Safety of nuclear installations in Slovakia

International Nuclear Information System (INIS)

1998-01-01

In this part next aspects are described: (1) Site selection (Legislation related to site selection; Meeting criteria at Bohunice and Mochovce sites; International agreements); (2) Design preparation and construction (Designing and construction-relevant legislation; Nuclear installation project preparation of nuclear installation at Mochovce site); (3) Operation (Operator licensing procedure; Operation limits and conditions; Maintenance testing and control documentation for management and operation; Technical support of operation; Analysis of events at nuclear installations and Radioactive waste production); (4) Planned safety upgrading activities at nuclear installations

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)

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)

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

German-Brazilian nuclear deal

International Nuclear Information System (INIS)

Krugmann, H.

1981-01-01

Examination of the arguments in favor of the nuclear deal with West Germany and the resulting program suggests that revisions of both are in order to make them more compatible with Brazil's national interests. The deficiencies of current policy appear to be too weighty and numerous to be ignored. Sooner or later the government will have to move toward adjusting its nuclear agreement with West Germany, if not for the reasons discussed here then for lack of capital. Current estimates of the nuclear package lie in the range of $25 to $30 billion, compared to an initial projection of about $5 billion. The deal has become so expensive that it would draw capital from the hydropower and alcohol programs essential for the short and medium-term energy needs of the country. Mr. Krugman feels the Brazilian government should hold off on further nuclear contracts. And it should thoroughly reassess what Brazil's nuclear energy and technology requirements are and how to meet them. There are indications that the reassessment process is already underway. As long as the German nuclear industry depends on the sale of technology to Brazil, the Brazilian government will have considerable bargaining power to enforce further changes in the deal. If this power is used wisely, the result could be cooperation between the two countries toward nuclear options that are consistent with Brazil's energy and development needs

Brazilian emergency planning for radiological accidents

International Nuclear Information System (INIS)

Mendonca, A.H.

1986-01-01

Brazilian emergency planning for radiological accidents is organized to respond promptly to any emergency at nuclear power plants or other installations utilizing nuclear fuel. It consists of several committees: a general coordination committee with representatives from several federal departments, with final decision with the Brazilian Nuclear Energy Commission (CNEN), and the Federal Environmental Protection Agency (SEMA). Some committees conduct support activities. For example, the Operational Coordination Committee supervises the tasks undertaken by the Army, Navy, and Air Force in response to the needs and decisions of the general coordination committee

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

Genesis of the Brazilian nuclear power plants program

International Nuclear Information System (INIS)

Syllus, G.; Lepecki, W.

1996-01-01

The genesis of the Brazilian Nuclear Power Program is described by the authors - who participated in the events - from the beginning of the sixties, until the definition and the start of the implementation in 1975 of the Reference Nuclear Power Program. A description is made of the main events, studies and decisions that contributed to the evolution of the Program: the GTRP (Nuclear Power Plant Working Group); the Thorium Group; the Lane Group; the decision about Angra 1; CNEN's analyses about the reactor line and, finally, the creation of CBTN (Nuclear Technology Brazilian Company), which elaborated the studies that resulted in the final definition of the Program and led to the Brazilian German Agreement and the establishment of NUCLEBRAS. (author)

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

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

Organization and development of the Brazilian nuclear programme

International Nuclear Information System (INIS)

Pinto, C.S.M.; Souza, J.A.M. de; Grinberg, M.; Alves, R.N.; Costa, H.M. da; Grimberg, M.

1977-01-01

The paper presents the Brazilian Nuclear Energy Programme, its development, the organizations and the distribution of responsibilities involved in its execution at the present time. The nuclear power policy is established at the Presidency of the Republic and is planned, executed and controlled through the Ministry of Mines and Energy. Directly subject to the Ministry is the Brazilian Nuclear Energy Commission (CNEN), which has regulatory, standardization, licensing, planning and surveillance functions. The nuclear fundamental research and manpower formation are also under CNEN responsibility. Also subject to the Ministry are two companies responsible for the execution of the Programme: the Centrais Eletricas Brasileiras S.A. - Eletrobras, which advises on the granting of permits for the construction and operation of nuclear power plants, and the Empresas Nucleares Brasileiras S.A. - Nuclebras, which holds the monopoly of the nuclear fuel cycle in the country, designs and builds nuclear power plants and provides assistance to the electric utilities and promotes the participation of Brazilian industry. Besides describing the new distribution of regulatory functions given by law to CNEN, the paper gives special emphasis to the large industrial complex in the process of being established through the setting-up of the many Nuclebras subsidiaries in joint venture with German firms under the Industrial Co-operation Agreement Between Brazil and the Federal Republic of Germany in the Field of the Peaceful Uses of Nuclear Energy. The programmes for these subsidiaries are presented and their participation in the Brazilian Nuclear Energy Programme is discussed. The technology transfer aspects of the industrial activities are also discussed. (author)

Site evaluation for nuclear installations. Safety requirements

International Nuclear Information System (INIS)

2003-01-01

This Safety Requirements publication supersedes the Code on the Safety of Nuclear Power Plants: Siting, which was issued in 1988 as Safety Series No. 50-C-S (Rev. 1). It takes account of developments relating to site evaluations for nuclear installations since the Code on Siting was last revised. These developments include the issuing of the Safety Fundamentals publication on The Safety of Nuclear Installations, and the revision of various safety standards and other publications relating to safety. Requirements for site evaluation are intended to ensure adequate protection of site personnel, the public and the environment from the effects of ionizing radiation arising from nuclear installations. It is recognized that there are steady advances in technology and scientific knowledge, in nuclear safety and in what is considered adequate protection. Safety requirements change with these advances and this publication reflects the present consensus among States. This Safety Requirements publication was prepared under the IAEA programme on safety standards for nuclear installations. It establishes requirements and provides criteria for ensuring safety in site evaluation for nuclear installations. The Safety Guides on site evaluation listed in the references provide recommendations on how to meet the requirements established in this Safety Requirements publication. The objective of this publication is to establish the requirements for the elements of a site evaluation for a nuclear installation so as to characterize fully the site specific conditions pertinent to the safety of a nuclear installation. The purpose is to establish requirements for criteria, to be applied as appropriate to site and site-installation interaction in operational states and accident conditions, including those that could lead to emergency measures for: (a) Defining the extent of information on a proposed site to be presented by the applicant; (b) Evaluating a proposed site to ensure that the site

Organization and development of the Brazilian nuclear program

International Nuclear Information System (INIS)

Pinto, C. Syllus M.; Alves, R. Nazare; Lepecki, W.; Costa, H.M. da; Grinberg, M.; Grimberg, M.

1977-01-01

The paper presents the Brazilian Nuclear Energy Program: its development until the present stage, as well as the organizations and the distribution of responsibilities involved in its execution at the present time. The nuclear power policy is established at the Presidency of the Republic and is planned, executed and controlled through the Ministry of Mines and Energy. Directly subject to the Ministry is the Brazilian Nuclear Energy Commission (CNEN), which has regulatory, standardization, licensing, planning and surveillance functions. The nuclear fundamental research and manpower formation are also under CNEN responsibility. Also subject to the Ministry are two companies responsible for the execution of the Programme: the Centrais Eletricas Brasileiras S.A. - ELETROBRAS, which advises on the granting of permits for the construction and operation of nuclear power plants, and the Empresas Nucleares Brasileiras S.A. - NUCLEBRAS, which holds the monopoly of the nuclear fuel cycle in the country, designs and builds nuclear power plants and provides assistance to the electric utilities as well as promotes the participation of the Brazilian industry in the nuclear field. Besides describing the new distribution of regulatory functions given by law to the CNEN, this paper gives special emphasis to the large industrial complex which is in the process of being established with the setting-up of the many NUCLEBRAS subsidiaries in joint-venture with German firms in the nuclear field, as a consequence of the Industrial Cooperation between Brazil and the Federal Republic of Germany in the Field of the Peaceful Uses of Nuclear Energy signed between the two countries on June 27, 1975. The programs for these subsidiaries are presented and their participation in the Brazilian Nuclear Energy Programme is discussed. The technology transfer aspects of the industrial activities are also discussed, based on the Government's policy on the subject [es

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

Review of the Brazilian experience in the licensing of nuclear power plants

International Nuclear Information System (INIS)

Lederman, L.; Laborne, J.J.

1983-01-01

Survey of the licensing of the Brazilian Nuclear Power Plants (NPPs) is presented. The organization and technical expertise of the Comissao Nacional de Energia Nuclear, the Brazilian Regulatory Body, is reviewed with regard to in-house experience, foreign consultants, agreements with regulatory bodies of other countries and research contracts with Brazilian univerisities. The application of the two-stage licensing process and the stage of development of Brazilian nuclear standards is described. Finally, the paper speculates about the future role of probabilistic risk assessment in the Brazilian licensing process

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

Importance of the licensing process on the safety culture in the Brazilian nuclear fuel cycle facilities

International Nuclear Information System (INIS)

Motta, E.S.; Sousa, A.L.B. de; Paiva, R.L.C. de; Mezrahi, A.

2013-01-01

The main objective of the Nuclear Fuel Cycle Facilities licensing processes is to ensure the safety of these installations in their entire life cycle (in the installation site selection, designing, construction, pre-operational tests, operational and decommissioning phases). The Brazilian licensing process requires from the operator, among others, before the operating license: (I) a Site Report and a Final Safety Analysis Report, ensuring that all safety related issues are adequately analyzed and understood; (II) a formal structured Management System focused on the installation safety; and (III) dissemination of safety related information to all involved operator employees and subcontractors. Therefore, these requirements reflect in an adequate operator actions and practices, ensuring a working environment with a high level of safety culture. (author)

Importance of the licensing process on the safety culture in the Brazilian nuclear fuel cycle facilities

Energy Technology Data Exchange (ETDEWEB)

Motta, E.S.; Sousa, A.L.B. de; Paiva, R.L.C. de; Mezrahi, A., E-mail: emotta@cnen.gov.br [Comissao Nacional de Energia Nuclear (CNEN-RJ), Rio de Janeiro, RJ (Brazil)

2013-07-01

The main objective of the Nuclear Fuel Cycle Facilities licensing processes is to ensure the safety of these installations in their entire life cycle (in the installation site selection, designing, construction, pre-operational tests, operational and decommissioning phases). The Brazilian licensing process requires from the operator, among others, before the operating license: (I) a Site Report and a Final Safety Analysis Report, ensuring that all safety related issues are adequately analyzed and understood; (II) a formal structured Management System focused on the installation safety; and (III) dissemination of safety related information to all involved operator employees and subcontractors. Therefore, these requirements reflect in an adequate operator actions and practices, ensuring a working environment with a high level of safety culture. (author)

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)

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.

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)

An Unusual Partnership: Brazilian-Italian Forms of Cooperation in the Nuclear Field (1951-1986)

International Nuclear Information System (INIS)

Patti, Carlo

2017-01-01

This chapter discusses the Brazilian-Italian cooperation in the nuclear field between the early 1950s and 1986. Since the late 1930s, Italian or Italian-Brazilian scientists promoted the development of studies in nuclear physics. Immediately after World War II, the Brazilian-Italian collaboration continued. Between the 1950s and the 1970s, Brazilian nuclear scientists studied in Italian institutions. Relying on primary sources from Brazilian archives and oral history interviews with protagonists of the Brazilian nuclear program, this chapter explore the relations between Italy and Brazil from 1951, the year of the establishment of the Brazilian nuclear program, until the 1980s. This study focuses on the bidirectional transfer of knowledge on sensitive technologies, and on the formal and informal cooperation between the two countries.

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)

Actualization of the Brazilian nuclear regulations

International Nuclear Information System (INIS)

Wieland, Patricia; Soares, Abner Duarte; Nogueira, Tindyua de Moraes; Monteiro, Iara Arraes; Pitta, Maria Adelia Rocha; Bruno, Natanael Carvalho; Pereira, Enneite Souza; Pinto, Marvio dos S.; Lidington, Regina Marcia Rocha; Rocha, Marco Aurelio Toledo

2011-01-01

The present work has the objective of making public the methodological approach adopted by the Brazilian Nuclear Energy Commission (CNEN) to create a nuclear normative structure up-dated and coherent. According to the Law 4118/62, 6189/74 and 7781/89, is the attribution the CNEN to establish specific guidelines for nuclear safety and radiological protection, and also do dictate safety norms through the emission of Resolutions

Leukaemia near british nuclear installations

International Nuclear Information System (INIS)

Hubert, D.

1991-01-01

An excess of childhood leukaemia has been seen near some British nuclear installations, especially near the Sellafield reprocessing plant. The same result was found in a more general study including a large number of nuclear sites. Similar studies made in USA, Canada and France have been negative. Moreover, epidemiological studies made in England have discovered other childhood leukaemia clusters in areas far from nuclear facilities, and especially near potential sites of nuclear installations. Several explanations are suggested but no definite conclusion is yet possible. Doses from radioactive releases seem to be too low to account for the additional deaths from leukaemia by environmental contamination. A virus activation, which might be associated with population influx into rural isolated areas, has been considered. The hypothesis of genetic mutation induced by ionising radiation in the fathers of children with leukaemia has been made because a higher risk of leukaemia was observed for children of fathers employed at Sellafield. No firm conclusion is possible considering the small number of observed cases and the lack of excess leukaemias in the offspring of Hiroshima and Nagasaki survivors. The possibility of internal contamination, chemicals or even radon is discussed as other causes. Studies in progress might allow to find an answer to the problem of leukaemia in the vicinity of British nuclear installations [fr

Economical and strategical aspects of Brazilian-Germany nuclear agreement

International Nuclear Information System (INIS)

Carvalho, J.F. de.

1981-01-01

The strategical and economical aspects of Brazilian-Germany nuclear agreement are analyzed in three aspects: 1) The nuclear agreement in the context of the Brazilian economic - and social development process, considering the availability of energetic resouces of the country. Political implications. Considerations about creation and transfer of technology. 2) The economy aspects involved in the agreement. Comparison costs of electrical energy generated in a nuclear power plants and hydroelectric plant in Brazil. Impacts on the industrial development. 3) Strategical aspects. (E.G.) [pt

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)

The new Brazilian legislation on nuclear protection

International Nuclear Information System (INIS)

Fischer, Denise

1981-10-01

This paper considers the new system on nuclear protection in Brazil which was established to integrate all government agencies and private bodies involved in nuclear activities. The role of each organisation is analysed in relation to the Brazilian political and administrative structure, in particular that of the Nuclear Energy Commission. (NEA) [fr

Brazilian nuclear legislation. Revision n.1/2002

International Nuclear Information System (INIS)

Matos, Gilberto Cardoso de

2002-01-01

This work intends to facilitate the access to the Brazilian nuclear legislation and other legal instruments, foreseeing the use of nuclear energy and ionizing radiation in health, work and environment areas up to 2002. Legislation on the civil liability of nuclear damage, the law of licensing taxes, controlling and inspection are also included

Nuclear future: thinking for building. Proceedings of the 12. Brazilian national meeting on reactor physics and thermal hydraulics; 8. General congress on nuclear energy; 5. Brazilian national meeting on nuclear applications

International Nuclear Information System (INIS)

2000-01-01

These proceedings, for the first time, present jointly the 12. Brazilian national meeting on reactor physics and thermal hydraulics (12 ENFIR), 8. General congress on nuclear energy (8. CGEN), and 5. Brazilian national meeting on nuclear applications (5. ENAN). The main theme of discussion was: 'Nuclear Future: thinking for building'. The papers have analysed the progresses of peaceful utilization of nuclear technology and its forecasting for the beginning of the new millennium. The construction of Angra-3 nuclear power plant have been discussed

The Brazilian Nuclear Energy Commission and the health

International Nuclear Information System (INIS)

Anon.

1987-01-01

The Program of Health Section / Brazilian Cnen, which was elaborated to promote the use of ionizing radiations (nuclear and x-ray techniques) in benefit of Brazilian health, with safety assurance of patients, personnels, population and environment, is presented. The Ministry of Health, industries, Medical and Physicist Associations, Universities and Research Centers are participants of this program. The activities involved in the program are: production of isotopes and radiopharmaceuticals; radiation detectors and nuclear instrumentation; radiation protection and dosimetry; education and training of human resources; applied research and new technologies. The guiding and actions that the section will adopt to attend the growing necessities of Brazilian society, considering technological powers, management, available substructure and associated difficulties are defined. (M.C.K.) [pt

The Management System for Nuclear Installations (Russian Edition)

International Nuclear Information System (INIS)

2014-01-01

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 installation. (f

The Management System for Nuclear Installations Safety Guide

International Nuclear Information System (INIS)

2009-01-01

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 installation. (f

Nuclear future: thinking for building. Proceedings of the 5. Brazilian national meeting on nuclear applications; 8. General congress on nuclear energy; 12. Brazilian national meeting on reactor physics and thermal hydraulics

International Nuclear Information System (INIS)

2000-01-01

These proceedings, for the first time, present jointly the 12. Brazilian national meeting on reactor physics and thermal hydraulics (12. ENFIR), the 8. General congress on nuclear energy (8. CGEN), and the 5. Brazilian national meeting on nuclear applications (5. ENAN). The main theme of discussion was: 'Nuclear Future: thinking for building'. The papers have analysed the progresses of peaceful utilization of nuclear technology and its forecasting for the beginning of the new millennium. The construction of Angra-3 nuclear power plant have been discussed

Chapter 4. Assessment and inspection of nuclear installations

International Nuclear Information System (INIS)

2001-01-01

Supervisory activity of Nuclear Regulatory Authority of the Slovak Republic (UJD) upon the safety of nuclear installations in compliance with the 'Atomic Act' and other legal regulations includes also inspection and assessment activities of UJD. Assessment activity of UJD in relation to nuclear installations lies in assessment of safety documentation for constructions realised as nuclear installations, or constructions through which changes are realised on nuclear installations. The scope of safety documentation required for the assessment is stipulated in the Atomic Act. In 2000 the assessment activity focused first of all on Unit 1 of NPP Bohunice after completing its Gradual Reconstruction Programme, on National Repository of Radioactive waste in Mochovce and on radioactive waste conditioning and treatment technology in Jaslovske Bohunice. Activities of UJD in assessment focused mainly on control of compliance with requirements for nuclear safety, assessment of commissioning programmes, operating procedures, limits and conditions, etc. The assessment of changes, which influence nuclear safety of nuclear installations in operation, realisation of which is conditioned by the approval from UJD, is a significant part of the assessment activity of UJD. Mainly it is the assessment of design changes, changes in limits and conditions, operating procedures, changes in programmes of periodical testing of equipment important in terms of nuclear safety, changes in physical protection of nuclear equipment, etc. The assessment of nuclear installations operational safety, based on assessment of operational events, on maintaining limits and conditions of safe operation, on operational safety performance indicators and on inspection results is a separate category in the assessment activity of UJD. Inspection activity specified in the 'Atomic Act' is governed by an internal guideline, an important part of which is an annual inspection plan that considers the following types of

Complex organizations: the case of the Brazilian nuclear sector

International Nuclear Information System (INIS)

Xavier, Roberto Salles

2009-01-01

The resumption of the Brazilian Nuclear Program (BNP), in the proposed size and after 20 years of paralysis, requires profound changes in the current organizational modeling of the national nuclear industry. The effectiveness of any process of organizational change is limited to three factors. The theoretical bottleneck happens when you do not know enough about a phenomenon in order to effect the desired changes. The resource bottleneck occurs when knowledge may be available to change people's behavior but the funds necessary for implementation may be lacking. The organizational bottleneck emerges when there are knowledge and resources to solve a problem, but may not able to organize the resources in order to carry out the problem-solving effort. In the case of resumption of BNP seems clear that there is the knowledge of what is needed to make policy and the intention to allocate the necessary resources. But the question is the following: the current organizational model of the Brazilian nuclear sector is consistent with the goals laid down in the scenario of resumption of BNP? That is, is there organizational ability to leverage a program of the size proposed for the nuclear area? Find answers to these questions is crucial, because the organizational model of the Brazilian nuclear sector consists of elements involving a complex interorganizational system. Thus, this article is to examine the appropriateness of the current organizational modeling of the Brazilian nuclear sector to current demands of society. As a result, the article aims to propose recommendations for a remodeling of the nuclear sector, taking into account the current national and international scenarios of nuclear energy. (author)

The nuclear contribution to the solution of Brazilian energy problem

International Nuclear Information System (INIS)

1995-01-01

This report presents the justifying of Brazilian Nuclear Programme. Due to the demand increasing of electric energy in Brazil, the government decided to an alternative source. Although the brazilian electric power program continue basically hydroelectric, the nuclear power plants began to be constructed. The strategy adopted, the prospection of uranium enrichment, the project and construction of nuclear power plants, the responsibilities of Nuclebras and Nuclen and several stages of this program are described. (C.M.)

