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Sample records for safety research institute

  1. Forschungszentrum Rossendorf, Institute of Safety Research. Annual report 2004

    International Nuclear Information System (INIS)

    Weiss, F.P.; Rindelhardt, U.

    2005-01-01

    The Institute of Safety Research (ISR) is one of the six Research Institutes of Forschungszentrum Rossendorf e.V. (FZR e.V.) which is a member institution of the Wissenschaftsgemeinschaft Gottfried Wilhelm Leibniz (Leibniz Association). Together with the Institute of Radiochemistry, ISR constitutes the research programme ''Safety and Environment'' which is one from three scientific programmes of FZR. In the framework of this research programme, the institute is responsible for the two subprogrammes ''Plant and Reactor Safety'' and ''Thermal Fluid Dynamics'', respectively. We also provide minor contributions to the sub-programme ''Radio-Ecology''. Moreover, with the development of a pulsed photo-neutron source at the radiation source ELBE (Electron linear accelerator for beams of high brilliance and low emittance), we are involved in a networking project carried out by the FZR Institute of Nuclear and Hadron Physics, the Physics Department of TU Dresden, and ISR. (orig.)

  2. Forschungszentrum Rossendorf, Institute of Safety Research. Annual report 2004

    Energy Technology Data Exchange (ETDEWEB)

    Weiss, F.P.; Rindelhardt, U. (eds.)

    2005-07-01

    The Institute of Safety Research (ISR) is one of the six Research Institutes of Forschungszentrum Rossendorf e.V. (FZR e.V.) which is a member institution of the Wissenschaftsgemeinschaft Gottfried Wilhelm Leibniz (Leibniz Association). Together with the Institute of Radiochemistry, ISR constitutes the research programme ''Safety and Environment'' which is one from three scientific programmes of FZR. In the framework of this research programme, the institute is responsible for the two subprogrammes ''Plant and Reactor Safety'' and ''Thermal Fluid Dynamics'', respectively. We also provide minor contributions to the sub-programme ''Radio-Ecology''. Moreover, with the development of a pulsed photo-neutron source at the radiation source ELBE (Electron linear accelerator for beams of high brilliance and low emittance), we are involved in a networking project carried out by the FZR Institute of Nuclear and Hadron Physics, the Physics Department of TU Dresden, and ISR. (orig.)

  3. Institute for Safety Research. Annual report 1992

    International Nuclear Information System (INIS)

    Weiss, F.P.; Boehmert, J.

    1993-11-01

    The Institute is concerned with evaluating the design based safety and increasing the operational safety of technical systems which include serious sources of danger. It is further occupied with methods of mitigating the effects of incidents and accidents. For all these goals the institute does research work in the following fields: modelling and simulation of thermofluid dynamics and neutron kinetics in cases of accidents; two-phase measuring techniques; safety-related analyses and characterizing of mechanical behaviours of material; measurements and calculations of radiation fields; process and plant diagnostics; development and application of methods of decision analysis. This annual report gives a survey of projects and scientific contributions (e.g. Single rod burst tests with ZrNb1 cladding), lists publications, institute seminars and workshops, names the personal staff and describes the organizational structure. (orig./HP)

  4. Helmholtz-Zentrum Dresden-Rossendorf, Institute of Safety Research. Annual report 2010

    International Nuclear Information System (INIS)

    Gerbeth, Gunter; Schaefer, Frank

    2011-01-01

    The Institute of Safety Research (ISR) was over the past 20 years one of the six Research Institutes of Forschungszentrum Dresden-Rossendorf e.V. (FZD), which in 2010 belonged to the Wissenschaftsgemeinschaft Gottfried Wilhelm Leibniz. Together with the Institutes of Radiochemistry and Radiation Physics, ISR implements the research programme ''Nuclear Safety Research'' (NSR), which was during last years one of the three scientific programmes of FZD. NSR involves two main topics, i.e. ''Safety Research for Radioactive Waste Disposal'' and ''Safety Research for Nuclear Reactors''. The research of ISR aims at assessing and enhancing the safety of current and future reactors, the development of advanced simulation tools including their validation against experimental data, and the development of the appropriate measuring techniques for multi-phase flows and liquid metals.

  5. Helmholtz-Zentrum Dresden-Rossendorf, Institute of Safety Research. Annual report 2010

    Energy Technology Data Exchange (ETDEWEB)

    Gerbeth, Gunter; Schaefer, Frank (eds.)

    2011-07-01

    The Institute of Safety Research (ISR) was over the past 20 years one of the six Research Institutes of Forschungszentrum Dresden-Rossendorf e.V. (FZD), which in 2010 belonged to the Wissenschaftsgemeinschaft Gottfried Wilhelm Leibniz. Together with the Institutes of Radiochemistry and Radiation Physics, ISR implements the research programme ''Nuclear Safety Research'' (NSR), which was during last years one of the three scientific programmes of FZD. NSR involves two main topics, i.e. ''Safety Research for Radioactive Waste Disposal'' and ''Safety Research for Nuclear Reactors''. The research of ISR aims at assessing and enhancing the safety of current and future reactors, the development of advanced simulation tools including their validation against experimental data, and the development of the appropriate measuring techniques for multi-phase flows and liquid metals.

  6. Proceedings of Twenty-Seventh Annual Institute on Mining Health, Safety and Research

    Energy Technology Data Exchange (ETDEWEB)

    Bockosh, G.R. [ed.] [Pittsburgh Research Center, US Dept. of Energy (United States); Langton, J. [ed.] [Mine Safety and Health Administration, US Dept. of Labor (United States); Karmis, M. [ed.] [Virginia Polytechnic Institute and State University. Dept. of Mining and Minerals Engineering, Blacksburg (United States)

    1996-12-31

    This Proceedings contains the presentations made during the program of the Twenty-Seventh Annual Institute on Mining Health, Safety and Research held at Virginia Polytechnic Institute and State University, Blacksburg, Virginia, on August 26-28, 1996. The Twenty-Seventh Annual Institute on Mining, Health, Safety and Research was the latest in a series of conferences held at Virginia Polytechnic Institute and State University, cosponsored by the Mine Safety and Health Administration, United States Department of Labor, and the Pittsburgh Research Center, United States Department of Energy (formerly part of the Bureau of Mines, U. S. Department of Interior). The Institute provides an information forum for mine operators, managers, superintendents, safety directors, engineers, inspectors, researchers, teachers, state agency officials, and others with a responsible interest in the important field of mining health, safety and research. In particular, the Institute is designed to help mine operating personnel gain a broader knowledge and understanding of the various aspects of mining health and safety, and to present them with methods of control and solutions developed through research. Selected papers have been processed separately for inclusion in the Energy Science and Technology database.

  7. Forschungszentrum Rossendorf. Institute of Safety Research. Annual report 1998

    International Nuclear Information System (INIS)

    Weiss, F.P.; Rindelhardt, U.

    1999-07-01

    The Institute of Safety Research is one of the five scientific institutes of Forschungszentrum Rossendorf e.V. The Forschungszentrum Rossendorf is a member of the 'Wissenschaftsgemeinschaft Gottfried Wilhelm Leibniz' und is funded by the Federal Ministry of Education and Research and by the Saxon Ministry of Science and Arts with 50% each. The research work of the institute aims at the assessment and increase of the safety and environmental sustainability of technical plants. The emphasis is put on the development and validation of mathematical and physical models for process and plant analysis, and of techniques for process and components monitoring. Subject of investigations are equally nuclear plants and installations of process industries. (orig.)

  8. 75 FR 12554 - Mine Safety and Health Research Advisory Committee, National Institute for Occupational Safety...

    Science.gov (United States)

    2010-03-16

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES Centers for Disease Control and Prevention Mine Safety and Health Research Advisory Committee, National Institute for Occupational Safety and Health (MSHRAC, NIOSH... priorities in mine safety and health research, including grants and contracts for such research, 30 U.S.C...

  9. 78 FR 40743 - Mine Safety and Health Research Advisory Committee, National Institute for Occupational Safety...

    Science.gov (United States)

    2013-07-08

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES Centers for Disease Control and Prevention Mine Safety and Health Research Advisory Committee, National Institute for Occupational Safety and Health (MSHRAC, NIOSH... Director, NIOSH, on priorities in mine safety and health research, including grants and contracts for such...

  10. 77 FR 40622 - Mine Safety and Health Research Advisory Committee, National Institute for Occupational Safety...

    Science.gov (United States)

    2012-07-10

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES Centers for Disease Control and Prevention Mine Safety and Health Research Advisory Committee, National Institute for Occupational Safety and Health (MSHRAC, NIOSH..., oxygen supply partnership, safety culture, occupational health and safety management systems, preventing...

  11. Forschungszentrum Rossendorf, Institute for Safety Research. Annual report 1995

    International Nuclear Information System (INIS)

    Weiss, F.P.; Rindelhardt, U.

    1996-09-01

    The scientific work of the Institute of Safety Research covers a wide range of safety related investigations. During 1995 important results on thermo-fluid dynamic single effects, thermalhydraulics and neutron kinetics for accident analysis, materials safety, simulation of radiation and particle transport, mechanical integrity of technical systems and process monitoring, risk management for waste deposits, magneto-hydrodynamics of conductive fluids, and of renewable energies were reached. The annual report presents also lists of publications, conference contributions, meetings, and workshops. (DG)

  12. The Armstrong Institute: An Academic Institute for Patient Safety and Quality Improvement, Research, Training, and Practice.

    Science.gov (United States)

    Pronovost, Peter J; Holzmueller, Christine G; Molello, Nancy E; Paine, Lori; Winner, Laura; Marsteller, Jill A; Berenholtz, Sean M; Aboumatar, Hanan J; Demski, Renee; Armstrong, C Michael

    2015-10-01

    Academic medical centers (AMCs) could advance the science of health care delivery, improve patient safety and quality improvement, and enhance value, but many centers have fragmented efforts with little accountability. Johns Hopkins Medicine, the AMC under which the Johns Hopkins University School of Medicine and the Johns Hopkins Health System are organized, experienced similar challenges, with operational patient safety and quality leadership separate from safety and quality-related research efforts. To unite efforts and establish accountability, the Armstrong Institute for Patient Safety and Quality was created in 2011.The authors describe the development, purpose, governance, function, and challenges of the institute to help other AMCs replicate it and accelerate safety and quality improvement. The purpose is to partner with patients, their loved ones, and all interested parties to end preventable harm, continuously improve patient outcomes and experience, and eliminate waste in health care. A governance structure was created, with care mapped into seven categories, to oversee the quality and safety of all patients treated at a Johns Hopkins Medicine entity. The governance has a Patient Safety and Quality Board Committee that sets strategic goals, and the institute communicates these goals throughout the health system and supports personnel in meeting these goals. The institute is organized into 13 functional councils reflecting their behaviors and purpose. The institute works daily to build the capacity of clinicians trained in safety and quality through established programs, advance improvement science, and implement and evaluate interventions to improve the quality of care and safety of patients.

  13. Operational safety experience at 14 MW research reactor from Institute for Nuclear Research Pitesti

    International Nuclear Information System (INIS)

    Ciocanescu, M.

    2007-01-01

    The main challenges identified in TRIGA Research Reactor operated in Institute for Nuclear Research in Pitesti, Romania, are in fact similar with challenges of many other research reactors in the world, those are: Ageing of work forces and knowledge management; Maintaining an enhanced technical and scientific competences; Ensuring adequate financial and human resources; Enhancing excellence in management; Ensuring confidence of stakeholders and public; Ageing of equipment and systems.To ensure safety availability of TRIGA Research Reactor in INR Pitesti, the financial resources were secured and a large refurbishment programme and modernization was undertaking by management of institute. This programme concern the modernization of reactor control and safety systems, primary cooling system instrumentation, radiation protection and releases monitoring with new spectrometric computerized abilities, ventilation filtering system and cooling towers. The expected life extension of the reactor will be about 15 years

  14. Forschungszentrum Rossendorf. Institute of Safety Research. Report. January 1998 - June 1999

    Energy Technology Data Exchange (ETDEWEB)

    Weiss, F P; Rindelhardt, U [eds.

