of 'classified' installations exists according to extent of hazard involved. Similar legislation is applicable in the Netherlands. Neither does such a system of 'classified' installations exist in the United Kingdom. Moreover, there is only one single authorization (the 'site licence'), which is succesively adapted during construction. On the other hand, in Denmark and Ireland, no detailed legislation has been developed on the subject

Authorization procedure for the construction and operation of nuclear installations within the EEC member states

International Nuclear Information System (INIS)

Didier, J.M.

1974-12-01

For Belgium and Luxembourg, the authorization procedure varies according to the class in which the installation concerned falls (assigned according to the degree of hazard involved classes I, II or III). Moreover, separate authorizations are needed, one for construction and another for operation of class I and II installations. With respect to Germany also, two such separate authorizations are needed, but there is no specific procedure relating to the potential extent of hazard involved in the installation concerned. In France, the basic nuclear installations are subject to a special procedure. Furthermore, the construction and operation of these installations are also subject to two separate authorizations. While the latter two authorizations are required in Italy for the main nuclear installations, no system of classified installations exists according to extent of hazard involved. Similar legislation is applicable in the Netherlands. Neither does such a system of classified installations exist in the United Kingdom. Moreover, there is only one single authorization (the site licence), which is successively adapted during construction. On the other hand, in Denmark and Ireland, no detailed legislation has been developed on the subject

A study on safety concept and criteria of site release of nuclear installation proposed by international organizations and adopted in decommissioning practices

International Nuclear Information System (INIS)

Enokido, Yuji; Miyasaka, Yasuhiko; Ishikawa, Hironori

2008-01-01

Regulatory systems and safety criteria of site release of nuclear installation proposed by international organizations such as IAEA and applied in decommissioning in domestic and foreign countries have been studied, in order to avail them to deliberate the relevant domestic regulation and guides. In addition, the applicability of the proposal and practices to domestic legislation have been discussed. Regarding the national safety criteria, the annual individual dose constraint is optimized between 10 μSv and 300 μSv after recommendation and/or guides of IAEA etc. Unconditional release should be achieved, but the conditional and/or partial site release are possible under the same safety criteria to make the selection flexible for licensees. (author)

Standardization of Nuclear Instrumentation Applied in the NPP and in other nuclear installations

International Nuclear Information System (INIS)

Kusnowo, Arlinah; Darmawati, Suzie

2002-01-01

Nuclear power plant (NPP) and other nuclear installations have been recognized as applications needing very sophisticated technologies. One of technologies used in this all nuclear facilities is nuclear instrumentation. In order that NPP and other nuclear installations be operated safely, nuclear instrumentation requires standardization from design to its operation. Internationally, standardizations of nuclear instrumentation have been issued by IEC (International Electrotechnical Commission). Formulation of standard in nuclear instrumentation in IEC is carried out by Technical Committee (TC) 45. This paper describes briefly the standardization of nuclear instrumentation applied in Indonesia as Indonesian National Standard (SNI, Standard National Indonesia), standardization of nuclear instrumentation developed by TC 45, SC 45A, and SC 45B, as well as the possibility to adopt and apply those IEC standard in Indonesia

1990 No. 1918. The Nuclear Installations Act 1965 (Repeal and Modifications) Regulations 1990

International Nuclear Information System (INIS)

1990-01-01

These Regulations entered into force on 31 October 1990. They repeal part of Section (1) of the Nuclear Installations Act 1965 to remove the exemption of the United Kingdom Atomic Energy Authority (UKAEA) from licensing under the Act. The Regulations also amend the 1965 Act to ensure that the UKAEA's duties in respect of the safety of premises it occupies will continue to apply whether or not a nuclear site licence has been granted. (NEA) [fr

Sites for locations of nuclear reactors; Sitios para emplazamientos de reactores nucleares

Energy Technology Data Exchange (ETDEWEB)

Balcazar, M.; Huerta, M.; Lopez, A., E-mail: miguel.balcazar@inin.gob.mx [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

2014-10-15

A restriction on sites of nuclear energy is the history of seismic activity, in its magnitude (Richter) and intensity (Mercalli). This article delimits the areas of greatest magnitude and national seismic intensity, with restrictions of ground acceleration; the supplement areas with a low magnitude of seismic activity are shown. Potential sites for the location of these sites are introduced into a geographic information system. The set of geo-referenced data contains the location of the active volcanic manifestations; the historical record of earthquake epicenters, magnitudes and intensities; major geological faults; surface hydrology and water bodies; location of population density; protected areas; contour lines; the rock type or geology. The geographic information system allows entering normative criteria and environmental restrictions that correlate with geo-referenced data described above, forms both probable and exclusion areas for the installation of nuclear sites. (Author)

Nuclear installations and childhood cancer in the U.K

International Nuclear Information System (INIS)

Goldsmith, J.R.

1990-01-01

The report in November 1983 of a cluster of childhood leukemia cases in the vicinity of the Sellafield (Windscale) nuclear facility on the west coast of England has led to a substantial effort to study possible excess cancer in the vicinity of British nuclear installations. Although some additional excesses were found, the causal relationship with radionuclides was thought unlikely because the estimated doses were below those established as causal of increase in human leukemia. Since 1956, we have known that diagnostic x-rays during pregnancy are associated with increased risks from childhood cancer, especially leukemia. Gardner et al. showed that excess cases near Sellafield were in children born there, and no excess occurred among in-migrants. Roman et al. showed that significant elevations in leukemia among children living near three nuclear installations in the Midlands were only at 0-5 y, suggesting that the relevant exposure was prenatal. We identify and discuss a set of epidemiological, dosage estimation, and modeling problems relevant to interpretation of such data. We conclude that: (1) a red bone marrow-based model for brief, high-level exposures of adults associated with myelogenous leukemia is inappropriate for evaluating the impact of internal emitters, relatively continuous exposures in perinatal periods in association with acute lymphatic leukemia; (2) incidence of mortality rates of childhood leukemia should be evaluated in the vicinity of nuclear installations in many countries; and (3) in contrast to nuclear reprocessing and nuclear weapons installations, there is little evidence of excess childhood leukemia among residents in areas adjacent to nuclear power installations in the U.K

Siting technology of underground nuclear power station

International Nuclear Information System (INIS)

Motojima, M.; Hibino, S.

1989-01-01

For the site of a nuclear power station, it may be possible to select a seaside mountain area, if the condition is suitable to excavate large rock caverns in which a reactor and other equipments are installed. As the case study on the siting technology for an underground nuclear power station, the following example was investigated. The site is a seaside steep mountain area, and almost all the equipments are installed in plural tunnel type caverns. The depth from the ground surface to the top of the reactor cavern is about 150 m, and the thickness of the rock pillar between the reactor cavern of 33 m W x 82 mH x 79 mD and the neighboring turbine cavern is 60 m. In this paper, the stability of rock caverns in this example, evaluated by numerical analysis, is described. The numerical analysis was carried out on the central cross section of the reactor cavern, taking the turbine cavern, geostress, the mechanical properties of rock mass and the process of excavation works in consideration. By the analysis, the underground caverns in this example were evaluated as stable, if the rock quality is equivalent to C H class or better according to the CRIEPI rock classification. (K.I.)

Proposal of a dry storage installation in Angra NPP for spent nuclear fuel

International Nuclear Information System (INIS)

Romanato, Luiz S.; Rzyski, Barbara M.

2009-01-01

When nuclear fuel is removed from a power reactor core after the depletion of efficiency in generating energy is called Spent Nuclear Fuel (SNF). After its withdrawal from the reactor core, SNF is temporarily stored in pools usually at the same site of the reactor. During this time, short-living radioactive elements and generated heat undergo decay until levels that allow removing the SNF from the pool and sending it for reprocessing or a temporary storage whether any of its final destinations has not yet been defined. It can be loaded in casks and disposed during years in a dry storage installations until be sent to a reprocessing plant or deep repositories. Before any decision, reprocessing or disposal, the SNF needs to be safely and efficiently isolated in one of many types of storages that exist around the world. Worldwide, the amount of SNF increases annually and in the next years this amount will be higher as a consequence of new Nuclear Power Plants (NPP) construction. In Brazil, that is about to construct the Angra 3 nuclear power reactor, a project about the final destination of the SNF is not yet ready. This paper presents a proposal for a dry storage installation in the Angra NPP site since it can be an initial solution for the Brazilian's SNF, until a final decision is taken. (author)

Decommissioning nuclear installations

International Nuclear Information System (INIS)

Dadoumont, J.

2010-01-01

When a nuclear installation is permanently shut down, it is crucial to completely dismantle and decontaminate it on account of radiological safety. The expertise that SCK-CEN has built up in the decommissioning operation of its own BR3 reactor is now available nationally and internationally. Last year SCK-CEN played an important role in the newly started dismantling and decontamination of the MOX plant (Mixed Oxide) of Belgonucleaire in Dessel, and the decommissioning of the university research reactor Thetis in Ghent.

Preparation of Act on State Surveillance of Nuclear Safety of Nuclear Installations

International Nuclear Information System (INIS)

Kyncl, J.

1983-01-01

The Czechoslovak Government Decree no. 179 of June 1982 approved the principles underlying the first Czechoslovak legal norm to complexly resolve the problem of State surveillance of nuclear safety of nuclear installations. In the introduction the law will define the concept of nuclear safety of nuclear installations and will justify the reasons for which it has to be assured. The individual parts of the law will deal with the establishment of State surveillance of nuclear safety, the tasks of the Czechoslovak Atomic Energy Commission in this area, the control activity of Commission personnel, the measures taken against responsible organizations and personnel for failing to observe their duties, the obligations of bodies and organizations, and the cooperation between inspection bodies. (A.K.)

Practical decommissioning experience with nuclear installations in the European Community

International Nuclear Information System (INIS)

Skupinski, E.

1993-01-01

Initiated by the Commission of the European Communities (CEC), this seminar was jointly organized by Kernkraftwerke RWE Bayernwerk GmbH (KRB) and the CEC at Gundremmingen-Guenzburg (D), where the former KRB-A BWR is presently being dismantled. The meeting aimed at gathering a limited number of European experts for the presentation and discussion of operations, the results and conclusions on techniques and procedures presently applied in the dismantling of large-scale nuclear installations in the European Community. Besides the four pilot dismantling projects of the presently running third R and D programme (1989-93) of the European Community on decommissioning of nuclear installations (WAGR, BR-3 PWR, KRB-A BWR and AT-1 FBR fuel reprocessing), the organizers selected the presentation of topics on the following facilities which have a significant scale and/or representative features and are presently being dismantled: the Magnox reprocessing pilot plant at Sellafield, the HWGCR EL4 at Monts d'Arree, the operation of an on-site melting furnace for G2/G3 GCR dismantling waste at Marcoule, an EdF confinement conception of shut-down LWRs for deferred dismantling, and the technical aspects of the Greifswald WWER type NPPs decommissioning. This was completed by a presentation on the decommissioning of material testing reactors in the United Kingdom and by an overview on the conception and implementation of two EC databases on tools, costs and job doses. The seminar concluded with a guided visit of the KRB-A dismantling site. This meeting was attended by managers concerned by the decommissioning of nuclear installations within the European Community, either by practical dismantling work or by decision-making functions. Thereby, the organizers expect to have contributed to the achievement of decommissioning tasks under optimal conditions - with respect to safety and economics - by making available a complete and updated insight into on-going dismantling projects and by

Authorization procedure for the construction and operation of nuclear installations within the EC Member States, including supervision and control

International Nuclear Information System (INIS)

Amaducci, Sandro; Didier, J.M.

1978-01-01

This report is an updating of the report EUR 5284, Authorization procedure for the construction and operation of nuclear installations within the EEC Member States, prepared in 1974 by J.M. Didier and Associates. Recent developments regarding the authorization procedure for the construction and operation of nuclear installations have taken place in Italy (introduction of a site approval procedure) and in Denmark (adoption of an overall legislation on the subject, however not yet in force). With respect to supervision and control of nuclear installations during construction and operation, competences of, as well as their exercise by, supervisory authorities in all EC Member States, with the exception of Ireland, are also analysed in the current study

The control of base nuclear facilities (I.N.B.); Le controle des installations nucleaires de base (INB)

Energy Technology Data Exchange (ETDEWEB)

Anon

2009-02-15

The Authority of Nuclear Safety ( A.S.N). presents in this column the current events of the control of the nuclear basic installations during august, september, october 2008, classified by nuclear site. This information is also available in real-time on the A.S.N. web site, www.asn.fr, in the column 'news'. We can consult all the notices of significant incident published as well as the following letters of inspection, the notices of information about the reactors shutdown, press releases and the A.S.N. information notes. (N.C.)

Philosophy and safety requirements for land-based nuclear installations

International Nuclear Information System (INIS)

Kellermann, Otto

1978-01-01

The main ideas of safety philosophy for land-based nuclear installations are presented together with their background of protection goals. Today's requirements for design and quality assurance are deductively shown. Finally a proposition is made for a new balancing of safety philosophy according to the high safety level that nuclear installations have reached

Quality assurance during site construction of nuclear power plants

International Nuclear Information System (INIS)

1981-01-01

This Safety Guide provides requirements and recommendations related to the establishment and implementation of a quality assurance programme for the site construction activities at nuclear power plants. These include activities such as fabricating, erecting, installing, handling, storing, cleaning, flushing, inspecting, testing, modifying, repairing, and maintaining

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

International Nuclear Information System (INIS)

Roenty, V.; Keski-Rahkonen, O.; Hassinen, J.P.

2004-12-01

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

Change of nuclear reactor installation in the first nuclear ship of Japan Nuclear Ship Development Agency

International Nuclear Information System (INIS)

1979-01-01

The written application concerning the change of nuclear reactor installation in the first nuclear ship was presented from the JNSDA to the prime minister on January 10, 1979. The contents of the change are the repair of the primary and secondary shields of the reactor, the additional installation of a storage tank for liquid wastes, and the extension of the period to stop the reactor in cold state. The inquiry from the prime minister to the Nuclear Safety Commission was made on June 9, 1979, through the examination of safety in the Nuclear Safety Bureau, Science and Technology Agency. The Nuclear Safety Commission instructed to the Committee for the Examination of Nuclear Reactor Safety on June 11, 1979, about the application of criteria stipulated in the law. The relevant letters and the drafts of examination papers concerning the technical capability and the safety in case of the change of nuclear reactor installation in the first nuclear ship are cited. The JNSDA and Sasebo Heavy Industries, Ltd. seem to have the sufficient technical capability to carry out this change. As the result of examination, it is recognized that the application presented by the JNSDA is in compliance with the criteria stipulated in the law concerning the regulation of nuclear raw materials, nuclear fuel materials and nuclear reactors. (Kako, I.)

Development of a quality management system for Brazilian nuclear installations

International Nuclear Information System (INIS)

Kibrit, Eduardo; Zouain, Desiree Moraes

2005-01-01

The present work is a proposal for developing a quality management system for Brazilian nuclear installations, based on applicable standards. The standard ISO 9001:2000 [4] establishes general requirements for the implementation of a quality management system in all kinds of organizations. The standard IAEA 50-C/SG-Q [1] establishes general requirements for the implementation of a quality assurance system in nuclear installations. The standard CNEN-NN- 1.16 [5] establishes the regulating requirements for the quality assurance systems and programs of nuclear installations, for licensing and authorization for operation of these installations in Brazil. The revision of standard IAEA 50-C/SG-Q [1], to be replaced by IAEA DS 338 [2] and IAEA DPP 349 [3], introduces the concept of 'Integrated Management System' for the nuclear area, in preference to the concept of 'Quality Assurance'. This approach is incorporated with the current tendency, because it guides the system to manage, in an integrated way, the requirements of quality, safety, health, environment, security and economics of the installation. The results of the characterization of the quality management systems established in the applicable standards are presented, with the determination of the common and conflicting points among them. Referring data to quality assurance program/quality management system in some nuclear installations of IAEA Member States are also presented. (author)

Practical methods for radiation survey in nuclear installations

International Nuclear Information System (INIS)

Shweikani, R.

2001-12-01

This study is placed to those who are responsible to perform radiation survey in the nuclear installations, especially the beginners. Therefore, it gives a comprehensive view to all-important aspects related to their work starting from the structure of atoms to the practical steps for radiation survey works. So, it clarify how to perform personal monitoring, methods for monitoring surface contamination, methods for measuring radioactivity of gases and radioactive aerosols in air, monitoring radiation doses, measuring radiation influences in workplaces and finally measuring internal exposure of radiation workers in nuclear installations. Finally, The study shows some cases of breaches of radiation protection rules in some American nuclear installations and describes the final results of these breaches. The aim of this is to assure that any breach or ignore to radiation protection principles may produce bad results, and there is no leniency in implementing environmental radiation protection principles. (author)

Practical decommissioning experience with nuclear installations in the European Community

International Nuclear Information System (INIS)

Skupinski, E.

1992-01-01

Initiated by the Commission of the European Communities (CEC), this seminar was jointly organized by the AEA, BNFL and the CEC at Windermere and the sites of Windscale/Sellafield, where the former Windscale advanced gas-cooled reactor and the Windscale piles are currently being dismantled. The meeting aimed at gathering a limited number of European experts for the presentation and discussion of operations, results and conclusions on techniques and procedures currently applied in the dismantling of large scale nuclear installations in the European Community

Seismic evaluation of nuclear installations; Avaliacao sismica de instalacoes nucleares

Energy Technology Data Exchange (ETDEWEB)

Mattar Neto, Miguel [Instituto de Pesquisas Energeticas e Nucleares (IPEN), Sao Paulo, SP (Brazil)

1997-10-01

Some considerations regarding extreme external events, natural or man-induce, such as earthquakes, floods, air crashes, etc, shall be done for nuclear facilities to minimizing the potential impact of the installation on the public and the environment. In this paper the main aspects of the seismic evaluation of nuclear facilities (except the nuclear power reactors) will be presented based on different codes and standards. (author). 7 refs., 2 tabs.

The work of the OECD Nuclear Energy Agency on safety and licensing of nuclear installations

International Nuclear Information System (INIS)

Strohl, P.

1975-01-01

The acceleration of nuclear power programmes in OECD Member countries is reflected in the emphasis given by OECD/NEA to its activities in nuclear safety and regulatory matters. Particular effort is devoted to work on radiation protection and radioactive waste management, safety of nuclear installations and nuclear law development. A Committee on the Safety of Nuclear Installations reviews the state of the art and identifies areas for research and co-ordination of national programmes. A Sub-Committee on Licensing collates information and data on licensing standards and practices of different countries with a view to considering problems of common interest. Comparative studies of various licensing systems and discussions between licensing authorities should help to improve regulatory control of nuclear installations for which there appears to be a need for internationally accepted standards in the long run. (author)

Border installations

International Nuclear Information System (INIS)

Lenaerts, Koen

1988-01-01

Border installations cover all nuclear plants located near the border with a neighbouring state. However, the actual distance depends on the context. The distance can vary considerably. Also the prohibition on siting near a heavily populated area also defines the actual distance variably. The distance criteria may be modified by other factors of topography, prevailing climate and so on. Various examples which illustrate the problems are given. For example, the Creys-Melville nuclear power plant is 80km from Geneva and the Cattonam installation is 12km from the French border with Luxembourg and Germany. The Cattenom case is explained and the legal position within the European Institutions is discussed. The French licensing procedures for nuclear power stations are described with special reference to the Cattenom power plant. Border installations are discussed in the context of European Community Law and Public International Law. (U.K.)

Nuclear installations: decommissioning and dismantling

International Nuclear Information System (INIS)

Anon.

1995-01-01

This document is a compilation of seven talks given during the 1995 EUROFORUM conference about decommissioning and dismantling of Nuclear installations in the European Community. The first two papers give a detailed description of the legal, financial and regulatory framework of decommissioning and dismantling of nuclear facilities in the European Union and a review of the currently available decommissioning techniques for inventory, disassembly, decontamination, remote operations and management of wastes. Other papers describe some legal and technical aspects of reactor and plants dismantling in UK, Germany, Spain and France. (J.S.)

Competent person for radiation protection. Practical radiation protection for base nuclear installations and installations classified for the environment protection

International Nuclear Information System (INIS)

Pin, A.; Perez, S.; Videcoq, J.; Ammerich, M.

2008-01-01

This book corresponds to the practical module devoted to the base nuclear installations and to the installations classified for the environment protection, that is to say the permanent nuclear installations susceptible to present risks for the public, environment or workers. Complied with the legislation that stipulates this module must allow to apply the acquired theoretical training to practical situations of work, it includes seven chapters as follow: generalities on access conditions in regulated areas of nuclear installation,s or installations classified for environment protection and clothing against contamination; use of control devices and management of damaged situations; methodology of working place studies, completed by the application to a real case of a study on an intervention on a containment wall; a part entitled 'take stock of the situation' ends every chapter and proposes to the reader to check its understanding and acquisition of treated knowledge. (N.C.)

Nuclear installations in Belarus: Implications of political and technical issues

International Nuclear Information System (INIS)

Zaitsev, S.I.

2001-01-01

The report deals with some aspects of past and present supervisory activities at nuclear installations in Belarus. It briefly describes an existing supervisory system for nuclear installations in the Republic of Belarus, its legislative basis and functions of the supervisory body. Consideration is given to further development and improvement of the supervision in such fields as revision and elaboration of normative documents on nuclear safety, training of inspectors, co-operation with other governmental bodies while examining the nuclear option in the Republic of Belarus. (author)

Should the public be encouraged to visit nuclear plant sites?

International Nuclear Information System (INIS)

Ferte, J. de la

1993-01-01

As we all know, technological progress does not only depend on the innovation capacity of scientists and engineers or the sophistication of technology, but also on public acceptance. People - today - are not only more curious about new applications of technology but also more inquiring about their potential impact on their own safety and environment. This is particularly true in the nuclear field, where the people are afraid of nuclear installations and processes unknown to them. On the contrary, the more opportunities they have to see or live near nuclear plants, the less they are inclined to reject them as a whole. The past two decades have confirmed the increasing importance of visitor centres at nuclear plant sites as a major communication tool between the nuclear industry and the public. Already today, for example, 16% of the US public and 11% of the French public have visited a nuclear power plant or its information centre. A rich experience is therefore available from existing visitor centres at nuclear power stations in most industrialised countries. Furthermore, the construction and industrial operation of new facilities in the nuclear fuel cycle presents new challenges in terms of public understanding and acceptance which are progressively taken into account. As a result, visitor centres with new communication strategies and tools are now being put in place at radioactive waste management sites and nuclear fuel cycle sites as well as near nuclear installations being dismantled. The OECD Nuclear Energy Agency (NEA) organised an international Seminar in November 1992 in Madrid (Spain) in co-operation with the Spanish Agency for the Management of Radioactive Waste (ENRESA) and the Union of Spanish Electricity Utilities (UNESA) to: 1. take stock of the experience of OECD countries in the design and operation of visitor centres; 2. assess the educational and information methods and tools used in these centres, and 3. measure their impact on public opinion and

Should the public be encouraged to visit nuclear plant sites?

Energy Technology Data Exchange (ETDEWEB)

Ferte, J de la [External Relations and Public Affairs, OECD Nuclear Energy Agency, Paris (France)

1993-07-01

As we all know, technological progress does not only depend on the innovation capacity of scientists and engineers or the sophistication of technology, but also on public acceptance. People - today - are not only more curious about new applications of technology but also more inquiring about their potential impact on their own safety and environment. This is particularly true in the nuclear field, where the people are afraid of nuclear installations and processes unknown to them. On the contrary, the more opportunities they have to see or live near nuclear plants, the less they are inclined to reject them as a whole. The past two decades have confirmed the increasing importance of visitor centres at nuclear plant sites as a major communication tool between the nuclear industry and the public. Already today, for example, 16% of the US public and 11% of the French public have visited a nuclear power plant or its information centre. A rich experience is therefore available from existing visitor centres at nuclear power stations in most industrialised countries. Furthermore, the construction and industrial operation of new facilities in the nuclear fuel cycle presents new challenges in terms of public understanding and acceptance which are progressively taken into account. As a result, visitor centres with new communication strategies and tools are now being put in place at radioactive waste management sites and nuclear fuel cycle sites as well as near nuclear installations being dismantled. The OECD Nuclear Energy Agency (NEA) organised an international Seminar in November 1992 in Madrid (Spain) in co-operation with the Spanish Agency for the Management of Radioactive Waste (ENRESA) and the Union of Spanish Electricity Utilities (UNESA) to: 1. take stock of the experience of OECD countries in the design and operation of visitor centres; 2. assess the educational and information methods and tools used in these centres, and 3. measure their impact on public opinion and

Drones and safety of nuclear installations

International Nuclear Information System (INIS)

Tourneur, Jean-Claude

2015-01-01

Recent flyovers of French nuclear power plants by drones or UAVs (the owners of these drones could not be identified) has made the safety of these nuclear installations a matter of concern. These events also raised the question of balance between secret and information about these installations. The French Parliamentary Office for the Assessment of Scientific and Technological Choices (OPECST) organised two sets of hearings, a confidential one with people in charge of information related to national defence and security, and a public one opened to all stakeholders. This article briefly reports and discusses the results of these hearings. It appeared that these flyovers are not really a threat, are more a communication action than anything else. Suggestions have been made for the development of researches in the field of drone detection, and also for evolutions of French legislation on drones

Nuclear reactor installation

International Nuclear Information System (INIS)

Keller, W.

1976-01-01

A nuclear reactor installation includes a pressurized-water coolant reactor vessel and a concrete biological shield surrounding this vessel. The shield forms a space between it and the vessel large enough to permit rapid escape of the pressurized-water coolant therefrom in the event the vessel ruptures. Struts extend radially between the vessel and shield for a distance permitting normal radial thermal movement of the vessel, while containing the vessel in the event it ruptures, the struts being interspaced from each other to permit rapid escape of the pressurized-water coolant from the space between the shield and the vessel

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

International Nuclear Information System (INIS)

Sene, Monique; Sene, Raymond

2011-11-01

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

Decree of the Czechoslovak Atomic Energy Commission concerning the security protection of nuclear installations and nuclear materials

International Nuclear Information System (INIS)

1989-01-01

In compliance with the Czechoslovak State Surveillance over Nuclear Safety of Nuclear Installations Act No. 28/1984, the Decree specifies requirements for assuring security protection of nuclear installations (and their parts) and of nuclear materials with the aim to prevent their abuse for jeopardizing the environment and the health and lives of people. (P.A.)

Quality assurance for safety in nuclear power plants and other nuclear installations. Code and safety guides Q1-Q14. A publication within the NUSS programme

International Nuclear Information System (INIS)

1996-01-01

The code provides the basic requirements for establishing and implementing quality assurance programmes for the stages of siting, design, construction, commissioning, operation and decommissioning of nuclear power plants. These basic requirements apply to all individuals and organizations, including designers, suppliers, constructors, manufacturers and operators. The basic quality assurance requirements presented in this Code also apply, with appropriate modifications, to nuclear installations other than nuclear power plants

Nuclear installations safety in France. Compilation of regulatory guides

International Nuclear Information System (INIS)

1988-01-01

General plan: 1. General organization of public officials. Procedures 1.1. Texts defining the general organization and the procedures 1.2. Interventing organisms; 2. Texts presenting a technical aspect other than basic safety rules and associated organization texts; 2.1. Dispositions relating to safety of nuclear installations 2.2. Dispositions relating to pressure vessels 2.3. Dispositions relating to quality 2.4. Dispositions relating to radioactive wastes release 2.5. Dispositions relating to activities depending of classified installations; 3. Basic Safety Rules (BSR) 3.1. BSR relating to PWR 3.2. BSR relating to nuclear installations other than PWR 3.3. Other BSR [fr

Managing and regulating organisational change in nuclear installations

International Nuclear Information System (INIS)

Pyy, P.; Reiersen, C.

2004-01-01

To the extent that organisational change in nuclear installations can potentially impact nuclear safety, it is imperative to ensure that such change is property managed and regulated. A number of key elements can help achieve successful management of change. (author)

SNRIU nuclear installation modifications

International Nuclear Information System (INIS)

Goroshanskyi, Andrii

2013-01-01

Design stages of Nuclear Instalations (NI): NI design is performed in three stages: • Feasibility study: - Feasibility study is developed on the basis of the customer task for production facilities and linear facilities engineering and transport infrastructure that require detailed study of relevant decisions and identify options for and feasibility of construction. • Design: - The design is developed on the basis of design task, initial data and approved the previous stage under three-stage design. • Detailed documentation

UK nuclear installations

International Nuclear Information System (INIS)

Gronow, W.S.

Regulations and conditions for the commissioning of nuclear power plants in the UK, their siting, licence conditions, design safety assessment, inspection during construction and conditions for safety in operation are listed. (J.P.)

Experience with HEPA filters at United States nuclear installations

International Nuclear Information System (INIS)

Bellamy, R.R.