1993 Annual report of the Brazilian-Argentine Agency for Accounting and Control of Nuclear Materials - ABACC

International Nuclear Information System (INIS)

1994-01-01

The 1993 annual report of the Brazilian Argentine Agency for Accounting and Control of Nuclear Materials, (ABACC), describes the activities regarding the administration and application of the Control and Accounting Common System (SCCC) established by the bilateral agreement between the Republic of Argentine and Federative Republic of Brazil for exclusive peaceful use of the nuclear energy. The main goal to verify practically all the installations which were not subjected to the international safeguards, before the agreement, was reached. Considering the safeguards application under implementation in both countries, the ABACC is preparing itself technically for the quadripartite agreement to be into force and signed among Argentine, Brazil, IAEA and ABACC. On checking the procedures established by the SCCC and controlled material, nothing was detected that could indicate nuclear material diversion either for nuclear weapon or for other explosive nuclear device. (B.C.A.)

National report of Brazil: nuclear safety convention - September 1998

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-09-01

This National Report was prepared by a group composed of representatives of the various Brazilian organizations with responsibilities in the field of nuclear safety, aiming the fulfilling the Convention of Nuclear Energy obligations. The Report contains a description of the Brazilian policy and programme on the safety of nuclear installations, and an article by article description of the measures Brazil is undertaking in order to implement the obligations described in the Convention. The last chapter describes plans and future activities to further enhance the safety of nuclear installations in Brazil.

National report of Brazil: nuclear safety convention - September 1998

International Nuclear Information System (INIS)

1998-09-01

This National Report was prepared by a group composed of representatives of the various Brazilian organizations with responsibilities in the field of nuclear safety, aiming the fulfilling the Convention of Nuclear Energy obligations. The Report contains a description of the Brazilian policy and programme on the safety of nuclear installations, and an article by article description of the measures Brazil is undertaking in order to implement the obligations described in the Convention. The last chapter describes plans and future activities to further enhance the safety of nuclear installations in Brazil

Demographic characteristics of nuclear installations sites

International Nuclear Information System (INIS)

Doumenc, A.; Faure, J.

1988-01-01

The selection of a nuclear installations sites can not be conceived without a deep analysis of demographic context. This analysis permits to define the critical populations around the installation and is an essential element of emergency plans. 1 tab., 2 refs. (F.M.)

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

Management report 2004 CNEN - Brazilian Nuclear Energy Commission

International Nuclear Information System (INIS)

2005-03-01

This document reports the results of the activity management of the Comissao Nacional de Energia Nuclear - CNEN - Brazil during the year of 2004, involving the Brazilian program of nuclear activities in the areas of nuclear safety, research and development, radiopharmaceutical production, institutional management, teaching, administration in general and miscellaneous

Management report 2006 CNEN - Brazilian Nuclear Energy Commission

International Nuclear Information System (INIS)

2007-03-01

This document reports the results of the activity management of the Comissao Nacional de Energia Nuclear - CNEN - Brazil during the year of 2005, involving the Brazilian program of nuclear activities in the areas of nuclear safety, research and development, radiopharmaceutical production, institutional management, teaching, administration in general and miscellaneous

Management report 2005 CNEN - Brazilian Nuclear Energy Commission

International Nuclear Information System (INIS)

2006-03-01

This document reports the results of the activity management of the Comissao Nacional de Energia Nuclear - CNEN - Brazil during the year of 2005, involving the Brazilian program of nuclear activities in the areas of nuclear safety, research and development, radiopharmaceutical production, institutional management, teaching, administration in general and miscellaneous

The Brazilian emergency response system

International Nuclear Information System (INIS)

Santos, Raul dos

1997-01-01

With the objective of improving the response actions to potential or real emergency situations generated by radiological or nuclear accidents, the Brazilian National Nuclear Energy Commission (CNEN) installed an integrated response system on a 24 hours basis. All the natiowide notifications on events that may start an emergency situation are converged to this system. Established since July 1990, this system has received around 300 notifications in which 5% were classified as potential emergency situation. (author)

The nuclear agreement with Germany in the context of Brazilian 'model' and the crisis

International Nuclear Information System (INIS)

Rosa, L.P.; Pires, R.L.N.F.

1984-01-01

The Brazilian Nuclear Program is discussed in the context of the so-called Brazilian 'model' which conditions the industrial and technological structure of Brazil. The relations between the Brazilian private industry, the Brazilian state industry and the foreign multinational industry in the nuclear agreement Brazil - Germany are indicated. The economic crisis, the 'energy crisis', the mistakes of the nuclear program, the political fight for the revision of the agreement, the present situation and the problems of technological transfer are also discussed. Some alternatives are suggested for NUCLEBRAS. In an annex, comments are made on the question of Brazilian reactors safety. The so-called system of Protection to the Nucleare Program is also mentioned. (I. de C.R.) [pt

Brazilian nuclear programme - energy in Brazil

International Nuclear Information System (INIS)

Lima, J.O.V.

1988-01-01

The brazilian energetic model, highly dependent of petroleum, have been changed in the sense to adopt diversified and regionalized solutions. This paper describes the role and the perspective of the nuclear energy in this context. (M.I.)

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

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

Management report 2007 CNEN - Brazilian Nuclear Energy Commission

International Nuclear Information System (INIS)

2007-01-01

This document reports the general activity management of the Comissao Nacional de Energia Nuclear - CNEN - Brazil during the year of 2007, involving the CNEN role in the public policy execution, the Brazilian program of nuclear activities in the areas of nuclear safety, research and development, radiopharmaceutical production, teaching, administration in general and miscellaneous

Actualization of the Brazilian nuclear regulations; Atualizacao das normas nucleares brasileiras

Energy Technology Data Exchange (ETDEWEB)

Wieland, Patricia; Soares, Abner Duarte; Nogueira, Tindyua de Moraes; Monteiro, Iara Arraes; Pitta, Maria Adelia Rocha; Bruno, Natanael Carvalho; Pereira, Enneite Souza; Pinto, Marvio dos S.; Lidington, Regina Marcia Rocha; Rocha, Marco Aurelio Toledo, E-mail: pwieland@cnen.gov.b, E-mail: asoares@cnen.gov.b, E-mail: tnogueira@cnen.gov.b, E-mail: iara@cnen.gov.b, E-mail: mpitta@cnen.gov.b, E-mail: nbruno@cnen.gov.b, E-mail: espereira@cnen.gov.b, E-mail: marvio@cnen.gov.b, E-mail: , E-mail: rmliding@cnen.gov.b, E-mail: mtoledo@cnen.gov.b [Comissao Nacional de Energia Nuclear (CNEN), Rio de Janeiro, RJ (Brazil). Div. de Normas

2011-10-26

The present work has the objective of making public the methodological approach adopted by the Brazilian Nuclear Energy Commission (CNEN) to create a nuclear normative structure up-dated and coherent. According to the Law 4118/62, 6189/74 and 7781/89, is the attribution the CNEN to establish specific guidelines for nuclear safety and radiological protection, and also do dictate safety norms through the emission of Resolutions

Activity report 2006 - INB - Brazilian Nuclear Industries Inc

International Nuclear Information System (INIS)

2006-01-01

This document reports the activities of Brazilian Nuclear Industry company during 2006 as follows: uranium isotope enrichment; production of nuclear fuel; mineral resources; finance and administration; planning and sales; quality, safety and environment, communication and social action; economic and financial management

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

Evaluation of organic endocrine disruptors in water at Brazilian Multipurpose Reactor - RMB installation area

Energy Technology Data Exchange (ETDEWEB)

Silva, Larissa L.; Martins, Elâine A.J.; Cotrim, Marycel E.B.; Pires, Maria A.F., E-mail: larissa.limeira07@gmail.com, E-mail: elaine@ipen.br, E-mail: mecotrim@ipen.br, E-mail: mapires@ipen.br [Instituto de Pesquisas Energéticas e Nucleares (IPEN/CNEN-SP), São Paulo, SP (Brazil)

2017-07-01

The study of pollutants with organic and inorganic characteristics in groundwater and surface waters of a given region is an important tool in the assessment of pollution. Endocrine interferers are synthetic or natural chemicals that have the ability to act on the endocrine system of humans and animals by mimetizing natural hormones and may produce adverse effects on organisms, even in low concentrations (μg or ng.L{sup -1}). Anthropic activities are the major source of input of endocrine disruptors into the environment. The Brazilian government has a project to construct a multipurpose reactor, Brazilian Multipurpose Reactor (RMB), at the Iperó city, to improve the nuclear research Brazilian capacity. The object of this research in to analyze 14 organic compounds that may be present in the groundwater and surface waters of the RMB installation area. This is an unprecedented and extremely important study for the evaluated region; since it will provide guidance on the degree of contamination of the local waters before the construction begins. The study will also make it possible to verify if the construction of the RMB will offer environmental issues to the place. For the determination of the compounds of interest, a developed and validated analytical method was used. This methodology consists of the concentration of the samples by solid phase extraction (SPE) followed by quantification by gas chromatography coupled to the mass spectrometry detector (GC/MS). The water column particulate was also evaluated by ultrasonic extraction, followed by quantification by GC/MS. The results reveal that some of the compounds were found and it was due to anthropic activities in the vicinity of the regions. By initial analysis it was possible verify river that cross the RMB area present values below 0.05 μg L{sup -1}. (author)

Evaluation of organic endocrine disruptors in water at Brazilian Multipurpose Reactor - RMB installation area

International Nuclear Information System (INIS)

Silva, Larissa L.; Martins, Elâine A.J.; Cotrim, Marycel E.B.; Pires, Maria A.F.

2017-01-01

The study of pollutants with organic and inorganic characteristics in groundwater and surface waters of a given region is an important tool in the assessment of pollution. Endocrine interferers are synthetic or natural chemicals that have the ability to act on the endocrine system of humans and animals by mimetizing natural hormones and may produce adverse effects on organisms, even in low concentrations (μg or ng.L -1 ). Anthropic activities are the major source of input of endocrine disruptors into the environment. The Brazilian government has a project to construct a multipurpose reactor, Brazilian Multipurpose Reactor (RMB), at the Iperó city, to improve the nuclear research Brazilian capacity. The object of this research in to analyze 14 organic compounds that may be present in the groundwater and surface waters of the RMB installation area. This is an unprecedented and extremely important study for the evaluated region; since it will provide guidance on the degree of contamination of the local waters before the construction begins. The study will also make it possible to verify if the construction of the RMB will offer environmental issues to the place. For the determination of the compounds of interest, a developed and validated analytical method was used. This methodology consists of the concentration of the samples by solid phase extraction (SPE) followed by quantification by gas chromatography coupled to the mass spectrometry detector (GC/MS). The water column particulate was also evaluated by ultrasonic extraction, followed by quantification by GC/MS. The results reveal that some of the compounds were found and it was due to anthropic activities in the vicinity of the regions. By initial analysis it was possible verify river that cross the RMB area present values below 0.05 μg L -1 . (author)

Brazilian nuclear renaissance in a sustainable development scenario - 097

International Nuclear Information System (INIS)

Dias, M.S.; Mattos, J.R.L.

2010-01-01

Brazil generated 326 TWh of hydroelectric power in 2005, accounting for ∼81% of the electricity production for that year. The 2005 to 2030 projections for the Brazilian development indicate growths from 2,020 kWh to 4,380 kWh in the per capita electricity consumption and from US$4,300 to US$8,950 in the per capita GDP (in market exchange rate and 2005 US$). The consumption of electricity is to grow from 375 TWh in 2005 to 1,030 TWh in 2030. In simple view and without considerations of aspects related with energy efficiency, this growth means 1.8 times the generation capacity of the 20. century should be built along of 25 years of the 21. century. The Brazilian electricity generation will demand all primary sources to meet the foreseen growth of the electricity consumption. As economical, safe and clean primary energy source for electricity generation, the nuclear energy is one option capable of large-scale and short-term deployment in the Brazilian growth of the electricity consumption. The contribution of nuclear generation in the electricity consumption should evolve from the current 2.6% for amounts over 5% in 2030. The perspective of the Brazilian nuclear sector is evolving to be resumed and present an opportunity for pooling and rationalizing the available skills - technical, cultural and human. The role of business opportunities and the future demands in the value chain of nuclear activities are summarized in this document. Institutions of R and D and Brazilian universities play an important role for the formation of new demanded knowledge and human resources. (authors)

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)

Plutonium recycle in PWR reactors (Brazilian Nuclear Program)

International Nuclear Information System (INIS)

Rubini, L.A.

1978-02-01

An evaluation is made of the material requirements of the nuclear fuel cycle with plutonium recycle. It starts from the calculation of a reference reactor and allows the evaluation of demand under two alternatives of nuclear fuel cycle for Pressurized Water Reactors (PWR): without plutonium recycle; and with plutonium recycle. Calculations of the reference reactor have been carried out with the CELL-CORE codes. For plutonium recycle, the concept of uranium and plutonium homogeneous mixture has been adopted, using self-produced plutonium at equilibrium, in order to get minimum neutronic perturbations in the reactor core. The refueling model studied in the reference reactor was the 'out-in' scheme with a constant number of changed fuel elements (approximately 1/3 of the core). Variations in the material requirements were studied considering changes in the installed nuclear capacity of PWR reactors, the capacity factor of these reactors, and the introduction of fast breeders. Recycling plutonium produced inside the system can reach economies of about 5%U 3 O 8 and 6% separative work units if recycle is assumed only after the 5th operation cycle of the thermal reactors. The cumulative amount of fissile plutonium obtained by the Brazilian Nuclear Program of PWR reactors by 1991 should be sufficient for a fast breeder with the same capacity as Angra 2. For the proposed fast breeder programs, the fissile plutonium produced by thermal reactors is sufficient to supply fast breeder initial necessities. Howewer, U 3 O 8 and SWU economy with recycle is not significant when the proposed fast breeder program is considered. (Author) [pt

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.)

CNEN activities and brazilian nuclear power policy

International Nuclear Information System (INIS)

Costa, E.M. da

1989-01-01

The goal of the brazilian policy in nuclear power is to provide its use in a pacific way to promote the well being of our people. It is intended, as well, to finish the construction of Angra II and III and proceed with the implementation of the nuclear fuel cycle, progressively fomenting its nationalization. (A.C.A.S.)

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

Volcanic Hazards in Site Evaluation for Nuclear Installations

Energy Technology Data Exchange (ETDEWEB)

NONE

2012-10-15

This publication provides comprehensive and updated guidance for site evaluation in relation to volcanic hazards. It includes recommendations on assessing the volcanic hazards at a nuclear installation site, in order to identify and characterize, in a comprehensive manner, all potentially hazardous phenomena that may be associated with future volcanic events. It describes how some of these volcanic phenomena may affect the acceptability of the selected site, resulting in exclusion of a site or determining the corresponding design basis parameters for the installation. This Safety Guide is applicable to both existing and new sites, and a graded approach is recommended to cater for all types of nuclear installations. Contents: 1. Introduction; 2. Overview of volcanic hazard assessment; 3. General recommendations; 4. Necessary information and investigations (database); 5. Screening of volcanic hazards; 6. Site specific volcanic hazard assessment; 7. Nuclear installations other than nuclear power plants; 8. Monitoring and preparation for response; 9. Management system for volcanic hazard assessment; Annex I: Volcanic hazard scenarios; Annex II: Worldwide sources of information.