    1999-09-01

    The Institute of Safety Research is one of the five scientific institutes of Forschungszentrum Rossendorf e.V. The Forschungszentrum Rossendorf is a member of the 'Wissenschaftsgemeinschaft Gottfried Wilhelm Leibniz' and is funded by the Federal Ministry of Education and Research and by the Saxon Ministry of Science and Arts with 50% each. The research work of the institute aims at the assessment and increase of the safety and environmental sustainability of technical plants. The emphasis is put on the development and validation of mathematical and physical models for process and plant analysis, and of techniques for process and components monitoring. Subject of investigations are equally nuclear plants and installations of process industries. To analyse the thermo-fluiddynamics of normal plant operation and of the behaviour during accidents, physical models and computer codes are developed for multi-phase and multi-component flows, and for the space and time dependent heat release (neutron kinetics, chemical kinetics). (orig.)

  15. Forschungszentrum Rossendorf. Institute of Safety Research. Report. January 1998 - June 1999

    Energy Technology Data Exchange (ETDEWEB)

    Weiss, F.P.; Rindelhardt, U. [eds.

    1999-09-01

    The Institute of Safety Research is one of the five scientific institutes of Forschungszentrum Rossendorf e.V. The Forschungszentrum Rossendorf is a member of the 'Wissenschaftsgemeinschaft Gottfried Wilhelm Leibniz' and is funded by the Federal Ministry of Education and Research and by the Saxon Ministry of Science and Arts with 50% each. The research work of the institute aims at the assessment and increase of the safety and environmental sustainability of technical plants. The emphasis is put on the development and validation of mathematical and physical models for process and plant analysis, and of techniques for process and components monitoring. Subject of investigations are equally nuclear plants and installations of process industries. To analyse the thermo-fluiddynamics of normal plant operation and of the behaviour during accidents, physical models and computer codes are developed for multi-phase and multi-component flows, and for the space and time dependent heat release (neutron kinetics, chemical kinetics). (orig.)

  16. Forschungszentrum Rossendorf, Institute of Safety Research. Annual report 1996

    International Nuclear Information System (INIS)

    Weiss, F.P.; Rindelhardt, U.

    1997-08-01

    The research of the institute aims at the safety assessment of the design of nuclear and chemical facilities, the development of accident management procedures, and the increase of operational safety by improved plant surveillance. Physical models and computer codes are developed for multiphase/multicomponent flows and for the space and time dependent power release in nuclear and chemical reactors to be able to analyse the thermo-fluiddynamic phenomena during assumed accident scenarios. Emphasis is particularly focussed on spatial flow phenomena and the time dependent change of flow patterns. Sustainable void fraction probes and tomographic systems are developed to measure those parameters of two phase flows that characterize the exchange of pulse, energy and mass between the phases and components. The research related to materials safety is directed to the behaviour of components exposed to neutron and gamma radiation. The susceptibility to irradiation induced embrittlement and the behaviour of annealed material during reirradiation are investigated by fracture mechanical methods in dependence on the materials composition. The work on process and plant diagnostics makes available basic methods for early failure detection and operational monitoring which are important means of accident prevention. Recent initiatives of the institute are concerned with the transport of pollutants in the geosphere. Particularly, codes are developed for the simulation of physical and chemical processes during the transport of pollutants in unsaturated zones of the soil. (orig.)

  17. Forschungszentrum Rossendorf, Institute of Safety Research. Annual report 1996

    Energy Technology Data Exchange (ETDEWEB)

    Weiss, F P; Rindelhardt, U [eds.

    1997-08-01

    The research of the institute aims at the safety assessment of the design of nuclear and chemical facilities, the development of accident management procedures, and the increase of operational safety by improved plant surveillance. Physical models and computer codes are developed for multiphase/multicomponent flows and for the space and time dependent power release in nuclear and chemical reactors to be able to analyse the thermo-fluiddynamic phenomena during assumed accident scenarios. Emphasis is particulary focussed on spatial flow phenomena and the time dependent change of flow patterns. Sustainable void fraction probes and tomographic systems are developed to measure those parameters of two phase flows that characterize the exchange of pulse, energy and mass between the phases and components. The research related to materials safety is directed to the behaviour of components exposed to neutron and gamma radiation. The susceptibility to irradiation induced embrittlement and the behaviour of annealed material during reirradiation are investigated by fracture mechanical methods in dependence on the materials composition. The work on process and plant diagnostics makes available basic methods for early failure detection and operational monitoring which are important means of accident prevention. Recent initiatives of the institute are concerned with the transport of pollutants in the geosphere. Particularly, codes are developed for the simulation of physical and chemical processes during the transport of pollutants in unsaturated zones of the soil. (orig.)

  18. Paul Scherrer Institut annual report 1994. Annex IV: PSI nuclear energy and safety research progress report 1994

    Energy Technology Data Exchange (ETDEWEB)

    Williams, T; Kallfelz, J M; Mathews, D [eds.; Paul Scherrer Inst. (PSI), Villigen (Switzerland)

    1995-10-01

    Nuclear energy research in Switzerland is concentrated at PSI. It is explicitly mentioned in the Institute`s official charter and commands about one fifth of the Institute`s federal resources. Presently, PSI invests approx. 200 py/a in nuclear energy research, one third of this being externally funded; the share of external funding in investment costs totals approx. 50%. This funding is provided by the Swiss utilities and the NAGRA, the Safety Authority (HSK) and the former National Fund for Energy Research (NEFF). PSI`s activities in nuclear research concentrate on three main areas: safety of operating plants, safety features of future reactor concepts and waste management. 7% of personnel are invested in addressing global aspects of energy. (author) figs., tabs., refs.

  19. Safety considerations of new critical assembly for the Research Reactor Institute, Kyoto University

    International Nuclear Information System (INIS)

    Umeda, Iwao; Matsuoka, Naomi; Harada, Yoshihiko; Miyamoto, Keiji; Kanazawa, Takashi

    1975-01-01

    The new critical assembly type of nuclear reactor having three cores for the first time in the world was completed successfully at the Research Reactor Institute of Kyoto University in autumn of 1974. It is called KUCA (Kyoto University Critical Assembly). Safety of the critical assembly was considered sufficiently in consequence of discussions between the researchers of the institute and the design group of our company, and then many bright ideas were created through the discussions. This paper is described the new safety design of main equipments - oil pressure type center core drive mechanism, removable water overflow mechanism, core division mechanism, control rod drive mechansim, protection instrumentation system and interlock key system - for the critical assembly. (author)

  20. Institutional Oversight of Occupational Health and Safety for Research Programs Involving Biohazards.

    Science.gov (United States)

    Dyson, Melissa C; Carpenter, Calvin B; Colby, Lesley A

    2017-06-01

    Research with hazardous biologic materials (biohazards) is essential to the progress of medicine and science. The field of microbiology has rapidly advanced over the years, partially due to the development of new scientific methods such as recombinant DNA technology, synthetic biology, viral vectors, and the use of genetically modified animals. This research poses a potential risk to personnel as well as the public and the environment. Institutions must have appropriate oversight and take appropriate steps to mitigate the risks of working with these biologic hazards. This article will review responsibilities for institutional oversight of occupational health and safety for research involving biologic hazards.

  1. Forschungszentrum Rossendorf, Institute of Safety Research. Annual report 1999

    International Nuclear Information System (INIS)

    Weiss, F.P.; Rindelhardt, U.

    2000-02-01

    The work of the institute is directed to the assessment and enhancement of the safety of large technical plants and to the increase of the effectiveness and environmental sustainability of those facilities. Subjects of investigations are equally nuclear plants and installations of process industries. To achieve the above mentioned goals, the institute is engaged in two scientific fields, i.e. thermo-fluiddynamics including magneto-hydrodynamics (MHD) and materials/components safety. (orig.)

  2. Forschungszentrum Rossendorf, Institute of Safety Research. Annual report 1997

    Energy Technology Data Exchange (ETDEWEB)

    Weiss, F P; Rindelhardt, U [eds.

    1998-10-01

    The research work of the institute aims at the assessment and increase of the safety of technical facilities. Subject of the investigation are equally nuclear plants and installations of process industries. To analyse thermo-fluiddynamic phenomena of accident scenarios physical models and computer codes are developed as well for multi-phase and multi-component flows as for the time and space dependent power release (neutron kinetics in light water reactors, reaction kinetics of exothermic chemical reactions). Emphasis is put on the description of spatial flows and the transient evolution of flow patterns. (orig.)

  3. Paul Scherrer Institut annual report 1994. Annex IV: PSI nuclear energy and safety research progress report 1994

    International Nuclear Information System (INIS)

    Williams, T.; Kallfelz, J.M.; Mathews, D.

    1995-01-01

    Nuclear energy research in Switzerland is concentrated at PSI. It is explicitly mentioned in the Institute's official charter and commands about one fifth of the Institute's federal resources. Presently, PSI invests approx. 200 py/a in nuclear energy research, one third of this being externally funded; the share of external funding in investment costs totals approx. 50%. This funding is provided by the Swiss utilities and the NAGRA, the Safety Authority (HSK) and the former National Fund for Energy Research (NEFF). PSI's activities in nuclear research concentrate on three main areas: safety of operating plants, safety features of future reactor concepts and waste management. 7% of personnel are invested in addressing global aspects of energy. (author) figs., tabs., refs

  4. Paul Scherrer Institut annual report 1996. Annex IV: PSI nuclear energy and safety research

    International Nuclear Information System (INIS)

    Birchley, J.; Roesel, R.; Wellner, A.

    1997-01-01

    The department 'Nuclear Energy and Safety Research' (F4) at PSI carries the responsibility of performing the essential nuclear energy research in Switzerland. This research is part of the remit of PSI and follows government directive; about one-fifth of the Institute's Federal budget is allocated to this task. Currently about 190 persons are working in this field. Approximately 45% of the salary and investment costs (5.5 million CHF in the budget period 1996/97) are externally funded. This funding is provided primarily by the Swiss Utilities, the NAGRA and the safety authority HSK. The activities in nuclear research concentrate on three main domains: safety and safety related problems of operating plants, safety features of future reactor and fuel cycle concepts and waste management; another 4% of staff are addressing broader aspects of energy. At the end of 1996, a policy evaluation with the laboratory heads took place in order to redefine the direction of F4 activities. (author) figs., tabs., refs

  5. 77 FR 25179 - Patient Safety Organizations: Voluntary Relinquishment From Surgical Safety Institute

    Science.gov (United States)

    2012-04-27

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES Agency for Healthcare Research and Quality Patient Safety... voluntary relinquishment from the Surgical Safety Institute of its status as a Patient Safety Organization (PSO). The Patient Safety and Quality Improvement Act of 2005 (Patient Safety Act) authorizes the...

  6. Annual report for FY 2012 on the activities of radiation safety in Nuclear Science Research Institute etc. April 1, 2012 - March 31, 2013

    International Nuclear Information System (INIS)

    2014-02-01

    This annual report describes the activities in the 2012 fiscal year of Department of Radiation Protection in Nuclear Science Research Institute, Safety Section in Takasaki Advanced Radiation Research Institute, Safety Section in Kansai Photon Science Institute, Operation Safety Administration Section in Aomori Research and Development Center and Safety Section in Naka Fusion Institute. The activities described are environmental monitoring, radiation protection practices in workplaces, individual monitoring, maintenance of monitoring instruments, and research and development of radiation protection. At these institutes the occupational exposures did not exceed the dose limits. The radioactive gaseous and liquid discharges from the facilities were well below the prescribed limits. The radiological situations at the institutes in Tokai, Aomori and Naka have been affected by the Fukushima Dai-ichi nuclear power plant accident in March 2011. The research and development activities produced certain results in the fields of radiation protection technique. The radiation protection experts in the institutes actively participated in the projects after the Fukushima nuclear power plant accident. (author)

  7. Annual report for FY 2012 on the activities of radiation safety in Nuclear Science Research Institute etc. April 1, 2012 - March 31, 2013

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2014-02-15

    This annual report describes the activities in the 2012 fiscal year of Department of Radiation Protection in Nuclear Science Research Institute, Safety Section in Takasaki Advanced Radiation Research Institute, Safety Section in Kansai Photon Science Institute, Operation Safety Administration Section in Aomori Research and Development Center and Safety Section in Naka Fusion Institute. The activities described are environmental monitoring, radiation protection practices in workplaces, individual monitoring, maintenance of monitoring instruments, and research and development of radiation protection. At these institutes the occupational exposures did not exceed the dose limits. The radioactive gaseous and liquid discharges from the facilities were well below the prescribed limits. The radiological situations at the institutes in Tokai, Aomori and Naka have been affected by the Fukushima Dai-ichi nuclear power plant accident in March 2011. The research and development activities produced certain results in the fields of radiation protection technique. The radiation protection experts in the institutes actively participated in the projects after the Fukushima nuclear power plant accident. (author)

  8. 78 FR 21607 - National Institute for Occupational Safety and Health Partnership Opportunity on a Research...