1977-01-01

Part 50 of Title 10 of the United States Code of Federal Regulations requires that a number of atmosphere cleanup systems be included in the design of commercial nuclear power plants to be licensed in the United States. These filtering systems are to contain high efficiency particulate air (HEPA) filters for removal of radioactive particulate matter generated during normal and accident conditions. Recommendations for the design, testing and maintenance of the filtering systems and HEPA filter components are contained in a number of United States Nuclear Regulatory Commission documents and industry standards. This paper will discuss this published guidance available to designers of filtering systems and the plant operators of U.S. commercial nuclear power plants. The paper will also present a survey of published reports of experience with HEPA filters, failures and possible causes for the failures, and other abnormal occurrences pertaining to HEPA filters installed in U.S. nuclear power installations. A discussion will be included of U.S. practices for qualification of HEPA filters before installation, and verification of continued performance capability at scheduled intervals during operation

Quality and safety of nuclear installations: the role of administration, and, nuclear safety and regulatory procedures

International Nuclear Information System (INIS)

Queniart, D.

1979-12-01

In the first paper the author defines the concepts of safety and quality and describes the means of intervention by the Public Authorities in safety matters of nuclear installations. These include individual authorisations, definition and application of technical rules and surveillance of installations. In the second paper he defines the distinction between radiation protection and safety and presents the legislative and regulatory plan for nuclear safety in France. A central safety service for nuclear installations was created in March 1973 within the Ministry of Industrial and Scientific Development, where, amongst other tasks, it draws up regulatory procedures and organizes inspections of the installations. The main American regulations for light water reactors are outlined and the French regulatory system for different types of reactors discussed

Information report on nuclear safety and radiation protection of La Hague AREVA site. Issue 2014

International Nuclear Information System (INIS)

2013-01-01

Published in compliance with the French code of the environment, this report first presents the Areva's La Hague site which comprises several basic nuclear installations (INB), is dedicated to several activities related to the nuclear fuel cycle, is submitted to a constraining legal and regulatory framework, and implements a policy for a sustainable development and continuous progress. The document describes the various measures regarding nuclear safety and radiation protection, reports nuclear events which are classified according to the INES scale and occurred and had to be declared in 2014, describes the management of effluents by the different installations present on this site and the control of the environment. It addresses the waste management and the management of other impacts. It gives an overview of actions undertaken regarding information and transparency. Recommendations of the CHSCT are reported

Information report on nuclear safety and radiation protection of La Hague AREVA site. Issue 2013

International Nuclear Information System (INIS)

2014-01-01

Published in compliance with the French code of the environment, this report first presents the Areva's La Hague site which comprises several basic nuclear installations (INB), is dedicated to several activities related to the nuclear fuel cycle, is submitted to a constraining legal and regulatory framework, and implements a policy for a sustainable development and continuous progress. The document describes the various measures regarding nuclear safety and radiation protection, reports nuclear events which are classified according to the INES scale and occurred and had to be declared in 2013, describes the management of effluents by the different installations present on this site and the control of the environment. It addresses the waste management and the management of other impacts. It gives an overview of actions undertaken regarding information and transparency. Recommendations of the CHSCT are reported

Evaluation of the nuclear installations safety of the CEA in 1998

International Nuclear Information System (INIS)

Laverie, M.

1999-09-01

Michel Laverie, Director of the nuclear safety and quality at the Cea, took stoke of the CEA nuclear installations in 1998. After a recall of the nuclear safety policy and organization, the author presents the risks factors bound to the CEA activities as the dismantling, the wastes and the human factors. A last part is devoted to the list of the accidents occurred during 1998 in the nuclear installations. Tables and statistics illustrate this analysis. (A.L.B.)

Assessment of safety of the nuclear installations of the world

International Nuclear Information System (INIS)

Thomas, B.A.; Pozniakov, N.; Banga, U.

1992-01-01

Incidents and accidents periodically remind us that preventive measures at nuclear installations are not fully reliable. Although sound design is widely recognized to be prerequisite for safe operation, it is not sufficient. An active management that compensates for the weak aspects of the installations design by redundant operational provisions, is the key factor to ensure safe operation. Safety of nuclear installations cannot be assessed on an emotional basis. Since 1986, accurate safety assessment techniques based on an integrated approach to operational safety have been made available by the ASSET services and are applicable to any industrial process dealing with nuclear materials. The ASSET methodology enables to eliminate in advance the Root Causes of the future accidents by introducing practical safety culture principles in the current managerial practices

Computer systems for nuclear installation data control

International Nuclear Information System (INIS)

1987-09-01

The computer programs developed by Divisao de Instalacoes Nucleares (DIN) from Brazilian CNEN for data control on nuclear installations in Brazil are presented. The following computer programs are described: control of registered companies, control of industrial sources, irradiators and monitors; control of liable person; control of industry irregularities; for elaborating credence tests; for shielding analysis; control of waste refuge [pt

Responsible management: the Dutch licensing policy for nuclear installations

International Nuclear Information System (INIS)

Slange, R.

1994-01-01

The governmental policy, to tolerate operation of existing nuclear installations not backed by the required operating permits, certainly is applied only in exceptional cases, and this all the more when the plant is a nuclear installation. Any decision to tolerate further operation must be justified by compliance with a number of rigid criteria, there may be a debate in Parliament about the case, third parties have the right participate in the decision-finding procedure, and there is the right of appeal. (orig.) [de

Nuclear medicine installations supervisors interactive course (CD-ROM)

International Nuclear Information System (INIS)

Williart, A.; Shaw, M.; Tellez, M.

2000-01-01

The professionals who work as Nuclear Medicine Installations Supervisors need a suitable training. This training must be based on the guidelines of the C.S.N. (the Spanish Agency for Nuclear Safety). The traditional training courses must comply with a set of requirements, that not always is possible to get: They are given in a settled place. They are developed during a time, more or less lengthy. This time is pre-established. However, the persons willing to follow these courses have some difficulties with the place and the time. Many of them do not live near the places where the courses are given, in general in big cities, while there are Nuclear Medicine Installations scattered through all Spain. Moreover in some occasions they have not available time to attend the courses. Many times, faced with so many obstacles, the option is not to do the suitable training course. In order to solve this kind of problems we offer an Interactive Training Course (supported by CD-ROM). The course contents are based on Spanish Regulations and on the Safety Guide, established by C.S.N., for approval Radioactive Installations Supervisors Training Courses. This guide includes General Topics for Radioactive Installations and Specific Subjects for Nuclear Medicine. (General topics) Basic knowledge on the fundamental concepts on the action and nature of Ionizing Radiations, their risks and preventions. The ionizing radiations. Biological effects of ionizing radiations. Radiological protection. Legislation on radioactive installations. (Specific Subjects) Knowledge on the radiological risks associated to the proper techniques in the specific field of application. In our case the specific field is Nuclear Medicine Installations, where the radioactive sources are used for diagnostic or for therapy. Specific legal and administrative aspects. Non-encapsulated radioactive sources. Associated radiological risks to the use of non-encapsulated sources. Installations design. Operative procedures

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

International Nuclear Information System (INIS)

Pinchuk, M.G.

2001-01-01

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

Statement of nuclear incidents at nuclear installations. Third quarter 2001

International Nuclear Information System (INIS)

2002-01-01

A statement of nuclear incidents at nuclear installations in Britain during the third quarter of 2001 is published today by the Health and Safety Executive. It covers the period 1 July to 30 September 2001. The statement is published under arrangements that came into effect from the first quarter of 1993, derived from the Health and Safety Commission's powers under section 11 of the Health and Safety at Work, etc. Act 1974

A dynamic system for ATLAS software installation on OSG grid sites

International Nuclear Information System (INIS)

Zhao, X; Maeno, T; Wenaus, T; Leuhring, F; Youssef, S; Brunelle, J; De Salvo, A; Thompson, A S

2010-01-01

A dynamic and reliable system for installing the ATLAS software releases on Grid sites is crucial to guarantee the timely and smooth start of ATLAS production and reduce its failure rate. In this paper, we discuss the issues encountered in the previous software installation system, and introduce the new approach, which is built upon the new development in the areas of the ATLAS workload management system (PanDA), and software package management system (pacman). It is also designed to integrate with the EGEE ATLAS software installation framework. In the new system, ATLAS software releases are packaged as pacball, a uniquely identifiable and reproducible self-installing data file. The distribution of pacballs to remote sites is managed by ATLAS data management system (DQ2) and PanDA server. The installation on remote sites is automatically triggered by the PanDA pilot jobs. The installation job payload connects to a central ATLAS software installation portal, making the information of installation status easily accessible across OSG and EGEE Grids. The issues encountered in running the new system in production, and our future plan for improvement, will also be discussed.

Site-specific issues related to structural/seismic design of an underground independent spent fuel storage installation (ISFSI)

International Nuclear Information System (INIS)

Tripathi, B.P.

2005-01-01

Utilities owning and operating commercial nuclear power plants (NPP) in USA may choose to build an underground Independent Spent Fuel Storage Installation (ISFSI) to store the spent nuclear fuels. The regulatory requirements and other guidance are based on 10 CFR Part 72, Regulatory Guide RG 3.73, Standard Review Plans NUREG-1536 and NUREG-1567, and Interim staff Guidance (ISG) documents as applicable. Structures, Systems, and Components (SSCs) classified as important to safety are designed to withstand the effects of site-specific environmental conditions and natural phenomena such as earthquake, tornado, flood, etc. An underground ISFSI for storage of spent nuclear fuel, presents some unique analysis and design challenges. This paper will briefly address some of these challenges and discuss site-specific loads, including seismic for the ISFSI design. (authors)

Fire protection and fire fighting in nuclear installations

International Nuclear Information System (INIS)

1989-01-01

Fires are a threat to all technical installations. While fire protection has long been a well established conventional discipline, its application to nuclear facilities requires special considerations. Nevertheless, for a long time fire engineering has been somewhat neglected in the design and operation of nuclear installations. In the nuclear industry, the Browns Ferry fire in 1975 brought about an essential change in the attention paid to fire problems. Designers and plant operators, as well as insurance companies and regulators, increased their efforts to develop concepts and methods for reducing fire risks, not only to protect the capital investment in nuclear plants but also to consider the potential secondary effects which could lead to nuclear accidents. Although the number of fires in nuclear installations is still relatively large, their overall importance to the safety of nuclear power plants was not considered to be very high. Only more recently have probabilistic analyses changed this picture. The results may well have to be taken into account more carefully. Various aspects of fire fighting and fire protection were discussed during the Symposium, the first of its kind to be organized by the IAEA. It was convened in co-operation with several organizations working in the nuclear or fire protection fields. The intention was to gather experts from nuclear engineering areas and the conventional fire protection field at one meeting with a view to enhancing the exchange of information and experience and to presenting current knowledge on the various disciplines involved. The presentations at the meeting were subdivided into eight sessions: standards and licensing (6 papers); national fire safety practices (7 papers); fire safety by design (11 papers); fire fighting (2 papers); computer fire modeling (7 papers); fire safety in fuel center facilities (7 papers); fire testing of materials (3 papers); fire risk assessment (5 papers). A separate abstract was

Protection of base nuclear installations against external flooding - Guide nr 13, release of the 08/01/2013

International Nuclear Information System (INIS)

2013-01-01

As the French law requires the flooding risk to be taken into account in the demonstration of the nuclear safety of base nuclear installations (INB), this guide aims at defining situations to be taken into account when assessing the flooding risk for a site (identification of water sources and of flooding causes, definition of flooding situations), at proposing an acceptable method to quantify these situations (local rains, rise of water level, problems on hydraulic works, dam failure, ocean waves, and so on), and at listing recommendations to define the protection means which are adapted to the specificities of the flooding risk, and are implemented by the operator with respect to the installation lifetime

Legal bases for the installation of nuclear power plants

International Nuclear Information System (INIS)

Faria, N.M. de; Barros, E.A.

1980-01-01

The role of the National Nuclear Energy Comission, the National Department of Water and Electrical Energy and the 'Centrais Eletricas Brasileiras S.A.' for the installation of Nuclear Power Plants is presented. (A.L.) [pt

A legislative framework for the safety of nuclear installations in the European Union

International Nuclear Information System (INIS)

Kus, S.; Emmerechts, S.

2009-01-01

For the first time since the inception of the European Community in 1957 and after two previously unsuccessful attempts, on 25 June 2009 the Council of the European Union adopted European-wide, binding requirements on nuclear safety. The goal of the 'Council Directive establishing a Community framework for the nuclear safety of nuclear installations' ('the Directive') is to maintain and to promote the continuous improvement of nuclear safety and to ensure that a high level of nuclear safety is provided by EU member states to protect workers and the general public against the dangers arising from nuclear installations. The Directive is based on the IAEA Safety Fundamentals and the Convention on Nuclear Safety. The 27 member states of the Community are required to bring into force the laws, regulations and administrative provisions necessary to comply with the Directive by 22 July 2011. The Directive applies to a range of nuclear installations that is wider than the one adopted in the Convention on Nuclear Safety.9 The Directive applies to any civilian nuclear installation, defined as: a) an enrichment plant, nuclear fuel fabrication plant, nuclear power plant, reprocessing plant, research reactor facility, spent fuel storage facility; and b) storage facilities for radioactive waste that are on the same site and are directly related to nuclear installations listed under point a). The Directive is without doubt a milestone in international and regional law making in the field of nuclear law, not so much because of its content but because of the supranational nature of European law and the powers of EU institutions. Member states have long resisted the Directive because of the powers which it delegates to the European Commission, and more importantly, to the European Court of Justice. The Commission, as the guardian of the treaties and the measures taken by the institutions, ensures that EU legislation is applied correctly by the member states. It can start

Safeguards Strategy in Physical Protection System for Nuclear Installation

International Nuclear Information System (INIS)

Ade lndra B; Kasturi; Tatang Eryadi

2004-01-01

Safeguards strategy is directed at efforts of eliminating theft of nuclear materials and sabotage of nuclear installation. For achieving the above objective, it is necessary to set up safeguards strategy in physical protection of nuclear materials and installation. The safeguards strategy starts from anticipated security condition, list of thefts, planning referred to as safeguards planning. Safeguards planning are implemented in safeguards implementation, followed up then by evaluation. Results of evaluation are equipped with results of safeguards survey already developed. Safeguards' planning is made from these results and serve as guidelines for next safeguards implementation and is repeated to form a safeguard cycle. One safeguard cycle is made on a periodical basis, at least annually. (author)

Regulatory oversight report 2008 concerning nuclear safety in Swiss nuclear installations

International Nuclear Information System (INIS)

2009-04-01

This annual report issued by the Swiss Federal Nuclear Inspectorate (ENSI) reports on the work carried out by the Inspectorate in 2008. This report reviews the regulatory activities in the four Swiss nuclear power stations and in four further nuclear installations in various Swiss research facilities. It deals with topics such as operational details, technologies in use, radiation protection, radioactive wastes, emergency dispositions, personnel and provides an assessment of operations from the safety point of view. Also, the transportation of nuclear materials - both nuclear fuels and nuclear wastes - is reported on. General topics discussed include probabilistic safety analyses and accident management, earthquake damage analysis and agreements on nuclear safety. The underground disposal of highly-radioactive nuclear wastes and work done in the rock laboratories are discussed, as are proposals for additional nuclear power stations

Information report on nuclear safety and radiation protection of the La Hague AREVA site- Issue 2012

International Nuclear Information System (INIS)

2013-06-01

Published in compliance with the French code of the environment, this report first presents the Areva's La Hague site which comprises several basis nuclear installations (INB), is dedicated to several activities related to the nuclear fuel cycle, is submitted to a constraining legal and regulatory framework, and implements a policy for a sustainable development and continuous progress. The document describes the various measures regarding nuclear safety and radiation protection, reports nuclear events which are classified according to the INES scale and occurred and had to be declared in 2012, describes the management of effluents by the different installations present on this site and the control of the environment. It addresses the waste management and the management of other impacts. It gives an overview of actions undertaken regarding information and transparency. Recommendations of the CHSCT are reported

Regulatory oversight report 2007 concerning nuclear safety in Swiss nuclear installations

International Nuclear Information System (INIS)

2008-04-01

This annual report issued by the Swiss Federal Nuclear Inspectorate (HSK) reports on the work carried out by the Inspectorate in 2007. This report reviews the regulatory activities in the four Swiss nuclear power stations and in four further nuclear installations in various Swiss research facilities. It deals with topics such as operational details, technologies in use, radiation protection, radioactive wastes, emergency dispositions and personnel and provides an assessment of operations from the point of view of safety. Also, the transportation of nuclear materials - both nuclear fuels and nuclear wastes - is reported on. General topics discussed include probabilistic safety analyses and accident management. Finally, the disposal of nuclear wastes and work done in the rock laboratories in Switzerland is commented on

Social and economic implications of the installation of nuclear plants

International Nuclear Information System (INIS)

Olivetti, F.A.

1981-01-01

This chapter summarizes the Italian experience with the evaluation, control, and containment of the social and economic impacts of nuclear power plant installations. Social and economic impact is defined as a set of causal relationships, direct and indirect, which are established between a nuclear plant and a surrounding territory. A nuclear plant imposes certain permanent restrictions in the use of the surrounding territory. The utilization of particularly dangerous substances requires that the plants be sited at a due distance from large urban centers and industrial areas. Therefore they are located in rural areas where the social and economic equilibria are less stable and more easily subjected to disturbances from outside factors. Essential services which must be provided for nonresident workers during the construction phase result in massive impacts which are compensated by the inflow of economic resources into the community. Social tension is also a likely consequence of importing workers into a community. There are disruptive effects induced by the high salaries paid to the construction workers such as local inflation. During the operating phase, the impacts will be smaller in proportion to the construction phase. Examples of social and economic impacts of nuclear plants in Italy are cited

Seismic methodology in determining basis earthquake for nuclear installation

International Nuclear Information System (INIS)

Ameli Zamani, Sh.

2008-01-01

Design basis earthquake ground motions for nuclear installations should be determined to assure the design purpose of reactor safety: that reactors should be built and operated to pose no undue risk to public health and safety from earthquake and other hazards. Regarding the influence of seismic hazard to a site, large numbers of earthquake ground motions can be predicted considering possible variability among the source, path, and site parameters. However, seismic safety design using all predicted ground motions is practically impossible. In the determination of design basis earthquake ground motions it is therefore important to represent the influences of the large numbers of earthquake ground motions derived from the seismic ground motion prediction methods for the surrounding seismic sources. Viewing the relations between current design basis earthquake ground motion determination and modem earthquake ground motion estimation, a development of risk-informed design basis earthquake ground motion methodology is discussed for insight into the on going modernization of the Examination Guide for Seismic Design on NPP

Annual Report 1998 concerning the nuclear safety and radiological protection in the Swiss nuclear installations

Energy Technology Data Exchange (ETDEWEB)

NONE

1999-05-01

The report presents detailed information about the nuclear safety and radiological protection in the Swiss nuclear power plants, the central interim storage at Wuerenlingen, the Paul Scherrer Institute (PSI) and other nuclear installations in Switzerland.

Annual Report 1998 concerning the nuclear safety and radiological protection in the Swiss nuclear installations

International Nuclear Information System (INIS)

1999-05-01

The report presents detailed information about the nuclear safety and radiological protection in the Swiss nuclear power plants, the central interim storage at Wuerenlingen, the Paul Scherrer Institute (PSI) and other nuclear installations in Switzerland

Annual Report 1999 concerning the nuclear safety and radiological protection in the Swiss nuclear installations

International Nuclear Information System (INIS)

2000-08-01

The report presents detailed information about the nuclear safety and radiological protection in the Swiss nuclear power plants, the central interim storage at Wuerenlingen, the Paul Scherrer Institute (PSI) and other nuclear installations in Switzerland

Annual Report 1999 concerning the nuclear safety and radiological protection in the Swiss nuclear installations

Energy Technology Data Exchange (ETDEWEB)

NONE

2000-08-15

The report presents detailed information about the nuclear safety and radiological protection in the Swiss nuclear power plants, the central interim storage at Wuerenlingen, the Paul Scherrer Institute (PSI) and other nuclear installations in Switzerland.

Study of the legal problems raised by the siting of nuclear power stations in artificial islands

International Nuclear Information System (INIS)

Hebert, J.; Guieze, J.L.

1975-01-01

The creation and operation of a nuclear power station on an artificial island in French waters are governed by domestic law and are subject to two types of procedure: the first concerns erection of the artificial island and the second the control of the public authorities over creation and operation of the nuclear power station. At administrative level, the setting up of an artificial island requires that it be attached to a commune as well as permission for occupancy from the maritime authorities. Furthermore, setting up of a nuclear power station on an artificial island is subject to the licensing procedure for large nuclear installations and to delivery of the licenses required for release of gaseous and liquid radioactive effluents. Given the proximity of the high seas and eventually, the borders of other States, siting of a nuclear power station on an artificial island imposes obligations at international level. These requirements, which concern prevention of transfrontier pollution, stem from the London (1972) and Paris (1974) Conventions on marine pollution. The third party liability regime for a nuclear incident caused by an installation sited in territorial seas is that of the 1960 Paris Convention on third party liability in the nuclear field and the 1963 Brussels Supplementary Convention. Another problem likely to be raised is that of the right of innocent passage of ships near such installations [fr

Annual report 1996 concerning the nuclear safety and radiological protection in the Swiss nuclear installations

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-05-01

The report presents detailed information about the nuclear safety and radiological protection in the Swiss nuclear power plants, the central interim storage at Wuerenlingen, the Paul Scherrer Institute (PSI) and other nuclear installations in Switzerland. figs., tabs., refs.

Annual report 1996 concerning the nuclear safety and radiological protection in the Swiss nuclear installations

International Nuclear Information System (INIS)

1997-05-01

The report presents detailed information about the nuclear safety and radiological protection in the Swiss nuclear power plants, the central interim storage at Wuerenlingen, the Paul Scherrer Institute (PSI) and other nuclear installations in Switzerland. figs., tabs., refs

Seismic risk and safety of nuclear installations. A look at the Cadarache Centre

International Nuclear Information System (INIS)

Verrhiest-Leblanc, G.; Chevallier, A.

2010-01-01

After a brief recall of some important seismic events which occurred in the past in the south-eastern part of France, the authors indicate the nuclear installations present in this region. They outline the difference between requirements for a usual building and for basic nuclear installations. They indicate laws and regulations which are to be applied to these installations like to any hazardous industrial installation. They describe the seismic risk as it has been determined for the Cadarache area, and evoke the para-seismic design of new nuclear installations which are to be built in Cadarache and actions for a para-seismic reinforcement of existing constructions. Finally, they evoke organisational aspects (emergency plans) and the approach for a better information and transparency about the seismic risk

Y2K bug and nuclear installations; Le passage a l'an 2000 sur les installations nucleaires

Energy Technology Data Exchange (ETDEWEB)

Anon

1999-10-01

Most nuclear installations except power plants, will be shut down on the eve of new year. By september 1999, EDF will have realized all the corrective and preventive actions that are necessary to pass Y2K. CEA has committed to present to safety authorities a complete report concerning preventive actions in its own basic nuclear installations. Safety authorities plan to organize a crisis center in order to face any problem. (A.C.)

International guidelines for fire protection at nuclear installations including nuclear fuel plants, nuclear fuel stores, teaching reactors, research establishments

International Nuclear Information System (INIS)

The guidelines are recommended to designers, constructors, operators and insurers of nuclear fuel plants and other facilities using significant quantities of radioactive materials including research and teaching reactor installations where the reactors generally operate at less than approximately 10 MW(th). Recommendations for elementary precautions against fire risk at nuclear installations are followed by appendices on more specific topics. These cover: fire protection management and organization; precautions against loss during construction alterations and maintenance; basic fire protection for nuclear fuel plants; storage and nuclear fuel; and basic fire protection for research and training establishments. There are numerous illustrations of facilities referred to in the text. (U.K.)

Offshore nuclear installations

International Nuclear Information System (INIS)

Albano, R.

1976-01-01

It is possible now to foresee the creation of nuclear power plants on floating or fixed islands although from the safety viewpoint, floating islands are preferable. The definition of the legal nature of artificial islands raises a first problem insofar as artificial islands are neither islands nor ships. Furthermore, their statute would differ according to whether they were sited in territorial seas or in the new 'economic zones'. This leads to consideration of the applicability of Italian maritime legislation to nuclear power plants on floating islands without setting aside that of international regulations on radioactive maritime pollution. (N.E.A.) [fr

Environmental assessment [of nuclear installations

International Nuclear Information System (INIS)

Townsley, M.

1989-01-01

The European Community has introduced a directive which instructs that for all projects likely to have a significant effect on the environment consent should only be given after a rigorous assessment of such effects has been carried out and presented as an environmental statement. Projects requiring environmental assessment include nuclear power stations, any thermal power station over 300MW, any radioactive waste storage or disposal facility, any installation which produces electricity, power lines, installations for fuel production, fuel reprocessing, radioactive waste processing and fuel enrichment. The statement must include a description of the likely effects, direct and indirect, on the environment of the development, with reference to human beings, flora, fauna, soil, water, air, climate, landscape, interactions of two or more of these, material assets and cultural heritage. Measures to avoid or remedy the impact must be included. (U.K.)

Characteristics of acoustic wave from atmospheric nuclear explosions conducted at the USSR Test Sites

Science.gov (United States)

Sokolova, Inna

2015-04-01

Availability of the acoustic wave on the record of microbarograph is one of discriminate signs of atmospheric (surface layer of atmosphere) and contact explosions. Nowadays there is large number of air wave records from chemical explosions recorded by the IMS infrasound stations installed during recent decade. But there is small number of air wave records from nuclear explosions as air and contact nuclear explosions had been conducted since 1945 to 1962, before the Limited Test Ban Treaty was signed in 1963 (the treaty banning nuclear weapon tests in the atmosphere, in outer space and under water) by the Great Britain, USSR and USA. That time there was small number of installed microbarographs. First infrasound stations in the USSR appeared in 1954, and by the moment of the USSR collapse the network consisted of 25 infrasound stations, 3 of which were located on Kazakhstan territory - in Kurchatov (East Kazakhstan), in Borovoye Observatory (North Kazakhstan) and Talgar Observatory (Northern Tien Shan). The microbarograph of Talgar Observatory was installed in 1962 and recorded large number of air nuclear explosions conducted at Semipalatinsk Test Site and Novaya Zemlya Test Site. The epicentral distance to the STS was ~700 km, and to Novaya Zemlya Test Site ~3500 km. The historical analog records of the microbarograph were analyzed on the availability of the acoustic wave. The selected records were digitized, the database of acoustic signals from nuclear explosions was created. In addition, acoustic signals from atmospheric nuclear explosions conducted at the USSR Test Sites were recorded by analogue broadband seismic stations at wide range of epicentral distances, 300-3600 km. These signals coincide well by its form and spectral content with records of microbarographs and can be used for monitoring tasks and discrimination in places where infrasound observations are absent. Nuclear explosions which records contained acoustic wave were from 0.03 to 30 kt yield for

Control of the Saclay CEA's base nuclear installations - Inspection n. INS-2010-CEASAC-0006 31 May 2010-4 June 2010 - Safety management

International Nuclear Information System (INIS)

2010-01-01

This document reports an inspection dedicated to safety management, and performed by the ASN (the French Nuclear Safety Authority) on several nuclear installations present on the CEA's Saclay site. The inspected installations have been the INBs (base nuclear installations) number 35 (STEL), 40 (Osiris), 49 (LHA), 50 (LECI), 77 (Poseidon) and 101 (Orphee), and four departments (CCSIMN, USL2TI, SP2S and DANS) involved in safety or in charge of it. The report describes the requested corrective actions about the quality of the internal diagnosis, about the follow-up of actions and directives, about internal authorizations, about the follow-up of commitments, about second level control, about the management of the return on experience, about interesting events, about the control of subcontractors. Some additional information requests are also formulated

Establishment of the nuclear regulatory framework for the process of decommissioning of nuclear installations in Mexico

International Nuclear Information System (INIS)

Salmeron V, J. A.; Camargo C, R.; Nunez C, A.

2015-09-01

Today has not managed any process of decommissioning of nuclear installations in the country; however because of the importance of the subject and the actions to be taken to long term, the Comision Nacional de Seguridad Nuclear y Salvaguardias (CNSNS) in Mexico, accordance with its objectives is developing a National Nuclear Regulatory Framework and defined requirements to ensure the implementation of appropriate safety standards when such activities are performed. In this regard, the national nuclear regulatory framework for nuclear installations and the particular case of nuclear power reactors is presented, as well as a proposed licensing process for the nuclear power plant of Laguna Verde based on international regulations and origin country regulations of the existing reactors in nuclear facilities in accordance with the license conditions of operation to allow to define and incorporate such regulation. (Author)

The siting of UK nuclear reactors.