Status of the implementation of Brazilian National Repository

International Nuclear Information System (INIS)

Tello, Cledola Cassia Oliveira de

2015-01-01

In Brazil, the use of nuclear energy and radioisotopes is increasing and it already justifies the construction of a national repository for radioactive wastes of low and intermediate-level. The Brazilian National Commission for Nuclear Energy (CNEN) is legally responsible for designing and constructing intermediate and final storages for radioactive wastes generated in all Country, in accordance to Federal Law No. 10308. Additionally, the Brazilian Environmental Regulator (IBAMA) lately is imposing to the implementation of new nuclear installations (e.g. Angra 3 NPP and Brazilian Multipurpose Reactor) that the National Repository should be in construction, before the start-up of those ones. In November 2009, the RBMN Project Charter was signed. The RBMN Project aims at the implantation of a National Repository to dispose the radioactive wastes of low- and intermediate-level. Some aspects about the Repository construction are very challenging, mainly due to the licensing process, which will be made for two different regulatory bodies, nuclear and environmental. The main achievements obtained till now are the establishment of the current Brazilian radioactive waste inventory, the conceptual design and the selection of candidate sites for the repository. The current status of the Project is summarized. (author)

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

Seismic Hazards in Site Evaluation for Nuclear Installations. Specific Safety Guide

Energy Technology Data Exchange (ETDEWEB)

NONE

2010-08-15

This Safety Guide was prepared under the IAEA programme for safety standards for nuclear installations. It supplements the Safety Requirements publication on Site Evaluation for Nuclear Installations. The present publication provides guidance and recommends procedures for the evaluation of seismic hazards for nuclear power plants and other nuclear installations. It supersedes Evaluation of Seismic Hazards for Nuclear Power Plants, IAEA Safety Standards Series No. NS-G-3.3 (2002). In this publication, the following was taken into account: the need for seismic hazard curves and ground motion spectra for the probabilistic safety assessment of external events for new and existing nuclear installations; feedback of information from IAEA reviews of seismic safety studies for nuclear installations performed over the previous decade; collective knowledge gained from recent significant earthquakes; and new approaches in methods of analysis, particularly in the areas of probabilistic seismic hazard analysis and strong motion simulation. In the evaluation of a site for a nuclear installation, engineering solutions will generally be available to mitigate, by means of certain design features, the potential vibratory effects of earthquakes. However, such solutions cannot always be demonstrated to be adequate for mitigating the effects of phenomena of significant permanent ground displacement such as surface faulting, subsidence, ground collapse or fault creep. The objective of this Safety Guide is to provide recommendations and guidance on evaluating seismic hazards at a nuclear installation site and, in particular, on how to determine: (a) the vibratory ground motion hazards, in order to establish the design basis ground motions and other relevant parameters for both new and existing nuclear installations; and (b) the potential for fault displacement and the rate of fault displacement that could affect the feasibility of the site or the safe operation of the installation at

Second national report of Brazil for the nuclear safety convention - September 2001

International Nuclear Information System (INIS)

2001-09-01

This National Report was prepared by a group composed of representatives of the various Brazilian organizations with responsibilities in the field of nuclear safety, aiming the fulfilling the Convention of Nuclear Energy obligations. The Report contains a description of the Brazilian policy and programme on the safety of nuclear installations, and an article by article description of the measures Brazil is undertaking in order to implement the obligations described in the Convention. The chapter 6 describes plans and future activities to further enhance the safety of nuclear installations in Brazil

Second national report of Brazil for the nuclear safety convention - September 2001

Energy Technology Data Exchange (ETDEWEB)

NONE

2001-09-01

This National Report was prepared by a group composed of representatives of the various Brazilian organizations with responsibilities in the field of nuclear safety, aiming the fulfilling the Convention of Nuclear Energy obligations. The Report contains a description of the Brazilian policy and programme on the safety of nuclear installations, and an article by article description of the measures Brazil is undertaking in order to implement the obligations described in the Convention. The chapter 6 describes plans and future activities to further enhance the safety of nuclear installations in Brazil.

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)

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)

The Brazilian nuclear power manpower development programme

International Nuclear Information System (INIS)

Barbalho, A.R.; Spitalnik, J.; Machado, J.B.

1983-01-01

Since the early stages of decision making, manpower availability has been recognized to be a key factor for the implementation of Brazil's nuclear power programme. Though care has been given to securing an industrial base and financial resources, the consequences of a lack of sufficient qualified manpower could be critical for the success of the whole programme. The broad scope of the Brazilian nuclear power programme which, as a main concept, aimed at establishing in the country a complete fuel cycle industry together with the construction of nuclear power plants, added another burden to the already complex task of providing appropriate human resources when advanced technologies are introduced in a developing country. Thus, not only the work-force required for nuclear power plant operation but also that needed for plant design, component manufacture, fuel cycle plant design and operation, had to be made available in number and qualification in accordance with the standards of the nuclear industry. The feasibility of the Brazilian programme depended on a complete transfer of technology, essentially achieved through personnel training. Again, the process of manpower preparation for an efficient know-how transfer required careful planning, and the great difficulty in its implementation was the lack of reliable experience at the time. (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

Argentine-Brazilian declaration on common nuclear policy

International Nuclear Information System (INIS)

1990-12-01

The document reproduces the texts of the speeches made by the Presidents of Argentina and Brazil at Foz do Iguacu, Brazil, on 28 November 1990, at the signing of the Argentine-Brazilian Declaration on Common Nuclear Policy

Seismic studies for nuclear installations sites

International Nuclear Information System (INIS)

Mohammadioun, B.; Faure, J.

1988-01-01

The french experience in seismic risks assessment for french nuclear installations permits to set out the objectives, the phases the geographic extensions of workings to be realized for the installation safety. The data to be collected for the safety analysis are specified, they concern the regional seismotectonics, the essential seismic data for determining the seism level to be taken into account and defining the soil movement spectra adapted to the site. It is necessary to follow up the seismic surveillance during the installation construction and life. 7 refs. (F.M.)

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

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.)

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

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

Brazilian nuclear legislation. Revision n.1/2002; Legislacao nuclear brasileira. Revisao n. 1/2002

Energy Technology Data Exchange (ETDEWEB)

Matos, Gilberto Cardoso de

2002-07-01

This work intends to facilitate the access to the Brazilian nuclear legislation and other legal instruments, foreseeing the use of nuclear energy and ionizing radiation in health, work and environment areas up to 2002. Legislation on the civil liability of nuclear damage, the law of licensing taxes, controlling and inspection are also included.

performance-based approach to design and evaluation of nuclear security systems for Brazilian nuclear facilities

Energy Technology Data Exchange (ETDEWEB)

Tavares, Renato L. A.; Filho, Josélio S. M., E-mail: renato.tavares@cnen.gov.br, E-mail: joselio@cnen.gov.br [Comissão Nacional de Energia Nuclear (CNEN), Rio de Janeiro, RJ (Brazil). Diretoria de Radioproteção e Segurança Nuclear. Divisão de Normas e Segurança Física; Fontes, Gladson S.; Fiel, J.C.B., E-mail: gsfontes@hotmail.com, E-mail: fiel@ime.eb.br [Instituto Militar de Engenharia (SE-7/IME), Rio de Janeiro, RJ (Brazil). Seção de Engenharia Nuclear

2017-07-01

This study presents an application of a performance-based approach to definition of requirements, design and evaluation of physical protection systems for nuclear facilities. Such approach considers a probabilistic analysis of the threat, equipment, systems and response forces used to prevent, dissuade and detain malicious acts against the integrity of facilities and the nuclear materials inside them. Nowadays, in the context of Brazilian nuclear facilities licensing, a mostly prescriptive approach is adopted, which despite having advantages such as simplified inspections and homogeneous regulatory requisites amid different fuel cycle facility types, does not consider evolution, dynamism and capacities of external or internal threats to facilities and to Brazilian Nuclear Program itself, neither provides metrics to evaluate system performance facing such threats. In order to preserve actual plans and systems confidentiality, a facility hypothetical model is created, including a research reactor and a waste storage facility. It is expected that the methodology and results obtained in this study serve in the future as a basis to Brazilian nuclear operators, in elaboration process of their Physical Protection Plans, which must comply with future regulation CNEN-NN 2.01, a revision of CNEN-NE 2.01, once that regulation will include performance requisites. (author)

performance-based approach to design and evaluation of nuclear security systems for Brazilian nuclear facilities

International Nuclear Information System (INIS)

Tavares, Renato L. A.; Filho, Josélio S. M.; Fontes, Gladson S.; Fiel, J.C.B.

2017-01-01

This study presents an application of a performance-based approach to definition of requirements, design and evaluation of physical protection systems for nuclear facilities. Such approach considers a probabilistic analysis of the threat, equipment, systems and response forces used to prevent, dissuade and detain malicious acts against the integrity of facilities and the nuclear materials inside them. Nowadays, in the context of Brazilian nuclear facilities licensing, a mostly prescriptive approach is adopted, which despite having advantages such as simplified inspections and homogeneous regulatory requisites amid different fuel cycle facility types, does not consider evolution, dynamism and capacities of external or internal threats to facilities and to Brazilian Nuclear Program itself, neither provides metrics to evaluate system performance facing such threats. In order to preserve actual plans and systems confidentiality, a facility hypothetical model is created, including a research reactor and a waste storage facility. It is expected that the methodology and results obtained in this study serve in the future as a basis to Brazilian nuclear operators, in elaboration process of their Physical Protection Plans, which must comply with future regulation CNEN-NN 2.01, a revision of CNEN-NE 2.01, once that regulation will include performance requisites. (author)

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.)

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

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)

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.

Aspects of the Brazilian law on civil liability for nuclear damage

International Nuclear Information System (INIS)

Rocha, L.M.G. da

1980-06-01

The civil liability for nuclear damage in the Brazilian law is analysed. The innovations introduced by the 6.453 act of October 17 th, 1977 are emphasized. The influence of international conventions on the Brazilian law are also mentioned. (A.L.) [pt

The nuclear energy in the context of Brazilian law

International Nuclear Information System (INIS)

Faria, N.M. de; Goes Fischer, M.D. de

1981-01-01

The present work has as its objective the study of nuclear activity within the context of Brazilian Law. It focuses on the organizational structure in which, as part of the Directives of the National Nuclear Energy Policy, this activity is being developed through specific legal norms. (Author) [pt

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)

Diagnosis of the Brazilian Nuclear Regulatory body

International Nuclear Information System (INIS)

Santos Gomes, Rogerio dos; Magalhaes Ennes Ennes, Edson Carlos

2008-01-01

This work has the objective to present the diagnosis of the existing structure in the Brazilian Government to ensure the radioprotection and nuclear safety in the country, being compared the current situation with the conclusions presented in another studies, carried through in last 30 years, with special attention in the existence of the necessary available to support and independence of the national regulatory body for the development of the regulatory inspections activities in the radioprotection and nuclear safety. (author)

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)

Argentine-Brazilian declaration on common nuclear policy

International Nuclear Information System (INIS)

1990-12-01

The document reproduces the text of the Argentine-Brazilian Declaration on Common Nuclear Policy, signed by the Presidents of Argentina and Brazil at Foz do Ignacu, Brazil, on 28 November 1990. At the invitation of the Governments of Argentina and Brazil, the Agency's Director General attended the signing ceremony

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.)

PREFACE: XXXVII Brazilian Meeting on Nuclear Physics

Science.gov (United States)

2015-07-01

The XXXVII Brazilian Meeting on Nuclear Physics (or XXXVII RTFNB 2014) gave continuity to a long sequence of workshops held in Brazil, devoted to the study of the different aspects of nuclear physics. The meeting took place in the Maresias Beach Hotel, in the town of Maresias (state of São Paulo) from 8th to 12th September 2014. Offering gentle weather, a charming piece of green land of splendid natural beauty with beach and all amenities, the place had all the conditions for very pleasant and fruitful discussions. The meeting involved 162 participants and attracted undergraduate and graduate students, Brazilian and South American physicists and invited speakers from overseas (USA, Italy, Spain, France, England, Switzerland, Germany and South Corea). In the program we had plenary morning sessions with review talks on recent developments in theory, computational techniques, experimentation and applications of the many aspects of nuclear physics. In the parallel sessions we had a total of 58 seminars. This volume contains 60 written contributions based on these talks and on the poster sessions. Evening talks and poster sessions gave still more insight and enlarged the scope of the scientific program. The contributed papers, representing mainly the scientific activity of young physicists, were exhibited as posters and are included in the present volume. Additional information about the meeting can be found at our website: http://www.sbfisica.org.br/~rtfnb/xxxvii-en Support and sponsorship came from brazilian national agencies: Conselho Nacional de Desenvolvimento Científico e Tecnoógico (CNPq); Coordenação de Aperfeiçoamento de Pessoal de Nível Superior (CAPES); Fundação de Amparo á Pesquisa do Estado de São Paulo (FAPESP); Fundação de Amparo á Pesquisa do Estado do Rio de Janeiro (FAPERJ); Sociedade Brasileira de Física (SBF) and Instituto de Física da Universidade de São Paulo (IFUSP). We honored Professor Alejandro Szanto de Toledo, who completed

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'

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.)

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)

Annual and activity report 2005 - INB - Brazilian Nuclear Industries. Nuclear fuel: technology for the essential

International Nuclear Information System (INIS)

2005-01-01

This document reports the activities of Brazilian Nuclear Industry company during 2005 as follows: uranium isotope enrichment; production of nuclear fuel; mineral resources; finance and administration; planning and sales; quality, safety and environment, communication and social action; economic and financial management

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)

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

Accountability and non-proliferation nuclear regime: a review of the mutual surveillance Brazilian-Argentine model for nuclear safeguards

International Nuclear Information System (INIS)

Xavier, Roberto Salles

2014-01-01

The regimes of accountability, the organizations of global governance and institutional arrangements of global governance of nuclear non-proliferation and of Mutual Vigilance Brazilian-Argentine of Nuclear Safeguards are the subject of research. The starting point is the importance of the institutional model of global governance for the effective control of non-proliferation of nuclear weapons. In this context, the research investigates how to structure the current arrangements of the international nuclear non-proliferation and what is the performance of model Mutual Vigilance Brazilian-Argentine of Nuclear Safeguards in relation to accountability regimes of global governance. For that, was searched the current literature of three theoretical dimensions: accountability, global governance and global governance organizations. In relation to the research method was used the case study and the treatment technique of data the analysis of content. The results allowed: to establish an evaluation model based on accountability mechanisms; to assess how behaves the model Mutual Vigilance Brazilian-Argentine Nuclear Safeguards front of the proposed accountability regime; and to measure the degree to which regional arrangements that work with systems of global governance can strengthen these international systems. (author)

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.)

Technology development in materials working for nuclear sector and its consequences for the Brazilian market

International Nuclear Information System (INIS)

Volta, A.R.

1992-01-01

The technology transfer model adopted in materials development for Brazilian nuclear sector is described. Materials are very important for the industrial development and the National nuclear program has contributed with others areas, for example, metallurgical, siderurgical, equipment sectors, etc. Grafenrheinfeld Power Plant is used like reference plant for Angra-1, a Brazilian nuclear power plant. (M.V.M.)

Nuclear energy in the increasingly deregulated brazilian energy market

International Nuclear Information System (INIS)

Mathias, Sergio G

2003-01-01

The Brazilian Electric Energy Market is presently undergoing an institutional transition from a strictly regulated to a commercially competitive market, due to be completed by January, 2006. The operation and maintenance costs of the two presently existing Brazilian nuclear power plants allow them to be economically competitive with other types of plants for meeting the load demand in the country. The commercialization of the energy produced by the two existing nuclear power plants must cope with the impact of the new market rules, which establish that power purchase contracts must be freely negotiated between generating and distributing companies. The projected costs for the construction and operation of a third NPP also indicate that it may be economically feasible under the new market rules (author)

The brazilian nuclear submarine dossier: Navy's priority and its application

International Nuclear Information System (INIS)

Rosa, L.P.

1990-01-01

This work discusses the feasibility of the brazilian nuclear submarine. It is related to navy's remodeling and is considered as a priority. It would bring Brazil closer to developed countries. It considers the slip, itself, the weapon's system as well as the nuclear propulsion. (author)

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

Contribution to the Brazilian legislation in nuclear energy field

International Nuclear Information System (INIS)

Barbosa, Jose Alberto Maia

2009-01-01

Nuclear technology: to keep its domain is actually considered a differential for a country in relation to other ones, being able to represent an international threat to be contained or an aspect on technological and political valorization for those ones with recognized international credibility. Face to a raising use of new technologies in the field and the requirement asking for regulation in accordance with international safety standards, in order to assure its employment, the objective of this study was to demonstrate whether occupational and environmental radioprotection performed in our country is within radiological and nuclear safety international standards, and so it was updated and revised the Brazilian law in nuclear energy area, by comparing it with European Union, contextualized strong and weak points from national law, indicating criticisms and suggestions, in order that modifications will be able to be accomplished, aiming to its adequacy to international standards. The considered hypothesis showed that are required changes in the regulation structure in Brazilian nuclear area, aiming to the creation of a regulator agency of nuclear activities, with the purpose of assuring that the state of art and of technology, in terms of nuclear safety, to be the basis of the exercise related to their normative, control and safety assessment activities, on environment preservation, public and workers health, face to nuclear energy applications. (author)

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

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

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

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.)

Consequences of bilateral and multilateral restrictions in the Brazilian Nuclear Program

International Nuclear Information System (INIS)

Alves, R.N.

1987-01-01

A brief historical aspects on research activities for the nuclear energy development, the historical antecedents related to restrictions in the international cooperation agreements and, the Brazilian relationship with the international nuclear policy, are presented. (M.C.K.) [pt

Nuclear energy: Brazilian Nuclear Program behind the scenes and the reflections in the national society and economy

International Nuclear Information System (INIS)

Grippi, Sidney

2006-01-01

The nuclear energy in the world, the Brazilian nuclear program, the industrial and social risks of nuclear segment, 20th century and the radiation accidents, the ionizing radiation effects in living beings, radioactive wastes, the Earth Letter and a list of CNEN regulations are presented

The Brazilian participation in the nuclear power plant construction

International Nuclear Information System (INIS)

Fabricio, R.A.C.

1981-01-01

A brief review about the origin of the brazilian nuclear power program and the strategy adopted for its implementation in Brazil is presented. The creation of the Nuclebras Engineering S/A, the Germany technology transfer and the personell job-training in Brasil are discussed. Some management models used for nuclear power plant construction in the world are still presented. (E.G.) [pt

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

Volcanic Hazard Assessments for Nuclear Installations: Methods and Examples in Site Evaluation

International Nuclear Information System (INIS)

2016-07-01

To provide guidance on the protection of nuclear installations against the effects of volcanoes, the IAEA published in 2012 IAEA Safety Standards Series No. SSG-21, Volcanic Hazards in Site Evaluation for Nuclear Installations. SSG-21 addresses hazards relating to volcanic phenomena, and provides recommendations and general guidance for evaluation of these hazards. Unlike seismic hazard assessments, models for volcanic hazard assessment have not undergone decades of review, evaluation and testing for suitability in evaluating hazards at proposed nuclear installations. Currently in volcanology, scientific developments and detailed methodologies to model volcanic phenomena are evolving rapidly.This publication provides information on detailed methodologies and examples in the application of volcanic hazard assessment to site evaluation for nuclear installations, thereby addressing the recommendations in SSG-21. Although SSG-21 develops a logical framework for conducting a volcanic hazard assessment, this publication demonstrates the practicability of evaluating the recommendations in SSG-21 through a systematic volcanic hazard assessment and examples from Member States. The results of this hazard assessment can be used to derive the appropriate design bases and operational considerations for specific nuclear installations

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

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.)