    Science.gov (United States)

    2013-04-11

    ... Institute for Occupational Safety and Health Partnership Opportunity on a Research Project To Evaluate the... disposable (single use) gown submitted; (3) A minimum of 200 ``new'' (unprocessed, unused, unwashed) reusable... performance criteria for single-use and reusable isolation gowns. The research objective is to evaluate...

  9. Annual report for FY 2010 on the activities of radiation safety in Nuclear Science Research Institute etc. April 1, 2010 - March 31, 2011

    International Nuclear Information System (INIS)

    2012-03-01

    This annual report describes the activities of Radiation Protection Sector in Department of Radiation Protection in Nuclear Science Research Institute, Safety Section in Takasaki Advanced Radiation Research Institute, Safety Section in Kansai Photon Science Institute, Operation Safety Administration Section in Aomori Research and Development Center and Safety Section in Naka Fusion Institute. The activities described are environmental monitoring, radiation protection in workplaces, individual monitoring, maintenance of monitoring instruments, and research and development of radiation protection. At these institutes the occupational exposures did not exceed the dose limits. The radioactive gaseous and liquid discharges from the facilities were well below the prescribed limits. The research and development activities obtained certain results in the fields of operational radiation protection technique and the construction of calibration fields for neutron beams. The institutes in Tokai, Takasaki, Aomori and Naka were suffered from the Great East Japan Earthquake and the nuclear power plant accident which followed the earthquake. (author)

  10. Overview of research potential of Institute for Nuclear Research

    International Nuclear Information System (INIS)

    Ciocanescu, Marin

    2007-01-01

    The main organizations involved in nuclear power production in Romania, under supervision of Presidency, Prime Minister and Parliament are: CNCAN (National Commission for Nuclear Activities Control), Nuclear Agency, Ministry of Economy and Commerce, ANDRAD (Waste Management Agency), SNN (Nuclearelectrica National Society), RAAN (Romanian Authority for Nuclear Activities), ICN (Institute for Nuclear Research - Pitesti), SITON (Center of Design and Engineering for Nuclear Projects- Bucharest); ROMAG-PROD (Heavy Water Plant), CNE-PROD (Cernavoda Nuclear Power Plant - Production Unit), CNE-INVEST (Cernavoda Nuclear Power Plant -Investments Unit), FCN (Nuclear Fuel Factory). The Institute for Nuclear Research, Pitesti INR, Institute for Nuclear Research, Pitesti is endowed with a TRIGA Reactor, Hot Cells, Materials Laboratories, Nuclear Fuel, Nuclear Safety Laboratories, Nuclear Fuel, Nuclear Safety. Waste management. Other research centers and laboratories implied in nuclear activities are: ICIT, National Institute for cryogenics and isotope technologies at Rm Valcea Valcea. with R and D activity devoted to heavy water technologies, IFIN, Institute for nuclear physics and engineering, Bucharest, as well as the educational institutions involved in atomic energy applications and University research, Politechnical University Bucharest, University of Bucharest, University of Pitesti, etc. The INR activity outlined, i.e. the nuclear power research as a scientific and technical support for the Romanian nuclear power programme, mainly dedicated to the existing NPP in the country (CANDU). Focused with priority are: - Nuclear Safety (behavior of plant materials, components, installations during accident conditions and integrity investigations); - Radioactive Waste Management Radioactive; - Radioprotection; Product and services supply for NPP. INR Staff numbers 320 R and D qualified and experienced staff, 240 personnel in devices and prototype workshops and site support

  11. Institute for safety technology

    International Nuclear Information System (INIS)

    1991-01-01

    In the area of nuclear reactor safety studies, the Institute for Safety Technology (STI) concentrated its efforts in analysing experimentally and numerically phenomena which characterize highly-improbable but very severe accidents either for light water or for sodium cooled reactors. In the STI nuclear isle, three new laboratories for waste (PETRA), fusion (ETHEL) and safeguards, (PERLA) activities are approaching completion and have made substantial progress in their licensing procedure. The Institute started activities in the non-nuclear safety research area only a few years ago and has been able this year to present its first significant experimental and theoretical results in the areas of runaway reactions, accidental release of products and their deflagration/detonation. Concerning Reference Methods for the Evaluation of Structure Reliability a better understanding was gained of the nonlinear cyclic and dynamic behaviour of materials and structures by performing experiments and developing constitutive and structural member models leading to the computer simulation of complete structures

  12. The hot cell laboratories for material investigations of the Institute for Safety Research

    Energy Technology Data Exchange (ETDEWEB)

    Viehrig, H W

    1998-10-01

    Special facilities for handling and testing of irradiated specimens are necessary, to perform the investigation of activated material. The Institute for Safety Research has two hot cell laboratories: - the preparation laboratory and - the materials testing laboratory. This report is intended to give an overview of the available facilities and developed techniques in the laboratories. (orig.)

  13. Forschungszentrum Rossendorf, Institute of Safety Research. Annual report 2003

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2004-07-01

    The work of the institute is directed to the assessment and enhancement of the safety of technical plants and to the increase of the efficiency and environmental sustainability of those facilities. Subjects of investigation are equally nuclear plants and installations of process industries. To achieve the goals mentioned, the institute is mainly engaged in the scientific fields of thermal fluid dynamics including magneto-hydrodynamics (MHD) and materials sciences. In 2003, the ISR worked on the following main scientific projects. Sub-programme: Plant and Rector Safety. Project: accident analysis of nuclear reactors, safety of materials and components, particle and radiation transport, safety and efficiency of chemical processes. Sub-programme: Thermal Fluid Dynamics. Project: magneto-hydrodynamics, thermal fluid dynamics of multiphase systems. Considerable progress could also be achieved in the CFD simulation of two-phase flows. New approaches for the forces acting on steam bubbles in a water flow could be developed and implemented into the CFX code in close cooperation with the CFX developer ANSYS/CFX. The qualified models allow to simulate the evolution of bubble size specific radial void distribution profiles along the flow path. These theoretical studies and the related experiments at the Rossendorf TOPFLOW test facility represent an important part of the German CFD network that aims at the improvement of thermal hydraulic calculation methods in reactor safety. (orig.)

  14. Forschungszentrum Rossendorf, Institute of Safety Research. Annual report 2003

    International Nuclear Information System (INIS)

    2004-01-01

    The work of the institute is directed to the assessment and enhancement of the safety of technical plants and to the increase of the efficiency and environmental sustainability of those facilities. Subjects of investigation are equally nuclear plants and installations of process industries. To achieve the goals mentioned, the institute is mainly engaged in the scientific fields of thermal fluid dynamics including magneto-hydrodynamics (MHD) and materials sciences. In 2003, the ISR worked on the following main scientific projects. Sub-programme: Plant and Rector Safety. Project: accident analysis of nuclear reactors, safety of materials and components, particle and radiation transport, safety and efficiency of chemical processes. Sub-programme: Thermal Fluid Dynamics. Project: magneto-hydrodynamics, thermal fluid dynamics of multiphase systems. Considerable progress could also be achieved in the CFD simulation of two-phase flows. New approaches for the forces acting on steam bubbles in a water flow could be developed and implemented into the CFX code in close cooperation with the CFX developer ANSYS/CFX. The qualified models allow to simulate the evolution of bubble size specific radial void distribution profiles along the flow path. These theoretical studies and the related experiments at the Rossendorf TOPFLOW test facility represent an important part of the German CFD network that aims at the improvement of thermal hydraulic calculation methods in reactor safety. (orig.)

  15. National Nuclear Research Institute (NNRI) - Annual Report 2015

    International Nuclear Information System (INIS)

    2015-01-01

    The 2015 report of the National Nuclear Research Institute (NNRI) of the Ghana Atomic Energy Commission (GAEC) lists various programmes undertaken by the Institute under the following headings: Water resources programme, Energy Research programme, Environmental and Health Safety Programme, Digital Instrumentation programme, Nuclear Applications and Materals programme and Radiation Occupational safety programme. Also, included are abstracts of publications and technical reports.

  16. Nuclear safety research in HGF 2011

    International Nuclear Information System (INIS)

    Tromm, Walter

    2012-01-01

    partners in the Nuclear Competence Association. As of January 2011, the Dresden-Rossendorf Helmholtz Center (HZDR), with its 2 Institutes of Safety Research and for Radiochemistry, is an integral part of the Nuclear Safety Research Program within the Energy Research Area. Both institutes work on topics of safety research for nuclear reactors and safety research for nuclear waste management. In this way, the 2 institutes represent very welcome added value as well as a supplement to the Nuclear Safety Research Program. (orig.)

  17. 77 FR 27776 - Safety and Occupational Health Study Section (SOHSS), National Institute for Occupational Safety...

    Science.gov (United States)

    2012-05-11

    ... Occupational Health Study Section (SOHSS), National Institute for Occupational Safety and Health (NIOSH) In... Services Office, CDC, pursuant to Public Law 92-463. Purpose: The Safety and Occupational Health Study... standard grants review and funding cycles pertaining to research issues in occupational safety and health...

  18. 76 FR 18220 - Safety and Occupational Health Study Section (SOHSS), National Institute for Occupational Safety...

    Science.gov (United States)

    2011-04-01

    ... Occupational Health Study Section (SOHSS), National Institute for Occupational Safety and Health (NIOSH) In... Services Office, CDC, pursuant to Public Law 92-463. Purpose: The Safety and Occupational Health Study... standard grants review and funding cycles pertaining to research issues in occupational safety and health...

  19. Paul Scherrer Institut annual report 1995. Annex IV: PSI nuclear energy and safety

    Energy Technology Data Exchange (ETDEWEB)

    Birchley, J.; Roesel, R.; Doesburg, R. van [eds.] [Paul Scherrer Inst. (PSI), Villigen (Switzerland)

    1996-09-01

    Nuclear energy research in Switzerland is concentrated at PSI`s Department F4. It is explicitly mentioned in the Institute`s official charter and commands about one fifth of the Institute`s federal resources. Presently, PSI invests approx. 200 py/a in nuclear energy research, one third of this being externally funded; the share of external funding in investment costs totals approx. 50%. This funding is provided by the Swiss utilities and the NAGRA, the Safety Authority (HSK) and the former National Fund for Energy Research (NEFF). PSI`s activities in nuclear research concentrate on three main areas: safety of operating plants, safety features of future reactor concepts and waste management. 7% of personnel are invested in addressing global aspects of energy. (author) figs., tabs., refs.

  20. Nuclear-safety institution in France: emergence and development

    International Nuclear Information System (INIS)

    Vallet, B.M.

    1986-01-01

    This research work examines the social construction of the nuclear-safety institution in France, and the concurrent increased focus on the nuclear-risk issue. Emphasis on risk and safety, as primarily technical issues, can partly be seen as a strategy. Employed by power elites in the nuclear technostructure, this diverts emphasis away from controversial and normative questions regarding the political and social consequences of technology to questions of technology that appear to be absolute to the technology itself. Nuclear safety, which started from a preoccupation with risk related to the nuclear energy research and development process, is examined using the analytic concept of field. As a social arena patterned to achieve specific tasks, this field is dominated by a body of state engineers recognized to have high-level scientific and administrative competences. It is structured by procedures and administrative hierarchies as well as by technical rules, norms, and standards. These are formalized and rationalized through technical, economic, political, and social needs; over time; they consolidate the field into an institution. The study documents the nuclear-safety institution as an integral part of the nuclear technostructure, which has historically used the specificity of its expertise as a buffer against outside interference

  1. 75 FR 26266 - Safety and Occupational Health Study Section (SOHSS), National Institute for Occupational Safety...

    Science.gov (United States)

    2010-05-11

    ... Occupational Health Study Section (SOHSS), National Institute for Occupational Safety and Health (NIOSH) In...) Public Law 92-463. Purpose: The Safety and Occupational Health Study Section will review, discuss, and... cycles pertaining to research issues in occupational safety and health, and allied areas. It is the...

  2. Researches in radiation protection and safety at Moscow engineering physics institute

    International Nuclear Information System (INIS)

    Kramer-Ageev, E.A.; Lebedev, L.A.

