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Sample records for nuclear installations annual

  1. 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

  2. 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

  3. 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.

  4. 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

  5. The community's research and development programme on decommissioning of nuclear installations. Fourth annual progress report 1988

    International Nuclear Information System (INIS)

    Anon.

    1989-01-01

    This is the fourth annual progress report on the European Community's programme (1984-88) of research on the decommissioning of nuclear installations. It shows the status of the programme at 31 December 1988. The fourth progress report describes the objectives, scope and work programme of the 72 research contracts concluded, as well as the progress of work achieved and the results obtained in 1988

  6. The Community's research and development programme on decommissioning of nuclear installations. Third annual progress report 1987

    International Nuclear Information System (INIS)

    1988-01-01

    This is the third annual progress report of the European Community's programme (1984-88) of research on the decommissioning of nuclear installations. It shows the status of the programme on 31 December 1987. The third progress report describes the objectives, scope and work programme of the 69 research contracts concluded, as well as the progress of work achieved and the results obtained in 1987

  7. The Community's research and development programme on decommissioning of nuclear installations (1989-1993). Annual progress report 1991

    International Nuclear Information System (INIS)

    1992-01-01

    This is the second annual progress report of the European Community's programme (1989-93) of research on decommissioning of nuclear installations. It shows the status of the programme on 31 December 1991. This second progress report summarizes the objectives, scope and work programme of the 76 research contracts concluded, as well as the progress of work achieved and the results obtained in 1991

  8. The Community's research and development programme on decommissioning of nuclear installations. Second annual progress report (year 1986)

    International Nuclear Information System (INIS)

    1987-01-01

    This is the second annual progress report of the European Community's programme (1984-88) of research on the decommissioning of nuclear installations. It shows the status of the programme on 31 December 1986. This second progress report describes the objectives, scope and work programme of the 58 research contracts concluded, as well as the progress of work achieved and the results obtained in 1986

  9. 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.

  10. 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

  11. 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

  12. 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.

  13. 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.

  14. 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

  15. Nuclear Installations Act 1965

    International Nuclear Information System (INIS)

    1965-01-01

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

  16. 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)

  17. 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

  18. 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

  19. The insurance of nuclear installations

    International Nuclear Information System (INIS)

    Francis, H.W.

    1977-01-01

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

  20. Nuclear installations

    International Nuclear Information System (INIS)

    1998-01-01

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

  1. Nuclear installations

    International Nuclear Information System (INIS)

    2001-01-01

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

  2. 2010 ANNUAL MEETING ON NUCLEAR TECHNOLOGY. Pt. 3. Section reports

    International Nuclear Information System (INIS)

    Arnold, Uwe; Baumann, Erik; Fischer, Ulrich; Bohnstedt, Angelika; Gehring, Michael; Roedig, Manfred; Willschuetz, Hans-Georg; Goers, Stefan; Schoenfelder, Christian

    2010-01-01

    Summary report on these 6 - out of 12 - Sessions of the Annual Conference on Nuclear Technology held in Berlin on May 3 to 6, 2010: - Decommissioning of Nuclear Installations (Session 7), - Fusion Technology (Session 8), - Energy Industry and Economics (Session 10), - Radiation Protection (Session 11), - New Build and Innovations (Session 12), and - Education, Expert Knowledge, Know-how-Transfer (Session 13). The other Sessions: - Reactor Physics and Methods of Calculation (Session 1), - Thermodynamics and Fluid Dynamics (Session 2), - Safety of Nuclear Installations - Methods, Analysis, Results (Session 3), - Front End and Back End of the Fuel Cycle, Radioactive Waste, Storage (Session 4), - Front End of the Fuel Cycle, Fuel Elements and Core Components (Session 5), - Operation of Nuclear Installations (Session 6) have been covered in atw issues 10 and 11 (2010). (orig.)

  3. 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

    , including post-closure monitoring of such repositories; g) expenditures connected with Fund activities up to a maximum of 0,3% of annual Fund revenues. The Minister appoints Fund Council as his advisory body for generation and utilisation of Fund resources. Council members are appointed and recalled by the Minister, in particular from among experts in the fields of nuclear energy, health, environmental protection, economy and local government. The Minister at Council's suggestion decides upon granting of resources from the Fund. The operator of nuclear installations submits applications until 15 June every year. Grants from the Fund may only be used for purposes for which they were granted. Audits of Fund management are the responsibility of Ministry of Finances of the Slovak Republic. The Prognosis for full financial support of back end of nuclear fuel cycle is compiled every other year for long-term phase (e.g. year 2130). Sources and utilisation of financial means are analysed in the prognosis, which is approved by the Government of the Slovak Republic. Outcome of this analysis defines financial contributions of operators of nuclear installations for the Fund

  4. 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

  5. Annual report 1993 by the Rossendorf Society of Nuclear Engineering and Analysis

    International Nuclear Information System (INIS)

    Haefele, W.

    1994-03-01

    The second annual report contains, apart from the business report and the organigram, priorities and results achieved in the special fields of nuclear installations (decommissioning and disposal), nuclear waste management (radioactive wastes), nuclear analyses and rehabilitation, radiopharmaceuticals, and safety and radiation protection. (HP) [de

  6. 2010 ANNUAL MEETING ON NUCLEAR TECHNOLOGY. Pt. 4. Section reports

    International Nuclear Information System (INIS)

    Berlepsch, Thilo v.; Hering, Wolfgang

    2011-01-01

    Summary report on 2 Sessions of Section: - New Build and Innovations (Section 12) of the ANNUAL MEETING On NUCLEAR TECHNOLOGY held in Berlin on May 4 to 6, 2010. The other Sections 'Reactor Physics and Methods of Calculation (Section 1)', 'Thermodynamics and Fluid Dynamics (Section 2)', 'Safety of Nuclear Installations - Methods, Analysis, Results (Section 3)', 'Front End and Back End of the Fuel Cycle, Radioactive Waste, Storage (Section 4)', 'Front End of the Fuel Cycle, Fuel Elements and Core Components (Section 5)', 'Operation of Nuclear Installations (Section 6)', 'Decommissioning of Nuclear Installations (Section 7)', 'Fusion Technology (Section 8)', 'Energy Industry and Economics (Section 10)', 'Radiation Protection (Section 11)', 'New Build and Innovations (Session New Build and Innovations, Section 12)', and 'Education, Expert Knowledge, Know-how-Transfer (Section 13)' have been covered in atw issues 10, 11 and 12 (2010). (orig.)

  7. 2009 annual meeting on nuclear technology. Pt. 1. Section reports

    International Nuclear Information System (INIS)

    Schaffrath, Andreas; Hartmann, Miks; Hoffmann, Petra Britt; Stieglitz, Robert; Hoehne, Thomas; Weiss, Frank-Peter; Hollands, Thorsten; Sanchez Espinoza, Victor Hugo; Tietsch, Wolfgang; Sonnenburg, H.G.

    2009-01-01

    Summary report on these 3 - out of 13 - Sessions of the Annual Conference on Nuclear Technology held in Dresden on May 12 to 14, 2009: Thermodynamics and Fluid Dynamics (Session 2), Safety of Nuclear Installations - Methods, Analysis, Results (Session 3), and, Front End of the Fuel Cycle, Fuel Elements and Core Components (Session 4). The other Sessions Reactor Physics and Methods of Calculation (Session 1), Front End and Back End of the Fuel Cycle, Radioactive Waste, Storage (Session 5), Operation of Nuclear Installations (Session 6), Decommissioning of Nuclear Installations (Session 7), Fusion Technology (Session 8), Research Reactors, Neutron Sources (Session 9), Energy Industry and Economics (Session 10), Radiation Protection (Session 11), New Build and Innovations (Session 12), and Education, Expert Knowledge, Know How Transfer (Session 13) have be covered in reports in further issues of atw. (orig.)

  8. Safety of nuclear installations in Slovakia

    International Nuclear Information System (INIS)

    1998-01-01

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

  9. Professional operation and management of nuclear island installation

    International Nuclear Information System (INIS)

    Ma Limin

    2011-01-01

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

  10. Annual Report 2007. Nuclear Regulatory Authority

    International Nuclear Information System (INIS)

    2008-01-01

    The present Annual Report of Activities of the Nuclear Regulatory Authority (ARN), prepared regularly from the creation as independent institution, describes across tree parts and seven annexes the activities developed by the organism during 2007. The main topic are: the organization and the activity of the ARN; the regulatory standards; the licensing and inspection of nuclear power plants and critical facilities; the emergency systems; the occupational surveillance; the environmental monitoring; improved organizational. Also, this publication have annexes with the following content: regulatory documents; inspections to medical, industrial and training installations; regulatory guides; measurement and evaluation of the drinking water of Ezeiza.

  11. Annual meeting on nuclear technology 2005. Proceedings

    International Nuclear Information System (INIS)

    2005-03-01

    The proceedings of the annual meeting on nuclear technology 2005 covers the following issues: (1) reactor physics and methods of calculation: design and transients; method development and validation; (2): thermodynamics and fluid dynamics: analytical thermohydraulics for existing reactors; experiments and operational behavior; analytical methods for innovative reactors; (3) Safety of nuclear installations - methods, analysis, results: special problems; PSA and in-vessel phenomena; ex-vessel phenomena; (4) front end and back end of the fuel cycle, radioactive waste, storage: intermediate storage of fuel elements, waste treatment, (5) fuel elements and core components: fuel elements, new methods in the interpretation, manufacturing and service; (6) operation of nuclear installations: experience with the operation of NPPs; management systems, digital instrumentation and control of NPPs revision management; (7) decommissioning of nuclear installations: concepts and strategies for decommissioning and dismantling; experiences with decommissioning projects; (8) fusion technology: fusion facilities; materials and test facility; cryo technique and simulations; (9) research reactors: building new and backfitting of existing research reactors; current development; dismantling of research reactors; (10) advanced reactor concepts, energy systems, energy economics; (11) communication with the public; (12) component materials, fabrication and service behavior: degradation effects of component materials; component behavior; (13): radiation protection: PSA and in-vessel phenomena, ex-vessel phenomena.

  12. Civilian protection and Britain's commercial nuclear installations

    International Nuclear Information System (INIS)

    1981-01-01

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

  13. 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

  14. Nuclear installations and their environment

    International Nuclear Information System (INIS)

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

    2002-01-01

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

  15. 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

  16. Council for Nuclear Safety annual report 1988/89

    International Nuclear Information System (INIS)

    1989-01-01

    An overview of the structure, duties and activities of the Council for Nuclear Safety during 1988/1989 is presented in this annual report. It is the Council's first duty to ensure that all aspects - siting, design, construction and operation - in all areas of the nuclear industry, from mining of the nuclear ores to the ultimate disposal of nuclear waste, are conducted in such a manner that the potential for harm associated with the radioactive properties of the materials involved is kept under proper control. In order to achieve this the Council is responsible for the establishment and application of safety standards, the issuing of nuclear licenses and the evaluation and inspection of nuclear installations to ensure that the licensees are complying with the conditions laid down in the license and that they are adhering to all the safety criteria established by the Council. Other information contained in this annual report is, inter alia, the financial statements of the Council, the meetings attended by members of the Council and the administrative and management aspects of the Council. 8 figs

  17. Annual Report 2009. Nuclear Regulatory Authority

    International Nuclear Information System (INIS)

    2010-01-01

    The present Annual Report of Activities of the Nuclear Regulatory Authority (ARN), prepared regularly from the creation as independent institution, describes across four parts and seven annexes the activities developed by the organism during 2009. The main topic are: the organization and the activity of the ARN; the regulatory standards; the licensing and inspection of nuclear power plants and critical facilities; the emergency systems; the environmental monitoring; the occupational surveillance; the training and the public information; improved organizational and budgetary developments. Also, this publication have annexes with the following content: regulatory documents; inspections to medical, industrial and training installations; regulatory guides; measurement and evaluation of the drinking water of Ezeiza.

  18. The safety of nuclear installations

    International Nuclear Information System (INIS)

    1993-01-01

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

  19. 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

  20. 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)

  1. Decommissioning and dismantling of nuclear installations

    International Nuclear Information System (INIS)

    Pelzer, N.

    1993-01-01

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

  2. 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.

  3. 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

  4. 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)

  5. 2008 annual meeting on nuclear technology. Pt. 1. Section reports

    International Nuclear Information System (INIS)

    Dagan, Ron; Sanchez Espinoza, Victor Hugo; Faber, Wolfgang; Berlepsch, Thilo v.; Spann, Holger; Schaffrath, Andreas; Schubert, Bernd; Rieger, Udo; Christ, Bernhard G.; Gulden, Werner; Bogusch, Edgar

    2008-01-01

    Summary report on these 5 - out of 11 - Sections of the Annual Conference on Nuclear Technology held in Hamburg on May 27-29, 2008: - Reactor Physics and Methods of Calculation - Thermodynamics and Fluid Dynamics - Safety of Nuclear Installations - Methods, Analysis, Results - Front End and Back End of the Fuel Cycle, Radioactive Waste, Storage - Fusion Technology. Other Sections will be covered in reports in further issues of atw. (orig.)

  6. 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

  7. Annual Report 2007. Nuclear Regulatory Authority; Informe Anual 2007. Autoridad Regulatoria Nuclear

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2008-07-01

    The present Annual Report of Activities of the Nuclear Regulatory Authority (ARN), prepared regularly from the creation as independent institution, describes across tree parts and seven annexes the activities developed by the organism during 2007. The main topic are: the organization and the activity of the ARN; the regulatory standards; the licensing and inspection of nuclear power plants and critical facilities; the emergency systems; the occupational surveillance; the environmental monitoring; improved organizational. Also, this publication have annexes with the following content: regulatory documents; inspections to medical, industrial and training installations; regulatory guides; measurement and evaluation of the drinking water of Ezeiza.

  8. 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

  9. 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

  10. 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

  11. Estimating the whole-body exposure annual dose of radiation workers of petroleum nuclear well logging

    International Nuclear Information System (INIS)

    Tian Yizong; Gao Jianzheng; Liu Wenhong

    2006-01-01

    Objective: By imitating experiment of radioactive sources being installed, to estimate the annual whole-body exposure dose of radiation workers of petroleum nuclear determining wells; Methods: To compre the values of the theory, imitating experiment and γ individual dose monitor calculations. Results: The three values measured above tally with one anather. Conclusion: The annual whole-body exposure doses of radiation workers of petroleum nuclear determining wells are no more than 5 mSv. (authors)

  12. Annual Report 2010. Nuclear Regulatory Authority

    International Nuclear Information System (INIS)

    2010-01-01

    The present Annual Report of Activities of the Nuclear Regulatory Authority (ARN), prepared regularly from the creation as independent institution, describes across six chapters and seven annexes the activities developed by the organism during 2010. The main topic are: institutional issues; regulatory guides and standards; argentinean nuclear regulatory system; quality assurance of the ARN; the institutional communications; the licensing and inspection of nuclear power plants and critical facilities; the emergency systems; the safeguards and the physical protection; the environmental control; the institutional relations; the training and the public information. Also, this publication have annexes with the following content: the regulatory framework; regulatory documents; inspections to medical, industrial and training installations; measurement and evaluation of the drinking water of Ezeiza; international expert's report on the application of the international standards of radiological protection of the public in the zone of the Ezeiza Atomic Center; ethical code

  13. Annual Report 2011. Nuclear Regulatory Authority

    International Nuclear Information System (INIS)

    2011-01-01

    The present Annual Report of Activities of the Nuclear Regulatory Authority (ARN), prepared regularly from the creation as independent institution, describes across six chapters and seven annexes the activities developed by the organism during 2011. The main topic are: institutional issues; regulatory guides and standards; argentinean nuclear regulatory system; quality assurance of the ARN; the institutional communications; the licensing and inspection of nuclear power plants and critical facilities; the emergency systems; the safeguards and the physical protection; the environmental control; the institutional relations; the training and the public information. Also, this publication have annexes with the following content: the regulatory framework; regulatory documents; inspections to medical, industrial and training installations; measurement and evaluation of the drinking water of Ezeiza; international expert's report on the application of the international standards of radiological protection of the public in the zone of the Ezeiza Atomic Center; ethical code

  14. 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.

  15. Annual Report 2009. Nuclear Regulatory Authority; Informe Anual 2009. Autoridad Regulatoria Nuclear

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2010-07-01

    The present Annual Report of Activities of the Nuclear Regulatory Authority (ARN), prepared regularly from the creation as independent institution, describes across four parts and seven annexes the activities developed by the organism during 2009. The main topic are: the organization and the activity of the ARN; the regulatory standards; the licensing and inspection of nuclear power plants and critical facilities; the emergency systems; the environmental monitoring; the occupational surveillance; the training and the public information; improved organizational and budgetary developments. Also, this publication have annexes with the following content: regulatory documents; inspections to medical, industrial and training installations; regulatory guides; measurement and evaluation of the drinking water of Ezeiza.

  16. 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)

  17. Annual report 1999

    International Nuclear Information System (INIS)

    2002-01-01

    This 1999 annual report of the Authorities of Nuclear Safety presents the main technical topics of the year: time evolution of nuclear installations, crisis and particular plan of intervention, impacts of the nuclear activities on the human and the environment, the criticality risk, EdF, the EPR project, the ANDRA, transportation events and the nuclear safety at the East. It provides also information on nuclear safety, organization of nuclear safety supervision, BIN regulatory provisions, plant supervision, information of the public, international relations, emergency response, radiation protection, radioactive material transportation, radioactive waste, PWR reactors, research reactors and other installations, nuclear fuel cycle installations and final shutdown and dismantling of nuclear installations. (A.L.B.)

  18. 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)

  19. 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

  20. 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)

  1. 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

  2. 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

  3. 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.

  4. 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.

  5. 2009 annual meeting on nuclear technology. Pt. 1. Section reports; JAHRESTAGUNG KERNTECHNIK 2009. T. 1. Sektionsberichte

    Energy Technology Data Exchange (ETDEWEB)

    Schaffrath, Andreas [TUeV NORD SysTec GmbH und Co. KG, Hamburg (Germany); Hartmann, Miks; Hoffmann, Petra Britt [Areva NP GmbH, Erlangen (Germany); Stieglitz, Robert [Forschungszentrum Karlsruhe, Eggenstein-Leopoldshafen (Germany); Hoehne, Thomas [Forschungszentrum Dresden-Rossendorf, Dresden (Germany); Weiss, Frank-Peter [Forschungszentrum Dresden-Rossendorf, Inst. fuer Sicherheitsforschung, Dresden (Germany); Hollands, Thorsten [Ruhr-Univ. Bochum (RUB), Energy Systems and Energy Economics (LEE), Bochum (Germany); Sanchez Espinoza, Victor Hugo [Forschungszentrum Karlsruhe, Inst. fuer Reaktorsicherheit, Eggenstein-Leopoldshafen (Germany); Tietsch, Wolfgang [Westinghouse Electric Germany GmbH, Mannheim (Germany); Sonnenburg, H.G. [Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) mbH, Muenchen (Germany)

    2009-08-15

    Summary report on these 3 - out of 13 - Sessions of the Annual Conference on Nuclear Technology held in Dresden on May 12 to 14, 2009: Thermodynamics and Fluid Dynamics (Session 2), Safety of Nuclear Installations - Methods, Analysis, Results (Session 3), and, Front End of the Fuel Cycle, Fuel Elements and Core Components (Session 4). The other Sessions Reactor Physics and Methods of Calculation (Session 1), Front End and Back End of the Fuel Cycle, Radioactive Waste, Storage (Session 5), Operation of Nuclear Installations (Session 6), Decommissioning of Nuclear Installations (Session 7), Fusion Technology (Session 8), Research Reactors, Neutron Sources (Session 9), Energy Industry and Economics (Session 10), Radiation Protection (Session 11), New Build and Innovations (Session 12), and Education, Expert Knowledge, Know How Transfer (Session 13) have be covered in reports in further issues of atw. (orig.)

  6. 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.)

  7. 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

  8. 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

  9. 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

  10. 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

  11. Conference summaries. Canadian Nuclear Association 29. annual conference; Canadian Nuclear Society 10. annual conference

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1990-12-31

    Separate abstracts were prepared for 15 papers from the twenty-ninth Annual Conference of the Canadian Nuclear Association. Abstracts were also prepared for the 102 papers from the tenth Annual Conference of the Canadian Nuclear Society.

  12. Conference summaries. Canadian Nuclear Association 29. annual conference; Canadian Nuclear Society 10. annual conference

    International Nuclear Information System (INIS)

    1989-01-01

    Separate abstracts were prepared for 15 papers from the twenty-ninth Annual Conference of the Canadian Nuclear Association. Abstracts were also prepared for the 102 papers from the tenth Annual Conference of the Canadian Nuclear Society

  13. 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

  14. Uptake of radionuclides by farm animals close to a major nuclear installation

    International Nuclear Information System (INIS)

    Sumerling, T.J.; Green, N.; Dodd, N.J.

