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)

The epidemiological studies of leukemia around nuclear installations for children and young adults: synthesis of the critical review

International Nuclear Information System (INIS)

2008-01-01

An epidemiological study published at the end of 2007 described an increased risk of leukemia among children less than five years leaving at less than 5 kilometers from German nuclear power plants. The objective of this report was to make a synthesis and a critical analysis of the results relative to the risk of leukemia among the children and young adults of less than twenty five years leaving near these nuclear installations. (N.C.)

Fifty years of German nuclear legislation

International Nuclear Information System (INIS)

Heller, W.

2006-01-01

The political situation and the state of legislation after World War II make it difficult to pinpoint a precise date of origin of German nuclear legislation. The restrictions imposed by the Allied High Commission (AHC) without any exception put a ban on the production of uranium and thorium metal as well as the construction of nuclear reactors. These restrictions were lifted expressly when the German Atomic Energy Act (AtG) entered into force on January 1, 1960, i.e. much later than the formal step of gaining sovereignty, which was marked by the protocol of May 5, 1955 terminating the Occupation Statute. In October 1955, the German federal government established the then Federal Ministry for Atomic Matters also in an attempt to reconnect to developments in nuclear fission in other parts of the Western world. To supersede the AHC law, the German federal government in December 1956 publicized a draft Atomic Energy Act. It is safe, therefore, to consider that year the starting point of German atomic legislation. This step was followed by deliberations preparatory to the adoption of the Atomic Energy Act. In 1957, however, adoption failed because no two-thirds majority was reached to amend the Basic Law, i.e. the Constitution. As a consequence, some federal states saw the need to adopt state legislation to regulate this area. On December 3, 1959, a new draft Atomic Energy Act was adopted by the German federal parliament after the second and third readings - coupled with an amendment to the Basic Law on that same day - with the votes of the opposition and with one abstention. (orig.)

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

The characteristic features of the German and the U.S. American law governing the licensing of nuclear installations

International Nuclear Information System (INIS)

Heitsch, C.

1993-01-01

The author's comparative analysis of the German and the U.S. American legislation is intended to exhibit the specific structures of the two regulatory systems, and their performance regarding the intended purpose of providing the best possible protection against the risks posed by nuclear energy. It is further analysed whether instruments or structures of the U.S. American law can be adopted by the German law and applied to solving problems arising in Germany. In the selfcontained review of the German Atomic Energy Act and the nuclear licensing provisions, emphasis is placed on the development of judicial control in Germany, as the court decisions have a major impact on accepted practice in Germany. This is followed by a self-contained review of the licensing procedure in the U.S.A., with a focus on the right to be heard of the general public, and on the system of rulemaking powers by the state commissions and agencies. The author finally explains the most significant differences of the two regulatory systems and draws some conclusions as to the underlying legal policy. A concluding analysis examines the question of whether the recent judgments by the Federal Administrative Court, relating to judicial control and the binding effect of substantiating administrative regulations, are justifiable from the dogmative point of views. (orig.) [de

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

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

The German-German history of the nuclear power plant Greifswald. Nuclear power between east and west. 2. ed.

International Nuclear Information System (INIS)

Hoegselius, Per

2015-01-01

The historical study covers the chapters The nuclear power plant Greifswald; Lubmin shortly before the ''Wende'' 1989; the German ''Wende''; from the last vote for the ''Volkskammer (parliament of the German Democratic Republic) to the German reunification; Lubmin in reunified Germany; conclusions and perspectives. In the attachment technical data about the reactors WWER-440/W-230 are summarized, including a list of WWERs in the former eastern bloc countries.

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

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

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

International Nuclear Information System (INIS)

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

1992-01-01

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

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)

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)

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

The German Debate on Tactical Nuclear Weapons

International Nuclear Information System (INIS)

Meier, Olivier

2008-01-01

This report analyses the debate in Germany about tactical nuclear weapons deployments in Europe. It is mainly based on interviews conducted with senior officials from the German Federal Foreign Ministry, the Federal Ministry of Defence, senior members of Parliament as well as experts from research institutes and think-tanks. The interviews focused on the more recent past in the German debate as well as the future of tactical nuclear weapon deployments in Germany and Europe. The report concludes that while a change of Germany's position on tactical nuclear weapons is unlikely to change in the short-term, several developments will make it unlikely that the continued involvement of Germany in NATO nuclear sharing will have to be debated in the medium term. Should the next Parliamentary elections, which will take place in 2009 at the latest, result in a Social Democrat-led government, a push for a reduction of Germany's involvement in NATO nuclear sharing appears possible. A conservative-led government is likely to maintain the nuclear status quo within NATO

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 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

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

Assessment of accident risks from german nuclear plants

International Nuclear Information System (INIS)

Heuser, F.W.

1979-01-01

The German risk study are presented. The main objectives can be summed up as follows: (a) An assessment of the societal risk due to accidents in nuclear power plants with reference to German conditions; (b) To get experience in the field of risk analysis and to provide a basis for estimation of uncertainties; (c) To provide guidance for future activities in the German Reactor Safety Research Program. Finally several conclusions reached by this study are discussed. (author)

Annual report 1993 of the German Atomic Forum

International Nuclear Information System (INIS)

Petroll, M.

1994-01-01

In retrospect it is stated that in 1993 the hopes of an energy policy consensus between the political parties have not come true; the operation of existing plants continues to be politically endangered, and the future of nuclear energy continues to be unclear. Particularly depressing is the large number of nuclear installations whose fate is undecided. To save German industry from serious harm, an energy policy consensus has to be found which the German Atomic Forum seeks to bring about. An account is given of organized events and working groups, of international cooperation and cooperation with other organizations. In 1993 German nuclear power plants generated more than 153,5 thousand million kilowatt-hours, thus contributing, as the year before, more than one third (34%) to power supply. In Western Germany this percentage even amounted to almost 40%. The use of nuclear energy made it possible in 1993 to avoid release of more than 150 million tons of carbon dioxide, that is about 15% of German overall emissions. (orig./HSCH) [de

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.)

SMiRT 23. 14{sup th} international seminar on fire safety in nuclear power plants and installations

Energy Technology Data Exchange (ETDEWEB)

Roewekamp, Marina (ed.) [Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) gGmbH, Koeln (Germany); Berg, Heinz-Peter [Bundesamt fuer Strahlenschutz, Salzgitter (Germany)

2015-12-15

In the frame of the project 3614R01575 funded by the German Ministry for the Environment, Nature Conservation, Building and Nuclear Safety (Bundesministerium fuer Umwelt, Naturschutz, Bau und Reaktorsicherheit, BMUB) the meanwhile fourteenth international seminar on ''Fire Safety in Nuclear Power Plants and Installations'' has been conducted as P ost-Conference Seminar of the 23{sup rd} International Conference on Structural Mechanics In Reactor Technology (SMiRT 23) in Salford, United Kingdom in August 2015. The following seminar proceedings contain the entire twenty-one technical contributions to the two day s seminar with in total fifty-five participants from ten countries in Asia, Europe and America.

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

Anticipatory opt-out of nuclear power at German universities and research centers? Employment and education opportunities in the nuclear field

International Nuclear Information System (INIS)

Fritz, P.; Closs, K.D.; Kuczera, B.; Erlenwein, P.; Langetepe, G.; Weiss, F.P.; Wolfert, K.

2001-01-01

The energy policy objectives of the present German federal government include the regulated, not-to-be-indemnified termination of the use of nuclear power for electricity generation in Germany. This objective was initialed in an agreement between the federal government and the operators of nuclear power plants in June 2000. The criterion it contains for the residual life of existing nuclear power plants are the 'residual electricity volumes' to be generated by existing plants. According to present data, the first nuclear power plant would be decommissioned in late 2002, the last one, in early 2021. A report by an evaluating committee established by the competent German Federal Ministry of Economics and Technology published in January 2000 indicates that, even in the light of this medium-term perspective for the use of nuclear power for electricity generation, sufficient competence in terms of manpower in this field must be maintained and promoted in all areas of research, industry, expert consultant organizations, and regulatory authorities far beyond 2021. This makes government support indispensable in the light of the political criteria requiring the preservation of competence in this sector. The 'Kompetenzverbund Kerntechnik' (Association for Nuclear Technology Competence) was established within the framework of the Energy Research Division of the Hermann von Helmholtz-Gemeinschaft Deutscher Forschungszentren. Its mandate outlines its objectives as follows: 'Irrespective of political decisions establishing criteria for terminating the use of nuclear power in Germany, it is necessary that competence in nuclear safety be preserved for the next few decades. Only this will ensure that the government's provident duties can be fulfilled, and the safety of nuclear installations and waste and spent fuel management pathways can be ensured in accordance with the international state of the art'. (orig.) [de

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

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

Standard rules for liability and cover for nuclear installations

International Nuclear Information System (INIS)

Pfaffelhuber, J.K.; Kuckuck, B.

1980-01-01

To afford full protection for possible victims, the authors of this article are in favour of doing away with the limitation of liability of nuclear operators presently provided under the German Atomic Energy Act, the principle of which is based on the Paris Convention and the Brussels Supplementary Convention. In support of this argument reference is made to the recent accident at Three Mile Island, trends in other national legislation towards unlimited liability as well as high safety standards in German nuclear plants. Finally, possible ways of providing unlimited liability are proposed, in particular increased insurance cover and the constitution of an interest-bearing fund in addition to State intervention in case of a major nuclear incident. (NEA) [fr

Childhood leukaemia around nuclear facilities

International Nuclear Information System (INIS)

Wojcik, Andrzej; Feychting, Maria

2010-06-01

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

Childhood leukaemia around nuclear facilities

Energy Technology Data Exchange (ETDEWEB)

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

2010-06-15

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

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)

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.)

Nuclear energy and German foreign policy

International Nuclear Information System (INIS)

Kaiser, K.

1979-01-01

The author shows that the present foreign-policy situation with regard to the nuclear-energy complex is due to political and energy-policy origins. He is further of the opinion that the expansion of nuclear energy - in spite of internal political difficulties - will continue in the long term. Hence breeders and reconditioning will become realities. For German foreign policy this means that it must also carry responsibilities on a global scale in this respect. (orig.) [de

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.

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

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)

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

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)

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

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

German nuclear policy reconsidered. Implications for the electricity market

International Nuclear Information System (INIS)

Fuersch, Michaela; Lindenberger, Dietmar; Malischek, Raimund; Nagl, Stephan; Panke, Timo; Trueby, Johannes

2011-01-01

In the aftermath of the nuclear catastrophe in Fukushima, German nuclear policy has been reconsidered. This paper demonstrates the economic effects of an accelerated nuclear phase-out on the German electricity generation sector. A detailed optimization model for European electricity markets is used to analyze two scenarios with different lifetimes for nuclear plants (phase-out vs. prolongation). Based on political targets, both scenarios assume significant electricity demand reductions and a high share of generation from renewable energy sources in Germany. Our principal findings are: First, nuclear capacities are mainly replaced by longer lifetimes of existing coal-fired plants and the construction of new gas-fired plants. Second, fossil fuel-based generation and power imports increase, while power exports are reduced in response to the lower nuclear generation. Third, despite the increased fossil generation, challenging climate protection goals can still be achieved within the framework of the considered scenarios. Finally, system costs and electricity prices are clearly higher. We conclude that the generation sector can generally cope with an accelerated nuclear phase-out under the given assumptions. Yet, we emphasize that such a policy requires a substantial and costly transformation of the supply and the demand side.

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

The German risk study for nuclear power plants

International Nuclear Information System (INIS)

Birkhofer, A.

1980-01-01

In August 1979 results of the ''German Risk Study for Nuclear Power Plants'' were published. The Main Report, in which approach and results of the study are documented, has been available since the end of 1979. It was the charter of the study - which was performed on behalf of the Minister of Research and Technology of the Federal Republic of Germany - to apply as far as possible the methods of the US Reactor Safety Study (WASH-1400) to German plant and site conditions. A direct transfer of the results was not deemed justified, mainly for the following reasons: There is quite a number of differences between the design of the reference plants of WASH-1400 (Surry-1, Peach Bottom-2) and German nuclear power plants. The mean population density in the Federal Republic of Germany is more than ten times of the United States. In the vicinity of nuclear power plants the ratio is about 3:1. To calculate the collective risk resulting from reactor accidents, a total of 25 plants at 19 different sites in the Federal Republic of Germany were considered. This included all plants with 600 MW or more electrical output, which were in operation, under construction or in licensing process by July 1, 1977. As an approximation to the real situation, it has been assumed that all 25 plants are technically identical to the reference plant

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.)

The availability of German nuclear power plants in an international comparison

International Nuclear Information System (INIS)

Fehndrich, W.; Kutsch, W.

1975-01-01

The availability of German nuclear power stations is discussed in comparison with European and American light-water nuclear power stations. Furthermore, the availability or utilization is shown as a function of the year of operation and of the unit size (the latter only for the USA), and the trends observed during the last 4 years are made evident. The unscheduled shutdowns of light-water nuclear power stations during the past 4 years are analysed on the basis of publications of the IAEA in Vienna and the ABE-Committees of the German Atomforum with special emphasis on the affected systems. (orig.) [de

Development of a quality management system for Brazilian nuclear installations

International Nuclear Information System (INIS)

Kibrit, Eduardo; Zouain, Desiree Moraes

2005-01-01

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

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.

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)

Hitler's bomb: the secret story of Germans' attempts to get the nuclear weapon

International Nuclear Information System (INIS)

Karlsch, Rainer

2007-01-01

In this historical book, the author claims to have evidence concerning the development and testing of a possible 'nuclear weapon' by Nazi Germany in 1945. The 'weapon' in question is not alleged to be a standard nuclear weapon powered by nuclear fission, but something closer to either a radiological weapon (a so-called 'dirty bomb') or a hybrid-nuclear fusion weapon. Its new evidence is concerned primarily with the parts of the German nuclear energy project (an attempted clandestine scientific effort led by Germany to develop and produce atomic weapons during World War II) under Kurt Diebner, a German nuclear physicist who directed and administrated the project

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)

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.)

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)

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)

The German competence network on nuclear technology

International Nuclear Information System (INIS)

Kuczera, B.; Fritz, P.

2004-01-01

Full text: The present German energy policy is based on the phase-out of nuclear electricity generation, which means that the last of the currently operating eighteen German nuclear power plants will run until about 2022. While the plants will be shut down one after the other, decommissioning will start together with interim storage of the radioactive waste. The safe waste disposal in a final repository is planned to start around 2030 and may take another two decades, i.e., in Germany nuclear competence is further needed, at least until the mid of this century. Against this background, a high-ranking commission under the direction of the Federal Ministry of Economy and Technology evaluated the publicly funded nuclear safety related research and development (R and D) activities in Germany. One of the recommendations made by the commission was the foundation of a Competence Network on Nuclear Technology for an optimum coordination of the remaining nuclear activities including aspects of future human resources in this area. This Network was established in March 2000 with the following member institutions: Research Centre Juelich, Research Centre Karlsruhe, Research Centre Rossendorf and the Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) in Munich and their neighbouring Technical Universities. The strategic objectives of the Competence Network include: Trend investigations on job development and on university education capacities in the nuclear technology sector; Enhanced cooperation of the Research Centres with universities in the nuclear field and support of international education initiatives (e.g. ENEN, WNU); Coordination and bundling of the activities in publicly funded reactor safety and waste management R and D programmes; Support of qualified young scientists and engineers (pre-doctoral students) - also by third-party funds; Participation in and collaboration with international projects and activities for advancements of international nuclear safety

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

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.)

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

Great nuclear debate: German--American disagreements

International Nuclear Information System (INIS)

Kaiser, K.

1978-01-01

The post-war international consensus on nuclear nonproliferation has been eroding because of the debate over actions taken by some countries and because of the U.S. response with a unilateral change in nuclear policy. The chronology of developments is traced, noting that the 1973--74 oil crisis, India's nuclear explosion in 1974, and the exchange of Brazilian uranium for German technology all had a major role in the policy controversy. New nonproliferation proposals by the Carter administration, by precipitating debate between those wanting tighter export controls and those with nuclear commercial interests, also introduced several foreign-relations problems because of the emphasis on international agreements and a technological approach. The U.S. is credited with taking a constructive step to correct the inadequacies of the present policies and exerting pressure for global involvement in reassessing the rules on armaments and proliferation. Significant U.S. leadership could also take the form of lower energy consumption

Electricity: the German example

International Nuclear Information System (INIS)

Huet, Sylvestre

2013-01-01

The author proposes some comments on the content of the Energiewende, i.e. the definition of the energy transition in Germany which aims at producing and consuming a green energy, without carbon nor nuclear. He comments the German energy mix for 2010 in terms of electricity production per origin (nuclear, coal and lignite, gas, oil, wind, solar photovoltaic, other renewable sources) and of installed capacities per origin. He notices that gas and coal still have a major weight in this mix, and discusses the content of a scenario based 100 per cent renewable energies as it has been studied by the Fraunhofer Institute, notably in terms of production level and of costs

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

R&D Activities in German Nuclear Sector

International Nuclear Information System (INIS)

Schwenk-Ferrero, A.