    1994-01-01

    Department of Radiation Physics of Moscow Engineering Physics Institute is a research and teaching institution in the field of radiation protection, dosimetry, shielding and in radioecology. The scientific activity which has been doing at the department for many years includes the following directions: 1. Development of mathematical models and computational methods for an evaluation of external and internal exposure of people living on contaminated areas. Recently the computational model for forecast of internal irradiation via food chains was linked with computer geographical information systems. 2. Development of techniques and instruments for the measurements of radioactive contamination of soil, air, water and agricultural products. Department has special laboratory for this. 3. Application of computational methods to the problem of nuclear medicine. The whole body spectrometry and radiation 'coding' are used as an efficient methods of obtaining information on the radionuclides location in the human body. 4. Application of computational methods to the problem of radiation safety at nuclear power plants. It allows one to calculate radiation fields in shielding and the characteristics of nuclear wastes. (author)

  3. Meeting on reactor safety research

    International Nuclear Information System (INIS)

    1982-09-01

    The meeting 'Reactor Safety Research' organized for the second time by the GRS by order of the BMFT gave a review of research activities on the safety of light water reactors in the Federal Repulbic of Germany, international co-operation in this field and latest results of this research institution. The central fields of interest were subjects of man/machine-interaction, operational reliability accident sequences, and risk. (orig.) [de

  4. Progress of nuclear safety research, (1)

    International Nuclear Information System (INIS)

    Amano, Hiroshi; Nakamura, Hiroei; Nozawa, Masao

    1981-01-01

    The Japan Atomic Energy Research Institute was established in 1956 in conformity with the national policy to extensively conduct the research associated with nuclear energy. Since then, the research on nuclear energy safety has been conducted. In 1978, the Division of Reactor Safety was organized to conduct the large research programs with large scale test facilities. Thereafter, the Divisions of Reactor Safety Evaluation, Environmental Safety Research and Reactor Fuel Examination were organized successively in the Reactor Safety Research Center. The subjects of research have ranged from the safety of nuclear reactors to that in the recycling of nuclear fuel. In this pamphlet, the activities in JAERI associated with the safety research are reported, which have been carried out in the past two years. Also, the international cooperation research program in which JAERI participated is included. This pamphlet consists of two parts, and in this Part 1, the reactor safety research is described. The safety of nuclear fuel, the integrity and safety of pressure boundary components, the engineered safety in LOCA, fuel behavior in accident and others are reported. (Kako, I.)

  5. Progress of nuclear safety research, (2)

    International Nuclear Information System (INIS)

    Amano, Hiroshi; Nakamura, Hiroei; Nozawa, Masao

    1981-01-01

    The Japan Atomic Energy Research Institute was established in 1956 in conformity with the national policy to extensively conduct the research associated with nuclear energy. Since then, the research on nuclear energy safety has been conducted. In 1978, the Division of Reactor Safety was organized to conduct the large research programs with large scale test facilities. Thereafter, the Divisions of Reactor Safety Evaluation, Environmental Safety Research and Reactor Fuel Examination were organized successevely in the Reactor Safety Research Center. The subjects of research have ranged from the safety of nuclear reactors to that in the recycling of nuclear fuel. In this pamphlet, the activities in JAERI associated with the safety research are reported, which have been carried out in the past two years. Also the international cooperation research program in which JAERI participated is included. This pamphlet consists of two parts and in this Part 2, the environmental safety research is described. The evaluation and analysis of environmental radioactivity, the study on radioactive waste management and the studies on various subjects related to environmental safety are reported. (Kako, I.)

  6. Proceedings of the seminar on nuclear safety research and the workshop on reactor safety research

    International Nuclear Information System (INIS)

    2001-07-01

    The seminar on the nuclear safety research was held on November 20, 2000 according to the start of new five year safety research plan (FY2001-2005: established by Nuclear Safety Commission) with 79 participants. In the seminar, Commissioner Dr. Kanagawa gave the outline of the next five year safety research plan. Following this presentation, progresses and future scopes of safety researches in the fields of reactor facility, fuel cycle facility, radioactive waste and environmental impact on radiation at Japan Atomic Energy Research Institute (JAERI) were reported. After the seminar, the workshop on reactor safety research was held on November 21-22, 2000 with 141 participants. In the workshop, four sessions titled safety of efficient and economic utilization of nuclear fuel, safety related to long-term utilization of power reactors, research on common safety-related issues and toward further improvement of nuclear safety were organized and, outcomes and future perspectives in these wide research R and D in the related area at other organizations including NUPEC, JAPEIC and Kansai Electric Power Co. was presented in each session. This report compiles outlines of the presentations and used materials in the seminar and the workshop to form the proceedings for the both meetings. (author)

  7. Accomplishments and needs in safety research

    International Nuclear Information System (INIS)

    Beckjord, E.S.

    1988-01-01

    My purpose today is to review recent accomplishments in water reactor safety research and to point out important tasks that remain to be done. I will also comment on the changes of focus that I see ahead in reactor safety research. I speak from a U.S. perspective on the subject, but note that the program of the U.S. Nuclear Regulatory Commission and also that of the U.S. industry's Electric Power Research Institute include many international collaborative research efforts. Without any doubt, nuclear safety research today is international in scope, and the collaborative movement is gaining in strength

  8. Progress of nuclear safety research - 2005

    International Nuclear Information System (INIS)

    Anoda, Yoshinari; Amaya, Masaki; Saito, Junichi; Sato, Atsushi; Sono, Hiroki; Tamaki, Hitoshi; Tonoike, Kotaro; Nemoto, Yoshiyuki; Motoki, Yasuo; Moriyama, Kiyofumi; Yamaguchi, Tetsuji; Araya, Fumimasa

    2006-03-01

    The Japan Atomic Energy Research Institute (JAERI), one of the predecessors of the Japan Atomic Energy Agency (JAEA), had conducted nuclear safety research primarily at the Nuclear Safety Research Center in close cooperation with the related departments in accordance with the Long Term Plan for Development and Utilization of Nuclear Energy and Five-Years Program for Safety Research issued by the Japanese government. The fields of conducting safety research at JAERI were the engineering safety of nuclear power plants and nuclear fuel cycle facilities, and radioactive waste management as well as advanced technology for safety improvement or assessment. Also, JAERI had conducted international collaboration to share the information on common global issues of nuclear safety and to supplement own research. Moreover, when accidents occurred at nuclear facilities, JAERI had taken a responsible role by providing experts in assistance to conducting accident investigations or emergency responses by the government or local government. These nuclear safety research and technical assistance to the government have been taken over as an important role by JAEA. This report summarizes the nuclear safety research activities of JAERI from April 2003 through September 2005 and utilized facilities. (author)

  9. Inquiry relating to safety due to modification of usage of nuclear fuel material (establishment of waste safety testing facility) in Tokai Laboratory, Japan Atomic Energy Research Institute

    International Nuclear Information System (INIS)

    1979-01-01

    Application was made to the director of the Science and Technology Agency (STA) for the license relating to the modification of usage of nuclear fuel material (the establishment of waste safety testing facility) from the director of the Japan Atomic Energy Research Institute on November 30, 1978. After passing through the safety evaluation in the Nuclear Safety Bureau of STA, inquiry was conducted to the head of the Atomic Energy Safety Commission (AESC) on June 6, 1979, from the director of the STA. The head of AESC directed to conduct the safety examination to the head of the Nuclear Fuel Safety Examination Specialist Committee on June 7, 1979. The content of the modification of usage of nuclear fuel material is the establishment of waste safety testing facility to study and test the safety relating to the treatment and disposal of high level radioactive liquid wastes due to the reprocessing of spent fuel. As for the results of the safety examination, the siting of the waste safety testing facility which is located in the Tokai Laboratory, Japan Atomic Energy Research Institute (JAERI), and the test plan of the glass solidification of high level radioactive liquid are presented as the outline of the study plan. The building, main equipments including six cells, the isolation room and the glove box, the storage, and the disposal facilities for gas, liquid and solid wastes are explained as the outline of the facilities. Concerning the items from the viewpoint of safety, aseismatic design, slightly vacuum operation, shielding, decay heat removal, fire protection, explosion protection, criticality management, radiation management and environmental effect were evaluated, and the safety was confirmed. (Nakai, Y.)

  10. Light water reactor safety research project

    International Nuclear Information System (INIS)

    Markoczy, G.; Aksan, S.N.; Behringer, K.; Prodan, M.; Stierli, F.; Ullrich, G.

    1980-07-01

    The research and development activities for the safety of Light Water Power Reactors carried out 1979 at the Swiss Federal Institute for Reactor Research are described. Considerations concerning the necessity, objectives and size of the Safety Research Project are presented, followed by a detailed discussion of the activities in the five tasks of the program, covering fracture mechanics and nondestructive testing, thermal-hydraulics, reactor noise analysis and pressure vessel steel surveillance. (Auth.)

  11. Spanish Nuclear Safety Research under International Frameworks

    Energy Technology Data Exchange (ETDEWEB)

    Herranz, L. E.; Reventos, F.; Ahnert, C.; Jimenez, G.; Queral, C.; Verdu, G.; Miro, R.; Gallardo, S.

    2013-10-01

    The Nuclear Safety research requires a wide international collaboration of several involved groups. In this sense this paper pretends to show several examples of the Nuclear Safety research under international frameworks that is being performed in different Universities and Research Institutions like CIEMAT, Universitat Politecnica de Catalunya (UPC), Universidad Politecnica de Madrid (UPM) and Universitat Politenica de Valencia (UPV). (Author)

  12. Paul Scherrer Institut annual report 1995. Annex IV: PSI nuclear energy and safety

    International Nuclear Information System (INIS)

    Birchley, J.; Roesel, R.; Doesburg, R. van

    1996-01-01

    Nuclear energy research in Switzerland is concentrated at PSI's Department F4. It is explicitly mentioned in the Institute's official charter and commands about one fifth of the Institute's federal resources. Presently, PSI invests approx. 200 py/a in nuclear energy research, one third of this being externally funded; the share of external funding in investment costs totals approx. 50%. This funding is provided by the Swiss utilities and the NAGRA, the Safety Authority (HSK) and the former National Fund for Energy Research (NEFF). PSI's activities in nuclear research concentrate on three main areas: safety of operating plants, safety features of future reactor concepts and waste management. 7% of personnel are invested in addressing global aspects of energy. (author) figs., tabs., refs

  13. Overview of Gas Research Institute environmental research programs

    International Nuclear Information System (INIS)

    Evans, J.M.

    1991-01-01

    The Gas Research Institute (GRI) is a private not-for-profit membership organization of natural gas pipelines, distribution companies and natural gas producers. GRI's purpose is to plan, to manage and to develop financing for a gas-related research and development (R and D) program on behalf of its members and their customers. GRI does not do any research itself. GRI's R and D program is designed to provide advanced technologies for natural gas supply, transport, storage, distribution and end-use applications in all markets. In addition, basic research is conducted for GRI in these areas to build a foundation for future technology breakthroughs. Work in the Environment and Safety Research Department includes sections interested in: supply related research, air quality research, end use equipment safety research, gas operations safety research, and gas operations environmental research. The Natural Gas Supply Program has research ongoing in such areas as: restoration of pipeline right-of-ways; cleaning up town gas manufacturing sites; the development of methanogenic bacteria for soil and groundwater cleanup; development of biological fluidized carbon units for rapid destruction of carbonaceous compounds; research on liquid redox sulfur recovery for sulfur removal from natural gas; research on produced water and production wastes generated by the natural gas industry; environmental effects of coalbed methane production; and subsurface effects of natural gas operations. The western coalbed methane and ground water programs are described

  14. Safety research program of NUCEF

    International Nuclear Information System (INIS)

    Naito, Y.