    1984-01-01

    A field investigation of the transfer of artificially produced radionuclides in the pasture-cow-milk pathway has been made at a farm close to the nuclear fuel reprocessing installation at Sellafield. The routine discharges from the plant have resulted in enhanced levels of several artificial radionuclides in the local environment. The annual depositions of 90 Sr and 137 Cs at the farm were a factor of about five higher than the average deposition of these radionuclides in the UK. Even if extremely cautious assumptions concerning local eating habits are made, the consumption of meat and dairy products from this farm would give rise to an annual activity intake of less than one percent of the limit for adult members of the public. (orig./HP)

  15. 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

  16. 2010 ANNUAL MEETING ON NUCLEAR TECHNOLOGY. Pt. 3. Section reports; JAHRESTAGUNG KERNTECHNIK 2010. T. 3. Sektionsberichte Technische Sitzungen

    Energy Technology Data Exchange (ETDEWEB)

    Arnold, Uwe; Baumann, Erik [AREVA NP GmbH, Erlangen (Germany); Fischer, Ulrich; Bohnstedt, Angelika [Karlsruher Institut fuer Technologie (KIT), Eggenstein-Leopoldshafen (Germany); Gehring, Michael [Babcock Noell GmbH, Wuerzburg (Germany); Roedig, Manfred [Forschungszentrum Juelich GmbH (Germany); Willschuetz, Hans-Georg [E.ON Kernkraft GmbH, Hannover (Germany); Goers, Stefan [TUEV NORD SysTec GMbH und Co. KG, Hamburg (Germany); Schoenfelder, Christian [AREVA NP GmbH, Offenbach (Germany)

    2010-12-15

    Summary report on these 6 - out of 12 - Sessions of the Annual Conference on Nuclear Technology held in Berlin on May 3 to 6, 2010: - Decommissioning of Nuclear Installations (Session 7), - Fusion Technology (Session 8), - Energy Industry and Economics (Session 10), - Radiation Protection (Session 11), - New Build and Innovations (Session 12), and - Education, Expert Knowledge, Know-how-Transfer (Session 13). The other Sessions: - Reactor Physics and Methods of Calculation (Session 1), - Thermodynamics and Fluid Dynamics (Session 2), - Safety of Nuclear Installations - Methods, Analysis, Results (Session 3), - Front End and Back End of the Fuel Cycle, Radioactive Waste, Storage (Session 4), - Front End of the Fuel Cycle, Fuel Elements and Core Components (Session 5), - Operation of Nuclear Installations (Session 6) have been covered in atw issues 10 and 11 (2010). (orig.)

  17. 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)

  18. 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.)

  19. 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.

  20. 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.

  1. 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

  2. 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

  3. 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)

  4. 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)

  5. 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

  6. 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.)

  7. 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

  8. 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.

  9. 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.)

  10. 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

  11. 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

  12. 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)

  13. Statement on incidents at nuclear installations - second quarter 1987

    International Nuclear Information System (INIS)

    1988-01-01

    The first incident reported occurred at the Sellafield reprocessing plant when a process worker was contaminated on the right knee of his overalls and received a skin dose in excess of the annual dose limit. Following an inquiry, he was allowed to return to normal working within 3 months. The second incident occurred at the Oldbury nuclear power station when reaction-1 tripped following the failure of one of the three phases of the electricity supply to part of the instrumentation. This caused a loss of forced coolant circulating for a short time following the reactor shutdown. However, following safety checks it was allowed to return to power. Improvements in the instrument supply system protection were subsequently installed on reactor-2 and will be, when possible, on reactor-1. (UK)

  14. 2008 annual meeting on nuclear technology. Pt. 1. Section reports; JAHRESTAGUNG KERNTECHNIK 2008. T. 1. Sektionsberichte

    Energy Technology Data Exchange (ETDEWEB)

    Dagan, Ron; Sanchez Espinoza, Victor Hugo [Forschungszentrum Karlsruhe GmbH Technik und Umwelt (Germany). Inst. fuer Reaktorsicherheit; Rohde, U.; Kliem, Soeren [Forschungszentrum Rossendorf e.V. (FZR), Dresden (Germany); Faber, Wolfgang; Berlepsch, Thilo v.; Spann, Holger [E.ON Kernkraft GmbH, Hannover (Germany); Schaffrath, Andreas [TUEV Nord SysTec GmbH und Co. KG, Hamburg (Germany); Schubert, Bernd [Vattenfall Europe Nuclear Energy GmbH, Hamburg (Germany); Rieger, Udo [Vattenfall Nuclear Energy GmbH, Hamburg (Germany); Christ,, Bernhard G. [NUKEM Technologies GmbH, Alzenau (Germany); Gulden, Werner [Fusion for Energy, Barcelona (Spain); Bogusch, Edgar [AREVA NP GmbH, Erlangen (Germany)

    2008-08-15

    Summary report on these 5 - out of 11 - Sections of the Annual Conference on Nuclear Technology held in Hamburg on May 27-29, 2008: - Reactor Physics and Methods of Calculation - Thermodynamics and Fluid Dynamics - Safety of Nuclear Installations - Methods, Analysis, Results - Front End and Back End of the Fuel Cycle, Radioactive Waste, Storage - Fusion Technology. Other Sections will be covered in reports in further issues of atw. (orig.)

  15. 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

  16. 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.)

  17. 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)

  18. 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

  19. 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)

  20. 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.

  1. 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)

  2. 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)

  3. 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.)

  4. 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'

  5. 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.)

  6. 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)

  7. 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)

  8. 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

  9. Nuclear Regulatory Authority of the Slovak Republic. Annual Report 2002

    International Nuclear Information System (INIS)

    Seliga, M.

    2003-04-01

    A brief account of activities carried out by the Nuclear Regulatory Authority of the Slovak Republic in 2002 is presented. These activities are reported under the headings: (1) Foreword; (2) Legislation; (3) Assessment and inspection of nuclear installations; (4) Safety analyses; (5) Nuclear materials and physical protection of nuclear installations; (6) Radioactive waste; (7) Quality assurance; (8) Personnel qualification and training; (9) Emergency preparedness; (10) International co-operation; (11) Public information; (12) Personnel and economy data; Appendix: Abbreviations; Special Enclosure: 10. Years of the Nuclear Regulation Authority of the Slovak Republic. An independent and professional state regulatory authority supervising the nuclear safety is one of prerequisites of the safe operation of nuclear installations in each country. In the Slovak Republic this role has been fulfilled by the Nuclear Regulatory Authority (UJD) since 1993. The main mission of UJD set down by the law is to guarantee for the Slovak citizens as well as for international society that the nuclear power on the territory of the Slovak Republic will be used exclusively for peaceful purposes and that the Slovak nuclear installations are designed, constructed, operated and decommissioned in compliance with relevant legal documents. The mission of UJD is also to tender the operation of nuclear installations so that their operation would not jeopardise the nuclear power plant staff or public and would not cause detrimental effects to the environment or property. UJD prepares laws or comments to the laws and issues decrees in the area of its competencies, issues authorisations for operators of nuclear facilities, reviews and evaluates the safety documentation of nuclear installations, performs the inspections at nuclear installations comparing whether the legal requirements are fulfilled and whether the real status of nuclear installations and their operation is or not in compliance with

  10. 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

  11. 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.)

  12. 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

  13. 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)

  14. 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

  15. Conference summaries of the Canadian Nuclear Association 30. annual conference, and the Canadian Nuclear Society 11. annual conference

    International Nuclear Information System (INIS)

    1990-01-01

    This volume contains conference summaries for the 30. annual conference of the Canadian Nuclear Association, and the 11. annual conference of the Canadian Nuclear Society. Topics of discussion include: energy needs and challenges facing the Canadian nuclear industry; the environment and nuclear power; the problems of maintaining and developing industrial capacity; the challenges of the 1990's; programmes and issues for the 1990's; thermalhydraulics; reactor physics and fuel management; nuclear safety; small reactors; fuel behaviour; energy production and the environment; computer applications; nuclear systems; fusion; materials handling; and, reactor components

  16. Nuclear Physics Department annual report

    International Nuclear Information System (INIS)

    1997-07-01

    This annual report presents articles and abstracts published in foreign journals, covering the following subjects: nuclear structure, nuclear reactions, applied physics, instrumentation, nonlinear phenomena and high energy physics

  17. 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

  18. 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

  19. 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

  20. 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.)

  1. 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

  2. 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

  3. 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

  4. Annual meeting on nuclear technology '88. Technical session on focal points of the atomic energy law and the radiation protection law in 1988

    International Nuclear Information System (INIS)

    1988-06-01

    This issue of Annual Meeting on Nuclear Technology reports presents the papers of the technical session on 'Focal points of the atomic energy law and the radiation protection law in 1988'. The titles are: Is there a binding link between decisions of the atomic energy authority and criminal law? Conclusions to be drawn from the Alkem case court decision. - Recent developments in atomic energy law. - Current radiation protection law. - Codetermination at plant level in a nuclear installation. - The legal position of foreigners from neigbour countries in the field of atomic energy law. The licensing of nuclear installations near the border. (RST) [de

  5. 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

  6. 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

  7. The dismantling of nuclear installations

    International Nuclear Information System (INIS)

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

    1997-01-01

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

  8. 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

  9. 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

  10. 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

  11. 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

  12. Nuclear Physics Laboratory: Annual report

    International Nuclear Information System (INIS)

    1987-05-01

    Topics covered in this annual report are: astrophysics and cosmology, giant resonances in excited nuclei, heavy ions, fundamental symmetries, nuclear reactions, accelerator mass spectrometry, accelerators and ion sources, nuclear instrumentation, computer systems and the booster linac project

  13. 2004 Annual report

    International Nuclear Information System (INIS)

    2005-01-01

    This annual report presents information of the main activities on the scope of radiation protection and nuclear safety of the Nuclear Regulatory Authority (ARN) of the Argentina during 2004. The main topics are the regulatory framework, the national systems to supervise nuclear installations, the emergency systems, the environmental control, the laboratories of the ARN, the institutional relations and the non-proliferation, the training and the public information, the radiological and the nuclear safety inspections, the safeguards and the physical protection, the quality assurance in the ARN, the environmental monitoring, and the human and economic resources. Also, this publication has four annexes with the following content: regulatory documents; inspections to medical, industrial and training installations; ethical code; measurements and evaluations of the drinking water in Ezeiza (Argentina)

  14. Proceedings of the 29th annual conference of the Canadian Nuclear Association and 10th annual conference of the Canadian Nuclear Society. V. 1-3

    Energy Technology Data Exchange (ETDEWEB)

    Harvey, M; Fehrenbach, P J [eds.

    1990-12-31

    The symposium was designed to highlight how the technical information for nuclear energy came to Canada, the effect this information had in Canada in the fields of Physics, Chemistry, Medicine and Nuclear Power. Volume 1 is the combined proceedings of the Canadian Nuclear Association twenty-ninth annual conference and the Canadian Nuclear Society tenth annual conference. Volume 2 is the proceedings of the Canadian Nuclear Association twenty-ninth annual conference, and volume 3 is the proceedings of the Canadian Nuclear Society tenth annual conference.

  15. Proceedings of the 29th annual conference of the Canadian Nuclear Association and 10th annual conference of the Canadian Nuclear Society. V. 1-3

    International Nuclear Information System (INIS)

    Harvey, M.; Fehrenbach, P.J.

    1989-01-01

    The symposium was designed to highlight how the technical information for nuclear energy came to Canada, the effect this information had in Canada in the fields of Physics, Chemistry, Medicine and Nuclear Power. Volume 1 is the combined proceedings of the Canadian Nuclear Association twenty-ninth annual conference and the Canadian Nuclear Society tenth annual conference. Volume 2 is the proceedings of the Canadian Nuclear Association twenty-ninth annual conference, and volume 3 is the proceedings of the Canadian Nuclear Society tenth annual conference

  16. 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

  17. 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.)

  18. Regulatory oversight report 2016 concerning nuclear safety in Swiss nuclear installations

    International Nuclear Information System (INIS)

    2017-06-01

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

  19. 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.)

  20. 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.)

  1. 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

  2. 1996 Annual report

    International Nuclear Information System (INIS)

    1997-01-01

    This annual report present information of the main activities on the scope of the radiation protection and nuclear safety of the Nuclear Regulatory Authority (ARN) of the Argentina during 1996. The activities are developed in 10 chapters and 2 appendices, were are described the activities and the bases of the Argentine Regulatory System. The followings chapters and appendices are: 1.-Evolution of the nuclear regulatory activities in the Argentina since the beginnings in the CNEA. 2.-Regulatory system, laws and regulations. 3.-Institutional relations with national and international organizations. 4. and 5.-Safeguards and inspections of the nuclear installations. 6.-Radiation control of the occupational and public doses. 7.-Radiological emergencies. 8.-Projects and tasks scientific-technological. 9.-Training courses and meetings. 10.-Economic and human recourses. Appendix I.-Regulatory documentation. Appendix II.- Inspections of nuclear installations

  3. 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)

  4. 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).

  5. 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)

  6. 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)

  7. 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

  8. 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

  9. 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)

  10. Annual report, 1987-88

    International Nuclear Information System (INIS)

    1988-01-01

    This is the forty-first annual report of the Atomic Energy Control Board (AECB). The period covered by this report is the year ending March 31, 1988. The AECB controls the development, application and use of nuclear energy in Canada, and participates on behalf of Canada in international measures of control of nuclear energy. The AECB was established in 1946, by the Atomic Energy Control Act. It is a departmental corporation within the meaning and purpose of the Financial Administration Act. The AECB also is responsible for the administration of the Nuclear Liability Act, including the designation of nuclear installations and the prescription of basic insurance to be carried by the operators of such nuclear installations. The AECB reports to Parliament through designated Minister, currently the Minister of Energy, Mines and Resources

  11. Proceedings of the Canadian Nuclear Society 12. annual conference

    International Nuclear Information System (INIS)

    1991-01-01

    This volume contains the Proceedings of the seventeen Technical Sessions from the Twelfth Annual Conference of the Canadian Nuclear Society held in Saskatoon, Saskatchewan, June 9 to 12, 1991. As in previous years, the Annual Conference of the Canadian Nuclear Society was held in conjunction with the Annual Conference of the Canadian Nuclear Association. The major topics of discussion included: reactor physics; thermal hydraulics; industrial irradiation; computer applications; fuel channel analysis; small reactors; severe accidents; fuel behaviour under accident conditions; reactor components; safety related computer software; nuclear fuel management; nuclear waste management; and, uranium mining processing

  12. Nuclear Medicine Annual, 1989

    International Nuclear Information System (INIS)

    Freeman, L.M.; Weissmann, H.S.

    1989-01-01

    Among the highlights of Nuclear Medicine Annual, 1989 are a status report on the thyroid scan in clinical practice, a review of functional and structural brain imaging in dementia, an update on radionuclide renal imaging in children, and an article outlining a quality assurance program for SPECT instrumentation. Also included are discussions on current concepts in osseous sports and stress injury scintigraphy and on correlative magnetic resonance and radionuclide imaging of bone. Other contributors assess the role of nuclear medicine in clinical decision making and examine medicolegal and regulatory aspects of nuclear medicine

  13. 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.)

  14. 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

  15. Papers of the Third Annual Congress of the Mexican Nuclear Society, C.A

    International Nuclear Information System (INIS)

    1992-11-01

    Once again the Sociedad Nuclear Mexicana fulfill its annual Congress being this time the installations of the Instituto de Investigaciones Electricas the place for the event with a collection of forty documents in the following areas: modelling of nuclear systems, expert systems, dosimetry, experimentation and fuel cycle among others. This significant number of papers is a sample of the great interest of the nuclear community in the participation in this forum presenting its more recent works. The participants belongs to the main institutions in the country dedicated to the technological development of the nuclear area in its different branches. Our best wishes are that this event allows not only the exchange of ideas and the knowledge of the type of works that other colleagues are developing, but also to present the opportunity to live together in a pleasant environment where the main ingredient be the surmounting spirit. We welcome all the participants to the Third Congress of our Society. (Author)

  16. 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.)

  17. 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)

  18. 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)

  19. Annual report 1983

    International Nuclear Information System (INIS)

    Van de Vyver, R.E.

    1983-01-01

    In 1983, the various research projects in which the nuclear physics laboratory of Ghent State University is involved, were continued. In the present Annual Report, the results obtained in the field of photofission, photonuclear reactions positron annihilation, dosimetry and nuclear theory are summarized. The new 10 MeV high duty factor linear electron accelerator is presently being installed: performance tests will be carried out until July 1984; after which this facility will gradually become available for nuclear research purposes. (AF)

  20. Annual report 2000

    International Nuclear Information System (INIS)

    2000-01-01

    This year 2000 annual report of the CEA (atomic energy commissariat) gives a general overview of the CEA activities and organization in the domains of the defence, the nuclear energy the technological research and the fundamental research. It is presented in seven main parts: contribution to national defence, civil nuclear research, technological research for the industry, pushing back the frontiers of scientific knowledge in physics and life science, mastery of installations; institute for protection and nuclear safety, research resources. (A.L.B.)

  1. 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)

  2. 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

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

    International Nuclear Information System (INIS)

    Mahrenholtz, Philipp; Eligehausen, Rolf

    2015-01-01

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

  4. 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)

  5. 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)

  6. 1993 Annual report of the Brazilian-Argentine Agency for Accounting and Control of Nuclear Materials - ABACC

    International Nuclear Information System (INIS)

    1994-01-01

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

  7. 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)

  8. 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

  9. Nuclear Regulatory Authority of the Slovak Republic. Annual Report 2004

    International Nuclear Information System (INIS)

    Seliga, M.

    2005-04-01

    A brief account of activities carried out by the Nuclear Regulatory Authority of the Slovak Republic in 2004 is presented. These activities are reported under the headings: (1) Foreword; (2) Legislation; (3) Assessment and inspection of nuclear power plants; (3.1) Assessment and inspection of other nuclear installations; (3.2) Safety analyses; (4) Nuclear materials and physical protection of nuclear installations; (5) Radioactive waste; (6) Quality assurance; (7) Personnel qualification and training; (8) Emergency preparedness; (9) International co-operation; (10) Public information; (11) Personnel and economy data; Appendix: Abbreviations; INES

  10. 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

  11. Annual report of Nuclear Engineering Research Laboratory, University of Tokyo in fiscal 1993

    International Nuclear Information System (INIS)

    1994-08-01

    In this annual report, the activities of research and education, the state of operation of research facilities and others in fiscal year 1993 are summarized. Four main research facilities are the fast neutron source reactor 'Yayoi', the electron linear accelerator, the basic experiment facility for nuclear fusion reactor blanket design and the heavy irradiation research facility. The reactor and the accelerator are for the joint utilization by all universities in Japan, the blanket is used by the Faculty of Engineering, and the HIT is for the joint utilization in University of Tokyo. In fiscal year 1993, the installation of the fast neutron science research facility was approved. In this annual report, the management and operation of the above research facilities are described, and the research activities, the theses for doctorate and graduation theses of teachers, are summarized. (K.I.)

  12. 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

  13. Nuclear Regulatory Authority of the Slovak Republic. Annual Report 2003

    International Nuclear Information System (INIS)

    Seliga, M.

    2004-04-01

    A brief account of activities carried out by the Nuclear Regulatory Authority of the Slovak Republic in 2003 is presented. These activities are reported under the headings: (1) Foreword; (2) Legislation; (3) Assessment and inspection of nuclear installations; (4) Safety analyses; (5) Nuclear materials and physical protection of nuclear installations; (6) Radioactive waste; (7) Quality assurance; (8) Personnel qualification and training; (9) Emergency preparedness; (10) International co-operation; (11) Public information; (12) Personnel and economy data; Appendix: Abbreviations; Radiation safety

  14. Nuclear Physics Laboratory. Annual report no.21

    International Nuclear Information System (INIS)

    1986-11-01

    The annual report of the Nuclear Physics Laboratory covers the following subjects: 1) the accelerators; 2) work in experimental nuclear physics; 3) research in particle physics: experiments at TRIUMF and CERN; 4) work in applied nuclear physics; and 5) work in theoretical physics

  15. Nuclear Physics Laboratory. Annual report no.22

    International Nuclear Information System (INIS)

    1987-11-01

    The annual report of the Nuclear Physics Laboratory covers the following subjects: 1) the accelerators; 2) work in experimental nuclear physics; 3) research in particle physics: experiments at TRIUMF and CERN; 4) work in applied nuclear physics; and 5) work in theoretical physics

  16. 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

  17. 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

  18. 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)

  19. 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.

  20. 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)

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

    International Nuclear Information System (INIS)

    Romanato, Luiz Sergio

    2009-01-01

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

  2. 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

  3. Annual report of the Nuclear Structure Committee

    International Nuclear Information System (INIS)

    1977-01-01

    The Annual Report for the period 1 August 1975 to 31 July 1976 of the Nuclear Structure Committee of the Nuclear Physics Board, under the (United Kingdom) Science Research Council, is presented. Details are given of nuclear structure grants and laboratory agreements. (U.K.)

  4. Nuclear Regulatory Authority of the Slovak Republic. Annual Report 2001

    International Nuclear Information System (INIS)

    Seliga, M.

    2002-04-01

    A brief account of activities carried out by the Nuclear Regulatory Authority of the Slovak Republic in 2001 is presented. These activities are reported under the headings: (1) Foreword; (2) Legislation; (3) Assessment and inspection of nuclear installations; (4) Safety analyses; (5) Nuclear materials and physical protection of nuclear installations; (6) Radioactive waste (RAW); (7) Quality assurance; (8) Personnel qualification and training; (9) Emergency preparedness; (10) International co-operation; (11) Public information; (12) Personnel and economy data; (13) Conclusion; (14) Appendix: Abbreviations; Radiation safety

  5. 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

  6. 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)

  7. Nuclear Regulatory Authority of the Slovak Republic. Annual Report 2000

    International Nuclear Information System (INIS)

    Seliga, M.