Science.gov (United States)

Grimston, Malcolm; Nuttall, William J; Vaughan, Geoff

2014-06-01

Choosing a suitable site for a nuclear power station requires the consideration and balancing of several factors. Some 'physical' site characteristics, such as the local climate and the potential for seismic activity, will be generic to all reactors designs, while others, such as the availability of cooling water, the area of land required and geological conditions capable of sustaining the weight of the reactor and other buildings will to an extent be dependent on the particular design of reactor chosen (or alternatively the reactor design chosen may to an extent be dependent on the characteristics of an available site). However, one particularly interesting tension is a human and demographic one. On the one hand it is beneficial to place nuclear stations close to centres of population, to reduce transmission losses and other costs (including to the local environment) of transporting electricity over large distances from generator to consumer. On the other it is advantageous to place nuclear stations some distance away from such population centres in order to minimise the potential human consequences of a major release of radioactive materials in the (extremely unlikely) event of a major nuclear accident, not only in terms of direct exposure but also concerning the management of emergency planning, notably evacuation.This paper considers the emergence of policies aimed at managing this tension in the UK. In the first phase of nuclear development (roughly speaking 1945-1965) there was a highly cautious attitude, with installations being placed in remote rural locations with very low population density. The second phase (1965-1985) saw a more relaxed approach, allowing the development of AGR nuclear power stations (which with concrete pressure vessels were regarded as significantly safer) closer to population centres (in 'semi-urban' locations, notably at Hartlepool and Heysham). In the third phase (1985-2005) there was very little new nuclear development, Sizewell

Safety culture in nuclear installations. Proceedings

Energy Technology Data Exchange (ETDEWEB)

Carnino, A [ed.; International Atomic Energy Agency, Vienna (Austria); Weimann, G [ed.; Oesterreichisches Forschungszentrum Seibersdorf GmbH (Austria)

1995-04-01

These proceedings of the International Topical Meeting on Safety Culture in Nuclear Installations held in Vienna, Austria from 24 to 28 April 1995 provide a wide forum of information exchange and discussions on the topic safety culture in nuclear power plants. Safety culture deals with human factors since it deals with attitudes, organization and management. It then means that it has a natural component in it which is linked to the national culture and education. There are about 95 contributions, some of them presented by title and abstract only. All of them are in the subject scope of INIS. (Botek).

Safety culture in nuclear installations. Proceedings

International Nuclear Information System (INIS)

Carnino, A.; Weimann, G.

1995-04-01

These proceedings of the International Topical Meeting on Safety Culture in Nuclear Installations held in Vienna, Austria from 24 to 28 April 1995 provide a wide forum of information exchange and discussions on the topic safety culture in nuclear power plants. Safety culture deals with human factors since it deals with attitudes, organization and management. It then means that it has a natural component in it which is linked to the national culture and education. There are about 95 contributions, some of them presented by title and abstract only. All of them are in the subject scope of INIS. (Botek)

Application of nuclear power station design criteria to non-nuclear installations

International Nuclear Information System (INIS)

Regan, J.D.; Hughes, D.J.

1989-01-01

The nuclear industry is multi faceted, in that it includes large and complex chemical plants, a large number of different types of nuclear power stations, and on shore ship maintenance facilities, each with its own unique problems. Since the early days the industry has been aware of the additional problem which is superimposed on what may be classed as traditional fire risks, that is, the risk of an uncontrolled release of radioactivity. This has led to the development of sophisticated fire prevention and control techniques which are applied to new plants, and to the backfitting of older plants. The techniques of analysis, design and operation can be applied to both nuclear and non-nuclear installations. Passive protection is preferred backed up by active techniques. Segregation of essential plant to increase the probability of sufficient surviving to ensure safety systems operate and the provision of smoke free, protected escape routes are important aspects of layout and design. Reliability assessments, venting of smoke and hot gases, fire severity analysis, application of mathematical models contribute to the final design to protect against fires. Experiences built up in the fire fighting profession is integrated into the numerical approach by frequent involvement of the local Fire Officers at each stage of the design and layout of installations. (author)

Quality assurance in nuclear installations

International Nuclear Information System (INIS)

Torres M, Nelson.

1985-08-01

It has been proven that the bad quality of products, equipment, installations, and services is not due to the lack of tests, experiments and verifications. The main causes are associated with insufficient organization of the activities that have influence on the quality. The garantee of quality is conceptualized as an appropriate instrument composed of normalized criteria initially in advanced technologies. Such as nuclear science and aerospace technology. However, with the appropriate modifications it can be applied to conventional technologies

The Choice of Sites for the First Nuclear Power Plants in Brazil

International Nuclear Information System (INIS)

Cintra do Prado, L.

1966-01-01

In selecting the sites for nuclear power plants a decision has to be taken as to (1) which area of the country is best suited for the purpose - e.g. the area of Recife, Rio or Sao Paulo, etc. - given the trend in energy requirements and the availability of resources, and (2) where to site the plant or plants within that area. In this paper I shall concentrate on the first of these problems and shall be concerned with assessing the merits and demerits of installing nuclear power plants in certain regions of Brazil which seem particularly well suited for the purpose

Optimal Procedure for siting of Nuclear Power Plant

International Nuclear Information System (INIS)

Aziuddin, Khairiah Binti; Park, Seo Yeon; Roh, Myung Sub

2013-01-01

This study discusses on a simulation approach for sensitivity analysis of the weights of multi-criteria decision models. The simulation procedures can also be used to aid the actual decision process, particularly when the task is to select a subset of superior alternatives. This study is to identify the criteria or parameters which are sensitive to the weighting factor that can affect the results in the decision making process to determine the optimal site for nuclear power plant (NPP) site. To perform this study, we adhere to IAEA NS-R-3 and DS 433. The siting process for nuclear installation consists of site survey and site selection stages. The siting process generally consists of an investigation of a large region to select one or more candidate sites by surveying the sites. After comparing the ROI, two candidate sites are compared for final determination, which are Wolsong and Kori site. Some assumptions are taken into consideration due to limitations and constraints throughout performing this study. Sensitivity analysis of multi criteria decision models is performed in this study to determine the optimal site in the site selection stage. Logical Decisions software will be employed as a tool to perform this analysis. Logical Decisions software helps to formulate the preferences and then rank the alternatives. It provides clarification of the rankings and hence aids the decision makers on evaluating the alternatives, and finally draw a conclusion on the selection of the optimal site

Optimal Procedure for siting of Nuclear Power Plant

Energy Technology Data Exchange (ETDEWEB)

Aziuddin, Khairiah Binti; Park, Seo Yeon; Roh, Myung Sub [KEPCO International Nuclear Graduate School, Ulsan (Korea, Republic of)

2013-10-15

This study discusses on a simulation approach for sensitivity analysis of the weights of multi-criteria decision models. The simulation procedures can also be used to aid the actual decision process, particularly when the task is to select a subset of superior alternatives. This study is to identify the criteria or parameters which are sensitive to the weighting factor that can affect the results in the decision making process to determine the optimal site for nuclear power plant (NPP) site. To perform this study, we adhere to IAEA NS-R-3 and DS 433. The siting process for nuclear installation consists of site survey and site selection stages. The siting process generally consists of an investigation of a large region to select one or more candidate sites by surveying the sites. After comparing the ROI, two candidate sites are compared for final determination, which are Wolsong and Kori site. Some assumptions are taken into consideration due to limitations and constraints throughout performing this study. Sensitivity analysis of multi criteria decision models is performed in this study to determine the optimal site in the site selection stage. Logical Decisions software will be employed as a tool to perform this analysis. Logical Decisions software helps to formulate the preferences and then rank the alternatives. It provides clarification of the rankings and hence aids the decision makers on evaluating the alternatives, and finally draw a conclusion on the selection of the optimal site.

Planned reliability in the transport and installation of large nuclear components

International Nuclear Information System (INIS)

Bieler, L.

1988-01-01

The transport and installation of heavy and bulky large components require detailed planning of all jobs and activities, trained and experienced personnel and corresponding technical equipment for reliable and quality-assured implementation. The correct approach to the planning and implementation of such transports and installations has been confirmed by years of successful performance of these jobs e.g. in reactor pressure vessels and steam generators for nuclear power plants. Large components for nuclear power plants are truly extreme examples but will be all the better suited for demonstrating the problems inherent in transport and installation. (orig.) [de

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

Energy Technology Data Exchange (ETDEWEB)

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

2013-07-01

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

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

A study on the nuclear computer codes installation and management system

International Nuclear Information System (INIS)

Kim, Yeon Seung; Huh, Young Hwan; Kim, Hee Kyung; Kang, Byung Heon; Kim, Ko Ryeo; Suh, Soong Hyok; Choi, Young Gil; Lee, Jong Bok

1990-12-01

From 1987 a number of technical transfer related to nuclear power plant had been performed from C-E for YGN 3 and 4 construction. Among them, installation and management of the computer codes for YGN 3 and 4 fuel and nuclear steam supply system was one of the most important project. Main objectives of this project are to establish the nuclear computer code management system, to develop QA procedure for nuclear codes, to secure the nuclear code reliability and to extend techanical applicabilities including the user-oriented utility programs for nuclear codes. Contents of performing the project in this year was to produce 215 transmittal packages of nuclear codes installation including making backup magnetic tape and microfiche for software quality assurance. Lastly, for easy reference about the nuclear codes information we presented list of code names and information on the codes which were introduced from C-E. (Author)

S.I. 1987 No.688, The Nuclear Installations (Isle of Man) (Variation) Order 1987

International Nuclear Information System (INIS)

1987-01-01

This Order, which amends the Nuclear Installations (Isle of Man) Order 1977, came into force on 7 May 1987. The Nuclear Installations (Isle of Man) Order 1977 extends certain provisions of the Nuclear Installations Act 1965 as appropriate, to the Isle of Man. This Order extends amendments made to that Act by the Energy Act 1983 and the Congenital Disabilities (Civil Liability) Act 1976, as appropriate, to the Isle of Man. (NEA) [fr

On alteration of reactor installation (additional installation of No.3 and No.4 plants in the Genkai Nuclear Power Station, Kyushu Electric Power Co., Inc.)

International Nuclear Information System (INIS)

1985-01-01

The Nuclear Safty Commission sent the reply to the Minister of International Trade and Industry on October 4, 1984, on this matter after having received the report from the Committee on Examination of Nuclear Reactor Safety and carried out the deliberation. It was judged that the applicant has the technical capability required for installing and operating these reactor facilities. Also it was judged that on the safety after these reactor plants are installed, there is no obstacle in the prevention of disaster due to contaminated substances and reactors. The policy of the investigation and deliberation is reported. The contents of the investigation and deliberation are the condition of location such as site, geological features and ground, earthquake, weather, hydraulic problem and social environments, the safety design of reactor facilities, the evaluation of radiation exposure dose in normal operation, the analysis of abnormal transient change in operation, accident analysis and the evaluation of location. (Kako, I.)

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)

Nuclear Installation Safety: General Observations and Trends from IAEA Peer Reviews

International Nuclear Information System (INIS)

Rzentkowski, G.

2016-01-01

The Safety Review Services (SRSs) for nuclear installations address the needs of Member States at all stages of installations’ lifecycle. SRSs are based on the IAEA Safety Standards and are provided on Member States’ request to peer review national regulatory frameworks and safety provisions for nuclear installations. They result in recommendations and suggestions to improve national regulations and operational safety, and serve to exert peer pressure to ensure that that every Member State with nuclear installations recognizes its safety responsibility and the need to comply with the IAEA Safety Standards. This presentation provides an overview of SRSs for Nuclear Installations, including their structure and main subject areas. The presentation also summarizes general findings and trends which clearly demonstrate that there is continuous improvement in regulation of nuclear installations and in safety of their operation. Nevertheless, there is the need to further enhance the efficiency and effectiveness of SRSs through review of the overall governance model and service delivery to better serve the needs of Member States. The presentation points out some areas of improvements which have already been implemented or are being considered for implementation. Just as important, SRSs are conducted by teams of experts from around the world to strengthening international cooperation, ensure diversity and impartiality, and improve the overall quality of the safety review being conducted. The review team members are also provided with the opportunity for mutual learning and sharing good practices among themselves and with the Member State undergoing the review. As a result, SRAs play an important role in a quest to harmonize regulatory requirements and approaches globally. (author)

Protection of Basic Nuclear Installations Against External Flooding - Guide No. 13

International Nuclear Information System (INIS)

2013-01-01

The French regulations require that the flooding hazard be taken into consideration in the demonstration of nuclear safety of basic nuclear installations (BNI). This guide details the recommendations concerning the external flooding hazard which is defined, for the purpose of this guide, as being a flood whose origin is external to the structures, areas or buildings of the BNI accommodating systems or components to be protected, whatever the cause(s) of that flooding (rainfall, river spates, storms, pipes failures, etc.). An external flood therefore means any flood originating outside the perimeter of the BNI and certain floods originating within the BNI perimeter. The terms 'flood' or 'flooding' as used henceforth designate external flooding. The purpose of this guide is to: - define the situations to consider when assessing the flood hazard for the site in question; - propose an acceptable method of quantifying them; - list recommendations for defining means of protection adapted to the specifics of the flooding hazard, implemented by the licensee according to the life cycle phases of the installation. The guide has taken climate change into account when the state of knowledge so allows. It is necessary to take into account - on the basis of current knowledge - the predictable climate changes for a period representative of the installations' foreseeable life times, and until the next safety review. The use of this guide necessitates prior identification - for the installation in question - of the functions required to demonstrate nuclear safety and which shall be preserved in the event of flooding. These functions are called 'safety functions' in this guide. This guide applies to all the basic nuclear installations defined by article L. L.593-2 of the Environment Code. With regard to radioactive waste disposal installations, this guide only applies to above-ground facilities. This guide can be used to assess the external flooding hazards and the associated

Investigation And Mitigation Techniques Of Power Quality Problems In Nuclear Installations

International Nuclear Information System (INIS)

Ayad, N.; Elsherbiny, E.; Eleissawi, H.; Zaher, M.; AbdelSalam, G.

2013-01-01

The electrical power systems are exposed to different types of power quality disturbances problems. Investigation and monitoring of power quality is necessary to maintain accurate operation of sensitive equipment especially for nuclear installations. The present research discusses investigation and monitoring of power quality problems for the electrical sources of nuclear installations. Field power quality data is collected by power analyzer and analyzed with reference to power quality standards. There were several disturbances exceeded the thresholds, they were voltage harmonics and voltage flicker. Mitigation techniques were suggested to install a passive filter at low voltage side and all sensitive and critical loads should be isolated and fed through uninterruptible power supply (UPS)

Software for simulation of nuclear simulation of nuclear installations

International Nuclear Information System (INIS)

Castaneda, J.O.; Ramos, L.M.; Arjona, O.; Rodriguez, L.

1993-01-01

The software is an instrument to build conceptual-type simulators of low, medium and full scale for used in nuclear installations. The system is composed by composed by two basic modules: one for the edition and the other for the simulation. The first one allows to prepare the information to simulate: mathematical model, technological design (fundamentally, operation board or mnemotechnical design), parameters to be shown, failures to be simulated

Assessment of the radiological consequences in case of an emergency on a nuclear installation

International Nuclear Information System (INIS)

Manesse, D.; Crabol, B.

1988-04-01

The French Institute for Health Physics and Nuclear Safety (IPSN) has, for emergency cases on nuclear installations, an Emergency Technical Centre (Centre Technique de Crise - CTC) to provide the public authorities with the technical analysis of the events and with information concerning possible developments in terms of potential releases and radiological consequences to the environment. The CTC is connected, by a special line, to the French Meteorological Office so as to have access to meteorological parameters and local forecasts on the nuclear site at all times. For atmospheric dispersion and radiological consequences, three methods have been developed: a set of operational graphs (for first aid), a gaussian plume model and a gaussian puff model (SIROCCO); the latter two models are implanted on a VAX 8530 computer (with graphical monitors) reserved for that purpose [fr

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

International Nuclear Information System (INIS)

Mahrenholtz, Philipp; Eligehausen, Rolf

2015-01-01

Graphical abstract: - Highlights: • Review of qualification and design regulations for anchors in nuclear power plants. • First complete set of nuclear anchor load–displacement data and its evaluation ever. • Demonstration of robust test behavior of a qualified post-installed anchor product. - Abstract: In nuclear power plants (NPPs), post-installed anchors are widely used for structural and non-structural connections to concrete. In many countries, anchor products employed for safety relevant applications have to be approved by the authorities. For the high safety standards in force for NPPs, special requirements have to be met to allow for extreme design situations. This paper presents an experimental test program conducted to evaluate the performance of anchors according to the German Guideline for Anchorages in Nuclear Power Plants and Nuclear Technology Installations (DIBt KKW Leitfaden, 2010). After a brief introduction to anchor behavior and the regulative context, the results of tension and shear tests carried out on undercut anchors are discussed. Robust load capacities and relatively small displacements determined for demanding load and crack cycling tests demonstrated the suitability of anchors qualified according to a state-of-the-art qualification guideline

New experience on construction and installation work in Qinshan PHWR nuclear power plant

International Nuclear Information System (INIS)

Lu Huaxiang

2004-01-01

The article provides a summary of the new experience on construction management and construction technology in the field of civil construction and installation work in Qinshan PHWR nuclear power plant, with focus on innovation in project management mode, new technology application and computerized management of construction and installation work. Management innovation, technical innovation and information technology are the key contributors to overall success of Qinshan PHWR nuclear power plant in construction and installation work. The new experience derived in these fields will be of great significance to promote independent construction of the new-round nuclear power projects in China. (author)

Rules and regulations on ionizing radiations sources installations

International Nuclear Information System (INIS)

1980-01-01

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

Inventory of chemical releases of nuclear installations in the North-Cotentin

International Nuclear Information System (INIS)

2002-05-01

The nuclear installations concerned by this study are Cogema La Hague, the Flamanville nuclear power plant, the Manche plant and the National Navy of Cherbourg.The objective followed by the ' source term ' work group has consisted in counting and examining the whole of existing measures relative to the releases of chemical substances in the liquid and gaseous effluents. Then because of the lack of measures for the operation first years of installations, the work group has estimated the order of magnitude of these chemical releases (essentially for Cogema La Hague). This report presents a review of the literature looking at the background levels of chemicals in different environmental compartments: air, soil, plants and animals products. these values have been summarized here to be available for comparisons with concentrations input by the North Cotentin nuclear installations, calculated by the G.R.N.C. (radioecology group of Nord Cotentin)

Decree No. 83/7405 of 18 November 1983 on the licensing procedure for nuclear installations

International Nuclear Information System (INIS)

1983-01-01

This Decree (No. 83/7405) on the licensing procedure for nuclear installations came into force on 19 December 1983 and supersedes Decree No. 7/9141 of 5 December 1974 on the same subject. The general lines of the licensing procedure laid down by this new Decree are similar to that provided by the 1979 Decree; it is also carried out in three stages: site, construction and operating licences are delivered in succession. (NEA) [fr

Study of a brazilian cask and its installation for PWR spent nuclear fuel dry storage

International Nuclear Information System (INIS)

Romanato, Luiz Sergio

2009-01-01

Spent nuclear fuel (SNF) is removed from the nuclear reactor after the depletion on efficiency in generating energy. After the withdrawal from the reactor core, the SNF is temporarily stored in pools at the same site of the reactor. At this time, the generated heat and the short and medium lived radioactive elements decay to levels that allow removing SNF from the pool and sending it to temporary dry storage. In that phase, the fuel needs to be safely and efficiently stored, and then, it can be retrieved in a future, or can be disposed as radioactive waste. The amount of spent fuel increases annually and, in the next years, will still increase more, because of the construction of new nuclear plants. Today, the number of new facilities back up to levels of the 1970's, since it is greater than the amount of decommissioning in old installations. As no final decision on the back-end of the nuclear fuel cycle is foreseen in the near future in Brazil, either to recover the SNF or to consider it as radioactive waste, this material has to be isolated in some type of storage model existing around the world. In the present study it is shown that dry SNF storage is the best option. A national cask model for SNF as well these casks storage installation are proposed. It is a multidisciplinary study in which the engineering conceptual task was developed and may be applied to national SNF removed from the Brazilian power reactors, to be safely stored for a long time until the Brazilian authorities will decide about the site for final disposal. (author)

International Co-operation in providing insurance cover for nuclear damage to third parties and for damage to nuclear installations

International Nuclear Information System (INIS)

Deprimoz, Jacques

1983-01-01

This article in three parts analyses cover for damage to third parties by fixed nuclear installations, cover for damage to third parties during transport of nuclear substances and finally, cover for damage to nuclear installations. Part I reviews the principles of nuclear third party liability and describes nuclear insurance pools, the coverage and contracts provided. Part II describes inter alia the role of pools in transport operations as well as the type of contracts available, while Part III discusses material damage, the pools' capacities and the vast sums involved in indemnifying such damage. (NEA) [fr

Lifetime Evaluation of PV Inverters considering Panel Degradation Rates and Installation Sites

DEFF Research Database (Denmark)

Sangwongwanich, Ariya; Yang, Yongheng; Sera, Dezso

2017-01-01

The PV inverter lifetime is affected by the installed sites related to different solar irradiance and ambient temperature profiles. In fact, the installation site also affects the PV panel degradation rate, and thus the long-term power production. Prior-art lifetime analysis in PV inverters has...... not yet investigated the impact of panel degradation. This paper thus evaluates the lifetime of PV inverters considering panel degradation rates and installation sites. Evaluations have been carried out on PV systems installed in Denmark and Arizona. The results reveal that the PV panel degradation rate...... has a considerable impact on the PV inverter lifetime, especially in the hot climate (e.g., Arizona), where the panel degrades at a faster rate. In that case, the PV inverter lifetime estimation can be deviated by 54%, if the impact of PV panel degradation is not taken into account....

Technical and legal aspects of the decommissioning of nuclear installations

International Nuclear Information System (INIS)

Rowden, M.A.; Fowler, S.E.

1983-01-01

Many of the plants licensed at the start of nuclear power programmes will require decommissioning in the 1990's and this issue should now be confronted by the nuclear industry, its regulators and governments. This paper deals with the United States programme and experience in the decommissioning of nuclear installations and describes alternative decommissioning methods including safety and financial aspects. (NEA) [fr

Procedures for permission of installation of nuclear power stations

International Nuclear Information System (INIS)

Narita, Yoriaki

1980-01-01

The locations of atomic power stations are first selected by electric power enterprises in consultation with the Ministry of International Trade and Industry or under the guidance of authorities concerned. The surveys of the climate, topography, water and plants in the planned sites and the influences of nuclear power generation to the surrounding areas are made by the enterprisers under the administrative guidance of the MITI. Secondly, the basic project shall be submitted to and decided by the Power Resource Development Council headed by the Prime Minister (Article 10, the Power Resource Development Law). The Council shall, if necessary, call for the attendance of the governors of prefectures concerned and hear their opinions (Article 11, the Law). As the third and most complicated phase, various procedures include; (a) permission of the changes of electrical facilities under the Electricity Enterprises Act; (b) authorization of the installation of reactors under the Nuclear Reactor Regulation Law; (c) permission or authorization under other regulations including the Agricultural Land Act, etc.; (d) additional procedures related to the indemnification to fishery and so forth. Finally the reactors are to be operated after receiving the certificates of the Minister of ITI on the inspections of construction works, nuclear fuel materials used for the reactors and welding processes of reactor containment vessels, boilers, turbines, etc. (Okada, K.)

Liabilities identification and long-term management decommissioning of nuclear installations in Slovak Republic

International Nuclear Information System (INIS)

Burclova, Jana; Konecny, Ladislav

2003-01-01

The decommissioning is defined as the safe removal of nuclear facilities from service and reduction of residual radioactivity and/or risk to a level enabling their use for the purpose of another nuclear facility or unrestricted use (site release) and termination of license. The Legal Basis for Decommissioning and Waste Management are described in 4 acts: - 1. Act 130/98 Coll. on peaceful use of nuclear energy (Atomic Act); - 2. The act No 127/1994 Coll. on environmental impact assessment (amended 2000); - 3. The act No 254/1994 Coll. on creation of state found for NPP decommissioning, spent fuel management and disposal investment (amended 2000, 2001); 4. The act No 272/1994 Coll. on protection of public health (amended 1996,2000). The licensing process for radioactive waste management installations as for all nuclear installations is running in following principal steps. The permits for siting, construction, operation including commissioning, individual steps of decommissioning and site release are issued by municipal environmental office on the basis of the Act No 50/1976 Coll. on territorial planning and construction rules and the decisions of the Nuclear regulatory Authority (UJD SR) based on the Atomic Act. The safety documentation shall be prepared by applicant and it is subject of the regulatory bodies approval, for nuclear safety is responsible UJD SR, for radiation protection Ministry of Health, for fire protection Ministry of Interior and for general safety Ministry of Labour, Social Policy and Family. UJD SR issues the permit for each decommissioning phase based on review and approval of safety documentation. Decommissioning Strategy of Slovak Republic was strongly influenced by the changes of Waste Management Strategy. During the last time UJD SR dedicated the great effort to principal improvement of legislation, to cooperation with Ministry of Economy with the aim to create rules for financial sources for decommissioning activities and to enforcement of

Days of dismantling activities of installations and rehabilitation of contaminated sites in France

International Nuclear Information System (INIS)

2008-01-01

The objective of these days, organized by the section environment of the French society of radiation protection, is to present a panorama of the activities of nuclear installations dismantling and contaminated sites rehabilitation in France, by leaning in the same time on practical cases and by stating the French rule and the national and international recommendations on the subject. These days have also for object to approach the stakes associated with the sectors of waste management and the materials generated by these activities and in a more general way, the stakes to come for the different actors of the dismantling and the rehabilitation. (N.C.)

Siting of nuclear facilities. Selections from Nuclear Safety

Energy Technology Data Exchange (ETDEWEB)

Buchanan, J.R.

1976-07-01

The report presented siting policy and practice for nuclear power plants as developed in the U.S. and abroad. Twenty-two articles from Nuclear Safety on this general topic are reprinted since they provide a valuable reference source. The appendices also include reprints of some relevant regulatory rules and guides on siting. Advantages and disadvantages of novel siting concepts such as underground containment, offshore siting, and nuclear energy parks are addressed. Other topics include site criteria, risk criteria, and nuclear ship criteria.

Siting of nuclear facilities. Selections from Nuclear Safety

International Nuclear Information System (INIS)

Buchanan, J.R.

1976-07-01

The report presented siting policy and practice for nuclear power plants as developed in the U.S. and abroad. Twenty-two articles from Nuclear Safety on this general topic are reprinted since they provide a valuable reference source. The appendices also include reprints of some relevant regulatory rules and guides on siting. Advantages and disadvantages of novel siting concepts such as underground containment, offshore siting, and nuclear energy parks are addressed. Other topics include site criteria, risk criteria, and nuclear ship criteria

The regulation of radioactive effluent release in France (mainly from large nuclear installations)

International Nuclear Information System (INIS)

Hebert, Jean.

1978-01-01

In parallel with the licensing system for construction and operation of classified or so-called large nuclear installations (INB) there are in France regulations for the release of radioactive effuents from such installations. The regulations applicable to installations other than INBs are not specifically of a nuclear nature, while those covering INBs, which are analysed in this study, in particular, cover effluent release in liquid or gaseous form. The licensing and control procedures for such release are analysed in detail. (NEA) [fr

Strategic considerations for the sustainable remediation of nuclear installations.

Science.gov (United States)

Mobbs, S; Orr, P; Weber, I

2017-08-05

Nuclear sites around the world are being decommissioned and remedial actions are being undertaken to enable the sites or parts of the sites to be reused. Although this is relatively straightforward for most sites, experience has suggested that preventative action is needed to minimise the impact of remediation activities on the environment and the potential burden to future generations. Removing all contamination in order to make a site suitable for any use generates waste and has associated environmental, social and economic detriments and benefits that should be taken into account. Recent experience of OECD Nuclear Energy Agency (NEA) member countries in the remediation of contaminated land, predominantly contaminated soil and groundwater, on nuclear sites during decommissioning has been assessed by an NEA task group. The experience was used to identify strategic considerations for nuclear site remediation, to consider the application of sustainability principles to nuclear site remediation, to describe good practice, and to make recommendations for further research and development. The key aspects that were identified were that 1) site remediation should be sustainable by resulting in an overall net benefit; and 2) an adaptive approach is essential in order to take into account the inherent uncertainty associated with the decommissioning and site remediation timescales. A report describing the findings was published by OECD/NEA in 2016. The conclusions provide insights to decision makers, regulators, implementers and stakeholders involved in nuclear site decommissioning so that they can achieve sustainable remediation of nuclear sites, now and in the future. Copyright © 2017 Elsevier Ltd. All rights reserved.