    1996-01-01

    To contribute the safety and establishment of advanced technologies in the area of nuclear fuel cycle, Japan Atomic Energy Research Institute (JAERI) has constructed a new research facility NUCEF (Nuclear Fuel Cycle Safety Engineering Research Facility) as the center for the research and development, particularly on the reprocessing technology and transuranium (TRU) waste management. NUCEF consist of three buildings, administration building, experiment building A and B. Building A has two experiment facilities STACY (Static Experiment Critical Facility) and TRACY (Transient Experiment Critical Facility). The experiment building B is referred to as BECKY (Back-end Fuel Cycle Key Elements Research Facility). Researches on the reprocessing and the waste management are carried out with spent fuels, high-level liquid waste, TRU etc. in the α γ cell and glove boxes. NUCEF was constructed with the following aims. Using STACY and TRACY, are aimed, (1) research on advanced technology for criticality safety control, (2) reconfirmation of criticality safety margin of the Rokkasho reprocessing plant. Using BECKY, are aimed, (1) research on advanced technology of reprocessing process, (2) contribution to develop the scenario for TRU waste disposal, (3) development of new technology for TRU partitioning and volume reduction of radioactive waste. To realize the above aims, following 5 research subjects are settled in NUCEF, (1) Criticality safety research, (2) Research on safety and advanced technology of fuel reprocessing, (3) Research on TRU waste management, (4) Fundamental research on TRU chemistry, (5) Key technology development for TRU processing. (author)

  15. Safety research for LWR type reactors

    International Nuclear Information System (INIS)

    1989-07-01

    The current R and D activities are to be seen in connection with the LWR risk assessment studies. Two trends are emerging, of which the one concentrates more on BWR-specific problems, and the other on the efficiency or safety-related assessment of accident management activities. This annual report of 1988 reviews the progress of work done by the institutes and departments of the Karlsruhe Nuclear Research Center, (KfK), or on behalf of KfK by external institutions, in the field of safety research. The papers of this report present the state of work at the end of the year 1988. They are written in German, with an abstract in English. (orig./HP) [de

  16. Forschungszentrum Rossendorf, Institute for Safety Research. Annual report 1994

    International Nuclear Information System (INIS)

    Weiss, F.P.; Rindelhardt, U.

    1995-06-01

    Striving for the assessment and enhancement of design based safety, for improving operational safety, and for risk management IFS is engaged in the following methodical fields: - Experimental and theoretical thermo-fluiddynamics, - 3-dimensional neutron kinetics, - characterization of the mechanical behaviour of aged materials and microstructural analysis, -transport calculations of particle and radiation fields, - early failure diagnostics of processes and plants, - hazard ranking of non-nuclear waste deposits and support of the selection of appropriate remediation procedures by means of decision analysis. In 1994, special efforts were directed to the extension of experimental facilities needed for radioactive materials testing and for two phase flow investigations. Moreover, first research projects on the safety of VVER reactors could successfully be finished. (orig./HP)

  17. IRSN research programs concerning reactor safety

    International Nuclear Information System (INIS)

    Bardelay, J.

    2005-01-01

    This paper is made up of 3 parts. The first part briefly presents the missions of IRSN (French research institute on nuclear safety), the second part reviews the research works currently led by IRSN in the following fields : -) the assessment of safety computer codes, -) thermohydraulics, -) reactor ageing, -) reactivity accidents, -) loss of coolant, -) reactor pool dewatering, -) core meltdown, -) vapor explosion, and -) fission product release. In the third part, IRSN is shown to give a major importance to experimental programs led on research or test reactors for collecting valid data because of the complexity of the physical processes that are involved. IRSN plans to develop a research program concerning the safety of high or very high temperature reactors. (A.C.)

  18. IRSN safety research carried out for reviewing geological disposal safety case

    International Nuclear Information System (INIS)

    Serres, Christophe; Besnus, Francois; Gay, Didier

    2010-01-01

    The Radiation Protection and Nuclear Safety Institute develops a research programme on scientific issues related to geological disposal safety in order to supporting the technical assessment carried out in the framework of the regulatory review process. This research programme is organised along key safety questions that deal with various scientific disciplines as geology, hydrogeology, mechanics, geochemistry or physics and is implemented in national and international partnerships. It aims at providing IRSN with sufficient independent knowledge and scientific skills in order to be able to assess whether the scientific results gained by the waste management organisation and their integration for demonstrating the safety of the geological disposal are acceptable with regard to the safety issues to be dealt with in the Safety Case. (author)

  19. Program nuclear safety research: report 2000

    International Nuclear Information System (INIS)

    Muehl, B.

    2001-09-01

    The reactor safety R and D work of forschungszentrum karlsruhe (FZK) had been part of the nuclear safety research project (PSF) since 1990. In 2000, a new organisational structure was introduced and the Nuclear Safety Research Project was transferred into the nuclear safety research programme (NUKLEAR). In addition to the three traditional main topics - Light Water Reactor safety, Innovative systems, Studies related to the transmutation of actinides -, the new Programme NUKLEAR also covers Safety research related to final waste storage and Immobilisation of HAW. These new topics, however, will only be dealt with in the next annual report. Some tasks related to the traditional topics have been concluded and do no longer appear in the annual report; other tasks are new and are described for the first time. Numerous institutes of the research centre contribute to the work programme, as well as several external partners. The tasks are coordinated in agreement with internal and external working groups. The contributions to this report, which are either written in German or in English, correspond to the status of early/mid 2001. (orig.)

  20. Progress of nuclear safety research, 1990

    International Nuclear Information System (INIS)

    1990-07-01

    Since the Japan Atomic Energy Research Institute (JAERI) was founded as a nonprofit, general research and development organization for the peaceful use of nuclear energy, it has actively pursued the research and development of nuclear energy. Nuclear energy is the primary source of energy in Japan where energy resources are scarce. The safety research is recognized at JAERI as one of the important issues to be clarified, and the safety research on nuclear power generation, nuclear fuel cycle, waste management and environmental safety has been conducted systematically since 1973. As of the end of 1989, 38 reactors were in operation in Japan, and the nuclear electric power generated in 1988 reached 29 % of the total electric power generated. 50 years have passed since nuclear fission was discovered in 1939. The objective of the safety research at JAERI is to earn public support and trust for the use of nuclear energy. The overview of the safety research at JAERI, fuel behavior, reliability of reactor structures and components, reactor thermal-hydraulics during LOCA, safety assessment of nuclear power plants and nuclear fuel cycle facilities, radioactive waste management and environmental radioactivity are reported. (K.I.)

  1. Criticality safety research on nuclear fuel cycle facility

    Energy Technology Data Exchange (ETDEWEB)

    Miyoshi, Yoshinori [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    2004-07-01

    This paper present d s current status and future program of the criticality safety research on nuclear fuel cycle made by Japan Atomic Energy Research Institute. Experimental research on solution fuel treated in reprocessing plant has been performed using two critical facilities, STACY and TRACY. Fundamental data of static and transient characteristics are accumulated for validation of criticality safety codes. Subcritical measurements are also made for developing a monitoring system for criticality safety. Criticality safety codes system for solution and power system, and evaluation method related to burnup credit are developed. (author)

  2. Outline of criticality safety research project

    International Nuclear Information System (INIS)

    Kobayashi, Iwao; Tachimori, Shoichi; Suzaki, Takenori; Takeshita, Isao; Miyoshi, Yoshinori; Nakajima, Ken; Sakurai, Satoshi; Yanagisawa, Hiroshi

    1987-01-01

    As the power generation capacity of LWRs in Japan increased, the establishment and development of nuclear fuel cycle have become the important subject. Conforming to the safety research project of the nation, the Japan Atomic Energy Research Institute has advanced the project of constructing a new research facility, that is, Nuclear Fuel Cycle Engineering Research Facility (NUCEF). In this facility, it is planned to carry out the research on criticality safety, upgraded reprocessing techniques, and the treatment and disposal of transuranium element wastes. In this paper, the subjects of criticality safety research and the research carried out with a criticality safety experiment facility which is expected to be installed in the NUCEF are briefly reported. The experimental data obtained from the criticality safety handbooks and published literatures in foreign countries are short of the data on the mixture of low enriched uranium and plutonium which is treated in the reprocessing of spent fuel from LWRs. The acquisition of the criticality data for various forms of fuel, the elucidation of the scenario of criticality accidents, and the soundness of the confinement system for gaseous fission products and plutonium are the main subjects. The Static Criticality Safety Facility, Transient Criticality Safety Facility and pulse column system are the main facilities. (Kako, I.)

  3. Current status of nuclear safety research

    International Nuclear Information System (INIS)

    Anon.

    1977-01-01

    Efforts at nuclear safety research have expanded year by year in Japan, in term of money and technical achievement. The Atomic Energy Commission set last year the five year nuclear safety research program, a guideline by which various research institutes will be able to develop their own efforts in a concerted manner. From the results of the nuclear safety research which cover very wide areas ranging from reactor engineering safety, safety of nuclear fuel cycle facilities, prevention of radiation hazards to the adequate treatment and disposal of radioactive wastes, AIJ hereafter focuses of LWR engineering safety and prevents two articles, one introducing the current results of the NSSR program developed by JAERI and the other reporting the LWR reliability demonstration testing projects being promoted by MITI. The outline of these demonstration tests was reported in this report. The tests consist of earthquake resistance reliability test of nuclear power plants, steam generator reliability tests, valve integrity tests, fuel assembly reliability tests, reliability tests of heat affected zones and reliability tests of pumps. (Kobatake, H.)

  4. Summary of fuel safety research meeting 2004

    International Nuclear Information System (INIS)

    Fuketa, Toyoshi; Hidaka, Akihide; Nakamura, Jinichi; Suzuki, Motoe; Nagase, Fumihisa; Sasajima, Hideo; Fujita, Misao; Otomo, Takashi; Kudo, Tamotsu; Amaya, Masaki; Sugiyama, Tomoyuki; Ikehata, Hisashi; Iwasaki, Ryo; Ozawa, Masaaki; Kida, Mitsuko

    2004-10-01

    Fuel Safety Research Meeting 2004, which was organized by the Japan Atomic Energy Research Institute, was held on March 1-2, 2004 at Toranomon Pastoral, Tokyo. The purposes of the meeting are to present and discuss the results of experiments and analyses on reactor fuel safety and to exchange views and experiences among the participants. The technical topics of the meeting covered the status of fuel safety research activities, fuel behavior under RIA and LOCA conditions, high burnup fuel behavior, and radionuclides release under severe accident conditions. This summary contains all the abstracts and OHP sheets presented in the meeting. (author)

  5. Participation of the research institutes in the safety aspects of the Laguna Verde nuclear power plant

    International Nuclear Information System (INIS)

    Sanchez G, J.

    1991-01-01

    The main activities undertaken by two research institutes of Mexico, the Instituto de Investigaciones Electricas and the Instituto Nacional de Investigaciones Nucleares, related to the safety of the Laguna Verde Nuclear Power Plant, are described. Among these activities, the development of a system for data acquisition and analysis during pre-operational tests, the design and construction of a full-scope simulator, the in-core fuel management and the establishment of an equipment qualification laboratory, stand out. It is considered that there exists a large potential for further participation. (author)

  6. 78 FR 11651 - Board of Scientific Counselors, National Institute for Occupational Safety and Health (BSC, NIOSH)

    Science.gov (United States)

    2013-02-19

    ... Scientific Counselors, National Institute for Occupational Safety and Health (BSC, NIOSH) In accordance with..., research, experiments, and demonstrations relating to occupational safety and health and to mine health... Occupational Safety and Health on research and prevention programs. Specifically, the Board shall provide...

  7. 77 FR 47850 - Board of Scientific Counselors, National Institute for Occupational Safety and Health (BSC, NIOSH)

    Science.gov (United States)

    2012-08-10

    ... Scientific Counselors, National Institute for Occupational Safety and Health (BSC, NIOSH) In accordance with..., research, experiments, and demonstrations relating to occupational safety and health and to mine health... Occupational Safety and Health on research and prevention programs. Specifically, the Board shall provide...

  8. Proceedings of fuel safety research specialists' meeting

    International Nuclear Information System (INIS)

    Suzuki, Motoe

    2002-08-01

    Fuel Safety Research Specialists' Meeting, which was organized by Japan Atomic Energy Research Institute, was held on March 4-5, 2002 at JAERI in Tokai Establishment. Purposes of the Meeting are to exchange information and views on LWR fuel safety topics among the specialist participants from domestic and foreign organizations, and to discuss the recent and future fuel research activities in JAERI. In the Meeting, presentations were given and discussions were made on general report of fuel safety research activities, fuel behaviors in normal operation and accident conditions, FP release behaviors in severe accident conditions, and JAERI's ''Advanced LWR Fuel Performance and Safety Research Program''. A poster exhibition was also carried out. The Meeting significantly contributed to planning future program and cooperation in fuel research. This proceeding integrates all the pictures and papers presented in the Meeting. The 10 of the presented papers are indexed individually. (J.P.N.)