    2001-01-01

    A brief account of activities carried out by the Nuclear Regulatory Authority of the Slovak Republic in 2000 is presented. These activities are reported under the headings: (1) Foreword and organisation structure; (2) Mission of the Nuclear Regulatory Authority; (3) Legislation; (4) Assessment and inspection of nuclear installations; (5) Safety analyses; (6) Nuclear materials and physical protection of nuclear installations; (7) Radioactive waste; (8) Quality assurance; (9) Personnel qualification and training; (10) Emergency preparedness; (11) International co-operation; (12) Public information; (13) Personnel and economic data of the UJD; (14) Conclusion; (15) Attachments: Abbreviations; Radiation safety

  8. 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.)

  9. 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

  10. 46{sup th} annual meeting on nuclear technology (AMNT 2015). Key topics / Outstanding know-how and sustainable innovations enhanced safety and operation excellence

    Energy Technology Data Exchange (ETDEWEB)

    Lamm, Matthias [AREVA GmbH, Erlangen (Germany). R and D; Hollands, Thorsten [Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) gGmbH, Garching (Germany). Reactor Safety Research Div.

    2016-01-15

    Summary report on the Technical Sessions ''Know-how, New Build and Innovations'' and ''Operation and Safety of Nuclear Installations, Fuel SA: WASA-BOSS + CESAM'' of the 46{sup th} Annual Conference on Nuclear Technology (AMNT 2015) held in Berlin, 5 to 7 May 2015. Other Sessions of AMNT 2015 have been covered in atw 7 to 12 (2015) and will be covered in further issues of atw.

  11. Annual report of the Institute for Nuclear Study, University of Tokyo, 1995

    International Nuclear Information System (INIS)

    Kubono, Shigeru; Mori, Yoshiharu; Niki, Kazuaki; Ohshiro, Yukimitsu; Outa, Haruhiko; Sekiguchi, Masayuki; Tsutsui, Izumi; Itagaki, Toshiko

    1996-01-01

    This report is an annual report from April, 1995 to March 1996 at Institute for Nuclear Study, University of Tokyo. In this fiscal year 1995, both the SF cyclotron and the 1.3 GeV electron synchrotron operated smoothly for users from universities. A new radioactive nuclear facility was completed. The research programs at the TARN II cooler ring further made progress in the field of atomic physics. The superconducting large solid-angle kaon spectrometer (SKS) installed at the 12 GeV PS of KEK has continued to produce interesting results concerning hypernuclei. In order to preform a long-baseline neutrino-oscillation experiment, a new collaboration has been formed among INS, KEK and ICRR. And, internal collaborations are progressing, and much effort was concentrated on realizing the future project. This report contains the following thema: Nuclear physics division, Intermediate-energy physics division, High-energy physics division, Theoretical physics division, Accelerator research division, Interdisciplinary research laboratory, Research and development for Japanese Hadron Project, Supporting division, Meetings and Appendices. (G.K.)

  12. 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)

  13. Annual report ''nuclear safety in France''

    International Nuclear Information System (INIS)

    2001-01-01

    This document is the 2001 annual report of the French authority of nuclear safety (ASN). It summarizes the highlights of the year 2000 and details the following aspects: the nuclear safety in France, the organization of the control of nuclear safety, the regulation relative to basic nuclear facilities, the control of facilities, the information of the public, the international relations, the organisation of emergencies, the radiation protection, the transport of radioactive materials, the radioactive wastes, the PWR reactors, the experimental reactors and other laboratories and facilities, the nuclear fuel cycle facilities, and the shutdown and dismantling of nuclear facilities. (J.S.)

  14. Annual report

    International Nuclear Information System (INIS)

    1986-01-01

    This is the thirty-ninth annual report of the Atomic Energy Control Board. The period covered by this report is the year ending March 31, 1986. The Atomic Energy Control Board (AECB) was established in 1946, by the Atomic Energy Control Act (AEC Act), (Revised Statues of Canada (R.S.C.) 1970 cA19). It is a departmental corporation (Schedule B) within the meaning and purpose of the Financial Administration Act. The AECB controls the development, application and use of atomic energy in Canada, and participates on behalf of Canada in international measures of control. The AECB is also repsonsible for the administration of the Nuclear Liability Act, (R.S.C. 1970 c29 1st Supp) as amended, including the designation of nuclear installations and the prescription of basic insurance to be carried by the operators of such nuclear installations. The AECB reports to Parliament through a designated Minister, currently the Minister of Energy, Mines and Resources

  15. 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

  16. KWIKPLAN: a computer program for projecting the annual requirements of nuclear fuel cycle operations

    International Nuclear Information System (INIS)

    Salmon, R.; Kee, C.W.

    1977-06-01

    The computer code KWIKPLAN was written to facilitate the calculation of projected nuclear fuel cycle activities. Using given projections of power generation, the code calculates annual requirements for fuel fabrication, fuel reprocessing, uranium mining, and plutonium use and production. The code uses installed capacity projections and mass flow data for six types of reactors to calculate projected fuel cycle activities and inventories. It calculates fissile uranium and plutonium flows and inventories after allowing for an economy with limited reprocessing capacity and a backlog of unreprocessed fuel. All calculations are made on a quarterly basis; printed and punched output of the projected fuel cycle activities are made on an annual basis. Since the punched information is used in another code to determine waste inventories, the code punches a table from which the effective average burnup can be calculated for the fuel being reprocessed

  17. 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)

  18. Nuclear physics annual report 1986

    International Nuclear Information System (INIS)

    1986-01-01

    The paper is the annual report of Manchester University Nuclear Physics Group, 1985/6. The bulk of the work has been carried out at the Nuclear Structure Facility, often in collaboration with other groups. The research programme topics include: high spin states, nuclei far from stability, reactions and fission, spectroscopy and related subjects, and technical developments. The experiments associated with these topics are described, together with the results of the investigations. (UK)

  19. 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

  20. 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)

  1. 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

  2. 41st Annual Meeting of the Spanish Nuclear Society

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2015-07-01

    The Spanish Nuclear Society (SNE) is a non-profit association, made up of professionals and institutions, in order to promote awareness and dissemination of nuclear science and technology. The 41 Annual Meeting of the Spanish Nuclear Society was held in A Coruña from 23 to 25 September 2015. This Annual Meeting allows professionals and companies in the sector to analyze the current state of nuclear energy and its future challenges, covering different topics from engineering to R & D, nuclear safety, also impact on health and the environment, climate change, nuclear facilities, experience spanish companies in the management of knowledge in the nuclear sector. This congress has involved some 600 experts who have dealt with current issues and maximum interest.

  3. The annual report for 1992

    International Nuclear Information System (INIS)

    1993-07-01

    The most significant achievements of the International Atomic Energy Agency during 1992 are summarized in the Introduction. The following topics are considered in detail: (i) nuclear power; (ii) nuclear fuel cycle; (iii) radioactive waste management; (iv) comparative assessment of nuclear power and other energy sources; (v) food and agriculture; (vi) human health; (vii) industry and earth science; (viii) physical and chemical sciences; (ix) radiation protection; (x) safety of nuclear installations; and (xi) safeguards. The annual report ends with a description of the direction and support, statistical appendices, a list of abbreviations, and an organization chart

  4. World nuclear generating capacity 1993/94

    International Nuclear Information System (INIS)

    Anon.

    1994-01-01

    This article is the annual summary of world nuclear generating capacity for 1994. A global summary is first provided, reviewing total installed capacity and growth in installed capacity over the next five years. A more detailed discussion of the nuclear efforts in 34 countries follows, with a tabular listing of nuclear projects in each of these countries. The listing includes reactor supplier, reactor type, size, current status, and date of commercial operation

  5. 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)

  6. 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)

  7. 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

  8. 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

  9. 1996 Annual report; 1996 Informe anual

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-12-31

    This annual report present information of the main activities on the scope of the radiation protection and nuclear safety of the Nuclear Regulatory Authority (ARN) of the Argentina during 1996. The activities are developed in 10 chapters and 2 appendices, were are described the activities and the bases of the Argentine Regulatory System. The followings chapters and appendices are: 1.-Evolution of the nuclear regulatory activities in the Argentina since the beginnings in the CNEA. 2.-Regulatory system, laws and regulations. 3.-Institutional relations with national and international organizations. 4. and 5.-Safeguards and inspections of the nuclear installations. 6.-Radiation control of the occupational and public doses. 7.-Radiological emergencies. 8.-Projects and tasks scientific-technological. 9.-Training courses and meetings. 10.-Economic and human recourses. Appendix I.-Regulatory documentation. Appendix II.- Inspections of nuclear installations.

  10. 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

  11. 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

  12. 48{sup th} Annual meeting on nuclear technology (AMNT 2017). Key topic / Enhanced safety and operation excellence. Technical session: Operation and safety of nuclear installations, fuel

    Energy Technology Data Exchange (ETDEWEB)

    Hollands, Thorsten [Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) gGmbH, Garching (Germany). Bereich Reaktorsicherheitsforschung

    2017-12-15

    The sessions Fuel and Materials and Containment and SFP, as part of the Technical Sessions Operation and Safety of Nuclear Installations, Fuel implemented in the Key Topic Enhanced Safety and Operation Excellence were chaired by Dr. Thorsten Hollands (Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) gGmbH) and Dr. Erwin Fischer (PreussenElektra GmbH) who was the keynote coordinator for the Technical Sessions. Both sessions consist of a keynote lecture followed by technical presentations.

  13. 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)

  14. 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

  15. Nuclear Regulatory Commission: 1981 annual report

    International Nuclear Information System (INIS)

    1981-01-01

    This seventh annual report of the US Nuclear Regulatory Commission covers major actions, events and planning that occurred during fiscal year 1981, with some coverage of later events, where appropriate. Chapters of the report address the agency's various functions or areas of activity: regulating nuclear power plants; evaluating reactor operating experience; licensing nuclear materials and their transportation; safeguarding nuclear plants and materials; managing nuclear wastes; inspection and enforcement; cooperation with state governments; international activities; research and standards development; hearings; decisions and litigation; and administrative and public communications matters. Each chapter presents a detailed review of program accomplishments during the report period, fiscal year 1981

  16. The 1989 annual report: Nuclear Physics Institute

    International Nuclear Information System (INIS)

    1989-01-01

    The 1988 annual report of the Nuclear Physics Institute (Orsay, France) is presented. The results concerning exotic nuclei and structure studies by means of nuclear reactions are summarized. Research works involving the inertial fusion and the actinides are discussed. Theoretical and experimental work on the following fields is also included: high excitation energy nuclear states, heavy ion collision, intermediate energy nuclear physics, transfer reactions, dibaryonic resonances, thermodiffusion, management of radioactive wastes [fr

  17. 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)

  18. 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

  19. Malaysian Nuclear Agency: Annual report 2008

    International Nuclear Information System (INIS)

    2008-01-01

    The establishment of Malaysian Nuclear Agency (Nuclear Malaysia) was mooted from idea of the then Malaysia's Deputy Prime Minister, Tun Dr. Ismail Dato Abdul Rahman, that Malaysia should play a role in the development of nuclear science and technology for peaceful purposes. The Centre for Application of Nuclear Energy (CRANE) was the entity to mark the of Malaysia's nuclear programme, focussing on manpower development for a nuclear power programme to provide an option for energy source, following the worldwide oil crisis of the early 1970s. The Cabinet officially approved the establishment of the Tun Ismail Atomic Research Centre (PUSPATI), under the Ministry of Science, Technology and the environment on 19 September 1972. The era of nuclear research in Malaysia began with the historic event signified by the Reaktor TRIGA PUSPATI reaching its first criticality on 28 June 1982. When PUSPATI was placed under the auspices of the Prime Ministers Department, it assumed the name Nuclear Energy Unit (UTN). The Nuclear Energy Unit was later placed under the Minister of Science, Technology and the Environment. In line with the national development, the institute was name Malaysian Institute for Nuclear Technology Research (MINT) on 10 August 1994. To reflect its vision, mission, objectives and activities in the challenging world, a new identity was established, and was officially named as Malaysian Nuclear Agency (Nuclear Malaysia) on 28 September 2006. Nuclear Malaysia, is strategically located nearby the government administration, centre Putrajaya, and Cyberjaya. These annual report highlights all the activities that have been through by the agency in 2008. All the achievements and triumph were highlights in this annual report. It also contained all the agency planning during 2008 to fulfill the objectives, mission and vision to become main players in nuclear research in Malaysia. Finally, there also highlights some publications contribute by all the researchers from

  20. Malaysian Nuclear Agency: Annual report 2009

    International Nuclear Information System (INIS)

    2009-01-01

    The establishment of Malaysian Nuclear Agency (Nuclear Malaysia) was mooted from idea of the then Malaysia's Deputy Prime Minister, Tun Dr. Ismail Dato Abdul Rahman, that Malaysia should play a role in the development of nuclear science and technology for peaceful purposes. The Centre for Application of Nuclear Energy (CRANE) was the entity to mark the of Malaysia's nuclear programme, focussing on manpower development for a nuclear power programme to provide an option for energy source, following the worldwide oil crisis of the early 1970s. The Cabinet officially approved the establishment of the Tun Ismail Atomic Research Centre (PUSPATI), under the Ministry of Science, Technology and the environment on 19 September 1972. The era of nuclear research in Malaysia began with the historic event signified by the Reaktor TRIGA PUSPATI reaching its first criticality on 28 June 1982. When PUSPATI was placed under the auspices of the Prime Ministers Department, it assumed the name Nuclear Energy Unit (UTN). The Nuclear Energy Unit was later placed under the Minister of Science, Technology and the Environment. In line with the national development, the institute was name Malaysian Institute for Nuclear Technology Research (MINT) on 10 August 1994. To reflect its vision, mission, objectives and activities in the challenging world, a new identity was established, and was officially named as Malaysian Nuclear Agency (Nuclear Malaysia) on 28 September 2006. Nuclear Malaysia, is strategically located nearby the government administration, centre Putrajaya, and Cyberjaya. These annual report highlights all the activities that have been through by the agency in 2009. All the achievements and triumph were highlights in this annual report. It also contained all the agency planning during 2009 to fulfill the objectives, mission and vision to become main players in nuclear research in Malaysia. Finally, there also highlights some publications contribute by all the researchers from

  1. Malaysian Nuclear Agency: Annual report 2010

    International Nuclear Information System (INIS)

    2010-01-01

    The establishment of Malaysian Nuclear Agency (Nuclear Malaysia) was mooted from idea of the then Malaysia's Deputy Prime Minister, Tun Dr. Ismail Dato Abdul Rahman, that Malaysia should play a role in the development of nuclear science and technology for peaceful purposes. The Centre for Application of Nuclear Energy (CRANE) was the entity to mark the of Malaysia's nuclear programme, focussing on manpower development for a nuclear power programme to provide an option for energy source, following the worldwide oil crisis of the early 1970s. The Cabinet officially approved the establishment of the Tun Ismail Atomic Research Centre (PUSPATI), under the Ministry of Science, Technology and the environment on 19 September 1972. The era of nuclear research in Malaysia began with the historic event signified by the Reaktor TRIGA PUSPATI reaching its first criticality on 28 June 1982. When PUSPATI was placed under the auspices of the Prime Ministers Department, it assumed the name Nuclear Energy Unit (UTN). The Nuclear Energy Unit was later placed under the Minister of Science, Technology and the Environment. In line with the national development, the institute was name Malaysian Institute for Nuclear Technology Research (MINT) on 10 August 1994. To reflect its vision, mission, objectives and activities in the challenging world, a new identity was established, and was officially named as Malaysian Nuclear Agency (Nuclear Malaysia) on 28 September 2006. Nuclear Malaysia, is strategically located nearby the government administration, centre Putrajaya, and Cyberjaya. These annual report highlights all the activities that have been through by the agency in 2010. All the achievements and triumph were highlights in this annual report. It also contained all the agency planning during 2010 to fulfill the objectives, mission and vision to become main players in nuclear research in Malaysia. Finally, there also highlights some publications contribute by all the researchers from

  2. Malaysian Nuclear Agency; Annual report 2013

    International Nuclear Information System (INIS)

    2013-01-01

    The establishment of Malaysian Nuclear Agency (Nuclear Malaysia) was mooted from idea of the then Malaysia's Deputy Prime Minister, Tun Dr. Ismail Dato Abdul Rahman, that Malaysia should play a role in the development of nuclear science and technology for peaceful purposes. The Centre for Application of Nuclear Energy (CRANE) was the entity to mark the of Malaysia's nuclear programme, focussing on manpower development for a nuclear power programme to provide an option for energy source, following the worldwide oil crisis of the early 1970s. The Cabinet officially approved the establishment of the Tun Ismail Atomic Research Centre (PUSPATI), under the Ministry of Science, Technology and the environment on 19 September 1972. The era of nuclear research in Malaysia began with the historic event signified by the Reaktor TRIGA PUSPATI reaching its first criticality on 28 June 1982. When PUSPATI was placed under the auspices of the Prime Ministers Department, it assumed the name Nuclear Energy Unit (UTN). The Nuclear Energy Unit was later placed under the Minister of Science, Technology and the Environment. In line with the national development, the institute was name Malaysian Institute for Nuclear Technology Research (MINT) on 10 August 1994. To reflect its vision, mission, objectives and activities in the challenging world, a new identity was established, and was officially named as Malaysian Nuclear Agency (Nuclear Malaysia) on 28 September 2006. Nuclear Malaysia, is strategically located nearby the government administration, centre Putrajaya, and Cyberjaya. These annual report highlights all the activities that have been through by the agency in 2013. All the achievements and triumph were highlights in this annual report. It also contained all the agency planning during 2013 to fulfill the objectives, mission and vision to become main players in nuclear research in Malaysia. Finally, there also highlights some publications contribute by all the researchers

  3. Malaysian Nuclear Agency; Annual report 2014

    International Nuclear Information System (INIS)

    2009-01-01

    The establishment of Malaysian Nuclear Agency (Nuclear Malaysia) was mooted from idea of the then Malaysia's Deputy Prime Minister, Tun Dr. Ismail Dato Abdul Rahman, that Malaysia should play a role in the development of nuclear science and technology for peaceful purposes. The Centre for Application of Nuclear Energy (CRANE) was the entity to mark the of Malaysia's nuclear programme, focussing on manpower development for a nuclear power programme to provide an option for energy source, following the worldwide oil crisis of the early 1970s. The Cabinet officially approved the establishment of the Tun Ismail Atomic Research Centre (PUSPATI), under the Ministry of Science, Technology and the environment on 19 September 1972. The era of nuclear research in Malaysia began with the historic event signified by the Reaktor TRIGA PUSPATI reaching its first criticality on 28 June 1982. When PUSPATI was placed under the auspices of the Prime Ministers Department, it assumed the name Nuclear Energy Unit (UTN). The Nuclear Energy Unit was later placed under the Minister of Science, Technology and the Environment. In line with the national development, the institute was name Malaysian Institute for Nuclear Technology Research (MINT) on 10 August 1994. To reflect its vision, mission, objectives and activities in the challenging world, a new identity was established, and was officially named as Malaysian Nuclear Agency (Nuclear Malaysia) on 28 September 2006. Nuclear Malaysia, is strategically located nearby the government administration, centre Putrajaya, and Cyberjaya. These annual report highlights all the activities that have been through by the agency in 2014. All the achievements and triumph were highlights in this annual report. It also contained all the agency planning during 2014 to fulfill the objectives, mission and vision to become main players in nuclear research in Malaysia. Finally, there also highlights some publications contribute by all the researchers

  4. Malaysian Nuclear Agency; Annual report 2011

    International Nuclear Information System (INIS)

    2008-01-01

    The establishment of Malaysian Nuclear Agency (Nuclear Malaysia) was mooted from idea of the then Malaysia's Deputy Prime Minister, Tun Dr. Ismail Dato Abdul Rahman, that Malaysia should play a role in the development of nuclear science and technology for peaceful purposes. The Centre for Application of Nuclear Energy (CRANE) was the entity to mark the of Malaysia's nuclear programme, focussing on manpower development for a nuclear power programme to provide an option for energy source, following the worldwide oil crisis of the early 1970s. The Cabinet officially approved the establishment of the Tun Ismail Atomic Research Centre (PUSPATI), under the Ministry of Science, Technology and the environment on 19 September 1972. The era of nuclear research in Malaysia began with the historic event signified by the Reaktor TRIGA PUSPATI reaching its first criticality on 28 June 1982. When PUSPATI was placed under the auspices of the Prime Ministers Department, it assumed the name Nuclear Energy Unit (UTN). The Nuclear Energy Unit was later placed under the Minister of Science, Technology and the Environment. In line with the national development, the institute was name Malaysian Institute for Nuclear Technology Research (MINT) on 10 August 1994. To reflect its vision, mission, objectives and activities in the challenging world, a new identity was established, and was officially named as Malaysian Nuclear Agency (Nuclear Malaysia) on 28 September 2006. Nuclear Malaysia, is strategically located nearby the government administration, centre Putrajaya, and Cyberjaya. These annual report highlights all the activities that have been through by the agency in 2011. All the achievements and triumph were highlights in this annual report. It also contained all the agency planning during 2011 to fulfill the objectives, mission and vision to become main players in nuclear research in Malaysia. Finally, there also highlights some publications contribute by all the researchers from

  5. 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)

  6. US Nuclear Regulatory Commission 1983 annual report

    International Nuclear Information System (INIS)

    1984-01-01

    The thirteen chapters of this annual report are titled: 1983 highlights/1984 planning; reactor regulation; cleanup at TMI-2; operational experience; nuclear materials; safeguards; waste management; inspection, enforcement and emergency preparedness; cooperation with the states; international programs; nuclear regulatory research; proceedings and litigation; and management and communication

  7. 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

  8. Nuclear Safety Project - annual report 1980

    International Nuclear Information System (INIS)

    1981-08-01

    The Annual Report 1980 is a detailed description (in German language) of work within the Nuclear Safety Project performed in 1980 in the nuclear safety field by KfK institutes and departments and by external institutes on behalf of KfK. It includes for each individual research activity short summaries in English language on work completed, essential results, plans for the near future. (orig./RW) [de

  9. Nuclear physics annual report 1987

    International Nuclear Information System (INIS)

    1988-01-01

    The paper presents the annual report of the Schuster Laboratory, Manchester University Nuclear Physics Group, United Kingdom, 1986-7. Much of the work has been carried out at the Daresbury Nuclear Structure Facility, often in collaboration with other U.K. groups and with foreign participation. The report contains the work on: studies of light nuclei, spectroscopy of medium mass nuclei, low and high spin spectroscopy of nuclei with A ≥ 100, and the fission process. Technical developments carried out at the Laboratory are also described. (U.K.)