Atomic Energy and Radioactive Substances. The Nuclear Installations (Isle of Man) Order 1977

International Nuclear Information System (INIS)

1977-01-01

This Order extends to the Isle of Man, with the exceptions, adaptations and modifications specified in the Schedule, those provisions of the Nuclear Installations Act 1965, as amended, which relate to the duty in respect of the carriage of nuclear matter, to the right to compensation for breach of that duty and to the bringing and satisfaction of claims. Under the Nuclear Installations Act, the duty of the operator is to secure that no nuclear occurrence taking place within the realm of the Act causes injury to persons or damage to property. (NEA) [fr

Safety of nuclear installations. An international comparison

International Nuclear Information System (INIS)

Renner, Andrea; Diwes, Andreas; Reingardt, Martin

2010-01-01

Safeguarding of nuclear power plants against disruptive actions or other external hazards is part of the plant design and presumption of an operation license. The general principle is defense in depth involving different security zones with separate barriers. The safeguards for nuclear installations are organized in three areas of responsibility: governmental measures (police, military), technical (detectors, scanners, illuminations, camera tracking, concrete barriers) and personnel measures (access control, security personnel, alarm) of the operating company. International responsibilities results from the treaty on the non-proliferation of nuclear weapons and several IAEA documents. The authors discuss the national regulations in Germany, Switzerland, United Kingdom and USA. Older NPPs that are not in compliance with actual safety standards will be a topic of increasing importance.

Remote installation of risers on underground nuclear waste storage tanks

International Nuclear Information System (INIS)

Jackson, J.P.; Gessner, R.F.

1988-03-01

The West Valley Demonstration Project was established to solidify 2120 m 3 (560,000) gallons of high-level nuclear waste generated during six years of commercial nuclear fuel reprocessing. This liquid will be processed to remove radioactive elements which, with the remaining sludge, will be combined with glass formers and be converted into borosilicate glass. Risers were installed on the high-level tank for installation of pumps which will be used to remove the liquid and sludge. The extensive use of remote technology was required to install the risers and to minimize operator exposure to high levels of radiation and contamination. The riser installation required remotely: drilling through two feet of concrete shielding; installing pump access pipes which are welded to the tank top; and cutting holes in tanks located 3658 mm (12) feet below ground. These operations were successfully completed 13 times without exposing personnel to high-level radiation or contamination. Specially designed remote equipment was developed for each step of this operation. Extensive operator training in the use of this equipment was performed on a tank with low radiation prior to work on the high-level tank. This paper discusses the application of remote technology that assured a quality job was safely accomplished. 3 refs., 18 figs., 2 tabs

Management of procurement activities in a nuclear installation

International Nuclear Information System (INIS)

1996-12-01

Discussions held within the framework of IAEA regional technical co-operation projects implemented in the Latin America, Asia-Pacific and eastern Europe regions revealed an area of frequent difficulties related to the proper control, by the management of nuclear utilities, of the effective fulfilment of contractual quality and safety requirements. Evaluation of the results of a number of OSART missions has also pointed to a need for improving the control that some utilities exercise on their suppliers. The IAEA was thus prompted to initiate the development of a technical document providing guidance on these subjects. In October 1995, a consultants meeting was convened to determine the target users of the technical document and to develop the scope, contents, structure and the reference material. A first draft was then prepared. An Advisory Group meeting consisting of experts from 17 Members States was held in Vienna in May 1996 to review and complete the draft. The technical document is intended to provide practical guidance on controlling procurement, with supporting information for senior management, line managers and line supervisors in a nuclear installation. Although the guidance is structured to address the needs during the operating stage of a nuclear power plant, much of the material is also applicable to the construction and decommissioning stages and to other nuclear installations. 1 fig

History of creation of Semipalatinsk test nuclear site. Chapter 1

International Nuclear Information System (INIS)

1999-01-01

In 1949 August USSR's Government adopted decision about creation of nuclear site with conditional name Uchebnyj polygon 2. For its building was chosen territory in 140 km from Semipalatinsk city. Semipalatinsk test site consists of the land of three regions: Semipalatinsk, Pavlodar, Karaganda and it occupies 18,500 km 2 of fertile land, rich with minerals. Now this territory was alienated from national using. Polygon was complex object and it incorporated three main zones: Opytnoe Pole, zone of radiation safety, site Sh. Opytnoe Pole was equipped by special constructions ensuring nuclear test conducting, its observing and registration of physical measurements and occupied 2,300 km 2 . Around of the Opytnoe Pole is situated zone of radiation safety with area 45 thousand ha. Site Sh was situated in 14 km from center of Opytnoe Pole and it was intended for distribution of individual protection devices, dosimeters and for conducting of dis-activation and sanitary works. History of the site creation is connected with building of Kurchatov city. In dozen and hundred of kilometers from Kurchatov city there were top secret objects: site Balapan with total area 100,000 ha intended for conducting of nuclear tests in wells with threshold capacity 100-200 kt. Here simultaneously with main problems on the site the military-applied works were conducted on mechanics, physics of combustion, simulation of Earthquakes and determination of seismic stability of buildings and constructions. Research site Degelen with total area 33,100 ha which has been used for underground testing of nuclear charges with small capacity. Site 10 one of large research technical complex on which two reactor units were installed. Main tasks of the complex were as follows: high-temperature fuel materials testing, conducting of fundamental researches in field of physics of fissile products, thermal physics and gas hydrodynamics. On site M a laboratory base for radiochemical, radiological and chemical

Evaluation and surveillance of radioactive releases of nuclear installations

International Nuclear Information System (INIS)

Hartmann, Ph.

2002-01-01

The two days organised by the section Environment of the SFRP have to objective to connect experts in radiation protection in order to debate around the following questions: the actual evaluations modes of releases impacts from nuclear installations, the organisation of the surveillance, to favour the implication of local actors in the evaluation and surveillance around nuclear facilities, the evolutions to envisage. (N.C.)

Nuclear relevant installations licensing methodology in the Argentine Republic

International Nuclear Information System (INIS)

Paganini, C.E.

1986-01-01

A review of the requeriments of the Nuclear Installations Advisory Committee on Licensing (CALIN) from the nuclear security point of view, is presented. The methodology applied by the CALIN for the licensing in the Argentine Republic is included as well as codes, standards of applications and the interaction between the licensing Authority and the Responsible Entity during the whole process. Finally, the Atucha II nuclear power plant's licensing, in construction at present, is explained and the standard, of the licensing schedule, is presented graphically. (author) [es

The Role of Tectonic and Seismicity in Siting of Nuclear Power Plant

International Nuclear Information System (INIS)

Abdel Aziz, M.A.H.

2008-01-01

The site selection for the a nuclear power plant (NPP) is controlled by many criteria. One of the most important criterion is the tectonic and seismicity of the site and its surroundings. Since, it is preferable the site in concern is characterized by low tectonic and low seismicity to avoid the damage effects associated with the occurrence of destructive earthquakes. The investigation of the tectonic and seismicity maps of egypt has been carried out to candidate potential areas or sites for nuclear power plant installation from seismicity point of view. Also, the design basis ground motion in terms of peak ground acceleration and response spectra of some of the potential sites are defined through the conduct of probabilistic seismic hazard analysis The study revealed that although there is no criterion to exclude areas of high tectonic and high seismicity as potential sites for nuclear power plant installation but, it is preferable avoiding such areas. This is attributed to the critical seismic curve that characterizes such areas and is required high seismic design levels to resist the destructive vibratory ground motion associated with the expected earthquake. Consequently, the required high seismic design levels will have a negative impact on the economic cost of the facility compared with that built in low and moderate seismic areas. Hence, areas like the gulf of suez, the northern part of the Red Sea and the southern part of Sinai Peninsula should be avoided as potential sites for NPP from the tectonic and seismicity point of view. On the other hand, areas like Nile delta and its valley, the Northern and Southern parts of Western desert and the central and southern parts of the Eastern Desert should be candidate as potential sites on condition, the other criteria meet the IAEA's regulations. Also, the seismic hazard curve of the Northwest littoral zone reflects low design basis ground motion values compared with the Nile delta region

Studies of works management and automation of nuclear power installations

International Nuclear Information System (INIS)

Besch, P.; Grossmann, J.; Hollasky, R.

1989-01-01

Erection and operation of nuclear power installations require investigations on their safety and availability. The works performed on the management of nuclear power plants and nuclear heating stations in the Working Group on Automation Engineering of the Dresden University of Technology are presented. Emphasis of the works is on simulation of dynamical performance of the plants and studies on the utilization of novel techniques concerning plant automation and process management. (author)

Concerning installation of reactor at Noto nuclear power plant of Hokuriku Electric Power Co., Inc. (reply to inquiry)

International Nuclear Information System (INIS)

1988-01-01

In response to an inquiry on the conformity of the title issue to the applicable law concerning nuclear material, nuclear fuel and nuclear reactor, the Nuclear Safety Commission ordered the Nuclear Reactor Safety Expert Group to make a study, made an examination after receiving a report from the Group, and submit the findings to the Minister of International Trade and Industry. The study on the site conditions covered the site location, geology, effects or earthquakes, meteorology, hydrology and social environment. The study on the safety design of the reactor covered the design of the facilities as a whole, anti-earthquake design, reactor, instrumentation, reactor shutdown system, reactivity control, protection, cooling system, reactor vessel, fuel handling, fuel storage, and radiation control. The study also included exposure evaluation, abnormal transient state analysis and accident analysis. It is concluded that the relevant company has a technical capability required for the installation and proper operation of the reactor in question, and that the reactor will have adequate safety with no possibility of causing a disaster. (Nogami, K.)

Cancer risks near nuclear installations?

International Nuclear Information System (INIS)

Hubert, D.

1999-01-01

The descriptive studies actually at disposal bring to the fore some children leukemia aggregates around some nuclear sites. (Sellafield, and Dounreay in the United kingdom, Kruemmel in Germany). Nevertheless, the studies grouping several sites do not find any global excess. The analytical studies have not brought any answer until now, but have allowed to eliminate some hypothesis such the Gardner genetic hypothesis. (N.C.)

Inventory of chemical releases of nuclear installations in the North-Cotentin; Inventaire des rejets chimiques des installations nucleaires du Nord-Cotentin

Energy Technology Data Exchange (ETDEWEB)

NONE

2002-05-15

The nuclear installations concerned by this study are Cogema La Hague, the Flamanville nuclear power plant, the Manche plant and the National Navy of Cherbourg.The objective followed by the ' source term ' work group has consisted in counting and examining the whole of existing measures relative to the releases of chemical substances in the liquid and gaseous effluents. Then because of the lack of measures for the operation first years of installations, the work group has estimated the order of magnitude of these chemical releases (essentially for Cogema La Hague). This report presents a review of the literature looking at the background levels of chemicals in different environmental compartments: air, soil, plants and animals products. these values have been summarized here to be available for comparisons with concentrations input by the North Cotentin nuclear installations, calculated by the G.R.N.C. (radioecology group of Nord Cotentin)

Strategic Considerations for the Sustainable Remediation of Nuclear Installations

International Nuclear Information System (INIS)

Miller, Susan; Wilson, Ian; Decung, Fabien; Ollivier Dehaye, Catherine; Pellenz, Gilles; Palut-Laurent, Odile; Nitzsche, Olaf; Rehs, Bernd; Altavilla, Massimo; Osimani, Celso; Florya, Sergey; Revilla, Jose-Luis; Efraimsson, Henrik; Baines, Kim; Clark, Anna; Cruickshank, Julian; Mitchell, Nick; Mobbs, Shelly; Orr, Peter; Abu-Eid, Rateb Boby; Durham, Lisa; Morse, John; Walker, Stuart; Weber, Inge; ); Monken-Fernandes, Horst; )

2016-01-01

Nuclear sites around the world are being decommissioned and remedial actions are being undertaken to enable sites, or parts of sites, to be reused. Although such activities are relatively straightforward for most sites, experience has suggested that preventative action is needed to minimise the impact of remediation activities on the environment and the potential burden to future generations. Removing all contamination in order to make a site suitable for any use generates waste and has associated environmental, social and economic drawbacks and benefits. Site remediation should thus be sustainable and result in an overall net benefit. This report draws on recent experience of NEA member countries in nuclear site remediation during decommissioning in order to identify strategic considerations for the sustainable remediation of subsurface contamination - predominantly contaminated soil and groundwater - to describe good practice, and to make recommendations for further research and development. It provides insights for the decision makers, regulators, implementers and stakeholders involved in nuclear site decommissioning so as to ensure the sustainable remediation of nuclear sites, now and in the future. (authors)

Report on Activities of the Nuclear Regulatory Authority of the Slovak Republic and on Safety of Nuclear Installations in the Slovak Republic in 2006. Annual Report 2006

International Nuclear Information System (INIS)

Zemanova, D.; Pirozekova, M.

2007-04-01

A brief account of activities carried out by the Nuclear Regulatory Authority of the Slovak Republic in 2006 is presented. These activities are reported under the headings: Foreword; (1) Vision, Mission and Principles of Activities; (2) Legislation; (3) Issuance of Authorisations, Safety Assessment and Enforcement; (3.1) Issuance of Authorizations/Permissions; (3.2) Assessment and Inspections Activities; (3.3) Safety Assessment and Enforcement; (4) Nuclear Safety of Nuclear Installations in the Slovak Republic; (4.1) Nuclear installations in operation in the Slovak Republic; (4.2) Nuclear Installations under construction in the Slovak Republic; (4.3) Decommissioning of nuclear installations in the Slovak Republic; (5) Safety of Other Nuclear Installations; (5.1) Other Nuclear Installations in Operation; (5.2) Other Nuclear Installations under Construction; (5.3) Other Nuclear Installations under Decommissioning; (6) Management of Radioactive Waste; (6.1) Generation and minimisation of radioactive waste; (6.2) Management of radioactive waste; (6.3) Pre-disposal management of radioactive waste; (6.4) Disposal of radioactive waste; (6.5) Shipment of radioactive waste; (7) Nuclear Materials; (7.1) Accounting for and Control of Nuclear Materials; (7.2) Shipment of Nuclear Materials; (7.3) Illicit Trafficking of Nuclear Materials and Other Radioactive Material; (8) Emergency Planning and Preparedness; (9) International Activities; (9.1) European Affairs; (9.2) Membership in International Organisations; (9.3) Fulfilment of Obligations under International Contractual Instruments; (9.4) Bilateral Co-operation; (10) Public Communication; (11) UJD SR; (11.1) Economy Data; (11.2) Human resources and training; (11.3) Internal Management Quality System; (11.4) Development of UJD SR Regulatory Activities; (12) Abbreviations

Legal bases for the installation of nuclear power plants

International Nuclear Information System (INIS)

Faria, N.M. de

1980-06-01

The process of installation of nuclear power plants in the context of the Brazilian legal system is analysed. The structure of the political and administrative system related to the matter and the correspondent legislation are discussed. (A.L.) [pt

Licensing of nuclear and radioactive installations in Peru

International Nuclear Information System (INIS)

Medina Gironzini, E.

1987-01-01

In Peru, the Regulation for Ionizing Radiation Sources is applied, which establishes the norms and procedures to follow in the nuclear and radioactive installations of the country in order to assure their correct operation as concerns to the nuclear safety and radiological protection, allowing the emission of the respective licenses. As for the nuclear facilities, this authorization includes the Previous License, the Construction License and the Operation License (provisional and definitive) and for radioactive facilities and equipment generating ionizing radiations: the Construction License and the Operation License. The personnel also require a license that can be an operator license (as for nuclear reactors) or a supervisor license (for nuclear and radioactive facilities). In spite of the above mentioned regulation and its long enforcement period, less than 10% of radioactive facilities in this country are licensed, due to different problems which will be solved in the medium term. (Author)

Contributions by emissions from nuclear installations to concentrations of radionuclides in milk

CERN Document Server

Green, N

1983-01-01

A year-long study has been carried out to determine whether milk produced near nuclear sites contains concentrations of radionuclides that can be attributed to discharges from the installations, and, as a consequence, whether there is enhanced exposure of those members of the public who consume this milk. Eight creameries were chosen and monthly samples of milk were taken for analysis. The concentrations of caesium-137 and strontium-90 were measured and compared with results from a national survey conducted as part of the Board's environmental radioactivity surveillance programme. No effect attributable to discharges from the nuclear establishments was identified. The activity concentrations ranged between 0.1 and 3 times the national average; the variation relates mainly to rainfall in the area, although other factors may also have an effect. However, milk contributes only a small fraction of the total dietary intake of caesium-137 and strontium-90, and so the exposure of persons consuming the milk varies on...

Review of the seismic risk in the design of civil engineering of nuclear installations excepted the long term storage of radioactive wastes

International Nuclear Information System (INIS)

2006-01-01

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

Utilization of analytical techniques in aid the implantation of nuclear installations

International Nuclear Information System (INIS)

Ferreira, M.P.; Sabino, C.V.S.; Avelar, M.M.

1984-01-01

Nuclear, physico-chemical and classic techniques developed and utilized by Centro de Desenvolvimento de Tecnicas Nucleares are presented, as back up to the implementation and operation of nuclear installations related with several parts of fuel cycle from uranium prospecting to waste treatment samples of soils, ores, alloys, plastics, paints, biological materials, air and water were analysed. (M.C.K) [pt

The ATLAS Software Installation System v2: a highly available system to install and validate Grid and Cloud sites via Panda

Science.gov (United States)

De Salvo, A.; Kataoka, M.; Sanchez Pineda, A.; Smirnov, Y.

2015-12-01

The ATLAS Installation System v2 is the evolution of the original system, used since 2003. The original tool has been completely re-designed in terms of database backend and components, adding support for submission to multiple backends, including the original Workload Management Service (WMS) and the new PanDA modules. The database engine has been changed from plain MySQL to Galera/Percona and the table structure has been optimized to allow a full High-Availability (HA) solution over Wide Area Network. The servlets, running on each frontend, have been also decoupled from local settings, to allow an easy scalability of the system, including the possibility of an HA system with multiple sites. The clients can also be run in multiple copies and in different geographical locations, and take care of sending the installation and validation jobs to the target Grid or Cloud sites. Moreover, the Installation Database is used as source of parameters by the automatic agents running in CVMFS, in order to install the software and distribute it to the sites. The system is in production for ATLAS since 2013, having as main sites in HA the INFN Roma Tier 2 and the CERN Agile Infrastructure. The Light Job Submission Framework for Installation (LJSFi) v2 engine is directly interfacing with PanDA for the Job Management, the Atlas Grid Information System (AGIS) for the site parameter configurations, and CVMFS for both core components and the installation of the software itself. LJSFi2 is also able to use other plugins, and is essentially Virtual Organization (VO) agnostic, so can be directly used and extended to cope with the requirements of any Grid or Cloud enabled VO. In this work we will present the architecture, performance, status and possible evolutions to the system for the LHC Run2 and beyond.

Report on Activities of the Nuclear Regulatory Authority of the Slovak Republic and on Safety of Nuclear Installations in the Slovak Republic in 2005. Annual report 2005

International Nuclear Information System (INIS)

Zemanova, D.; Seliga, M.; Sladek, V.

2006-04-01

A brief account of activities carried out by the Nuclear Regulatory Authority of the Slovak Republic in 2005 is presented. These activities are reported under the headings: Foreword; (1) Vision, Mission and Principles of Activities; (2) Legislation; (3) Issuance of Authorisations, Safety Assessment and Enforcement; (4) Nuclear Safety of Nuclear Installations in the Slovak Republic; (4.1) Nuclear installations in operation in the Slovak Republic; (4.2) Nuclear Installations under construction in the Slovak Republic; (4.3) Decommissioning of nuclear installations in the Slovak Republic; (5) Spent Fuel and Radioactive Waste Management and Safety of other Nuclear Installations in the Slovak Republic; (5.1) Generation and minimisation of radioactive waste; (5.2) Management of radioactive waste; (5.3) Pre-disposal management of radioactive waste; (5.4) Disposal of radioactive waste; (5.5) Shipment of radioactive waste; (5.6) Safety of other nuclear installations in the Slovak Republic; (6) Personnel Qualification and Training; (7) Nuclear Materials and Physical Protection of Nuclear installations; (8) Emergency Preparedness; (9) International Co-operation; (10) Public Communication; (11) UJD SR; (11.1) UJD SR organizational chart; (11.2) UJD SR organizational chart; (11.3) Human resources and training; (11.4) Internal system of quality assurance; (11.5) Development of UJD SR regulatory activities; Appendix: Abbreviations; Development of UJD SR regulatory activities

Safety aspects of spent nuclear fuel interim storage installations

Energy Technology Data Exchange (ETDEWEB)

Romanato, Luiz Sergio [Centro Tecnologico da Marinha em Sao Paulo (CTMSP), Sao Paulo, SP (Brazil). Dept. da Qualidade. Div. de Sistemas da Qualidade]. E-mail: romanato@ctmsp.mar.mil.br; Rzyski, Barbara Maria [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil). Div. de Ensino]. E-mail: bmrzyski@ipen.br

2007-07-01

Nowadays safety and security of spent nuclear fuel (SNF) interim storage installations are very important, due to a great concentration of fission products, actinides and activation products. In this kind of storage it is necessary to consider the physical security. Nuclear installations have become more vulnerable. New types of accidents must be considered in the design of these installations, which in the early days were not considered like: fissile material stolen, terrorists' acts and war conflicts, and traditional accidents concerning the transport of the spent fuel from the reactor to the storage location, earthquakes occurrence, airplanes crash, etc. Studies related to airplane falling had showed that a collision of big commercials airplanes at velocity of 800 km/h against SNF storage and specially designed concrete casks, do not result in serious structural injury to the casks, and not even radionuclides liberation to the environment. However, it was demonstrated that attacks with modern military ammunitions, against metallic casks, are calamitous. The casks could not support a direct impact of this ammo and the released radioactive materials can expose the workers and public as well the local environment to harmful radiation. This paper deals about the main basic aspects of a dry SNF storage installation, that must be physically well protected, getting barriers that difficult the access of unauthorized persons or vehicles, as well as, must structurally resist to incidents or accidents caused by unauthorized intrusion. (author)

Safety aspects of spent nuclear fuel interim storage installations

International Nuclear Information System (INIS)

Romanato, Luiz Sergio

2007-01-01

Nowadays safety and security of spent nuclear fuel (SNF) interim storage installations are very important, due to a great concentration of fission products, actinides and activation products. In this kind of storage it is necessary to consider the physical security. Nuclear installations have become more vulnerable. New types of accidents must be considered in the design of these installations, which in the early days were not considered like: fissile material stolen, terrorists' acts and war conflicts, and traditional accidents concerning the transport of the spent fuel from the reactor to the storage location, earthquakes occurrence, airplanes crash, etc. Studies related to airplane falling had showed that a collision of big commercials airplanes at velocity of 800 km/h against SNF storage and specially designed concrete casks, do not result in serious structural injury to the casks, and not even radionuclides liberation to the environment. However, it was demonstrated that attacks with modern military ammunitions, against metallic casks, are calamitous. The casks could not support a direct impact of this ammo and the released radioactive materials can expose the workers and public as well the local environment to harmful radiation. This paper deals about the main basic aspects of a dry SNF storage installation, that must be physically well protected, getting barriers that difficult the access of unauthorized persons or vehicles, as well as, must structurally resist to incidents or accidents caused by unauthorized intrusion. (author)

The Nuclear Installations (Excepted Matter) Regulations 1978 (Statutory Instrument No. 1779, 4 December 1978)

International Nuclear Information System (INIS)

1979-01-01

These Regulations prescribe, for the purposes of the definition of 'excepted matter' in the Nuclear Installations Act 1965, certain specified quantities and forms of nuclear matter, and supersede the Nuclear Installations (excepted Matter) Regulations 1965. They bring the definition of excepted matter in those Regulations into line with the decisions of 27 October 1977 of the OECD Nuclear Energy Agency's Steering Committee excluding certain kinds and quantities of nuclear substances from the scope of the Paris Convention on Third Party Liability in the Field of Nuclear Energy. Compared with the 1965 Regulations, the principal changes in relation to consignments are that activity limits and packing requirements now take account of the most recent IAEA Regulations. (NEA) [fr

Nuclear power: Siting and safety

International Nuclear Information System (INIS)

Openshaw, S.

1986-01-01

By 2030, half, or even two-thirds, of all electricity may be generated by nuclear power. Major reactor accidents are still expected to be rare occurrences, but nuclear safety is largely a matter of faith. Terrorist attacks, sabotage, and human error could cause a significant accident. Reactor siting can offer an additional, design-independent margin of safety. Remote geographical sites for new plants would minimize health risks, protect the industry from negative changes in public opinion concerning nuclear energy, and improve long-term public acceptance of nuclear power. U.K. siting practices usually do not consider the contribution to safety that could be obtained from remote sites. This book discusses the present trends of siting policies of nuclear power and their design-independent margin of safety

Nuclear reactor installation

International Nuclear Information System (INIS)

Jungmann, A.

1976-01-01

A nuclear reactor metal pressure vessel is surrounded by a concrete wall forming an annular space around the vessel. Thermal insulation is in this space and surrounds the vessel, and a coolant-conductive layer is also in this space surrounding the thermal insulation, coolant forced through this layer reducing the thermal stress on the concrete wall. The coolant-conductive layer is formed by concrete blocks laid together and having coolant passages, these blocks being small enough individually to permit them to be cast from concrete at the reactor installation, the thermal insulation being formed by much larger sheet-metal clad concrete segments. Mortar is injected between the interfaces of the coolant-conductive layer and concrete wall and the interfaces between the fluid-conductive layer and the insulation, a layer of slippery sheet material being interposed between the insulation and the mortar. When the pressure vessel is thermally expanded by reactor operation, the annular space between it and the concrete wall is completely filled by these components so that zero-excursion rupture safeguard is provided for the vessel. 4 claims, 1 figure

The function of specialized organization in work safety engineering for nuclear installations

International Nuclear Information System (INIS)

Salvatore, J.E.L.

1989-01-01

The attributions of Brazilian CNEN in the licensing procedures of any nuclear installation are discussed. It is shown that the work safety engineering and industrial safety constitute important functions for nuclear safety. (M.C.K.) [pt

The Asteroid Threat and the Safety of Surface Nuclear Installations

International Nuclear Information System (INIS)

Shestopalov, V.M.; Shibetskij, Yu.A.; Makarenko, A.N.

2015-01-01

Surface nuclear installations are much more vulnerable to impact events than it has traditionally been considered. They can be destroyed by events with energies greater than 100 Mt. According to the most unfavorable (conservative) estimates, the probability of destruction can reach 10 -7 ...10 -6 year -1 for certain areas of the Earth. In fact, any cosmic body that can reach the surface of the Earth, or an atmospheric explosion can cause a serious accident to or even completely destroy a nuclear facility. The burden of the radiological consequences of such an accident will be determined by the total activity of radioactive substances located on site and by meteorological factors. The most dangerous (probable) are low-energy events (10 0 ...10 2 Mt). They can occur during the collision of the Earth with a cosmic body with a diameter of 30...200 m. The risk of death resulting from the direct effects of the impact of the given energy is approximately two orders of magnitude lower than the risk of death due to additional radiological impacts of the destroyed facility. Within the energy range of 10 2 ...10 5 Mt, the radiological consequences of impact events (opposite to non-radiological) will be global. In our opinion, this is a strong argument for the inclusion of impact events into the list of possible external events when assessing the suitability of sites for placement of NPPs and storage facilities for spent nuclear fuel. The safety analysis of the indicated facilities should consider the complexity of the damaging factors (high temperatures, shock, seismic shock, tsunamis) and also the fact that the loads associated with the phenomena induced by the impact will depend on its energy and can greatly exceed the values of loads typical for the region of the facility location

The Role Of Quality Assurance Program For Safety Operation Of Nuclear Installations

International Nuclear Information System (INIS)

Harjanto, N.T.; Purwadi, K.P.; Boru, D.S.; Farida; Suharni

2000-01-01

Nuclear installations expose potential hazard of radiation, therefore in their construction, operation and maintenance, it is necessary to consider safety aspect, in which the safety requirements which has been determined must be met. One of the requirements that is absolutely needed is quality assurance, which covers arrangement of quality assurance program, organization and administration of the implementation of quality assurance, and supervision. Quality Assurance program is a guideline containing quality policies and basic determination on the realization of activities that effect the quality of equipment's and items used in the operation of nuclear installations in order that the operation of nuclear installation can run safety and in accordance with their design aims and operation limits. Quality Assurance Program includes document control, design control, supply control, control of equipment s and items, operation/process control, inspection and control of equipment test, and control of nonconformance and corrections. General system of nuclear installation operation is equipped with safety and supporting systems. These systems must apply the quality assurance program that cover control of activities in the systems. In the implementation of the quality assurance program, it is necessary to establish procedures, work guidelines/instructions, and quality recording that constitutes documents of quality system 2 nd , 3 th , and 4 th level after the quality assurance program. To ensure the effectivity and to prove whether the realization of the program has been pursuant to the determined requirements, an internal audit must be conducted accordingly

Social acceptance for seismic safety of nuclear installations

International Nuclear Information System (INIS)

Oiso, Shinichi

2010-01-01

The social acceptance of seismic safety of the nuclear installations was considered based on the situation that people's concern and anxieties for it having risen by earthquake suffering of the Kashiwazaki Kariwa facility in 2007, etc. It aimed mainly to extract a social awareness (acknowledgment and evaluation) which is peculiar to the earthquake in the field of nuclear power generation, and to show the attention point concerning the public relations of seismic safety of the nuclear power plant. As a result, it was suggested that we should explain based on the opinion of the third party which has a high trust such as specialist scholars, and emphasize that the severe examinations of outside third parties such as committee of the prefecture are conducted. (author)

The ATLAS Software Installation System v2: a highly available system to install and validate Grid and Cloud sites via Panda

CERN Document Server

De Salvo, Alessandro; The ATLAS collaboration; Sanchez, Arturo; Smirnov, Yuri

2015-01-01

The ATLAS Installation System v2 is the evolution of the original system, used since 2003. The original tool has been completely re-designed in terms of database backend and components, adding support for submission to multiple backends, including the original WMS and the new Panda modules. The database engine has been changed from plain MySQL to Galera/Percona and the table structure has been optimized to allow a full High-Availability (HA) solution over WAN. The servlets, running on each frontend, have been also decoupled from local settings, to allow an easy scalability of the system, including the possibility of an HA system with multiple sites. The clients can also be run in multiple copies and in different geographical locations, and take care of sending the installation and validation jobs to the target Grid or Cloud sites. Moreover, the Installation DB is used as source of parameters by the automatic agents running in CVMFS, in order to install the software and distribute it to the sites. The system i...