2015-01-01

Germany is phasing out its nuclear energy use. The seven oldest Light Water Reactors (taken offline in 2011 for a safety review immediately following the Fukushima accident) and the Kruemmel Nuclear Power Plant (NPP) are already shut down; six others would go offline by 2021 at the latest and the three newest by 2022. Phasing out nuclear power must not be regarded as synonymous with “phasing out” nuclear expertise. Long after Germany has completed its NPP shutdown, such skills will remain essential for activities such as ensuring reactor safety, radiation protection, decommissioning, ultimate disposal of radioactive waste and crisis management, and for maintaining a critical outlook on international developments. The German Government underlined this fact when launching the 6th Energy Research Programme entitled “Research for an Environmentally Sound, Reliable and Affordable Energy Supply” in August 2011. The dispute on questions of nuclear waste management and disposal in Germany is not only framed by the political parties’ different perspectives and conflicts between the antinuclear movement and official politics, but is also characterised by the dissent among experts regarding fundamental questions of nuclear waste storage. Especially for high-level radioactive waste there are still debates about the possible repository type and site. In 2014 the study on “Partitioning and Transmutation of Nuclear Waste: benefits and Challenges in Research and Implementation” has been performed under the supervision of National Academy of Science and Engineering–acatech. Acatech recommended continuing the R&D activities on P&T in Germany within a wide European framework and examining the options for future participation of Germany in P&T oriented research in Europe in order to follow a European perspective with a possible benefit to German nuclear industry. German research should concentrate on the key areas: efficient partitioning and transmutation of

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.)

Assessment of safety of the nuclear installations of the world

International Nuclear Information System (INIS)

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

1992-01-01

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

Computer systems for nuclear installation data control

International Nuclear Information System (INIS)

1987-09-01

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

The trend and precept of present nuclear energy policy in German

International Nuclear Information System (INIS)

Murakami, Takashi

2000-01-01

In German, the coalition political power of SPD and Gruene decided the present nuclear policy on 20th October 1998. It consisted of three steps: the first step is amendment of the present Atomic Energy Law, the second step the consensus conference with the power industry for one year and the third step is enactment of law to decrease nuclear power with compensation. The first consensus conference opened 26th January 1999. The content was that the stop of reprocessing did not decide the limit and the atomic power plants were operated until obtaining consensus. Then, Muller Secretary of Commerce and the power industry carried out unofficial meeting and decided the following: limit of operating atomic power plants is 35 years (until 2024), reprocessing can be done until 2004 and the undertakers do not request compensation to the governmental agencies. However the environmental secretary and Gruene objected to them. 570 of German scientists and technologists published memorandum for discussing the present conditions of German and the earth. England and France opposite limit of reprocessing spent fuel. A joint concern between Siemens (German) and Framatome (France) is going to establish. The point under discussion about present power policy is selection of energy. There are many problems in German. (S.Y.)

Pressurized thermal shock analysis in German nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Fricke, Stefan; Braun, Michael [TUEV NORD Nuclear, Hannover (Germany)

2015-03-15

For more than 30 years TUeV NORD is a competent consultant in nuclear safety is-sues giving expert third party opinion to our clients. According to the German regulations the safety against brittle fracture has to be proved for the reactor pressure vessel (RPV) and with a new level of knowledge the proof has to be continuously updated with the development in international codes and standards like ASME, BS and RCC-M. The load of the RPV is a very complex transient pressure and temperature situation. Today these loading conditions can be modeled by thermal hydraulic calculations and new experimental results much more detailed than in the construction phase of German Nuclear Power Plants in the 1980s. Therefore, the proof against brittle fracture from the construction phase had to be updated for all German Nuclear Power Plants with the new findings of the loading conditions especially for a postulated small leakage in the main coolant line. The RPV consists of ferritic base material (about 250 mm) and austenitic cladding (about 6 mm) at the inner side. The base material and the cladding have different physical properties which have to be considered temperature dependently in the cal-culations. Radiation-embrittlement effects on the material are to be respected in the fracture mechanics assessment. The regions of the RPV of special interest are the core weld, the inlet and outlet nozzle region and the flange connecting weld zone. The fracture mechanics assessment is performed for normal and abnormal operating conditions and for accidents like LOCA (Loss of Coolant Accident). In this paper the German approach to fracture mechanics assessment to brittle fracture will be discussed from the point of view of a third party organization.

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

Radiation exposure in German nuclear power plants

International Nuclear Information System (INIS)

Mueller, W.

1981-01-01

The individual and collective doses in German nuclear power stations have decreased remarkably since the beginning of the commercial nuclear power production. The paper discusses the influencing factors, that have caused this development and points out areas where improvements are possible in the future. Moreover the interaction between radiation protection practice and the relevant legal regulations is considered. Usually the recording of job related doses is regarded as the most direct access to possible improvements. Concluding, it is therefore demonstrated by some examples how the evaluation of such information has taken effect in practice. (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

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

The Brussels Nuclear Ship Convention and its impact on the German Atomic Energy Act

International Nuclear Information System (INIS)

Bernaerts, A.

1976-01-01

Although the Brussels Nuclear Ship Liability Convention of 1962, whose incorporation into German law was agreed upon by the German Federal Parliament (the Bundestag) in 1975, will have only minor international significance once it has entered into force, it will yet provide a new legal basis for the nuclear liability of the German vessel N.S. 'Otto Hahn' for the periods of her stay within the Federal Republic of Germany. However, there is no smooth concurrence of the Brussels Convention and the German Atomic Energy Act adapted to the Paris Liability Convention in 1975. This means that a number of questions still need to be resolved with respect to the protection of victims and the liability of shipowners. (orig.) [de

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

Safeguards Strategy in Physical Protection System for Nuclear Installation

International Nuclear Information System (INIS)

Ade lndra B; Kasturi; Tatang Eryadi

2004-01-01

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

Regulatory oversight report 2008 concerning nuclear safety in Swiss nuclear installations

International Nuclear Information System (INIS)

2009-04-01

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

Life extension for German nuclear power plants

International Nuclear Information System (INIS)

Heller, W.

2005-01-01

The Federation of German Industries (BDI) commissioned a study of the ''Economic Effects of Alternative Lifetimes of Nuclear Power Plants in Germany.'' The expert organizations invited as authors were the Power Economy Institute of the University of Cologne (EWI) and Energy Environment Forecast Analysis GmbH (EEFA), Berlin. The reasons for commissioning the Study include the changed framework conditions (deregulation, CO 2 emission certificate trading, worldwide competition for resources), which have altered the energy supply situation in Europe. The findings of the Study were presented to the public by the BDI on October 26, 2005. The study deals with two scenarios of extended lifetimes for German nuclear power plants of 40 and 60 years as against the existing regulations with plant lifetimes limited to approx. 32 years. The longer service lives of plants are reflected in reduced electricity generation costs and thus may have a positive influence on electricity prices. Moreover, there would be additional growth of production together with additional jobs, all of which would add up to nearly 42,000 persons for all sectors of the economy as compared to the basic scenario. Also, CO 2 emissions could be curbed by up to 50 million tons of carbon dioxide. The Study offers ample and valid reasons in favor of extending the lifetimes of nuclear power plants. In the interest of general welfare, politics would be well advised to relax the restrictions on plant life in the course of this legislative term. (orig.)

German risk study 'nuclear power plants, phase B'

International Nuclear Information System (INIS)

Heuser, F.W.

1989-01-01

The results of the German risk study 'Nuclear power plants, phase B' indicate that an accident in a nuclear power plant which cannot be managed by the safety systems according to design, is extremely improbable: Its probability is at about 3 to 100,000 per year and plant. Even if the safety systems fail, emergency measures can be effected in a nuclear power plant to prevent an accident. These in-plant emergency measures diminish the probability of a core meltdown to about 4 to 1,000,000 per year and plant. Hence, the accident risk is greatly reduced. The information given by the author are to smooth the emotional edge in the discussion about the safety of nuclear power plants. (orig.) [de

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

Franco-German nuclear cooperation

International Nuclear Information System (INIS)

Leny, J.C.; Huettl, A.

1996-01-01

Nuclear energy is the number one power source in the European Union. However, the first generation units would be replaced from the year 2010 onwards. In this prospect, Siemens and Framatome have drawn together in designing and commercializing a common product initially destined for the export market which has become the EPR (European Pressurized water Reactor) project. The two companies have floated with equal participation the NPI (Nuclear Power International) sub-company to manage this project. The French and German utilities participate to the financing of the project, at present at the basic stage, and the safety authorities of both countries have carried out a joint evaluation of EPR safety. With a 1500 Mwe capacity, EPR will be equipped with advanced safety systems more performing than the existing systems. Conceivers want to maintain the economic competitiveness of EPR with respect to coal power plants. EPR will take over the oldest power plants by producing a safer and cheaper energy to provide for the needs of the developed countries and then of the developing countries with no risk for the environment. An enormous effort of communication must be carried out to reduce the public anxiety and to calm down the nuclear debate and show up its merits, in particular in Europe, where its contribution is vital. (J.S.)

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.

German Spent Nuclear Fuel Legacy: Characteristics and High-Level Waste Management Issues

Directory of Open Access Journals (Sweden)

A. Schwenk-Ferrero

2013-01-01

Full Text Available Germany is phasing-out the utilization of nuclear energy until 2022. Currently, nine light water reactors of originally nineteen are still connected to the grid. All power plants generate high-level nuclear waste like spent uranium or mixed uranium-plutonium dioxide fuel which has to be properly managed. Moreover, vitrified high-level waste containing minor actinides, fission products, and traces of plutonium reprocessing loses produced by reprocessing facilities has to be disposed of. In the paper, the assessments of German spent fuel legacy (heavy metal content and the nuclide composition of this inventory have been done. The methodology used applies advanced nuclear fuel cycle simulation techniques in order to reproduce the operation of the German nuclear power plants from 1969 till 2022. NFCSim code developed by LANL was adopted for this purpose. It was estimated that ~10,300 tonnes of unreprocessed nuclear spent fuel will be generated until the shut-down of the ultimate German reactor. This inventory will contain ~131 tonnes of plutonium, ~21 tonnes of minor actinides, and 440 tonnes of fission products. Apart from this, ca.215 tonnes of vitrified HLW will be present. As fission products and transuranium elements remain radioactive from 104 to 106 years, the characteristics of spent fuel legacy over this period are estimated, and their impacts on decay storage and final repository are discussed.

Nuclear power in the energy economics of the German Democratic Republic

International Nuclear Information System (INIS)

Hildebrand, H.J.

1977-01-01

The present structure of the energy economy in the German Democratic Republic (East Germany) is described and the need of nuclear power stations for the future supply of energy is demonstrated. The selection of the type of nuclear reactor, the existing operating experience with nuclear equipment and the collaboration in this field with the U.S.S.R. is described. The training of personnel in nuclear techniques is noted. (H.E.G.)

Safety evaluation of the nuclear power plant at Cattenom

International Nuclear Information System (INIS)

Anon.

1987-01-01

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

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

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-05-01

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

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

International Nuclear Information System (INIS)

1997-05-01

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

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

International Nuclear Information System (INIS)

Verrhiest-Leblanc, G.; Chevallier, A.

2010-01-01

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

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

Energy Technology Data Exchange (ETDEWEB)

Anon

1999-10-01

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

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

International Nuclear Information System (INIS)

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

The German-German history of the nuclear power plant Greifswald. Nuclear power between east and west. 2. ed.; Die deutsch-deutsche Geschichte des Kernkraftwerkes Greifswald. Atomenergie zwischen Ost und West

Energy Technology Data Exchange (ETDEWEB)

Hoegselius, Per [Technische Hochschule Stockholm (Sweden). Bereich Gesellschaft, Wissenschaft und Technik

2015-07-01

The historical study covers the chapters The nuclear power plant Greifswald; Lubmin shortly before the ''Wende'' 1989; the German ''Wende''; from the last vote for the ''Volkskammer (parliament of the German Democratic Republic) to the German reunification; Lubmin in reunified Germany; conclusions and perspectives. In the attachment technical data about the reactors WWER-440/W-230 are summarized, including a list of WWERs in the former eastern bloc countries.

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)

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

West German nuclear politics: a study of international cooperative behavior

International Nuclear Information System (INIS)

Driscoll, R.F.

1983-01-01

This dissertation is an investigation of the motivations behind West German policies and behavior in the area of nuclear politics. It examines and attempts to explain this behavior using a taxonomy built around the factors of vulnerability, power, domestic support, and autonomy. These are called international cooperative behavior factors. Chapters I and II develop the taxonomy and define the factors in terms of the Federal Republic. Chapter III covers the period up through the functioning of the Nuclear Planning Group, while Chapter IV analyzes NATO's December 1979 modernization decision. The presentation is less chronological and more selective: it focuses on the four international cooperative behavior factors as explanatory concepts. Chapter V examines the utility of the taxonomy. It concludes that the factors of autonomy, domestic support and vulnerability appear to be key in understanding and predicting West German nuclear behavior. The chapter then studies the potential applicability of the taxonomy to other nations or issues. It concludes that the factors are very nation-specific, but they do in fact provide a useful classification and explanatory scheme

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.)

Fundamentals, constitution and tasks of the German authorities for quality assurance in nuclear medicine

International Nuclear Information System (INIS)

Rink, T.

2005-01-01

Among other novelties, the national realization of the European Council Directive 97/43 Euratom demanded the formation of competent authorities for quality assurance in nuclear medicine that have become operative in the meantime. Their tasks are laid down in the revised versions of the German ''Strahlenschutzverordnung'' and ''Richtlinie Strahlenschutz in der Medizin''. They perform periodical investigations in all nuclear medicine installations to verify compliance with legal provisions on radiological protection, functioning as independent mediators between practitioners and persons legally responsible for the medical facilities on the one hand, and the supervisory board of the national administration on the other hand. They assist physicians and managers with fulfillment of the legal requirements and give advise for optimizing medical radiological procedures. The government has to be notified about the summarized results of the regular examinations at least once a year. However, severe infringements, consistent excess of the diagnostic reference levels or refusal to contribute the demanded documents by a facility undergoing an inspection, have to be reported immediately. This section describes the legal fundamentals, the constitution and the tasks of the inspecting authorities in Germany with accentuation on the course of the investigations. (orig.)

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

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.)

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)

Further studies on melting of radioactive metallic wastes from the dismantling of nuclear installations

International Nuclear Information System (INIS)

Diepenau, H.; Seidler, M.

1991-01-01

Melting of radioactive waste metal from the dismantling/refurbishing of nuclear installations is an acceptable way for nuclear waste recycling. This material can be used for the casting of qualified products such as type A- and type B-waste containers. The results of the melting facility -TAURUS- were used to build the industrial scale melting facility -CARLA- at Siempelkamp. The test results and the longterm-behaviour of the facility showed that the licensing conditions can be respected. The radiation exposure of workers was in the range of the admissible limit for non-exposed people. The radiation exposure of the environment is far below the value of the German Radiation Protection Law. The activity distribution within the product is homogeneous, so that its activity can be measured exactly before it is sent back in the nuclear area. By melting waste copper it is possible to respect the specific limits for unrestricted reuse, whereas for brass the limit for conditioned reuse in the industrial field was reached. Radioactive carbon can only be bound in form of small graphite lamellas or nodules in the cast iron; i.e. radioactive carbon can only be added to the melt as crushed material. During the research programme 2000 Mg of waste steel was melted at industrial scale and mainly products such as shielding blocks and waste containers were produced. 12 figs., 27 tabs., 6 refs

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)

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)

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

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)

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

International Nuclear Information System (INIS)

Gutschmidt, W.D.

1975-11-01

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

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)

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)

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

Five years of partnership programme between German and East European nuclear power plant operators

International Nuclear Information System (INIS)

Kraemer, P.

1995-01-01

In a jointly adopted communique in August 1992 the regulations governing the partnerships were laid down. The following principles are given priority: bilateral exchange of operating experience on the basis of equal partnership; the knowledge gained from the exchange of experience is used to improve the operation and safety of the respective partner plant; the partnership programme is free from commercial interests and does not include transfer of funds. Since the establishment of the first partnership relations (Biblis) with an east european nuclear power plant (Balakowo) late in April 1990, a total of 126 reciprocal visits was paid, 82 of which to German nuclear power plants. The balance of the efforts made by German nuclear power plant operators to integrate east european nuclear plant operators can be considered positive. (orig./HP) [de

Ageing management in German nuclear power plants

International Nuclear Information System (INIS)

Becker, D.E.; Reiner, M.

1998-01-01

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

The opening of the debates on the extension of German nuclear plant lifetime

International Nuclear Information System (INIS)

Guidez, J.