The influence of Goiania radiological accident on Brazilian public opinion concerning new nuclear electric plants

International Nuclear Information System (INIS)

Meldonian, Nelson Leon; Mattos, Luis Antonio Terribile de

1997-01-01

The Brazilian society is against applications of nuclear energy, mainly respecting to construction of new nuclear power plants, believing that they are harmful to population's welfare and the environment. By this reason, Brazilian nuclear sector would promote a more intensive program of public discussion, not limited to technical and scientific community. Intending to contribute to a better judgment by society about the differences between diverse employment of nuclear energy, arguments concerned to its benefits are presented, pointing out that adverse accounts to nuclear electricity based on Goiania radiological accident, are not justified

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

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

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

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

Nuclear future: thinking for building. Proceedings of the 5. Brazilian national meeting on nuclear applications; 8. General congress on nuclear energy; 12. Brazilian national meeting on reactor physics and thermal hydraulics; Futuro nuclear: refletindo para construir. Anais do 5. Encontro nacional de aplicacoes nucleares; 8. Congresso geral de energia nuclear; 12. Encontro nacional de fisica de reatores e termo-hidraulica

Energy Technology Data Exchange (ETDEWEB)

NONE

2000-07-01

These proceedings, for the first time, present jointly the 12. Brazilian national meeting on reactor physics and thermal hydraulics (12. ENFIR), the 8. General congress on nuclear energy (8. CGEN), and the 5. Brazilian national meeting on nuclear applications (5. ENAN). The main theme of discussion was: 'Nuclear Future: thinking for building'. The papers have analysed the progresses of peaceful utilization of nuclear technology and its forecasting for the beginning of the new millennium. The construction of Angra-3 nuclear power plant have been discussed.

Nuclear future: thinking for building. Proceedings of the 12. Brazilian national meeting on reactor physics and thermal hydraulics; 8. General congress on nuclear energy; 5. Brazilian national meeting on nuclear applications; Futuro nuclear: refletindo para construir. Anais do 12. Encontro nacional de fisica de reatores e termo-hidraulica; 8. Congresso geral de energia nuclear; 5. Encontro nacional de aplicacoes nucleares

Energy Technology Data Exchange (ETDEWEB)

NONE

2000-07-01

These proceedings, for the first time, present jointly the 12. Brazilian national meeting on reactor physics and thermal hydraulics (12 ENFIR), 8. General congress on nuclear energy (8. CGEN), and 5. Brazilian national meeting on nuclear applications (5. ENAN). The main theme of discussion was: 'Nuclear Future: thinking for building'. The papers have analysed the progresses of peaceful utilization of nuclear technology and its forecasting for the beginning of the new millennium. The construction of Angra-3 nuclear power plant have been discussed.

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)

Progress report 2011-2013 - Brazilian Energy and Nuclear Research Institute - IPEN

International Nuclear Information System (INIS)

2014-01-01

This progress report presents the results of the R&D center of IPEN in accordance with the main programs: Lasers Technology, Applications of Ionizing Radiations, Biotechnology, Renewable Energies, Radiopharmacy, Nuclear Science and Technology, Environmental Science and Technology, Nuclear Reactors and Fuel Cycle, Materials and Nanotechnology, Nuclear Safety, Education, Brazilian Multipurpose Reactor and Scientific and Technical Production

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

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

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.

Nuclear energy generation and the safety criteria for Brazilian power plants

International Nuclear Information System (INIS)

Silva, Gustavo Brandão e

2016-01-01

The purpose of this paper is to show how the use of nuclear technology can help to diversify the national electricity matrix in a sustainable and efficient way. For this, an analysis of the current situation of the Brazilian electric sector will be made, exposing its fragilities and highlighting the advantages of the nuclear source as an alternative to integrate the necessary thermoelectric base to the reliable supply of electricity in the country. In addition, the objective of the work is to detail the process of exploiting atomic energy in Brazil from raw material mining, through the stages involving the manufacture of nuclear fuel, to the current operation and situation of Brazilian power plants. By taking the Angra 2 Nuclear Power Plant as a case study, the safety criteria adopted in its design and operation will be highlighted. Particular attention will also be given to the electric supply alternatives and to the active safety systems of the plant

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

Management report 2004 CNEN - Brazilian Nuclear Energy Commission; Relatorio de gestao 2004 CNEN - Comissao Nacional de Energia Nuclear

Energy Technology Data Exchange (ETDEWEB)

NONE

2005-03-15

This document reports the results of the activity management of the Comissao Nacional de Energia Nuclear - CNEN - Brazil during the year of 2004, involving the Brazilian program of nuclear activities in the areas of nuclear safety, research and development, radiopharmaceutical production, institutional management, teaching, administration in general and miscellaneous.

Management report 2005 CNEN - Brazilian Nuclear Energy Commission; Relatorio de gestao 2005 CNEN - Comissao Nacional de Energia Nuclear

Energy Technology Data Exchange (ETDEWEB)

NONE

2006-03-15

This document reports the results of the activity management of the Comissao Nacional de Energia Nuclear - CNEN - Brazil during the year of 2005, involving the Brazilian program of nuclear activities in the areas of nuclear safety, research and development, radiopharmaceutical production, institutional management, teaching, administration in general and miscellaneous.

Management report 2006 CNEN - Brazilian Nuclear Energy Commission; Relatorio de gestao 2006 CNEN - Comissao Nacional de Energia Nuclear

Energy Technology Data Exchange (ETDEWEB)

NONE

2007-03-15

This document reports the results of the activity management of the Comissao Nacional de Energia Nuclear - CNEN - Brazil during the year of 2005, involving the Brazilian program of nuclear activities in the areas of nuclear safety, research and development, radiopharmaceutical production, institutional management, teaching, administration in general and miscellaneous.

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.)

Proposal of a national system to supervise nuclear installations out of international safeguards

International Nuclear Information System (INIS)

Rosa, L.P.

1990-01-01

It is proposed a national system to safeguard, supervise and inspect nuclear facilities in Brazil, apart from international safeguards. It discusses also the military nuclear activities and the uranium enrichment plants. The system should be controlled by Brazilian CNEN. (A.C.A.S.)

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.)

Nuclear installations sites safety

International Nuclear Information System (INIS)

Barber, P.; Candes, P.; Duclos, P.; Doumenc, A.; Faure, J.; Hugon, J.; Mohammadioun, B.

1988-11-01

This report is divided into ten parts bearing: 1 Safety analysis procedures for Basis Nuclear Installations sites (BNI) in France 2 Site safety for BNI in France 3 Industrial and transport activities risks for BNI in France 4 Demographic characteristics near BNI sites in France 5 Meteorologic characteristics of BNI sites in France 6 Geological aspects near the BNI sites in France 7 Seismic studies for BNI sites in France 8 Hydrogeological aspects near BNI sites in France 9 Hydrological aspects near BNI sites in France 10 Ecological and radioecological studies of BNI sites in France [fr

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)

RMB: the new Brazilian Multipurpose Research Reactor

Energy Technology Data Exchange (ETDEWEB)

Perrotta, Jose Augusto, E-mail: perrotta@ipen.br [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

2016-07-01

Full text: The Brazilian research reactors have a limited capacity for radioisotopes production, leading to a high dependence on external supply for radioisotopes used in nuclear medicine. In order to overcome this condition and due to the old age of these research reactors, the Brazilian Nuclear Energy Commission decided, in 2008, to construct a new research reactor. The new reactor named RMB (Brazilian Multipurpose Reactor) will be part of a new nuclear research center, to be built on a site about 100 kilometers from São Paulo city, in the southern part of Brazil. The new nuclear research center will have a 30 MW open pool type research reactor using low enriched uranium fuel, and several associated laboratories in order to produce radioisotopes for medical and industrial use, to use neutron beams in scientific and technological research; to perform neutron activation analysis; and to perform materials and fuels irradiation tests. Regarding the neutron beams use, the RMB design provides thermal and cold neutron beams. From one side of the reactor, the neutron guides will extend to an experimental hall of instruments named Neutron Guide Hall where it will be installed the scattering instruments. In the initial stage of the reactor operation, the intent is to implement two neutron guides for thermal neutrons and another two for cold neutrons. The 2015 SBPMAT symposium has presented the technical overview of the RMB project and its main buildings, structures and components. At this year symposium, the RMB presentation updates some technical information and the development status of the project, discussing the negative results of the Brazilian political and economic crisis to the project development and its future perspectives. (author)

Industrial development - consequences about the implantation of Brazilian Nuclear Program

International Nuclear Information System (INIS)

Syllus, C.

1987-07-01

The strategy to promote the growing industry participation in the Brazilian Nuclear Program, the difficulties, the measurements adopted for overcoming and the results obtained in terms of industrial development, are presented. (M.C.K.) [pt

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

Management report 2007 CNEN - Brazilian Nuclear Energy Commission; Relatorio de gestao 2007 CNEN - Comissao Nacional de Energia Nuclear

Energy Technology Data Exchange (ETDEWEB)

NONE

2007-07-01

This document reports the general activity management of the Comissao Nacional de Energia Nuclear - CNEN - Brazil during the year of 2007, involving the CNEN role in the public policy execution, the Brazilian program of nuclear activities in the areas of nuclear safety, research and development, radiopharmaceutical production, teaching, administration in general and miscellaneous.

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

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)

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.)

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

Brazilian nuclear power plants decommissioning plan for a multiple reactor site

Energy Technology Data Exchange (ETDEWEB)

Monteiro, Deiglys B.; Moreira, Joao M.L.; Maiorino, Jose R., E-mail: deiglys.monteiro@ufabc.edu.br, E-mail: joao.moreira@ufabc.edu.br, E-mail: joserubens.maiorino@ufabc.edu.br [Universidade Federal do ABC (CECS/UFABC), Santo Andre, SP (Brazil). Centro de Engenharia, Modelagem e Ciencias Aplicadas. Programa de Pos-Graduacao em Energia e Engenharia da Energia

2015-07-01

Actually, Brazil has two operating Nuclear Power Plants and a third one under construction, all at Central Nuclear Almirante Alvaro Alberto - CNAAA. To comply with regulatory aspects the power plants operator, Eletronuclear, must present to Brazilian Nuclear Regulatory Agency, CNEN, a decommissioning plan. Brazilian experience with decommissioning is limited because none of any nuclear reactor at the country was decommissioned. In literature, decommissioning process is well described despite few nuclear power reactors have been decommissioned around the world. Some different approach is desirable for multiple reactors sites, case of CNAAA site. During the decommissioning, a great amount of wastes will be produced and have to be properly managed. Particularly, the construction of Auxiliary Services on the site could be a good choice due to the possibility of reducing costs. The present work intends to present to the Eletronuclear some aspects of the decommissioning concept and decommissioning management, storage and disposal de wastes, based on the available literature, regulatory standards of CNEN and international experience as well as to suggest some solutions to be implemented at CNAAA site before starts the decommissioning project in order to maximize the benefits. (author)

Brazilian nuclear power plants decommissioning plan for a multiple reactor site

International Nuclear Information System (INIS)

Monteiro, Deiglys B.; Moreira, Joao M.L.; Maiorino, Jose R.

2015-01-01

Actually, Brazil has two operating Nuclear Power Plants and a third one under construction, all at Central Nuclear Almirante Alvaro Alberto - CNAAA. To comply with regulatory aspects the power plants operator, Eletronuclear, must present to Brazilian Nuclear Regulatory Agency, CNEN, a decommissioning plan. Brazilian experience with decommissioning is limited because none of any nuclear reactor at the country was decommissioned. In literature, decommissioning process is well described despite few nuclear power reactors have been decommissioned around the world. Some different approach is desirable for multiple reactors sites, case of CNAAA site. During the decommissioning, a great amount of wastes will be produced and have to be properly managed. Particularly, the construction of Auxiliary Services on the site could be a good choice due to the possibility of reducing costs. The present work intends to present to the Eletronuclear some aspects of the decommissioning concept and decommissioning management, storage and disposal de wastes, based on the available literature, regulatory standards of CNEN and international experience as well as to suggest some solutions to be implemented at CNAAA site before starts the decommissioning project in order to maximize the benefits. (author)

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.)

The protection system to Brazilian Nuclear Program

International Nuclear Information System (INIS)

Andreuzza, Mario Giussepp Santezzi Bertottelli

1997-01-01

The Sistema de Protecao ao Programa Nuclear Brasileiro-SIPRON (Protection System to Brazilian Nuclear Program) was established in 1980. It is intended to accomplish in only one system, all the actions related to security and protection for Nuclear Facilities in Brazil. The author presents in detail the protection system SIPRON, describing the system structure and organization, the functions and obligations of the system involved main organizations, as well as, the system operation and behaviour during an postulated occurrence of a nuclear emergency. It is also described an Exercise that happened in June of 1997 at the Nuclear Power Plant (NPP) Angra I, after two simulated tests in December of 1996 and April of 1997. The NPP Angra I Emergency Plan Exercise was a good opportunity to test the SIPRON structure and preparedness program. It was verified, included by International Atomic Energy Agency observers, the system involved organizations effectiveness and the procedures efficacy to protect the public and the environmental. Finally, it is shown the SIPRON activities of routine, the system obstacles and the expected future performances. (author)

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)

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)

Study of energetic balance in uranium cycle and in the nuclear Brazilian program

International Nuclear Information System (INIS)

Davi, E.M.

1982-01-01

The direct and indirect energetic investments for the construction and maintenance of nuclear power plants as well as for the fuel cycle, were analysed. The existing data in the literature was applied to the brazilian nuclear programme with a special attention to those peculiar aspects, particularly the enrichment process and mining. The energetic investments required by the various systems, using the 626 MW nuclear power stations or the 1240 MW, were determined in function of the brazilian ore with 0.108% of U 3 O 8 and of a mine with a stripping ratio (the ratio of tons of overburden to tons of ore) of 28/1. About the enrichment, two hypothesis were considered for the concentration of 235 U in the enrichment plant tails - the tails assay (0.25 and 0.35% of 235 U) and for the specific energy consumption per unit of separative work (3.60 and 4.40 MWh/UTS). The fuel cycles with and without recycling of uranium and plutonium were taken in consideration. During the lifetime of the plants and for the various cases considered there is a self-consumption between 10 and 16 percent of the produced energy. The cumulative energy requirements as a function of time, was made for individual plants and for the brazilian nuclear programme as a whole in its actual form (9 nuclear power plants). (E.G.) [pt

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)

Policies of industrial market and science and technology: the case of Brazilian nuclear program

International Nuclear Information System (INIS)

Oliveira, R.G. de.

1981-01-01

The relationship between policies and the definition of a national program of nuclear energy, is considered. The case under study is the Brazilian one. It is shown that an overall evaluation of market, industry and science and technology is mandatory for the definition of a nuclear energy program, and serious fault and hesitation, leading to contradiction and failure, have their roots in a basic lack of definition in policies. The evolution of the Brazilian Nuclear Energy Program will probably remain at a mediocre level until a definition at the level of policy-making in marketing, industry and science and technology is firmly pursued and maintained. (Author) [pt

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

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)

Considerations about the impact of the Convention on Nuclear Safety on the regulatory action of the CNEN in Brazilian nuclear power plants

International Nuclear Information System (INIS)

Camargo, Claudio; Pontedeiro, Auro

1995-01-01

Preliminary discussion is conducted about the impact of the terms of the Convention on Nuclear safety, adopted by Diplomatic Conference in September 1994 in the International Atomic Energy Agency, on the regulatory action of Brazilian Nuclear Regulatory Body - CNEN. Following the Convention articles structure, the paper emphasizes technical aspects of the nuclear safety standards adopted in the licensing process of Brazilian Nuclear Power Plants. The recent experience in the issuance of Angra-1 NPP Permanent Operation Authorization is used to demonstrate that current safety standards in Brazil are in compliance with the international compromises and in agreement with what is expected by the so called Safety Culture. (author). 9 refs

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)

Methodology for inspection parametrization of radioprotection at radioactive installations: a research agenda

International Nuclear Information System (INIS)

Filgueiras, Bruno Costa; Sauerbronn, Fernanda F.

2011-01-01

This paper establishes a research agenda based on documental and bibliographic research for radioprotection inspection parametrization at radioactive installations, which is one of the constitutional attributions of Brazilian Nuclear Energy Commission. Such proposal, aiming to guarantee that the evaluation of normative requests of radiation protection generated a quantitative result, useful for various institutions in the safety and regulation areas, bringing relevant contribution for the sector

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)

Bridging Nuclear Knowledge to a Brazilian Decree: A Case Study at the National Nuclear Energy Commission (CNEN)

International Nuclear Information System (INIS)

Muguet-Haisman, T. M.

2016-01-01

Full text: Since the term“knowledge management”was coined, it has gained more and more attention in an effort to re-structure organizations. A good deal of effort has been done in order to better implement a knowledge management culture in organizations throughout all the work sectors. The Brazilian Federal Government through the Decree no.5.707, dated February 23, 2006, democratically created a national policy for human development. This initiative made equally available additional education opportunities for all staff in order to form a competent workforce which included official recognition of work-related skills. In the field of nuclear energy, the National Nuclear Energy Commission is a Brazilian governmental authority which has long served as the leader in the matter. In this respect, and in the light of the International Atomic Energy Agency (IAEA) nuclear knowledge management role and the perspective of the first and third dimensions, the aim of this paper is to share the outcome of the Government programme in the National Nuclear Energy Commission. (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

The role of the decomissioning process on the development of the Brazilian nuclear program

International Nuclear Information System (INIS)

Mattos, Joao Roberto L. de; Dias, Marcio S.