  10. 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

  11. 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

  12. 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

  13. Nuclear Structure Committee annual report 1976-1977, nuclear structure grants and laboratory agreements

    International Nuclear Information System (INIS)

    1977-01-01

    The Annual Report for the period 1 August 1976 to 31 July 1977 of the Nuclear Structure Committee of the Nuclear Physics Board, under the (United Kingdom) Science Research Council, is presented. Details are given of nuclear structure grants and laboratory agreements. (U.K.)

  14. ASN annual report 2007 - ASN report abstracts on the state of Nuclear Safety and Radiation Protection in France in 2007

    International Nuclear Information System (INIS)

    2008-01-01

    The 2007 annual report of the French nuclear safety authority (ASN) presents the highlights of the year in the domain of nuclear safety and radiation protection in France. The year 2007 was marked by the implementation of a new legislative and regulatory framework created by the 13 June 2006 Act on transparency and security in the nuclear field (TSN) and the 28 June Act on the sustainable management of radioactive materials and wastes. As in the previous two years, the year was relatively satisfactory from the nuclear safety viewpoint and slightly less so with regard to small-scale nuclear activities. For two years now, the medical field has been marked by the declaration to ASN of a number of serious radiotherapy accidents which have led to several deaths or the need for extensive surgery. The following main topics are reviewed in the document: 1 - the decrees implementing the 'TSN' act and the 'Waste' act; 2 - the new ASN, one year on; 3 - ASN regulatory actions in the field of radiotherapy; 4 - regulation of new installations; 5 - the key issues for regulation of existing installations; 6 - nuclear safety and radiation protection research; 7 - policy for management of the post-accident phase of a radiological emergency; 8 - sites and soils polluted by radioactive materials; 9 - international harmonization of nuclear safety and radiation protection

  15. Annual report 2000; Rapport annuel 2000

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-07-01

    This year 2000 annual report of the CEA (atomic energy commissariat) gives a general overview of the CEA activities and organization in the domains of the defence, the nuclear energy the technological research and the fundamental research. It is presented in seven main parts: contribution to national defence, civil nuclear research, technological research for the industry, pushing back the frontiers of scientific knowledge in physics and life science, mastery of installations; institute for protection and nuclear safety, research resources. (A.L.B.)

  16. 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.)

  17. 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.)

  18. 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

  19. Papers of the Third Annual Congress of the Mexican Nuclear Society, C.A.; Memorias del Tercer Congreso Anual de la Sociedad Nuclear Mexicana, A.C.

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1992-11-01

    Once again the Sociedad Nuclear Mexicana fulfill its annual Congress being this time the installations of the Instituto de Investigaciones Electricas the place for the event with a collection of forty documents in the following areas: modelling of nuclear systems, expert systems, dosimetry, experimentation and fuel cycle among others. This significant number of papers is a sample of the great interest of the nuclear community in the participation in this forum presenting its more recent works. The participants belongs to the main institutions in the country dedicated to the technological development of the nuclear area in its different branches. Our best wishes are that this event allows not only the exchange of ideas and the knowledge of the type of works that other colleagues are developing, but also to present the opportunity to live together in a pleasant environment where the main ingredient be the surmounting spirit. We welcome all the participants to the Third Congress of our Society. (Author).

  20. Nuclear Safety Project. Annual report 1983

    International Nuclear Information System (INIS)

    1984-06-01

    The annual report 1983 is a detailed description (in German language) of work within the Nuclear Safety Project performed in 1983 in the nuclear safety field by KfK institutes and departments and by external institutes on behalf of KfK. It includes for each individual research activity short summaries in English language on work performed, results obtained and plans for future work. This report was compiled by the project management. (orig.) [de

  1. Nuclear safety project. Annual report 1985

    International Nuclear Information System (INIS)

    1986-07-01

    The annual report 1985 is a detailed description (in German language) of work within the nuclear safety project performed in 1985 in the nuclear safety field by KfK institutes and departments and by external institutes on behalf of KfK. It includes for each individual research activity short summaries in English language on work performed, results obtained and plans for future work. This report was compiled by the project management. (orig./HP) [de

  2. Annual report 1999 - Brazil Nuclear Industry (INB)

    International Nuclear Information System (INIS)

    2000-01-01

    This document presents the 1999 annual report covering the following activities: nuclear fuel, resources and application, ISO 9001, environment social activities, personnel, financial indicators, and countability

  3. 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

  4. 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

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

    International Nuclear Information System (INIS)

    Dominique Laurier; Bernd Grosche; Hall, Per

    2002-01-01

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

  6. 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

  7. 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

  8. Annual colloquium 1976 of the project nuclear safety

    International Nuclear Information System (INIS)

    1976-11-01

    The present report gives the full text of the nine papers read during the annual colloquium 1976 of the Project Nuclear Safety at Karlsruhe Nuclear Research Centre, in which the main activities and findings of the project in 1976 are contained. (RW) [de

  9. 1999 Annual Report

    International Nuclear Information System (INIS)

    1999-01-01

    This annual report presents information on the main activities carried out by the Nuclear Regulatory Authority (ARN) of Argentina during 1999, on radiation protection and nuclear safety. The work is developed in 9 chapters, 1 summary and 2 appendixes, where a description of the following activities and the bases of the Argentina Regulatory Systems are given: 1. Evolution of the nuclear regulatory activities in Argentina. Organic structures, tasks and budget. 2. Regulatory system, laws, transport of radioactive materials, safety at the management of radioactive wastes, regulatory documents issued. 3. Institutional relations with national and international organizations. 4. Inspection and evaluations of nuclear installations. Safeguards and physical protection. 5. Occupational and environmental surveillance. 6. Radiological emergencies. 7. Scientific and technological activities. Nuclear Regulatory Authority's laboratories. 8. Training, technical information and software development. 9. Radioactive facilities inspections

  10. 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

  11. 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

  12. 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

  13. 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.

  14. 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)

  15. 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

  16. 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

  17. 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)

  18. 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)

  19. 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

  20. 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)

  1. [Experimental nuclear physics]. Annual report 1989

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1989-04-01

    This is the April 1989 annual report of the Nuclear Physics Labortaory of the University of Washington. It contains chapters on astrophysics, giant resonances, heavy ion induced reactions, fundamental symmetries, polarization in nuclear reactions, medium energy reactions, accelerator mass spectrometry (AMS), research by outside users, Van de Graaff and ion sources, computer systems, instrumentation, and the Laboratory`s booster linac work. An appendix lists Laboratory personnel, Ph.D. degrees granted in the 1988-1989 academic year, and publications. Refs., 23 figs., 3 tabs.

  2. 2007 annual meeting on nuclear technology. Report

    International Nuclear Information System (INIS)

    Anon.

    2007-01-01

    This year's Annual Nuclear Technology Conference (JK) organized by the Deutsches Atomforum e.V. (DAtF) and the Kerntechnische Gesellschaft e.V. (KTG) was held in Karlsruhe on May 22-24. The attendance of more than 1,200 persons from 21 nations, and the increase in participation over the past few years, underline the role of this specialized congress as one of the leading international events in the field of the peaceful uses of nuclear power. The first day of the conference, with its plenary presentations, traditionally focused mainly on political and economic problems of the use of nuclear power. The situation of nuclear power in the United Kingdom, the key country of this year's meeting, was covered in depth. As usual, the program of the three-day event was organized as follows: plenary sessions on the first day were followed by topical sessions, technical sessions, and special events on the other days. This year, the conference featured a record program of 251 papers presented at these sessions. The 'Nuclear Power Campus' was arranged very successfully for the 5th time as an event comprising lectures and a 'hands-on' exhibition explaining the world of nuclear power in a transparent way to students from schools and universities. The special commitment to young scientists and to the preservation of competence in the nuclear field were emphasized at the JK 2007, among other things, in a workshop on 'Preservation of Competence in Nuclear Technology'. Nearly 20 young scientists presented results of their scientific work. The Annual Meeting on Nuclear Technology was accompanied by a specialized exhibition with meeting points of industry organized by 33 manufacturers, vendors, and service companies. (orig.)

  3. 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

  4. 2005 annual nuclear technology conference

    International Nuclear Information System (INIS)

    Anon.

    2005-01-01

    This year's Annual Nuclear Technology Conference of the Deutsches Atomforum and Kerntechnische Gesellschaft was held in Nuremberg on May 10-12, 2005. More than 1 100 participants from eighteen countries make this specialized event one of the largest international conventions in the field of the peaceful uses of nuclear power, whose attendance has steadily increased over the past few years. The first day of the conference was devoted to plenary lectures traditionally dealing mainly with political and economic problems of the use of nuclear power. The partner country of JK 2005 was Switzerland. Traditionally, the program of the three-day conference was organized in the proven format of plenary sessions on the first day, followed by technical sessions, specialized sessions, poster sessions, and special events on the following days. For the third time, the ''Nuclear Campus'' was organized which successfully made the world of nuclear technology transparent to high school and university students in lectures and an exhibition. The meeting was accompanied by a technical exhibition with meeting points of manufacturers, suppliers, and service industries. (orig.)

  5. 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

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

    International Nuclear Information System (INIS)

    2010-01-01

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

  7. 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)

  8. 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)

  9. 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

  10. 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

  11. 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

  12. 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

  13. 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.)

  14. 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)

  15. 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

  16. 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

  17. Nuclear Safety Project. Annual report 1986

    International Nuclear Information System (INIS)

    1987-09-01

    The annual report 1986 is a detailed description of work within the Nuclear Safety Project performed in 1986 in the nuclear safety field by KfK institutes and departments and by external institutes on behalf of KfK. It includes individual research activities on dynamic loads and strains of reactor components under accident conditions, fuel behaviour under accident conditions, investigation and control of LWR core-meltdown accidents, improvement of fission product retention and reduction of radiation exposure, and on behaviour, impact and removal of released pollutants. (DG)

  18. Proceedings of the Canadian Nuclear Society sixth annual conference

    International Nuclear Information System (INIS)

    French, P.M.; Phillips, G.J.

    1985-01-01

    The proceedings of the Sixth Annual Conference of the Canadian Nuclear Society comprise 103 papers on the following subjects: fuel technology, nuclear plant safety, instrumentation, public and regulatory matters, fusion, fuel behaviour under normal and accident conditions, nuclear plant design and operations, thermal hydraulics, reactor physics, accelerators, waste management, new reactor concepts

  19. 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)

  20. 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

  1. Nuclear Regulatory Authority of the Slovak Republic. Annual Report 2016

    International Nuclear Information System (INIS)

    2017-01-01

    A brief account of activities carried out by the Nuclear Regulatory Authority of the Slovak Republic (UJD SR) in 2016 is presented. These activities are reported under the headings: Foreword by the Chairperson; (1) Legislative activities; (2) Regulatory Activities; (3) Nuclear safety of nuclear installations; (4) Nuclear Materials; (5) Competence of the building authority; (6) Emergency planning and preparedness; (7) International activities; (8) Public relations; (9) Nuclear Regulatory Authority of the Slovak Republic; (10) Annexes; (11) Abbreviations.

  2. Institute of Nuclear Chemistry and Technology annual report 1994

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-12-31

    This annual report is a collection of short communications being a review of scientific activity of the Institute of Nuclear Chemistry and Technology, Warsaw, Poland in 1994. The papers are gathered into several branches as follows: radiation chemistry and physics (16 papers); radiochemistry, stable isotopes, nuclear analytical methods, chemistry in general (17 papers); radiobiology (6 papers); nuclear technologies and methods (30 papers). The annual report of INCT-1994 contains also a general information about the Institute, the full list of papers published in 1994, information about Nukleonika - the International Journal of Nuclear Research being edited in INCT, the list of patent granted and patent applications in 1994, information about conferences organized by the Institute, the list of Ph.D. and D.Sc. finished in 1994 as well as the list of research projects and contracts being realized in INCT during 1994.

  3. Institute of Nuclear Chemistry and Technology annual report 1994

    International Nuclear Information System (INIS)

    1995-01-01

    This annual report is a collection of short communications being a review of scientific activity of the Institute of Nuclear Chemistry and Technology, Warsaw, Poland in 1994. The papers are gathered into several branches as follows: radiation chemistry and physics (16 papers); radiochemistry, stable isotopes, nuclear analytical methods, chemistry in general (17 papers); radiobiology (6 papers); nuclear technologies and methods (30 papers). The annual report of INCT-1994 contains also a general information about the Institute, the full list of papers published in 1994, information about Nukleonika - the International Journal of Nuclear Research being edited in INCT, the list of patent granted and patent applications in 1994, information about conferences organized by the Institute, the list of Ph.D. and D.Sc. finished in 1994 as well as the list of research projects and contracts being realized in INCT during 1994

  4. Institute of Nuclear Chemistry and Technology annual report 1994

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-12-31

    This annual report is a collection of short communications being a review of scientific activity of the Institute of Nuclear Chemistry and Technology, Warsaw, Poland in 1994. The papers are gathered into several branches as follows: radiation chemistry and physics (16 papers); radiochemistry, stable isotopes, nuclear analytical methods, chemistry in general (17 papers); radiobiology (6 papers); nuclear technologies and methods (30 papers). The annual report of INCT-1994 contains also a general information about the Institute, the full list of papers published in 1994, information about Nukleonika - the International Journal of Nuclear Research being edited in INCT, the list of patent granted and patent applications in 1994, information about conferences organized by the Institute, the list of Ph.D. and D.Sc. finished in 1994 as well as the list of research projects and contracts being realized in INCT during 1994.

  5. 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

  6. 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

  7. 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)

  8. KFA Institute of Nuclear Physics. Annual report 1990

    International Nuclear Information System (INIS)

    1991-03-01

    This annual report contains extended abstracts about the work performed in the named research center together with a list of talks and publications. The work concerns experimental studies on nuclear reactions and scattering processes, nuclear spectroscopy, and intermediate-energy physics, theoretical studies on nuclear structure, nuclear reactions, and intermediate- and high-energy physics, developments of the isochronous cyclotron, the ISIS ion source, the magnetic spectrometer BIG KARL, and the cooler synchrotron COSY, as well as technical developments on spectrometers and detectors, computer systems, and radiation protection. (orig.)

  9. KFA Institute of Nuclear Physics. Annual report 1989

    International Nuclear Information System (INIS)

    1990-04-01

    This annual report contains extended abstracts about the work performed in the named research center together with a list of talks and publications. The work concerns experimental studies on nuclear reactions and scattering processes, nuclear spectroscopy, and intermediate-energy physics, theoretical studies on nuclear structure, nuclear reactions, and intermediate- and high-energy physics, developments of the isochronous cyclotron, the ISIS ion source, the magnetic spectrometer BIG KARL, and the cooler synchrotron COSY, as well as technical developments on spectrometers and detectors, computer systems, and radiation protection. (HSI)

  10. 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

  11. 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

  12. Annual report and accounts 1994/95: Scottish Nuclear

    International Nuclear Information System (INIS)

    1995-01-01

    The Annual Report and Accounts for Scottish Nuclear are presented for the year 1994/1995. Scottish Nuclear Limited produces about half of Scotland's electricity requirement in its advanced gas-cooled reactors (AGRs) at Hunterston and Torness. It also has responsibility for decommissioning the Hunterston A Magnox nuclear power station. The role of the company in the international arena and as part of the United Kingdom's electric power industry, following privatisation, are discussed. (UK)

  13. KfA Institute of Nuclear Physics. Annual report 1987

    International Nuclear Information System (INIS)

    Gruemmer, F.; Kilian, K.; Schult, O.; Seyfarth, H.; Speth, J.; Turek, P.

    1988-04-01

    This annual report contains extended abstracts about the work performed at the named institute together with a list of publications and speeches. The work concerns nuclear reactions, nuclear spectroscopy, intermediate-energy physics, nuclear structure, developments of the isochronous cyclotron and the ISIS ion source, construction of spectrometers, detectors, and targets, computer development, counting electronics, and radiation protection. (HSI)

  14. 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)

  15. 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)

  16. 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

  17. Proceedings of the Canadian Nuclear Association 35. annual conference

    International Nuclear Information System (INIS)

    Loewer, R.

    1995-01-01

    The proceedings of the thirty-fifth annual conference of the Canadian Nuclear Association contain 22 papers organized in the following sessions: update on the status of the Canadian nuclear industry, non-proliferation and related political issues, nuclear waste disposal perspectives, regulatory issues, trade development, new markets, economics of nuclear electricity, public acceptance or rejection. In addition one paper from a CNA/CNS special session on nuclear diffraction is included. The individual papers have been abstracted separately

  18. 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

  19. 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

  20. Annual conference on nuclear technology. Nuclear power 2001: option for the future

    International Nuclear Information System (INIS)

    Anon.

    2001-01-01

    The Dresden Palace for Culture was the venue of the ANNUAL MEETING ON NUCLEAR TECHNOLOGY on May 15-17, 2001, the first to be held in Dresden and the first also to be held in one of the new German federal states. Although no nuclear plant is in operation in East Germany after the Greifswald Nuclear Power Station was decommissioned, nuclear technology continues to play an important role especially in research and university teaching in this part of Germany. The organizers of the conference, Deutsches Atomforum e.V. (DAtF) and Kerntechnische Gesellschaft e.V. (KTG), welcomed more than 1000 participants from nineteen countries. The three-day program, with its traditional, proven structure, featured plenary sessions on the first day, and specialized sessions, technical sessions, poster sessions, and other events on the following days. The partner country at the Annual Meeting on Nuclear Technology was Russia, with a session specially devoted to selected topics of the country. The conference was accompanied by a technical exhibition with company meeting points of vendors, suppliers, and service industries. A video film forum was arranged for the interested public which featured contributions about nuclear research, nuclear power plant operation, transport and storage as well as decommissioning. Another major event was a workshop on 'Preserving Competence in Nuclear Technology'. The plenary day is described in this summary report, while the results of the technical sessions as seen by the rapporteurs are printed elsewhere in this issue of atw 8/9, 2001. (orig.) [de

  1. Cost estimation of thermal and nuclear power using annual securities report

    International Nuclear Information System (INIS)

    Matsuo, Yuji; Nagatomi, Yu; Murakami, Tomoko

    2011-01-01

    Cost estimation of generation cost derived from various power sources was widely conducted using model plant or annual securities report of electric utilities. Although annual securities report method was subjected to some limitation in methodology itself, useful information was obtained for cost comparison of thermal and nuclear power. Studies on generation cost evaluation of thermal and nuclear power based on this method during past five years showed that nuclear power cost was almost stable 7 Yen/kWh and thermal power cost was varying 9 - 12 Yen/kWh dependent on violent fluctuations of primary energy cost. Nuclear power was expected cost increase due to enhanced safety requirements or damage compensation of accidents as well as decommissioning and back-end cost, which were difficult to evaluate accurately with annual securities report. Further comprehensive and accurate cost estimation should be encouraged including these items. (T. Tanaka)

  2. 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)

  3. 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)

  4. Annual report of Japan Nuclear Ship Development Agency, 1980

    International Nuclear Information System (INIS)

    1981-01-01

    Japan Nuclear Ship Development Agency executed the works centering around the repair of shielding and the general inspection on safety of the nuclear-Ship Mutsu in the fiscal year 1980. On the other hand, the law revising the law concerning Japan Nuclear Ship Development Agency was enforced, and the Agency was entitled to carry out the research and investigation required for the development of new nuclear ships. As for the repair of reactor shielding, the alteration of the reactor installation was permitted in November, 1979, and the design and the method of construction were approved in August, 1980. The preparatory works were carried out from April to August, 1980, prior to the main works. The repair works were started in August, and the new shields have been manufactured, while the existing shields and the equipments in the containment vessel were removed. The completed new shields have been installed successively in the containment vessel. It was confirmed that there is no problem in the safety of the nuclear ship Mutsu, as the result of the general inspection on safety completed in June, 1980. Maintenance works were carried out for the Mutsu and the normally berthing port. The periodic measurement of radiation dose rate, the selection of the new normally berthing port, the research and development of nuclear ships and others are also reported. (Kako, I.)