  9. The perspective of European researchers of national occupational safety and health institutes for contributing to a European research agenda: a modified Delphi study

    Science.gov (United States)

    Gagliardi, Diana; Rondinone, Bruna M; Mirabile, Marco; Buresti, Giuliana; Ellwood, Peter; Hery, Michel; Paszkiewicz, Peter; Valenti, Antonio; Iavicoli, Sergio

    2017-01-01

    Objectives This study, developed within the frame of the Partnership for European Research on Occupational Safety and Health joint research activities and based on the frame designed by the 2013 European Agency for Safety and Health at Work (EU-OSHA) study, is the first example of using the points of view of European occupational safety and health (OSH) researchers. The objective is to identify priorities for OSH research that may contribute to the achievement of present and future sustainable growth objectives set by the European strategies. Methods The study was carried out using a modified Delphi method with a two-round survey. Each round involved a panel of about 110 researchers representing the network member institutes was selected according to specific criteria, including the ownership of research expertise in at least one of the four macroareas identified by the reference report developed by EU-OSHA in 2013. Results The study identified some innovative research topics (for example, ‘Emerging technological devices’ and ‘OSH consequences of markets integration’) and research priorities (ie, crowdsourcing, e-work, zero-hours contracts) that are not reflected in previous studies of this nature. The absence of any reference to violence and harassment at work among the researchers’ proposals is a major difference from previous similar studies, while topics related to gender issues and electromagnetic fields show a lower importance. Conclusions The innovative design of a research priorities identification process, which takes advantage of a large, representative and qualified panel of European researchers allowed the definition of a number of research priorities able to support the inclusion of innovative OSH research issues in the scope of the next European research agenda. PMID:28645965

  10. Safety research in nuclear fuel cycle at PNC

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-09-01

    This report collects the results of safety research in nuclear fuel cycle at Power Reactor and Nuclear Fuel Development Corporation, in order to answer to the Questionnaire of OECD/NEA. The Questionnaire request to include information concerning to research topic, description, main results (if available), reference documents, research institutes involved, sponsoring organization and other pertinent information about followings: a) Recently completed research projects. b) Ongoing (current) research projects. Achievements on following items are omitted by the request of OECD/NEA, uranium mining and milling, uranium refining and conversion to UF{sub 6}, uranium enrichment, fuel manufacturers, spent fuel storage, radioactive waste management, transport of radioactive materials, decommissioning. We select topics from the fields of a) nuclear installation, b) seismic, and c) PSA, in projects from frame of annual safety research plan for nuclear installations established by Nuclear Safety Commission. We apply for the above a) and b) projects as follows: a) Achievements in Safety Research, fiscal 1991-1995, b) fiscal 1996 Safety Research Achievements: Progress. (author)

  11. Safety research in nuclear fuel cycle at PNC

    International Nuclear Information System (INIS)

    1998-09-01

    This report collects the results of safety research in nuclear fuel cycle at Power Reactor and Nuclear Fuel Development Corporation, in order to answer to the Questionnaire of OECD/NEA. The Questionnaire request to include information concerning to research topic, description, main results (if available), reference documents, research institutes involved, sponsoring organization and other pertinent information about followings: a) Recently completed research projects. b) Ongoing (current) research projects. Achievements on following items are omitted by the request of OECD/NEA, uranium mining and milling, uranium refining and conversion to UF 6 , uranium enrichment, fuel manufacturers, spent fuel storage, radioactive waste management, transport of radioactive materials, decommissioning. We select topics from the fields of a) nuclear installation, b) seismic, and c) PSA, in projects from frame of annual safety research plan for nuclear installations established by Nuclear Safety Commission. We apply for the above a) and b) projects as follows: a) Achievements in Safety Research, fiscal 1991-1995, b) fiscal 1996 Safety Research Achievements: Progress. (author)

  12. Safety-related LWR research. Annual report 1989

    International Nuclear Information System (INIS)

    1990-11-01

    The main topics in this annual report 1989 are phenomena of heavy fuel damage and single aspects of a core meltdown accident. The examined single aspects refer to aerosol behavior and filter engineering and to methods for assessment and minimization of the radiological consequences of reactor accidents. Different contributions to selected, safety-related problems of an advanced pressurized-water reactor complete the topic spectrum. The annual report 1989 describes the progress of the research work wich was carried out in the area of safety research by institutes and departments of the KfK, and on behalf of the KfK by external institutions. The individual contributions represent the status of work at the end of the year under review, 1989. (orig./HP) [de

  13. Proceedings of second JAERI-JNC joint conference on nuclear safety research

    International Nuclear Information System (INIS)

    Sugimoto, Jun; Anoda, Yoshinari; Araya, Fumimasa; Yamaguchi, Toshio

    2004-08-01

    The second JAERI-JNC Joint Conference on Nuclear Safety Research was held on February 6, 2004 in Tokyo for those who are relevant to nuclear industries and regulatory organizations, and general public. The nuclear safety research has been conducted in both institutes according to the Five-Year Program for Nuclear Safety Research established periodically by the Nuclear Safety Commission (NSC) and needs from the regulatory organizations. The objectives of the conference are to present its recent results and to collect views and opinions from the participants for its future program through the discussion after each presentation and panel discussion on how to conduct efficiently the nuclear safety in the New Organization. A total of 259 people participated in the conference mainly from the nuclear industries and regulatory organizations and the number was much larger than that in the last conference of 188. The conference consisted of presentations on the safety research results, a special lecture and a panel discussion. First, the overview of safety research results was presented from each institute. Then, the results in the field of nuclear installations, environmental radioactivity and radioactive waste were presented from each institute. Then, Dr. Higashi, the Nuclear Safety Commissioner, made a special lecture on the radiation protection from the high-level radioactive waste disposal. Finally, a panel discussion was conducted with the title of ''how to conduct efficiently the nuclear safety research in the New Organization'' chaired by Prof. Kimura, the chairperson of Standing Committee on Nuclear Safety Research under the NSC. The panelists from the regulatory organizations, nuclear industry, JAERI and JNC discussed the subject together with the participants on the floor. The panelists not from JAERI and JNC expressed their views and opinions on how to conduct efficiently the nuclear safety research in the New Organization that were valuable inputs for developing

  14. Karlsruhe Nuclear Research Center, Institute of Neutron Physics and Reactor Engineering. Progress report on research and development work in 1993

    International Nuclear Information System (INIS)

    1994-03-01

    The Institute of Neutron Physics and Reactor Engineering is concerned with research work in the field of nuclear engineering related to the safety of thermal reactors as well as with specific problems of fusion reactor technology. Under the project of nuclear safety research, the Institute works on concepts designed to drastically improve reactor safety. Apart from that, methods to estimate and minimize the radiological consequences of reactor accidents are developed. Under the fusion technology project, the Institute deals with neutron physics and technological questions of the breeding blanket. Basic research covers technico-physical questions of the interaction between light ion radiation of a high energy density and matter. In addition and to a small extent, questions of employing hydrogen in the transport area are studied. (orig.) [de

  15. The perspective of European researchers of national occupational safety and health institutes for contributing to a European research agenda: a modified Delphi study.

    Science.gov (United States)

    Gagliardi, Diana; Rondinone, Bruna M; Mirabile, Marco; Buresti, Giuliana; Ellwood, Peter; Hery, Michel; Paszkiewicz, Peter; Valenti, Antonio; Iavicoli, Sergio

    2017-06-23

    This study, developed within the frame of the Partnership for European Research on Occupational Safety and Health joint research activities and based on the frame designed by the 2013 European Agency for Safety and Health at Work (EU-OSHA) study, is the first example of using the points of view of European occupational safety and health (OSH) researchers.The objective is to identify priorities for OSH research that may contribute to the achievement of present and future sustainable growth objectives set by the European strategies. The study was carried out using a modified Delphi method with a two-round survey. Each round involved a panel of about 110 researchers representing the network member institutes was selected according to specific criteria, including the ownership of research expertise in at least one of the four macroareas identified by the reference report developed by EU-OSHA in 2013. The study identified some innovative research topics (for example, 'Emerging technological devices' and 'OSH consequences of markets integration') and research priorities (ie, crowdsourcing, e-work, zero-hours contract s ) that are not reflected in previous studies of this nature.The absence of any reference to violence and harassment at work among the researchers' proposals is a major difference from previous similar studies, while topics related to gender issues and electromagnetic fields show a lower importance. The innovative design of a research priorities identification process, which takes advantage of a large, representative and qualified panel of European researchers allowed the definition of a number of research priorities able to support the inclusion of innovative OSH research issues in the scope of the next European research agenda. © Article author(s) (or their employer(s) unless otherwise stated in the text of the article) 2017. All rights reserved. No commercial use is permitted unless otherwise expressly granted.

  16. Safety management of radioisotopes and others in educational institutions

    International Nuclear Information System (INIS)

    1981-01-01

    Radioisotopes are extensively used in the fields of research in various educational institutions. While considerable progress has been seen in the safety management of RI utilization, such accidents as the loss of radioisotopes and radioactive contamination occurred. Under the situation, the safety management of RIs and others in RI-using facilities provided by the law has been examined by the ad hoc committee. A report by the committee is described as follows: need for a RI safety management organization, defining the responsibility of the chief technicians handling radiation, need for the practices of using RIs, etc. in education and traininng, planned RI-handling facilities, cautions for the loss of RIs and the contamination, centralization in RI safety management, improvement of remuneration for the chief technicians handling radiation, occasional restudy on the safety management of RIs, etc. (J.P.N.)

  17. National Institute for Occupational Safety and Health

    Science.gov (United States)

    ... Submit Search The CDC The National Institute for Occupational Safety and Health (NIOSH) Note: Javascript is disabled or is not ... and Events NIOSH Contact Information Related Federal Agencies Occupational Safety and Health Administration Mine Safety and Health Administration Follow NIOSH ...

  18. The evolution of the role of the Philippine Nuclear Research Institute in the national nuclear and radiation safety regime

    International Nuclear Information System (INIS)

    Dela Rosa, A.M.

    2007-01-01

    The Philippine Nuclear Research Institute (PNRI), formerly the Philippine Atomic Energy Commission (PAEC) was created by law in 1958 with a dual mandate namely, to promote the peaceful applications of nuclear energy, and to regulate the safe utilization of nuclear energy. Through its almost 50 years of existence, the PNRI has assumed different roles and functions. As the premier national nuclear research institution the PNRI initiates R and D work in various applications, establishes nuclear and radiation facilities, and undertakes human resource development not only for its staff but also for the prospective users of nuclear energy. At the same time, the PNRI exercises regulatory control over radioactive materials in the country including the regulatory control over the construction of the first Philippine nuclear power plant in the late 1970's and early 1980's. Presently, the PNRI still exercises the dual mandate of promoting and regulating the peaceful and safe use of radioactive materials. In these evolving roles of the Institute, both management and the staff are committed to excellence in nuclear science and to nuclear safety. Initiatives are underway to create a separate nuclear regulatory body from the developmental agency to enable the country to conform with international safety standards and to prepare for the future re-introduction of nuclear power in the Philippine energy mix. A strong regulatory agency and an equally strong technical and scientific support organization are necessary for a successful and safe nuclear energy program. (author)

  19. Institute for Environment, Health and Safety

    International Nuclear Information System (INIS)

    Loos, M.

    2007-01-01

    The article describes the key activities of the Institute for Environment, Health and Safety of the Belgian Nuclear Research Centre SCK-CEN. Through the performance of experiments, the development of models and the integration of human sciences in our R and D, propose new durable methods, computer codes and measuring instruments for radiation protection, management and disposal of radioactive waste and dismantling of nuclear installations. These developments belong to the disciplines environmental chemistry, radiobiology and radioecology and include the transfer of radio nuclides in the geosphere and biosphere, as also the behaviour of micro-organisms in space

  20. 78 FR 70560 - Patient Safety Organizations: Voluntary Relinquishment From Morgridge Institute for Research PSO

    Science.gov (United States)

    2013-11-26

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES Agency for Healthcare Research and Quality Patient Safety... Research and Quality (AHRQ), HHS. ACTION: Notice of delisting. SUMMARY: The Patient Safety and Quality Improvement Act of 2005 (Patient Safety Act), Public Law 109-41, 42 U.S.C. 299b-21-b-26, provides for the...