2009-01-01

The National Energy Plan 2030, issued by the Energy Research Company of the Brazilian Ministry of Mines and Energy (EPE, 2007), formalized a reference scenario for the renaissance of the nuclear option in Brazil. This scenario includes the completion of Angra 3 Nuclear Power Plant up to 2014 and the construction of four additional nuclear power plants of 1000 MWe: a fourth unit by 2020, a fifth unit by 2025 and the sixth and seventh plants by 2030. Worldwide, the energy demand and the renaissance of nuclear energy as a primary source for electric power generation are leading the industry toward new constructions as well as uprates and operational life extensions. In this new scenario the decommissioning is pushed further into the future and Brazil is not an exception, considering that Angra 1 NPP is under a process of uprating and certainly will apply for and will receive license renewals allowing its operation for 20 or more years beyond its original project. Thus, why to focus on decommissioning in the present? What is the importance of decommissioning for the development of the Brazilian nuclear industry considering the existing reactors? Should the decommissioning be considered in the design of the new nuclear power plants? What would be the decommissioning plan for the Brazilian Nuclear Power Plants? The present paper is intended to contextualize the decommissioning in the present scenarios as well as to try to answer the above questions. (author)

Time response prediction of Brazilian Nuclear Power Plant temperature sensors using neural networks

Energy Technology Data Exchange (ETDEWEB)

Santos, Roberto Carlos dos; Pereira, Iraci Martinez, E-mail: rcsantos@ipen.br [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

2011-07-01

This work presents the results of the time constants values predicted from ANN using Angra I Brazilian nuclear power plant data. The signals obtained from LCSR loop current step response test sensors installed in the process presents noise end fluctuations that are inherent of operational conditions. Angra I nuclear power plant has 20 RTDs as part of the protection reactor system. The results were compared with those obtained from traditional way. Primary coolant RTDs (Resistance Temperature Detector) typically feed the plant's control and safety systems and must, therefore, be very accurate and have good dynamic performance. An in-situ test method called LCSR - loop current step response test was developed to measure remotely the response time of RTDs. In the LCSR method, the response time of the sensor is identified by means of the LCSR transformation that involves the dynamic response modal time constants determination using a nodal heat transfer model. For this reason, this calculation is not simple and requires specialized personnel. This work combines the two methodologies, Plunge test and LCSR test, using neural networks. With the use of neural networks it will not be necessary to use the LCSR transformation to determine sensor's time constant and this leads to more robust results. (author)

Time response prediction of Brazilian Nuclear Power Plant temperature sensors using neural networks

International Nuclear Information System (INIS)

Santos, Roberto Carlos dos; Pereira, Iraci Martinez

2011-01-01

This work presents the results of the time constants values predicted from ANN using Angra I Brazilian nuclear power plant data. The signals obtained from LCSR loop current step response test sensors installed in the process presents noise end fluctuations that are inherent of operational conditions. Angra I nuclear power plant has 20 RTDs as part of the protection reactor system. The results were compared with those obtained from traditional way. Primary coolant RTDs (Resistance Temperature Detector) typically feed the plant's control and safety systems and must, therefore, be very accurate and have good dynamic performance. An in-situ test method called LCSR - loop current step response test was developed to measure remotely the response time of RTDs. In the LCSR method, the response time of the sensor is identified by means of the LCSR transformation that involves the dynamic response modal time constants determination using a nodal heat transfer model. For this reason, this calculation is not simple and requires specialized personnel. This work combines the two methodologies, Plunge test and LCSR test, using neural networks. With the use of neural networks it will not be necessary to use the LCSR transformation to determine sensor's time constant and this leads to more robust results. (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

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

Portfolio of patents after the Brazilian Innovation Act: the case of the Comissao Nacional de Energia Nuclear - CNEN (Brazilian National Nuclear Energy Commission)

International Nuclear Information System (INIS)

Pereira, Gustavo Jose; Guimaraes, Regia Ruth Ramirez; Perry, Katia da Silva Peixoto; Teruya, Dirceu Yoshikazu

2013-01-01

The process of technological development is due to the need to promote a solution to a particular problem of agents, compete with products and/or processes on the international market and to promote scientific advancement. Thus, the patent system is a repository of knowledge for protection, for promotion of diffusion through licensing agreements and an indicator of technological development. In 2004, the Brazilian Government enacted the Brazilian Innovation Act and the mechanisms were improved for cooperation between firms and public education, science and technology organisations and also promoted the commercialisation of technology produced by public education, science and technology organisations and the mandatory establishment of Technology Transfer Offices. The Comissao Nacional de Energia Nuclear (CNEN) is a federal agency responsible for basic and applied research in the field of nuclear technology and has used the patent system since the 1980s to protect its knowledge. With the advent of the Innovation Act in 2004, there was a significant boost in requests for patents in CNEN which also established an internal set of normative acts and created a System of Innovation Management and Technology Innovation Offices in its research institutes to support management and dissemination of knowledge. The aim of this case study is to present the profile of the requests for patents by CNEN before and after the enactment of the Brazilian Innovation Act covering the period of time between 1980 and 2010. (author)

Some basic considerations about the brazilian nuclear program

International Nuclear Information System (INIS)

Ishiguro, Y.

1983-01-01

In order to assure the continued utilization of fission energy development of fast breeder reactors is a necessity. Binary fueled LMFBRs are proposed as the best type for future Brazilian nuclear systems. The inherent safety characteristics are superior to current fast breeder reactors and an efficient utilization of thorium can be realized. A possible strategy for the development of the reactor and related technologies are discussed. (Author) [pt

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

Brazilian nuclear politics in the context of contemporary international relations

International Nuclear Information System (INIS)

Carpes, Mariana Montez

2006-09-01

The present dissertation analyses the retaking of the debate over Brazilian nuclear Program's recovery by Luis Inacio Lula da Silva government, based on the defense of the utilization of an already acquired technology of its own to enrich uranium. In spite of the intrinsic duality on this subject and having in mind the pacific ends concerning the utilization of such technology by Brazil, the hypothesis sustained in this work is that the Program's defense is considered a strategy of sovereign international insertion with relative autonomy and an instrument of national valorization against other powers. In order to verify the hypothesis outlined above, we will analyse the actual government, comparing it to, two other moments in Brazilian History in which the nuclear issue also acquired preponderance on the national agenda, namely, Geisel and Sarney governments. Although these three moments differ in relation to their internal political regime, our goal is to identify their similarities. (author)

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

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)

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.

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)

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

National report of Brazil. Nuclear Safety Convention

International Nuclear Information System (INIS)

1998-09-01

This document represents the national report prepared as a fulfillment of the brazilian obligations related to the Convention on Nuclear Safety. In chapter 2 some details are given about the existing nuclear installations. Chapter 3 provides details about the legislation and regulations, including the regulatory framework and the regulatory body. Chapter 4 covers general safety considerations as described in articles 10 to 16 of the Convention. Chapter 5 addresses to the safety of the installations during siting, design, construction and operation. Chapter 6 describes planned activities to further enhance nuclear safety. Chapter 7 presents the final remarks related to the degree of compliance with the Convention obligations

Successful pipeline installation for Parque das Conchas development; Subsea installation

Energy Technology Data Exchange (ETDEWEB)

Bartz, Cesar

2010-07-01

Subsea 7 has successfully delivered again in Brazilian deep-waters. The subsea engineering and construction company has recently completed pipeline installation activities for the Parque das Conchas (BC-10) development, offshore Brazil. (AG)

Legal aspects of search and mining of nuclear ores under Brazilian law

International Nuclear Information System (INIS)

Godinho, T.M.

1980-06-01

The legal aspects of mining in the Brazilian law its general principles, the basic concepts and rules established in the constitution of Brazil, in the mining code and in special laws are analysed. The rules for mining and usage of nuclear ores and other ores of interest to the nuclear field are emphasized. (A.L.) [pt

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

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)

From Angra to Tehran: Brazilian nuclear policy under Lula’s administration

Directory of Open Access Journals (Sweden)

Diego Santos Vieira de JESUS

2011-11-01

Full Text Available The aim of this article is to explain the positions taken by Brazil under Lula’s administration (2003-2010 on nuclear non-proliferation, disarmament and arms control. In order to strengthen its position in dispute settlement and to expand its participation in international institutions, Brazil wished to intermediate between nuclear-weapon and non-nuclear weapon States. The country also tried to pressure the nuclear weapon States to fulfill their disarmament obligations and to reduce asymmetries in relations with the strongest countries in the nuclear arena. The Brazilians also sought to maintain flexibility to ensure the safety of their own atomic program.

The Perspective of Small and Medium Size Nuclear Power Reactors in the Brazilian Isolated Electricity Grids

International Nuclear Information System (INIS)

Moutinho dos Santos, E.

1998-01-01

As a consequence of the international crisis that has shaken the nuclear industry almost all over the world during the late 1980s, new academic contributions, which could settle a new basis for the nuclear energy in Brazil, have been scarce. This paper aims to partially fulfill this gap. We discuss some perspectives for the nuclear option to regain some prominence in the Brazilian energy matrix. Recent developments in the nuclear industry, including advances in plant design, have been opening interesting markets for small and medium nuclear power reactors (SMNPRs). We access the suitability and feasibility of such new technology in the Brazilian isolated electricity grids. We conclude by saying that, although the difficulties are still huge, SMNPRs may be a good strategy for Brazil to revitalize its nuclear policy. (author)

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

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)

Nuclear knowledge portal to support licensing and control nuclear activities in the Brazilian Nuclear Energy Commission

International Nuclear Information System (INIS)

Gomes, Elizabeth; Braga, Fabiane

2004-01-01

importance of keeping the intellectual capital in the organizations that is to work with the knowledge from the collaborators. In Brazil still have many authors that discusses this concept and we adopt for this paper the definition form Cavalcanti where is the concept 'intellectual capital' refers either to the capacity, ability or experience, as well as to the formal education that the collaborators members have and add to the Organization. The 'intellectual capital' is an intangible asset, which belongs to the individual himself, thus it might be utilized by the organizations in order to generate value. The development and preservation of this intellectual capital is made through the implementation of forums of discussion, workshops or knowledge portals where the organization's collaborators share their experiences. Nevertheless, to assimilate and to develop the 'intellectual capital' does not add value to the organization: It is necessary to keep it. And one way to do so is to create desirable and encouraging work environments, to promote a sharing management and to offer programs of profits sharing. The objective of this paper is to describe how Brazilian Nuclear Energy Commission - CNEN has been developing a nuclear knowledge portal, focused in the Radiation and Safety Nuclear area. The Brazilian Nuclear Energy Commission (CNEN) is a federal autarchy created in October 10 of 1956, as a superior agency of planning, guiding, supervision and inspection in nuclear area being also the body entitled to establish standards and regulations on radiological protection, to issue licenses (permissions) and to survey and control the nuclear activities in Brazil. CNEN also develops researches related to the use of nuclear techniques in benefit of the society. The Radiation and Safety Nuclear directorate of CNEN acts, mainly, in the licensing of nuclear and radioactive installations. The people who work at this area recognize the importance of management and sharing the accumulated

Centro Regional de Ciencias Nucleares (a Brazilian regional center for nuclear sciences) - activities report - 1999

International Nuclear Information System (INIS)

1999-12-01

The annual activities report of 1999 of nuclear sciences regional center - Brazilian organization - introduces the next main topics: institutional relations; sectorial actions - logistic support and training, laboratory of radiation protection and dosimetry, laboratory of metrology, laboratory of chemical characterization; technical and scientific events; and financial resources and perspectives for 2000

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

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)

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

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)

NUCLEBRAS' installations for tests of nuclear power plants components

International Nuclear Information System (INIS)

Vasconcelos Paiva, I.P. de; Horta, J.A.L.; Avelar Esteves, F. de; Pinheiro, R.B.

1983-05-01

The reasons for NUCLEBRAS' Nuclear Technology Development Center to implement a laboratory for supporting Brazilian manufacturers, giving to them the means for performing functional tests of industrial products, are presented. A brief description of the facilities under construction: the Components Test Loop and the Facility for Testing N.P.P. Components under Accident Conditions, and of other already in operation, is given, as well as its objectives and main technical characteristics. Some test results already obtained are also presented. (Author) [pt

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

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

The protection and the preservation of the environment the Brazilian nuclear law

International Nuclear Information System (INIS)

Faria, N.M. de; Goes Fischer, M.D. de; Rocha, L.M.G. da; NUCLEBRAS, Rio de Janeiro; Associacao Brasileira de Direito Nuclear, Rio de Janeiro)

1981-01-01

A set of Brazilian rules governing the protection and the preservation of the environment in relation to nuclear activities is presented. The role of CNEN, as an institution that defends the environment is also mentioned. (A.L.) [pt

Fuel for the next Brazilian nuclear power plants

International Nuclear Information System (INIS)

Lameiras, Fernando S.; Faeda, Kelly Cristina Ferreira

2009-01-01

The conclusion of the Angra III nuclear power plant ends a cycle of the nuclear energy in Brazil that started about forty years ago. Nowadays the country is planning the installation of 4 GWe to 8 GWe of nuclear power up to the year 2030. The nuclear reactors considered for this new cycle should take into account the current technologic development and environment of the nuclear market. They certainly will have significant differences in relation to the Angra I, II, and III reactors. Important impacts may result on the nuclear fuel production chain, e. g., case high temperature reactors were chosen, which can deliver electricity and heat. The differences between the fuels of the candidate reactors after Angra III are analyzed and development lines are suggested to minimize these impacts. (author)

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

Toxic elements in sediment from two water bodies near Brazilian Multipurpose Reactor: RMB installation area

Energy Technology Data Exchange (ETDEWEB)

Silva, Tatiane B.S.C. da; Stellato, Thamiris B.; Monteiro, Lucilena R.; Marques, Joyce R.; Faustino, Mainara G.; Santos, Camila F.R.T.T.; Oliveira, Cintia C. de; Miranda, Gabrielle S.; Pires, Maria Aparecida F.; Cotrim, Marycel E.B., E-mail: tatianebscs@live.com [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

2017-07-01

Aquatic ecosystems are directly affected by contaminants, such as, toxic elements that do not remain in sediment in a insoluble form. Anthropogenic and natural actions influence sediment dynamics that could lead to a potential contaminant accumulation. Therefore, to evaluate possible environmental impacts is,in many cases, mandatory. Environmental impact assessment studies are a licensing tool that seeks to control degradation activities, taking into account the legal and regulatory provisions and technical standards applicable to the case. The present study aims to evaluate the sediment quality in the area of influence of the Brazilian Multipurpose Nuclear Reactor (RMB) to be installed in the contiguous area of the Experimental Center of Aramar of the Technological Center of the Navy in São Paulo (CTMSP), located in the city of Iperó - SP. The potentially toxic elements As, Cd and Hg were analyzed by Graphite Furnace Atomic Absorption Spectrometry (GFAAS) and Cr, Cu, Ni and Zn by Inductively Coupled Plasma Optical Emission Spectrometry (ICP-OES). Results were compared with Canadian Council of Ministers of the Environment (CCME) guideline values (TEL and PEL) and the maximum permitted values of Resolution 454/12. These toxic elements (As, Cd, Hg, Cr, Cu, Ni and Zn) were found below maximum allowed concentrations from national and international legislation. This study provides support for RMB post-completion evaluations, in order to prevent these elements to exceed tolerated levels, ensuring ecological, social and economic values. (author)

Toxic elements in sediment from two water bodies near Brazilian Multipurpose Reactor: RMB installation area

International Nuclear Information System (INIS)

Silva, Tatiane B.S.C. da; Stellato, Thamiris B.; Monteiro, Lucilena R.; Marques, Joyce R.; Faustino, Mainara G.; Santos, Camila F.R.T.T.; Oliveira, Cintia C. de; Miranda, Gabrielle S.; Pires, Maria Aparecida F.; Cotrim, Marycel E.B.

2017-01-01

Aquatic ecosystems are directly affected by contaminants, such as, toxic elements that do not remain in sediment in a insoluble form. Anthropogenic and natural actions influence sediment dynamics that could lead to a potential contaminant accumulation. Therefore, to evaluate possible environmental impacts is,in many cases, mandatory. Environmental impact assessment studies are a licensing tool that seeks to control degradation activities, taking into account the legal and regulatory provisions and technical standards applicable to the case. The present study aims to evaluate the sediment quality in the area of influence of the Brazilian Multipurpose Nuclear Reactor (RMB) to be installed in the contiguous area of the Experimental Center of Aramar of the Technological Center of the Navy in São Paulo (CTMSP), located in the city of Iperó - SP. The potentially toxic elements As, Cd and Hg were analyzed by Graphite Furnace Atomic Absorption Spectrometry (GFAAS) and Cr, Cu, Ni and Zn by Inductively Coupled Plasma Optical Emission Spectrometry (ICP-OES). Results were compared with Canadian Council of Ministers of the Environment (CCME) guideline values (TEL and PEL) and the maximum permitted values of Resolution 454/12. These toxic elements (As, Cd, Hg, Cr, Cu, Ni and Zn) were found below maximum allowed concentrations from national and international legislation. This study provides support for RMB post-completion evaluations, in order to prevent these elements to exceed tolerated levels, ensuring ecological, social and economic values. (author)

Annual report 2000. ABACC - Brazilian-Argentine Agency for Accounting and Control of Nuclear Materials, RJ, Brazil

International Nuclear Information System (INIS)

2000-01-01

This document reports the general activities of the ABACC - Brazilian-Argentine Agency for Accounting and Control of Nuclear Materials during the year of 2000, covering safeguards, accounting and control of nuclear materials

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

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

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)

The brazilian nuclear policy with respect to the public opinion

International Nuclear Information System (INIS)

Freitas Brandao Bittencourt, C.

1988-01-01

Four decades of the Brazilian nuclear history have been analysed with special emphasis placed on government policy and its repercussion on public opinion. The implications of the new constitutional regulations which rule the issue are discussed. it is also studied the change in the nuclear program structure, enforced in August 1988. At different times, the government decisions on nuclear energy could be classified as miser, extravagant, dissimulated and frank, successively. Their aftermaths, which show little consistency with the expectations laid on them, have led to discredit by part of the society, which is controlled by a scientific - intellectual elite. However, recent successes are likely to reverse this trend, if the government explores them properly. (author) [pt

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)

Accountability and non-proliferation nuclear regime: a review of the mutual surveillance Brazilian-Argentine model for nuclear safeguards; Accountability e regime de nao proliferacao nuclear: uma avaliacao do modelo de vigilancia mutua brasileiro-argentina de salvaguardas nucleares

Energy Technology Data Exchange (ETDEWEB)

Xavier, Roberto Salles

2014-08-01

The regimes of accountability, the organizations of global governance and institutional arrangements of global governance of nuclear non-proliferation and of Mutual Vigilance Brazilian-Argentine of Nuclear Safeguards are the subject of research. The starting point is the importance of the institutional model of global governance for the effective control of non-proliferation of nuclear weapons. In this context, the research investigates how to structure the current arrangements of the international nuclear non-proliferation and what is the performance of model Mutual Vigilance Brazilian-Argentine of Nuclear Safeguards in relation to accountability regimes of global governance. For that, was searched the current literature of three theoretical dimensions: accountability, global governance and global governance organizations. In relation to the research method was used the case study and the treatment technique of data the analysis of content. The results allowed: to establish an evaluation model based on accountability mechanisms; to assess how behaves the model Mutual Vigilance Brazilian-Argentine Nuclear Safeguards front of the proposed accountability regime; and to measure the degree to which regional arrangements that work with systems of global governance can strengthen these international systems. (author)

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)

Intercomparison of 131I and 99mTc activity measurements in Brazilian nuclear medicine services

International Nuclear Information System (INIS)

Iwahara, Akira; De Oliveira, Antonio E.; Tauhata, Luiz; Silva, Carlos J. da; Lopes, Ricardo T.