  5. 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

  6. 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

  7. 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)

  8. Nuclear Regulatory Authority of the Slovak Republic. Annual Report 2015

    International Nuclear Information System (INIS)

    2016-01-01

    A brief account of activities carried out by the Nuclear Regulatory Authority of the Slovak Republic (UJD SR) in 2015 is presented. These activities are reported under the headings: Foreword by the Chairperson; (1) Legislative activities; (2) Regulatory Activities; (3) Safety of nuclear installations; (4) Nuclear Materials; (5) Competence of the building authority; (6) Emergency planning and preparedness; (7) International activities; (8) Public relations; (9) Nuclear Regulatory Authority of the Slovak Republic; (10) Annexes; (11) Abbreviations.

  9. Proceedings of the Canadian Nuclear Association 34. annual conference

    International Nuclear Information System (INIS)

    Girard, A.M.

    1994-01-01

    The proceedings of the thirty-fourth annual conference of the Canadian Nuclear Association contain 23 complete papers and three speeches organized in the following sessions: opening, plenary, new environmental regulations and their effect on the energy industry, CANDU update, life cycle management of nuclear power plants, evolution of nuclear technology, technologies for tomorrow, nuclear used fuel and disposal of low-level waste, world economics and energy consumption. The complete papers have been abstracted separately

  10. Proceedings of the Canadian Nuclear Association 34. annual conference

    Energy Technology Data Exchange (ETDEWEB)

    Girard, A M [Atomic Energy of Canada Ltd., Montreal, PQ (Canada). CANDU Operations

    1994-12-31

    The proceedings of the thirty-fourth annual conference of the Canadian Nuclear Association contain 23 complete papers and three speeches organized in the following sessions: opening, plenary, new environmental regulations and their effect on the energy industry, CANDU update, life cycle management of nuclear power plants, evolution of nuclear technology, technologies for tomorrow, nuclear used fuel and disposal of low-level waste, world economics and energy consumption. The complete papers have been abstracted separately.

  11. 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

  12. 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

  13. 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)

  14. Annual Report 2008. Nuclear Regulatory Authority

    International Nuclear Information System (INIS)

    2009-01-01

    The present Annual Report of Activities of the Nuclear Regulatory Authority (ARN), prepared regularly from the creation as independent institution, describes across four parts and seven annexes the activities developed by the organism during 2008. The main topic are: the organization and the activity of the ARN; the regulatory standards; the licensing and inspection of nuclear power plants and critical facilities; the emergency systems; the occupational surveillance; the environmental monitoring; improved organizational and budgetary developments. Also, this publication have annexes with the following content: regulatory documents; regulatory guides; measurement and evaluation of the drinking water of Ezeiza.

  15. 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

  16. Nuclear Regulatory Authority of the Slovak Republic. Annual Report 1999

    International Nuclear Information System (INIS)

    Seliga, M.

    2000-01-01

    A brief account of activities carried out by the Nuclear Regulatory Authority of the Slovak Republic in 1999 is presented. These activities are reported under the headings: (1) Foreword; (2) Mission of the Nuclear Regulatory Authority; (3) Legislation; (4) Assessment and inspection of safety at nuclear installations; (4) Safety analyses; (5) Nuclear materials; (6) Radioactive waste; (7) Quality assurance; (8) Personnel qualification and training; (9) Emergency preparedness; (10) International co-operation; (11) Public information; (12) Conclusions; (13) Appendices: Economic and personnel data; Abbreviations; The International nuclear event scales - INES

  17. 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)

  18. 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.

  19. ASN annual report 2007 - ASN report abstracts on the state of Nuclear Safety and Radiation Protection in France in 2007; ASN rapport annuel 2007

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2008-07-01

    The 2007 annual report of the French nuclear safety authority (ASN) presents the highlights of the year in the domain of nuclear safety and radiation protection in France. The year 2007 was marked by the implementation of a new legislative and regulatory framework created by the 13 June 2006 Act on transparency and security in the nuclear field (TSN) and the 28 June Act on the sustainable management of radioactive materials and wastes. As in the previous two years, the year was relatively satisfactory from the nuclear safety viewpoint and slightly less so with regard to small-scale nuclear activities. For two years now, the medical field has been marked by the declaration to ASN of a number of serious radiotherapy accidents which have led to several deaths or the need for extensive surgery. The following main topics are reviewed in the document: 1 - the decrees implementing the 'TSN' act and the 'Waste' act; 2 - the new ASN, one year on; 3 - ASN regulatory actions in the field of radiotherapy; 4 - regulation of new installations; 5 - the key issues for regulation of existing installations; 6 - nuclear safety and radiation protection research; 7 - policy for management of the post-accident phase of a radiological emergency; 8 - sites and soils polluted by radioactive materials; 9 - international harmonization of nuclear safety and radiation protection.

  20. ASN annual report 2007 - ASN report abstracts on the state of Nuclear Safety and Radiation Protection in France in 2007; ASN rapport annuel 2007

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2008-07-01

    The 2007 annual report of the French nuclear safety authority (ASN) presents the highlights of the year in the domain of nuclear safety and radiation protection in France. The year 2007 was marked by the implementation of a new legislative and regulatory framework created by the 13 June 2006 Act on transparency and security in the nuclear field (TSN) and the 28 June Act on the sustainable management of radioactive materials and wastes. As in the previous two years, the year was relatively satisfactory from the nuclear safety viewpoint and slightly less so with regard to small-scale nuclear activities. For two years now, the medical field has been marked by the declaration to ASN of a number of serious radiotherapy accidents which have led to several deaths or the need for extensive surgery. The following main topics are reviewed in the document: 1 - the decrees implementing the 'TSN' act and the 'Waste' act; 2 - the new ASN, one year on; 3 - ASN regulatory actions in the field of radiotherapy; 4 - regulation of new installations; 5 - the key issues for regulation of existing installations; 6 - nuclear safety and radiation protection research; 7 - policy for management of the post-accident phase of a radiological emergency; 8 - sites and soils polluted by radioactive materials; 9 - international harmonization of nuclear safety and radiation protection.

  1. 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

  2. Annual meeting on nuclear technology '92. Technical session 'Nuclear energy discussion'

    International Nuclear Information System (INIS)

    1992-05-01

    The report contains the six special papers red at the 1992 annual conference on nuclear engineering at Karlsruhe, all of which are individually retrievable from the database. They deal with the following subjects: historical development of the basic trends of technology criticism; communication problems in connection with the conveying of technical facts; psycho-sociological patterns of technology anxiety-mental infection or risk consciousness; field of tension between technology and journalism; handling of insecurities; ethical justifiability of nuclear energy use. (HSCH) [de

  3. 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.

  4. Annual Report 2013. Nuclear Regulatory Authority

    International Nuclear Information System (INIS)

    2010-01-01

    The present Annual Report of Activities of the Nuclear Regulatory Authority (ARN), prepared regularly from the creation as independent institution, describes across seven parts and eight annexes the activities developed by the organism during 2013. The main topic are: the organization and the activity of the ARN; the regulatory standards; the licensing and inspection of nuclear power plants and critical facilities; the emergency systems; the environmental monitoring; the occupational surveillance; the training and the public information; improved organizational and budgetary developments. Also, this publication has annexes with the following content: regulatory documents; inspections to medical; presentations of publications from ARN staff; measurement and evaluation of the drinking water of Ezeiza; international expert report on the implementation of international standards on radiation protection in the Ezeiza Atomic Center; Code of Ethics of the Nuclear Regulatory Authority.

  5. 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

  6. 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)

  7. First annual report on nuclear non-proliferation: supplement to annual report to Congress

    International Nuclear Information System (INIS)

    1979-01-01

    Section 602 of the Nuclear Non-Proliferation Act of 1978 (NNPA) requires that DOE's Annual Report include views and recommendations regarding non-proliferation policies and actions for which the Department is responsible. The Act also requires a detailed analysis of the proliferation implications of advanced enrichment and reprocessing techniques, advanced reactors, and alternative fuel cycles, including an unclassified summary and a comprehensive version containing relevant classified information. The goals of United States non-proliferation policy are to minimize the spread of nuclear weapons and to create a stable international environment for the peaceful use of nuclear energy

  8. Proceedings of the seventeenth annual Canadian Nuclear Society conference

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-12-31

    The seventeenth annual conference of the Canadian Nuclear Society, presented in Fredericton, New Brunswick. The conference includes papers on general topics of interest on the nuclear community, waste management and the environment, instrumentation and design of Candu reactors, safety analysis, thermal hydraulics, fuel channels, plant operations and in-core instrumentation.

  9. Proceedings of the seventeenth annual Canadian Nuclear Society conference

    International Nuclear Information System (INIS)

    1996-01-01

    The seventeenth annual conference of the Canadian Nuclear Society, presented in Fredericton, New Brunswick. The conference includes papers on general topics of interest on the nuclear community, waste management and the environment, instrumentation and design of Candu reactors, safety analysis, thermal hydraulics, fuel channels, plant operations and in-core instrumentation

  10. 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)

  11. Annual report 1992-93

    International Nuclear Information System (INIS)

    1993-01-01

    The mission of the Atomic Energy Regulatory Board (AERB) is to ensure that the use of ionizing radiation and nuclear energy in India does not cause undue risk to health, safety and the environment, and in it's function is supported by various Advisory Committees. The annual report of AERB for the year 1992-93 contains brief safety reviews of the new and existing nuclear power plants in India, details about the safety standards, codes and guidelines being followed in the nuclear facilities, regulatory procedures to be adopted in all the installations using radioactive materials and relevant details of other important activities of the Board. The report also contains annexures which give details about the constitution of various committees of the Board and AERB. (M.K.V.)

  12. 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

  13. Annual report of Nuclear Engineering Research Laboratory, Faculty of Engineering, University of Tokyo, fiscal year 1994

    International Nuclear Information System (INIS)

    1995-08-01

    This annual report is the summary of the research and education activities, the state of operating research facilities and others in fiscal year 1994 in this Research Laboratory. In this Research Laboratory, there are four main installations, namely the fast neutron source reactor 'Yayoi', the electron linear accelerator, the basic experiment facility for the design of nuclear fusion reactor blanket and the heavy irradiation research facility. The former two are put to the joint utilization by all Japanese universities, the blanket is to that within Faculty of Engineering, and the HIT is to that within this university. The fast neutron science research facility, the installation of which was approved in 1993 as the ancillary equipment of the Yayoi, has been put to the joint utilization for all Japan, and achieved good results. In this report, the management and operation of these main installations, research activities, the publication of research papers,graduation and degree theses, the publication of research papers, graduation and degree theses, the events in the Laboratory for one year, the list of the visitors to the Laboratory, the list of the records of official trips to foreign countries and others, and the list of UTNL reports are described. (K.I.)

  14. Centre for nuclear engineering University of Toronto annual report 1984

    International Nuclear Information System (INIS)

    1984-12-01

    The annual report of the Centre for Nuclear Engineering, University of Toronto covers the following subjects: message from the Dean; Chairman's message; origins of the centre; formation of the centre; new nuclear appointments; and activities of the centre, 1984

  15. 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

  16. 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

  17. 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

  18. 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

  19. 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)

  20. 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

  1. Annual activity report of Atomic Energy Organization of Iran 1981

    International Nuclear Information System (INIS)

    1981-01-01

    Annual research activities of atomic energy organization of Iran AEOI is described for 1981. 1.Nuclear research centre acompolishment is devoted to nuclear physics radiochemistry, reactor operation, electronic and health physics. 2.The nuclear power plants activities are centered on the maintenance of the installed equipments of power plants sites and making use of these installation in the line of countrys needs. 3.Isfahan nuclear technology has reported it's goal and according to it planned a research program for reactor control systems, preparation of pure uranium oxide from yellow cake, installation and operation of equipments for fuel pellet production. 4.The exploration centre exploited a geologic survey for the potential uranium ores and despite of difficulties and deficiences rich deposits are identifed. 5.The radiation protection centre research is allocated to a)Measuring the environmental radioactivity, b)dosimetry, c)inspection and controlling the radioactivity, of the medical and industrial centers 6.The renewable energy sources described their studies on solar energy and biogas application in Iran and finally attributes of International affiars, staff services, budget and adminis trative departments are outlined

  2. Annual report - Industrias Nucleares do Brasil S A - 1998

    International Nuclear Information System (INIS)

    1999-01-01

    The annual report of 1998 of Industrias Nucleares do Brasil S A - Brazilian company responsible for the industrial activities of the nuclear fuel cycle - introduces the next main topics: mineral resource directory main actions; industrial directory main actions; finance and administration directory main actions; transparency; environment, safety and quality; the company; and financial statements

  3. 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

  4. Shanghai institute of nuclear research, academia sinica annual report 1991

    International Nuclear Information System (INIS)

    1992-01-01

    The Annual Report is a comprehensive review of achievements made by Shanghai Institute of Nuclear Research (SINR), Academia Sinica in 1991, Which concerns nuclear physics (theories, experimentation, and application), nuclear chemistry (radiochemistry, radiopharmaceuticals, labelled compounds, analytical chemistry), radiation chemistry, accelerator physics and technology, nuclear detectors, computer application and maintenance, laboratory engineering, radiation protection and waste treatment. The maintenance, reconstruction and operation of its major facilities are also described

  5. 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)

  6. 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

  7. Civaux nuclear facilities. 2009 annual report

    International Nuclear Information System (INIS)

    2010-01-01

    This annual report is established on account of article 21 of the 2006-686 French law from June 13, 2006, relative to the transparency and safety in the nuclear domain. It describes, first, the nuclear facilities of Civaux, and then the measures taken to ensure their safety (personnel radioprotection, actions implemented for nuclear safety improvement, organisation in crisis situation, external and internal controls, technical assessment of the facilities, administrative procedures carried out in 2009), incidents and accidents registered in 2009, radioactive and chemical effluents released by the facilities in the environment, other pollutions, management of radioactive wastes, and, finally, the actions carried out in the domain of transparency and public information. A glossary and the viewpoint of the Committee of Hygiene, safety and working conditions about the content of the document conclude the report. (J.S.)

  8. Chooz nuclear facilities. 2009 annual report

    International Nuclear Information System (INIS)

    2010-01-01

    This annual report is established on account of article 21 of the 2006-686 French law from June 13, 2006, relative to the transparency and safety in the nuclear domain. It describes, first, the nuclear facilities of Chooz, and then the measures taken to ensure their safety (personnel radioprotection, actions implemented for nuclear safety improvement, organisation in crisis situation, external and internal controls, technical assessment of the facilities, administrative procedures carried out in 2009), incidents and accidents registered in 2009, radioactive and chemical effluents released by the facilities in the environment, other pollutions, management of radioactive wastes, and, finally, the actions carried out in the domain of transparency and public information. A glossary and the viewpoint of the Committee of Hygiene, safety and working conditions about the content of the document conclude the report. (J.S.)

  9. Brennilis nuclear facilities. 2009 annual report

    International Nuclear Information System (INIS)

    2010-01-01

    This annual report is established on account of article 21 of the 2006-686 French law from June 13, 2006, relative to the transparency and safety in the nuclear domain. It describes, first, the nuclear facilities of Brennilis, and then the measures taken to ensure their safety (personnel radioprotection, actions implemented for nuclear safety improvement, organisation in crisis situation, external and internal controls, technical assessment of the facilities, administrative procedures carried out in 2009), incidents and accidents registered in 2009, radioactive and chemical effluents released by the facilities in the environment, other pollutions, management of radioactive wastes, and, finally, the actions carried out in the domain of transparency and public information. A glossary and the viewpoint of the Committee of Hygiene, safety and working conditions about the content of the document conclude the report. (J.S.)

  10. 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

  11. 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)

  12. 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

  13. 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

  14. HMI Section of Nuclear and Radiation Physics - annual report 1987

    International Nuclear Information System (INIS)

    1988-01-01

    This annual report contains extended abstracts of the scientific work performed at the named institute together with a list of publications and talks. The scientific work is concerned with the theory of nuclear and atomic processes with heavy ions, the experimental study of heavy ion reactions, nuclear structure studies, nuclear solid-state physics, atomic collisions, and the operation of VICKSI. (HSI)

  15. 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

  16. 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

  17. 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

  18. Nuclear Physics Laboratory annual report 1982

    International Nuclear Information System (INIS)

    1982-06-01

    This Annual Report describes the activities of the Nuclear Physics Laboratory of the University of Washington for the year ending approximately April 30, 1982. As in previous years we report here on a strong nuclear physics research program based upon use of the Laboratory's principal facility, an FN tandem and injector accelerator system. Other major elements of the Laboratory's current program include the hydrogen parity mixing experiment, intermediate-energy experiments conducted at Los Alamos and elsewhere, an accelerator mass spectrometry program emphasizing 10 Be and 14 C measurements on environmental materials, and a number of researches carried out by Laboratory members working collaboratively at other institutions both in this country and abroad

  19. 1999 Annual Report; 1999 Informe Anual

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-07-01

    This annual report presents information on the main activities carried out by the Nuclear Regulatory Authority (ARN) of Argentina during 1999, on radiation protection and nuclear safety. The work is developed in 9 chapters, 1 summary and 2 appendixes, where a description of the following activities and the bases of the Argentina Regulatory Systems are given: 1. Evolution of the nuclear regulatory activities in Argentina. Organic structures, tasks and budget. 2. Regulatory system, laws, transport of radioactive materials, safety at the management of radioactive wastes, regulatory documents issued. 3. Institutional relations with national and international organizations. 4. Inspection and evaluations of nuclear installations. Safeguards and physical protection. 5. Occupational and environmental surveillance. 6. Radiological emergencies. 7. Scientific and technological activities. Nuclear Regulatory Authority's laboratories. 8. Training, technical information and software development. 9. Radioactive facilities inspections.

  20. 2005 Annual report

    International Nuclear Information System (INIS)

    2006-01-01

    This annual report presents information on the activities, on the scope of the radiation protection and nuclear safety, of the Nuclear Regulatory Authority (ARN) of the Argentina during 2005. The main topics are the water measurements associated with the expert's report of Ezeiza, the emergency systems, the environmental control, the institutional relations and the non-proliferation, the training and the public information, the safeguards and the physical protection, the quality assurance in the ARN, the environmental monitoring, and the human and economic resources. Also, this publication has annexes with the following content: the regulatory framework; regulatory documents; inspections to medical, industrial and training installations; international expert's report on the application of the radiological protection international standards of the public at the Ezeiza Atomic Center zone; ethical code

  1. 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

  2. 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.)

  3. 2011 annual meeting on nuclear technology fully on line

    International Nuclear Information System (INIS)

    Anon.

    2010-01-01

    The 2010 ANNUAL MEETING ON NUCLEAR TECHNOLOGY, in its familiar structure of 3 days of conferencing about topics from politics, economy, and technology, was the forum for presentations and discussions in the field of nuclear power. Participants accepted the new concept. This was borne out in particular by the great interest shown in the pre-conference evening with its keynote address, but also by the success of the plenary day, which included a press forum and a panel discussion as components of active communication making the plenary day much more attractive. The 2011 Annual Meeting on Nuclear Technology will be held again at the Berlin Congress Center (bcc) in Alexanderplatz on May 17-19. From September 1, some first important information is available under www.kerntechnik.info, for instance, the call for Papers. All other information about the program will be published in due course. All steps of importance to participants, from registration for the meeting to booking hotel accommodation, can be handled online. (orig.)

  4. 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

  5. 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

  6. 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

  7. 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

  8. 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

  9. Proceedings of the Canadian Nuclear Society 15. annual conference

    Energy Technology Data Exchange (ETDEWEB)

    Huynh, H M [Hydro-Quebec, Montreal, PQ (Canada)

    1994-12-31

    The proceedings of the 15. annual conference of the Canadian Nuclear Society cover a wide range of nuclear topics, but the emphasis is on CANDU reactors and Canadian experience. The 89 papers are arranged in 17 sessions dealing with the following subjects: thermalhydraulics, fuel channels, operations, reactor physics, fuel, new technology, safety, training, waste management. The individual papers have been abstracted separately.

  10. Proceedings of the Canadian Nuclear Society 15. annual conference

    International Nuclear Information System (INIS)

    Huynh, H.M.

    1994-01-01

    The proceedings of the 15. annual conference of the Canadian Nuclear Society cover a wide range of nuclear topics, but the emphasis is on CANDU reactors and Canadian experience. The 89 papers are arranged in 17 sessions dealing with the following subjects: thermalhydraulics, fuel channels, operations, reactor physics, fuel, new technology, safety, training, waste management. The individual papers have been abstracted separately

  11. Max-Planck-Institute for Nuclear Physics. Annual report 1987

    International Nuclear Information System (INIS)

    Klapdor, H.V.; Jessberger, E.K.

    1987-01-01

    This annual report contains short communications and extended abstracts about the work performed at the named institute together with a list of publications and talks. The work concerns technical developments on accelerators and ion sources, developments of detectors and experimental setups, electronics, data processing, target developments, giant resonances, nuclear spectroscopy, nuclear reaction mechanisms, atomic physics, medium- and high-energy physics, statistical models of nuclei and nuclear reactions, nuclear reactions at high energies, many-particle theory, quantum chromodynamics, meteorites, comets, interstellar dust, planetary atmospheres, cosmic radiation, molecular collisions in the earth atmosphere, nuclear geology and geochemistry, as well as archaeology. See hints under the relevant topics. (HSI)

  12. 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

  13. Hochtemperatur-Kernkraftwerk GmbH (HKG). Annual report 1985

    International Nuclear Information System (INIS)

    1986-01-01

    The annual report presents the agenda of the general meeting of members, held on July 3, 1986 at Hamm-Uentrop, the report of the managing board, and the annual financial statement as of December 31, 1985, including the profit and loss account of the period January 1 to December 31, 1985. The object of the HKG GmbH is the planning, financing, installation, and operation of the Hamm-Uentrop nuclear power station equipped with a high-temperature reactor, as a joint enterprise of the European partners. (UA) [de

  14. 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

  15. 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

  16. 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

  17. 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

  18. 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

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

    International Nuclear Information System (INIS)

    Enokido, Yuji; Miyasaka, Yasuhiko; Ishikawa, Hironori

    2008-01-01

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

  20. 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

  1. Planning of the regulatory inspection activity during manufacturing, construction and operation of the Italian nuclear plants

    International Nuclear Information System (INIS)

    Messore, G.A.