  1. Voluntary research results for five years along the master plan on nuclear safety research. FY 2001 - 2005

    International Nuclear Information System (INIS)

    Sato, Yoshinori

    2006-05-01

    Safety Research has been conducted from FY 2001 to FY 2005 according to the Master Plan on Nuclear Safety Research (FY 2001-2005) in Japan Atomic Energy Agency which took over former Japan Nuclear Cycle Development Institute. This report shows the voluntary research results for five years conducted from FY 2001 to FY 2005 according to the Master Plan on Nuclear Safety Research (FY 2001-2005). (author)

  2. Radiation safety in educational, medical and research institutions. Regulatory guide G-121

    International Nuclear Information System (INIS)

    2000-05-01

    This regulatory guide is intended to help educational, medical and research institutions design and implement radiation protection programs that meed regulatory requirements. This guide applied to educational, medical or research institutions that require a licence from the CNSC to posses or use radioactive materials. It describes programs to assure that radioactive materials are used safely during licensed activities. (author)

  3. Proceedings of third JAERI-JNC joint conference on nuclear safety research

    International Nuclear Information System (INIS)

    Anoda, Yoshinari; Oikawa, Tetsukuni; Araya, Fumimasa; Suzuki, Tsugio

    2006-03-01

    The present report is the proceedings of the third JAERI-JNC joint conference on nuclear safety research held on July 29, 2005 in Tokyo before integration of JAERI and JNC to JAEA. The conference was held for those who are relevant to nuclear industries and regulatory organizations, and general public. The nuclear safety research has been conducted in both institutes according to the Five-Year Program for Nuclear Safety Research established periodically by the Nuclear Safety Commission (NSC) and needs from the regulatory organizations. The objectives of the conference are to present its recent results and to collect views and opinions from the participants for its future program through the discussion after each presentation and panel discussion on how to conduct efficiently the nuclear safety research in the new organization. A total of 234 people participated in the conference mainly from the nuclear industries and regulatory organizations. The conference consisted of presentations on the safety research results, a special lecture and a panel discussion. First, the overview of safety research results was presented from each institute. Then, the results in the field of nuclear installations, environmental radioactivity and radioactive waste were presented from each institute. Then, Dr. Suzuki, deputy chairperson of NSC, made a special lecture on recent trends in nuclear safety regulation and expectation for the new organization. Finally, a panel discussion was conducted with the title of 'how to conduct efficiently the nuclear safety research in the new organization' chaired by Prof. Kimura, the chairperson of Standing Committee on Nuclear Safety Research under the NSC. The panelists from JAERI and JNC presented and discussed the subject together with the participants on the floor. Through vigorous exchange of views in the panel discussion and descriptions on the questionnaires, it was obviously expressed that expectation to the safety research of the new

  4. Nuclear safety research project (PSF). 1999 annual report

    International Nuclear Information System (INIS)

    Muehl, B.

    2000-08-01

    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 summarizes the R and D results of PSF during 1999. The research tasks cover three main topics: Light Water Reactor safety, innovative systems, and studies related to the transmutation of actinides. The importance of the Light Water Reactor safety, however, has decreased during the last year in favour of the transmutation of actinides. Numerous institutes of the research centre contribute to the PSF programme, as well as several external partners. The tasks are coordinated in agreement with internal and external working groups. The contributions to this report, which are either written in German or in English, correspond to the status of early/mid 2000. (orig.) [de

  5. Retooling Institutional Support Infrastructure for Clinical Research

    Science.gov (United States)

    Snyder, Denise C.; Brouwer, Rebecca N.; Ennis, Cory L.; Spangler, Lindsey L.; Ainsworth, Terry L.; Budinger, Susan; Mullen, Catherine; Hawley, Jeffrey; Uhlenbrauck, Gina; Stacy, Mark

    2016-01-01

    Clinical research activities at academic medical centers are challenging to oversee. Without effective research administration, a continually evolving set of regulatory and institutional requirements can detract investigator and study team attention away from a focus on scientific gain, study conduct, and patient safety. However, even when the need for research administration is recognized, there can be struggles over what form it should take. Central research administration may be viewed negatively, with individual groups preferring to maintain autonomy over processes. Conversely, a proliferation of individualized approaches across an institution can create inefficiencies or invite risk. This article describes experiences establishing a unified research support office at the Duke University School of Medicine based on a framework of customer support. The Duke Office of Clinical Research was formed in 2012 with a vision that research administration at academic medical centers should help clinical investigators navigate the complex research environment and operationalize research ideas. The office provides an array of services that have received high satisfaction ratings. The authors describe the ongoing culture change necessary for success of the unified research support office. Lessons learned from implementation of the Duke Office of Clinical Research may serve as a model for other institutions undergoing a transition to unified research support. PMID:27125563

  6. Annual report of the Japan Atomic Energy Research Institute, for fiscal 1989

    International Nuclear Information System (INIS)

    1990-01-01

    Japan Atomic Energy Research Institute has promoted the research on nuclear safety, the research and development of high temperature engineering and nuclear fusion which are the leading projects bringing about the breakthrough in atomic energy technology, the research on radiation utilization and the research and development of nuclear-powered ships, following the 'Plan of development and long term utilization of atomic energy' decided in 1987, as the central, general research institute in atomic energy field in Japan. Also the advanced basic research for opening atomic energy frontier and various international cooperation as well as the cooperation in Japan have been promoted. The engineering safety of nuclear facilities and environmental safety, the construction of the Nuclear Fuel Cycle Safety Engineering Research Facility, the design of the High Temperature Engineering Test Reactor and the various tests related to it, the reconstruction of JT-60 for increasing the current, the design of a nuclear fusion reactor, the high utilization of radiation using ion beam, the construction of Sekinehama Port for the nuclear-powered ship 'Mutsu', the power increasing test of the reactor of the Mutsu, the reconstruction of JRR-3 and others are reported. (K.I.)

  7. Integrating gender medicine into the workplace health and safety policy in the scientific research institutions: a mandatory task.

    Science.gov (United States)

    Giammarioli, Anna Maria; Siracusano, Alessandra; Sorrentino, Eugenio; Bettoni, Monica; Malorni, Walter

    2012-01-01

    Gender medicine is a multi-faceted field of investigation integrating various aspects of psycho-social and biological sciences but it mainly deals with the impact of the gender on human physiology, pathophysiology, and clinical features of diseases. In Italy, the Decree Law 81/2008 recently introduced the gender issue in the risk assessment at the workplaces. This review briefly describes our current knowledge on gender medicine and on the Italian legislation in risk management. Public or private scientific institutions should be the first to pay attention to the safety of their workers, who are simultaneously subjected to biological, chemical and physical agents. Main tasks of risk management in scientific research institutions are here analyzed and discussed in a gender perspective.

  8. Integrating gender medicine into the workplace health and safety policy in the scientific research institutions: a mandatory task

    Directory of Open Access Journals (Sweden)

    Anna Maria Giammarioli

    2012-01-01

    Full Text Available BACKGROUND: Gender medicine is a multi-faceted field of investigation integrating various aspects of psycho-social and biological sciences but it mainly deals with the impact of the gender on human physiology, pathophysiology, and clinical features of diseases. In Italy, the Decree Law 81/2008 recently introduced the gender issue in the risk assessment at the workplaces. AIMS: This review briefly describes our current knowledge on gender medicine and on the Italian legislation in risk management. CONCLUSIONS: Public or private scientific institutions should be the first to pay attention to the safety of their workers, who are simultaneously subjected to biological, chemical and physical agents. Main tasks of risk management in scientific research institutions are here analyzed and discussed in a gender perspective.

  9. Annual report of the Japan Atomic Energy Research Institute, for fiscal 1988

    International Nuclear Information System (INIS)

    1989-01-01

    At present, a half century has elapsed since the discovery of nuclear fission, and atomic energy has taken the position of basic energy already, accordingly the development and utilization of atomic energy is very important as the energy source which can supply energy for long term economically and stably. Along the long term plan of atomic energy development and utilization decided in 1987, Japan Atomic Energy Research Institute (JAERI) advanced the research and development, thus it has borne the role as the nucleus general research institute in atomic energy fields. It has exerted efforts to obtain the understanding and trust of the nation on atomic energy, and has promoted the pioneering project research, such as safety research, high temperature engineering test and research, the research and development of nuclear fusion, the research on radiation utilization and the research and development of nuclear-powered ships. In the safety research, in order to contribute to the further rooting of LWRs and the establishment of nuclear fuel cycle, the research on the engineering safety of nuclear facilities and environmental safety has been advanced. The activities in respective research fields are summarized. Also the international cooperation with USA, FRG, China and others were carried out smoothly. (K.I.)

  10. Recent tasks and status of National Research Institute for Radiobiology and Radiohygiene as TSO

    International Nuclear Information System (INIS)

    Pellet, S.

    2007-01-01

    The technical support function of the National Research Institute for Radiobiology and Radiohygiene has been introduced at the time of its establishment. In order to support the actual requirements the Institute carries on extended research in the fields of radiation protection and radiation biology participating in national and international projects. Supporting the proper performance of national radiation protection and safety tasks the Institute gives professional directives and expert opinions for decision processes of authorities. The Institutes main areas of radiation protection activity are: - Radiation-related licensing, inspection, record keeping; - assuring safety of radiation sources; - National Personal Dosimetry Service; - radiological monitoring of the environment; - preparedness for radiological incidents and accidents; - radiation protection training activities. The Institute has an accredited Testing Laboratory with nearly sixty examination protocols. Together with its Central Environmental Testing Laboratory, the Institute thus provides a significant support for both theoretical and practical accomplishment of the national radiation protection and safety tasks. (author)

  11. Research and exploration on nuclear safety culture construction

    International Nuclear Information System (INIS)

    Zhang Lifang; Zhao Hongtao; Wang Hongwei

    2012-01-01

    This thesis mainly researched the definition, characteristics, development stage and setup procedure concerning nuclear safety culture, based on practice and experiences in Technical Physics Institute of Heilongjian. Academy of Science. The author discussed the importance of nuclear safety culture construction for an enterprise of nuclear technology utilization, and emphasized all the enterprise and individual who engaged in nuclear and radiation safety should acquire good nuclear safety culture quality, and ensure the application and development of the nuclear safety cult.ure construction in the enterprises of nu- clear technological utilization. (authors)

  12. Research on PWR safety in France

    International Nuclear Information System (INIS)

    Zammite, R.

    1988-07-01

    The French nuclear safety arrangements form a centralized system characterized by cooperation between the government authorities, their technical advisers and the operators of the installations, especially between the Commissariat a l'Energie Atomique (CEA) and Electricite de France (EDF). This cooperation in no way contradicts the respective responsibilities of the different parties, in particular those of EDF regarding the safety of its installations and those of CEA as the government's technical adviser and safety analyst. However, it considerably affects the research on reactor safety, which is mainly performed by the CEA Institute for Nuclear Safety and Protection (IPSN), in collaboration with EDF. For PWRs, the safety preoccupations concerning their development, commissioning and operation can be divided into the following three categories: A. Safety in design and construction, B. Safety in operation and the control of potential accidents, C. Maintaining safety - aging problems. The effort consecrated to each category has varied in the past and will continue to do so in the future. At the present stage, emphasis is being given to categories B and C. The appendix includes tables which indicate, for categories A, B and C, the relationship between the existing research programmes and the questions remaining open that they are intended to solve

  13. Maintaining competence in nuclear safety and waste management research by BMBF

    International Nuclear Information System (INIS)

    Ehrlich, Alexander

    2012-01-01

    Germany is to undertake a structured phasing-out of power generation from nuclear energy. Until the last nuclear power plant is shut down, safety must be guaranteed in line with the very latest developments in science and technology. The R and D work performed is in accord with the resolution for the structured phasing-out of the use of nuclear power. The Federal Ministry of Education and Research (BMBF) with its 'Basic Energy Research 2020+' funding concept supplements institutionally funded work of Helmholtz Institutes in a few core areas to further extend co-operation with universities. Close coordination between institutional and project funding will be ensured via the Alliance for Competence in Nuclear Technology in Germany ('Kompetenzverbund Kerntechnik'). In the area of nuclear safety and disposal research, R and D is carried out on the scientific and technological aspects of safety in existing nuclear reactors, the safety of nuclear disposal, the minimisation of highly radioactive substances ultimately requiring disposal and radiation research. Special attention is to be paid within this concept to the funding of young scientists. In addition to doctorate posts in research projects, special funding instruments are to be offered to promote the next generation of scientists. (orig.)

  14. Institute of Energy and Climate Research IEK-6 : nuclear waste management & reactor safety report 2009/2010 ; material science for nuclear waste management

    OpenAIRE

    Klinkenberg, M.; Neumeier, S.; Bosbach, D. (Editors)

    2011-01-01

    This is the first issue of a new series of bi-annual reports intended to provide an overview of research activities for the safe management of nuclear waste in the Institute of Energy and Climate Research (IEK-6), Nuclear Waste Management and Reactor Safety devision in Jülich. The report gives a thematic overview of the research in 2009 and 2010 by short papers of five to eight pages. Some papers are discussing the work within different projects with intensive overlap, such as ...