Nuclear Installations (Jersey) Order 1980 SI No. 1527

International Nuclear Information System (INIS)

1980-01-01

This Order extends to the Bailiwick of Jersey with the exceptions, adaptations and modifications specified in the Schedule to the Order, certain provisions of the Nuclear Installations Act 1965, as amended. It is the 1965 Act which implements the provisions of the Paris Convention and the Brussels Supplementary Convention in the United Kingdom. These provisions relate to the duty in respect of the carriage of nuclear matter, to the right to compensation for breach of that duty and to the bringing and satisfaction of claims and other matters. This Order came into operation on 3 November 1980. (NEA) [fr

Environmental Impact Assessment for the Decommissioning of Nuclear Installations. Vol. 1-3

International Nuclear Information System (INIS)

Bussell, M.J.; Haigh, C.P.; O'Sullivan, P.J.; Mathieson, J.; Braeckeveldt, M.; Deconinck, J.M.; Vidaechea, S.; Beceiro, A.; Ziegenhagen, J.; Biurrun, E.; Codee, H.; Palerm, J.; Bond, A.J.; Warren, L.; Sheate, B.

2001-06-01

This Report presents the results of a study concerned with Environmental Impact Assessment (EIA) for the decommissioning of nuclear installations in European Union Member States and in the Applicant Countries in Central and Eastern Europe. The study, undertaken for the Environment Directorate General of the European Commission, took place between January 2000 and March 2001 under contract number B4-3040/99/136035/MAR/C2 entitled Environmental Impact Assessment for the Decommissioning of nuclear Installations. The study presents an analysis of the current situation in the European Union and in the Applicant Countries, and develops guidance for applying the relevant Directives for EIA to the specific issue of decommissioning nuclear installations although there is also scope for application to other large or controversial projects. The first part of the report (Volume 1) describes the current situation in the EU Member States and Applicant Countries. On the basis of this status, the guidance presented in Volume 2 was developed. Draft versions of these volumes were reviewed by an independent review panel and were then subjected to detailed discussion and debate at a Workshop held in Brussels in January 2001. The Workshop was attended by more than 60 representatives of the nuclear industry, nuclear regulators, public interest groups and EIA experts. Some minor changes were made following the Workshop, a record of which can be found in Volume 3. (author)

Legal questions relating to nuclear installations close to national frontiers

International Nuclear Information System (INIS)

Zieger, G.

1983-01-01

Main emphasis is placed on the criteria to decide whether the construction and operation of a nulcear power plant close to a national frontier is permissible or not. The author discusses the relevant provisions of the international law and those of the Treaty of Rome pertaining to the settlement of conflicts between neighbour states. According to the opinion of the author, nuclear installations close to borders are incompatible with international law only if they do not comply with accepted safety standards. The international agreements do not prohibit the construction of nuclear installations close to frontiers. It would be desirable, however, the author says, to conclude international treaties providing for mutual consultation and information, thus offering a platform for discussing controversial national interests; this idea already being put into practice in customary international law. (WB) [de

Resolving piping analysis issues to minimize impact on installation activities during refueling outage at nuclear power plants

International Nuclear Information System (INIS)

Bhavnani, D.

1996-01-01

While it is required to maintain piping code compliance for all phases of installation activities during outages at a nuclear plant, it is equally essential to reduce challenges to the installation personnel on how plant modification work should be performed. Plant betterment activities that incorporate proposed design changes are continually implemented during the outages. Supporting analysis are performed to back these activities for operable systems. The goal is to reduce engineering and craft man-hours and minimize outage time. This paper outlines how plant modification process can be streamlined to facilitate construction teams to do their tasks that involve safety related piping. In this manner, installation can proceed by minimizing on the spot analytical effort and reduce downtime to support the proposed modifications. Examples are provided that permit performance of installation work in any sequence. Piping and hangers including the branch lines are prequalified and determined operable. The system is up front analyzed for all possible scenarios. The modification instructions in the work packages is flexible enough to permit any possible installation sequence. The benefit to this approach is large enough in the sense that valuable outage time is not extended and on site analytical work is not required

Design basis of off-site emergency response plans for fuel cycle installations

International Nuclear Information System (INIS)

Rzepka, J.P.; Dubiau, Ph.; Jouve, A.C.; Charles, T.; Mercier, J.P.

1995-01-01

In France, the term 'off-site emergency response plan' refers to all the arrangements which should be made by the government authorities to protect the population in the event of an accident affecting the installations of the site considered. The outline of the method of defining typical accidents, evaluation of 'source-terms' and health consequences is presented. Two applications to installations from the front-end and from the back-end of the fuel cycle are discussed. (K.A.). 1 tab

Safeguards by Design - Experiences from New Nuclear Installation

International Nuclear Information System (INIS)

Okko, O.; Honkamaa, T.; Kuusi, A.; Rautjaervi, J.

2010-01-01

The experiences obtained from the current construction projects at Olkiluoto clearly point out the need to introduce the safeguards requirements into facility design process at an early stage. The early Design Information is completed, in principle, before the construction. However, during the design of containment, surveillance systems, and non-destructive assay equipment and their cabling, the design requirements for safeguards systems were not available either for the new reactor unit or for the disposal plant with a geological repository. Typically, the official Design Information documents are not available early enough for efficient integration of safeguards systems into new facilities. In case of the Olkiluoto projects, this was due to understandable reasons: at the new reactor unit the design acceptance by the ordering company and by the nuclear safety authorities was a long process, ongoing simultaneously with parts of the construction; and at the geological repository the national legislation assigns the repository the status of a nuclear facility only after the initial construction and research phase of the repository when the long-term safety of the disposal concept is demonstrated. As similar factors are likely to delay the completion of the official Design Information documents with any new reactor projects until the construction is well underway and efficient integration of safeguards systems is impossible. Therefore, the proliferation resistance of new nuclear installations should be addressed in the design phase before the official Design Information documents are finished. This approach was demonstrated with the enlargement of the Olkiluoto spent fuel storage building. For this approach to work, strong national contribution is needed to facilitate the early communication and exchange of information between the IAEA and the other stakeholders to enable the design of facilities that can be efficiently safeguarded. With the renaissance of nuclear

Liability for injury to the unborn - Recent amendments to the United Kingdom Nuclear Installations Act

International Nuclear Information System (INIS)

Coleman, J.E.

1977-01-01

The adoption in the United Kingdom in 1976 of an Act to determine liability for injury to the unborn (foetus) has provided the opportunity to amend the Nuclear Installations Act which governs the liability of nuclear operators, which is now extended to such injury. Any 'injury' attributable to a nuclear operator which so affects a mother that her child is born disabled involves the liability of that operator within the meaning of the Nuclear Installations Act whether or not either parent has suffered an injury on that occasion. (NEA) [fr

Current emergency programs for nuclear installations in Japan

International Nuclear Information System (INIS)

Chino, Masamichi

2007-01-01

Large effort has been taken for nuclear emergency programs in Japan especially after the JCO accident. A special law for nuclear emergency was established after the accident. The law extended the scope of emergency preparedness to fuel cycle facilities, research reactors, etc. and clarified the roles and responsibilities of the national government, local governments and license holders. For initial responses, the action levels and action procedures are defined based on environmental doses and specific initial events of NPPs. A senior specialist was dispatched to each site for nuclear emergency and a facility 'Off-site center' to be used as the local emergency headquator was designated at each site. This paper describes the structure of emergency program, responsibility of related organizations and the definition of unusual events for notification and emergency. Emergency preparedness, emergency radiation monitoring and computer-based prediction of on- and off-site situation are also addressed. (author)

A future for nuclear sites beyond their service life. Nuclear site value development

International Nuclear Information System (INIS)

2008-01-01

As the nuclear industry moves into a new development phase, many facilities built in the fifties and sixties are reaching the end of their service life. Dismantling them and rehabilitating the sites on which they stand is a major industrial challenge which will give rise to a number of new projects. AREVA has more than 20 years' experience in these highly technical fields. As more and more sites reach the end of their service life, AREVA considers nuclear site value development as a fully-fledged industrial activity. The group's competencies in this field have been grouped together to form a dedicated entity: the Nuclear Site Value Development Business Unit, created in 2008. Several billion euros are invested in site value development projects which are far-reaching and complex, and often last for several decades. Long before work actually begins, lengthy studies and preparations are required to schedule operations, select the techniques to be used and optimize costs and deadlines. The Nuclear Site Value Development BU is currently working on four major projects involving its own facilities and those of the CEA: - La Hague: dismantling of the first generation of used fuel recycling facilities. Between 1966 and 1998, almost 5,000 tons of used fuel from graphite-moderated gas-cooled reactors, 4,500 tons of light water reactor fuel, as well as fuel from fast reactors and research reactors, were treated at UP2 400, the very first industrial recycling plant on the La Hague site. - Marcoule: first-time dismantling of a recycling plant. 1,000 rooms to be cleaned up, 30,000 tons of waste to be treated, 30 years of work. - Cadarache: first-time dismantling of a Mox fuel fabrication plant. The Cadarache plant was commissioned in 1962 to fabricate fuel for fast reactors; this was followed by MOX fuel for light water reactors, an activity which continued until the plant was shut down in 2003. - Annecy and Veurey: giving a new lease of life to former industrial sites in built

Nuclear site selection studies

International Nuclear Information System (INIS)

Gharib, A.; Zohoorian Izadpanah, A.A.; Iranmanesh, H.

2000-01-01

It is of special importance, especially from the nuclear safety viewpoint, to select suitable sites for different nuclear structures with the considered future activities. Site selection sometimes involves high costs not necessarily for merely selecting of site but for some preliminary measures to be taken so as the site may have the necessary characteristics. The more suitable the natural characteristics of the site for the considered project, the more successful and efficient the project, the lower the project costs and the longer the project operation period. If so, the project will cause the growth of public culture and sustainable socioeconomic development. This paper is the result of the conclusion of numerous massive reports of this activity in the preliminary phase based on theories, practices and the related safety principles on this ground as well as the application of data and information of the past and a glance to the future. The conception of need for a site for medium structures and nuclear research projects and how to perform this process are presented step by step here with a scientific approach to its selection during the investigations. In this study, it is practically described how the site is selected, by determining and defining the characteristics of research and nuclear projects with medium structures and also its fitting to the optimum site. The discovered sites typically involve the best advantages in technical and economic aspects and no particular contrast with the concerned structures

Regulatory oversight report 2016 concerning nuclear safety in Swiss nuclear installations; Aufsichtsbericht 2016 zur nuklearen Sicherheit in den schweizerischen Kernanlagen

Energy Technology Data Exchange (ETDEWEB)

NONE

2017-06-15

packages as well as one cask with the fuel assemblies from the shut down research reactor DIORIT of PSI and six casks with waste from the decommissioning of the experimental nuclear power plant at Lucens. During 2016 only one campaign to incinerate and melt radioactive waste was carried out. ENSI recorded no reportable events at Zwilag during the reporting year. The nuclear facilities at PSI consist of the hot laboratory, the three former research reactors SAPHIR, DIORIT and PROTEUS now in varying phases of decommissioning, the former experimental incineration plant and the facilities for the disposal of radioactive materials including the Federal Government's interim storage facility. During 2016, no events were reported at the PSI, at EPFL or at UniB. In 2016, the amount of radioactive material released into the environment via waste water and exhaust air from the nuclear power plants, Zwilag and the nuclear facilities at PSI, Basel and Lausanne was significantly less than the limits specified in the operating licenses. Analyses showed that the maximum dose for persons in the immediate vicinity of a plant was less than 1% of the annual exposure to natural radiation. The waste produced during reprocessing at the reprocessing facilities of La Hague (France) and Sellafield (United Kingdom) must be returned to Switzerland. In the reporting year, compacted, metallic, intermediate level waste and intermediate level vitrified residue packets were transported to Zwilag. All nuclear waste from Swiss fuel assemblies sent abroad for reprocessing is now stored at Zwilag. During 2016, all transports of radioactive substances to and from Swiss nuclear installations took place without any incidents. The site selection procedure for the storage of radioactive waste has been running since 2008. ENSI bears overall responsibility for the safety assessment of the geological site areas. The National Cooperative for the Disposal of Radioactive Waste (Nagra) submitted its suggestion for

Leasing of nuclear installations

International Nuclear Information System (INIS)

Capaccioli, Enzo.

1977-01-01

The high costs to be borne in industrialised countries for expanding nuclear programmes make leasing, in terms of funding, an attractive proposition even in times of recession. This system is advantageous to both parties: the bodies providing funds make substantial profits without untoward risk, given the internationally-recognised regime of channelling liability onto the nuclear operator and because such contracts usually provide that ownership of the property involved will eventually be transferred to the operator. The latter obtains the sums needed by a simple, speedy procedure enabling him to start operations more quickly than if he had to seek funds by a more conventional method. The problem in Italy is that nuclear electricity generating plants are a State monopoly while leasing is a private enterprise. The Italian 1975 Siting Act provides a consultation procedure of regional and State authorities, with the ultimate decision taken by the latter. To maintain the momentum, arrangements could be made for leasing, before starting the licensing procedure proper according to the Act. (NEA) [fr

Complementary safety assessment assessment of nuclear facilities - Tricastin facility - AREVA; Evaluation complementaire de la surete des installations nucleaires de base - Site du Tricastin - AREVA

Energy Technology Data Exchange (ETDEWEB)

NONE

2011-07-01

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

Fatigue damage of nuclear facilities; Endommagement par fatigue des installations nucleaires

Energy Technology Data Exchange (ETDEWEB)

NONE

2001-07-01

The conference on the fatigue damage of nuclear facilities, organized by the SFEN (french society of nuclear energy), took place at Paris the 23. of november 2000. Eleven papers were presented, showing the state of the art and the research programs in the domain of the sizing rules, safety, installations damage, examination and maintenance. (A.L.B.)

Note n. SD3-DEM-01 regulations procedures relative to the based nuclear installations dismantling

International Nuclear Information System (INIS)

2003-02-01

This note aims to define the regulations procedures relative to the safety of based nuclear installations dismantling defined by the decree of the 11 december 1963 modified. The first part describes the two main phases of a based nuclear installation life, the operating and the dismantling phase. The second part is devoted to the procedures. (A.L.B.)

Quality assurance in the structural installations of nuclear power stations

International Nuclear Information System (INIS)

Schnellenbach, G.; Wrage, S.

1985-01-01

The concept of quality assurance distinguishes between self-monitoring of the design, manufacturing and executing firms and external monitoring by state institutions or by experts commissioned by them. The long-term control of structures is within the area of responsibility of the owner. This quality assurance concept is controlled in detail by statutes, which clearly define responsibilities. This structural engineering quality assurance system also forms the basis for the design, construction and utilization of structural installations of nuclear power stations; requirements emanating from the Atomic Energy Acts for the structural installations demand, however, to some extent a sharpening of self- and external monitoring. Therefore, today a quality concept has been developed for the important engineering safety-related buildings of nuclear power stations. This concept takes account of the strict requirements imposed and fulfils the requirement of KTA 1401. (orig.) [de

The regulatory process, nuclear safety research and the fuel cycle in the United Kingdom

International Nuclear Information System (INIS)

Watson, P.

1996-01-01

The main legislation governing the safety of nuclear installations in the United Kingdom is the Health and Safety at Work Act 1974 (HSWA) and the associated relevant statutory provisions of the Nuclear Installations Act 1965 (as amended). The HSWA sought to simplify and unify all industrial safety legislation and set in place the Health and Safety Commission (HSC) and its executive arm, the Health and Safety Executive (HSE). The Health and Safety Executive's Nuclear Safety Division (NSD) regulates the nuclear activities on such sites through HM Nuclear Installations Inspectorate (NII). Under the Nuclear Installations Act (NIA) no corporate body may use any site for the purpose of installing or operating any reactor, other than such a reactor comprised in a means of transport, or other prescribed installation unless the operator has been granted a nuclear site licence by the Health and Safety Executive. Nuclear fuel cycle facilities are examples of such prescribed installations. (J.P.N.)

Report on activities of Nuclear Regulatory Authority of the Slovak Republic and safety of nuclear installations in the Slovak Republic in 2007. Annual report

International Nuclear Information System (INIS)

2007-04-01

A brief account of activities carried out by the Nuclear Regulatory Authority of the Slovak Republic (UJD SR) in 2007 is presented. These activities are reported under the headings: (1) Foreword; (2) Legislation; (3) Issuance of authorizations, assessment, supervisory activities and enforcement; (4) Nuclear safety of nuclear installations in the Slovak Republic; (5) Safety of other nuclear installations; (6) Management of radioactive waste; (7) Nuclear materials; (8) Emergency planning and preparedness; (9) International activities; (10) Public communication; (11) Nuclear Regulatory Authority of the Slovak Republic; (12) Abbreviations

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

International Nuclear Information System (INIS)

Torino Araoz, Ines; Parera, Maria D.

2011-01-01

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

Installation Of A Training Center With Nuclear Instruments In The I.N.E.A

International Nuclear Information System (INIS)

Camargo B, Ana C.; Periaza C, A.

1993-01-01

In the framework of the regional technical cooperation of the countries in development, at present, the IAEA executes some investigation projects such as the program of Regional Arrangements of Technical Cooperation for Latin America and Caribbean (ARCAL), from which the program of nuclear instrumentation ARCAL II is derived and by agreement the INEA should install a reference center in Electronic and Nuclear Instrumentation. To complete this objective it has assigned the development of different sub projects, among which is the installation of a training center for operation, cares and quality control of nuclear instruments of medical applications

Evaluation of Aqua-Ammonia Chiller Technologies and Field Site Installation

Energy Technology Data Exchange (ETDEWEB)

Zaltash, Abdolreza [ORNL

2007-09-01

The Naval Facilities Engineering Service Center (NFESC) has sponsored Oak Ridge National Laboratory (ORNL) to review, select, and evaluate advanced, gas-fired, 5-ton, aqua-ammonia, chiller technologies. The selection criteria was that units have COP values of 0.67 or better at Air-conditioning and Refrigeration Institute (ARI) 95 F outdoor rating conditions, an active refrigerant flow control, and a variable-speed condenser fan. These features are expected to allow these units to operate at higher ambient temperatures (up to the maximum operating temperature of 110 F) with minimal degradation in performance. ORNL evaluated three potential manufacturers of advanced, gas-fired, 5-ton, aqua-ammonia chillers-Robur, Ambian, and Cooling Technologies. Unfortunately, Robur did not meet the COP requirements and Cooling Technologies could not deliver a unit to be tested at the U.S. Department of Energy (DOE)-ORNL environmental chamber testing facility for thermally activated heat pumps. This eliminated these two technologies from further consideration, leaving only the Ambian chillers for evaluation. Two Ambian chillers were evaluated at the DOE-ORNL test facility. Overall these chillers operated well over a wide range of ambient conditions with minimal degradation in performance due to several control strategies used such as a variable speed condenser fan, a modulating burner, and active refrigerant flow control. These Ambian pre-commercial units were selected for installation and field testing at three federal facilities. NFESC worked with ORNL to assist with the site selection for installation and evaluation of these chillers. Two sites (ORNL and Naval Surface Warfare Center [NSWC] Corona) had a single chiller unit installed; and at one site (Naval Amphibious Base [NAB] Little Creek), two 5-ton chillers linked together were installed to provide 10 tons of cooling. A chiller link controller developed under this project was evaluated in the field test at Little Creek.

New safety standards of nuclear power station with no requirements of site evaluation. No public dose limit published with possible inappropriateness of reactor site

International Nuclear Information System (INIS)

Takitani, Koichi

2013-01-01

Nuclear Regulation Authority was preparing new safety standards in order to aim at starting safety reviews of existing nuclear power station in July 2013. This article commented on issues of major accident, which was defined as severely damaged core event. Accumulated dose at the site boundary of the Fukushima Daiichi Nuclear Power Station totaled to about 234 mSv on March just after the accident with rare gas of 500 PBq, iodine 131 of 500 PBq, cesium 134 of 10 PBq and cesium 137 of 10 PBq released to the atmosphere, which was beyond 100 mSv. As measures for preventing containment vessel failure after core severely damaged, filtered venting system was required to be installed for low radiological risk to the public. However filter was not effective to rare gas. Accumulated doses at the site boundary of several nuclear power stations after filtered venting with 100% release of rare gas could be estimated to be 2-37 Sv mostly depending on the site condition, which might be surely greater than 100 mSv. Omitting site evaluation for major accident, which was beyond design basis accident, was great concern. (T. Tanaka)

Rules specific to nuclear incidence occurring in installations or during transport of nuclear substances

International Nuclear Information System (INIS)

Rocamora, P.

1976-01-01

International nuclear third party liability conventions deal in depth with the liability system governing the transport of nuclear substances. Without appropriate legislation, international transport would be likely to meet very serious legal difficulties. The rule of nuclear conventions apply the same system to transport as to nuclear installations and mainly enable a determination of the operator liable. They also allow the person responsible for transport to assume liability therefor in place of the operator who whould normally have been liable. These nuclear conventions do not affect application of international transport conventions and this provision has been the cause of serious difficulties regarding maritime transport. This resulted in the adoption in 1971 in Brussels of a convention relating to civil liability in the field of maritime carriage of nuclear material. The purpose of this convention is to establish in the field of maritime transport, the priority of the system of absolute, exclusive and limited liability in the nuclear conventions. (NEA) [fr

Nuclear installations operated without the required permits: the policy pursued in the Netherlands

International Nuclear Information System (INIS)

Huygen, A.

1994-01-01

The authoress presents two topical cases from the Netherlands where two nuclear installations are allowed to continue operation by a joint decision of the government and the courts, although the legal operating permits have been declared void by a government senate. The legal basis constructed for this approach allowing plant operation to continue for a limited number of years is an explicit statement by the government to tolerate such procedure. The installations are the Bodeward nuclear power station with a BWR and the Almelo URENCO uranium enrichment facility. (orig./HSCH) [de

On the safety of nuclear installations in the Soviet Union

International Nuclear Information System (INIS)

Anon.

1989-01-01

The cooperation agreements between authorities and industries of the Soviet Union and West Germany now are gaining shape in practice. In this context, the framework conditions are of great interest that govern the realisation of the extensive nuclear energy programme of the Soviet Union. The chairman of the State Commission established in 1984 for supervision of nuclear installations and guidance on safety-engineering enhancement of nuclear power plant in the USSR has been interviewed by atw on topics of organisations, measures and regulatory activities in the field of reactor safety and radiation protection. The interview is given in full. (orig.) [de

Public information and licensing procedures for nuclear installations. European experience

International Nuclear Information System (INIS)

Mayoux, J.C.; Chevillard, F.; Mutschler, U.; Stubbe, C.

1981-10-01

This paper reviews the licensing procedures for nuclear installations in various European countries and examines the form, content and methods selected for information and consultation of the public. The author stresses the importance of this stage in the procedure, both for the nuclear operator and the public authorities, given the population's concern about the environment. He concludes that, irrespective of its complexity, the nuclear field cannot remain the concern of a few initiates competent to take decisions and that, consequently, this implies creation of new information systems to meet the public's desire to participate more directly in the process. (NEA) [fr

Nuclear power plant attempts in Turkey and the first licensed site

International Nuclear Information System (INIS)

Bektur, Y.; Bezdegumeli, U.

2004-01-01

Turkey is currently in a rapid industrialization process with a young population of 71 million. Electricity is an inevitable need for Turkey as a fast developing country. Turkey's average annual growth rates of electricity consumption have been 8% in the last two decades. The installed electricity generating capacity of Turkey reached 36 GW; the annual gross power generation was 140 TWh (23% lignite and coal, 44% natural gas, 25% hydro and 8% others); and the annual gross per capita consumption of electricity was around 2.000 kWh as of end-2003. According to forecasts prepared by the Ministry of Energy and Natural Resources (MENR), Turkey will need about 60 GW of capacity by 2010, and about 100 GW by 2020. This implies power demand growth rates of at least 8% per annum for the coming decade and at least 6% per annum for the following decade. This means that there is a need for rapid build-up of 3 GW new capacities per year for at least several years. Turkey's experience with nuclear power dates back to the 1960s - a research reactor has been operating in Istanbul since 1962 - and successive governments have had plans to introduce commercial nuclear power to the country for three decades or more. Since 1965, four attempts were made for the construction of an NPP in Turkey, but all failed. Turkish Electricity Authority (TEK, reorganized as Electricity Generation Corporation in 2002) was granted a site license for the Akkuyu site in 1976. According to the current long-term energy planning studies made by MENR, nuclear power is an important option to enhance the national energy security and reliability. In the light of this study, the Turkish Government has an intention for commencement of a nuclear power program that envisages the construction of 4500 M We nuclear power installed capacity in the next decade if the private energy sector do not make an attempt

The Community's research and development programme on decommissioning of nuclear installations: First annual progress report (year 1985)

International Nuclear Information System (INIS)

1986-01-01

This is the first Annual Progress Report of the European Community's 1984-88 programme of research on the decommissioning of nuclear installations. It shows the status of implementation reached on 31 December 1985. The 1984-88 programme has the following contents: A. Research and development projects concerning the following subjects: Project No 1: Long-term integrity of building and systems; Project No 2: Decontamination for decommissioning purposes; Project No 3: Dismantling techniques; Project No 4: Treatment of specific waste materials: steel, concrete and graphite; Project No 5: Large containers for radioactive waste produced in the dismantling of nuclear installations; Project No 6: Estimation of the quantities of radioactive wastes arising from the decommissioning of nuclear installations in the Community; Project No 7: Influence of installation design features on decommissioning. B. Identification of guiding principles, namely: - certain guiding principles in the design and operation of nuclear installations with a view to simplifying their subsequent decommissioning, - guiding principles in the decommissioning of nuclear installations which could form the initial elements of a Community policy in this field. C. Testing of new techniques under real conditions, within the framework of large-scale decommissioning operations undertaken in Member States. This first progress report, covering the period of putting the programme into action, describes the work to be carried out under the 27 research contracts concluded, as well as initial work performed and first results obtained

Report on activities of Nuclear Regulatory Authority of the Slovak Republic and safety of nuclear installations in the Slovak Republic in 2009. Annual report

International Nuclear Information System (INIS)

2010-04-01

A brief account of activities carried out by the Nuclear Regulatory Authority of the Slovak Republic (UJD SR) in 2009 is presented. These activities are reported under the headings: (1) Foreword; (2) Legislation; (3) Issuance of authorizations, assessment, supervisory activities and enforcement; (4) Nuclear safety of nuclear installations in the Slovak Republic; (5) Safety of other nuclear installations; (6) Management of radioactive waste; (7) Nuclear materials and physical protection of nuclear materials; (8) Emergency planning and preparedness; (9) International activities; (10) Public communication; (11) Nuclear Regulatory Authority of the Slovak Republic; (12) UJD SR organization chart; (13) Abbreviations.

Report on activities of Nuclear Regulatory Authority of the Slovak Republic and safety of nuclear installations in the Slovak Republic in 2008. Annual report

International Nuclear Information System (INIS)

Zemanova, D.; Pirozekova, M.

2009-04-01

A brief account of activities carried out by the Nuclear Regulatory Authority of the Slovak Republic (UJD SR) in 2008 is presented. These activities are reported under the headings: (1) Foreword; (2) Legislation; (3) Issuance of authorizations, assessment, supervisory activities and enforcement; (4) Nuclear safety of nuclear installations in the Slovak Republic; (5) Safety of other nuclear installations; (6) Management of radioactive waste; (7) Nuclear materials and physical protection of nuclear materials; (8) Activity of Building Office; (9) Emergency planning and preparedness; (10) International activities; (11) Public communication; (11) Nuclear Regulatory Authority of the Slovak Republic; (12) UJD SR organization chart; (13) Abbreviations

Liability for on-site nuclear property damage

International Nuclear Information System (INIS)

Neems, H.J.