    1977-01-01

    After a brief review of the provisions in force in Italy on the inspection of nuclear installations the paper deals with the main criteria which determine the general and annual inspection programmes for every nuclear installation and the procedures for recording the results of inspections. It also describes the classification of nuclear installations into different categories according to the degree of hazard presented by their respective activities and consequently, the selection of the minimum number of inspections to be conducted every year for each of these categories. (NEA) [fr

  2. 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)

  3. 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)

  4. 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)

  5. 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

  6. Nuclear science. Annual report, July 1, 1980-June 30, 1981

    International Nuclear Information System (INIS)

    Friedlander, E.M.

    1982-06-01

    This annual report describes the scientific research carried out within the Nuclear Science Division between July 1, 1980 and June 30, 1981. The principal activity of the division continues to be the experimental and theoretical investigation of the interaction of heavy ions with target nuclei. Complementary research programs in light-ion nuclear science, in nuclear data evaluations, and in the development of advanced instrumentation are also carried out

  7. Annual Report of Institute of Nuclear Chemistry and Technology 2001

    International Nuclear Information System (INIS)

    2002-06-01

    The INCT 2001 Annual Report is the review of scientific activities in all branches being developed in the Institute of Nuclear Chemistry and Technology in Warsaw. The studies are connected in general with the following fields: radiation chemistry and physics, radiation technologies, radiochemistry, stable isotopes, nuclear analytical methods, chemistry in general, radiobiology, process engineering, material engineering, structural studies and diagnostics, nucleonic control systems and accelerators and nuclear analytical methods

  8. Annual Report 2004 of Institute of Nuclear Chemistry and Technology

    International Nuclear Information System (INIS)

    Michalik, J.; Smulek, W.; Godlewska-Para, E.

    2005-06-01

    The INCT 2004 Annual Report is the review of scientific activities in all branches being developed in the Institute of Nuclear Chemistry and Technology Warsaw. The studies are connected in general with the following fields: radiation chemistry and physics, radiation technologies, radiochemistry, stable isotopes, nuclear analytical methods, chemistry in general, radiobiology, process engineering, material engineering, structural studies and diagnostics, nucleonic control systems and accelerators, radiobiology and nuclear analytical methods

  9. Annual Report 2004 of Institute of Nuclear Chemistry and Technology

    Energy Technology Data Exchange (ETDEWEB)

    Michalik, J; Smulek, W; Godlewska-Para, E [eds.

    2005-06-01

    The INCT 2004 Annual Report is the review of scientific activities in all branches being developed in the Institute of Nuclear Chemistry and Technology Warsaw. The studies are connected in general with the following fields: radiation chemistry and physics, radiation technologies, radiochemistry, stable isotopes, nuclear analytical methods, chemistry in general, radiobiology, process engineering, material engineering, structural studies and diagnostics, nucleonic control systems and accelerators, radiobiology and nuclear analytical methods.

  10. Annual Report of Institute of Nuclear Chemistry and Technology 2001

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2002-06-01

    The INCT 2001 Annual Report is the review of scientific activities in all branches being developed in the Institute of Nuclear Chemistry and Technology in Warsaw. The studies are connected in general with the following fields: radiation chemistry and physics, radiation technologies, radiochemistry, stable isotopes, nuclear analytical methods, chemistry in general, radiobiology, process engineering, material engineering, structural studies and diagnostics, nucleonic control systems and accelerators and nuclear analytical methods.

  11. Nuclear science. Annual report, July 1, 1980-June 30, 1981

    Energy Technology Data Exchange (ETDEWEB)

    Friedlander, E.M. (ed.)

    1982-06-01

    This annual report describes the scientific research carried out within the Nuclear Science Division between July 1, 1980 and June 30, 1981. The principal activity of the division continues to be the experimental and theoretical investigation of the interaction of heavy ions with target nuclei. Complementary research programs in light-ion nuclear science, in nuclear data evaluations, and in the development of advanced instrumentation are also carried out.

  12. 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.)

  13. Max-Planck-Institute for Nuclear Physics. Annual report 1986

    International Nuclear Information System (INIS)

    Klapdor, H.V.; Jessberger, E.K.

    1987-01-01

    This annual report contains short descriptions of the research performed at the given institute together with an extensive list of publications. The research in nuclear physics is concerned with developments in accelerators and ion sources, radiation detectors, solid-state studies by nuclear methods, counting circuits, data processing, target preparation, fission, fusion, and nuclear friction, giant resonances, nuclear spectroscopy, nuclear reaction mechanisms, atomic physics and interaction of charged particles with matter, medium and high energy physics. The research in cosmophysics works on meteorites and lunar rocks, the gallium-solar-neutrino experiment (project GALLEX), problems of Halley's comet, interplanetary and interstellar dust, planetary atmospheres, interstellar medium and cosmic rays, molecular collision processes in the gas phase, nuclear geology and geochemistry, and archaeometry. (GG)

  14. 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.)

  15. Regulatory oversight report 2010 concerning nuclear safety in Swiss nuclear installations

    International Nuclear Information System (INIS)

    2011-06-01

    Acting as the regulatory body of the Swiss Confederation, the Swiss Federal Nuclear Safety Inspectorate, ENSI, assesses and monitors nuclear facilities in Switzerland. This includes the five nuclear power plants (NPPs), the plant-based interim storage facilities, the Central Interim Storage Facility (ZWILAG) at Wuerenlingen, the nuclear facilities at the Paul Scherrer Institute (PSI), the two universities of Basel and Lausanne, the transport of radioactive materials from and to nuclear facilities and the preparation for a deep geologic repository for radioactive waste. Using inspections, surveillance meetings, reviews and analyses as well as reports from plant licensees, ENSI obtains the required overview of the safety of the nuclear facilities. It maintains its own emergency organisation, which is an integral part of the national emergency structure. The legislative framework at the basis of the activity of ENSI specifies the criteria by which it evaluates the activities and plans of the operators of nuclear facilities. ENSI provides the public with information on particular events and observations relating to nuclear facilities. The five nuclear power plants in Switzerland (Beznau Units 1 und 2, Muehleberg, Goesgen and Leibstadt) were all operated safely in 2010. Last year, there were 39 notifiable events in Switzerland: 4 events affected both Beznau Units, 10 events the Goesgen NPP, 6 the Leibstadt NPP and 13 the Muehleberg NPP and 6 in other facilities. Based on the International Nuclear Event Scale (INES) of 0-7, ENSI rated 38 events as Level 0, and as INES Level 2 the event on 31 August 2010 during maintenance work at the Leibstadt NPP, where a diver was exposed to radiation in excess of the maximum annual exposure rate of 20 mSv. The ZWILAG at Wuerenlingen consists of several interim storage halls, a conditioning plant and the plasma plant (incineration/melting plant). At the end of 2010, the cask storage hall contained 34 transport/storage casks with spent

  16. 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.

  17. 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)

  18. Lippe-Ems GmbH nuclear power stations. Annual report 1992

    International Nuclear Information System (INIS)

    1993-01-01

    The Nuclear power company Lippe-Ems GmbH (KLE) runs the Emsland Nuclear Power Station (KKE) in Lingen (Ems) with a 1300 MW pressurized Water reactor. Partners of KLE are VEW and Elektromark. This 1992 annual report reveals numerous financial data of the operator (balance sheet, profit and loss account.) (orig./UA) [de

  19. 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)

  20. Status of safety at Areva group facilities. 2006 annual report; Etat de surete des installations nucleaires. Rapport annuel 2006

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-07-01

    This report presents a snapshot of nuclear safety and radiation protection conditions in the AREVA group's nuclear installations in France and abroad, as well as of radiation protection aspects in service activities, as identified over the course of the annual inspections and analyses program carried out by the General Inspectorate in 2006. This report is presented to the AREVA Supervisory Board, communicated to the labor representation bodies concerned, and made public. In light of the inspections, appraisals and coordination missions it has performed, the General Inspectorate considers that the nuclear safety level of the AREVA group's nuclear installations is satisfactory. It particularly noted positive changes on numerous sites and efforts in the field of continuous improvement that have helped to strengthen nuclear safety. This has been possible through the full involvement of management teams, an improvement effort initiated by upper management, actions to increase personnel awareness of nuclear safety culture, and supervisors' heightened presence around operators. However, the occurrence of certain events in facilities has led us to question the nuclear safety repercussions that the changes to activities or organization on some sites have had. In these times of change, drifts in nuclear safety culture have been identified. The General Inspectorate considers that a preliminary analysis of the human and organizational factors of these changes, sized to match the impact the change has on nuclear safety, should be made to ensure that a guaranteed level of nuclear safety is maintained (allowance for changes to references, availability of the necessary skills, resources of the operating and support structures, etc.). Preparations should also be made to monitor the changes and spot any telltale signs of drift in the application phase. Managers should be extra vigilant and the occurrence of any drift should be systematically dealt with ahead of

  1. Annual report and balance 2003

    International Nuclear Information System (INIS)

    2004-01-01

    This annual report presents the CNEA's (National Atomic Energy Commission) activities during the year 2003. The first part is devoted to the general objectives and accomplishments of the Organization. The second part describes the programs and projects in different fields such as reactors and nuclear power plants, fuel cycle, radioactive waste management, radioisotopes and radiation, research and development in basic sciences and engineering, decommissioning of nuclear installations, etc. The evolution of the human resources and the training activities are outlined in the third part of the report. The CNEA's nuclear centers are described in part 4 and the technical assistance services and production activities in part 5. Nuclear safety and safeguards are covered in the 6th section. Parts 7 and 8 present the information on inter institutional affairs and on the CNEA related enterprises respectively. The last part is the financial accounting

  2. www.kerntechnik.info = annual meeting on nuclear technology on the web

    International Nuclear Information System (INIS)

    Anon.

    2009-01-01

    The ANNUAL MEETING ON NUCLEAR TECHNOLOGY can be found under the new Internet address of www.kerntechnik.info as of now. The Web site offers systematic access to all important information and features about this largest European specialized meeting of its kind. Pages showing the program of the Conference with its plenary session, topical sessions, technical sessions, and the ''Nuclear Power Campus'' and ''Competency Workshop'' special events, are updated continuously. In addition, contributions to the technical sessions may be submitted on line at an early point in time; registrating for the meeting as well as booking hotel accommodation are also possible on line. The next ANNUAL MEETING ON NUCLEAR TECHNOLOGY will be held at the Berlin Congress Center in Berlin/Germany on May 4-6, 2010. (orig.)

  3. 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)

  4. US Nuclear Regulatory Commission, 1984 annual report. Volume 1

    International Nuclear Information System (INIS)

    1985-01-01

    This is the 10th annual report of the US Nuclear Regulatory Commission (NRC). This report covers the major activities, events, decisions and planning that took place during fiscal year 1984 (October 1983 through September 1984) within the NRC or involving the NRC. Information is presented concerning 1984 highlights and planning for 1985; reactor regulation; cleanup at Three Mile Island Unit 2; operational experience; nuclear materials; safeguards; waste management; inspection, enforcement, quality assurance, and emergency preparedness; cooperation with the States; international programs; nuclear regulatory research; proceedings and litigation; and management and communication

  5. 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)

  6. 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

  7. 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

  8. Max-Planck-Institute for Nuclear Physics. Annual report 1988

    International Nuclear Information System (INIS)

    Klapdor, H.V.; Jessberger, E.K.

    1989-01-01

    This annual report contains short notes and abstracts about the work performed at the named institute together with a list of publications and talks. The work concerns technical developments of accelerators and ion sources, experimental and theoretical studies on nuclear structure and reactions, high-energy physics, studies on meteorites and lunar rocks, comets, interplanetary and interstellar dust, interstellar dynamics, nuclear geology, and archaeometry. See hints under the relevant topics. (HSI)

  9. Regulatory control of nuclear safety in Finland. Annual report 2008

    International Nuclear Information System (INIS)

    Kainulainen, E.

    2009-06-01

    This report covers the regulatory control of nuclear safety in 2008, including the design, construction and operation of nuclear facilities, as well as nuclear waste management and nuclear materials. The control of nuclear facilities and nuclear waste management, as well as nuclear non-proliferation, concern two STUK departments: Nuclear Reactor Regulation and Nuclear Waste and Material Regulation. It constitutes the report on regulatory control in the field of nuclear energy, which the Radiation and Nuclear Safety Authority (STUK) is required to submit to the Ministry of Employment and the Economy pursuant to section 121 of the Finnish Nuclear Energy Decree. The first parts of the report explain the basics of the nuclear safety regulation included as part of STUK's responsibilities, as well as the objectives of the operations, and briefly introduce the objects of regulation. The chapter concerning the development and implementation of legislation and regulations describes changes in nuclear legislation, as well as the progress of STUK's YVL Guide revision. The chapter also includes a summary of the application of the updated YVL Guides to nuclear facilities. The section concerning the regulation of nuclear facilities contains a complete safety assessment of the nuclear facilities currently in operation or under construction. For the nuclear facilities in operation, the section describes plant operation, events during operation, annual maintenance, development of the plants and their safety, and observations made during monitoring. Data and observations gained during regulatory activities are reviewed with a focus on ensuring the safety functions of nuclear facilities and the integrity of structures and components. The report also includes a description of the oversight of the operations and quality management of organisations, oversight of operational experience feedback activities, and the results of these oversight activities. The radiation safety of nuclear

  10. 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

  11. FY08 Annual Report for Nuclear Resonance Fluorescence Imaging

    Energy Technology Data Exchange (ETDEWEB)

    Warren, Glen A.; Caggiano, Joseph A.

    2009-01-06

    FY08 annual report for project the "Nuclear Resonance Fluorescence Imaging" project. Reviews accomplishments of last 3 years, including U-235 signature search, comparison of different photon sources, and examination of NRF measurements using monochromatic photon source.

  12. Regulatory oversight report 2015 concerning nuclear safety in Swiss nuclear installations

    International Nuclear Information System (INIS)

    2016-06-01

    The Swiss Federal Nuclear Safety Inspectorate (ENSI) assesses and monitors nuclear facilities in Switzerland. These include the five nuclear power plants (Beznau Units 1 and 2, Muehleberg, Goesgen and Leibstadt), the interim storage facilities based at each plant, the Central Interim Storage Facility (Zwilag) at Wuerenlingen together with the nuclear facilities at the Paul Scherrer Institute (PSI), the University of Basel and the Federal Institute of Technology in Lausanne (EPFL), as well as the transport of radioactive materials and the preparatory work for a deep geological repository for nuclear waste. Using a combination of inspections, regulatory meetings, examinations and analyses together with reports from the licensees of individual facilities, ENSI obtains the required overview of nuclear safety in these facilities. ENSI maintains its own emergency organization. It provides the public with information on particular events and findings in nuclear facilities. ENSI publishes an annual Radiological Protection Report and a Research and Experience Report. Chapters 1 to 4 of this Surveillance Report deal with operational experience, systems technology, radiological protection and management of the 5 Swiss nuclear power plants. Chapter 5 deals with Zwilag. Chapters 6 and 7 are devoted to the nuclear facilities at PSI and the research reactor at EPFL as well as the decommissioned University of Basel’s research reactor. Chapter 8 covers the transport of radioactive materials. The subject of Chapter 9 is the deep geological storage of radioactive waste including work within the framework of the Sectoral Plan. Finally, Chapter 10 deals with generic issues relevant to all facilities such as probabilistic safety analyses. In 2015, all five nuclear power plants in Switzerland were safely operated and ENSI concluded that each had adhered to its approved operating conditions. There were 34 reportable events at the nuclear power plants; 32 events were rated at Level 0 on

  13. Nuclear Chemistry Division annual report FY83

    International Nuclear Information System (INIS)

    Struble, G.

    1983-01-01

    The purpose of the annual reports of the Nuclear Chemistry Division is to provide a timely summary of research activities pursued by members of the Division during the preceding year. Throughout, details are kept to a minimum; readers desiring additional information are encouraged to read the referenced documents or contact the authors. The Introduction presents an overview of the Division's scientific and technical programs. Next is a section of short articles describing recent upgrades of the Division's major facilities, followed by sections highlighting scientific and technical advances. These are grouped under the following sections: nuclear explosives diagnostics; geochemistry and environmental sciences; safeguards technology and radiation effect; and supporting fundamental science. A brief overview introduces each section. Reports on research supported by a particular program are generally grouped together in the same section. The last section lists the scientific, administrative, and technical staff in the Division, along with visitors, consultants, and postdoctoral fellows. It also contains a list of recent publications and presentations. Some contributions to the annual report are classified and only their abstracts are included in this unclassified portion of the report (UCAR-10062-83/1); the full article appears in the classified portion (UCAR-10062-83/2)

  14. 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.)

  15. 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)

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2017-06-15

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

  17. Nuclear Waste Treatment Program: Annual report for FY 1986

    International Nuclear Information System (INIS)

    Burkholder, H.C.; Brouns, R.A.; Powell, J.A.

    1987-09-01

    To support DOE's attainment of its goals, Nuclear Waste Treatment Program (NWTP) is to provide technology necessary for the design and operation of nuclear waste treatment facilities by commercial enterprises as part of a licensed waste management system and problem-specific treatment approaches, waste form and treatment process adaptations, equipment designs, and trouble-shooting. This annual report describes progress during FY 1986 toward meeting these two objectives. 29 refs., 59 figs., 25 tabs

  18. Nuclear Waste Treatment Program: Annual report for FY 1986

    Energy Technology Data Exchange (ETDEWEB)

    Burkholder, H.C.; Brouns, R.A. (comps.); Powell, J.A. (ed.)

    1987-09-01

    To support DOE's attainment of its goals, Nuclear Waste Treatment Program (NWTP) is to provide technology necessary for the design and operation of nuclear waste treatment facilities by commercial enterprises as part of a licensed waste management system and problem-specific treatment approaches, waste form and treatment process adaptations, equipment designs, and trouble-shooting. This annual report describes progress during FY 1986 toward meeting these two objectives. 29 refs., 59 figs., 25 tabs.

  19. 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

  20. 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

  1. 2006 annual nuclear technology conference Aachen

    International Nuclear Information System (INIS)

    Anon.

    2006-01-01

    This year's ANNUAL NUCLEAR TECHNOLOGY CONFERENCE (JK) was organized in Aachen by the Deutsches Atomforum e.V. (DAtF) and the Kerntechnische Gesellschaft e.V. (KTG). The attendance by more than 1,200 participants from 17 nations underlines the role of this specialized congress as one of the leading events in the field of nuclear power use. For several years in a row, the number of participants has been increasing steadily. The first conference day offered plenary presentations traditionally dealing mainly with political and economic issues of the use of nuclear power, including a presentation by the President of the DAtF. The lead countries of JK 2006 were Belgium and Finland with contributions to the plenary day and special meetings on selected topics. The traditional proven scheme of the three-day meeting offered plenary sessions on the first day, and technical sessions, topical sessions, poster sessions, and special events on the following days. The 'Nuclear Power Campus' was run most successfully for the fourth time, presenting to high school students and university freshmen the world of nuclear power in a transparent way. The special commitment to the young generation was stressed at JK 2006 also by the 'Competence Preservation in Nuclear Technology' workshop. Nearly 2 dozen young scientists used the forum to present results of their work. The meeting was accompanied by a technical exhibition with meeting points established by vendors, suppliers, and service providers. (orig.)

  2. 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)

  3. Annual Report 2008. Nuclear Regulatory Authority; Informe Anual 2008. Autoridad Regulatoria Nuclear

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2009-07-01

    The present Annual Report of Activities of the Nuclear Regulatory Authority (ARN), prepared regularly from the creation as independent institution, describes across four parts and seven annexes the activities developed by the organism during 2008. The main topic are: the organization and the activity of the ARN; the regulatory standards; the licensing and inspection of nuclear power plants and critical facilities; the emergency systems; the occupational surveillance; the environmental monitoring; improved organizational and budgetary developments. Also, this publication have annexes with the following content: regulatory documents; regulatory guides; measurement and evaluation of the drinking water of Ezeiza.