2001-01-01

This work outlines the quality assurance program for the activity measurements of the most used radionuclides at Brazilian Nuclear Medicine Services (NMS). The program aims to guarantee that the patient is given the correct prescribed amount of activity in diagnostic or therapeutic applications. This accurate administration depends upon proper use and calibration of the activity meters by the NMS. Underestimation of administered activity in diagnostic practices could delay correct diagnosis disturbing the value of the investigation. On the other hand, the overestimation would be worse, mainly in therapeutic applications, because an unnecessarily high absorbed dose would be delivered to the patient. The preliminary results of intercomparison for 131 I and 99m Tc showed that many activity meters used at NMS's present problems giving results up to 41% greater than the reference values determined at the National Metrology Laboratory for Ionizing Radiation (LNMRI) which is recognized as the Brazilian authorized metrology laboratory for ionizing radiation. These results have demonstrated that the NMS should improve the accuracy of the activity measurements of the radionuclides administered to the patients and establish the traceability to the national standards of measurements. These standards are based on a pressurized well-type ionization chamber installed at LNMRI and calibrated with reference sources standardized by absolute methods. The protocol of the intercomparison and recommendations made in order to minimize errors in measuring procedures are described and results are discussed

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

Brazilian multipurpose reactor

Energy Technology Data Exchange (ETDEWEB)

NONE

2014-07-01

The Brazilian Multipurpose Reactor (RMB) Project is an action of the Federal Government, through the Ministry of Science Technology and Innovation (MCTI) and has its execution under the responsibility of the Brazilian National Nuclear Energy Commission (CNEN). Within the CNEN, the project is coordinated by the Research and Development Directorate (DPD) and developed through research units of this board: Institute of Nuclear Energy Research (IPEN); Nuclear Engineering Institute (IEN); Centre for Development of Nuclear Technology (CDTN); Regional Center of Nuclear Sciences (CRCN-NE); and Institute of Radiation Protection and Dosimetry (IRD). The Navy Technological Center in Sao Paulo (CTMSP) and also the participation of other research centers, universities, laboratories and companies in the nuclear sector are important and strategic partnerships. The conceptual design and the safety analysis of the reactor and main facilities, related to nuclear and environmental licensing, are performed by technicians of the research units of DPD / CNEN. The basic design was contracted to engineering companies as INTERTHECNE from Brazil and INVAP from Argentine. The research units from DPD/CNEN are also responsible for the design verification on all engineering documents developed by the contracted companies. The construction and installation should be performed by specific national companies and international partnerships. The Nuclear Reactor RMB will be a open pool type reactor with maximum power of 30 MW and have the OPAL nuclear reactor of 20 MW, built in Australia and designed by INVAP, as reference. The RMB reactor core will have a 5x5 configuration, consisting of 23 elements fuels (EC) of U{sub 3}Si{sub 2} dispersion-type Al having a density of up to 3.5 gU/cm{sup 3} and enrichment of 19.75% by weight of {sup 23{sup 5}}U. Two positions will be available in the core for materials irradiation devices. The main objectives of the RMB Reactor and the other nuclear and radioactive

Brazilian multipurpose reactor

International Nuclear Information System (INIS)

2014-01-01

The Brazilian Multipurpose Reactor (RMB) Project is an action of the Federal Government, through the Ministry of Science Technology and Innovation (MCTI) and has its execution under the responsibility of the Brazilian National Nuclear Energy Commission (CNEN). Within the CNEN, the project is coordinated by the Research and Development Directorate (DPD) and developed through research units of this board: Institute of Nuclear Energy Research (IPEN); Nuclear Engineering Institute (IEN); Centre for Development of Nuclear Technology (CDTN); Regional Center of Nuclear Sciences (CRCN-NE); and Institute of Radiation Protection and Dosimetry (IRD). The Navy Technological Center in Sao Paulo (CTMSP) and also the participation of other research centers, universities, laboratories and companies in the nuclear sector are important and strategic partnerships. The conceptual design and the safety analysis of the reactor and main facilities, related to nuclear and environmental licensing, are performed by technicians of the research units of DPD / CNEN. The basic design was contracted to engineering companies as INTERTHECNE from Brazil and INVAP from Argentine. The research units from DPD/CNEN are also responsible for the design verification on all engineering documents developed by the contracted companies. The construction and installation should be performed by specific national companies and international partnerships. The Nuclear Reactor RMB will be a open pool type reactor with maximum power of 30 MW and have the OPAL nuclear reactor of 20 MW, built in Australia and designed by INVAP, as reference. The RMB reactor core will have a 5x5 configuration, consisting of 23 elements fuels (EC) of U 3 Si 2 dispersion-type Al having a density of up to 3.5 gU/cm 3 and enrichment of 19.75% by weight of 23 5 U. Two positions will be available in the core for materials irradiation devices. The main objectives of the RMB Reactor and the other nuclear and radioactive facilities are

Status of nuclear power programs in South America

International Nuclear Information System (INIS)

Spitalnik, J.

2010-10-01

Analysis of nuclear power plants construction in four South American countries - Argentina, Brazil, Chile and Uruguay - is made based on programs set up by government specialized agencies. In Argentina, in a time-span up to 2023, the nuclear power program considers a five-fold increase of the current installed capacity reaching some 5,000 M We. The Brazilian reference scenario will install additional 4,000 M We, up to 2030, to reach a total installed capacity of about 6,000 M We. Other scenarios could bring this total to some 8,000 - 10,000 M We. Chile and Uruguay have started strategic studies to place the nuclear power option in the future energy matrix of the country. The government of Chile set up, in 2007, a Task Group to determine whether nuclear power could be considered a viable option. This Group concluded that nuclear power is a mature, safe competitive, and low carbon emitter technology that could be considered a viable option. A Nuclear Advisory Group was created who made studies to install a nuclear power plant in the 2016-2021 time-span. In December 2008, the Uruguayan Government created a high level Working Group to establish the feasibility conditions for Nuclear Power Generation in the country. (Author)

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

On December 15, 2000 Unit 3 of Chernobyl NPP, which is the last one in Ukraine having RBMK-type reactor, was permanently shutdown before the end of its lifetime. A number of projects related to establishing infrastructure for the plant decommissioning are being implemented in compliance with the Ukraine's commitments. Decommissioning stage includes activities on fuel unloading from the cores of Unit I and Unit 3, fuel cooling in the ponds followed by the fuel transportation to the spent fuel dry storage facility (currently under construction) for its safe long-term storage. Special facilities are being created for liquid and solid radioactive waste treatment. Besides, it is planned to implement a number of projects to convert Shelter Object in environmentally safe structure. Physical protection work being an essential part of the nuclear material management is organized in line with the recommendations of the IAEA, and the Laws of Ukraine 'On Nuclear Energy Utilization and Radiation Safety', 'On Physical Protection of Nuclear Installations and Materials', 'Regulations on Physical Protection of Nuclear Materials and Installations', other codes and standards. While organizing physical protection on ChNPP decommissioning stage we have to deal with some specific features, namely: Significant amount of fuel assemblies, which are continuously transferred between various storage and operation facilities; Big amount of odd nuclear material at Shelter Object; 'Theft of new fuel fragments from the central hall of the Shelter Object in 1995 with the intention of their further sale. The thieves were detained and sentenced. The stolen material was withdrawn, that prevented its possible proliferation and illicit trafficking. At present physical protection of ChNPP does not fully satisfy the needs of the decommissioning stage and Ukraine's commitments on non-admission of illicit trafficking. Work is carried out, aimed to improve nuclear material physical protection, whose main

Heat-electricity convertion systems for a Brazilian space micro nuclear reactor

Energy Technology Data Exchange (ETDEWEB)

Guimaraes, Lamartine N.F.; Marcelino, Natalia B.; Placco, Guilherme M.; Nascimento, Jamil A.; Borges, Eduardo M., E-mail: guimarae@ieav.cta.br, E-mail: lamartine.guimaraes@pq.cnpq.br, E-mail: jamil@ieav.cta.br, E-mail: jalnsgf@outlook.com, E-mail: borges.em@hotmail.com, E-mail: ecorborges@hotmail.com, E-mail: ivayolini@gmail.com, E-mail: guilherme_placco@ig.com.br [Instituto de Estudos Avancados (IEAv/DCTA), Sao Jose dos Campos, SP (Brazil); Barrios Junior, Ary Garcia, E-mail: arygarcia89@yahoo.com [Faculdade de Tecnologia Sao Francisco (FATESF), Jacarei, SP (Brazil)

2013-07-01

This contribution will discuss the evolution work in the development of thermal cycles to allow the development of heat-electricity conversion for the Brazilian space micro nuclear Reactor. Namely, innovative core and nuclear fuel elements, Brayton cycle, Stirling engine, heat pipes, passive multi-fluid turbine, among others. This work is basically to set up the experimental labs that will allow the specification and design of the space equipment. Also, some discussion of the cost so far, and possible other applications will be presented. (author)

Heat-electricity convertion systems for a Brazilian space micro nuclear reactor

International Nuclear Information System (INIS)

Guimaraes, Lamartine N.F.; Marcelino, Natalia B.; Placco, Guilherme M.; Nascimento, Jamil A.; Borges, Eduardo M.; Barrios Junior, Ary Garcia

2013-01-01

This contribution will discuss the evolution work in the development of thermal cycles to allow the development of heat-electricity conversion for the Brazilian space micro nuclear Reactor. Namely, innovative core and nuclear fuel elements, Brayton cycle, Stirling engine, heat pipes, passive multi-fluid turbine, among others. This work is basically to set up the experimental labs that will allow the specification and design of the space equipment. Also, some discussion of the cost so far, and possible other applications will be presented. (author)

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

Nuclebras' installations for performance tests of nuclear power plants components

International Nuclear Information System (INIS)

Vasconcelos Paiva, I.P. de; Avelar Esteves, F. de; Horta, J.A.L.; Resende, M.F.R.; Pinheiro, R.B.

1984-01-01

The reasons for Nuclebras' Nuclear Technology Development Center to implement a laboratory for supporting Brazilian manufactures, giving to them the means for performing functional tests of industrial products, are presented. A brief description of facilities under construction: the components Test Loop and Facility for Testing N.P.P. components under Accident conditions, and other already in operation, as well as its objectives and main technical characteristics. Some test results had already obtained are also presented. (Author) [pt

Sixth national report of Brazil for the nuclear safety convention

International Nuclear Information System (INIS)

2013-01-01

Brazil has presented periodically its National Report prepared by a group composed of representatives of the various Brazilian organizations with responsibilities related to nuclear safety. Due to the implications of the Fukushima nuclear accident in 2011, an Extraordinary National Report was presented in 2012. This Sixth National Report is an update of the Fifth National Report in relation to the Convention on Nuclear Safety articles and also an update of the Extraordinary Report with respect to the action taken related to lesson learned from the Fukushima accident. It includes relevant information for the period of 2010/2012. This document represents the national report prepared as a fulfillment of the brazilian obligations related to the Convention on Nuclear Safety. In chapter 2 some details are given about the existing nuclear installations. Chapter 3 provides details about the legislation and regulations, including the regulatory framework and the regulatory body. Chapter 4 covers general safety considerations as described in articles 10 to 16 of the Convention. Chapter 5 addresses to the safety of the installations during siting, design, construction and operation. Chapter 6 describes planned activities to further enhance nuclear safety. Chapter 7 presents the final remarks related to the degree of compliance with the Convention obligations

Sixth national report of Brazil for the nuclear safety convention

Energy Technology Data Exchange (ETDEWEB)

NONE

2013-07-01

Brazil has presented periodically its National Report prepared by a group composed of representatives of the various Brazilian organizations with responsibilities related to nuclear safety. Due to the implications of the Fukushima nuclear accident in 2011, an Extraordinary National Report was presented in 2012. This Sixth National Report is an update of the Fifth National Report in relation to the Convention on Nuclear Safety articles and also an update of the Extraordinary Report with respect to the action taken related to lesson learned from the Fukushima accident. It includes relevant information for the period of 2010/2012. This document represents the national report prepared as a fulfillment of the brazilian obligations related to the Convention on Nuclear Safety. In chapter 2 some details are given about the existing nuclear installations. Chapter 3 provides details about the legislation and regulations, including the regulatory framework and the regulatory body. Chapter 4 covers general safety considerations as described in articles 10 to 16 of the Convention. Chapter 5 addresses to the safety of the installations during siting, design, construction and operation. Chapter 6 describes planned activities to further enhance nuclear safety. Chapter 7 presents the final remarks related to the degree of compliance with the Convention obligations.

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

The Brazilian-Argentine Agency for Accounting and Control of Nuclear Materials (ABACC) as safeguard regional agency

International Nuclear Information System (INIS)

Alvim, C.F.

1994-01-01

The Brazilian-Argentine Agency for Accounting and Control of Nuclear Materials - ABACC applies regional safeguards on nuclear materials in Brazil and Argentina. The framework of international agreements concerning ABACC is presented, and the characteristics and requirements that a regional nuclear safeguards organization must fulfill are discussed. (author). 2 refs, 1 tab

Annual report 2004 of ABACC - Brazilian-Argentine Agency for Accounting and Control of Nuclear Materials, RJ, Brazil

International Nuclear Information System (INIS)

2004-01-01

This document reports the general activities of the ABACC - Brazilian-Argentine Agency for Accounting and Control of Nuclear Materials during the year of 2004, covering safeguards, accounting and control of nuclear materials

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 role of nuclear energy in brazilian energy matrix: socioeconomic and environmental aspects

International Nuclear Information System (INIS)

Schirmer, Priscila

2016-01-01

With the large increase of energy demand in the world, either for the continued expansion of industrialization, or by the raise of consumption, are increasing the need for energy sources diversification and the search for cleaner alternatives of energy production. Nuclear power has been considered as an option to curb the emission of greenhouse gases and reduce the dependence of fossil fuels. However, nuclear energy is an issue that still causes a lot of doubt and questions, turning the development of this work very important for a better understanding of the lay public as well as to contribute and encourage future research through an assessment of their environmental and socio-economic aspects, discussing the risks, benefits, and an assessment of the expansion of nuclear energy use, including an overview of nuclear energy in Brazil. Concluding that nuclear energy can contribute to the expansion of the Brazilian energy matrix, as the only heat source able to ensure constant supply of energy without emitting greenhouse gases. Considering that Brazil dominates the technology of the nuclear fuel cycle, and has a large reserves of uranium. A larger share of nuclear energy in the Brazilian energy matrix can generate greater diversification of the same, valuing the environmental and economic sustainability of the country and reducing the system's vulnerability. However, nuclear generation should not be considered as the only solution to the energy problems of the country, but make a part of it by the combination with other renewable sources, increasing the diversity and energy security of the country. (author)

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

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

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

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

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

Annual Report 2007 - ABACC - Brazilian-Argentine Agency for Accounting and Control of Nuclear Materials

International Nuclear Information System (INIS)

2007-01-01

This document reports activities during the year 2007 related to: technical activities as application of safeguards; management of the Quadripartite Agreement and the SCCC - Common System for Accounting and Control of Nuclear Materials; training; technical cooperation; outlook for 2008 and; institutional, administrative and financial activities; technical glossary; list of brazilian facilities; list of argentine facilities and a list of institution of nuclear area

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

Nuclear indecision: loss in the past and a risk for the future

International Nuclear Information System (INIS)

Mattos, Joao Roberto Loureiro de; Dias, Marcio Soares; Vasconcelos, Vanderley de; Jordao, Elizabete

2006-01-01

Presently the Brazil have a new opportunity exploring the nuclear option for providing a more diversification and reliability to the brazilian electric system and the first step is the conclusion of Angra 3, followed by another nuclear installations, giving priority to the northeast of the country which is the region with lack of primary sources and therefore with risk of deficit

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.

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)

Annual report 2001. ABACC 10 years - Brazilian-Argentine Agency for Accounting and Control of Nuclear Materials, RJ, Brazil

International Nuclear Information System (INIS)

2001-01-01

This document represents the 2001 Annual report. ABACC 10 years - Brazilian-Argentine Agency for Accounting and Control of Nuclear Materials during the year of 2000, covering safeguards, accounting and control of nuclear materials

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

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)

NUCLEBRAS' experience in the implantation of a nuclear power plants simulator

International Nuclear Information System (INIS)

Spitalnik, J.; Fonseca, G.

1985-01-01

The experiences gained by NUCLEBRAS in the setting up of a Nuclear Power Plant Simulator Training Center, cover the design and manufacture of the simulator for the Angra-2 type nuclear power plants, the training of the simulator operation and maintenance personnel, in preparation for the training of the Brazilian nuclear power plant operators, the development of the simulator training programs and materials, the temporary installation and utilization of the simulator in the FRG, including the training of operators of the Trillo nuclear power plant, in Spain. The simulator shall be finally installed in Brazil, at the vicinity of the Angra-2 site, in 1985, when it is foreseen to start the training of the Angra-2 operators. (Author) [pt

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)

Economy of scale for nuclear power plants operating in hydroelectric systems - Brazilian case study

International Nuclear Information System (INIS)

Andrade, Gilberto

1996-01-01

Economy of scale is considered to enhance competitiveness of nuclear energy for electricity generation but only when high capacity factors are considered. This study shows that for the brazilian electricity generation system low capacity factors are expected and economy of scale has to be considered against the size of the Nuclear program. Units of 600 MW are competitive both for small and large Programs. (author)

Brazilian Irradiation Project: CAFE-MOD1 validation experimental program

International Nuclear Information System (INIS)

Mattos, Joao Roberto Loureiro de; Costa, Antonio Carlos L. da; Esteves, Fernando Avelar; Dias, Marcio Soares

1999-01-01

The Brazilian Irradiation Project whose purpose is to provide Brazil with a minimal structure to qualify the design, fabrication and quality procedures of nuclear fuels, consists of three main facilities: IEA-R1 reactor of IPEN-CNEN/SP, CAFE-MOD1 irradiation device and a unit of hot cells. The CAFE-MOD1 is based on concepts successfully used for more than 20 years in the main nuclear institutes around the world. Despite these concepts are already proved it should be adapted to each reactor condition. For this purpose, there is an ongoing experimental program aiming at the certification of the criteria and operational limits of the CAFE-MOD1 in order to get the allowance for its installation at the IEA-R1 reactor. (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

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)

The protection system to Brazilian Nuclear Program; O sistema de protecao ao Programa Nuclear Brasileiro

Energy Technology Data Exchange (ETDEWEB)

Andreuzza, Mario Giussepp Santezzi Bertottelli [Secretaria de Assuntos Estrategicos (SAE), Brasilia, DF (Brazil)

1997-12-31

The Sistema de Protecao ao Programa Nuclear Brasileiro-SIPRON (Protection System to Brazilian Nuclear Program) was established in 1980. It is intended to accomplish in only one system, all the actions related to security and protection for Nuclear Facilities in Brazil. The author presents in detail the protection system SIPRON, describing the system structure and organization, the functions and obligations of the system involved main organizations, as well as, the system operation and behaviour during an postulated occurrence of a nuclear emergency. It is also described an Exercise that happened in June of 1997 at the Nuclear Power Plant (NPP) Angra I, after two simulated tests in December of 1996 and April of 1997. The NPP Angra I Emergency Plan Exercise was a good opportunity to test the SIPRON structure and preparedness program. It was verified, included by International Atomic Energy Agency observers, the system involved organizations effectiveness and the procedures efficacy to protect the public and the environmental. Finally, it is shown the SIPRON activities of routine, the system obstacles and the expected future performances. (author) 3 refs., 3 figs.