2010-01-01

After having recalled that the German nuclear plants were to be progressively stopped by 2021, the author reports that the political coalition has thrown this Agenda back into question, because the development of alternative energies is insufficient to compensate the programmed closing down, and the German government wants to avoid the use of thermal plants which are generating CO 2 emissions. Negotiations are underway between the German government and the four electric companies in charge of different plants. It appears that even plants which were to be stopped in 2010, could keep on operating. The report contains tables indicating, for each nuclear plant, its type, its operator, its power, its dates of beginning and programmed end of commercial activity, its production variation in time. Some comments are given about already stopped reactors (Brunsbuttel and Krummel) which faced some problems in the past, and about waste storing sites (Asse, Gorleben, Morsleben, Konrad)

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

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

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

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)

International nuclear safety experts complete IAEA peer review of German regulatory system

International Nuclear Information System (INIS)

2008-01-01

Full text: An international expert team has today completed a two-week IAEA review of Germany's nuclear regulatory system. The team identified good practices within the system and gave advice on some areas for further improvement. The IAEA has conveyed the initial findings to German authorities but the final report will be submitted within two months. At the request of the Government of the Federal Republic of Germany, the International Atomic Energy Agency (IAEA) assembled a team of 14 experts to conduct an Integrated Regulatory Review Service (IRRS) mission. This is a peer review based on IAEA Standards. It is not an inspection, nor an audit. The scope of the mission was limited to the safety regulation of nuclear power plants. Experts from Canada, the Czech Republic, Finland, France, Japan, the Netherlands, Republic of Korea, Spain, Switzerland, the UK, the US and from the IAEA took part in the mission, which was conducted from 7 to 19 September in Bonn, Stuttgart and Berlin. The main basis for the review was a well-prepared self-assessment made by the Federal Ministry of Environment, Nature Conservation and Nuclear Safety (BMU) and the Ministry of Environment of the federal state of Baden-Wuerttemberg (UM BW). 'The team members were impressed by the extensive preparation and dedication of the staff both at BMU and UM BW to excellence in nuclear safety,' said Mike Weightman, IRRS Team Leader and Chief Inspector of the UK nuclear regulatory body, the Nuclear Directorate of the Health and Safety Executive. 'We hope the IRRS mission will facilitate further improvements in the safety regulation of nuclear power in Germany and throughout the world.' 'Germany's invitation to undergo such a detailed review is a clear demonstration of its openness and commitment to continuously improve nuclear safety regulation,' said Philippe Jamet, Director of the IAEA's Nuclear Installation Safety Division. Among the particular strengths of BMU and UM BW associated with their

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 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

Nuclear Experts Complete IAEA Follow-up Review of German Regulatory System

International Nuclear Information System (INIS)

2011-01-01

Full text: Nuclear safety experts concluded a seven-day mission to review the German Regulatory System, conducted from 4-10 September in Bonn, Stuttgart and Berlin. At the request of the Government of the Federal Republic of Germany, the International Atomic Energy Agency assembled a peer-review team of six high-level regulatory experts from six nations (Finland, France, the Netherlands, Switzerland, the UK, the US and three IAEA senior staff members) to conduct a follow-up assessment of an Integrated Regulatory Review Service (IRRS) mission conducted in 2008. This follow-up IRRS mission examined the progress in acting upon the recommendations and suggestions made during the 2008 IRRS mission and reviewed the areas of significant regulatory changes since that review at both the Federal Ministry of Environment, Nature Conservation and Nuclear Safety (BMU) and the Ministry of Environment of the federal state of Baden-Wurttemberg (UM BW). The first mission reviewed Germany's regulatory framework against IAEA Safety Standards and fostered the exchange of information and experience on safety regulation. This is a peer review based on IAEA Standards. It is not an inspection, nor an audit. The scope of the mission was limited to the safety regulation of nuclear power plants. IRRS team leader, Mr. McCree, of the US Nuclear Safety Commission (USNRC), said, ''This was an important IRRS mission, particularly given the recent Fukushima Daiichi Nuclear Power Plant accident and the related insights which underscore the importance of having an independent, credible nuclear safety regulator.'' ''The IRRS team identified several strengths of the German nuclear safety regulators, including the prompt and coordinated incident response activities of BMU and UM BW to the Fukushima accident. Some suggestions were also made to further strengthen nuclear safety regulations concerning the future work of BMU,'' he said. The review team found that important progress has been made toward

Availability Improvement of German Nuclear Power Plants

International Nuclear Information System (INIS)

Wilhelm, Oliver

2008-01-01

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

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)

Effects of European energy policy on German nuclear phase-out policy

International Nuclear Information System (INIS)

Buedenbender, Martin

2009-01-01

After the election of the new German government on September 27th, 2009, the nuclear power phase-out decision appears back on top of the political agenda. Hence, an up to date survey of all relevant arguments seems absolutely necessary. In that matter, the scope should not remain national but should also take the European dimension into account. On the European level, a position in favour of nuclear power becomes apparent. Recent political decisions among the 27 member states show a renaissance of atomic energy. EU-Parliament, EU-Commission and EU-Council have all voted for the extensive, long term use of nuclear power in Europe. With its phase-out decision still valid, Germany is part of a minority in Europe. Germany is part of a European market for electricity whose national barriers will blur more and more in the future to form a fully integrated pan-European market in the end. Since nuclear power will provide a major share of the European electricity generation mix, Germany will always be supplied with atomic energy in the long term. This is imperative, regardless of nuclear power plants operating within the borders of Germany or not. Shutting down these facilities in Germany will hence not make the risks associated with atomic energy disappear. It will only add energy-technical challenges to assure long-term supply security. Thus, the new German government should withdraw the phase-out decision. (orig.)

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

German writers and the Intermediate-range Nuclear Forces debate in the 1980s

International Nuclear Information System (INIS)

Stokes, A.M.

1991-01-01

In 1979, NATO announced its decision to deploy American intermediate-range nuclear missiles throughout Western Europe. From then until 1987, when the historic Intermediate-range Nuclear forces (INF) treaty provided for the withdrawal of these weapons as well as those deployed by the Soviets in Eastern Europe, the issue of nuclear weapons preoccupied many Europeans, particularly Germans. Beginning in 1980, fear of nuclear war, with the two Germanies as a potential battlefield, mobilized the largest peace movement that the Federal Republic had witnessed since the fifties, occasioned a massive increase in peace propaganda in East Germany, and brought to public notice that country's first unofficial peace movement. Throughout most of the eighties, writers in both German states opposed missile deployment. This study examines their aims and achievements in this effort and investigates the implications of political engagement for the aesthetic production of selected authors. Analysis of press reports, writers' speeches, interviews, essays and literary texts yielded the following results: INF deployment motivated writers of all political persuasions to take up a variety of peace-oriented pursuits

Legal bases for the installation of nuclear power plants

International Nuclear Information System (INIS)

Faria, N.M. de

1980-06-01

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

Operating experiences with passive systems and components in German nuclear power plants

International Nuclear Information System (INIS)

Maqua, M.

1996-01-01

Operating experience with passive systems and components is limited to the equipment installed in existing NPPs. In German power plants, this experience is available for equipment of the IAEA categories A, C and D. The presentation is focused on typical examples out of these three categories. An overview is given on the number of reported events and typical failure modes. Selected failures are discussed in detail. 1 ref., 6 figs, 7 tabs

Operating experiences with passive systems and components in German nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Maqua, M [Gesellschaft fuer Anlagen- und Reaktorsicherheit mbH (GRS), Koeln (Germany)

1996-12-01

Operating experience with passive systems and components is limited to the equipment installed in existing NPPs. In German power plants, this experience is available for equipment of the IAEA categories A, C and D. The presentation is focused on typical examples out of these three categories. An overview is given on the number of reported events and typical failure modes. Selected failures are discussed in detail. 1 ref., 6 figs, 7 tabs.

Development of international law concerning nuclear liability

International Nuclear Information System (INIS)

Ifflaender, G.; Kantner, G.

1979-01-01

A short overview is given of the most important international conventions relating to civil liability for damage to, or loss of, life of persons or property, caused by nuclear incidents during the operation of stationary and non-stationary nuclear installations or transport of nuclear material. In accord with the international provisions, in the German Democratic Republic too, nuclear operators are exclusively liable for such damage unless it has been caused intentionally by the injury party. (author)

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)

German offsite accident consequence model for nuclear facilities: further development and application

International Nuclear Information System (INIS)

Bayer, A.

1985-01-01

The German Offsite Accident Consequence Model - first applied in the German Risk Study for nuclear power plants with light water reactors - has been further developed with the improvement of several important submodels in the areas of atmospheric dispersion, shielding effects of houses, and the foodchains. To aid interpretation, the presentation of results has been extended with special emphasis on the presentation of the loss of life expectancy. The accident consequence model has been further developed for application to risk assessments for other nuclear facilities, e.g., the liquid metal fast breeder reactor (SNR-300) and the high temperature gas cooled reactor. Moreover the model have been further developed in the area of optimal countermeasure strategies (sheltering, evacuation, etc.) in the case of the Central European conditions. Preliminary considerations has been performed in connection with safety goals on the basis of doses

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 Nuclear Safety Convention - does it confirm existing German law, and update international law?

International Nuclear Information System (INIS)

Lindemann, C.

1995-01-01

Some selected examples are discussed that are intended to answer the question of whether the NSC in its essence represents a development in confirmation of existing German nuclear law, and whether, assuming its coming into effect, this Convention will mean a step forward in the development of international law. The author examines the value of this codification of international law as such, and some of the obligations and standards such as retrofitting measures or shutdown of reactors below safety standard, and continues with briefly discussing the relationship between the NSC and nuclear liability law, the planned provisions for radiological protection in Art. 15, and the obligations for transboundary notification of safety-relevant events. These stipulations are analysed in comparison to existing international law, and with a view to their implementation under German law. Some provisions of the NSC that are based on standards of international technical guidance are compared with German regulatory guides. (orig./HP) [de

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

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

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

International Nuclear Information System (INIS)

Salvatore, J.E.L.

1989-01-01

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

Proposal for an integrated risk informed decision making process for German regulators

International Nuclear Information System (INIS)

Einarsson, Svante; Wielenberg, Andreas

2013-01-01

Regulatory decisions for German nuclear power plants (NPP) have traditionally been based on deterministic safety analyses. However, the IRRS-Mission of IAEA in 2008 proposed, among others, in 'Suggestion 25' to develop a national policy 'on the use of risk insights in the regulatory framework and decision making'. Consequently, the German Federal Ministry for the Environment, Nature Conservation and Nuclear Safety (BMU) launched a project with the goal of developing a proposal for a uniform federal approach on using risk information in decision making. To this end, the state of the application of probabilistic and risk informed methods has been investigated both on an international and a national level. On the international level, the concept of Integrated Risk Informed Decision Making (IRIDM) has been defined in INSAG-25. It is a structured process, in which all knowledge and requirements relevant to the issue in question are to be considered in a decision. Such knowledge and other requirements are e.g. deterministic and probabilistic safety analyses, regulatory requirements and other applicable findings (including cost-benefit analyses). The IRIDM concept according to INSAG-25 is the cornerstone of the proposal for a uniform federal German approach for IRIDM in the regulatory framework for nuclear installations in Germany. (orig.)

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 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

www.kernenergie.de - nuclear power has a German Internet address

International Nuclear Information System (INIS)

Anon.

2000-01-01

www.kernenergie.de is the address on the worldwide web under which the German nuclear organizations, Deutsches Atomforum (DAtF), Informationskreis Kernenergie (IK), and Kerntechnische Gesellschaft (KTG) as well as atw - internationale Zeitschrift fuer Kernenergie, and INFORUM can be reached. Extensive sources of information, discussions, on-line dictionaries, computer codes, dynamic web pages, digital documents and multimedia offerings can be called up via the portal under the individual web sites. In this way, www.kernenergie.de provides a comprehensive and up-to-date background of information about nuclear power and adjacent topics in the digital worldwide web. (orig.) [de

Lessons from American-German nuclear power plant construction. Quality, safety and costs of an attempt to integrate American and German nuclear power plant technology

International Nuclear Information System (INIS)

Buchwald, K.

1979-05-01

The 1300 MW nuclear power plant at Muelheim-Kaerlich has been under construction since the beginning of 1975. It is being equipped with a pressurised water reactor which has been adapted to the German client's requirements and German licensing practice, based on a license held by Babcock and Wilcox USA (B and W). The problems which have arisen in making this adaptation are the result of different requirements in the USA and the Federal Republic of Germany which make it very difficult to integrate the two technologies. Full integration will almost certainly be impossible, but integration to the widest possible extent is important because it might mean both greater safety and reduced costs. In this article it is intended to show where the problems of integration lie and how they might perhaps be overcome. (author)

German risk study on nuclear power stations. Phase B

International Nuclear Information System (INIS)

1989-11-01

The German Risk Study on Nuclear Power Stations is concerned with investigations of accidents in nuclear facilities and their associated risks. These investigations are undertaken on behalf of the federal Minister of Research and Technology. They have been broken down into two phases (Phase A and Phase B). The results of Phase A were published in 1979 (GRS 79). This report contains a summary of the investigations relating to Phase B. After an introduction setting out the basic principles and aim of the study, a general review will be given of the most important results. The course of the investigations and the results have already been published in a Technical Report (GRS 89). (author)

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)

Nuclear Installations (Jersey) Order 1980 SI No. 1527

International Nuclear Information System (INIS)

1980-01-01

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

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

International Nuclear Information System (INIS)

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

2001-06-01

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

Legal questions relating to nuclear installations close to national frontiers

International Nuclear Information System (INIS)

Zieger, G.

1983-01-01

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

Casualties in Federal German nuclear facilities

International Nuclear Information System (INIS)

1989-01-01

The social insurance companies are responsible for compensation in case of occupational accidents and therefore keep statistics on occupational accidents, which for the workplace 'nuclear installations' show the following data covering the period 1st January 1969 up to 1988: 25 fatal occupational accidents; 1 fatal occupational disease; 20 fatal road accidents. The 25 occupational accidents were of the conventional type. The death in 1988 caused by occupational disease was due to an asbestos mesothelioma acquired by the person during its former occupation in a coal-fired power plant. (orig./HP) [de

Analytic advanced development in the German Risk Study on Nuclear Power Plants

International Nuclear Information System (INIS)

1984-01-01

The study carried out by the Ecological Institute (Oeko-Institut) deals with the difficulties encountered with the decision-making models and statistical models and methods of the German Risk Study on Nuclear Power Plants for the determination of care meltdown frequency and for the estimation of the behaviour of components in the event of a failure. Related deficiencies of the German Risk Study and the absence of completeness and lading representiveness of the course and causes of incidents considered are pointed out. The accident consequences model and the climatological-meteorological data base are considered non-representative. (RF) [de

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

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

Dealing with the Y2K problem in German nuclear facilities

International Nuclear Information System (INIS)

Hagemann, A.

1999-01-01

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

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

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

On-site storage of spent nuclear fuel assemblies in German nuclear power plants

International Nuclear Information System (INIS)

Banck, J.

1999-01-01

The selection of back-end strategies for spent fuel assemblies is influenced by a number of different factors depending on the given situation in any specific country. In Germany, the back-end strategy implemented in the past was almost exclusively reprocessing. This strategy was required by the German Atomic Energy Act. Since 1994, when the Atomic Energy Act was amended, the option of direct final disposal has been granted the equivalent status by law to that afforded to reprocessing (and reuse of valuable materials). As a result, German utilities may now choose between these two alternatives. Another important condition for optimizing the back-end policy is the fact that fuel cycle costs in Germany are directly dependent on spent fuel volumes (in contrast to the US, for example, such costs are related to the amount of power generated). Another boundary condition for German utilities with respect to spent fuel management is posed by the problems with militant opponents of nuclear energy during transportation of spent fuel to interim storage sites. These facts have given rise to a reconsideration of the fuel cycle back-end, which has resulted in a change in strategy by most German utilities in favour of the following: Preference for long-term storage and maximized use of on-site storage capacity; Reduction in the amount of spent fuel by increasing burnup as much as possible. These decisions have also been driven by the deregulation of energy markets in Europe, where utilities are now permitted to sell electric power to consumers beyond their original supply network and must therefore offer electric power on a very cost competitive basis. (author)

German nuclear fuel exports and imports 1991

International Nuclear Information System (INIS)

Anon.

1993-01-01

The statistics compiled by the German Federal Office for Trade and Industry (Bundesamt fuer Wirtschaft) for the Federal Ministry for the Environment, Conservation of Nature, and Reactor Safety of imports and exports of nuclear fuels and source materials in 1991 show a major drop by 33.8% in imports and a pronounced rise by 191.5% in exports, compared to the levels in the previous year. Source material for the purposes of these statistics refers only to uranium concentrate. Quantitatively, the biggest import items are source materials, depleted uranium, and uranium enriched up to 3%. Exports of unirradiated material quantitatively comprise mainly depleted uranium, source material, and uranium enriched up to 10%. (orig.) [de

Imagined Modernity. Nuclear Power and West German Society in the 1960s

International Nuclear Information System (INIS)

Metzler, G.

2012-01-01

In 1969 the first commercial nuclear power plant went into operation in West Germany, making the country a latecomer (compared to other Western countries) in the civilian use of nuclear energy. Yet, in the late 1950s and 1960s, nuclear energy played a major part in public debates on energy supply, on science and technology policy, and the relationship between state and the economy. The civilian use of atomic energy also served as a source of national identity and a projection of modernity. The paper seeks to connect analyses of technical, economic, political, and cultural developments, in order to assess the overall impact of nuclear power on West German society. (author)

Influences of the Internal Market on the operation of nuclear installation

International Nuclear Information System (INIS)

Haeusler, D.