2000-01-01

Typically, liability for on-site property addressed in contracts between operator and its suppliers. Nuclear power plant operators ordinarily protect themselves against risk of nuclear damage to on-site property by insurance. Nuclear liability laws do not specifically address liability for nuclear damage to on-site property. Nuclear plant owners should address risk of damage to on-site property when developing risk management program

Ordinance of 14 March 1983 concerning the Federal Commission for the Safety of Nuclear Installations

International Nuclear Information System (INIS)

1983-01-01

The Frederal Council issued a new Ordinance concerning the Federal Commission for the Safety of Nuclear Installations. This Ordinance replaces an Ordinance of 13 June 1960 and takes into account the distribution of tasks decided several years ago between the Commission, which operates on a part-time basis, and the principal Division for the Safety of Nuclear Installations attached to the Federal Office of Energy. (NEA) [fr

International Conference on Topical Issues in Nuclear Installation Safety: Defence in Depth — Advances and Challenges for Nuclear Installation Safety. Proceedings of an International Conference held in Vienna, Austria, 21-24 October 2013

Energy Technology Data Exchange (ETDEWEB)

NONE

2014-10-15

The fifth International Conference on Topical Issues in Nuclear Installation Safety was dedicated to the defence in depth (DID) concept which is fundamental to the safety of nuclear installations. The main focus of the conference was to foster the exchange of information on the implementation of DID and the associated challenges. This CD-ROM contains the papers presented at the conference as well as the summary and conclusions, including recommendations for further actions to strengthen DID and its implementation.

Preparation, installation, and calibration of a 152-fiber imaging experiment at the Nevada Test Site

International Nuclear Information System (INIS)

Thayer, D.R.; Lyons, P.B.; Looney, L.D.; Manning, J.P.; Malone, R.M.

1981-01-01

Fiber-optic transmission lines are being used with increasing frequency in the demanding environment of nuclear device diagnostic tests at the Nevada Test Site. Previous reports have described diagnostic experiments that utilize properties of fiber-optic cables to provide capabilities that are extremely difficult to obtain with coaxial cable systems. This paper describes an imaging experiment conducted during the last quarter of 1980 at the Nevada Test Site involving 152 approx. 0.6-km long GI fibers in 18 cables. An imager cell sensitive to neutron and gamma radiation was located at approx. 8 m from the source. Individual elements of the fluor were coupled by approx. 10 m PCS fibers (for radiation damage resistance) to the GI fibers used for the uphole and surface lines to the detector station. Light from the imager cell in a 9-nm band, centered at 540 nm, was detected by photomultipliers and the electrical signals then recorded on oscilloscopes. Overall system bandwidth, including the fluor, was approx. 80 MHz. Due to the complexity of the experiment and the conditions associated with field testing, the PCS and GI fibers were cut and terminated under laboratory shop conditions prior to installation at the field site. Procedures used for quality assurance of the fiber assemblies as well as procedures used in checking fiber throughput during installation are described. The application of a large star coupler (5 input x 200 output fibers) used for system time and amplitude calibration and an attempt to shutter fibers with neutrons for a multiplexing application are also discussed

Gas turbine installations in nuclear power plants in Sweden

International Nuclear Information System (INIS)

Sevestedt, Lars

1986-01-01

At each of the four nuclear power stations in Sweden (Ringhals, Forsmark, Oskarshamn, Barsebaeck) gas turbine generating sets have been installed. These units are normally used for peak load operation dictated of grid and System requirements but they are also connected to supply the electrical auxiliary load of the nuclear plant as reserve power sources. The gas turbines have automatic start capability under certain abnormal conditions (such as reactor trips, low frequency grid etc) but they can also be started manually from several different locations. Starting time is approximately 2- 3 minutes from start up to full load. (author)

Gas turbine installations in nuclear power plants in Sweden

Energy Technology Data Exchange (ETDEWEB)

Sevestedt, Lars [Electrical Equipment and Gas Turbines, Swedish State Power Board, Ringhals Nuclear Power Plant, S-430 22 Vaeroebacka (Sweden)

1986-02-15

At each of the four nuclear power stations in Sweden (Ringhals, Forsmark, Oskarshamn, Barsebaeck) gas turbine generating sets have been installed. These units are normally used for peak load operation dictated of grid and System requirements but they are also connected to supply the electrical auxiliary load of the nuclear plant as reserve power sources. The gas turbines have automatic start capability under certain abnormal conditions (such as reactor trips, low frequency grid etc) but they can also be started manually from several different locations. Starting time is approximately 2- 3 minutes from start up to full load. (author)

Effective corrective actions to enhance operational safety of nuclear installations

International Nuclear Information System (INIS)

2005-07-01

The safe operation of nuclear power plants around the world and the prevention of incidents in these installations remain key concerns for the nuclear community. In this connection the feedback of operating experience plays a major role: every nuclear plant operator needs to have a system in place to identify and feed back the lessons learned from operating experience and to implement effective corrective actions to prevent safety events from reoccurring. An effective operating experience programme also includes a proactive approach that is aimed at preventing the first-time occurrence of safety events. In April 2003, the IAEA issued the PROSPER guidelines for nuclear installations to strengthen and enhance their own operating experience process and for self-assessment on the effectiveness of the feedback process. Subsequently, in the course of the Operational Safety Review Teams missions conducted by the IAEA that focused on the operational safety practices of nuclear power plants, the IAEA enhanced the review of the operating experience in nuclear power plants by implementing a new module that is derived from these guidelines. In order to highlight the effective implementation of the operating experience programme and to provide practical assistance in this area, the IAEA organized workshops and conferences to discuss recent trends in operating experience. The IAEA also performed assistance and review missions at plants and corporate organizations. The IAEA is further developing advice and assistance on operating experience feedback programmes and is reporting on good practices. The present publication is the outcome of two years of coordinated effort involving the participation of experts of nuclear organizations in several Member States. It provides information and good practices for successfully establishing an effective corrective actions programme. This publication forms part of a series that develops the principles set forth in these guidelines

Establishment of the nuclear regulatory framework for the process of decommissioning of nuclear installations in Mexico; Establecimiento del marco regulador nuclear para el proceso de cierre de instalaciones nucleares en Mexico

Energy Technology Data Exchange (ETDEWEB)

Salmeron V, J. A.; Camargo C, R.; Nunez C, A., E-mail: juan.salmeron@cnsns.gob.mx [Comision Nacional de Seguridad Nuclear y Salvaguardias, Dr. Barragan 779, Col. Narvarte, 03020 Ciudad de Mexico (Mexico)

2015-09-15

Today has not managed any process of decommissioning of nuclear installations in the country; however because of the importance of the subject and the actions to be taken to long term, the Comision Nacional de Seguridad Nuclear y Salvaguardias (CNSNS) in Mexico, accordance with its objectives is developing a National Nuclear Regulatory Framework and defined requirements to ensure the implementation of appropriate safety standards when such activities are performed. In this regard, the national nuclear regulatory framework for nuclear installations and the particular case of nuclear power reactors is presented, as well as a proposed licensing process for the nuclear power plant of Laguna Verde based on international regulations and origin country regulations of the existing reactors in nuclear facilities in accordance with the license conditions of operation to allow to define and incorporate such regulation. (Author)

Nuclear ventilation installations. Method of control of the scrubbing coefficient of iodine trap

International Nuclear Information System (INIS)

1982-12-01

The present standard aims at defining a method to control the scrubbing coefficient of radioactive iodine trapping systems, used in nuclear ventilation installations. It applies to the installations where the trapping, efficiency of radioactive iodine has to be known, tested and compared to a reference value generally included in the safety reports. It applies to the installations where the absolute pressure of the air in the ventilation systems is above 1,4. 10 5 Pa (1,4 Bar) [fr

Renewable energy sources and nuclear installations

International Nuclear Information System (INIS)

Hirschberg, S.; Bauer, Ch.; Burgherr, P.; Stucki, S.; Vogel, F.; Biollaz, S.; Schulz, T.; Durisch, W.; Hardegger, P.; Foskolos, K.; Meier, A.; Schenler, W.

2005-02-01

This comprehensive work report for the Swiss Federal Office of Energy (SFOE) made by the Paul Scherrer Institute PSI takes a look at work done in connection with the updating of the office's Energy Perspectives. In particular, the topic of electricity is reviewed in the light of pending important decisions in the area of nuclear energy and the newer renewable sources of energy. The report makes an attempt to estimate the effect on Swiss power production that the new renewables and new nuclear installations could have in the next 30-40 years and to what costs this could be done and which obstacles would have to overcome. The renewable energy sources include small hydro, wind, photovoltaics, solar thermal power plants, biogas, geothermal energy, wave-power and solar chemistry. The methods used include literature study and contacts with internal PSI experts on the various areas involved. The most important system characteristics were noted and learning curves for the various technologies were taken into account. Ecological and social factors were also considered

Nuclear energy and the nuclear industry

International Nuclear Information System (INIS)

1979-01-01

These notes have been prepared by the Department of Energy to provide information and to answer questions often raised about nuclear energy and the nuclear industry and in the hope that they will contribute to the public debate about the future of nuclear energy in the UK. The subject is dealt with under the headings; contribution of nuclear power, energy forecasts, nuclear fuels and reactor types, cost, thermal reactor strategy, planning margin, safety, nuclear licensing, unlike an atomic bomb, radiation, waste disposal, transport of nuclear materials, emergency arrangements at nuclear sites, siting of nuclear stations, security of nuclear installations, world nuclear programmes, international regulation and non-proliferation, IAEA safeguards arrangements in the UK, INFCE, and uranium supplies. (U.K.)

Installation method for the steel container and vessel of the nuclear heating reactor

International Nuclear Information System (INIS)

Chen Liying; Guo Jilin; Liu Wei

2000-01-01

The Nuclear Heating Reactor (NHR) has the advantages of inherent safety and better economics, integrated arrangement, full power natural circulation and dual vessel structure. However, the large thin container presents a new and difficult problem. The characteristics of the dual vessel installation method are analyzed with system engineering theory. Since there is no foreign or domestic experience, a new method was developed for the dual vessel installation for the 5 MW NHR. The result shows that the installation method is safe and reliable. The research on the dual vessel installation method has important significance for the design, manufacture and installation of the NHR dual vessel, as well as the industrialization and standardization of the NHR

Analytical methodology for optimization of waste management scenarios in nuclear installation decommissioning process - 16148

International Nuclear Information System (INIS)

Zachar, Matej; Necas, Vladimir; Daniska, Vladimir; Rehak, Ivan; Vasko, Marek

2009-01-01

The nuclear installation decommissioning process is characterized by production of large amount of various radioactive and non-radioactive waste that has to be managed, taking into account its physical, chemical, toxic and radiological properties. Waste management is considered to be one of the key issues within the frame of the decommissioning process. During the decommissioning planning period, the scenarios covering possible routes of materials release into the environment and radioactive waste disposal, should be discussed and evaluated. Unconditional and conditional release to the environment, long-term storage at the nuclear site, near surface or deep geological disposal and relevant material management techniques for achieving the final status should be taken into account in the analysed scenarios. At the level of the final decommissioning plan, it is desirable to have the waste management scenario optimized for local specific facility conditions taking into account a national decommissioning background. The analytical methodology for the evaluation of decommissioning waste management scenarios, presented in the paper, is based on the materials and radioactivity flow modelling, which starts from waste generation activities like pre-dismantling decontamination, selected methods of dismantling, waste treatment and conditioning, up to materials release or conditioned radioactive waste disposal. The necessary input data for scenarios, e.g. nuclear installation inventory database (physical and radiological data), waste processing technologies parameters or material release and waste disposal limits, have to be considered. The analytical methodology principles are implemented into the standardised decommissioning parameters calculation code OMEGA, developed in the DECOM company. In the paper the examples of the methodology implementation for the scenarios optimization are presented and discussed. (authors)

Regulatory procedures for the decommissioning of nuclear installations

International Nuclear Information System (INIS)

Woods, P.B.; Basu, P.K.

1988-01-01

The basic safety legislation under which operational safety at nuclear installations is regulated does not change when the plant is decommissioned. In the United Kingdom the relevant nuclear safety legislation is embodied in several Acts of Parliament or international conventions. These are listed and described. The potential risk in decommissioning is from radiation exposure of the workers and to a lesser extent of the public and environment. The regulations try to ensure this risk is reduced to acceptable levels. This objective can be achieved if the project is adequately planned, there is reliable information about the plant, the risks are identified and assessed, the quality assurance is good and personnel are trained, and the radioactive wastes produced are managed and disposed of suitably. (U.K.)

Site-Specific Atmospheric Dispersion Characteristics of Korean Nuclear Power Plant Sites

International Nuclear Information System (INIS)

Han, M. H.; Kim, E. H.; Suh, K. S.; Hwang, W. T.; Choi, Y. G.

2001-01-01

Site-specific atmospheric dispersion characteristics have been analyzed. The northwest and the southwest wind prevail on nuclear sites of Korea. The annual isobaric surface averaged for twenty years around Korean peninsula shows that west wind prevails. The prevailing west wind is profitable in the viewpoint of radiation protection because three of four nuclear sites are located in the east side. Large scale field tracer experiments over nuclear sites have been conducted for the purpose of analyzing the atmospheric dispersion characteristics and validating a real-time atmospheric dispersion and dose assessment system FADAS. To analyze the site-specific atmospheric dispersion characteristics is essential for making effective countermeasures against a nuclear emergency

Large fire scenarios in relation to sabotage of nuclear installations

International Nuclear Information System (INIS)

Contri, P.; Guerpinar, A.; ); Schneider, U.

2005-01-01

The analyses of sabotage scenarios carried out in recent years identified two major damaging mechanisms associated with such scenarios, namely: the mechanical interaction of solid bodies or pressure waves with the installations and the fire-related effects from burning substances. While the former effect may be addressed by available analytical tools developed for accidental scenarios, the latter deserves a new, specific engineering effort. In fact, all nuclear facilities are designed in relation to accidental fires; even so, they need to be assessed in relation to sabotage induced fire scenarios due to the special characteristics of such scenarios, not addressed by the current engineering practice for the design of nuclear installations. Conventional fire hazard analysis is based on the hypothesis of the presence of combustible materials in the buildings and limited number of contemporaneous sources of fire. In addition, conventional fire safety assessment relies upon the presence of mitigation measures and fire related operational procedures. In a sabotage event the validity of all these assumptions need to be checked and if the assumptions cannot be supported, then the analysis should be revised and other alternatives of protection should be developed. Also the implementation of emergency planning should be reviewed to take account of this concern. This paper collects state-of-the-art experience from some Countries, which represents the background information for the development of new IAEA documents in this field. The paper reviews how the current design practice for nuclear installations can cope with large fire scenarios caused by malevolent actions and provides recommendations to designers and operators on how to address these issues in a reasonable framework. (authors)

Statutory Instrument No. 126, The Nuclear Installations (Hong Kong) Order 1972

International Nuclear Information System (INIS)

1972-01-01

This Order extends to Hong Kong, with the exceptions, adaptations and modifications specified in the Schedule to the Order, certain provisions of the Nuclear Installations Act 1965, as amended. It is the 1965 Act which implements the provisions of the Paris Convention and the Brussels Supplementary Convention in the United Kingdom. The provisions so extended impose a duty on the nuclear operator to secure that no nuclear occurrence taking place within the territorial limits of Hong Kong causes nuclear injury or damage, and relate to the right to compensation for breach of that duty, the bringing and satisfaction of claims and other matters. (NEA) [fr

Statutory Instrument No. 123, The Nuclear Installations (Cayman Islands) Order 1972

International Nuclear Information System (INIS)

1972-01-01

This Order extends to the Cayman Islands, with the exceptions, adaptations and modifications specified in the Schedule to the Order, certain provisions of the Nuclear Installations Act 1965, as amended. It is the 1965 Act which implements the provisions of the Paris Convention and the Brussels Supplementary Convention in the United Kingdom. The provisions so extended impose a duty on the nuclear operator to secure that no nuclear occurrence taking place within the territorial limits of the Cayman Islands causes nuclear injury or damage, and relate to the right to compensation for breach of that duty, the bringing and satisfaction of claims and other matters. (NEA) [fr

Installation and commissioning of operation nuclear power plant reactor protection system modernization project

International Nuclear Information System (INIS)

Lu Weiwei

2010-01-01

Qinshan Nuclear Power Plant is the first nuclear power plant in mainland China; it is also the first one which realizes the modernization of analog technology based Reactor Protection System in the operation nuclear power plant of China. The implementation schedule is the shortest one which use same digital technology platform (TELEPERM XS of AREVA NP) to modifying the safety class I and C system in the world, the whole project spent 28 months from equipment contract signed to putting system into operation. It open up a era for operation nuclear power plant using mature digital technology to make safety class I and C system modernization in China. The important practical significance of this successful project is very obvious. This article focus on two important project stage--equipment installation and system commissioning, it is based on a large number of engineering implementation fact, it covers the problems and solutions happened during the installation and commission. The purpose of the article is to share the experience and lessons of safety I and C system modernization for other operation nuclear power plant. (authors)

Outline of a future security system to provide physical protection of nuclear installations

International Nuclear Information System (INIS)

Rossnagel, A.

1984-01-01

Nuclear energy, within three or four decades, may become a main pillar of the world's energy supply. The author discusses the problems entailed by the necessity to protect nuclear facilities against assaults, and whether this can be ensured without interference with civic rights. The method applied by the author to show the significance of the problems is to explain the current situation, and to compare it with a plausible outline of the developments to be expected over the next 50 years. He shows the hazards to be taken into account due to criminal actions by persons from outside, or by persons working in nuclear facilities. A main problem is the fact that the security system to be set up has to encompass not only the nuclear installation itself, but also the surrounding area, and the measures to be taken will have an impact on the society, which necessarily will curtail personal freedom. The author presumes that the necessity to guarantee physical protection of nuclear facilities will lead to a modification of the meaning of basic rights, and states his anxiety that security for nuclear installations might affect our concept of freedom. (HSCH) [de

Ultrasonic data acquisition installation for basis and in-service testing of nuclear pressure vessels

International Nuclear Information System (INIS)

Gutmann, G.; Engl, G.

1976-01-01

The safety of nuclear installations requires continuous safety inspections during construction and operation. Essential parts of this safety inspection are the basis and in-line inspections. For this purpose installation systems are used which allow an optimal statement to be made regarding the conditions of tested components

Regulation of the life cycle of nuclear installations. Peer discussions on regulatory practices

International Nuclear Information System (INIS)

1999-06-01

This report arises from the sixth series of peer discussions on regulatory practices entitled 'Regulation of Life Cycle of Nuclear Installations'. Senior regulators from 18 Member States participated in three peer group discussions during 1997-1998. This report presents the outcome of these meetings and recommendations of good practices identified by senior regulators, which do not necessarily reflect those of the governments of the nominating Member States, the nominating organizations, or the IAEA. The purpose of this report is to disseminate the views which the senior regulators presented at the meetings relating to the policies, principles and requirements imposed by regulatory bodies for the safe management of the life cycle of a nuclear installation. The intention of doing this is to assist Member States in the formulation and enhancement of their regulatory control over PLCM by identifying commonly accepted good practices. This report is structured to cover the subject matter under the following main headings: Policies and Principles for the Life Cycle Management of Nuclear Installations; Responsibilities of the Regulatory Body and the Operating Organization; Requirements and Criteria Imposed by the Regulatory Body; Licensing and Regulatory Assessment for Plant Life Cycle Management; and Good Practices

Environmental assessment of nuclear installations using accumulated litterfall cycling

International Nuclear Information System (INIS)

Coelho, Joaquim M.S.; Scapin, Marcos A.; Pires, Maria A.F.

2011-01-01

For 25 years the Nuclear and Energy Research Institute - IPEN/SP processed uranium oxide to produce the fuel element. Even with major care in the handling of uranium hexafluoride and uranium compounds, there is the probability of small fractions are dispersed into the atmosphere. Due to this fact, it was proposed a study of these compounds in the environment, aiming at the bio monitoring of toxic substances originating from the fabrications process of fuel element, as well toxic metals. The litterfall it's consisted of fragments of organic vegetable, including leaves, flowers, fruits, branches, twigs and animal waste. The objective of this study was to determine the production and seasonality of litterfall in the gardens of IPEN, establish a correlation between the compartment leaves, wood and reproductive parts and evaluate the chemical composition of leaves originated of litterfall through chemical analysis. Was installed 10 litterfall collectors to determinate the production . The determination of chemical elements was realized by X-ray fluorescence for dispersion of wavelength (WDXRF). The production of dry litterfall during the period was 5.86 Kg m 2 -1. The elements analyzed were Na, Mg, Al, Si, P, S, Cl, K, Ca, Ti, Mn, Fe, Ni, Cu, Br, Rb, Sr, Zr, Th and U. The major constituents of the composition of leaf Ca, Si, and K (1.8%, 0.5% and 0.6% respectively). The results allowed to conclude that the installations used in the nuclear fuel cycle earlier, as well as the installations in operation, actually didn't affect the biogeochemical cycle of plants. (author)

A Low Cost Shading Analyzer and Site Evaluator Design to Determine Solar Power System Installation Area

Directory of Open Access Journals (Sweden)

Selami Kesler

2015-01-01

Full Text Available Shading analyzer systems are necessary for selecting the most suitable installation site to sustain enough solar power. Afterwards, changes in solar data throughout the year must be evaluated along with the identification of obstructions surrounding the installation site in order to analyze shading effects on productivity of the solar power system. In this study, the shading analysis tools are introduced briefly, and a new and different device is developed and explained to analyze shading effect of the environmental obstruction on the site on which the solar power system will be established. Thus, exposure duration of the PV panels to the sunlight can be measured effectively. The device is explained with an application on the installation area selected as a pilot site, Denizli, in Turkey.

Safety Review Services, Site Review Services and IRRS

International Nuclear Information System (INIS)

Yllera, Javier

2010-01-01

The selection and the evaluation of the site for a nuclear power plant are crucial parts of establishing a nuclear power programme and can be significantly affected by costs, public acceptance and safety considerations. Siting is the process of selecting a suitable site for a facility. This is area containing the plant, defined by a boundary and under effective control of the Plant Management. For safety related issues comparison within topics is generally quite straightforward. For example, sites with relatively higher seismic hazard would be penalized in comparison with those in more stable areas. The site for the NPP is generally chosen at a relatively ‘aseismic’ part of the country. This generally means that well known seismogenic sources are more than at least 50 kms from the site. The proposed sites for nuclear installations shall be examined with respect to the frequency and the severity of natural and human induced events and phenomena that could affect the safety of the installation. The Events unconnected with the operation of a facility or activity which could have an effect on the safety of the facility or activity. The relationship between the site and the design for the nuclear installation shall be examined to ensure that the radiological risk to the public and the environment arising from releases defined by the source terms is acceptably low. The Nuclear Regulatory Authority should issue a document that sets out the technical safety and security criteria against which the Site Permit Application for a new NPP will be reviewed. The objective of the Site Safety Review Services (SSRS) is provided upon request from a Member State. An independent review and assessment of the site and nuclear installation safety in relation to external natural and man induced hazards. This is to make recommendations on additional analysis or plant modifications to be carried out in order to comply with the IAEA Safety Standards and to enhance safety

Statutory Instrument No. 2056, The Nuclear Installations Act 1965 etc. (Repeals and Modifications) Regulations 1974

International Nuclear Information System (INIS)

1975-01-01

These Regulations contain repeals and modifications of provisions of the Nuclear Installations Act 1965 and a modification of the Nuclear Installations (Dangerous Occurrences) Regulations 1965. They are made in consequence of the establishment on 1st January 1975 of the Health and Safety Executive and the coming into operation on that date of provisions of the Health and Safety at Work etc. Act 1974 which supersede or affect provisions of the 1965 Act and the 1965 Regulations. (NEA) [fr

Public perception of nuclear installations

International Nuclear Information System (INIS)

Kiipper, Felipe de Moura

2011-01-01

The key for nuclear renaissance is public acceptance. Facing energetic needs that occur around the world and lack of resources, the work of characterizing and proposing new models to represent public opinion is extremely important to all stakeholders. Even though public opinion's study on risks is relatively recent, may approaches of this subject have been suggested and presented, especially for the topic of perceptions on nuclear installations. Actual definitions on risk exist between objective and subjective models, that reflect opinions of lay public and experts. Strategies on communications with the public may be evaluated from many developed models, and its results may be registered. The use of structural models may present an exploratory character as well as confirmatory theories, as an adequate tool for the development of studies on public perception. In this work, a structural model is presented from data obtained in a previous report, and added to data collected before and after the Fukushima nuclear accident, in Japan. The effects developed from this accident offered a unique opportunity to study public opinion through the effects of a serious nuclear accident and its effects on risk communications. Aside, this work attempted to check the structural model according with obtained results, in order to sustain a constant improvement of the working tools. Yet, a comparison between data according to experts' respondents and lay public ones as well as a comparison among different students before and after a visit to nuclear station is considered. Obtained data for the structural models has been applied for on a structural model and analyzed by structural correlation matrix, latent variable structural coefficients and R 2 values. Results indicate that public opinion maintains its rejection on nuclear energy and the perception of benefits, facing perceived risks before the accident, has diminished. A new model that included a latent variable for corresponding

Lifetime Evaluation of Grid-Connected PV Inverters Considering Panel Degradation Rates and Installation Sites

OpenAIRE

Sangwongwanich, Ariya; Yang, Yongheng; Sera, Dezso; Blaabjerg, Frede

2018-01-01

Lifetime of PV inverters is affected by the installation sites related to different solar irradiance and ambient temperature profiles (also referred to as mission profiles). In fact, the installation site also affects the degradation rate of the PV panels, and thus long-term energy production and reliability. Prior-art lifetime analysis in PV inverters has not yet investigated the impact of PV panel degradations. This paper thus evaluates the lifetime of PV inverters considering panel degrada...

Assessment of safety culture in the Iranian nuclear installations

International Nuclear Information System (INIS)

Farahani, H.F.; Davilu, H.; Sepanloo, K.

2005-01-01

The deficient safety culture (S.C) is the center of safety issues of nuclear industry. To benefit from the advantages of nuclear technology and considering the fact of potential hazards of accidents in nuclear installations it is essential to view safety as the highest priority. S.C is an amalgamation of values, standards, morals and norms of acceptable behavior. Organizations having effective S.C show constant commitment to safety as a top level priority. Furthermore, the personnel of a nuclear facility shall recognize the safety significance of their tasks. Many people even those who work in the field of safety do not have a correct understanding of what S.C looks like in practical sense. In this study, by conducting a survey according to IAEA-TECDOC-1329 in some nuclear facilities, the S.C within the Iranian nuclear facilities is assessed. The human and organizational factors in Tehran Research Reactor are evaluated using a questionnaire method with active participation of the reactor operators. The results sho w that the operators are pretty aware of the subject. Also it has been identified some areas of improvement. (authors)

Assessment of the nuclear installation's safety significant events

International Nuclear Information System (INIS)

Vidican, D.

2005-01-01

This document tries to establish, based on the available documentation, the main steps in development of Assessment of the Events in Nuclear Installations. It takes into account: selection of the safety significant occurrences, establishing the direct cause and contributors as well as the root cause and contributors. Also, the document presents the necessary corrective actions and generic lessons to be learned from the event. The document is based especially on IAEA - ASSET guidelines and DOE root cause analysis Guidance. (author)

Policy and systems analysis for nuclear installation decommissioning

International Nuclear Information System (INIS)

Gu Jiande

1995-01-01

On the basis of introducing into principal concept for nuclear installation decommissioning, form policy, sciences point of view, the author analyses present problems in the policy, the administrative and programme for decommissioning work in China. According to the physical process of decommissioning, the author studied engineering economics, derived method and formulas to estimate decommissioning cost. It is pointed out that basing on optimization principle for radiation protection and analysing cost-benefit for decommissioning engineering, the corresponding policy decision can be made

Nuclear Plant Analyzer: Installation manual. Volume 1

International Nuclear Information System (INIS)

Snider, D.M.; Wagner, K.L.; Grush, W.H.; Jones, K.R.

1995-01-01

This report contains the installation instructions for the Nuclear Plant Analyzer (NPA) System. The NPA System consists of the Computer Visual System (CVS) program, the NPA libraries, the associated utility programs. The NPA was developed at the Idaho National Engineering Laboratory under the sponsorship of the US Nuclear Regulatory Commission to provide a highly flexible graphical user interface for displaying the results of these analysis codes. The NPA also provides the user with a convenient means of interactively controlling the host program through user-defined pop-up menus. The NPA was designed to serve primarily as an analysis tool. After a brief introduction to the Computer Visual System and the NPA, an analyst can quickly create a simple picture or set of pictures to aide in the study of a particular phenomenon. These pictures can range from simple collections of square boxes and straight lines to complex representations of emergency response information displays

Organisation arrangements of nuclear medicine services. Planning of installations. Laboratory monitoring

International Nuclear Information System (INIS)

Chanteur, J.