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

A diagnostic of the strategy employed for communicating nuclear related information to Brazilian communities around uranium mining areas

International Nuclear Information System (INIS)

Ferrari Dias, Fabiana; Tirollo Taddei, Maria H.

2008-01-01

This paper presents a diagnostic of the strategy used by the Brazilian uranium mining industry to communicate nuclear related information to communities around a mining area. The uranium mining industry in Brazil, which is run by the government, has been concerned with communication issues for quite some time. The need to communicate became more apparent after new mining operations started in the Northern region of Brazil. The fact that the government does not have a clear communication guideline made the operators of the uranium mining industry aware of the increasing demand for establishment of a good relationship with several types of Stake holders as well as employment of personnel with experience in dealing with them. A diagnostic of the current communication situation in Brazil and an analysis of the approaches over the past years was done through interviews with employees of the mining industry and review of institutional communication materials. The results were discussed during a Consultant's Meeting organized by the IAEA 's Seibersdorf Laboratory in October 2007. The output of the meeting included an overview of modern communication strategies used by different countries and a suggestion for new uranium mining operations in developing or under developed countries. The strategy for communicating nuclear related information to Brazilian communities varied according to the influence of different Stake holder groups. One initiative worth mentioning was the creation of a Mobile Nuclear Information Thematic Room, which was installed in several locations. This project was seen as one of the main tools to relate to community. Many Stake holders were identified during the diagnostic phase in preparation for the IAEA 's meeting on communication strategy: children, NGOs (Non Government Organizations), local churches, media and internal Stake holders, among others. An initial evaluation showed that the perception of a neighbouring community regarding an uranium

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

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

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

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.)

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

Study of the Brazilian scientific production in the nuclear field from 1970 to 1979

International Nuclear Information System (INIS)

Nascimento, M. de J.

1983-01-01

The study of some patterns of the Brazilian scientific literature production - e.g., generated and/or published in Brazil - in the nuclear field included in CIN (Nuclear Information Center) / INIS (International Nuclear Information System) data base from 1970 to 1979 is presented. The purpose is to research: - the growth of the production; - the main subject areas; - the language of the publication; - the literature presentation form; - the author's characterization; - the most productive institutions, their geographical distribution and countries where the literature is published. (E.G.) [pt

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

Fifth national report of Brazil for the nuclear safety convention

International Nuclear Information System (INIS)

2010-01-01

This Fifth National Report is a new update to include relevant information for the period of 2007/2009. This document represents the national report prepared as a fulfillment of the Brazilian obligations related to the Convention on Nuclear Safety. In chapter 2 some details are given about the existing nuclear installations. Chapter 3 provides details about the legislation and regulations, including the regulatory framework and the regulatory body. Chapter 4 covers general safety considerations as described in articles 10 to 16 of the Convention. Chapter 5 addresses to the safety of the installations during siting, design, construction and operation. Chapter 6 describes planned activities to further enhance nuclear safety. Chapter 7 presents the final remarks related to the degree of compliance with the Convention obligations

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)

Experience of a Brazilian A/E in seismic analysis of nuclear structures components

International Nuclear Information System (INIS)

Venancio Filho, F.; Leal, M.R.L.V.; Bevilacqua, L.

1980-01-01

The experience of Promon Engenharia S.A., a Brazilian A/E which participated in the civil and mechanical engineering projects of the first Nuclear Power Plant in Brazil, is presented. In these projects the aspects of input for seismic analysis, seismic analysis in nuclear structures founded on piles, dynamic analysis for airplane crash, and piping analysis had to be faced for the first time in the country. The solution of these problems and some case examples are presented. (Author) [pt

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

Nuclear policy retrospection in Brazil and forecasting for using of small nuclear power plants - SNPs - in the Brazilian electric system

International Nuclear Information System (INIS)

Santos, E.M. dos.

1992-02-01

This thesis highlights the nuclear energy perspectives to regain a prominent place in the world energy mix, as a competitive and safe energy source. Just considering the current international changes in the nuclear power features in the developed countries, it is assessed the suitability and feasibility of defining a new nuclear policy in Brazil, based on the development of small and medium nuclear power reactors - SMNPR. The SMNPR's may be a good nuclear strategy for Brazil to develop a national and evolutionary reactor design with several improvements in safety, by means of passive safety systems. This reactor may play a significant role in the brazilian electrical system in the long term. (author)

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)

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)

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)

Regulatory oversight report 2016 concerning nuclear safety in Swiss nuclear installations

International Nuclear Information System (INIS)

2017-06-01

ENSI, the Swiss Federal Nuclear Safety Inspectorate, assesses and monitors safety in the Swiss nuclear facilities. These include the five nuclear power plants: Beznau Units 1 and 2 (KKB1 and KKB2), Muehleberg (KKM), Goesgen (KKG) and Leibstadt (KKL), the interim storage facilities based at each plant, the Central Interim Storage Facility (Zwilag) in Wuerenlingen together with the nuclear facilities at the Paul Scherrer Institute (PSI), the University of Basel (UniB) and the Federal Institute of Technology in Lausanne (EPFL). Using a combination of inspections, regulatory meetings, checks, analyses and the reporting of the operators of individual facilities, ENSI obtains the required overview of nuclear safety in these facilities. It ensures that they operate as required by law. ENSI's regulatory responsibilities also include the transport of radioactive materials from and to nuclear facilities and preparations for a deep geological repository for radioactive waste. ENSI maintains its own emergency organisation, which is an integral part of the national emergency structure that would be activated in the event of a serious incident at a nuclear facility in Switzerland. ENSI reports periodically on its supervisory activities. It informs the public about special events and findings in the nuclear installations. All five nuclear power plants in Switzerland operated safely during the past year. Nuclear safety at all plants in operation was rated as good or satisfactory. In 2016, there were 31 reportable events at the nuclear power plants. 30 events were rated Level 0 (event of no or low safety significance) on the International Nuclear and Radiological Event Scale (INES) and one was rated Level 1 (anomaly) at KKL. Zwilag consists of several interim storage buildings, a conditioning plant and a plasma plant (incineration/melting plant). At the end of 2016, the cask storage hall contained 56 transport/storage casks with spent fuel assemblies and vitrified residue

Centro Regional de Ciencias Nucleares (a Brazilian regional center for nuclear sciences) - activities report - 1999; Centro Regional de Ciencias Nucleares - relatorio de atividades - 1999

Energy Technology Data Exchange (ETDEWEB)

NONE

1999-12-01

The annual activities report of 1999 of nuclear sciences regional center - Brazilian organization - introduces the next main topics: institutional relations; sectorial actions - logistic support and training, laboratory of radiation protection and dosimetry, laboratory of metrology, laboratory of chemical characterization; technical and scientific events; and financial resources and perspectives for 2000.

Fabrication of mechanical components and piping design for Brazilian nuclear reactors

International Nuclear Information System (INIS)

Deppe, L.O.

1987-01-01

The supply of Brazilian equipment and piping design for Angra 2 (and Angra 3 in some cases) have reached an advanced status in spite of the continuous outside difficulties which affect these nuclear power plants. The achieved quality is similar to the quality achieved in foreign countries and the nationalization program foreseen in 1975 is being largely surpassed. In this paper the actual situation is presented as well as the future perspectives. (Author) [pt

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

Nuclear low and environmental protection

International Nuclear Information System (INIS)

Vencato, A.C.B.

1982-01-01

The imperceptible character of nuclear radiation on the human senses and their harmful effects on living beings and the environment is emphasised. This is based on a review of published works about the concepts of energy and ecology. The potential hazards of a possible nuclear accident and the damage it would cause to a community as well as the problem of radioactive waste disposal are raised. The conclusions and recommendations of the Brazilian Physics Society's Report on Nuclear Pollution are endorsed. The general guidelines of Brazilian Legislation are presented. The legal aspects of nuclear reactor licensing in West Germany, the United Kingdom, France and Brazil are shown from the point of view of the applicable legal system, the licensing bodies, the general frame and scope, public participation, technical safety bodies, as well as the inspection procedures. The concepts of absolute and objective civil responsibility for nuclear damage are reviewed. The judicial principle of equity is considered in view of the exceptional character of the nuclear risk. The main aspects of the international Conventions of Paris, Brussels and Viena on civil ability of nuclear damage are presented. Some philosphical and judicial questions are discussed emphasising the instrumentality of the law control and effective protection. The final suggestion is the exchange of ideas with a view to obtain the maximum safety in the operation of nuclear installations. (author) [pt

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)

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.

Participation of the Nuclear Power Plants in the New Brazilian Electric Energy Market

International Nuclear Information System (INIS)

Mathias, S.G.

2004-01-01

A new regulation framework has been established for the Brazilian electric energy market by a law put into effect on March 15,2004. The main overall goals of this new regulation are: to allow the lowest possible tariffs for end users, while providing the necessary economic incentives for the operation of present installations (generating plants, transmission lines, distribution networks) and the expansion of the system; long-term planning of the extension of the installations required to meet the demand growth; separation of the generation, transmission and distribution activities by allocating them into different companies; new contracts between generating and distribution companies must result from bidding processes based on lowest-tariff criteria; and energy from new generating units required to meet the demand growth must be contracted by all distributing companies integrated to the National Interconnected Grid, in individual amounts proportional to their respective markets

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

Decommissioning of a nuclear facility: the Brazilian case

International Nuclear Information System (INIS)

Menezes, Regina M.; Deppe, Alzira L.; Nunes, Marcos E.C.; Cardoso, Eliezer M.; Nouailhetas, Y.; Mouco, Charles; Ferreira, Paulo R.; Matta, Luiz E.da

1996-01-01

The first decommissioning process of a nuclear facility in Brazil, has being taken place in Usina de Santo Amaro (USAM), located in Sao Paulo whose physical and chemical milling activities of the monazitic sands were interrupted in June 1992. Nowadays, materials and equipment generated from Minerals Physical Treatment and Rare Earths Separation Sectors, classified as low level radiation areas, are in final phase of dismantling, monitoring and release to the internal backyard of the facility or segregation in controlled areas. This decommissioning phase is considered as pilot for the verification of procedures, follow up of pieces and application of suitable radioprotection measures for the future dismantling of the Chemical Treatment of Monazite Sector, which will involve higher risks regarding radioprotection and safety aspects. The criteria of discharge of areas and equipment established by CNEN are conservative enough to assure that the contamination is not released to the environment. CNEN's activities conducted at the surveillance of works involving the dismantling and decontamination of materials and equipment verifying that they are in accordance with the requirements established by the Brazilian Commission of Nuclear Energy. (author)

Fourth national report of Brazil for the nuclear safety convention. Sep. 2007

International Nuclear Information System (INIS)

2007-09-01

This Fourth National Report of Brazil is a new update to include relevant information of the period of 2004-2007. This document represents the national report prepared as a fulfillment of the brazilian obligations related to the Convention on Nuclear Safety. In chapter 2 some details are given about the existing nuclear installations. Chapter 3 provides details about the legislation and regulations, including the regulatory framework and the regulatory body. Chapter 4 covers general safety considerations as described in articles 10 to 16 of the Convention. Chapter 5 addresses to the safety of the installations during siting, design, construction and operation. Chapter 6 describes planned activities to further enhance nuclear safety. Chapter 7 presents the final remarks related to the degree of compliance with the Convention obligations

Fourth national report of Brazil for the nuclear safety convention. Sep. 2007

Energy Technology Data Exchange (ETDEWEB)

NONE

2007-09-15

This Fourth National Report of Brazil is a new update to include relevant information of the period of 2004-2007. This document represents the national report prepared as a fulfillment of the brazilian obligations related to the Convention on Nuclear Safety. In chapter 2 some details are given about the existing nuclear installations. Chapter 3 provides details about the legislation and regulations, including the regulatory framework and the regulatory body. Chapter 4 covers general safety considerations as described in articles 10 to 16 of the Convention. Chapter 5 addresses to the safety of the installations during siting, design, construction and operation. Chapter 6 describes planned activities to further enhance nuclear safety. Chapter 7 presents the final remarks related to the degree of compliance with the Convention obligations

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)

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

Strategies of implementation and effects of national technological development big programmes: experiences of Brazilian Navy nuclear programme

International Nuclear Information System (INIS)

Guimaraes, Leonam dos Santos

2005-01-01

The science and technology development, for which creativity and innovation must be always present, are supported by three fundamental principles: the first is related to existence of human brains and good conditions for its realizations; the second could be located in people and institution mobilization for accomplishment of objectives and goals which generate strategic or social benefits; the third are relates to a national effort, making sufficient resources reach the scientific and technological areas. Brazilian Navy, trough its Technological Center in Sao Paulo, developed a particular approach to follow these principles in order to get a technological 'jump' which will give Brazilian Naval Power, through submarine nuclear propulsion, the capabilities required by the nation's importance in the international scene. This Program, started in the early 80's, has presented very impressive results, not only in the vertical sense pointing to its goal, but also in the horizontal sense of diversification, referring to a deliberate change of activities away from purely nuclear, and spin-offs, referring to application of results of nuclear R and D outside nuclear sector. (author)

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

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

The Non-Proliferation Treaty of Nuclear Weapons (NPT) and the insertion of the Brazilian State in its regime

International Nuclear Information System (INIS)

Silva, Marcos Valle Machado da

2010-01-01

The issue of nuclear weapons continues to appear as a focal point of International Relations. The efforts and concrete actions on disarmament, non-proliferation, and nuclear arms control are still issues that generate recurring tensions between States. However, in Brazil, there is little analysis of an academic nature about these issues and, with respect to current and prospective position of the Brazilian State in the Nuclear Weapons Non- Proliferation Regime, studies and analysis are even more scarce, or incipient. The present dissertation has as its object of study to the Treaty on the Non-Proliferation of Nuclear Weapons (NPT), the Regime arisen from NPT, and the Brazilian State insertion process in this Regime. Therefore our research work is structured in three areas: the first one is about the role of nuclear weapons in States security perception, the second is about NPT and its Regime, the third runs over the insertion of the Brazilian state in this regime. So, in summary, the research performed included the reasons that make a State to develop nuclear weapons, the NPT genesis and evolution of the perception of the meaning of that Treaty by the States, and the process and the degree of insertion of Brazil in the Nuclear Weapons Non- Proliferation Regime. The inquiry sought to place this object of study in the broader debate on Foreign Relations, based on the approaches of the discipline devoted to the question of managing the security of States, id est, the two approaches that constitute the mainstream of the discipline: the perspective theoretical liberal (and neoliberal variants) and realistic thinking (and neo-realist). Thus, we have used different theoretical lenses, which we think necessary for understanding the specific parts and causal connections between these parts of a complex issue. (author)

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)

The social construction of risk and the controversial Brazilian Nuclear Program: among scientific, political and public

International Nuclear Information System (INIS)

Camelo, Ana Paula

2015-01-01

This research aims to investigate the Brazilian Nuclear Program (PNB) stating as reference the Fukushima nuclear accident. Its main purpose is to analyze how the Japanese accident impacted the PNB. Therefore, the program will be analyzed within 10-years (2004-2014) in order to answer this question. The discussion launched in this thesis is based on the framework of the Social Studies of Science and Technology, which enables the understanding of socio-technical controversies beyond the social or technological determinism. Through the discussion of the concepts of framing, socio-technical imaginary, risk and governance of science and technology, the research shows how the controversy in focus has resulted in the opportunity to consider not only economic, technological, environmental issues about nuclear energy, but also its political dimensions and challenges. Among these challenges, and from very different perspectives, arise questions about the role nuclear energy plays in the Brazilian context, the future of the program and the decision making process on these issues. Despite the central purpose of this study is essentially on risks, PNB and on the Brazilian context, it should be pointed that it is impossible to consider it in isolation of what is happening internationally (considering interests, tensions, relations between actors, etc.) The research thereby identifies key implications of Fukushima in the international context, but focuses on the disputes regarding possible review of the PNB. It also highlights how the socio-technical controversies, such as the nuclear energy, demand or impose a discussion on the governance of science and technology, risk and on the engagement of different sectors and actors in decision-making on issues, that are at the same time about energy, technology and nationality relevance. All this reflection is made from multi-sited analysis, which allowed following the controversy surrounding nuclear energy, reheated by the Fukushima

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

RMB. The new Brazilian multipurpose research reactor

International Nuclear Information System (INIS)

Perrotta, Jose Augusto; Soares, Adalberto Jose

2015-01-01

Brazil has four research reactors (RR) in operation: IEA-R1, a 5 MW pool type RR; IPR-R1, a 100 kW TRIGA type RR; ARGONAUTA, a 500 W Argonaut type RR, and IPEN/MB-01, a 100 W critical facility. The first three were constructed in the 50's and 60's, for teaching, training, and nuclear research, and for many years they were the basic infrastructure for the Brazilian nuclear developing program. The last, IPEN/MB-01, is the result of a national project developed specifically for qualification of reactor physics codes. Considering the relative low power of Brazilian research reactors, with exception of IEAR1, none of the other reactors are feasible for radioisotope production, and even IEA-R1 has a limited capacity. As a consequence, since long ago, 100% of the Mo-99 needed to attend Brazilian nuclear medicine services has been imported. Because of the high dependence on external supply, the international Moly-99 supply crisis that occurred in 2008/2009 affected significantly Brazilian nuclear medicine services, and as presented in previous IAEA events, in 2010 Brazilian government formalized the decision to build a new research reactor. The new reactor named RMB (Brazilian Multipurpose Reactor) will be a 30 MW open pool type reactor, using low enriched uranium fuel. The facility will be part of a new nuclear research centre, to be built about 100 kilometres from Sao Paulo city, in the southern part of Brazil. The new nuclear research centre will have several facilities, to use thermal and cold neutron beams; to produce radioisotopes; to perform neutron activation analysis; and to perform irradiations tests of materials and fuels of interest for the Brazilian nuclear program. An additional facility will be used to store, for at least 100 years, all the fuel used in the reactor. The paper describes the main characteristics of the new centre, emphasising the research reactor and giving a brief description of the laboratories that will be constructed, It also presents the

RMB. The new Brazilian multipurpose research reactor

Energy Technology Data Exchange (ETDEWEB)

Perrotta, Jose Augusto; Soares, Adalberto Jose [Comissao Nacional de Energia Nuclear (CNEN) (Brazil)