1990-01-01

The author deals with the issues of harmonization of laws in the energy sector, competence of the Community for regulations under atomic energy law, legal harmonization in the area of nuclear energy, the Europeanization of the fuel cycle, effects of waste treatment abroad on proof of disposal and management of radioactive waste, the EC-wide nuclear standardization and a revision of Euratom, i.e. the motion for resolution of the Upper House of the German Federal Parliament, to change the Euratom Treaty in view of the creation of the European Internal Market, which was approved on 30.6.1989. (RST) [de

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

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

Blown by the wind. Replacing nuclear power in German electricity generation

International Nuclear Information System (INIS)

Lechtenböhmer, Stefan; Samadi, Sascha

2013-01-01

Only three days after the beginning of the nuclear catastrophe in Fukushima, Japan, on 11 March 2011, the German government ordered 8 of the country's 17 existing nuclear power plants (NPPs) to stop operating within a few days. In summer 2011 the government put forward a law – passed in parliament by a large majority – that calls for a complete nuclear phase-out by the end of 2022. These government actions were in contrast to its initial plans, laid out in fall 2010, to expand the lifetimes of the country's NPPs. The immediate closure of 8 NPPs and the plans for a complete nuclear phase-out within little more than a decade, raised concerns about Germany's ability to secure a stable supply of electricity. Some observers feared power supply shortages, increasing CO 2 -emissions and a need for Germany to become a net importer of electricity. Now – a little more than a year after the phase-out law entered into force – this paper examines these concerns using (a) recent statistical data on electricity production and demand in the first 15 months after the German government's immediate reaction to the Fukushima accident and (b) reviews the most recent projections and scenarios by different stakeholders on how the German electricity system may develop until 2025, when NPPs will no longer be in operation. The paper finds that Germany has a realistic chance of fully replacing nuclear power with additional renewable electricity generation on an annual basis by 2025 or earlier, provided that several related challenges, e.g. expansion of the grids and provision of balancing power, can be solved successfully. Already in 2012 additional electricity generation from renewable energy sources in combination with a reduced domestic demand for electricity will likely fully compensate for the reduced power generation from the NPPs shut down in March 2011. If current political targets will be realised, Germany neither has to become a net electricity importer, nor will be unable

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

Instalation of two emergency diesel groups in Angra-1

International Nuclear Information System (INIS)

Spitalnik, J.; Doria, L.

1990-01-01

As any technology that evolves, nuclear technology is no exception, mainly when new safety conditions of operation, more limited and restricted than previous ones, are introduced to assure increased protection to the public and the environment. NUCLEN has been actively involved in this type of activity in relation with the Angra-1 nuclear power plant. An important example is the Emergency Diesel Project to install in the power plant, two Diesel sets in addition to the existing ones. Experience gathered in this Project has also shown the way local firms, respectively in the fields of design engineering and power plant operation, were able to structure their teams to fulfill successfully a nuclear project both complex and pioneering. This report shows relevant aspects of the Diesel sets project design and erection, with special emphasis on the solution of problems related to the construction of a nuclear facility of the class-1 type, built under both German and US standards. (author) [pt

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

Uranium from German nuclear power projects of the 1940s - a nuclear forensic investigation

International Nuclear Information System (INIS)

Mayer, Klaus; Wallenius, Maria; Luetzenkirchen, Klaus; Horta, Joan; Nicholl, Adrian; Rasmussen, Gert; Belle, Pieter van; Varga, Zsolt; Buda, Razvan; Erdmann, Nicole; Kratz, Jens-Volker; Trautmann, Norbert; Fifield, L. Keith; Tims, Stephen G.; Froehlich, Michaela B.; Steier, Peter

2015-01-01

Here we present a nuclear forensic study of uranium from German nuclear projects which used different geometries of metallic uranium fuel. Through measurement of the 230 Th/ 234 U ratio, we could determine that the material had been produced in the period from 1940 to 1943. To determine the geographical origin of the uranium, the rare-earth-element content and the 87 Sr/ 86 Sr ratio were measured. The results provide evidence that the uranium was mined in the Czech Republic. Trace amounts of 236 U and 239 Pu were detected at the level of their natural abundance, which indicates that the uranium fuel was not exposed to any major neutron fluence. (copyright 2015 WILEY-VCH Verlag GmbH and Co. KGaA, Weinheim)

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

Elemental Germans Klaus Fuchs, Rudolf Peierls and the making of British nuclear culture 1939-59

CERN Document Server

Laucht, Christoph

2012-01-01

Christoph Laucht offers the first investigation into the roles played by two German-born emigre atomic scientists, Klaus Fuchs and Rudolf Peierls, in the development of British nuclear culture, especially the practice of nuclear science and the political implications of the atomic scientists' work, from the start of the Second World War until 1959.

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)

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)

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

The regulation and deregulation requirements for the decommissioning of nuclear installations

International Nuclear Information System (INIS)

Wagner, H.

1993-01-01

On the basis of a brief outline of the starting point in terms of technical conditions and status, and of the main aspects of application and interpretation of the law, the regulation and deregulation requirements are elaborated in the light of suggestions for change and with regard to their possible concretization in laws and subordinate laws; the strongest need for change undoubtedly is in the field of the technical codes and regulations, which hitherto have been established primarily for the construction and operation of nuclear installations and hence are not necessarily applicable to the activities to be performed for decommissioning. Practice so far has shown, however, that these regulations are applied not analogously, as would be adequate, but in direct manner. The required review and modification of the existing regulatory codes for the purpose of decommissioning will have to concentrate on the following aspects: - Scope and level of specification of application documents; - definition of important, safety-related events (as e.g. accidents); - scope and level of specification of expert opinions, taking into account the reduced risk level. As a long-term objective, it would be desirable to harmonize existing German regulatory provisions for the decommissioning of industrial plants with an environmental impact (as e.g, the Waste Management Act, Atomic Energy Act, mining law, Federal Emission Control Act), and to seek an approach of national regulatory systems and technical codes in this field under the roof of the EC. (orig./HSCH) [de

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

Energy Technology Data Exchange (ETDEWEB)

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

2015-09-15

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

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

International Nuclear Information System (INIS)

1982-12-01

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

Pakistan's rise to nuclear power and the contribution of German companies

International Nuclear Information System (INIS)

Ricke, Klaus-Peter

2013-01-01

The amendment of the Foreign Trade and Payments Act (Aussenwirtschaftsgesetz) has prompted the preparation of this paper because of concerns over potential setbacks in advances achieved over the past twenty years in regulating German exports to non-EU countries and shipments to member states of the EU and the watering down of export restrictions to correspond to the low standards in place at the EU level (with the objective of streamlining the Foreign Trade and Payments Act and nullifying special German requirements which place German exporters at a disadvantage compared with their European competitors, according to a spokesperson of the German Federal Ministry of Economics and Technology). This would send the wrong signal on combating proliferation. From the 1970s to 1990s the Federal Republic of Germany played an extremely negative role because it opened the doors wide to the proliferation of weapons of mass destruction through lax legislation and even more slipshod enforcement. Alarmed by several scandals, in recent years the German government has taken the lead regarding this issue and it would be appropriate for it to continue to fulfill this role. The attitude of the German governments in the 1970s to 1990s as well as the attitude of the key government authorities responsible for controlling exports becomes clear through the example of the cases of illegal exports of nuclear technology to Pakistan. Until the early 1990s the legal situation was such that some acts of proliferation could not even be prosecuted because the licensing regime included only goods listed in Part 1 of the Export Control List (Ausfuhrliste Teil I). The relevant authorities - the Bundesamt fuer Wirtschaft (Federal Office of Economics, BAW) and customs authorities - were neither in terms of personnel nor due to the deficiency of their computer equipment - in a position to carry out their legally prescribed duties. The maximum sentence for even the most serious proliferation violations

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)

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

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

2008 annual nuclear technology conference: opting out of the use of nuclear power. German special approach leads into a dead end of energy policy. Conference report

International Nuclear Information System (INIS)

Anon.

2008-01-01

The President of the Deutsches Atomforum, Dr. Walter Hohlefelder, emphasized in his opening address at the 2008 Annual Nuclear Technology Conference in Hamburg that the German special approach to nuclear power utilization led straight into a dead end of energy policy. ''The outcome is foreseeable: The ambitious German goals of carbon dioxide reduction are missed, the competitiveness of the country is jeopardized, dependency on foreign energy imports rises,'' Dr. Hohlefelder stated. In view of the growing challenges in energy policy Germany had no alternative but to reassess nuclear power. The only outcome of this reappraisal could be extension of the life of nuclear power plants currently in operation. This was necessary also in order to avoid an impending gap in German electricity supply, Dr. Hohlefelder added. He invited all stakeholders to join in an open, unbiased dialog. Dr. Hohlefelder openly criticized the continued ban on research into the development of new reactors. ''A policy of this kind, a policy which bans thinking, is unacceptable in a technology-oriented, industrialized nation such as Germany.'' Nuclear power technology as a high-tech area was a unique achievement which had contributed to the prosperity of the country. The Annual Nuclear Technology Conference, which was held for the 39th time this year, is one of the biggest specialized conferences in the nuclear field with an attendance, this year, of approximately 1300 participants from more than twenty nations. (orig.)

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.)

Uranium from German nuclear power projects of the 1940s - a nuclear forensic investigation

Energy Technology Data Exchange (ETDEWEB)

Mayer, Klaus; Wallenius, Maria; Luetzenkirchen, Klaus; Horta, Joan; Nicholl, Adrian; Rasmussen, Gert; Belle, Pieter van; Varga, Zsolt [European Commission, Joint Research Centre (JRC), Institute for Transuranium Elements (ITU), Karlsruhe (Germany); Buda, Razvan; Erdmann, Nicole [European Commission, Joint Research Centre (JRC), Institute for Transuranium Elements (ITU), Karlsruhe (Germany); Institut fuer Kernchemie, Universitaet Mainz (Germany); Kratz, Jens-Volker; Trautmann, Norbert [Institut fuer Kernchemie, Universitaet Mainz (Germany); Fifield, L. Keith; Tims, Stephen G. [Department of Nuclear Physics, Research School of Physics and Engineering, The Australian National University, Canberra, ACT (Australia); Froehlich, Michaela B. [Department of Nuclear Physics, Research School of Physics and Engineering, The Australian National University, Canberra, ACT (Australia); Universitaet Wien, Fakultaet fuer Chemie, Institut fuer Anorganische Chemie, Vienna (Austria); Steier, Peter [Universitaet Wien, Fakultaet fuer Physik, Isotopenforschung und Kernphysik, Vienna (Austria)

2015-11-02

Here we present a nuclear forensic study of uranium from German nuclear projects which used different geometries of metallic uranium fuel. Through measurement of the {sup 230}Th/{sup 234}U ratio, we could determine that the material had been produced in the period from 1940 to 1943. To determine the geographical origin of the uranium, the rare-earth-element content and the {sup 87}Sr/{sup 86}Sr ratio were measured. The results provide evidence that the uranium was mined in the Czech Republic. Trace amounts of {sup 236}U and {sup 239}Pu were detected at the level of their natural abundance, which indicates that the uranium fuel was not exposed to any major neutron fluence. (copyright 2015 WILEY-VCH Verlag GmbH and Co. KGaA, Weinheim)

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)

The future of nuclear power: An IAEA perspective. Address at the German atomic forum, Berlin, 27 January 2000

International Nuclear Information System (INIS)

ElBaradei, M.

2000-01-01

In his address at the German Atomic Forum (Berlin, 27 January 2000), the Director General of the IAEA presented a survey of the prospects for nuclear power as seen from the perspective of the IAEA. The speech focussed on the following aspects: nuclear power and world energy requirements, nuclear and radiation safety, competitiveness of nuclear power, and public support

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

International Nuclear Information System (INIS)

1972-01-01

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

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

International Nuclear Information System (INIS)

1972-01-01

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

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

International Nuclear Information System (INIS)

Lu Weiwei

2010-01-01

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

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

International Nuclear Information System (INIS)

Rossnagel, A.

1984-01-01

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

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

International Nuclear Information System (INIS)

Gutmann, G.; Engl, G.

1976-01-01

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

Progressive or accelerated phasing out nuclear? Lessons learned from the German choice

International Nuclear Information System (INIS)

Leveque, Francois

2013-01-01

This article first recalls the decision taken at the end of the 1990's by the SPD German government to close the last nuclear reactor in 2022. Back to power, the CDU which notably previously announced an extension of nuclear reactor lifetime and a development of renewable energy as an energy transition policy, but faces the Fukushima accident which resulted in a important change and a decision to close nuclear reactors. This decision resulted in an economic loss: cheap kWh's are to be replaced by expensive ones. The author states that phasing out nuclear would cost 63.8 billions euros. He also states that the macro-economic assessment might be negative although macro-economic effects are difficult to be precisely foreseen. Another consequence will be less production of nuclear wastes but more polluting atmospheric emissions. He thinks that a low carbon price will not affect coal-based electricity production. He finally comments the perception of the nuclear risk

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

Emergency planning and preparedness for nuclear facilities in the Federal Republic of Germany

International Nuclear Information System (INIS)

Koelzer, W.

1988-01-01

Because of their inventories of radioactive materials nuclear facilities represent a hazard potential which, though comparable with that posed by other large technical facilities, demands particular protective measures to be taken. As a consequence of the extreme safety provisions, made, accidents with major impacts on the environment of nuclear facilities are excluded to the best human knowledge. However, as there are distinct limits to human planning and recognition, a residual risk remains despite all these precautions. In order to reduce that risk, recommendations for emergency protection in the environment of nuclear facilities have been drafted. To the extent in which measures are required outside the specific emergency protection plans apply which contain non-object related planning preparations. The recommendation also omits potential repercussions of nuclear accidents which might require measures in the sector of preventive health protection under the Radiation Protection Provisions act or the government measures to be taken. The recommendation is applied to German nuclear installations and those foreign installations whose proximity to the border requires planning measures to be taken on German territory in the sense of this recommendation. (author) [pt

(Nuclear) energy policy in future

International Nuclear Information System (INIS)

1982-01-01

With this report the German Federal Diet submits the final results of the opinion-forming and decision-making process concerning the recommendations made by the investigation committee 'Future Nuclear Energy Policy' in June 1980. By means of this report it is intended to point out to an interested public the difficult and time-consuming process of parliamentary decision-making. This report is also to be seen as the final opinion delivered on the recommendations made by the investigation committee. The recommendations were to continue to pursue the peaceful use of nuclear energy, the necessity and technical justifiability of which had basically been approved by all parliamentary groups. In view of the import of the subject and in recognition of the work done by the investigation committee, the German Parliament has thoroughly discussed the report and has reviewed the analyses and recommendations in conjunction with other political fields to be considered. One part of the recommendations was taken up almost unanimously. As far as the safety of nuclear installations is concerned, the investigation committee could not submit any new findings which would give reasons for modifying the hitherto positive assessment of the safety of nuclear installations. The recommendations of the investigation committee mainly referred to the decision-making process in the field of energy policy which will effect the next decade. What fundamental decisions are to be made until when was pointed out as well as the findings and experience to be made until then. (orig./HP) [de

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)

Plant life extensions for German nuclear power plants? Controversial discussion on potential electricity price effects

International Nuclear Information System (INIS)

Matthes, Felix C.; Hermann, Hauke

2009-06-01

The discussions on electricity price effects in case of the plant life extension of German nuclear power plants covers the following topics: (1) Introduction and methodology. (2) Electricity generation in nuclear power plants and electricity price based on an empirical view: electricity generation in nuclear power plants and final consumption price for households and industry in the European Union; electricity generation in nuclear power plants and electricity wholesale price in case of low availability of nuclear power plants in Germany; comparison of electricity wholesale prices in Germany and France. (3) Model considerations in relation to electricity prices and nuclear phase-out. (4) Concluding considerations.

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

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

Expected returns from a tax on nuclear fuel elements in the context of longer service lives of German nuclear power plants

International Nuclear Information System (INIS)

Kondziella, Hendrik; Bruckner, Thomas

2010-01-01

To what extent will the fuel element tax introduced by the German government in combination with the longer service life of nuclear power stations reduce the profits of public utilities? A qualitative assessment suggests that the tax will not equal the full profits. Using an electricity market model, various scenarios can be calculated for an eight-year prolongation of the residual service life of existing nuclear power plants. (orig.)

Nuclear power and the opting-out policy of the German Government. A matter of responsibility and controversy

International Nuclear Information System (INIS)

Grawe, J.; Voss, A.

2000-01-01

The article critically reviews the energy policy of the German Government and the plans for winding down nuclear power generation and instead pursue a policy for a ''green reshufflement'' of generation technologies, providing for incentives to switch to options for decentralized power generation with enhanced use of renewable energy sources. The article explains arguments against the Government's opting-out policy which were laid down in a memorandum presented to the Government by a group of five university professors, among them the authors of this article who, as experts in this domain, are aware of their responsibility as scientists and members of society and therefore explain their view of the policy issues, also referring to a recent expert opinion of the German Wissenschaftsrat (science council), which recommended to continue nuclear energy research programmes and nuclear power generation. (orig./CB) [de

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

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

The new recommendations of ICRP and their possible consequences for operating nuclear installations

International Nuclear Information System (INIS)

Lorenz, Bernd; Hesse, Johannes; Schwarz, Wolfgang; Kapteinat, Heinzpeter; Holl, Matthias

2008-01-01

Full text: After an extensive and very open debate within the Radiation Protection Community the new recommendations of the ICRP on the basic principles of radiation protection have been issued in 2007. The German nuclear industry has watched the process intensively and tried to bring in their large amount of experience from the daily radiation protection practice in numerous nuclear installations. Notably the ICRP seemed to follow some of the comments given by those experienced operators. The ICRP key message 'stability and continuity' is highly welcomed by industry. The dose levels resulting from well managed operations today are far below the dose limits due to a working system of ALARA thinking and doing. The basic principles of radiation protection as pointed out by ICRP decades ago have been proven to be an effective tool and are an essential part of the legal system of most countries with developed nuclear industries. Unfortunately, not all of the comments of the experienced operators have been considered to the desirable extend. A mayor point of criticism is the central role ICRP devoted to the use of dose constraints for any source. Dose constraints do play a role in today's practice of radiation protection but they have been rather supplementary than central in the system. The idea that for all sources, and there might be Hundreds or Thousands sometimes very tiny sources in a practice, a dose constraint shall exist sounds quite inappropriate. Another example which might disturb the great vision of 'stability and continuity' is the change of ICRP into a different view on protection. Instead of processes now situations are in the focus. There are some doubts about the benefits of such a move. People will always ask if there is a change of content when using a different terminology. A lot of fruitless discussions will probably result. Nevertheless, in spite of some criticism the new ICRP will contribute to strengthen the protection regime and industry will

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

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.