1977-01-01

Apart from safety and quality requirements, the organisation of nuclear medicine services, or more generally of installations where nonsealed radioactive sources are used, is governed by profitability and efficiency criteria. In view of the high price of products and apparatus, the equipment must be based on a rationalisation of options guiding the organisation arrangements as a whole. The following items are dealt with in succession: various categories of installations; general planning of equipment; equipment regulations based on a major requirement, the confinement of contamination sources; practical observations concerning administrative and technical questions

Virtual instrumentation on mobile devices for deployment in nuclear installations

International Nuclear Information System (INIS)

Farias, Marcos Santana; Santos, Isaac Jose A. Luquetti dos; Jesus, Miller F. de; Sant'Anna, Claudio Reis de; Szabo, Andre Pedro; Carvalho, Paulo Victor R. de

2013-01-01

The virtual instrumentation can be defined as a layer of software and hardware, added to a general purpose computer, so that users can interact with the computer in the same way that they interacted with traditional electronic instruments such as oscilloscopes, multi-meters and signal generators, and may add other functions defined by software. The virtual instrumentation gets a new integration environment, little explored yet, with the great growth that occurred in the mobile devices area. Nowadays it is possible to take measurements in more places by combining mobile devices with data acquisition hardware to create extremely portable and interconnected measurement systems. This paper shows the development of software and hardware that make possible the use of instrumentation on mobile devices for monitoring nuclear installations. It's presented the hardware and the application software for data acquisition of radiation monitors, developed to iOS devices. It's also shown the possibilities of hardware and software to develop near real-time data transfer to and from the field in nuclear installations, with benefits in efficiency, safety and productivity. (author)

The Nuclear Installations (Guernsey) Order 1978 (Statutory Instrument 1528, 24 October 1978)

International Nuclear Information System (INIS)

1978-01-01

This Order extends to Guernsey, with the exceptions, adaptations and modifications specified in the Schedule to the Order, certain provisions of the Nuclear Installations Act 1965, as amended. It is the 1965 Act which implements the provisions of the Paris Convention and the Brussels Supplementary Convention in the United Kingdom. The provisions so extended impose a duty on the nuclear operator to secure that no nuclear occurrence taking place within the territorial limits of Guernsey causes nuclear injury or damage, and relate to the right to compensation for breach of that duty, the bringing and satisfaction of claims and other matters. (NEA) [fr

Regulations concerning licensing of nuclear reactor facilities and other nuclear installations, Decree No 7/9141, 6 January 1975

International Nuclear Information System (INIS)

1975-01-01

This Decree lays down the licensing system for nuclear installations in Turkey and also sets up a Nuclear Safety Committee whose duty is to ensure that the requirements of this Decree are met. The Committee is made up of members of the Atomic Energy Commission specialized in reactors, nuclear safety, health physics, reactor physics as well as two experts respectively appointed by the Ministry of Health and Social Welfare and the Ministry of Energy and National Resources. (NEA) [fr

Analysis of Leukemia incidence (1997-2007) in vicinity area of a nuclear installation

International Nuclear Information System (INIS)

Jin Rong; Sun Quanfu; Liu Fen; Zhang Xu; Xing Ru; Xu Xinmei; Li Xiaoliang; Su Xu

2012-01-01

Objective: To investigate the leukemia incidence among residents in the vicinity area of a nuclear installation. Methods: The data were collected by the retrospective survey. Diagnosis is based on the medical records in all the relevant hospitals. The study area was those residential areas within 10 km of radium surrounding the installation. All residents who had lived in the study area for six months and over were recruited into the study group. Results: The survey ascertained 643 newly diagnosed leukemia cases in the study area during 1997 to 2007. The crude rate was 2.51/100000, and its standardized rate to national population structure was 2.53/100000. The incidence rate in the study area was slightly lower than that in the whole city. No increase trend was detected during the period. Conclusions: No significant difference of the leukemia incidence rate was found between the vicinity area of the nuclear installation and the whole city. (authors)

Regulation of nuclear power in the UK after Chernobyl

International Nuclear Information System (INIS)

Ryder, E.A.

1987-01-01

The essential philosophy underlying safe nuclear power in the UK is to establish a safe design and then monitor the manufacture, construction, commissioning, operation and maintenance to ensure that the safe design intent is not violated either deliberately or unintentionally. In the UK any commercial nuclear installation must have a nuclear site licence. The Nuclear Installations Inspectorate (NII) is the agency responsible for granting licences and ensuring the safe design and operation of the installation by the licensee. The way in which the NII does this for the 27 licensed sites that it regulates in the UK is explained. This covers plant assessment and site inspection. Following the accident at Chernobyl the NII reviewed the way in which it regulates nuclear power in the UK. Some changes in specific areas were recommended but no changes in the general philosophy were considered necessary. (UK)

Anti-nuclear activities and critics concerning nuclear power plant sites

International Nuclear Information System (INIS)

Rhee, We-Beg

2000-01-01

Korea has dynamic nuclear power expansion programs, operating 16 nuclear units producing 13710 MW in total located on 4 different sites. Last year, nuclear power supplied over 40 % of national total electricity demands. In 1998, Korean government initiated re-designation work investigating circumstance changes to rule out the unnecessary sites in consideration of a long-term power supply. Korean government has determined to expand the Ulchin site and to designate one point of Woolju county as a new candidate site, and ruled out the rest candidate sites at the end of 1998. About such a governmental measure, the two areas show different reactions. Ulchin where nuclear power plant has been operated safely for about 10 years was likely to accept the governmental determination in spite of some opposition and called for several financial supports for local development. WooIju county, however, showed a strong opposition among local environmental groups and autonomous politicians, and they presented a variety of anti-nuclear activities including demonstrations mainly at the neighbouring metropolis, Ulsan city

Institutional support to the nuclear power based on transportable installations

International Nuclear Information System (INIS)

Kuznetsov, V.P.; Cherepnin, Y.S.

2010-01-01

Existing nuclear power uses large-power nuclear plants (more than 1,000 MWe) and enriched uranium fuel ( 2 35 U ). Each plant is treated as an exclusive costly project. As a result, large NPPs are operated predominantly in highly developed big countries. In many countries, construction of large power units is not reasonable because of the economic conditions and national specifics. This calls for the use of small- and medium-power nuclear plants (SMPNP), especially transportable nuclear installations (TNI). TNI feature small power (up to 100 MWe); serial production, and transportability. Small- and medium-power nuclear plants could serve to produce electricity and heat; perform water desalination; provide temporary and emergency energy supply. The authors discuss some findings of the studies carried out on the various aspects of the TNI life, as well as the legal and institutional support to their development, construction and operation. The studies have been performed in the framework of the INPRO Action Plan

Stakeholder involvement in the management of effluent discharges from nuclear installations in France

International Nuclear Information System (INIS)

Schneider, T.; Gadbois, S.; Heriard Dubreuil, G.; Oudiz, A.

2004-01-01

The involvement of local stakeholders in the decision-making process regarding health, safety and environmental issues is developing in many countries. As far as the management of effluent discharges from nuclear installations in France is concerned, members of Local Commission of Information, including elected people and NGOs, are playing an increasing role in that respect. To deepen the understanding of these risk governance processes, a working group of experts from different institutions was set up in 2000 by the Institute of Radiation Protection and Nuclear Safety (IRSN). The aim of this working group was to 1) analyse the stakeholder involvement processes already in place in France around nuclear and non-nuclear installations; 2) perform case studies of few national and international experiences around nuclear installations (notably concerning the revision of creation authorisation decree of COGEMA La Hague reprocessing plant, the environmental policy of BNFL Sellafield reprocessing plant, the discharges surveillance of EDF Fessenheim nuclear power plant); 3) study the evolution of the regulatory context for the stakeholder involvement. Four main elements, contributing to the social trust emerge from this analysis: 1) the social dynamics of the consultation process, notably with the emergence of 'new' stakeholders such as elected people and NGOs; 2) the readability of the plant follow-up from the point of view of local stakeholders and their involvement in the decision process (the relay role of these 'new' stakeholders); 3) the contribution of the institutional and pluralist expertise to the social trust (broadening of the range of values taken into account); 4) the issue of the local justification of the plant in the prospect of the sustainable development (no risk being acceptable without counter-parts). This paper will address these different issues on the basis of the case studies in the perspective of examining the radiological risk governance process

Piezometer installation and monitoring procedure: Revision 1

International Nuclear Information System (INIS)

1987-04-01

The Deaf Smith County (Texas) site has been selected by the US Department of Energy as one of three candidate sites for characterization to determine its suitability as a geologic repository for high-level nuclear waste. The installation and monitoring of piezometers has been identified as one of the tasks required during the development of an underground Exploratory Shaft Facility to satisfy specific information needs through a program of in situ testing, instrumentation and monitoring. The scope of piezometer installation and monitoring encompasses the installation of fluid pressure measuring equipment and the subsequent collection, presentation and interpretation of piezometric data from strata surrounding the Exploratory Shaft Facility (ESF) prior to, during and following construction of the ESF, and as part of geohydrologic testing within the ESF. This procedure describes the required instrumentation, equipment, and sequence of activities for piezometer installation in the ESF. The procedure also includes details on the data recording and presentation requirements, personnel responsibilities, test management and quality assurance. 16 refs., 12 figs., 2 tabs

A package for environmental impact assessment of nuclear installations (NGLAR)

International Nuclear Information System (INIS)

Yang Yin; Chen Xiaoqiu; Ding Jinhou; Zhao Hui; Xi Xiaojun; Li Hongsheng

1996-09-01

The main contents, designing strategies and properties of the microcomputer-based software package NGLAR are described for environmental impact assessment of nuclear installations. The package consists of the following components: NGAS and NACC, the codes for routine and accidental airborne releases respectively; NLIQ, the code for both routine and accidental liquid releases; and NRED, environmental database system of nuclear installations. NGAS and NACC are used for evaluating atmosphere dispersion and doses to public of radioactive materials released from nuclear facilities, giving the concentrations around the facilities of radionuclides in air, on ground surface, and in varieties of animal foods and farm produces, and further estimating collective doses and doses to critical group around the facilities. NLIQ is suitable for liquid effluence released to non-tide rivers, and is modelled to calculate firstly the concentration of radionuclides concerned in the polluted rivers, and then to estimate the resulting doses to public. Under routine releases, the doses obtained from NGAS and NLIQ can be appropriately categorized and summed up together. NRED can be run independently, also used to provide some input data for above programs and save data permanently for them. Having both English and Chinese versions, the package, which was fabricated of multiple functions can be run on IBM 386 or higher and its compatible microcomputers. (3 figs., 1 tabs)

Protocol between the Nuclear Protection and Safety Bureau representing the Nuclear Authorities of Portugal and the Nuclear Energy Commission of Spain on Co-operation in Nuclear Safety

International Nuclear Information System (INIS)

1980-01-01

This Protocol was signed further to the Agreement between Portugal and Spain on 14 January 1971 on co-operation in the peaceful use of nuclear energy. It provides for exchange of information on the general aspects of nuclear safety and radiation protection; study of the basic characteristics of siting, construction, operation and decommissioning of nuclear installations, and experience acquired in these areas; the problematics of planning against nuclear incidents and their environmental impact; legislation, regulations and technical standards concerning nuclear installations. The Protocol entered into force for a period of five years on the day of its signature. (NEA) [fr

UK safety and standards for radioactive waste management and decommissioning on nuclear licensed sites

International Nuclear Information System (INIS)

Mason, D.J.

2001-01-01

This paper discusses the regulation of radioactive waste and decommissioning in the United Kingdom and identifies the factors considered by HM Nuclear Installations Inspectorate in examining the adequacy arrangements for their management on nuclear licensed sites. The principal requirements are for decommissioning to be undertaken as soon as reasonably practicable and that radioactive wastes should be minimised, disposed of or contained and controlled by storage in a passively safe form. However, these requirements have to be considered in the context of major organisational changes in the UK nuclear industry and the non-availability of disposal routes for some decommissioning wastes. The legislative framework used to regulate decommissioning of nuclear facilities in the UK is described. Reference is made to radioactive waste and decommissioning strategies, quinquennial reviews criteria for delicensing and the forthcoming Environmental Impact Assessment Regulations. (author)

Licensing systems and inspection of nuclear installations

International Nuclear Information System (INIS)

1991-01-01

The first study analysing the regulations governing the licensing and inspection of nuclear installations in OECD countries was published by OECD/NEA in 1980, and revised in 1986. Since then there have been amendments to national regulations on the subject, which have warranted updating of this publication. This new study provides a description of the licensing regulations and practices applied in the twenty OECD countries with provisions in that field. The national systems have been described according to a standard format to make comparisons and research easier. In most cases, the descriptions are supplemented by flow charts illustrating the procedures and specifying the different authorities involved in the licensing procedures [fr

Regulation and inspection support radiation protection in nuclear and other installations

International Nuclear Information System (INIS)

Williams, M.K.; Potter, C.; Harbison, S.A.

1996-01-01

Over the past fifty years, radiation protection legislation in the UK has developed from a narrow industry-specific base to a comprehensive package of regulations and supporting Approved Code of Practice, with additional provisions for nuclear installations. Development of this legislation mirrors progress in international understanding about the risks from exposure to ionising radiation. The current Ionising Radiations Regulations 1985 largely implement the Euratom 1980 Basic Safety Standards Directive and place particular emphasis on the need to keep exposure as low as reasonably practicable. The regulations have been underpinned by the development of the concept of the Tolerability of Risk and the application of the ALARP/ALARA principle, particularly at nuclear installations. Analysis of dose data on HSE's Central Index of Dose Information has shown the general success of this approach in the UK; the data have also allowed targeting of inspection effort. Currently, the Health and Safety Commission and Executive are developing plans for implementing the revised EU Basic Safety Standards Directive. (author)

Acquired experience resulting from transforming a chemical installation into a nuclear one

Energy Technology Data Exchange (ETDEWEB)

Zamfirache, M.; Stefan, L.; Bornea, A.; Stefanescu, I. [National Research and Development Institute for Cryogenics and Isotopic Technologies - ICIT, Uzinei (Romania)

2015-03-15

ICIT-Valcea has developed an experimental pilot-scale installation for tritium and deuterium separation. The main objective of this pilot was to demonstrate the water detritiation technology and to transfer this technology to the CANDU reactors of the Cernavoda nuclear power plant. The pilot-scale installation was initiated in 1992. The initial design and construction were performed similarly to chemical plants as the separation of isotopes was focused on only hydrogen and deuterium to assess feasibility. In a second phase we have begun to transform it into a nuclear facility with the aim of separating tritium. Moving to tritium separation has imposed a lot of changes. Changes consisted mainly of: -) re-design of the technological systems for nuclear material processing, applying specific codes and standards (ASME, Romanian nuclear specific pressure boundary prescriptions for code classification); -) design and implementation of new systems, classified as safety systems; -) re-design and implementation of command and control systems, complying with the requirements of reliability and maintenance required for the project promoted; -) revaluation of auxiliary systems (utilities, power supply); -) implementing radiation protection systems, including secondary barriers; -) implementing and maintaining environment operational program specific to the new nuclear plant; -) developing and conducting safety analyzes; and -) the production of specific documentation to obtain the necessary permits for construction, commissioning and operation of the plant.

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

Design, fabrication and installation of irradiation facilities -Advanced nuclear material development-

International Nuclear Information System (INIS)

Kim, Yong Seong; Lee, Jeong Yeong; Lee, Seong Ho; Ji, Dae Yeong; Kim, Seok Hoon; An, Seong Ho; Kim, Dong Hoon; Seok, Ho Cheon; Kim, Joon Yeon; Yang, Seong Hong

1994-07-01

The objective of this study is to design and construct the steady state fuel test loop and non-instrumented capsules to be installed in KMRR. The principle contents of this project are to design, fabricate the steady-state fuel test loop and non-instrumented capsule to be installed in KMRR for nuclear technology development. This project will be completed in 1996, so preparation of design criteria for fuel test loop have been performed in 1993 as the first year of the first phase in implementing this project. Also design and pressure drop test of non-instrumented capsule have been performed in 1993

Meeting around industrial sites; Concertation autour des sites d'installations industrielles

Energy Technology Data Exchange (ETDEWEB)

Schneider, Th. [Centre d' etude sur l' Evaluation de la Protection dans le domaine Nucleaire (CEPN), 92 - Fontenay aux Roses (France); Sene, M. [Groupement de Scientifiques pour l' Information sur l' Energie Nucleaire, 91 - Orsay (France); Melguen, M. [Electricite de France (EDF), 75 - Paris (France); Saint-Raymond, Ph. [Direction Generale de la Surete Nucleaire et de la Radioprotection, 75 - Paris (France); Oudiz, A. [Institut de Radioprotection et de Surete Nucleaire, 92 - Fontenay-aux-Roses (France); Brie, J. [Charente Nature (France); Schmitt, P. [CLS de Fessenheim, 68 (France); Verot, Y [Atofina, 92 -Paris la Defense (France); Quintin, Ch. [DRIRE Rhone Alpes, 69 (France); Dubuis, Th. [Secretariat Permanent pour la Prevention des Pollutions Industrielles, 59 - Dunkerque (France); Adelfa, J.S.; Hocquet, M.P. [CLCV, France (France); Gheerardyn, P. [MEDEF Cote d' Opale (France); Villers, S. [EDA, France (France); Modrzejewski, F. [DRIRE Nord-Pas-de-Calais (France); Gadbois, S.; Heriard-Dubreuil, G. [MUTADIS, 75 - Paris (France); Geismar, N.; Eimer, M. [CLI de Saint-Laurent (France); Andre, S. [CEA Cadarache, 13 - Saint-Paul-lez-Durance (France); Vindimian, E. [Institut National de l' Environnement Industriel et des Risques, 60 - Verneuil en Halatte (INERIS) (France); Remond-Gouilloud, M. [Universite Paris-Sorbonne, 75 (France)

2005-07-01

Following the research work on the ' stakes in the social dialogue around the follow-up of the nuclear industrial installations ' engaged by the I.R.S.N. in 2000, a seminar was organized on January 21. and 22., 2003 in Ville d Avray. This seminar gathered personalities of different origins (administration, institutional experts, operators, associations, Local Commissions of Information, elected representatives) to discuss and enrich the conclusions of the research work and elaborate collectively a contribution to the current remarks in France on the public debate and the processes of dialogue. The present report establishes the acts of this seminar and redraws all the discussions between the participants. (N.C.)

Statement of nuclear incidents at nuclear installations

International Nuclear Information System (INIS)

1993-10-01

Three incidents were reported in April-June 1993. The first was on the British Nuclear Fuel plc (BNFL) site at Sellafield and concerned leakage of 0.5 TBq of alpha activity from plutonium contaminated waste stored in a steel drum. This was subsequently double contained and moved so it could be inspected regularly. No contamination of personnel occurred. The second concerned the leakage of thorium liquor from a pipe at the UKAEA's Thorium reprocessing plant at Dounreay. Two temporary repairs were made and no personnel were contaminated. The third was at the Sellafield site where a small quantity (5 mls) of plutonium containing liquor had leaked from a package and released alpha activity. The bags were temporary containment of engineering debris which may have had sharp edges. The bags had been piled up and one of the bags had torn. Recommendations were made following inquiries into each of the incidents to improve procedures and prevent similar incidents occurring. (UK)

Siting nuclear power plants

International Nuclear Information System (INIS)

Yellin, J.; Joskow, P.L.

1980-01-01

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

Radiation protection in Swiss nuclear installations; Strahlenschutz in Schweizer Kernanlagen

Energy Technology Data Exchange (ETDEWEB)

Hammer, J.; Brunell, M. [Eidgenoessisches Nuklearsicherheitsinspektorat ENSI, Brugg (Switzerland)

2015-07-01

Well developed measures on operational radiation protection within Swiss nuclear installations will be presented. The focus lays on competent authority actions. Results of the last ten years, including events on radiation issues, will be discussed. Finally a view on challenges for radiation protection personnel with respect to a renewed Swiss radiation protection legislation based on recent ICRP recommendations will be given.

Technical Orders of 10 August 1976 on the limits and procedures applicable to radioactive effluent discharges from nuclear installations

International Nuclear Information System (INIS)

1976-01-01

Seven technical Orders by the competent Ministers (mainly the Ministers of Health, of Industry and Research, of the Quality of Life) lay down the procedures, conditions and limits applicable to gaseous and liquid radioactive effluent discharges from nuclear installations. These Orders of 10 August were published on 12 September 1976 in the Official French Gazette and were made in implementation of the Decree of 6 November 1974 on gaseous radioactive effluent discharges from nuclear installations and the Decree of 31 December 1974 on liquid radioactive effluent discharges from nuclear installations. Apart from the general rules for setting limits and methods for effluent discharges, they specify the measures for environmental monitoring and for control by the Central Service for Protection against Ionizing Radiations. Certain of them contain the general rules for liquid or gaseous effluent discharges from all nuclear installations, while others lay down the rules proper to light water nuclear power plants. Other types of reactor ie. fast breeders are not yet subject to such regulations. (N.E.A.) [fr

Childhood leukaemia risks: from unexplained findings near nuclear installations to recommendations for future research

International Nuclear Information System (INIS)

Laurier, D; Jacob, S; Grosche, B; Dehos, A; Hornhardt, S; Ziegelberger, G

2014-01-01

Recent findings related to childhood leukaemia incidence near nuclear installations have raised questions which can be answered neither by current knowledge on radiation risk nor by other established risk factors. In 2012, a workshop was organised on this topic with two objectives: (a) review of results and discussion of methodological limitations of studies near nuclear installations; (b) identification of directions for future research into the causes and pathogenesis of childhood leukaemia. The workshop gathered 42 participants from different disciplines, extending widely outside of the radiation protection field. Regarding the proximity of nuclear installations, the need for continuous surveillance of childhood leukaemia incidence was highlighted, including a better characterisation of the local population. The creation of collaborative working groups was recommended for consistency in methodologies and the possibility of combining data for future analyses. Regarding the causes of childhood leukaemia, major fields of research were discussed (environmental risk factors, genetics, infections, immunity, stem cells, experimental research). The need for multidisciplinary collaboration in developing research activities was underlined, including the prevalence of potential predisposition markers and investigating further the infectious aetiology hypothesis. Animal studies and genetic/epigenetic approaches appear of great interest. Routes for future research were pointed out. (review)

IAEA Assistance in Helping Member States Develop Effectively Independent and Robust Regulators for Nuclear Installation Safety

Energy Technology Data Exchange (ETDEWEB)

Nicic, A., E-mail: A.Nicic@iaea.org [International Atomic Energy Agency (IAEA), Department of Nuclear Safety and Security, Wagramer Strasse 5, P.O. Box 100, 1400 Vienna (Austria)

2014-10-15

Full text: The International Conference on Topical Issues in Nuclear Installation Safety will be focused on the exchange of information on the latest thinking and advances in the implementation of the concept of Defence-in-Depth (DID) in nuclear installations, and the associated challenges. The focus will be on operating nuclear installations, including nuclear power plants, research reactors and fuel cycle facilities, and on how lessons learned from operating experience and recent events (e.g. the Fukushima Daiichi accident) are used to enhance safety. The implementation of DID covers a number of elements that are directly related to the different states and phases of a nuclear facility. This presentation will discuss the importance of the regulatory body in its oversight role as a cross-cutting element of DID in helping to assure the safety of nuclear installations. Taking note of the numerous challenges in developing an effectively independent and robust regulatory body, the presentation will describe how the IAEA assists Member States in their development of the appropriate regulatory infrastructure and necessary capacity to carry out their regulatory responsibilities – consistent with the IAEA Safety Standards. The presentation will describe the importance of the self-assessment process which serves as a starting point for helping Member States gain an understanding of what support they need and when the support should be provided as they develop into a competent regulatory authority. The presentation will discuss recent improvements in the self-assessment process and related IAEA services in this regard. Once regulatory bodies are established, it is essential that they seek continuous improvement. In this regard, the presentation will describe the IAEA’s assistance provided through the Integrated Regulatory Review Service (IRRS) and recent activities to improve the IRRS, consistent with the IAEA’s Action Plan on Nuclear Safety. (author)

Practical design considerations for nuclear cogeneration installations

International Nuclear Information System (INIS)

Koupal, J.R.

1987-01-01

Dual-purpose nuclear plants, cogeneration electricity and steam, offer significant economic benefits over comparable electricity generating stations. The design of such a nuclear facility requires the resolution of unique technical challenges. This paper reports on experience gained in the detailed design of such a dual-purpose facility with the steam supplied to a chemical plant for process heating. The following topics are discussed: Siting, Radioactivity of Export Steam, Optimization for Load Combinations, Steam Supply Reliability, Steam Transportation, Water Chemistry, Cost Allocation. (author)

Nuclear energy - Radioprotection - Procedure for radiation protection monitoring in nuclear installations for external exposure to weakly penetrating radiation, especially to beta radiation

International Nuclear Information System (INIS)

2002-01-01

This International Standard specifies a procedure for radiation protection monitoring in nuclear installations for external exposure to weakly penetrating radiation, especially to beta radiation and describes the procedure in radiation protection monitoring for external exposure to weakly penetrating radiation in nuclear installations. This radiation comprises β - radiation, β + radiation and conversion electron radiation as well as photon radiation with energies below 15 keV. This International Standard describes the procedure in radiation protection planning and monitoring as well as the measurement and analysis to be applied. It applies to regular nuclear power plant operation including maintenance, waste handling and decommissioning. The recommendations of this International Standard may also be transferred to other nuclear fields including reprocessing, if the area-specific issues are considered. This International Standard may also be applied to radiation protection at accelerator facilities and in nuclear medicine, biology and research facilities

Nuclear waste repository siting

International Nuclear Information System (INIS)

Soloman, B.D.; Cameron, D.M.

1987-01-01

This paper discusses the geopolitics of nuclear waste disposal in the USA. Constitutional choice and social equity perspectives are used to argue for a more open and just repository siting program. The authors assert that every potential repository site inevitably contains geologic, environmental or other imperfections and that the political process is the correct one for determining sites selected

2009 transparency and nuclear safety report. CEA Cadarache. Volumes 1 + 2

International Nuclear Information System (INIS)

2009-01-01

After a general presentation of the Cadarache site and of its nuclear installations, the first volume of this report describes the various measures concerning the site safety (safety organisation, general measures, measures related to various risks, inspections, control of emergency situations, audits and second level control, measures in basic nuclear installations) and radioprotection (organisation, significant facts, dosimeter results). It describes significant events which occurred in relationship with nuclear safety and radioprotection, presents results of measurements of releases and of their impact on the environment (chemical and radiological assessment). Then after a description of measures to limit the volume of stored radioactive wastes and their impact on health and on the environment, tables indicate the nature and quantities of wastes which are stored in the different basic nuclear installations of Cadarache. The second volume proposes the same information for two specific nuclear installations belonging to Areva and located in Cadarache, the INB 32 and 54 (INB stands for basic nuclear installation) for which a significant event occurred on the 6 October 2009. For these installations, release measurements concern gaseous and liquid releases

Information report on nuclear safety and radiation protection of the SOMANU site - Issue 2014

International Nuclear Information System (INIS)

2015-01-01

Published in compliance with the French code of the environment, this report first presents different aspects of the SOMANU plant which is dedicated to the maintenance of materials and equipment from nuclear installations: location and environment, history, description of activities, regulatory framework. It describes the various measures regarding nuclear safety and radiation protection: general principles of nuclear safety, organization, presentation of the Areva's nuclear safety Charter, inspections and controls, measures regarding radiation protection. The next part addresses nuclear events which occurred on this site and had to be declared. The report gives an overview of activities and measures regarding the management of releases and the control of the environment. The next part addresses waste management: general considerations on radioactive waste management in France, description and classification of radioactive wastes present in the INB, management of conventional wastes. The management of other impacts is also reported. The last chapter reviews the actions undertaken in the field of transparency and information. Recommendations of the CHSCT are reported

Information report on nuclear safety and radiation protection of the SOMANU site - Issue 2012

International Nuclear Information System (INIS)

2013-06-01

Published in compliance with the French code of the environment, this report first presents different aspects of the SOMANU plant which is dedicated to the maintenance of materials and equipment from nuclear installations: location and environment, history, description of activities, regulatory framework. It describes the various measures regarding nuclear safety and radiation protection: general principles of nuclear safety, organization, presentation of the Areva's nuclear safety Charter, inspections and controls, measures regarding radiation protection. The next part addresses nuclear events which occurred on this site and had to be declared. The report gives an overview of activities and measures regarding the management of releases and the control of the environment. The next part addresses waste management: generalities on radioactive waste management in France, description and classification of radioactive wastes present in the INB, management of conventional wastes. The management of other impacts is also reported. The last chapter reviews the actions undertaken in the field of transparency and information. Recommendations of the CHSCT are reported

Decree 2869/1972 of 21 July approving the Regulations on nuclear and radioactive installations

International Nuclear Information System (INIS)

1972-01-01

This Decree determines nuclear and radioactive installations and establishes their licensing system which is carried out in several stages and differs according to the category concerned. The procedures cover in particular prior authorization, construction licence and operating licence. Provision is also made for inspections. The Annex to the Decree classifies the radionuclides for determining the category of the installation. (NEA) [fr

Chapter No.5. Nuclear materials and physical protection of nuclear installations

International Nuclear Information System (INIS)

2002-01-01

The State System of Accounting for and Control of Nuclear Material (SSAC) is based on requirements resulting from the Safeguards Agreement between the Government of the Slovak Republic and the IAEA. UJD performs this activity according to the 'Atomic Act' and relevant decree. The purpose of the SSAC is also to prevent unauthorised use of nuclear materials, to detect loses of nuclear materials and provide information that could lead to the recovery of missing material. The main part of nuclear materials under jurisdiction of the Slovak Republic is located at NPP Jaslovske Bohunice, NPP Mochovce and at interim storage in Jaslovske Bohunice. Even though that there are located more then 99% of nuclear materials in these nuclear facilities, there are not any significant problems with their accountancy and control due to very simply identification of accountancy units - fuel assemblies, and due to stability of legal subjects responsible for operation and for keeping of information continuity, which is necessary for fulfilling requirements of the Agreement. The nuclear material located outside nuclear facilities is a special category. There are 81 such subjects of different types and orientations on the territory of the Slovak Republic. These subjects use mainly depleted uranium as a shielding and small quantity of natural uranium, low enrichment uranium and thorium for experimental purposes and education. Frequent changes of these subjects, their transformations into the other subjects, extinction and very high fluctuation of employees causes loss of information about nuclear materials and creates problems with fulfilling requirements resulting from the Agreement. In 2001, the UJD carried out 51 inspections of nuclear materials, of which 31 inspections were performed at nuclear installations in co-operation with the IAEA inspectors. No discrepancies concerning the management of nuclear materials were found out during inspections and safeguards goals in year 2001 were

Visitor centres at nuclear facility sites

International Nuclear Information System (INIS)

1993-01-01

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

Seismic qualification of existing nuclear installations in India - a proposal

International Nuclear Information System (INIS)

Basu, P.C.