  4. Institute of Nuclear Chemistry and Technology annual report 1995

    International Nuclear Information System (INIS)

    1996-01-01

    The report is a collection of short communications being a review of scientific activity of the Institute of Nuclear Chemistry and Technology (INCT), Warsaw, in 1995. The papers are gathered in several branches as follows: radiation chemistry and physics (15); radiochemistry, stable isotopes, nuclear analytical methods, chemistry in general (23); radiobiology (7); nuclear technologies and methods (21); nucleonic control systems (5). The Annual Report of INCT - 1995 contains also a general information about the staff and organization of the Institute, the full list of scientific publications and patents, conferences organized by INCT, thesis and list of projects granted by Polish and international organizations

  5. Section for nuclear physics and energy physics - Annual Report

    International Nuclear Information System (INIS)

    1992-04-01

    This annual report summarizes the research and development activities of the Section for Nuclear Physics and Energy Physics at the University of Oslo in 1991. It includes experimental and theoretical nuclear physics, as well as other fields of physics in which members of the section have participated. The report describes completed projects and work currently in progress. As in previous years, the experimental activities in nuclear physics have mainly been centered around the Cyclotron Laboratory with the SCANDITRONIX MC-35 Cyclotron. Using the CACTUS multidetector system, several experiments have been completed. Some results have been published while more data remains to be analyzed

  6. Section for nuclear physics and energy physics - Annual report

    International Nuclear Information System (INIS)

    1992-04-01

    This annual report summarizes the research and development activities of the Section for Nuclear Physics and Energy Physics at the University of Oslo in 1992. It includes experimental and theoretical nuclear physics, as well as other fields of physics in which members of the section have participated. The report describes completed projects and work currently in progress. As in previous years, the experimental activities in nuclear physics have mainly been centered around the Cyclotron Laboratory with the SCANDITRONIX MC-35 Cyclotron. Using the CACTUS multidetector system, several experiments have been completed. Some results have been published while more data remains to be analyzed

  7. Institute of Nuclear Chemistry and Technology annual report 1995

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-12-31

    The report is a collection of short communications being a review of scientific activity of the Institute of Nuclear Chemistry and Technology (INCT), Warsaw, in 1995. The papers are gathered in several branches as follows: radiation chemistry and physics (15); radiochemistry, stable isotopes, nuclear analytical methods, chemistry in general (23); radiobiology (7); nuclear technologies and methods (21); nucleonic control systems (5). The Annual Report of INCT - 1995 contains also a general information about the staff and organization of the Institute, the full list of scientific publications and patents, conferences organized by INCT, thesis and list of projects granted by Polish and international organizations.

  8. Institute of Nuclear Chemistry and Technology annual report 1995

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-12-31

    The report is a collection of short communications being a review of scientific activity of the Institute of Nuclear Chemistry and Technology (INCT), Warsaw, in 1995. The papers are gathered in several branches as follows: radiation chemistry and physics (15); radiochemistry, stable isotopes, nuclear analytical methods, chemistry in general (23); radiobiology (7); nuclear technologies and methods (21); nucleonic control systems (5). The Annual Report of INCT - 1995 contains also a general information about the staff and organization of the Institute, the full list of scientific publications and patents, conferences organized by INCT, thesis and list of projects granted by Polish and international organizations.

  9. 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

  10. 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.

  11. Annual Report of Institute of Nuclear Chemistry and Technology 1997

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-10-01

    The report is the collection of short communications being the review of the scientific activity of Institute of Nuclear Chemistry and Technology - Warsaw in 1997. The papers are gathered in several branches as follows: radiation chemistry and physics; radiochemistry, stable isotopes, nuclear analytical methods, chemistry in general; radiobiology; nuclear technologies and methods. The annual report of INCT-1997 contains also the general information about INCT as well as the full list of scientific papers being published by the staff in 1997

  12. Annual Report of Institute of Nuclear Chemistry and Technology 1997

    International Nuclear Information System (INIS)

    1998-06-01

    The report is the collection of short communications being the review of the scientific activity of Institute of Nuclear Chemistry and Technology - Warsaw in 1997. The papers are gathered in several branches as follows: radiation chemistry and physics; radiochemistry, stable isotopes, nuclear analytical methods, chemistry in general; radiobiology; nuclear technologies and methods. The annual report of INCT-1997 contains also the general information about INCT as well as the full list of scientific papers being published by the staff in 1997

  13. Institute of Nuclear Power Operations annual report, 1993

    International Nuclear Information System (INIS)

    1993-01-01

    This annual report highlights the activities of the Institute of Nuclear Power Operations. The topics of the report include the president and chairmen's joint message, overview of programs serving as the foundation for most of its activities, performance indicators for the US nuclear utility industry, and INPO's 1993 financial reports and rosters. INPO has four technical cornerstone programs that serve as the foundation for most of its activities. (1) Evaluations of nuclear power plants operated by member utilities are conducted on a regularly scheduled basis. (2) INPO supports its member utilities in their work to achieve and maintain accreditation of training programs. (3) Events analysis programs identify and communicate lessons learned from plant events so utilities can take action to prevent similar events at their plants. (4) INPO helps members improve in nuclear operations areas through assistance programs and other activities that continually evolve to meet the changing needs of the nuclear industry

  14. Institute of Nuclear Power Operations 1994 annual report

    International Nuclear Information System (INIS)

    1994-01-01

    This annual report highlights the activities of the Institute of Nuclear Power Operations. The topics of the report include the president and chairmen's joint message, overview of programs serving as the foundation for most of its activities, performance indicators for the US nuclear utility industry, and INPO's 1994 financial reports and rosters. INPO has four technical cornerstone programs that serve as the foundation for most of its activities. (1) Evaluations of nuclear power plants operated by member utilities are conducted on a regularly scheduled basis. (2) INPO supports its member utilities in their work to achieve and maintain accreditation of training programs. (3) Events analysis programs identify and communicate lessons learned from plant events so utilities can take action to prevent similar events at their plants. (4) INPO helps members improve in nuclear operations areas through assistance programs and other activities that continually evolve to meet the changing needs of the nuclear industry

  15. Institute of Nuclear Power Operations 1994 annual report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1994-12-31

    This annual report highlights the activities of the Institute of Nuclear Power Operations. The topics of the report include the president and chairmen`s joint message, overview of programs serving as the foundation for most of its activities, performance indicators for the US nuclear utility industry, and INPO`s 1994 financial reports and rosters. INPO has four technical cornerstone programs that serve as the foundation for most of its activities. (1) Evaluations of nuclear power plants operated by member utilities are conducted on a regularly scheduled basis. (2) INPO supports its member utilities in their work to achieve and maintain accreditation of training programs. (3) Events analysis programs identify and communicate lessons learned from plant events so utilities can take action to prevent similar events at their plants. (4) INPO helps members improve in nuclear operations areas through assistance programs and other activities that continually evolve to meet the changing needs of the nuclear industry

  16. ASN report abstracts on the state of Nuclear Safety and Radiation Protection in France in 2008. ASN annual report 2008

    International Nuclear Information System (INIS)

    2009-01-01

    ASN is an independent administrative authority tasked, on behalf of the state, with regulating nuclear safety and radiation protection in order to protect workers, patients and the environment from the hazards involved in nuclear activities. It also contributes to informing the public. ASN, run by a five-member commission, regulates the whole of the sector, acting in a completely impartial manner. The ASN Commission presents its report on the state of nuclear safety and radiation protection in France in 2008. Contents: A - Introduction: The year 2008. B - Key topics: 1. ASN actions to promote greater transparency; 2. EDF nuclear power plant ageing and operating life: the conditions for continued operation; 3. The prevention of malicious acts; 4. ASN regulation of the radiotherapy sector; 5. Regulating and monitoring the construction of the Flamanville 3 EPR reactor; 6. ASN's international nuclear safety responsibilities; 7. The new nuclear countries; 8. Decommissioning of basic nuclear installations and the low-level, long-lived waste disposal project. C - Overview: 1 - Nuclear activities: ionising radiations and health risks; 2 - Principles and stakeholders in the regulation of nuclear safety and radiation protection; 3 - Regulation; 4 - Regulation of nuclear activities and exposure to ionising radiations; 5 - Environmental protection; 6 - Public information and transparency; 7 - International relations; 8 - Radiological emergencies; 9 - Medical uses of ionising radiations; 10 - Industrial and research activities; 11 - Transport of radioactive materials; 12 - EDF nuclear power plants; 13 - Nuclear fuel cycle installations; 14 - Nuclear research facilities and various nuclear installations; 15 - Safe decommissioning of basic nuclear installations; 16 - Radioactive waste and polluted sites. D - Appendices: List of basic nuclear installations; ASN decisions and opinions published in 2008 in its Official Bulletin; Acronyms, abbreviations and names

  17. 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

  18. 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

  19. Annual report 1999 - Brazil Nuclear Industry (INB); Relatorio anual 1999 - Industrias Nucleares do Brasil S.A

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-07-01

    This document presents the 1999 annual report covering the following activities: nuclear fuel, resources and application, ISO 9001, environment social activities, personnel, financial indicators, and countability.

  20. 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

  1. Annual report 1991-92

    International Nuclear Information System (INIS)

    1992-01-01

    The Atomic Energy Regulatory Board (AERB) was constituted on November 15, 1983 to carry out certain regulatory and safety functions. The mission of the Board is to ensure that the use of ionizing radiation and nuclear energy in India does not cause undue risk to health, safety and the environment. The annual report of AERB for the year 1991-1992 contains a brief review of the safety aspects of Indian nuclear power plants, and other nuclear facilities, safety standards and guidelines being adopted in these installations, and the development and implementation of regulatory procedures and a comprehensive statement about the other activities of the Board. It also gives a list of training courses and seminars organised and research programmes being undertaken along with the public information campaigns. The report also contains annexures in which details about the constitution of the AERB and its various committees are given. (M.K.V.)

  2. 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

  3. Annual Report of Institute of Nuclear Chemistry and Technology 1999

    International Nuclear Information System (INIS)

    2000-06-01

    The INCT 1999 Annual Report is the review of scientific activities in all branches being developed in the Institute of Nuclear Chemistry and Technology, Warsaw. The studies are connected in general with the following fields: radiation chemistry and physics, radiation technologies, radiochemistry, stable isotopes, nuclear analytical methods, chemistry in general, radiobiology, process engineering, material engineering, structural studies and diagnostics and nucleonic control systems and accelerators

  4. Annual Report of Institute of Nuclear Chemistry and Technology 2002

    International Nuclear Information System (INIS)

    2003-06-01

    The INCT 2002 Annual Report is the review of scientific activities in all branches being developed in the Institute of Nuclear Chemistry and Technology, Warsaw. The studies are connected in general with the following fields: radiation chemistry and physics, radiation technologies, radiochemistry, stable isotopes, nuclear analytical methods, chemistry in general, radiobiology, process engineering, material engineering, structural studies and diagnostics, nucleonic control systems and accelerators

  5. Annual Report of Institute of Nuclear Chemistry and Technology 2002

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2003-06-01

    The INCT 2002 Annual Report is the review of scientific activities in all branches being developed in the Institute of Nuclear Chemistry and Technology, Warsaw. The studies are connected in general with the following fields: radiation chemistry and physics, radiation technologies, radiochemistry, stable isotopes, nuclear analytical methods, chemistry in general, radiobiology, process engineering, material engineering, structural studies and diagnostics, nucleonic control systems and accelerators.

  6. Annual Report of Institute of Nuclear Chemistry and Technology 1999

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-06-01

    The INCT 1999 Annual Report is the review of scientific activities in all branches being developed in the Institute of Nuclear Chemistry and Technology, Warsaw. The studies are connected in general with the following fields: radiation chemistry and physics, radiation technologies, radiochemistry, stable isotopes, nuclear analytical methods, chemistry in general, radiobiology, process engineering, material engineering, structural studies and diagnostics and nucleonic control systems and accelerators.

  7. Section for nuclear physics and energy physics - Annual report

    International Nuclear Information System (INIS)

    1994-08-01

    This annual report summarizes the research and development activities of the Section for Nuclear Physics and Energy Physics at the University of Oslo in 1993. It includes experimental and theoretical nuclear physics, as well as other fields of physics in which members of the section have participated. The report describes completed projects nd work currently in progress. As in previous years, the experimental activities in nuclear physics have mainly been centered around the Cyclotron Laboratory with the SCANDITRONIX MC-35 Cyclotron. Using the CACTUS multidetector system, several experiments have been completed. Some results have been published while more data remains to be analyzed. In experimental nuclear physics the section staff members are engaged within three main fields: nuclei at high temperature, high spin nuclear structure and high and intermediate energy nuclear physics. In theoretical physics the group is concerned with the many-body description of nuclear properties as well as with the foundation of quantum physics

  8. 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

  9. Nuclear Chemistry Division annual report FY83

    Energy Technology Data Exchange (ETDEWEB)

    Struble, G. (ed.)

    1983-01-01

    The purpose of the annual reports of the Nuclear Chemistry Division is to provide a timely summary of research activities pursued by members of the Division during the preceding year. Throughout, details are kept to a minimum; readers desiring additional information are encouraged to read the referenced documents or contact the authors. The Introduction presents an overview of the Division's scientific and technical programs. Next is a section of short articles describing recent upgrades of the Division's major facilities, followed by sections highlighting scientific and technical advances. These are grouped under the following sections: nuclear explosives diagnostics; geochemistry and environmental sciences; safeguards technology and radiation effect; and supporting fundamental science. A brief overview introduces each section. Reports on research supported by a particular program are generally grouped together in the same section. The last section lists the scientific, administrative, and technical staff in the Division, along with visitors, consultants, and postdoctoral fellows. It also contains a list of recent publications and presentations. Some contributions to the annual report are classified and only their abstracts are included in this unclassified portion of the report (UCAR-10062-83/1); the full article appears in the classified portion (UCAR-10062-83/2).

  10. Examination policy concerning the additional installation of No. 3 and No. 4 reactors in Takahama Nuclear Power Station and No. 3 and No. 4 reactors in Fukushima No. 2 Nuclear Power Station

    International Nuclear Information System (INIS)

    1980-01-01

    The Nuclear Safety Commission decided the annual examination policy on the modification of reactor installation in Takahama Nuclear Power Station to construct No. 3 and No. 4 reactors inquired under date of November 26, 1979, by the Minister of International Trade and Industry, so that the examination results of the accident in Three Mile Island nuclear power station are reflected to the examination for the purpose of improving reactor safety. The examination results of the accident in Three Mile Island power station are being investigated by the Committee on Examination of Reactor Safety, based on the policy shown in ''On the second report of the special committee examining the accident in a nuclear power station in the U.S.'' determined by the Nuclear Safety Commission under date of September 13, 1979. Though the Committee will further clarify the past guideline about the items concerning the criteria, design and operation management, the Committee decided the tentative policy to reflect it to safety examination. Further, a table is attached, in which 52 items to be reflected to the security measures are classified from the viewpoint of necessity to reflect them to the final examination. This table includes 13 items of criteria and examination, 7 items related to design, 10 items related to operation management, 10 antidisaster items, and 12 items related to safety research. (Wakatsuki, Y.)

  11. ASN 2009 annual report

    International Nuclear Information System (INIS)

    2010-01-01

    After a presentation of the roles, missions and organization of the ASN (the French Nuclear safety Authority), this document presents and reports its actions in various domains: ionizing radiations and health and environmental risks (knowledge on these risks and hazards, nuclear activities controlled by the ASN, surveillance of exposures to ionizing radiations), principles and actors of nuclear safety, radioprotection and environment protection control, regulation (general framework, proximity nuclear regulation, nuclear installation legal regime, radioactive material transport regulation, arrangements associated with some risks and some specific activities), control of nuclear activities and exposures to ionizing radiations, situations of radiological emergency, public information, international relationships (objectives in Europe and in the world, relationships within the EU and multilateral relationships, bilateral relationships, international convention, international conferences), regional overview of nuclear safety and radioprotection, medical and non medical uses of ionizing radiations, transport of radioactive materials, EDF nuclear plants, nuclear fuel cycle installations, nuclear research installations and other installations, basic nuclear installation dismantling safety, radioactive wastes and polluted sites. This report also provides presentations of incident and accident classification scales and law texts

  12. 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)

  13. 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

  14. Section for nuclear physics and energy physics - Annual report 1989

    International Nuclear Information System (INIS)

    1990-04-01

    The experimental activities in nuclear physics have in 1989 mainly been centered around the cyclotron laboratory with the Scanditronic MC-35 cyclotron. The installation of the CACTUS multidetector system has been completed. With 8 particle telescopes, 28 NaI detectors and 2 Ge detectors, this experimental arrangement represents a major improvement compared to earlier set-ups in the laboratory. Theoretical studies of manybody problems, and nuclear structure and reactions have continued. The study of problems related to the foundations of quantum mechanics has also been persued

  15. 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.)

  16. 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)

  17. Proceedings of NUCLEAR 2008 annual international conference on sustainable development through nuclear research and education

    International Nuclear Information System (INIS)

    Constantin, Marin; Turcu, Ilie

    2008-01-01

    The proceedings of the NUCLEAR 2008 annual international conference on sustainable development through nuclear research and education held at INR-Pitesti on May, 28 - 30 2008 contain 88 communications presented in 3 sections addressing the themes of Nuclear energy, Environmental protection, and Sustainable development. In turn these sections are addressing the following items: Section 1.1 - Nuclear safety and severe accidents (12 papers); Section 1.2 - Nuclear reactors (11 papers); Section 1.3 - Nuclear technologies and materials (20 papers); Section 2.1 - Radioprotection (5 papers); Section 2.2 - Radioactive waste management (20 papers); Section 2.3 - air, water and soil protection (5 papers); Section 3.1 - Strategies in energy (3 papers); Section 3.2 - Education, continuous formation and knowledge transfer (8 papers); Section 3.3 - International partnership for a sustainable development (4 papers)

  18. IPEN (Instituto de Pesquisas Energeticas e Nucleares) - annual report - 1997

    International Nuclear Information System (INIS)

    1998-01-01

    The annual activities report of 1997 of IPEN (Instituto de Pesquisas Energeticas e Nucleares) - Brazilian organization - introduces the next main topics: mission; permanent goals; year main achievements - health and bioengineering, industry and materials and environmental aspects, nuclear reactor technology and fuel cycle, radiation protection and nuclear assurance, human resources formation, infrastructure and support, administration innovation; more important projects summary developed in 1997; budgetary data summary; products and services commercialization; year evaluation of 1997; perspectives for 1998; projects and researches financed for resources captivated in fomentation agencies; and clients

  19. 2011 annual meeting on nuclear technology. Pt. 4. Topical sessions

    International Nuclear Information System (INIS)

    Schoenfelder, Christian; Dams, Wolfgang

    2011-01-01

    Summary report on the Topical Session of the Annual Conference on Nuclear Technology held in Berlin, 17 to 19 May 2011: - Nuclear Competence in Germany and Europe. The Topical Session: - Sodium Cooled Fast Reactors -- will be covered in a report in a further issue of atw. The reports on the Topical Sessions: - CFD-Simulations for Safety Relevant Tasks; and - Final Disposal: From Scientific Basis to Application; - Characteristics of a High Reliability Organization (HRO) Considering Experience Gained from Events at Nuclear Power Stations -- have been covered in atw 7, 8/9, and 10 (2011). (orig.)

  20. 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.)

  1. Proceedings of the first annual Nuclear Criticality Safety Technology Project

    International Nuclear Information System (INIS)

    Rutherford, D.A.

    1994-09-01

    This document represents the published proceedings of the first annual Nuclear Criticality Safety Technology Project (NCSTP) Workshop, which took place May 12--14, 1992, in Gaithersburg, Md. The conference consisted of four sessions, each dealing with a specific aspect of nuclear criticality safety issues. The session titles were ''Criticality Code Development, Usage, and Validation,'' ''Experimental Needs, Facilities, and Measurements,'' ''Regulation, Compliance, and Their Effects on Nuclear Criticality Technology and Safety,'' and ''The Nuclear Criticality Community Response to the USDOE Regulations and Compliance Directives.'' The conference also sponsored a Working Group session, a report of the NCSTP Working Group is also presented. Individual papers have been cataloged separately

  2. Annual congress of the European Association of Nuclear Medicine. EANM'14. Abstracts

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2014-10-15

    The proceedings of the annual congress of the European Association of Nuclear Medicine EANM'14 contain abstracts on the following issues: nuclear cardiology practices, PET in lymphoma, advances in nuclear cardiology, dosimetry for intra-arterial treatment in the liver, pediatric nuclear medicine, therapeutic nuclear medicine, SPECT/CT, prostate cancer, extended competencies for nuclear medicine technologists, neurosciences - neurodegeneration and neuroinflammation, radionuclide therapy and dosimetry - preclinical studies, physics and instrumentation, clinical molecular imaging, conventional and specialized nuclear medicine.

  3. 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.)

  4. 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)

  5. NEA activities in 1991. 20. Annual report of the OECD Nuclear Energy Agency

    International Nuclear Information System (INIS)

    1992-01-01

    This annual report gives informations on OECD Nuclear Energy Agency activities in 1991. This report is divided into ten chapters: 1 Trends in nuclear power. 2 Nuclear development and the fuel cycle. 3 Nuclear safety and regulation. 4 Radiation protection. 5 Radioactive waste management and disposal. 6 Nuclear science: Reactor physics, nuclear data, NEA data bank. 7 Joint projects and coordinated research programs. 8 Legal affairs. 9 informations programs. 10 relations with non-member countries

  6. 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

  7. 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.