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

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

The rise and the crisis of the German nuclear economy 1945-1975

International Nuclear Information System (INIS)

Radkau, J.

1983-01-01

The nuclear economy has for some time been complaining of being the scapegoat of a protest movement the origin and motive of which has nothing to do with nuclear technology. On the opposite side the sticker ''Nuclear energy - No thanks'' has long become the distinguishing sign of people longing to change their entire way of life. The fact that this protest movement around 1970 did spring from blatantly weak points of the nuclear technology which at the time became obvious has practically fallen into oblivion. The author describes the history of the German nuclear economy under changing aspects in its sociopolitical, economic and technical context. Files of the ministries in charge and their advisory committees, minites of the committees of the Bundestag, bequests of influential personages and oral communications - material which for the most part has not so far been either used or published - provide insight into connections unexplained until now or unknown altogether. This historic recourse might lead to the subject as such, viz. nuclear technology, becoming again the object of discussions instead of ''Nuclear energy. No thanks'' being used as a sticker. (orig./HP) [de

Supervision of nuclear material in the Federal Republic of Germany by the Commission of the European Communities (Euratom) and the International Atomic Energy Organisation (IAEO)

International Nuclear Information System (INIS)

Brueckner, C.

1979-01-01

Since the fifties Euratom has controlled nuclear material in the Federal Republic of Germany. When the verification agreement came into force in the treaty on the non-proliferation of atomic weapons in February 1977, the International Atomic Energy Organisation (IAEO) has commenced the supervision of nuclear material in German nuclear energy installations. The author describes the basic principle of the supervision and the possible effects on the installations. In addition, he also deals with the discussions which have flared up about the international supervision of nuclear material, and indicates possible future developments. (orig.) [de

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

Energy Technology Data Exchange (ETDEWEB)

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

2013-07-01

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

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

International Nuclear Information System (INIS)

Mahe, Carole; Leroy, Christine

2013-01-01

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

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

Dictionary of nuclear engineering. English-German-French-Russian. Kerntechnik. Englisch-Deutsch-Franzoesisch-Russisch

Energy Technology Data Exchange (ETDEWEB)

Sube, R

1985-01-01

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

Experience in commissioning and scientific support of nuclear power plant operation in the German Democratic Republic

International Nuclear Information System (INIS)

Ackermann, G.; Endler, A.; Loth, K.H.

1983-01-01

In the German Democratic Republic two nuclear power plants equipped with four pressurized-water WWER-440-type reactors were commissioned in the years 1973-1979 and have since been in routine operation. The nuclear power plants (NPPs) in the GDR were constructed on the basis of projects developed and tested in the Soviet Union. Their main equipment was also supplied by the USSR. Under the technical supervision of USSR scientific institutions and design organizations, the construction, commissioning and operation of NPPs had to be prepared and organized by the design organizations, scientific institutions and the prospective user in the German Democratic Republic. To this effect, and to ensure nuclear safety, availability and maximum exploitation of nuclear fuel, it was necessary to develop national scientific capacities. The organizations of the USSR supply basic and supplementary documents prescribing the required extent of investigations to prove that the equipment and systems will meet the projected and operational conditions from loading to commercial operation. Concrete test programmes for commissioning and operational instructions are elaborated by national organizations. Pre-operational and initial startup tests are performed by the personnel of the plant, of enterprises and scientific institutions under the technical supervision of the design organizations of the USSR and the German Democratic Republic. Proceeding from experience gained for more than 15 years in the scientific support of commissioning and operation, the required training and disciplines of personnel are reported. The tasks to be met by the various disciplines are described. Furthermore, information is given on the main stages of commissioning and on a number of results. Finally, selected results of work in connection with operational assistance are reported

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)

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

Comparative study of design of piping supports class 1, 2 and 3 considering german code KTA and ASME III - NF

International Nuclear Information System (INIS)

Faloppa, Altair A.; Fainer, Gerson; Mattar Neto, Miguel; Elias, Marcos V.

2013-01-01

The objective of this paper is developing a comparative study of the design criteria for class 1, 2, 3 piping supports considering the American Code ASME Section III - NF and the German Code KTA 3205.1 to the Primary Circuit, KTA 3205.2 to the others systems and KTA 3205.3 series-production standards supports of a PWR nuclear power plant. An additional purpose of the paper is a general analysis of the main design concepts of the American Code ASME Boiler and Pressure Vessel Code, Section III, Division 1 and German Nuclear Design Code KTA that was performed in order to aid the comparative study proposed. The relevance of this study is to show the differences between codes ASME and KTA since they were applied in the design of the Nuclear Power Plants Angra 1 and Angra 2, and to the design of Angra 3, which is at the moment under construction. It is also considered their use in the design of nuclear installations such as RMB - Reator MultiProposito Brasileiro and LABGENE - Laboratorio de Geracao Nucleoeletrica. (author)

Status of project design work for a German reprocessing plant

International Nuclear Information System (INIS)

Lang, K.; Zuehlke, P.

1976-01-01

A reprocessing plant will be built within the framework of a comprehensive waste management center planned by the Federal Government to treat the fuel elements unloaded from German nuclear power stations. On the basis of an annual throughput of 1,400 te of uranium averaged over the life of the plant, the center will be able to serve between 45,000 and 50,000 MWe of installed nuclear generating capacity. A comprehensive conceptual design study of the reprocessing plant to be built has been completed on the basis of the operating experience accumulated at the Karlsruhe reprocessing plant and the development work carried out by the Karlsruhe Nuclear Research Center and in the light also of an intensive exchange of experience with British and French reprocessing companies within the framework of United Reprocessors GmbH. This conceptual design study is the foundation for the preliminary project to be carried out on a collaborative basis by KEWA and PWK. (orig.) [de

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)

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

German study on the risks of nuclear power plants

International Nuclear Information System (INIS)

Wollny, V.

1987-01-01

The 'Deutsche Risikostudie Kernkraftwerke', DRS, (German study on the risks of nuclear plants) calculates a frequency of 1/10000 years (i.e. once in 10000 years of reactor operation) for the event of insufficient cooling of the reactor core occurring. The resulting collective risk is put at approximately 10 deaths per year for 25 plants. As the explanations show, the error margin of such a risk statement is enormous. Moreover, much seems to indicate that the risk was underrated. Apart from this, risk analyses are of doubtful value in the decision process for or against the introduction of large-scale technologies. They cannot replace the individual decision of all concerned. (orig./HSCH) [de

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)

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

German experience in recycling of ferrous metallic residues from nuclear decommissioning by melting

International Nuclear Information System (INIS)

Quade, U.; Kluth, Th.

2008-01-01

Due to the delay of commissioning of final depositories for nuclear waste on the one hand and the increasing amount of steel scrap resulting from operation and decommissioning of nuclear facilities on the other hand, recycling of ferrous metal scrap to packagings made of ductile cast iron becomes more and more economical. A pool of know-how from waste managers, radiation protection experts, metallurgists and foundry experts and their teamwork is required to run this recycling path successfully. Siempelkamp provides this combination of experience by operating a melting facility for slightly radioactive contaminated scrap as well as a foundry for manufacturing of ductile cast iron products for the nuclear industry, both licensed by the German Radiation Protection Ordinance. In 1989, the CARLA plant (Centrale Anlage zum Rezyklieren von leichtradioaktiven Abfollen) started operation. A medium frequency induction furnace with a capacity of 3,2 t is core of the plant. Tools for dismantling and cutting components to chargeable sizes are available. From the total of 23000 t of melted scrap, 12000 t have been recycled to the manufacturing of containers for transport and storage of medium- and high active waste and for shielding plates. Manufacture of the castings takes place in the Siempelkamp foundry located at the same site. 8000 t of melted scrap could be released for industrial recycling. Scrap metal which does not meet the metallurgical specification for cast iron, is converted into iron granules. Up to now more than 2000 t of iron granules have been recycled as additive for heavy concrete containers. This production is in cooperation with an external partner. With regard to the German situation, the cost for recycling is only half compared to high pressure compaction, long-term interim storage and final disposal. The advantage of recycling is approx. 90 % less volume compared to the volume resulting from other disposal paths. It can be concluded that the German

Decommissioning of NPPs with spent nuclear fuel present - efforts to amend the German regulatory framework to cope with this situation

International Nuclear Information System (INIS)

Brendebach, Boris; Rehs, Bernd

2016-01-01

The authorization to operate an installation for the fission of nuclear fuel for the commercial production of electricity was withdrawn for the seven oldest NPPs and NPP Kruemmel in Germany on August 6, 2011 after the events at Japanese Nuclear Power Plant (NPP) Fukushima Daiichi in March 2011. In the meantime, all these NPPs applied for decommissioning. One aspect reflected in the applications for these NPPs is the possibility that spent nuclear fuel elements or fuel rods will still be present in the cooling ponds at least during the first stage of decommissioning, i.a. due to limited availability of spent fuel casks. Although considerable decommissioning experiences are available in Germany, the approach 'decommissioning with fuel elements present' has been the exceptional case so far. The paper highlights the efforts undertaken to strengthen the regulatory framework with respect to decommissioning in Germany taking into account this changed approach. The paper presents a short introduction to the legal and regulatory requirements for decommissioning in Germany. Afterwards, the updates to the Decommissioning Guide, which includes proposals for an appropriate procedure for the decommissioning, safe enclosure and dismantling of facilities or parts thereof as defined in item 7 of the German Atomic Energy Act in respect of the application of the technical rules for planning and preparation of decommissioning measures as well as for licensing and supervision, are highlighted. In addition, the amendments to the Guidelines for the Decommissioning of Nuclear Facilities of the Nuclear Waste Management Commission (ESK), which is complementary to the Decommissioning Guide in a technical sense, are reported as well. (authors)

Crystalline phase of sodium germanate system determined by x-ray diffraction and 23Na magic angle spinning nuclear magnetic resonance

International Nuclear Information System (INIS)

Hussin, R.; Holland, D.; Dupree, R.

2000-01-01

Crystalline products of sodium germanate glasses system with composition from 10 mol% to 50 mol% Na 2 O have been investigated using 23 Na magic angle spinning (MAS) nuclear magnetic resonance (NMR) spectroscopy and x-ray diffraction (XRD). Fitting of the 23 Na NMR spectra of the crystalline phases concerning different crystallographically sodium atom in sodium germanate system are reasonably reproducible as observed by the spectra obtained. The line shape simulations of the 23 Na NMR spectra yielded NMR quadrupolar parameters such as nuclear quadrupole coupling constants (C Q ), asymmetry parameters (η), and isotropic chemical shifts (δ i ). 23 Na NMR isotropic chemical shift may also provide further information on the structural environment of the sodium atom. A simple correlation between structure and NMR parameters to be tested can be used to probe the structure of sodium germanate glasses. The experimental 23 Na chemical shifts correlate well with an empirical shift parameter based on the total oxygen-cation bond valence and Na-O distances of all oxygen atoms in the first coordination sphere of the sodium cation. In this study the different phases in the sodium germanate system were identified. These results show that 23 Na NMR can provide examples of the types of structural information for sodium germanate system. (Author)

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

EXTREMUS - the German solution for act of terrorism - non-nuclear risks coverage

International Nuclear Information System (INIS)

Harbrucker, D.

2004-01-01

As a consequence of the terrorist attacks of September 11, 2001 and the withdraw of reinsurance capacity worldwide for terrorism coverage under material damage policies EXTREMUS was founded on September 2nd, 2002 by the German insurance industry (shareholders are 16 (re) insurance groups operating in the country). EXTREMUS offers a maximum limit per insured of Euro 1,5 bn. and enjoys a warranty of the German Government to cover accumulation losses in xs of Euro 2.0 bn. up to Euro 10 bn. EXTREMUS only intervenes for policies exceeding Euro 25 mio. due to a self obligation of the primary market to maintain full coverage for smaller risks. Due to the demand of reinsurers losses caused by a b c weapons are excluded. Coverage is not available for nuclear power plants. The paper aims to deals with these issues in more details.(author)

Approach to long- term regalement of nuclear energy installation decommissioning

International Nuclear Information System (INIS)

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

2001-01-01

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

Performance study of the paints for use in nuclear installations

International Nuclear Information System (INIS)

Yamashita, T.

1978-01-01

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

Utilization of a full-scope simulation for training the operating personel of nuclear power plants

International Nuclear Information System (INIS)

Mathias, S.G.

1987-01-01

A full-scope simulator of the Angra-2 Nuclear Power Plant has been installed at the NUCLEBRAS Training Center in Mambucaba - close to the site where that Plant is being built -, the goal of providing training for the operating personnel of the KWU-design nuclear power plants to be installed in Brazil. Due to the delays which occurred in the construction of Angra-2, NUCLEBRAS has established an extensive program for the utilization of the simulator for the training of operators for German nuclear power plants and for Spain's Trillo Plant. Besides yielding profits to NUCLEBRAS, that program is resulting in considerable experience in the area of nuclear power plant operators' training generating international recognition to the NUCLEBRAS Training Center. (Author) [pt

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

Nuclear research in Strasbourg. The first ten years 1941-1951

International Nuclear Information System (INIS)

Casel, R.

1993-01-01

The story of the first decade of the nuclear research in Strasbourg includes three different periods. During the war there is the installation as part of the Reichsuniversitaet Strassburg (november 1941-november 1944) of one 'Medical Research Institute' the physics department of which is equipped with a very important equipment for the period, particularly a connection generator of 1.5 MeV. For the Liberation, the civil hospices and the Strasbourg Medicine Faculty decide to create from the old german installations an artificial radioisotope production laboratory: the 'Strasbourg Nuclear Research Institute' (N.R.I) which was born in 1947 as interfaculty Institute (Medicine, Science, Pharmacy). But the N.R.I doesn't make for the applied research but for the fundamental research. To the nuclear research institute will be added in 1950 the corpuscular physics and the nuclear chemistry laboratories. 163 refs., 20 figs

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

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

International Nuclear Information System (INIS)

1972-01-01

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

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

International Nuclear Information System (INIS)

1972-01-01

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

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

International Nuclear Information System (INIS)

1972-01-01

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

The cyber security of French nuclear installations: stakes and opportunities

International Nuclear Information System (INIS)

Marquez, Thierry

2016-01-01

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

ECAT ART - a continuously rotating PET camera: performance characteristics, initial clinical studies, and installation considerations in a nuclear medicine department

International Nuclear Information System (INIS)

Bailey, D.L.; Young, H.; Bloomfield, P.M.; Meikle, S.R.; Glass, D.; Myers, M.J.; Spinks, T.J.; Watson, C.C.; Luk, P.; Peters, A.M.; Jones, T.

1997-01-01

Advances in image reconstruction techniques have permitted the development of a commercial, rotating, partial ring, fully 3D scanner, the ECAT ART. The system has less than one-half the number of bismuth germanate detectors compared with a full ring scanner with the equivalent field of view, resulting in reduced capital cost. The performance characteristics, implications for installation in a nuclear medicine department, and clinical utility of the scanner are presented in this report. The sensitivity (20 cm diameter x 20 cm long cylindrical phantom, no scatter correction) is 11400 cps.kBq -1 .ml -1 . This compares with 5800 and 40500 cps.kBq -1 .ml -1 in 2D and 3D respectively for the equivalent full ring scanner (ECAT EXACT). With an energy window of 350-650 keV the maximum noise equivalent count (NEC) rate was 27 kcps at a radioactivity concentration of ∝15 kBq .ml -1 in the cylinder. Spatial resolution is ∝6 mm full width at half maximum on axis degrading to just under 8 mm at a distance of 20 cm off axis. Installation and use within the nuclear medicine department does not appreciably increase background levels of radiation on gamma cameras in adjacent rooms and the dose rate to an operator in the same room is 2 μSv .h -1 for a typical fluorine-18 fluorodeoxyglucose ( 18 F-FDG) study with an initial injected activity of 370 MBq. The scanner has been used for clinical imaging with 18 F-FDG for neurological and oncological applications. Its novel use for imaging iron-52 transferrin for localising erythropoietic activity demonstrates its sensitivity and resolution advantages over a conventional dual-headed gamma camera. The ECAT ART provides a viable alternative to conventional full ring PET scanners without compromising the performance required for clinical PET imaging. (orig.). With 9 figs., 3 tabs

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)

Nuclear Phase-Out: myth or reality?

International Nuclear Information System (INIS)

2012-01-01

Since the Fukushima accident, a new speech has come to enrich the energy debate, overtaking the one of the energy transition foreseen for 2025: it is possible to immediately get out of nuclear power. The proof put forward is that the Germans and the Japanese could do it. What is really going on in these countries and what comparison can be done with France is the purpose of this paper. In Japan, prior to the tsunami, nuclear production was representing only 27% of the overall power generation. In Germany, prior to the decision taken by Chancellor Merkel, nuclear energy was at a level even more lower: 22%. This is totally different from the 75% of the French energy mix, and even if the number of NPPs in Japan is close to the one of France (54 against 58), the power of Japanese NPPs reaches 47 GW (17% of the installed power), against 63 GW for the French nuclear park (52% of the total power). Moreover, the reflections about the German and Japanese situations were made on limited periods of time and cannot be extrapolated to longer periods

The importance of servicing for the safety and economic efficiency of nuclear installations

International Nuclear Information System (INIS)

Wild, E.