2015-01-15

Brazil has four research reactors (RR) in operation: IEA-R1, a 5 MW pool type RR; IPR-R1, a 100 kW TRIGA type RR; ARGONAUTA, a 500 W Argonaut type RR, and IPEN/MB-01, a 100 W critical facility. The first three were constructed in the 50's and 60's, for teaching, training, and nuclear research, and for many years they were the basic infrastructure for the Brazilian nuclear developing program. The last, IPEN/MB-01, is the result of a national project developed specifically for qualification of reactor physics codes. Considering the relative low power of Brazilian research reactors, with exception of IEAR1, none of the other reactors are feasible for radioisotope production, and even IEA-R1 has a limited capacity. As a consequence, since long ago, 100% of the Mo-99 needed to attend Brazilian nuclear medicine services has been imported. Because of the high dependence on external supply, the international Moly-99 supply crisis that occurred in 2008/2009 affected significantly Brazilian nuclear medicine services, and as presented in previous IAEA events, in 2010 Brazilian government formalized the decision to build a new research reactor. The new reactor named RMB (Brazilian Multipurpose Reactor) will be a 30 MW open pool type reactor, using low enriched uranium fuel. The facility will be part of a new nuclear research centre, to be built about 100 kilometres from Sao Paulo city, in the southern part of Brazil. The new nuclear research centre will have several facilities, to use thermal and cold neutron beams; to produce radioisotopes; to perform neutron activation analysis; and to perform irradiations tests of materials and fuels of interest for the Brazilian nuclear program. An additional facility will be used to store, for at least 100 years, all the fuel used in the reactor. The paper describes the main characteristics of the new centre, emphasising the research reactor and giving a brief description of the laboratories that will be constructed, It also

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)

Forecasting of the radioactive material transport demand for the Brazilian Nuclear Program and the security aspects

International Nuclear Information System (INIS)

Meldonian, Nelson Leon

1979-01-01

In the nuclear fuel cycle, a lot of radioactive materials are produced. These radioactive materials must be transported in order to promote the integration of the fuel cycle units. Considerations about the transport characteristics of radioactive material were made for each section of the fuel cycle. These considerations were based on the experience of several countries and in accordance with the International Atomic Energy Agency regulations. A prediction of transport demands for the Brazilian Nuclear Program until year 2.010 was made. The prediction refers mainly to the quantity of radioactive material produced in each section of the cycle the quantity of vehicles needed for the transport of these materials. Several safety aspects were considered specially, the accidents predictions for years 2.000 and 2.010. The accident probability in Brazilian railroads and highways was compared with that of the USA. (author)

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

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)

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

International Nuclear Information System (INIS)

Pereira, Wagner de S.; Py Junior, Delcy de A.; Kelecom, Alphonse; Mortagua, Valter

2009-01-01

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

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

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

Proceedings of the 2. SIPEN: Integration week from IPEN - Brazilian Institute for Energy and Nuclear Researches, CNEN/SP

International Nuclear Information System (INIS)

1994-01-01

The technical-scientific activities of IPEN (Instituto de Pesquisas Energeticas e Nucleares), Brazilian CNEN, has been presented in these proceedings. It includes the following topics: management and logistics, infra-structure and support, application of nuclear techniques, fuel cycle, materials, reactor research, development of products and services, radiation protection and monitoring. Nuclear medicine and application of radiation in biological assays are studied. Environmental impacts and management of radioactive wastes are also presented

Development of processes for the utilization of Brazilian coal using nuclear process heat and/or nuclear process steam

International Nuclear Information System (INIS)

Bamert, H.; Niessen, H.F.; Walbeck, M.; Wasrzik, U.; Mueller, R.; Schiffers, U.; Strauss, W.

1980-01-01

Status of the project: End of the project definition phase and preparation of the planned conceptual phase. Objective of the project: Development of processes for the utilization of nuclear process heat and/or nuclear process steam for the gasification of coal with high ash content, in particular coal from Brazil. Results: With the data of Brazilian coal of high ash content (mine Leao/ 43% ash in the mine-mouth quality, 20% ash after preparation) there have been worked out proposals for the mine planning and for a number of processes. On the basis of these proposals and under consideration of the main data specified by the Brazilian working group there have been choosen two processes and worked out in a conceptual design: 1) pressurized water reactor + LURGI-pressure gasifier/hydrogasification for the production of SNG and 2) high temperature reactor steam gasification for the production of town gas. The economic evaluation showed that the two processes are not substantially different in their cost efficiency and they are economical on a long-term basis. For more specific design work there has been planned the implementation of an experimental programme using the semi-technical plants 'hydrogasification' in Wesseling and 'steam gasification' in Essen as the conceptual phase. (orig.) [de

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

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.)

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 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

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

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

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

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

The effects of the Brazilian regulatory inspection programme on nuclear medicine facilities

Energy Technology Data Exchange (ETDEWEB)

Alves, C E G R; Azevedo, E M; Mendes, L C G; Franca, W F L; Gutterres, R F; Goncalves, M [Comissao Nacional de Energia Nuclear-CGMI/CNEN, Rua General Severiano 90, 22290-901, Rio de Janeiro (Brazil); De Sa, L V; Da Rosa, L A R [Instituto de Radioprotecao e Dosimetria-IRD/CNEN, Avenida Salvador Allende s/n, 22780-160, Rio de Janeiro (Brazil)], E-mail: telo@xexeu.org

2009-12-01

This paper aims to demonstrate the importance of the regulatory inspections carried out by the Brazilian regulatory body in the area of nuclear medicine. The main aspects observed during the inspections are presented as well as the time evolution of the non-compliances, according to their occurrence by type. We also evaluate factors concerning the working of the nuclear medicine facility responsible for solving the non-compliances. The results suggest a decrease of occurrence of non-compliances with time that can be related to the strictness of the inspections and the awareness of the personnel in the nuclear medicine facilities. An analysis of radiation dose exposure levels for the professionals involved in nuclear medicine was carried out; although dose values are below regulatory dose limits, their occurrence is not decreasing satisfactorily. Results indicate the need for staff training and commitment of the responsible nuclear medicine facility staff to the radiological protection procedures. Our results also emphasise the importance of continuous coercive actions to improve the level of radiological protection in nuclear medicine facilities in compliance with the standards established by the national regulatory authority and international recommendations.

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

Nuclear research reactors in Brazil

Energy Technology Data Exchange (ETDEWEB)

Cota, Anna Paula Leite; Mesquita, Amir Zacarias, E-mail: aplc@cdtn.b, E-mail: amir@cdtn.b [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)

2011-07-01

The rising concerns about global warming and energy security have spurred a revival of interest in nuclear energy, giving birth to a 'nuclear power renaissance' in several countries in the world. Particularly in Brazil, in the recent years, the nuclear power renaissance can be seen in the actions that comprise its nuclear program, summarily the increase of the investments in nuclear research institutes and the government target to design and build the Brazilian Multipurpose research Reactor (BMR). In the last 50 years, Brazilian research reactors have been used for training, for producing radioisotopes to meet demands in industry and nuclear medicine, for miscellaneous irradiation services and for academic research. Moreover, the research reactors are used as laboratories to develop technologies in power reactors, which are evaluated today at around 450 worldwide. In this application, those reactors become more viable in relation to power reactors by the lowest cost, by the operation at low temperatures and, furthermore, by lower demand for nuclear fuel. In Brazil, four research reactors were installed: the IEA-R1 and the MB-01 reactors, both at the Instituto de Pesquisas Energeticas Nucleares (IPEN, Sao Paulo); the Argonauta, at the Instituto de Engenharia Nuclear (IEN, Rio de Janeiro) and the IPR-R1 TRIGA reactor, at the Centro de Desenvolvimento da Tecnologia Nuclear (CDTN, Belo Horizonte). The present paper intends to enumerate the characteristics of these reactors, their utilization and current academic research. Therefore, through this paper, we intend to collaborate on the BMR project. (author)

Nuclear research reactors in Brazil

International Nuclear Information System (INIS)

Cota, Anna Paula Leite; Mesquita, Amir Zacarias

2011-01-01

The rising concerns about global warming and energy security have spurred a revival of interest in nuclear energy, giving birth to a 'nuclear power renaissance' in several countries in the world. Particularly in Brazil, in the recent years, the nuclear power renaissance can be seen in the actions that comprise its nuclear program, summarily the increase of the investments in nuclear research institutes and the government target to design and build the Brazilian Multipurpose research Reactor (BMR). In the last 50 years, Brazilian research reactors have been used for training, for producing radioisotopes to meet demands in industry and nuclear medicine, for miscellaneous irradiation services and for academic research. Moreover, the research reactors are used as laboratories to develop technologies in power reactors, which are evaluated today at around 450 worldwide. In this application, those reactors become more viable in relation to power reactors by the lowest cost, by the operation at low temperatures and, furthermore, by lower demand for nuclear fuel. In Brazil, four research reactors were installed: the IEA-R1 and the MB-01 reactors, both at the Instituto de Pesquisas Energeticas Nucleares (IPEN, Sao Paulo); the Argonauta, at the Instituto de Engenharia Nuclear (IEN, Rio de Janeiro) and the IPR-R1 TRIGA reactor, at the Centro de Desenvolvimento da Tecnologia Nuclear (CDTN, Belo Horizonte). The present paper intends to enumerate the characteristics of these reactors, their utilization and current academic research. Therefore, through this paper, we intend to collaborate on the BMR project. (author)

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

Monochromatic neutron beam production at Brazilian nuclear research reactors

Science.gov (United States)

Stasiulevicius, Roberto; Rodrigues, Claudio; Parente, Carlos B. R.; Voi, Dante L.; Rogers, John D.

2000-12-01

Monochomatic beams of neutrons are obtained form a nuclear reactor polychromatic beam by the diffraction process, suing a single crystal energy selector. In Brazil, two nuclear research reactors, the swimming pool model IEA-R1 and the Argonaut type IEN-R1 have been used to carry out measurements with this technique. Neutron spectra have been measured using crystal spectrometers installed on the main beam lines of each reactor. The performance of conventional- artificial and natural selected crystals has been verified by the multipurpose neutron diffractometers installed at IEA-R1 and simple crystal spectrometer in operator at IEN- R1. A practical figure of merit formula was introduced to evaluate the performance and relative reflectivity of the selected planes of a single crystal. The total of 16 natural crystals were selected for use in the neutron monochromator, including a total of 24 families of planes. Twelve of these natural crystal types and respective best family of planes were measured directly with the multipurpose neutron diffractometers. The neutron spectrometer installed at IEN- R1 was used to confirm test results of the better specimens. The usually conventional-artificial crystal spacing distance range is limited to 3.4 angstrom. The interplane distance range has now been increased to approximately 10 angstrom by use of naturally occurring crystals. The neutron diffraction technique with conventional and natural crystals for energy selection and filtering can be utilized to obtain monochromatic sub and thermal neutrons with energies in the range of 0.001 to 10 eV. The thermal neutron is considered a good tool or probe for general applications in various fields, such as condensed matter, chemistry, biology, industrial applications and others.

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)

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)

Assessing and improving the safety culture of non-power nuclear installations

International Nuclear Information System (INIS)

Bastin, S.J.; Cameron, R.F.; McDonald, N.R.; Adams, A.; Williamson, A.

2000-01-01

The development and application of safety culture principles has understandably focused on nuclear power plant and fuel cycle facilities and has been based on studies in Europe, North America, Japan and Korea. However, most radiation injuries and deaths have resulted from the mishandling of radioactive sources, inadvertent over-exposure to X-rays and critically incidents, unrelated to nuclear power plant. Within the Forum on Nuclear Cooperation in Asia (FNCA), Australia has been promoting initiatives to apply safety culture principles across all nuclear and radiation application activities and in a manner that is culturally appropriate for Asian countries. ANSTO initiated a Safety Culture Project in 1996 to develop methods for assessing and improving safety culture at nuclear and radiation installations other than power reactors and to trial these at ANSTO and in the Asian region. The project has sensibly drawn on experience from the nuclear power industry, particularly in Japan and Korea. There has been a positive response in the participating countries to addressing safety culture issues in non-power nuclear facilities. This paper reports on the main achievements of the project. Further goals of the project are also identified. (author)

Topics on Japanese aseismic design for nuclear installations

International Nuclear Information System (INIS)

Nakamura, Masahiko

2002-01-01

Major items of of Japanese anti-seismic design for nuclear installations involve three topics: earthquakes and ground motion; seismic design and safety evaluation. The first topic deal with: improvement of geological survey technology, evaluation of ground motion from active faults, and characterisation of earthquake from individual faults. Seismic design involves: evaluation of design ground motion (spectra), classification of structures, systems and components (SSCs) based on the seismic importance, and seismic design criteria and critical loads. Safety evaluation of seismic PSA is dependent on the consistency of the the two previous items. Seismic hazard evaluation methodology, database and examples of analysis are described. Analysis method using fault model is included

The role of nuclear energy in Brazilian energy matrix: environmental and socio-economical aspects

International Nuclear Information System (INIS)

Bones, Ubiratan A.; Schirmer, Priscila; Ceolin, Celina

2017-01-01

Due to the great increase demand for energy in the world, the continuous expansion of industrialization and the increase of consumption, together with the indispensable search for the sustainability of human acts, the need for diversification of the energy matrix and the search for less polluting energy comes increasing. Nuclear energy is increasingly seen as an option to contain greenhouse gas emissions and reduce dependence on fossil fuels. In this context, although it is not a source of renewable energy and also not the solution to all Brazilian problems, it can contribute to the expansion of the Brazilian energy matrix, being the only thermal source capable of guaranteeing the constant supply of energy without emitting greenhouse gases, considering that Brazil dominates nuclear fuel cycle technology and has large uranium reserves. However, this is a topic that generates a great deal of insecurity and questioning, making important the development of this work, both for a better understanding of the public, and to contribute and encourage future research through an evaluation of its environmental and socioeconomic aspects, discussing its risks and assessing the possibilities of expanding its use, including a panoramic view of nuclear energy in Brazil. In addition, for the full development of a country, it is necessary to diversify its energy sources, focusing on environmental and economic sustainability and reducing the vulnerability of the system

Safety aspects of geological studies around nuclear installations sites

International Nuclear Information System (INIS)

Faure, J.

1988-01-01

The experience of geological studies of about forty french nuclear sites allows to set out the objectives, the phases and the geographic extensions of workings to be realized for confirming a site. The data to be collected for the safety analysis are specified; they concern the local and regional geology, the geotechnical characteristics and the essential elements for evaluating the hazards related to the soil liquefaction, the surface fracturing and in some cases the volcanic risks. It is necessary to follow up the geology during the installation construction and life. 8 refs. (F.M.)

The directive establishing a community framework for the nuclear safety of nuclear installations: the European Union approach to nuclear safety

International Nuclear Information System (INIS)

Garribba, M.; Chirtes, A.; Nauduzaite, M.

2009-01-01

This article aims at explaining the evolution leading to the adoption of the recent Council Directive 2009/71/EURATOM establishing a Community framework for the nuclear safety of nuclear installations adopted with the consent of all 27 members states following the overwhelming support of the European Parliament, that creates for the first time, a binding legal framework that brings legal certainty to European Union citizens and reinforces the role and independence of national regulators. The paper is divided into three sections. The first section addresses the competence of the European Atomic energy Community to legislate in the area of nuclear safety. It focuses on the 2002 landmark ruling of the European Court of justice that confirmed this competence by recognizing the intrinsic link between radiation protection and nuclear safety. The second part describes the history of the Nuclear safety directive from the initial 2003 European Commission proposal to today 's text in force. The third part is dedicated to a description of the content of the Directive and its implications on the further development of nuclear safety in the European Union. (N.C.)

Limitation of fusion power plant installation on future power grids under the effect of renewable and nuclear power sources

Energy Technology Data Exchange (ETDEWEB)

Takeda, Shutaro, E-mail: takeda.shutarou.55r@st.kyoto-u.ac.jp [Graduate School of Advanced Integrated Studies in Human Survivability, Kyoto University, Kyoto, Kyoto (Japan); Sakurai, Shigeki [Graduate School of Advanced Integrated Studies in Human Survivability, Kyoto University, Kyoto, Kyoto (Japan); Yamamoto, Yasushi [Faculty of Engineering Science, Kansai University, Suita, Osaka (Japan); Kasada, Ryuta; Konishi, Satoshi [Institute of Advanced Energy, Kyoto University, Uji, Kyoto (Japan)

2016-11-01

Graphical abstract: - Highlights: • Future power grids would be unstable due to renewable and nuclear power sources. • Output interruptions of fusion plant would cause disturbances to future grids. • Simulation results suggested they would create limitations in fusion installation. • A novel diagram was presented to illustrate this suggested limitation. - Abstract: Future power grids would be unstable because of the larger share of renewable and nuclear power sources. This instability might bring some additional difficulties to fusion plant installation. Therefore, the authors carried out a quantitative feasibility study from the aspect of grid stability through simulation. Results showed that the more renewable and nuclear sources are linked to a grid, the greater disturbance the grid experiences upon a sudden output interruption of a fusion power plant, e.g. plasma disruption. The frequency deviations surpassed 0.2 Hz on some grids, suggesting potential limitations of fusion plant installation on future grids. To clearly show the suggested limitations of fusion plant installations, a novel diagram was presented.

The economic potential of a cassette-type-reactor-installed nuclear ice-breaking container ship

International Nuclear Information System (INIS)

Kondo, Koichi; Takamasa, Tomoji

1999-01-01

An improved cassette-type marine reactor MRX (Marine Reactor X) which is currently researched and developed by the Japan Atomic Energy Research Institute is designed to be easily removed and transferred to another ship. If the reactor in a nuclear-powered ship, which is the reason for its higher cost, were replaced by the cassette-type-MRX, the reusability of the MRX would reduce the cost difference between nuclear-powered and diesel ships. As an investigation of one aspect of a cassette-type MRX, we attempted in this study to do an economic review of an MRX-installed nuclear-powered ice-breaking container ship sailing via the Arctic Ocean. The transportation cost between the Far East and Europe to carry one TEU (twenty-foot-equivalent container unit) over the entire life of the ship for an MRX (which is used for a 20-year period)-installed container ship sailing via the Arctic Ocean is about 70% higher than the Suez Canal diesel ship, carrying 8,000 TEU and sailing at 25 knots, and about 10% higher than the Suez Canal diesel ship carrying 4,000 TEU and sailing at 34 knots. The cost for a cassette-type-MRX (which is used for a 40-year period, removed and transferred to a second ship after being used for 20 years in the first ship)-installed nuclear-powered container ship is about 7% lower than that for the one operated for 20 years. Considering any loss or reduction in sales opportunities through the extension of the transportation period, the nuclear-powered container ship via the Arctic Sea is a more suitable means of transportation than a diesel ship sailing at 25 knots via the Suez Canal when the value of the commodities carried exceeds 2,800 dollars per freight ton. (author)