  8. 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

  9. Progress report on nuclear science and technology in China (Vol.1). Proceedings of academic annual meeting of China Nuclear Society in 2009, No.7--nuclear fusion

    International Nuclear Information System (INIS)

    2010-11-01

    Progress report on nuclear science and technology in China (Vol. 1) includes 889 articles which are communicated on the first national academic annual meeting of China Nuclear Society. There are 10 books totally. This is the seventh one, the content is about nuclear electronics, nuclear detecting technology, pulse power technology, nuclear fusion and plasma

  10. Opening speech annual meeting on nuclear technology 2013, 14 to 16 May 2013, Berlin, Germany

    Energy Technology Data Exchange (ETDEWEB)

    Gueldner, Ralf [Deutsches Atomforum e.V. (DAtF), Berlin (Germany)

    2013-07-15

    Germany is an important location for nuclear technology also in the face of the 'Energiewende'. Our industry is not merely the object of political decisions, but it also continues to make its reliable and safe contribution to supplying energy and to this country's prosperity. The 9 nuclear power plants connected to the grid are a pillar of the energy supply especially for baseload generation, with an installed power of 12,700 MW at an average availability of over 90 %. With almost 100 billion kilowatt hours generated annually, they contributed 1/6 of the electricity generated in Germany in 2012 and made Germany the second largest nuclear power producer in the European Union. The nuclear power plants ensure, as do the other large power plants, the regional voltage and frequency stability and with their good controllability and the large standard service volume make an important contribution to integrating the production of electricity from renewables which is very high by international comparison. Nuclear technology in Germany is not restricted to the dismantling, final storage and remaining operations of plants, but rather it is made up of a vigorous, competitive nuclear industry that is among the best in the world. That does not merely show in the ranking of the nuclear power plants with the highest output rates, which placed 4 German plants in the top ten in the world also in 2012. It also becomes apparent when nuclear technology Made in Germany is sought after all over the world, in particular where the level of safety is concerned, e.g. worldwide in improving the safety of plants after the accident at Fukushima. Quite a number of safety components that are just being ordered elsewhere have been tried and tested for years already in Germany, and are supplied, installed and serviced by German suppliers and service providers. The broad range of the nuclear industry in Germany and its backing in a diverse research landscape means that the products

  11. NEA activities in 1992. 21. Annual report of the OECD Nuclear Energy Agency

    International Nuclear Information System (INIS)

    1993-01-01

    This annual report gives informations on OECD Nuclear Energy Agency activities in 1992. This report is divided into ten chapters: 1 Trends in nuclear power. 2 Nuclear development and the fuel cycle. 3 Reactor safety and regulation. 4 Radiation protection. 5 Radioactive waste management. 6 Nuclear science. 7 Joint projects. 8 Legal affairs. 9 Informations programs. 10 Relations with non-member countries

  12. 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

  13. 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

  14. 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

  15. 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.

  16. ENRESA : Second plan of research and development (1991-1995): Annual report 1993

    International Nuclear Information System (INIS)

    1994-01-01

    The annual report are articulated into following chapters: 1.- Technical management summary. 2.- Economical management summary. 3.- Participation in international projects. 4.- Low and medium Level radioactive wastes. 5.- High level radioactive wastes. 6.- Research and development in high level radioactive wastes: biosphere and geosphere-7.- Radiation protection. 8.- Decommissioning and dismantling of nuclear and radioactive installations

  17. Progress report on nuclear science and technology in China (Vol.1). Proceedings of academic annual meeting of China Nuclear Society in 2009, No.4--nuclear material

    International Nuclear Information System (INIS)

    2010-11-01

    Progress report on nuclear science and technology in China (Vol. 1) includes 889 articles which are communicated on the first national academic annual meeting of China Nuclear Society. There are 10 books totally.This is the fourth one, the content is about nuclear materials, isotope separation, nuclear chemistry and radiological chemistry.

  18. Nuclear safety research project. Annual report 1995

    International Nuclear Information System (INIS)

    Hueper, R.

    1996-08-01

    The reactor safety R and D work of the Karlsruhe Research Centre (FZK) has been part of the Nuclear Safety Research Project (PSF) since 1990. The present annual report 1995 summarizes the R and D results. The research tasks are coordinated in agreement with internal and external working groups. The contributions to this report correspond to the status of early 1996. An abstract in English precedes each of them, whenever the respective article is written in German. (orig.) [de

  19. Enhancing nuclear safety. Annual report 2015. Financial report 2015

    International Nuclear Information System (INIS)

    Le Guludec, Dominique; Niel, Jean-Christophe; Mouton, Georges-Henri; Repussard, Jacques; Schuler, Matthieu; Marchal, Valerie; Albert, Marc-Gerard; Bigot, Marie-Pierre; Brisset, Yves; Bruna, Giovanni; Charron, Sylvie; Clavelle, Stephanie; Deschamps, Patrice; Delattre, Aleth; Demeillers, Didier; Laloi, Patrick; Lorthioir, Stephane; Monti, Pascale; Rollinger, Francois; Rouyer, Veronique; Tharaud, Christine; Jaunet, Camille; Pascal-Heuze, Charlotte

    2016-01-01

    After some introductory texts proposed by several IRSN head managers, and a brief presentation of some key data illustrating the activity, the annual report presents the main strategic orientations, notably in the field of knowledge management, and of information and communication. After some images illustrating the past year, activities are presented. They first deal with safety: safety of civil nuclear facilities, from decommissioning old reactors to designing those of the future, reactor ageing, severe accidents, fuel, criticality and neutronics, fire and containment, safety and radiation protection of defence-related facilities and activities, geological disposal of radioactive wastes. They secondly deal with security and non-proliferation (nuclear security, nuclear non-proliferation, chemical weapon ban), thirdly with radiation protection for human and environment health (environment monitoring, radionuclide transfer in the environment, radon and polluted sites, human exposure, radiation protection in the workplace, effects of chronic exposures, protection in health care), and fourthly with emergency and post-accident situations (emergency and post-accident preparedness and response). The next part of the activity report addresses issues related to efficiency: improved economic and financial management, property, computer security, quality and corporate social responsibility, human resources, organisation chart. The financial report proposes a management report, financial statements with an appendix to annual accounts, and an auditor's report

  20. 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)

  1. HMI Section of Nuclear and Radiation Physics - annual report 1985

    International Nuclear Information System (INIS)

    1986-01-01

    This annual report contains extended abstracts about the work performed at the named institute concerning theoretical physics, nuclear reactions, hyperfine structure, atomic collisions, and developments of the VICKSI accelerator together with a list of publications and talks. (HSI) [de

  2. Nuclear expansion: projections and obstacles in the Far East and South Asia

    International Nuclear Information System (INIS)

    McDonald, A.; Rogner, H.H.

    2004-01-01

    The International Atomic Energy Agency (IAEA) annually publishes an analysis of medium-term projections of the development of nuclear power worldwide. The 2004 publication covers the period between the present and 2030. For the paths of minor and major expansion of nuclear power, the projections foresee an installed nuclear capacity comparable with todays's level and higher by some 50%, respectively, for 2030. The contribution of nuclear power to electricity generation will attain approx. 13 to 16%, i. e. roughly the present level. The main regions advancing the expansion of nuclear power will continue to be the Middle West and Asia with annual increases of approx. 9% of nuclear generating capacity; however, also in Eastern Europe, another 40,000 MW of plant capacity will be installed in the high expansion scenario. The report also looks into the reasons for the uncertainties of long-term analyses of the type also conducted by IAEA and, for instance, the International Energy-Agency (IAE). Major aspects involved are the cost situation and the economic and political risks of investing into nuclear power in countries with strong oppositions to the use of nuclear power. The article concludes with a few thoughts on proliferation and on the role of IAEA within the framework of global non-proliferation. (orig.)

  3. Annual Report 2003 of the Institute of Nuclear Chemistry and Technology

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2004-07-01

    The INCT 2003 Annual Report is the review of scientific activities in all branches being developed in the Institute of Nuclear Chemistry and Technology Warsaw. The studies are connected in general with the following fields: radiation chemistry and physics, radiation technologies, radiochemistry, stable isotopes, nuclear analytical methods, chemistry in general, radiobiology, process engineering, material engineering, structural studies, nucleonic control systems and accelerators.

  4. Annual Report 2003 of the Institute of Nuclear Chemistry and Technology

    International Nuclear Information System (INIS)

    2004-01-01

    The INCT 2003 Annual Report is the review of scientific activities in all branches being developed in the Institute of Nuclear Chemistry and Technology Warsaw. The studies are connected in general with the following fields: radiation chemistry and physics, radiation technologies, radiochemistry, stable isotopes, nuclear analytical methods, chemistry in general, radiobiology, process engineering, material engineering, structural studies, nucleonic control systems and accelerators

  5. Strategic Nuclear Research Collaboration - FY99 Annual Report

    Energy Technology Data Exchange (ETDEWEB)

    T. J. Leahy

    1999-07-01

    The Idaho National Engineering and Environmental Laboratory (INEEL) has created the Strategic Nuclear Research Collaboration. The SNRC brings together some of America's finest laboratory and university nuclear researchers in a carefully focused research program intended to produce ''breakthrough'' solutions to the difficult issues of nuclear economics, safety, non-proliferation, and nuclear waste. This integrated program aims to address obstacles that stand in the way of nuclear power development in the US These include fuel cycle concerns related to waste and proliferation, the need for more efficient regulatory practices, and the high cost of constructing and operating nuclear power plants. Funded at an FY99 level of $2.58M, the SNRC is focusing the efforts of scientists and engineers from the INEEL and the Massachusetts Institute of Technology to solve complex nuclear energy challenges in a carefully chosen, integrated portfolio of research topics. The result of this collaboration will be research that serves as a catalyst for future direct-funded nuclear research and technology development and which preserves and enhances the INEEL's role as America's leading national laboratory for nuclear power research. In its first year, the SNRC has focused on four research projects each of which address one or more of the four issues facing further nuclear power development (economics, safety, waste disposition and proliferation-resistance). This Annual Report describes technical work and accomplishments during the first year of the SNRC's existence.

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

    International Nuclear Information System (INIS)

    Van As, Deodandus.

    1975-11-01

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

  7. Enhancing nuclear safety. Annual report 2014. Financial report 2014

    International Nuclear Information System (INIS)

    2015-01-01

    After some introductory texts proposed by several IRSN head managers, and a brief presentation of some key data illustrating the activity, the annual report presents the main strategic orientations, notably in the field of knowledge management, and of information and communication. After some images illustrating the past year, activities are presented. They first deal with safety: Reactor safety (operating experience feedback), From decommissioning old reactors to designing those of the future, Safety of laboratories and plants, Safety regarding risks due to infrastructure near nuclear facilities, Reactor aging, Fuel: research on corrosion and deformation, Research and assessments for improved understanding of accident situations, Earthquakes: research and assessments, About defense, Geological disposal of radioactive waste. They secondly deal with security and non-proliferation (nuclear security, nuclear non-proliferation, chemical weapon ban), thirdly with radiation protection for human and environment health (environment monitoring, radionuclide transfer in the environment, radon and polluted sites, human exposure, radiation protection in the workplace, effects of low-dose chronic exposures, Organization of radiation protection at the European level, protection in health care), and fourthly with emergency and post-accident situations (emergency and post-accident preparedness and response, Emergency response tools). The next part of the activity report addresses issues related to efficiency: Real estate program (construction projects get started), Hygiene, safety, social responsibility, Human resources, Organization chart, Board of directors, Steering committee for the nuclear defense expertise Division - CODEND, Scientific council, Ethics commission composition, Nuclear safety and radiation protection Research policy committee - COR. The financial report proposes a management report, financial statements with an appendix to annual accounts, and an auditor

  8. Annual Report of Institute of Nuclear Chemistry and Technology 1998

    International Nuclear Information System (INIS)

    1999-04-01

    Actual edition of Annual Report is a full review of scientific activities of the Institute of Nuclear Chemistry and Technology (INCT), Warsaw, in 1998. The abstracts are presented in the following group of subjects: radiation chemistry and physics, radiation technologies (26); radiochemistry, stable isotopes, nuclear analytical methods, chemistry in general (25); radiobiology (11); nuclear technologies and methods - process engineering (5); material engineering, structural studies and diagnostics (9); nucleonic control systems (7). The edition also included the list of INCT scientific publications and patents as well as information on conferences organized or co-organized by the INCT in 1998

  9. 1992 Nuclear Regulatory Commission Annual Report

    International Nuclear Information System (INIS)

    1993-01-01

    This is the 18th annual report of the US Nuclear Regulatory Commission (NRC), covering events and activities occurring in fiscal year 1992 (the year ending September 30, 1992), with some treatment of events from the last quarter of calendar year 1992. The NRC was created by enactment in the Congress of the Energy Reorganization Act of 1974. It is an independent agency of the Federal Government. The five NRC Commissioners are nominated by the President and confirmed by the United States Senate. The Chairman of the Commission is appointed by the President from among the Commissioners confirmed

  10. Nuclear physics: appendix to the Daresbury annual report 1990/91

    International Nuclear Information System (INIS)

    1991-01-01

    This nuclear physics chapter of the Annual Report of the Daresbury Laboratory of the United Kingdom Science and Engineering Research Council describes the work of the Nuclear Structure Facility. In the limited space available it necessarily provides only a broad outline of the facility, its development and a flavour of the research in a selection of a few highlighted topics. This appendix complements the first volume of the Report reproducing users' short camera ready scientific reports. These describe the progress and results of each experimental proposal. Reports are grouped in five sections: research into nuclear structure with contributions ordered in increasing Z number of the nuclei studies; investigations of nuclear reaction mechanisms; nuclear theory; atomic physics; and accelerator operations, developments and instrumentation. The appendix forms a compact record of the work of the Nuclear Structure Facility for the year 1990/91. (author)

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

    International Nuclear Information System (INIS)

    2013-01-01

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

  12. External radiation levels in installations of nuclear technology center

    International Nuclear Information System (INIS)

    Maletta, Paulo Guilherme M.; Filipetto, Joao; Wakabayashi, Tetsuaki; Silva, Teogenes A. da

    2005-01-01

    The radiological protection is a basic activity of nuclear technology center so that can carry through its activities with security, having to be planned and executed with total effectiveness. One of the basic tools of the radiological protection is the adoption of monitoring programs, that have as objective generality to evaluate the radiological conditions of the workstation and to assure that these conditions are acceptable safe for the displayed individuals, either workers or members of the public, as established in the basic norms of radiological protection. The Centro de Desenvolvimento da Tecnologia Nuclear - CDTN, first institution in Brazil, created in 1952 to entirely dedicate the related works to the nuclear area, to own 39 building, of which they are kept the Triga Reactor, Irradiation Gamma Laboratory, Reject Laboratory, Calibration Dosemeters Laboratory and others. In such installations, radioactive materials are produced, handled, processed and stored, being necessary the levels of external radiation ambient monitoring. As part of the radioprotection plan, monitoring 63 points on strategically located in the external areas to the building of CDTN, using characterized and calibrated thermoluminescence dosemeters. This work describes the dose distribution of the points, the doses evaluation procedure and the 4 results carried through between 2001 and 2004. The data demonstrate the attendance to the level of security established in the basic norm, what it contributed for the operation licensing of to the IBAMA. (author)

  13. Procedures for permission of installation of nuclear power stations

    International Nuclear Information System (INIS)

    Narita, Yoriaki

    1980-01-01

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

  14. The Optimization of Radioactive Waste Management in the Nuclear Installation Decommissioning Process

    International Nuclear Information System (INIS)

    Zachar, Matej; Necas, Vladimir

    2008-01-01

    The paper presents a basic characterization of nuclear installation decommissioning process especially in the term of radioactive materials management. A large amount of solid materials and secondary waste created after implementation of decommissioning activities have to be managed considering their physical, chemical, toxic and radiological characteristics. Radioactive materials should be, after fulfilling all the conditions defined by the authorities, released to the environment for the further use. Non-releasable materials are considered to be a radioactive waste. Their management includes various procedures starting with pre-treatment activities, continuing with storage, treatment and conditioning procedures. Finally, they are disposed in the near surface or deep geological repositories. Considering the advantages and disadvantages of all possible ways of releasing the material from nuclear installation area, optimization of the material management process should be done. Emphasis is placed on the radiological parameters of materials, availability of waste management technologies, waste repositories and on the radiological limits and conditions for materials release or waste disposal. Appropriate optimization of material flow should lead to the significant savings of money, disposal capacities or raw material resources. Using a suitable calculation code e.g. OMEGA, the evaluation of the various material management scenarios and selection of the best one, based on the multi-criterion analysis, should be done. (authors)

  15. Installation and evaluation of a nitrogen-16 detector in the Ford nuclear reactor

    International Nuclear Information System (INIS)

    Burn, R.R.

    1995-01-01

    Core differential temperature is the final measure of steady-state power at the Ford nuclear reactor. During some evolutions, such as changing the number of cooling-tower fans in operation, differential temperature undergoes a transient and does not provide an accurate measure of true power. A 16 N detector was installed to provide a more stable measure of power, even under transient conditions

  16. Proceedings of NUCLEAR 2008 annual international conference on sustainable development through nuclear research and education

    International Nuclear Information System (INIS)

    Constantin, Marin; Turcu, Ilie

    2008-01-01

    The proceedings of the NUCLEAR 2008 annual international conference on sustainable development through nuclear research and education held at INR-Pitesti on May, 28 - 30 2008 contain 88 communications presented in 3 sections addressing the themes of Nuclear energy, Environmental protection, and Sustainable development. In turn these sections are addressing the following items: Section 1.1 - Nuclear safety and severe accidents (12 papers); Section 1.2 - Nuclear reactors (11 papers); Section 1.3 - Nuclear technologies and materials (20 papers); Section 2.1 - Radioprotection (5 papers); Section 2.2 - Radioactive waste management (20 papers); Section 2.3 - air, water and soil protection (5 papers); Section 3.1 - Strategies in energy (3 papers); Section 3.2 - Education, continuous formation and knowledge transfer (8 papers); Section 3.3 - International partnership for a sustainable development (4 papers). The conference proceedings where divided into two parts. This item refers particularly to the second part

  17. From the first nuclear power plant to fourth-generation nuclear power installations [on the 60th anniversary of the World's First nuclear power plant

    Science.gov (United States)

    Rachkov, V. I.; Kalyakin, S. G.; Kukharchuk, O. F.; Orlov, Yu. I.; Sorokin, A. P.

    2014-05-01

    Successful commissioning in the 1954 of the World's First nuclear power plant constructed at the Institute for Physics and Power Engineering (IPPE) in Obninsk signaled a turn from military programs to peaceful utilization of atomic energy. Up to the decommissioning of this plant, the AM reactor served as one of the main reactor bases on which neutron-physical investigations and investigations in solid state physics were carried out, fuel rods and electricity generating channels were tested, and isotope products were bred. The plant served as a center for training Soviet and foreign specialists on nuclear power plants, the personnel of the Lenin nuclear-powered icebreaker, and others. The IPPE development history is linked with the names of I.V. Kurchatov, A.I. Leipunskii, D.I. Blokhintsev, A.P. Aleksandrov, and E.P. Slavskii. More than 120 projects of various nuclear power installations were developed under the scientific leadership of the IPPE for submarine, terrestrial, and space applications, including two water-cooled power units at the Beloyarsk NPP in Ural, the Bilibino nuclear cogeneration station in Chukotka, crawler-mounted transportable TES-3 power station, the BN-350 reactor in Kazakhstan, and the BN-600 power unit at the Beloyarsk NPP. Owing to efforts taken on implementing the program for developing fast-neutron reactors, Russia occupied leading positions around the world in this field. All this time, IPPE specialists worked on elaborating the principles of energy supertechnologies of the 21st century. New large experimental installations have been put in operation, including the nuclear-laser setup B, the EGP-15 accelerator, the large physical setup BFS, the high-pressure setup SVD-2; scientific, engineering, and technological schools have been established in the field of high- and intermediate-energy nuclear physics, electrostatic accelerators of multicharge ions, plasma processes in thermionic converters and nuclear-pumped lasers, physics of compact

  18. Occupational exposures at nuclear power plants. Fourteenth annual report of the ISOE programme, 2004

    International Nuclear Information System (INIS)

    2006-01-01

    The ISOE Programme was created by the OECD Nuclear Energy Agency in 1992 to promote and co-ordinate international co-operative undertakings in the area of worker protection at nuclear power plants. The programme provides experts in occupational radiation protection with a forum for communication and exchange of experience. The ISOE databases enable the analysis of occupational exposure data from 478 operating and shutdown commercial nuclear power plants participating in the programme (representing some 90% of the world's total operating commercial reactors). The Fourteenth Annual Report of the ISOE Programme summarises achievements made during 2004 and compares annual occupational exposure data. Principal developments in ISOE participating countries are also described. (author)

  19. Occupational exposures at nuclear power plants. Eleventh annual report of the Isoe programme, 2001

    International Nuclear Information System (INIS)

    2002-01-01

    The ISOE Programme was created by the OECD Nuclear Energy Agency in 1992 to promote and co-ordinate international co-operative undertakings in the area of worker protection at nuclear power plants. The programme provides experts in occupational radiation protection with a forum for communication and exchange of experience. The ISOE databases enable the analysis of occupational exposure data from the 452 commercial nuclear power plants participating in the programme (representing some 90 per cent of the world's total operating commercial reactors). The Eleventh Annual Report of the ISOE Programme summarises achievements made during 2001 and compares annual occupational exposure data. Principal developments in ISOE participating countries are also described. (author)

  20. XXXVIII Annual meeting of the Argentine Association of Nuclear Technology (AATN 2011)

    International Nuclear Information System (INIS)

    2011-01-01

    The 38th Annual meeting of the Argentine Association of Nuclear Technology was organized by the AATN (Asociacion Argentina de Tecnologia Nuclear) in Buenos Aires, Argentine, between the 14 and 18 November of 2011. In this event 146 papers in 16 Sessions, with 13 Plenary Conferences and 3 Roundtables were presented. [es