1991-01-01

Experience-oriented preventive maintenance is the central and decisive instrument for plant safety. Preventive maintenance, in the overriding sense of the entire system consisting of man and machine, is identical with service. Such service must be readily available, efficient, purposeful, innovative and of high quality. The high quality of German nuclear power plants and their reliability are the result of a constructive cooperation between producer, supplier, service enterprise and operator. (DG) [de

Life extension of German nuclear power plants only with the consent of the Federal Council? The importance and extent of the need for consent to an amendment to the German Atomic Energy Act

International Nuclear Information System (INIS)

Schneider, Horst

2010-01-01

In its coalition agreement of October 26, 2009, the new German federal government plans ''to extend the service life of German nuclear power plants while, at the same time, complying with the strict German and international safety standards.'' This has triggered a debate not only about (nuclear) energy, as in the past election campaign in the summer of 2009, but also about the constitutional law issue whether an amendment to the Atomic Energy Act resulting in longer operating life of nuclear power plants required the consent of the Federal Council (the ''Bundesrat,'' the second chamber of parliament). After the election to the state parliament in North Rhine-Westphalia on May 9, 2010, majority in the Federal Council changed. As a consequence, no consent to an amendment to the Atomic Energy Act must be expected. In view of the large number of recent statements about constitutional law in opinions for various federal and ministerial accounts as well as firms and associations, the outline by R. Scholz in the May issue of atw 2010 will be followed in this issue by the key points of examination of the need for consent, under aspects of constitutional law, and an attempt will be made to explain the evaluations underlying the generation of a legal concept about these items. The decision by the German Federal Constitutional Court of May 4, 2010, published on June 11, 2010, plays a major role in this respect because it established clarity in some important aspects of a legal subject matter in the field of state admini-stration on behalf of the federation, albeit in the field of air traffic law, not nuclear law. However, the structures of the norms in the German Basic Law (Art. 87c and Art. 87d, para.2) to be applied are almost identical. The energy policy and energy economy aspects of a plant life extension are considered along with the option of an appeal to the Federal Constitutional Court against any plant life extension. Finally, the key findings are summarized briefly

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

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.)

West German alternatives for reducing reliance on nuclear weapons

International Nuclear Information System (INIS)

Brauch, H.G.

1988-01-01

Nuclear deterrence in general and the US doctrinal concept of mutual assured destruction as well as the common strategic understanding of mutual vulnerability, codified by the SALT process, and the nuclear first use option of NATO's flexible response strategy (MC14/3) have come under attack, both from official and unofficial circles, in the United States and Europe likewise. In spite of the general agreement, that the time may have come to search for alternatives, to move from MAD to MAS (mutual assured security), as President Reagan indicated in a New York Times interview or for a Common Security posture, as called for by the Palme Commission, nevertheless major disagreements and contradictions exist as to how European security could be enhanced with a defensive posture beyond deterrence. Two groups of alternatives are being distinguished in this paper: official efforts in the United States and in Europe, to use the anti-nuclear sentiment, to legitimate changes in the operative doctrine of the US and of NATO forces and to obtain funds both for a comprehensive buildup and modernization of conventional forces in Europe and for a Strategic (SDI) and probably soon also for a European Defence Initiative (EDI) or an extended air defence, and unofficial proposals by American, European and West German Experts for a non-provocative, inoffensive defence or for a gradual defensivity consisting of static and mobile components

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.

Involving private persons and corporations in the planning process according to paragraph 9b German nuclear law - practicability and limits

International Nuclear Information System (INIS)

Altmann, J.; Roesel, H.

1978-01-01

The 4th Amendment to the German Nuclear Law has procured the legal base for the disposal of radioactive waste in the German Federal Republic. The Nuclear Law states that the Physikalisch-Technische Bundesanstalt (PTB) in Braunschweig is responsible for the disposal of radioactive waste. The PTB can be assisted in its responsibilities by persons and institutions of private character. Involving private persons and corporations in the licensing process figures a legal problem, and there has been a seminar in the PTB discussing such problems. The present contribution gives a brief summary of the opinions stated by the various legal experts taking part in this seminar. (orig./HP) [de

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)

Advances and Challenges in the Implementation of DiD in Siting, Design, and Construction of Nuclear Installations in Vietnam

Energy Technology Data Exchange (ETDEWEB)

Nguyen, H.A., E-mail: nhanh@varans.vn [Vietnam Agency for Radiation and Nuclear Safety, Hanoi (Viet Nam)

2014-10-15

Vietnam is embarking on a development of a nuclear power program. The main focus is now on the initial 1000 MWe x 2 units of the nuclear power plant in Ninh Thuan province. Now, the nuclear projects of Vietnam are in the phase of siting approval and investment projects approval. The design assessment will be performed in 2013-2014; the construction and installation will be performed from now until the operating licensing is obtained in 2020-2021. With state of development of a nuclear power program in Vietnam, this paper only focuses on advances and challenges in the implementation of Defence in Depth (DID) in siting, design, and construction of nuclear installations in Vietnam. (author)

Nuclear fuel - is it the unknown thing

International Nuclear Information System (INIS)

Feldmann, U.

1986-01-01

Attempts to define the term ''nuclear fuel'' will meet with manifold difficulties in practice, due to the existence of many related terms in national law, and of identically worded, but not necessarily synonymous, terms in international or supranational law. In the provisions concerning the third party liability of owners of nuclear installations, the national law of the FRG uses the term as defined by the Paris Convention. In the context of financial security for nuclear installations, the term is used within the meaning of section 2, sub-sec.(1), no. 1 of the Atomic Energy Act. A comparison of the national German law and the provisions of the Paris Convention concerning the characterization of uranium as a nuclear fuel shows that the differences in definition between PC and Atomic Energy Act are not as significant as they seem to be when reading the different texts of the provision. So it is not absolutely necessary to adopt the special definition for enriched uranium given by the Steering Committee of ENEA in order to reach agreement on the interpretation of the term. (orig.) [de

The German energy transition: the end of ambitions?

International Nuclear Information System (INIS)

Beeker, Etienne

2017-08-01

This article proposes an overview of the German situation regarding the implementation of its energy transition policy (Energiewende) which mainly comprised phasing out nuclear and fossil energies, and their replacement by renewable energies. The authors notably comment figures and tables which illustrate the evolution of greenhouse gas emissions in Germany, France and Europe, the evolution of wind and photovoltaic installations in Germany, the status of the energy mix and the shares of renewable energies in primary consumption in Germany and in France, the electricity productions from the different sources in Germany and in France, the structure of electric power tariffs in Germany and in France. Focusing on the German case, they outline that the objectives defined for 2020 for renewable energies are almost reached, but what comes next remains uncertain. They also notice that the objective of phasing out nuclear in 2022 is kept. They discuss the various difficulties faced by the Energiewende: a too slow improvement of energy efficiency, a development of electric vehicles facing realities of the automotive industry, a difficult but necessary phasing out coal. They outline two main challenges: to face some resistance by the population: the risk of black-outs due to the difficult management of renewable intermittency, and a high level of expenses which are mainly paid by small consumers. The future of this policy may also been put into question again after the elections of September 2017

Requirements and criteria for choosing sites suitable for the construction of nuclear installations and power stations

International Nuclear Information System (INIS)

1978-05-01

The present document explains the selection criteria for areas in Italy suitable for the installation of nuclear power stations to be included in the 'National Site Map' provided for in Section 23 of Act No 393 of 2 August 1975. It represents the results of a thorough investigation into the various aspects of the problem of siting nuclear power stations, at the present stage of technology, taking into account the effect of the installations on the environment and the effect of the environment on the installations. The essential aim is to demonstrate that the requirements derived from these analyses, and on which there was full consultation with the other controlling bodies of European countries (in particular, France, Great Britain and West Germany) ensure the optimum choice of areas from the point of view of safety and public health. (author)

Role of the Regulatory Body in Implementing Defence in Depth in Nuclear Installations - Regulatory Oversight in Egypt

Energy Technology Data Exchange (ETDEWEB)

El-Sheikh, B. M., E-mail: badawymel@yahoo.com [Egyptian Nuclear and Radiological Regulatory Authority Cairo (Egypt)

2014-10-15

The fundamental objective of all nuclear safety regulatory bodies is to ensure that nuclear facilities are operated at all times in an acceptably safe manner including the safe conduct of decommissioning activities. Defence in depth is recognized as one of the fundamental safety principles that underlie the safety of nuclear power plants. Defence in depth is implemented to provide a graded protection against a wide variety of transients, incidents and accidents, including equipment failures and human errors within nuclear power plants and events initiated outside plants. The Regulator Body plays an important role in implementing defence in depth in nuclear installations in the context of a clear allocation of responsibilities with an operating organization. This role starting with setting safety objectives and by its own independent review and technical assessment of the safety justifications provided by the operating organization in addition to safety culture investigating within relevant organizations. This paper briefly reviews this role in normal operation and post accidents, and its effects on overall nuclear safety in nuclear installations with reference to Egyptian regulatory oversight. (author)

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

International Nuclear Information System (INIS)

1990-01-01

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

Handling and carrying head for nuclear fuel assemblies and installation including this head

International Nuclear Information System (INIS)

Artaud, R.; Cransac, J.P.; Jogand, P.

1986-01-01

The present invention proposes a handling and carrying head ensuring efficiently the cooling of the nuclear fuel asemblies it transports so that any storage in liquid metal in a drum within or adjacent the reactor vessel is suppressed. The invention claims also a nuclear fuel handling installation including the head; it allows a longer time between loading and unloading campaigns and the space surrounding the reactor vessel keeps free without occupying a storage zone within the vessel [fr

German Democratic Republic State system of accounting for and control of nuclear material

International Nuclear Information System (INIS)

Roehnsch, W.; Gegusch, M.

1976-01-01

The system of accountancy for and control of nuclear material in the German Democratic Republic (GDR) with its legal bases and components is embedded in the overall State system of protection in the peaceful uses of nuclear energy. As the competent State authority, the Nuclear Safety and Radiation Protection Board of the GDR is also responsible for meeting the GDR's national and international tasks in the control of nuclear material. At enterprise level, the observance of all safety regulations for nuclear material, including the regulations for the control, is within the responsibility of managers of establishments, which are in any way concerned with the handling of nuclear material. To support managers and to function as internal control authorities, nuclear material officers have been appointed in these establishments. Design information, operating data, physical inventory of nuclear material and the respective enterprise records and reports are subject to State control by the Nuclear Material Inspectorate of the Nuclear Safety and Radiation Protection Board. This Inspectorate keeps the central records on nuclear material, forwards reports and information to, and maintains the necessary contacts with, the IAEA. For the nuclear material in the GDR four material balance areas have been established for control purposes. To rationalize central recording and reporting, electronic data processing is increasingly made use of. In a year-long national and international control of nuclear material, the State control system has stood the test and successfully co-operates with the IAEA. (author)

Preparation of site emergency preparedness plans for nuclear installations

International Nuclear Information System (INIS)

1999-10-01

Safety of public, occupational workers and the protection of environment should be assured while activities for economic and social progress are pursued. These activities include the establishment and utilisation of nuclear facilities and use of radioactive sources. This safety guidelines is issued as a lead document to facilitate preparation of specific site manuals by the responsible organisation for emergency response plans at each site to ensure their preparedness to meet any eventuality due to site emergency in order to mitigate its consequences on the health and safety of site personnel. It takes cognizance of an earlier AERB publications on the subject: Safety manual on site emergency plan on nuclear installations. AERB/SM/NISD-1, 1986 and also takes into consideration the urgent need for promoting public awareness and drawing up revised emergency response plans, which has come about in a significant manner after the accidents at Chernobyl and Bhopal

Pakistan's rise to nuclear power and the contribution of German companies

Energy Technology Data Exchange (ETDEWEB)

Ricke, Klaus-Peter

2013-09-01

The amendment of the Foreign Trade and Payments Act (Aussenwirtschaftsgesetz) has prompted the preparation of this paper because of concerns over potential setbacks in advances achieved over the past twenty years in regulating German exports to non-EU countries and shipments to member states of the EU and the watering down of export restrictions to correspond to the low standards in place at the EU level (with the objective of streamlining the Foreign Trade and Payments Act and nullifying special German requirements which place German exporters at a disadvantage compared with their European competitors, according to a spokesperson of the German Federal Ministry of Economics and Technology). This would send the wrong signal on combating proliferation. From the 1970s to 1990s the Federal Republic of Germany played an extremely negative role because it opened the doors wide to the proliferation of weapons of mass destruction through lax legislation and even more slipshod enforcement. Alarmed by several scandals, in recent years the German government has taken the lead regarding this issue and it would be appropriate for it to continue to fulfill this role. The attitude of the German governments in the 1970s to 1990s as well as the attitude of the key government authorities responsible for controlling exports becomes clear through the example of the cases of illegal exports of nuclear technology to Pakistan. Until the early 1990s the legal situation was such that some acts of proliferation could not even be prosecuted because the licensing regime included only goods listed in Part 1 of the Export Control List (Ausfuhrliste Teil I). The relevant authorities - the Bundesamt fuer Wirtschaft (Federal Office of Economics, BAW) and customs authorities - were neither in terms of personnel nor due to the deficiency of their computer equipment - in a position to carry out their legally prescribed duties. The maximum sentence for even the most serious proliferation violations

The German simulator center for the training of nuclear power plant operators

International Nuclear Information System (INIS)

Hoffmann, E.

1996-01-01

Simulator training for nuclear power plant operators in Germany is conducted in The Simulator Center in Essen. The companies operating The Center are KSG/GfS. KSG provides simulators, GfS performs the training. The German Simulator Center is equipped with five simulators in training, nine simulators are under construction and will be ready for training until the beginning of 1997. This institution serves 22 nuclear power plants units in Germany, Switzerland (NPP Goesgen-Daeniken) and the Netherlands (NPP Borssele) and trains 1,800 persons every year. As a common enterprise the company is owned by 12 utilities, which leads to the necessity to prepare common rules and guidelines for simulator specification, training of instructors, assessment of trainees, training material and preparation and methodical running of simulator courses

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)

Nuclear installations safety and protection: thirty years of researches on earthquakes at the IRSN; Surete et protection des installations nucleaires: trente ans de recherches a l'IRSN sur les seismes

Energy Technology Data Exchange (ETDEWEB)

NONE

2003-03-01

Every years more than one hundred earthquakes occur in France. Taking into account this risk is essential for the safety of nuclear installations. In this context the IRSN develops research programs on earthquakes and realizes evolutions of safety procedures. This paper presents three sheets of researches realized by the IRSN on earthquakes risk assessment in the nuclear installations design and exploitation and the example of the Saint-Die earthquake. (A.L.B.)

Using management of aging in German nuclear power plants - aspects of KTA 1403 pertaining to residual power operation, post-shutdown operation and residual operation

International Nuclear Information System (INIS)

Barreiro, Pablo; Bever, Thomas; Brast, Gerhard; Elsche, Bjoern; Reese, Sven H.; Grossmann, Patrick; Widera, Martin; Huettner, Frank; Linnemann, Thomas; Smit, Swen-Olaf; Zander, Ralf-Michael

2013-01-01

Management of aging in nuclear power plants originated in the United States of America and became a topic of debate in Germany from the late 1990s onward. On the basis of the existing plant-specific measures practiced comprehensively, KTA 1403, ''Management of Aging in Nuclear Power Plants'', was drafted and finalized in 2010. This publication first presents the context of AM with regard to German nuclear power plants, including references to national and international historical developments. Against this backdrop, the difference between management of aging and lifetime management is discussed next. This is followed by a description of the status of the AM process in nuclear power plants currently in operation, especially organizational plant-specific implementation. As a consequence of the decision by the German federal government to discontinue the peaceful use of nuclear power in Germany and the associated 13th amendment to the Atomic Energy Act of July 31, 2011, a considerable part of the German nuclear power plant park already lost its right of power operation. In this situation, aspects of AM are discussed for plants in the no-power, post-operation and residual operation phases. Finally, experience accumulated in plant-specific execution of the AM process on the basis of KTA 1403 is considered and summarized.

Safety culture in nuclear installations: Bangladesh perspectives and key lessons learned from major events

International Nuclear Information System (INIS)

Jalil, A.; Rabbani, G.

2002-01-01

Steps necessary to be taken to ensure safety in nuclear installations are suggested. One of the steps suggested is enhancing the safety culture. It is necessary to gain a common understanding of the concept itself, the development stages of safety culture by way of good management practices and leadership for safety culture improvement in the long-term. International topical meetings on safety culture may serve as an important forum for exchange of experiences. From such conventions new initiatives and programmes may crop up which when implemented around the world is very likely to improve safety management and thus boost up the safety culture in nuclear installations. International co-operation and learning are to be prompted to facilitate the sharing of the achievements to face the challenges involved in the management of safety and fixing priorities for future work and identify areas of co-operations. Key lessons learned from some major events have been reported. Present status and future trend of nuclear safety culture in Bangladesh have been dealt with. (author)

New trends in the field of nuclear standardization on national, European and international level with the background of the German 'Energiewende'

International Nuclear Information System (INIS)

Winkler, Janine

2014-01-01

Participation in standardization in the nuclear energy field in Germany is still very high, because the involved parties have recognized that standards in the context of the energy transition in Germany will remain very important. However, in the last few years, international standardization has been carried out without German participation. Existing international bodies are currently greatly influenced by the leadership of France, which is also reflected in the content of international standards. In addition, on French initiative, a European body (CEN/TC 430 'Nuclear energy, nuclear technologies, and radiological protection') has been set up with the remit to replace all national standards in Europe with international standards. The present article summarizes this development and offers an overview for German experts on how they can respond to this trend. (orig.)