2001-01-01

In India, the work toward seismic qualification of existing nuclear facilities has been started. Preliminary work is being undertaken with respect to identifying the facilities which would be taken up for seismic qualification, approach and methodology for re-evaluation for seismic safety, acceptance criteria, etc. Work has also been started for framing up the criteria and methodology of the seismic qualification of these facilities. Present paper contains the proposal in this respect. This proposal is on similar lines of the present practice of seismic qualification of NPP, as summarized in the Appendix, but has been modified to suit the special requirements of Indian nuclear installations. (author)

Site selection - siting of the final repository for spent nuclear fuel

International Nuclear Information System (INIS)

2011-03-01

SKB has selected Forsmark as the site for the final repository for spent nuclear fuel. The site selection is the end result of an extensive siting process that began in the early 1990s. The strategy and plan for the work was based on experience from investigations and development work over a period of more than ten years prior to then. This document describes the siting work and SKB's choice of site for the final repository. It also presents the information on which the choice was based and the reasons for the decisions made along the way. The document comprises Appendix PV to applications under the Nuclear Activities Act and the Environmental Code for licences to build and operate an encapsulation plant adjacent to the central interim storage facility for spent nuclear fuel in Oskarshamn, and to build and operate a final repository for spent nuclear fuel in Forsmark in Oesthammar Municipality

Site selection - siting of the final repository for spent nuclear fuel

Energy Technology Data Exchange (ETDEWEB)

2011-03-15

SKB has selected Forsmark as the site for the final repository for spent nuclear fuel. The site selection is the end result of an extensive siting process that began in the early 1990s. The strategy and plan for the work was based on experience from investigations and development work over a period of more than ten years prior to then. This document describes the siting work and SKB's choice of site for the final repository. It also presents the information on which the choice was based and the reasons for the decisions made along the way. The document comprises Appendix PV to applications under the Nuclear Activities Act and the Environmental Code for licences to build and operate an encapsulation plant adjacent to the central interim storage facility for spent nuclear fuel in Oskarshamn, and to build and operate a final repository for spent nuclear fuel in Forsmark in Oesthammar Municipality

Protection of civilian nuclear installations in time of armed conflict

International Nuclear Information System (INIS)

Lamm, V.

2003-01-01

The inclusion of article 56 in Protocol 1 of the Geneva convention of 12 August 1949 represents a significant achievement in the development of international humanitarian law. Article 56 of protocol 1 reads as follow: firstly, works or installations containing dangerous forces, namely dams, dykes and nuclear electrical generating stations, shall not not be made the object of attack, even where these objects are military objectives, if such attack may cause the release of dangerous forces and consequent severe losses among the civilian population. Other military objectives located at or in the vicinity of these works or installations shall not be made the object of attack if such attack may cause the release of dangerous forces from the works or installations and consequent severe losses among the civilian population. Secondly, the special protection against attack provided by paragraph 1 shall cease: for a dam or a dyke only if it is used for other than its normal function and in regular, significant and direct support of military operations and if such attack is the only feasible way to terminate such support; for a nuclear electrical generating station only if it provides electric power in regular, significant and direct support of military operations and if such attack is the only feasible way to terminate such support;for other military objectives located at or in the vicinity of these works or installations only if they are used in regular, significant and direct support of military operations and if such attack is the only feasible way to terminate such support. Thirdly, in all cases, the civilian population and individual civilians shall remain entitled to all the protection accorded them by international law, including the protection of the precautionary measures provided for in article 57. If the protection ceases and any of the works, installations or military objectives mentioned in paragraph 1 is attacked, all practical precautions shall be taken to

Advanced LP turbine installation at 1300 MW nuclear power station Unterweser

International Nuclear Information System (INIS)

Jacobsen, G.; Oeynhausen, H.; Termuehlen, H.

1991-01-01

This paper reports on Preussen Elektra AG's Unterweser power plant. The steam turbine-generator features a disk-type LP turbine rotor design developed in the late 1960's to early 1970's. This rotor design has been installed in 19 nuclear power plants. The 47 rotors in these plants have been in operation for an average of almost 10 years. The design of the 1970 vintage nuclear LP turbine rotors was based on extensive experience gained with disk-type rotors of fossil turbines built in the 1950's. When EPRI reported about corrosion cracking in nuclear LP turbines, a program was initiated by Siemens/KWU as original steam turbine supplier to ultrasonically inspect all their disk-type rotors in nuclear power plats. Indications on one rotor disk in the Unterweser plant was found. This single event was the only one found out of 310 disks inspected in nuclear power plants

Study on the installation of the evacuation guide signs in a nuclear power plant

International Nuclear Information System (INIS)

Matsui, Yuko; Hamasaki, Kenichi; Ohuchi, Hiroko; Akagi, Shigefumi;; Sato, Takeyoshi

2005-01-01

In order to study the desirable sign system that leads people to the proper evacuation behavior in the nuclear plant, an experiment was conducted by using 3D simulation of a part of the nuclear buildings. As the condition of the experiment, 3 different simulations on the type of guide signs and the height of installation were provided. Participants in the experiment were asked: to reach the emergency exit as quickly as possible in case of the imaginary fire, to report the signs utilized for finding the way during his evacuation, and to evaluate their comprehensibility to evaluate synthetically each installation and guide sings from the view point of comprehensibility. Synthetic evaluation was highly rated when we indicated the signs on the face of the floor additionally and installed the guide signs at a height of 1000mm above the floor. For the individual guide sign, it tended to evaluate mostly comprehensible that the pathway guide sign was installed at 1,000mm above the floor, though it did not reach a statistical significant level. Furthermore, the necessity was suggested to take into consideration on the spatial relationship between a moving person and the guide signs. (author)

The nuclear safety authority (ASN) presents its report on the status of nuclear safety and radiation protection in France in 2010

International Nuclear Information System (INIS)

2011-01-01

After a presentation of the French nuclear safety authority (ASN) and of some events which occurred in 2010, this report present the actions performed by the ASN in different fields: nuclear activities (ionizing radiations and risks for health and for the environment), principles and actors of control of nuclear safety, radiation protection and environment protection, regulation, control of nuclear activities and of exposures to ionizing radiations, emergency situations, public information and transparency, international relationship. It proposes a regional overview of nuclear safety and radiation protection in France. It addresses the activities controlled by the ASN: medical and non medical usages of ionizing radiations, transportation of radioactive materials, electronuclear power stations, installations involved in the nuclear fuel cycle, research nuclear installations and other nuclear installations, safety in basic nuclear installation dismantling, radioactive wastes and polluted sites

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

Managing Siting Activities for Nuclear Power Plants

Energy Technology Data Exchange (ETDEWEB)

NONE

2012-06-15

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

Normative questions connected with the procedure for approval and operation of nuclear installations

International Nuclear Information System (INIS)

Nocera, F.

1980-03-01

Recent regulatory developments in the licensing procedure for nuclear installations in Italy are discussed in the light of technical and scientific developments and international rules. The author then discusses the questions likely to be further defined and regulated, i.e. requirements for possession of fuels and fuel storage facilities, nuclear plant decommissioning, protection of the population with reference to the directives of the European Communities. (NEA) [fr

The Regulation of Major Risks in Relation to Large Nuclear Installations in France

International Nuclear Information System (INIS)

Phan Van, L.

1991-01-01

Recently, major risk prevention has generated legislative and regulatory texts in French law, particularly regarding nuclear installations. This article reviews the context and analyses the scope of the new regulations. They require the nuclear operator to take preventive measures, namely more stringent obligations from the safety viewpoint to inform the public. These include risk assessments and preparing emergency plans in case if accidents. (NEA)

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

International Nuclear Information System (INIS)

2009-01-01

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

Manual on quality assurance for installation and commissioning of instrumentation, control and electrical equipment in nuclear power plants

International Nuclear Information System (INIS)

1989-01-01

The present Manual on Quality Assurance (QA) for Installation and Commissioning of Instrumentation, Control and Electrical (ICE) Equipment of Nuclear Power Plants contains supporting material and illustrative examples for implementing basic requirements of the quality assurance programme in procurement, receiving, installation and commissioning of this equipment. The Manual on Quality Assurance for Installation and Commissioning of ICE Equipment is designed to supplement and be consistent with the Guidebook as well as with the IAEA Code and Safety Guides on Quality Assurance. It is intended for the use of managerial staff and QA personnel of nuclear power plant owners or the organizations respectively responsible for the legal, technical, administrative and financial aspects of a nuclear power plant. The information provided in the Manual will also be useful to the inspection staff of the regulatory organization in the planning and performance of regulatory inspections at nuclear power plants

International conference on the operational safety performance in nuclear installations. Contributed papers

International Nuclear Information System (INIS)

2005-01-01

In 2001, the IAEA organized an 'International Conference on Topical Issues in Nuclear Safety'. The issues discussed during the conference were: (1) risk- informed decision-making; (2) influence of external factors on safety; (3) safety of fuel cycle facilities; (4) safety of research reactors; and (5) safety performance indicators. Senior nuclear safety decision makers reviewed the issues and formulated recommendations for future actions by national and international organizations. In 2004, the IAEA organized an 'International Conference on Topical Issues in Nuclear Safety' in Beijing China. The issues discussed during the conference were: (1) changing environment - coping with diversity and globalization; (2) operating experience - managing changes effectively; (3) regulatory management systems - adapting to changes in the environment; and (4) long term operations - maintaining safety margins while extending plant lifetimes. The results of this conference confirmed the importance of operators and regulators of nuclear facilities meeting periodically to share experience and opinion on emerging issues and future challenges of the nuclear industry. Substantial progress has been made, and continues to be made by Member States in enhancing the safety of nuclear installations worldwide. At the same time, more attention is being given to other areas of nuclear safety. The safety standards for research reactors are being updated and new standards are planned on the safety of other facilities in the nuclear fuel cycle. The Agency has taken a lead role in this effort and is receiving much support from its Member States to gain international consensus in these areas. The objective of the conference is to foster the exchange of information on operational safety performance and operating experience in nuclear installations, with the aim of consolidating an international consensus on: - the present status of these issues; - emerging issues with international implications

The Savannah River Site's Groundwater Monitoring Program 1991 well installation report

International Nuclear Information System (INIS)

1992-06-01

This report is a summary of the well and environmental soil boring information compiled for the groundwater monitoring program of the Environmental Protection Department/Environmental Monitoring Section (EPD/EMS) at the Savannah River Site (SRS) during 1991. It includes discussion of environmental soil borings, surveying, well installations, abandonments, maintenance, and stabilization

2007 transparency and nuclear safety report. CEA Cadarache. Volumes 1 + 2

International Nuclear Information System (INIS)

2007-01-01

After a general presentation of the Cadarache site and of its nuclear installations, the first volume of this report describes the various measures concerning the site safety: safety organisation, general measures, measures related to various risks, control of emergency situations, inspections, audits and second level control, measures in basic nuclear installations. It describes the measures concerning the radioprotection on this site: organisation, significant facts, and dose measurement results. It describes significant events which occurred in relationship with nuclear safety and radioprotection, presents results of release measurements and of radiological and chemical assessments of the impact these releases on the environment. The report then describes measures implemented to limit the volume of stored radioactive wastes and also their impact on health and on the environment. It provides a series of tables indicating the nature and quantities of wastes which are stored in the different basic nuclear installations of Cadarache. It reports the recommendations expressed by the CHSCT (committee on hygiene, security and working conditions) after the 2006 report. The second volume proposes the same information for two specific nuclear installations belonging to Areva and located in Cadarache, the INB 32 and 54 (INB stands for basic nuclear installation), for which the significant events occurred on the 13. of March and on the 25. of May 2007. For these installations, release measurements concern gaseous and liquid releases

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

International Nuclear Information System (INIS)

2003-01-01

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

Approach to long- term regalement of nuclear energy installation decommissioning

International Nuclear Information System (INIS)

Dryapachenko, Yi.P.; Rudenko, B. A.; Ozimaj, M.S.

2001-01-01

In this report we make an accent on because the rules of nuclear installation decommissioning should provide controllability with compounded operations not one generations of the performers. The strategy should take into account problems of the economic completion, environment and standards of health, script of decommissioning and its execution, and so on. These strategies are bound with the social conditions, with accent on work with the low level wastes

Performance study of the paints for use in nuclear installations

International Nuclear Information System (INIS)

Yamashita, T.

1978-01-01

The performance of some Brazilian commercial paints under physical, chemical and radiation conditions typical of nuclear installations is studied. Resistance to gama rays in the range of 10 4 - 10 9 rad as well as the susceptibility to contamination, ease of decontamination and chemical resistance in 9 different types of paints are studied. Finally, suggestions are provided for the best choice of commercial paints according to their specific uses [pt

Lifetime Evaluation of Grid-Connected PV Inverters Considering Panel Degradation Rates and Installation Sites

DEFF Research Database (Denmark)

Sangwongwanich, Ariya; Yang, Yongheng; Sera, Dezso

2018-01-01

Lifetime of PV inverters is affected by the installation sites related to different solar irradiance and ambient temperature profiles (also referred to as mission profiles). In fact, the installation site also affects the degradation rate of the PV panels, and thus long-term energy production...... and reliability. Prior-art lifetime analysis in PV inverters has not yet investigated the impact of PV panel degradations. This paper thus evaluates the lifetime of PV inverters considering panel degradation rates and mission profiles. Evaluations have been carried out on PV systems installed in Denmark...... and Arizona. The results reveal that the PV panel degradation rate has a considerable impact on the PV inverter lifetime, especially in the hot climate (e.g., Arizona), where the panel degrades at a faster rate. In that case, the PV inverter lifetime prediction can be deviated by 54%, if the impact of PV...

A future for nuclear sites beyond their service life. Nuclear site value development; Un avenir pour les sites nucleaires en fin de cycle. Valorisation des sites nucleaires

Energy Technology Data Exchange (ETDEWEB)

NONE

2008-07-01

As the nuclear industry moves into a new development phase, many facilities built in the fifties and sixties are reaching the end of their service life. Dismantling them and rehabilitating the sites on which they stand is a major industrial challenge which will give rise to a number of new projects. AREVA has more than 20 years' experience in these highly technical fields. As more and more sites reach the end of their service life, AREVA considers nuclear site value development as a fully-fledged industrial activity. The group's competencies in this field have been grouped together to form a dedicated entity: the Nuclear Site Value Development Business Unit, created in 2008. Several billion euros are invested in site value development projects which are far-reaching and complex, and often last for several decades. Long before work actually begins, lengthy studies and preparations are required to schedule operations, select the techniques to be used and optimize costs and deadlines. The Nuclear Site Value Development BU is currently working on four major projects involving its own facilities and those of the CEA: - La Hague: dismantling of the first generation of used fuel recycling facilities. Between 1966 and 1998, almost 5,000 tons of used fuel from graphite-moderated gas-cooled reactors, 4,500 tons of light water reactor fuel, as well as fuel from fast reactors and research reactors, were treated at UP2 400, the very first industrial recycling plant on the La Hague site. - Marcoule: first-time dismantling of a recycling plant. 1,000 rooms to be cleaned up, 30,000 tons of waste to be treated, 30 years of work. - Cadarache: first-time dismantling of a Mox fuel fabrication plant. The Cadarache plant was commissioned in 1962 to fabricate fuel for fast reactors; this was followed by MOX fuel for light water reactors, an activity which continued until the plant was shut down in 2003. - Annecy and Veurey: giving a new lease of life to former industrial sites

Situation of the environmental surveillance and situation of the water table and rivers labelling around nuclear sites and old radioactive waste storages. Report for the high committee for the transparency and information on nuclear safety

International Nuclear Information System (INIS)

2008-01-01

The High Committee for the openness and information on nuclear safety (H.C.T.I.S.N.) requested a study at I.R.S.N. concerning the situation of the surveillance of media and their quality and the diffusion of this information near the public, the identification of ground water or rivers that would present a radiological or chemical labelling, the link of these elements with the future national network of the radioactivity measurement in environment. This assessment must also allow to take stock of the situation relative to the surveillance of the quality of ground water that flow out of the level of old radioactive waste storages, especially registered in the ANDRA inventory. I.R.S.N. chose to limit its contribution: to the sites housing nuclear base installations and nuclear base installations that have been classified secret that come under the Minister in charge of energy; to old radioactive wastes storages located in these installations. (N.C.)

The dismantling of nuclear installations in the Grenoble CEA centre - Press book 2013

International Nuclear Information System (INIS)

Laveissiere, Stephane; Coronini, Vincent

2013-01-01

After having outlined the importance of the project for the Grenoble CEA centre, this document presents the objectives, issues and challenges of dismantling activities performed on various nuclear installations located in the CEA centre of Grenoble. Objectives are presented in terms of agenda, predicted production of radioactive wastes, budget, personnel and steering committee. The various nuclear installations are presented: experimental reactors (Melusine, Siloe, Siloette), LAMA (laboratory of analysis of active materials), STED (station for the treatment of effluents and wastes). The safety and protection of workers is addressed in terms of protection and monitoring measures, and of exposure to radiations. The next part deals with the monitoring of the environment (actors, history of control of the centre's releases, control points, releases, atmosphere monitoring, and hydrological monitoring). A second part presents the global strategy of the CEA for its activities of sanitation and nuclear dismantling: present operations, dismantling activities in Fontenay-aux-Roses and in Marcoule, economic organization, contribution of advanced technology in radiological measurement and control, simulation and modelling, decontamination techniques, cutting operations, and remotely controlled operations

Nuclear waste: Status of DOE's nuclear waste site characterization activities

International Nuclear Information System (INIS)

1987-01-01

Three potential nuclear waste repository sites have been selected to carry out characterization activities-the detailed geological testing to determine the suitability of each site as a repository. The sites are Hanford in south-central Washington State, Yucca Mountain in southern Nevada, and Deaf Smith in the Texas Panhandle. Two key issues affecting the total program are the estimations of the site characterization completion data and costs and DOE's relationship with the Nuclear Regulatory Commission which has been limited and its relations with affected states and Indian tribes which continue to be difficult

TESLA accelerator installation

International Nuclear Information System (INIS)

Neskovic, N.; Ostojic, R.; Susini, A.; Milinkovic, Lj.; Ciric, D.; Dobrosavljevic, A.; Brajuskovic, B.; Cirkovic, S.; Bojovic, B.; Josipovic, M.

1992-01-01

The TESLA accelerator Installation is described. Its main parts are the VINCY Cyclotron, the multiply charged heavy-ion mVINIS Ion Source, and the negative light-ion pVINIS Ion Source. The Installation should be the principal installation of a regional center for basic and applied research in nuclear physics, atomic physics, surface physics and solid state physics, for production of radioisotopes, for research and therapy in nuclear medicine. The first extraction of the ion beam from the Cyclotron is planned for 1995. (R.P.) 3 refs.; 1 fig

Agreement between Portugal and Spain on cooperation with regard to the safety of nuclear installations in border areas

International Nuclear Information System (INIS)

1980-01-01

This Agreement provides for exchange of information on nuclear safety and radiation protection in nuclear installations likely to affect mutually the territories of Portugal and Spain. The Agreement defines the type of nuclear installation concerned, the border areas and the respective competent authorities. The competent authorities of both Parties undertake to establish in their respective territories, the systems required to detect any radiation emergency and to inform each other in cases where such emergency may affect them. The Agreement was concluded for a period of the years as from its entry into force. (NEA) [fr

Nuclear power plants: recent developments in Brazil relating to the legal aspect of installation - erection - operation

International Nuclear Information System (INIS)

Lima Moreira, Y.M. de.

1981-10-01

A Federal statutory system governs the setting up and operation of nuclear power plants in Brazil. This paper describes the general regulatory framework for electric utilities and in particular analyses the licensing procedure for nuclear installations. (NEA) [fr

The protection of nuclear installations from outside aggressions

International Nuclear Information System (INIS)

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

1976-01-01

When selecting a site for a nuclear power station, the possibility of outside natural aggressions from atmospheric, hydrologic or seismic origin should be carefully considered. The site being chosen, outside natural or non-natural aggressions which are linked to it, such as plane crashes, projectiles, fires, bursting of dams, deliberate human aggressions... should be thoroughly appraised to take them into account when designing the future plant [fr

Nuclear reactor installation with outer shell enclosing a primary pressure vessel

International Nuclear Information System (INIS)

1975-01-01

The high temperature nuclear reactor installation described includes a fluid cooled nuclear heat source, a primary pressure vessel and outer shell around the primary pressure vessel and acting as a protection for it against outside projectiles. A floor is provided internally dividing the outside shell into two upper and lower sections and an inside wall dividing the lower section into one part containing the primary pressure vessel and a second part, both made pressure tight with respect to each other and with the outside shell and forming with the latter a secondary means of containment [fr

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

International Nuclear Information System (INIS)

Ganay, Claude de

2015-01-01

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

IAEA Assistance to developing countries in the regulation of nuclear installations

International Nuclear Information System (INIS)

Phuong, H.V.

1977-01-01

The paper analyses the IAEA assistance to developing countries in the regulation of nuclear installations. The projected growth of nuclear power both in industrialised and developing IAEA Member States has led to a reassessment of the role that the Agency should play pursuant to its statutory obligation in the area of nuclear safety. Accelerated work was begun nearly 3 years ago to establish a wide range of recommendations essential in matters of nuclear power plant safety so as to provide an internationally acceptable body of basic criteria and minimum requirements. In recent years the IAEA has increasingly provided advisory services to developing countries for the elaboration of enabling legislation; also intensive training programmes covering specific nuclear safety and regularoty topics have been carried out through special training courses and conducted in co-operation with host countries with extensive nuclear experience and appropriate training facilities. Experience has shown that these services have been of practical help to national authorities in providing guidance and initiatives for speeding up the process of framing laws and regulations. (NEA) [fr

Recommendations for the drafting of annual reports of public information related to nuclear base installations - Guide nr 3, Release of the 20/10/2010

International Nuclear Information System (INIS)

2010-01-01

After a recall of the regulatory context and references, this guide proposes a set of recommendations aiming at a better transparency of information in the nuclear sector. It contains general recommendations (notably making the report accessible to a large public, writing a document per site, limiting the size of reports, adopting a common plan for each report), proposes a typical plan (description of installations, measures related to nuclear security and radiation protection, incidents and accidents, releases, management of radioactive wastes and products, other risks and pollutions, actions regarding transparency and information, recommendations by the CHSCT), and addresses the report diffusion

Technical organization of safety authorities for the event of an accident at a nuclear installation

International Nuclear Information System (INIS)

Scherrer, J.; Evrard, J.M.; Ney, J.

1986-01-01

Within the general context of nuclear safety, the Central Nuclear Installation Safety Service of the French Ministry for Industry and its technical backup, the Institute for Radiation Protection and Nuclear Safety of the CEA (Atomic Energy Commission), have established a special organization designed to provide real-time forecasts of the evolution of a nuclear accident situation with sufficient forewarning for the local representative of the Government (the Commissaire de la Republique in the Departement affected) to implement, as required, effective countermeasures to protect the population - for example, confinement indoors or evacuation. Descriptions are given of the principles of this organization and the particular precautions taken to confront the problems of mobilizing experts and of dealing with the saturation of normal telecommunications channels to be expected in the event of a nuclear accident. The organization set up for the installations belonging to Electricite de France is given as a detailed example. Particular stress is placed on the organizational arrangements of the Institute for Radiation Protection and Nuclear Safety designed to provide the emergency teams with the evaluation and forecasting tools they require to carry out their tasks. The procedures are on the whole well developed for atmospheric radioactivity transport, for which operational models already exist. Computer-backed methods with improved performance are at present being developed. A method of forecasting the behaviour of the releases resulting from nuclear accidents is set out for pressurized water reactors, based on evaluating the physical state of the installation, confinement integrity, availability of safety and backup systems, support systems and feed sources and on forecasting how this state will develop on the basis of measured and inferred physical values transmitted from the affected power station through a national network. The experience acquired during accident

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

International Nuclear Information System (INIS)

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

2012-01-01

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

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

Energy Technology Data Exchange (ETDEWEB)

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

2012-06-01

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

Statutory Instrument No. 125, The Nuclear Installations (Gilbert and Ellice Islands) Order 1972

International Nuclear Information System (INIS)

1972-01-01

This Order extends to the Gilbert and Ellice Islands, with the exceptions, adaptations and modifications specified in the Schedule to the Order, certain provisions of the Nuclear Installations Act 1965, as amended. It is the 1965 Act which implements the provisions of the Paris Convention and the Brussels Supplementary Convention in the United Kingdom. The provisions so extended impose a duty on the nuclear operator to secure that no nuclear occurrence taking place within the territorial limits of the Gilbert and Ellice Islands causes nuclear injury or damage, and relate to the right to compensation for breach of that duty, the bringing and satisfaction of claims and other matters. (NEA) [fr

Statutory Instrument No. 125, The Nuclear Installations (Falkland Islands and Dependencies) Order 1972

International Nuclear Information System (INIS)

1972-01-01

This Order extends to the Falkland Islands, with the exceptions, adaptations and modifications specified in the Schedule to the Order, certain provisions of the Nuclear Installations Act 1965, as amended. It is the 1965 Act which implements the provisions of the Paris Convention and the Brussels Supplementary Convention in the United Kingdom. The provisions so extended impose a duty on the nuclear operator to secure that no nuclear occurrence taking place within the territorial limits of the Falkland Islands causes nuclear injury or damage, and relate to the right to compensation for breach of that duty, the bringing and satisfaction of claims and other matters. (NEA) [fr

Statutory Instrument No. 122, The Nuclear Installations (British Solomon Islands Protectorate) Order 1972

International Nuclear Information System (INIS)

1972-01-01

This Order extends to the British Solomon Islands Protectorate, with the exceptions, adaptations and modificatons specified in the Schedule to the Order, certain provisions of the Nuclear Installations Act 1965, as amended. It is the 1965 Act which implements the provisions of the Paris Convention and the Brussels Supplementary Convention in the United Kingdom. The provisions so extended impose a duty on the nuclear operator to secure that no nuclear occurrence taking place within the territorial limits of the British Solomon Islands Protectorate causes nuclear injury or damage, and relate to the right to compensation for breach of that duty, the bringing and satisfaction of claims and other matters. (NEA) [fr

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

Security of a nuclear material in an installation is determined by how far the installation is to assure that nuclear material remains at a predetermined location

International Nuclear Information System (INIS)

Djoko Hari Nugroho

2010-01-01

This paper observed a preliminary design on nuclear material tracking system in the installation for decision making support based on multi sensor fusion that is reliable and accurate to ensure that the nuclear material remains inside the control area. Capability on decision making in the Management Information System is represented by an understanding of perception in the third level of abstraction. The second level will be achieved with the support of image analysis and organizing data. The first level of abstraction is constructed by merger between several CCD camera sensors distributed in a building in a data fusion representation. Data fusion is processed based on Wavelett approach. Simulation utilizing Matlab programming shows that Wavelett fuses multi information from sensors as well. Hope that when the nuclear material out of control regions which have been predetermined before, there will arise a warning alarm and a message in the Management Information System display. Thus the nuclear material movement time event can be obtained and tracked as well. (author)