Social and economic implications of the installation of nuclear plants

International Nuclear Information System (INIS)

Olivetti, F.A.

1981-01-01

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

Adaptation of high pressure water jets with abrasives for nuclear installations dismantling

International Nuclear Information System (INIS)

Rouviere, R.; Pinault, M.; Gasc, B.; Guiadeur, R.; Pilot, M.

1989-01-01

This report presents the work realized for adjust the cutting technology with high pressure water jet with abrasives for nuclear installation dismantling. It has necessited the conception and the adjustement of a remote tool and the realization of cutting tests with waste produce analysis. This technic can be ameliorated with better viewing systems and better fog suction systems

Border installations: the experience of Wackersdorf

International Nuclear Information System (INIS)

Heller, K.

1988-01-01

Following the decision of the Government of the Federal Republic of Germany to construct a fuel reprocessing plant (in the wider context of organising radioactive waste disposal) at Wackersdorf, 130 km from the Austrian border, actions were brought against the German constructor before Austrian and German courts. The author describes the mechanisms governing administrative procedures in both countries and their connection with public international law. He analyses the legal argumentations developed before the different courts as well as the debate on the concept of territoriality and border installations (NEA) [fr

Regulatory oversight report 2008 concerning nuclear safety in Swiss nuclear installations; Aufsichtsbericht 2008 ueber die nukleare Sicherheit in den schweizerischen Kernanlagen

Energy Technology Data Exchange (ETDEWEB)

NONE

2009-04-15

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.

HM Nuclear Installations Inspectorate: a bibliography of published work, 1962-1987

International Nuclear Information System (INIS)

McNichol, K.

1988-04-01

This bibliography contains references to published reports, conference papers and journal articles produced by individual members of the Nuclear Installations Inspectorate and the Inspectorate as a whole. The bibliography has been compiled from records held by the Health and Safety Executive Library and Information Service. All items have been indexed in HSELINE, HSE's publicly available database. The bibliography is arranged in 2 parts: by author(s) and by subject. (author)

Availability of nuclear fuels: an aspect of supply assurance. [German Federal Republic

Energy Technology Data Exchange (ETDEWEB)

Dolinski, U; Ziesing, H J [Deutsches Inst. fuer Wirtschaftsforschung, Berlin (F.R. Germany)

1976-08-01

The future supply possibilities for the Federal Republic of Germany with nuclear fuel are investigated by the German Institute for Economy Research in an expertise on 'the safety, price and environmental aspects in the energy supply'. The requirements of natural uranium in the Federal Republic of Germany are dealt with, as well as the world-wide assured and probable deposits of natural uranium in relation to the extraction costs. After indicating the restrictive changes in the export policy of the supplying countries, the international and national state of development of recycling is shown.

Order of 6 October 1977 defining the characteristics of each type of large nuclear installation

International Nuclear Information System (INIS)

1978-01-01

This Order, made by the French Minister of Industry, Commerce and Crafts and the Minister of Labour, lays down the characteristics of large nuclear installations which should be included in the document provided for under Section 10 of decree No. 75-306 of 28 April 1975 on the protection of workers against the hazards of ionizing radiation in large nuclear installations. These include inter alia the reactor type, its nominal power, the nature and cladding of the fuel, the rate of loading/unloading of the fuel, provisions to prevent criticality risks outside normal operation of the reactor, controlled areas and the measures for protection against ionizing radiation. The Order also lays down the characteristics for plants for the preparation and treatment of irradiated nuclear fuels as well as the characteristics of facilities for the storage, use, manufacture and transformation of radioactive substances, and the maximum permissible annual quantities of radioactive releases. (NEA) [fr

Comparison of costs of electricity generation based on nuclear energy and pit coal

International Nuclear Information System (INIS)

1981-01-01

Despite of a meanwhile considerable increase in costs of installation, especially of nuclear power stations, the differences in costs have increased in favour of nuclear electricity generation. The cost advantages are estimated 4 German Pfennig per kilowatt-hour in the base-load field for plants coming into operation at the end of this decade compared with the most profitable variant of pit coal utilization on which this investigation is based; compared to the use of German hard coal, assuming a relatively optimistic development of prices for domestic hard coal in the future, the cost advantage is estimated 8 German Pfennig per kilowatt-hour. The main reason is that in the past years the price for German hard coal as well as for imported coal considerably rose and for the future further increases have to be expected whereas the largest share of the costs of nuclear electricity generation doesn't increase, after the plant is completed. Considering the importance of the fuel costs within the total costs of electricity generation in coal power stations this must have its effects on the total result. These results also prove to be valid for a variation of important cost parameters. Only if the unlikely assumption that considerable variations of influences on costs - each unfavourable effecting nuclear electricity generation - would come together would prove to be true the economic efficiency of nuclear energy would be reduced or questioned. (UA) [de

Decision and Recommendation of the Steering Committee Concerning the Application of the Paris Convention to Nuclear Installations in the Process of Being Decommissioned

International Nuclear Information System (INIS)

2013-01-01

The NEA Steering Committee for Nuclear Energy adopted the Decision and Recommendation Concerning the Application of the Paris Convention to Nuclear Installations in the Process of Being Decommissioned on 30 October 2014. The purpose of this Decision and Recommendation is to provide updated technical exclusion criteria, replacing the 1990 criteria that were in force. The criteria are relatively conservative, and some nuclear installations in the process of decommissioning will not, at first, be eligible for exclusion. However, at some point during the decommissioning process, the nuclear installation would meet the criteria and could be excluded from the Paris Convention nuclear liability regime, relieving the operator from the obligation to have and maintain the specific, high level nuclear liability insurance coverage. The Decision and Recommendation's Appendix and Explanatory Note are included in the document

Regulatory oversight report 2007 concerning nuclear safety in Swiss nuclear installations; Aufsichtsbericht 2007 ueber die nukleare Sicherheit in den schweizerischen Kernanlagen

Energy Technology Data Exchange (ETDEWEB)

NONE

2008-04-15

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.

Nondestructive Evaluation of Functionally Graded Subsurface Damage on Cylinders in Nuclear Installations Based on Circumferential SH Waves

Directory of Open Access Journals (Sweden)

Zhen Qu

2016-01-01

Full Text Available Subsurface damage could affect the service life of structures. In nuclear engineering, nondestructive evaluation and detection of the evaluation of the subsurface damage region are of great importance to ensure the safety of nuclear installations. In this paper, we propose the use of circumferential horizontal shear (SH waves to detect mechanical properties of subsurface regions of damage on cylindrical structures. The regions of surface damage are considered to be functionally graded material (FGM and the cylinder is considered to be a layered structure. The Bessel functions and the power series technique are employed to solve the governing equations. By analyzing the SH waves in the 12Cr-ODS ferritic steel cylinder, which is frequently applied in the nuclear installations, we discuss the relationship between the phase velocities of SH waves in the cylinder with subsurface layers of damage and the mechanical properties of the subsurface damaged regions. The results show that the subsurface damage could lead to decrease of the SH waves’ phase velocity. The gradient parameters, which represent the degree of subsurface damage, can be evaluated by the variation of the SH waves’ phase velocity. Research results of this study can provide theoretical guidance in nondestructive evaluation for use in the analysis of the reliability and durability of nuclear installations.

Regulatory oversight of safety culture in nuclear installations - New IAEA developments

International Nuclear Information System (INIS)

Kerhoas, Anne; )

2012-01-01

Ms. Anne Kerhoas described the IAEA work on guidance for regulatory oversight of safety culture. She summarised the various IAEA, OECD/NEA and ANS meetings that have been held on the topic between 1995 and 2011. The IAEA has carried out two recent projects with the Bulgarian and Romanian regulatory bodies to develop a safety culture oversight program. The work was funded by the Norwegian government and has involved 30 experts from 17 different countries. Draft guidance for regulators on how to monitor licensee safety culture has also been produced (IAEA-TECDOC-DD1070). The document is intended to provide practical guidance on oversight strategies and is applicable to a wide range of nuclear installations, including nuclear power plants, fuel cycle facilities, research reactors and waste management facilities. A number of principles for regulatory oversight of safety culture were summarised. For example, the primary responsibility for safety remains with the licensee, safety culture oversight should be performed at all stages of the life cycle of the nuclear installation, and multiple data collection methods should be used. The overall approach to safety culture described in the draft IAEA Tech doc includes a range of approaches to build up a meaningful picture of the licensee's safety culture. These include interviews, observations, review of documents, review of events, discussions and surveys. The importance of ongoing discussion with the licensee throughout the process to develop a deeper shared understanding of issues was emphasised. The results of the Chester 2 workshop will be used as an input to finalization of the draft Tech Doc

Nuclear energy and ensuring the long-term energy supply in the German Federal Republic

International Nuclear Information System (INIS)

Koenig, H.H.

1975-01-01

The author reports on the papers read at the Reactor Conference in 1975. He pays special attention to the development of energy supply from nuclear stations, investigates the motives behind the growing resistance of the public, and shows that the acceptance procedure ensures the construction and operation of safe nuclear power installations. He also discusses the possibilities of improved energy utilisation, the climatic changes in coming generations, the characteristics of supply with nuclear district heating and process heat, as well as the state of building projects with high-temperature reactors and fast breeders. (orig.) [de

Regulations by the DFTCE concerning the Fund for the decommissioning of nuclear installations

International Nuclear Information System (INIS)

1985-02-01

These Regulations were made by the Federal Ministry of Transport, Communications and Energy in implementation of the Ordinance of 5 December 1983 establishing a fund for the decommissioning of nuclear installations. They specify the way in which nuclear operators must contribute to the fund and the method for calculating the contributions. The costs of decommissioning also include dismantling and disposal of the resulting waste. The Regulations entered into force retroactively, on 1 January 1984, on the same date as the 1983 Ordinance. (NEA) [fr

Practical decommissioning experience with nuclear installations in the European Community

International Nuclear Information System (INIS)

Skupinski, E.

1992-01-01

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

Criteria for guidance in the safety assessment of nuclear installations in the United Kingdom

International Nuclear Information System (INIS)

Gausden, R.; Fryer, D.R.H.

1977-01-01

There is an increasing appreciation of the need for a consistent approach to nuclear safety between various groups having an interest in safety and between various types of installation. Licensing for construction and ultimate approval to operate any nuclear installation depend in the United Kingdom upon a searching assessment of the design, construction and operation of the proposed plant. Criteria of the kind discussed in this paper have been used by the Nuclear Installations Inspectorate in this assessment process. From time to time they are subject to comments from other bodies in the U.K. One aim of the criteria is to set out the broad objectives that should be met regarding the magnitude of radiological consequences of accidents or normal operation. In addition, the criteria give guidance on the design philosophy for nuclear safety and the principles of fault evaluation. Criteria must be conceived so that while maintaining safety standards their application does not frustrate design and development. It is also important that undue formalism is not induced in the assessment process at the expense of inhibiting the judgement of safety assessors. A balance must, therefore, be struck between detailed and generalised guidance. It is also accepted that experience in the use and interpretation of criteria will indicate a need for improvement and additions: the criteria are, therefore, regarded as living rather than fixed statements which are expected to develop in response to any need for change in a safe direction that may arise. In developing them, the Inspectorate has drawn heavily upon the experience accumulated during its 16 years of operation and has also referred to criteria published by other organisations. The paper deals specifically with certain of the most important sections of the criteria and indicates the total range of subjects which need to be included in such criteria

Rise and fall of the German nuclear industry; Aufstieg und Fall der deutschen Atomwirtschaft

Energy Technology Data Exchange (ETDEWEB)

Radkau, Joachim [Bielefeld Univ. (Germany). Neuere Geschichte; Hahn, Lothar

2013-02-01

The book on the rise and fall of the German nuclear industry includes five chapters: (1) From the atomic project of the second world war to the ''peaceful atom''. (2) The ''peaceful atom'' as vision: the phase of speculations. (3) Achieved facts: the unplanned triumph of the light water reactor. (4) The internally suppressed risk excites the public. (5) From the creeping to the open fall.

German energy turnaround and Poland's start in nuclear power? A survey

International Nuclear Information System (INIS)

Knopp, Lothar; Gorski, Marek

2015-01-01

The book includes contributions from two meetings: 1. Meeting in Berlin, October 8,2014: Energy transition in Poland - historical background, development and actual situation; legal boundary conditions of the entry into nuclear power in Poland; ecologic and economic causes motivation for the atomic energy entry in Poland; promotion systems for renewable energy in Poland, current status and political background; construction of a nuclear power plant in Northern Poland site specific impacts and social assessment. Meeting in Stettin on November 5, 2014: Energy turnaround in Germany -German nuclear phaseout under consideration of EU legislation; ecologic and economic motivation for the energy turnaround in Germany; energy turnaround in Germany - new legal boundary conditions, especially the amendment to tue renewable energy law; contribution of the industry to the energy turnaround - taking the example waste management and waste incineration plants; fracking as a factor of the energy turnaround? - legal boundary conditions and ecologic risks; ecological, ethical and sociopolitical aspects of the energy turnaround in Germany and Poland.

German power options: Lack of clarity will be costly

International Nuclear Information System (INIS)

Schuelke, Christian

2010-01-01

The German environment minister Norbert Roettgen (CDU) revived the German debate about the future of nuclear power in February when he argued for a limited lifetime extension of Germany's nuclear plants. His statements created much dissent in his own party and with the coalition partner FDP. The government will not take a formal decision before the autumn, but the contradicting messages from inside the government send highly ambiguous signals to electricity utilities with investment plans in Germany. What does the German government want the companies to do?

Conceptual Design of On-line Based Licensing Review and Assesment System of Nuclear Installations and Nuclear Materials ('PRIBEN')

International Nuclear Information System (INIS)

Melani, Ai; Chang, Soon Heung

2008-01-01

At the present Indonesia has no nuclear power plant in operation yet, although it is expected that the first nuclear power plant will be operated and commercially available in around the year of 2016 to 2017 in Muria Peninsula. There are only three research reactors, one nuclear fuel fabrication plant for research reactors, and one experimental fuel fabrication plant for nuclear power, one isotope production facility and some other research facilities. All the facility is under Nuclear Energy Regulatory Agency (BAPETEN) controlling through regulation, licensing and inspection. The organizations operation submits licensing application to BAPETEN before utilizing the facility. According to the regulation before BAPETEN give license they perform review and assessment for the utility application. Based on the review and assessment result, BAPETEN may stipulate, reject, delay or terminate the license. In anticipation of expansion of the nuclear program in Indonesia, BAPETEN should have an integrated and updated system for review and asses the licensing application. For this reason, an expert system for the review and asses the licensing application, so-called PRIBEN (Perizinan Reaktor, Instalasi dan Bahan Nuklir/Licensing of Reactor, Nuclear Installations and Nuclear Materials), is developed which runs on the online-based reality environment

Planning and installing photovoltaic systems a guide for installers, architects and engineers

CERN Document Server

Deutsche Gesellschaft für Sonnenenergie (DGS)

2013-01-01

New third edition of the bestselling manual from the German Solar Energy Society (DGS), showing you the essential steps to plan and install a solar photovoltaic system. With a global focus, it has been updated to include sections on new technology and concepts, new legislation and the current PV market.Updates cover:new developments in inverter and module technologymarket situation worldwide and outlookintegration to the grid (voltage stabilization, frequency, remote control)new legal requirements for installation and planningoperational costs for dismantling and recyclingfeed-in managementnew requirements for fire protectionnew requirements in Europe for electric waste (Waste Electrical and Electronic Equipment, WEEE) and the restriction of the use of certain hazardous substances (RoHS).Also providing information on current developments in system design, economic analysis, operation and maintenance of PV systems, as well as new software tools, hybrid and tracking systems.An essential manual for installers, e...

European Community (Radiological and Nuclear Medicine Installations) Regulations, 1998. Statutory Instrument S.I. No. 250 of 1998

International Nuclear Information System (INIS)

1998-01-01

These regulations establish the criteria of acceptability to be met for radiological installations and nuclear medicine installations. The regulations implement the provisions of EC Directive 84/466 Euratom of 3 September 1984 laying down the basic measures for radiation protection of persons undergoing medical examinations or treatment and to provide protection for workers and the general public. (author)

ASN guide project. Protection of base nuclear installations against external flooding

International Nuclear Information System (INIS)

2010-01-01

This guide aims at defining criteria to be taken into account to assess risks of flooding of a nuclear installation in case of external flooding, at proposing an acceptable method to assess such risks, at listing recommendations to define protection means adapted to the peculiarities of the flood risk and implemented by the operators with respect to the life phases of the installation, and in taking the climate change into account. The first part proposes an approach allowing the identification of reference situations which are to be taken into account for the flood risk. The second part deals with the quantification of parameters which characterize physical phenomena associated with these situations. The third part identifies the peculiarities of the flood risk as well as the guiding principles for designing options and protection mean selection with respect to a given flood risk

Change in plan for installation of nuclear reactor in No.1 atomic powered vessel of Japan Atomic Energy Research Institute (change in purpose of use and in method for nuclear reactor installation and spent fuel disposal) (report)

International Nuclear Information System (INIS)

1987-01-01

This report, compiled by the Nuclear Safety Commission to be submitted to the Prime Minister, deals with studies concerning some changes in the plan for the installation of a nuclear reactor in the No.1 atomic powered vessel to be constructed under the Japan Atomic Energy Research Institute (changes in the purpose of its use and in the methods for the nuclear reactor installation and spent fuel disposal). The conclusions of and procedures for the examination and evaluation are presented and then detailes of the studies are described. The study on the location requirements for the incidental land facilities at Sekinehama covers various conditions concerning the location, geology, earthquakes, meteorology, hydrology and social environment. The study on the safety design of the nuclear reactor facilities deals with the reactor, fuel handling facilities and other auxiliary facilities, as well as various land facilities to be constructed at Sekinehama including the reactor facilities and other facilities for fuel handling, waste disposal and protection and management of radioactive rays. Evaluation of possible radiation emission is shown and the accident analysis is also addressed. (Nogami, K.)

Assessments of conditioned radioactive waste arisings from existing and committed nuclear installations and assuming a moderate growth in nuclear electricity generation - June 1985

International Nuclear Information System (INIS)

Fairclough, M.P.; Goodill, D.R.; Tymons, B.J.

1985-03-01

This report describes an assessment of conditioned radioactive waste arisings from existing and committed nuclear installations, DOE Revised Scheme 1, and from an assumed nuclear power generation scenario, DOE Revised Scheme 3, representing a moderate growth in nuclear generation. Radioactive waste arise from 3 main groups of installations and activities: i. existing and committed commercial reactors; ii. fuel reprocessing plants, iii. research, industrial and medical activities. Stage 2 decommissioning wastes are considered together with WAGR decommissioning and the 1983 Sea Dump Consignment. The study uses the SIMULATION 2 code which models waste material flows through a system of waste treatment and packaging to disposal. With a knowledge of the accumulations and average production rates of untreated wastes and their isotopic compositions (or total activities), the rates at which conditioned wastes become available for transportation and disposal are calculated, with specific activity levels. The data for the inventory calculations have previously been documented. Some recent revisions and assumptions concerning future operation of nuclear facilities are presented in this report. (author)

Childhood leukaemia near British nuclear installations: Methodological issues and recent results

International Nuclear Information System (INIS)

Bithell, J. F.; Keegan, T. J.; Kroll, M. E.; Murphy, M. F. G.; Vincent, T. J.

2008-01-01

In 2008, the German Childhood Cancer Registry published the results of the Kinderkrebs in der Umgebung von Kernkraftwerken (KiKK) study of childhood cancer and leukaemia around German nuclear power stations. The positive findings appeared to conflict with the results of a recent British analysis carried out by the Committee on Medical Aspects of Radiation in the Environment (COMARE), published in 2005. The present paper first describes the COMARE study, which was based on data from the National Registry of Children's Tumours (NRCT); in particular, the methodology used in this study is described. Although the results of the COMARE study were negative for childhood leukaemia, this apparent discrepancy could be accounted for by a number of differences in approach, especially those relating to the distances from the power stations and the ages of the children studied. The present study was designed to match the KiKK study as far as possible. The incidence observed (18 cases within 5 km against 14.58 expected, p = 0.21) was not significantly raised. The risk estimate for proximity in the regression fitted was actually negative, though the confidence intervals involved are so wide that the difference from that reported in the KiKK study is only marginally statistically significant (p = 0.063). (authors)

Application and development of dismantling technologies for decommissioning of nuclear installations

International Nuclear Information System (INIS)

Bach, W.; Kremer, G.; Ruemenapp, T.

2006-01-01

The decommissioning of nuclear installations poses a challenge to high performance underwater cutting technologies because of complex limiting conditions, like radioactive contamination, accessibility, geometry of work piece, material thickness and composition. For the safe dismantling of the moderator tank and the thermal shield of the Multi-purpose Research Reactor (MZFR) Karlsruhe the development and the use of thermal cutting tools will be demonstrated, in this case the underwater plasma arc cutting and the contact arc metal cutting (CAMC). (orig.)

World survey of nuclear power

International Nuclear Information System (INIS)

Rippon, S.

1988-01-01

In 1987, nuclear power was still expanding worldwide, but in a climate of increasing short-term uncertainty. During 1987, 23 new reactors started supplying electricity, for a total of 415, of which 13 were prevented from producing. Total installed capacity was 295 GWe. A further 111 power reactors, to supply 102 GWe, were under construction. The widely differing situations in the following countries are discussed: USA, Italy, France, Belgium, F.R. Germany, UK, China, Japan, Taiwan, S. Korea, India, USSR, Bulgaria, Czechoslovakia, German D.R., Hungary, Romania, Argentina

Technological progress, safety, and the guardian role of inspection (with Appendix: Antecedants of the Nuclear Installation Inspectorate)

International Nuclear Information System (INIS)

Critchley, O.H.

1981-01-01

Technological progress inevitably brings hazards which must be inspected to reduce the occurence of any attendant risks to a minimum. Although the responsibility for regulatory safety inspection in Britain is spread amongst a number of specialist inspectorates, it is arguably the most fully developed, efficient and satisfactorily operating regime of its kind, this being especially true for commercial nuclear installations. The latter aspect is a complex mix of engineering, legal and managerial practices which has been modelled on the developments in safety technology in atomic energy in the Manhattan Project and in the UKAEA, among others, and on to the present Nuclear Installations Inspectorate. (U.K.)

Analysis of normative requirements for the development and implementation of a quality management system in Brazilian nuclear installations and activities

International Nuclear Information System (INIS)

Kibrit, Eduardo

2008-01-01

The present work identifies, characterizes and analyses the normative requirements for the development and implementation of quality management systems in Brazilian nuclear installations and activities. The requirements established in standards IAEA GS-R-3, IAEA GS-G-3.1, IAEA DS 349, NBR ISO 9001:2000 e CNEN-NN-1.16 are critically analyzed. A correlation matrix of the applicable standards is presented and the related topics among them are identified. The standards IAEA GS-R-3, IAEA GS-G-3.1 and IAEA DS 349 define general requirements for establishing, implementing, assessing and continually improving an integrated management system in nuclear installations and activities, in IAEA member countries. The standard NBR ISO 9001:2000 establishes general requirements for the implementation of a quality management system in all kinds of organizations. The standard CNEN NN-1.16 establishes the regulating requirements for the quality assurance systems and programs of nuclear installations, for licensing and authorization for operation of these installations in Brazil. The standard IAEA GS-R-3 that replaces the code IAEA 50-C-Q introduces the concept of 'Integrated Management System' for the nuclear area, in preference to the concepts of 'Quality Assurance' and 'Quality Management'. This new approach is aligned with the current tendency incorporating requirements of quality, safety, health, environment, security, economics and other in a unique management system. Examples of quality management systems implemented by Brazilian nuclear organizations and by nuclear organizations outside Brazil are analyzed and considered in the discussion of results. (author)

Performance of HEPA Filter Medium under Accidental Conditions in Nuclear Installations

International Nuclear Information System (INIS)

El-Fawal, M.M.

2011-01-01

High Efficiency Particulate Air filters (HEPA Filters) are the main components in ventilation or confinement system for the retention of radioactive particles in nuclear installations. During abnormal conditions or accidents (e.g. fire accident, criticality in a nuclear fuel cycle facility and LOCA in power reactors) the resulting heat, smoke and humidity affect to a large extent the performance of HEPA filters. As a part of a research programme aims at the evaluation and improvement of the performance of HEPA filter media during abnormal conditions, the effect of elevated temperatures up to 400 degree C on the resistance of medium to penetration of water under pressure has been investigated. The test results showed that the resistance of the medium to penetration of water decreases with increase in temperature and thermal exposure time. This could be attributed to burnout of the organic binder used to improve the resistance of the medium to the penetration of water. The results also showed that at 400 degree C the resistance of the medium to the penetration of water disappeared. This was confirmed by inspection of the filter medium samples after exposure to high temperature using a scanning electron microscope. The inspection of the medium samples showed that the organic binder in the medium was deformed and finally collapsed at 400 degree C. Also, a best estimate model for the relation of filter medium resistance to water penetration under elevated temperature has been implemented. The results of this study can help in establishing a regulatory operating limit conditions (OLCs) for HEPA filter operation at high temperatures conditions in nuclear installations

Performance of HEPA Filter Medium under Accidental Conditions in Nuclear Installations

International Nuclear Information System (INIS)

ElFawal, M.M.

2009-01-01

High Efficiency Particulate Air filters (HEPA Filters) are the main components in ventilation or confinement system for the retention of radioactive particles in nuclear installations. During abnormal conditions or accidents (e.g. fire accident, criticality in a nuclear fuel cycle facility and LOCA in power reactors) the resulting heat, smoke and humidity affect to a large extent the performance of HEPA filters. As a part of a research programme aims at the evaluation and improvement of the performance of HEPA filter media during abnormal conditions, the effect of elevated temperatures up to 400 degree C on the resistance of medium to penetration of water under pressure has been investigated. The test results showed that the resistance of the medium to penetration of water decreases with increase in temperature and thermal exposure time. This could be attributed to burnout of the organic binder used to improve the resistance of the medium to the penetration of water. The results also showed that at 400 degree C the resistance of the medium to the penetration of water disappeared. This was confirmed by inspection of the filter medium samples after exposure to high temperature using a scanning electron microscope. The inspection of the medium samples showed that the organic binder in the medium was deformed and finally collapsed at 400 degree C. Also, a best estimate model for the relation of filter medium resistance to water penetration under elevated temperature has been implemented. The results of this study can help in establishing a regulatory operating limit conditions (OLCs) for HEPA filter operation at high temperatures conditions in nuclear installations.

Maintaining the design Integrity of nuclear installations throughout their operating life. INSAG-19. A report by the International Nuclear Safety Advisory Group (Russian Edition)

International Nuclear Information System (INIS)

2015-01-01

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

The German radiation protection standards

International Nuclear Information System (INIS)

Becker, Klaus; Neider, Rudolf

1977-01-01

The German Standards Institute (DIN Deutsches Institut fuer Normung, Berlin) is engaged in health physics standards development in the following committees. The Nuclear Standards Committee (NKe), which deals mainly with nuclear science and technology, the fuel cycle, and radiation protection techniques. The Radiology Standards Committee (FNR), whose responsibilities are traditionally the principles of radiation protection and dosimetry, applied medical dosimetry, and medical health physics. The German Electrotechnical Commission (DKE), which is concerned mostly with instrumentation standards. The Material Testing Committee (FNM), which is responsible for radiation protection in nonmedical radiography. The current body of over one hundred standards and draft standards was established to supplement the Federal German radiation protection legislation, because voluntary standards can deal in more detail with the specific practical problems. The number of standards is steadily expanding due to the vigorous efforts of about thirty working groups, consisting of essentially all leading German experts of this field. Work is supported by the industry and the Federal Government. A review of the present status and future plans, and of the international aspects with regard to European and world (ISO, etc.) standards will be presented

Availability of nuclear fuels: one aspect of the reliability of supply. [German Federal Republic

Energy Technology Data Exchange (ETDEWEB)

Dolinski, U; Ziesing, H J [Deutsches Inst. fuer Wirtschaftsforschung, Berlin (F.R. Germany)

1976-09-01

In connection with the future supply of nuclear fuels to the Federal Republic of Germany the authors discuss the problems which arise. They describe the future development of the demand for natural uranium and the work involved in separation and deal with the possibilities of meeting the demand. They pay particular attention to the changed market situation and to the policies of the countries which produce uranium. The article is a detailed examination of the report by the German Institute for Economic Research (DIW) on aspects of the reliability of supply to the electricity supply industry in the Federal Republic of Germany, which was prepared under the aegis of the Bavarian Ministry for Economic and Transport. This investigation will be published, omitting the regional aspects, towards the middle of 1976, by the German Institute for Economic Research under the title 'Reliability, price and environmental protection aspects of energy supply'.

Preparation of off-site emergency preparedness plans for nuclear installations

International Nuclear Information System (INIS)

1999-10-01

Safety of public, occupational workers and the protection of environment should be assured while activities for economic and social progress are pursued. These activities include the establishment and utilisation of nuclear facilities and use of radioactive sources. This document is issued as a lead document to facilitate preparation of specific site manuals by the Responsible Organisation for emergency response plans at each site to ensure their preparedness to meet any eventuality due to site emergency in order to mitigate its consequences on the health and safety of site personnel. It takes cognizance of an earlier AERB publication on the subject: Safety Manual on Off-Site Emergency Plan for Nuclear Installations, AERB/SM/NISD-2, 1988 and also takes into consideration the urgent need for promoting public awareness and drawing up revised emergency response plans, which has come out in a significant manner after the accidents at Chernobyl and Bhopal

Earthquake experience and seismic qualification by indirect methods in nuclear installations

International Nuclear Information System (INIS)

2003-01-01

In recent years, many operational nuclear power plants around the world have conducted seismic re-evaluation programmes either as part of a review of seismic hazards or to comply with best international nuclear safety practices. In this connection, Member States have called on the IAEA to carry out several seismic review missions at their plants, primarily those of WWER and RBMK design. One of the critical safety issues that arose during these missions was that of seismic qualification (determination of fitness for service) of already installed plant distribution systems, equipment and components. The qualification of new components, equipment and distribution systems cannot be replicated for equipment that is already installed and operational in plants, as this process is neither feasible nor appropriate. For this reason, seismic safety experts have developed new procedures for the qualification of installed equipment: these procedures seek to demonstrate that installed equipment, through a process of comparison with new equipment, is apt for service. However, these procedures require large sets of criteria and qualification databases and call for the use of engineering judgement and experience, all of which open the door to wide margins of interpretation. In order to guarantee a sound technical basis for the qualification of in-plant equipment, currently applied to 70% to 80% of all plant equipment, the regulatory review of this type of qualification process calls for a detailed assessment of the technical procedures applied. Such an assessment is the first step towards eliminating the risk of large differences in qualification results between different plants, operators and countries, and guaranteeing the reliability of seismic re-evaluation programmes. Bearing this in mind, in 1999, the IAEA convened a seminar and technical meeting on seismic qualification under the auspices of the IAEA Technical Co-operation programme. Altogether 66 senior experts attended the

Safety culture in nuclear installations: Summary of an international topical meeting

International Nuclear Information System (INIS)

Carnino, A.; Derrough, M.; Weimann, G.

1996-01-01

An international topical meeting, Safety Culture in Nuclear Installations, was organized by the American Nuclear Society (ANS) Austria Local Section, cosponsored by the ANS Nuclear Reactor Safety and Human Factors Divisions in cooperation with the Nuclear Energy Agency of the Organization for Economic Cooperation and Development (NEA/OECD) and held in Vienna April 24-28, 1995. Some 250 experts from 30 different countries and organizations took part in the 85 paper presentations and two workshops. The concept of safety culture was initially used in the first International Nuclear Safety Advisory Group (INSAG) report on the Chernobyl accident analysis report in 1986. Although some elements of safety culture have been used over the years in nuclear safety activities, the new phrase safety culture and the concept were found interesting as highlighting the 'soft' aspects of safety and as encompassing more than human errors. Unfortunately, for many years it was used more in the way of identifying lack of safety culture. Conscious of this application, INSAG further developed the safety culture concept in the INSAG 4 report: The report contains a definition, the universal aspects of safety culture, the two main components of safety culture management and individual behaviour, and performance indicators of a good safety culture. This report is now quite famous and adopted with some additions or complementary definitions by many institutes and organizations for their daily activities

Regulatory Oversight of Safety Culture in Nuclear Installations

International Nuclear Information System (INIS)

2013-03-01

. Accordingly, this publication provides practical guidance on developing and implementing strategies and processes for regulators to employ to monitor a licensee's safety culture in nuclear installations and in related activities. It is based on a compilation of state of the art international and national efforts.

Plant life extensions for German nuclear power plants? Controversial discussion profit taking of nuclear power plant operators

International Nuclear Information System (INIS)

Matthes, Felix C.

2009-10-01

The discussion on the plant life extensions for German nuclear power plants beyond the residual quantity of electricity particularly focus on three aspects: Effects for the emission of carbon dioxide as a greenhouse gas; Development of the electricity price for which a reduction or attenuation is postulated due to a plant life extension; Skimming of additional profits at operating companies and their use in the safeguarding of the future (development of renewable energies, support of energy efficiency, promotion of the research, consolidation of the public budget, and so on). Under this aspect, the author of the contribution under consideration reports on the profit taking of nuclear power plant operators. The presented analysis considers three aspects: (a) Specification of the quantity structures for the investigated model of plant life extension; (b) The decisive parameter is the revenue situation and thus the price development for electricity at wholesale markets; (c) Determination and evaluation of the course in time of the profit taking.

The year 2000 embedded systems problem to maintain the safety of nuclear installations

International Nuclear Information System (INIS)

Ardisasmita, M.S.

1999-01-01

The Y2K problem may impact on nuclear installations in a number of ways because embedded systems are used in nuclear routine operation, monitoring and control system. The very simplest embedded systems are capable of performing only a single function or set of functions to meet a single predetermined purpose. In more complex systems the functioning of the embedded system is determined by an application program that enables the embedded system to be used for a particular purpose in a specific application. The simplest devices consist of a single microprocessor which may itself be packaged with other chips in a hybrid system or Application Specific Integrated Circuit (ASIC). Its input comes from a detector or sensor and its output goes to a switch or activator which may start or stop the operation of a positioning motors or, by operating a valve, may control the flow of cooling system to reactor core. Embedded systems in our organization are also be found in Batan security systems. These include systems for the security of buildings and premises, and in the communication systems on which these depend. In the enclosed paper we demonstrate the use of analytic model and reliability analysis. The subject of this reliability test is to detect the components of the embedded system with PLC's that could fail on Y2K problem in nuclear installation and safety system. (author)