  15. Criteria for the Research Institute for Fragrance Materials, Inc. (RIFM) safety evaluation process for fragrance ingredients.

    Science.gov (United States)

    Api, A M; Belsito, D; Bruze, M; Cadby, P; Calow, P; Dagli, M L; Dekant, W; Ellis, G; Fryer, A D; Fukayama, M; Griem, P; Hickey, C; Kromidas, L; Lalko, J F; Liebler, D C; Miyachi, Y; Politano, V T; Renskers, K; Ritacco, G; Salvito, D; Schultz, T W; Sipes, I G; Smith, B; Vitale, D; Wilcox, D K

    2015-08-01

    The Research Institute for Fragrance Materials, Inc. (RIFM) has been engaged in the generation and evaluation of safety data for fragrance materials since its inception over 45 years ago. Over time, RIFM's approach to gathering data, estimating exposure and assessing safety has evolved as the tools for risk assessment evolved. This publication is designed to update the RIFM safety assessment process, which follows a series of decision trees, reflecting advances in approaches in risk assessment and new and classical toxicological methodologies employed by RIFM over the past ten years. These changes include incorporating 1) new scientific information including a framework for choosing structural analogs, 2) consideration of the Threshold of Toxicological Concern (TTC), 3) the Quantitative Risk Assessment (QRA) for dermal sensitization, 4) the respiratory route of exposure, 5) aggregate exposure assessment methodology, 6) the latest methodology and approaches to risk assessments, 7) the latest alternatives to animal testing methodology and 8) environmental risk assessment. The assessment begins with a thorough analysis of existing data followed by in silico analysis, identification of 'read across' analogs, generation of additional data through in vitro testing as well as consideration of the TTC approach. If necessary, risk management may be considered. Copyright © 2014 Elsevier Ltd. All rights reserved.

  16. Public education in safe use of artificial UV radiation sources by the consumer safety institute in the Netherlands

    International Nuclear Information System (INIS)

    Bruggers, J.H.A.

    1987-01-01

    The Consumer Safety Institute in the Netherlands is a national institute which operates entirely in the field of home safety. Its main aim exists in reducing the possibility and severity of accidents happening in and around the home, at school and recreational areas. To attain this aim the institute is active in research, handling consumer complaints, education, and advising. To inform and educate consumers about product safety, special leaflets and brochures are published. One of these brochures deals with safety and safe use of artificial UV radiation sources, e.g. UV lamps, UV couches etc. This brochure about suntanning equipment and safety was published recently

  17. Post-market drug evaluation research training capacity in Canada: an environmental scan of Canadian educational institutions.

    Science.gov (United States)

    Wiens, Matthew O; Soon, Judith A; MacLeod, Stuart M; Sharma, Sunaina; Patel, Anik

    2014-01-01

    Ongoing efforts by Health Canada intended to modernize the legislation and regulation of pharmaceuticals will help improve the safety and effectiveness of drug products. It will be imperative to ensure that comprehensive and specialized training sites are available to train researchers to support the regulation of therapeutic products. The objective of this educational institution inventory was to conduct an environmental scan of educational institutions in Canada able to train students in areas of post-market drug evaluation research. A systematic web-based environmental scan of Canadian institutions was conducted. The website of each university was examined for potential academic programs. Six core programmatic areas were determined a priori as necessary to train competent post-market drug evaluation researchers. These included biostatistics, epidemiology, pharmacoepidemiology, health economics or pharmacoeconomics, pharmacogenetics or pharmacogenomics and patient safety/pharmacovigilance. Twenty-three academic institutions were identified that had the potential to train students in post-market drug evaluation research. Overall, 23 institutions taught courses in epidemiology, 22 in biostatistics, 17 in health economics/pharmacoeconomics, 5 in pharmacoepidemiology, 5 in pharmacogenetics/pharmacogenomics, and 3 in patient safety/pharmacovigilance. Of the 23 institutions, only the University of Ottawa offered six core courses. Two institutions offered five, seven offered four and the remaining 14 offered three or fewer. It is clear that some institutions may offer programs not entirely reflected in the nomenclature used for this review. As Heath Canada moves towards a more progressive licensing framework, augmented training to increase research capacity and expertise in drug safety and effectiveness is timely and necessary.

  18. Current status of international cooperation on nuclear safety research

    International Nuclear Information System (INIS)

    Katsuragi, Satoru

    1984-01-01

    JAERI (Japan Atomic Energy Research Institute), as a representative organization in Japan, has been participating in many international cooperations on nuclear safety research. This report reviews the recent achievement and evolution of the international cooperative safety studies. Twelve projects that are based on the agreements between JAERI and foreign organizations are reviewed. As the fuel irradiation studies, the recent achievement of the OECD Halden Reactor Project and the agreement between Pacific Northwest Laboratories, Battelle Memorial Institute, and JAERI are explained. As for the study of reactivity accident, the cooperation of the NSRR (Nuclear Safety Research Reactor) project in Japan with PBF, PNS and PHEBUS projects in the U.S., West Germany and France, respectively, are now in progress. The fuel performance in abnormal transient and the experiment and analysis of severe fuel damage are the new areas of international interest. The OECD/LOFT project and ROSA-4 projects are also explained in connection with the FP source term problem and the analysis codes such as RELAP-5 and TRAC. As the safety studies associated with the downstream of the nuclear fuel cycle, the BEFAST project of IAEA and the ISIRS project of OECD/NEA are shortly reviewed. (Aoki, K.)

  19. Report of the summative evaluation by the advisory committee on nuclear safety research

    International Nuclear Information System (INIS)

    2005-03-01

    The Research Evaluation Committee of the Japan Atomic Energy Research Institute (JAERI) set up an Advisory Committee on Nuclear Safety Research in accordance with the 'Fundamental Guideline for the Evaluation of Research and Development (R and D) at JAERI' and its subsidiary regulations. The Advisory Committee on Nuclear Safety Research evaluated the adequacy of the plans of nuclear safety research to be succeeded from JAERI to a new research institute which will be established by integration of JAERI and the Japan Nuclear Cycle Development Institute (JNC). The Advisory Committee consisted of eight specialists from outside the JAERI conducted its activities from June 2004 to August 2004. The evaluation was performed on the basis of the materials submitted in advanced and of the oral presentations made at the Advisory Committee meeting which was held on July 27, 2004, in line with the items, viewpoints, and criteria for the evaluation specified by the Research Evaluation Committee. The result of the evaluation by the Advisory Committee was submitted to the Research Evaluation Committee, and was judged to be appropriate at its meeting held on December 1, 2004. This report describes the result of the evaluation by the Advisory Committee on Safety Research. (author)

  20. Legitimacy and Reputation in the Institutional Field of Food Safety

    DEFF Research Database (Denmark)

    Merkelsen, Henrik

    2013-01-01

    The overall objective of this study is to examine how the institutional context of food safety affects and is affected by concerns for legitimacy and reputation. The paper employs a neo-institutional approach to analyzing the institutional field of food safety in a case study of a multinational...... food service provider where a tension between conflicting institutional logics implied a reputational challenge. The study shows how food safety as a well-defined operational risk is transformed into a high-priority reputational risk and how actors in the field of food safety are caught in a state...... of mutual distrust, partly as a consequence of an intense politicization of food risk over the past years and partly as a result of their respective concerns for legitimacy. The study points to how the field of food safety is colonized by a reputational logic that is paradoxically reproduced by actors...

  1. Nuclear safety research in HGF 2012

    International Nuclear Information System (INIS)

    Anon.

    2013-01-01

    Nuclear Competence Association. The Forschungszentrum Juelich GmbH, HZDR Helmholtz-Zentrum Dresden-Rossendorf and the KIT Karlsruhe Institute of Technology are involved in the Nuclear Safety Research Program within the Helmholtz Association. The work and results in 2012 are presented. (orig.)

  2. Institute for Nuclear Research and Nuclear Energy and Nuclear Science

    International Nuclear Information System (INIS)

    Stamenov, J.

    2004-01-01

    The Institute for Nuclear Research and Nuclear Energy (INRNE) of the Bulgarian Academy of Sciences is the leading Bulgarian Institute for scientific investigations and applications of nuclear science. The main Institute's activities in the field of elementary particles and nuclear physics, high energy physics and nuclear energy, radiochemistry, radioecology, radioactive wastes treatment, monitoring of the environment, nuclear instruments development ect. are briefly described. Several examples for: environmental radiation monitoring; monitoring of the radioactivity and heavy metals in aerosols, 99m Tc clinical use, Boron Neutron Capture Therapy application of IRT-2000 Research Reactor, neutron fluence for reactor vessel embrittlement, NPP safety analysis, nuclear fuel modelling are also presented

  3. Knowledge basis in safety culture for researchers and practitioners

    International Nuclear Information System (INIS)

    Vieira Neto, Antonio S.; Barroso, Antonio C.O.; Goncalves, Adriana

    2009-01-01

    This paper presents the main characteristics of the knowledge basis in safety culture which is being developed at the IPEN-CNEN/SP, one of the Brazilian nuclear institutes of research. The main objective of this basis is to organize the information about safety culture found in the literature and to make it available to researchers and practitioners. The first stage of the development of this basis is already finished being the subject of this work. (author)

  4. Annual report of the Japan Atomic Energy Research Institute for fiscal 1999

    International Nuclear Information System (INIS)

    2000-01-01

    The Japan Atomic Energy Research Institute (JAERI) has promoted some researches for contributing to general development of science and technology based on nuclear research and development such as neutron science research, light quantum and radiation beam science research, radiation application research, high level computational science research, advanced basic research, and so forth, along the 'Long-term plan on nuclear research, development and application' established on June, 1994. And, researches and developments on leading energy system bringing breakthrough of nuclear technology such as study on future type energy system, research and development of nuclear fusion, and high temperature engineering test research. In addition, as a research containing both fields of general nuclear science and nuclear energy, safety research and health and physics research were also promoted. Furthermore, together with not only inland co-operation with industry, university and institute, but also promotion of diverse international co-operation, effective research and development has been carried out by various research assistant business. Here were described in details on researches on neutron science, light quantum and radiation beam science, radiation application, material science, environmental science, advanced basic research, high level computational science, nuclear fusion, future type energy system, high-temperature engineering test, safety, and relative research, and on operation and safety management, relative technology and outsider operation, and construction arrangement. (G.K.)

  5. Nuclear safety research in HGF 2011; Nukleare Energieforschung 2011. Forschungszentren. Status und Entwicklung

    Energy Technology Data Exchange (ETDEWEB)

    Tromm, Walter [Karlsruher Institut fuer Technologie (KIT), Eggenstein-Leopoldshafen (Germany). Programm NUKLEAR

    2012-06-15

    of the partners in the Nuclear Competence Association. As of January 2011, the Dresden-Rossendorf Helmholtz Center (HZDR), with its 2 Institutes of Safety Research and for Radiochemistry, is an integral part of the Nuclear Safety Research Program within the Energy Research Area. Both institutes work on topics of safety research for nuclear reactors and safety research for nuclear waste management. In this way, the 2 institutes represent very welcome added value as well as a supplement to the Nuclear Safety Research Program. (orig.)

  6. Annual report of Nuclear Science Research Institute, JFY2005

    International Nuclear Information System (INIS)

    2007-04-01

    Japan Atomic Energy Agency (JAEA) was inaugurated on October 1st, 2005. Works for the operation and maintenance of various research facilities as well as safety management, radiation protection, and radioactive wastes management, which have been undertaken by departments in Tokai Research Establishment of Japan Atomic Energy Research Institute (JAERI), were inherited by newly established departments of Nuclear Science Research Institute (NSRI). The NSRI is composed of Planning and Coordination Office and seven departments such as Department of Operational Safety Administration, Department of Radiation Protection, Department of Research Reactor and Tandem Accelerator, Department of Hot Laboratories and Facilities, Department of Criticality and Fuel Cycle Research Facilities, Department of Decommissioning and Waste Management, and Engineering Services Department. This annual report of JFY 2005 summarizes the activities of NSRI and is expected to be referred to and utilized by R and D departments and project promotion sectors at NSRI site for the enhancement of their own research and management activities to attain their goals according to Middle-term Plan' successfully and effectively. In chapter 1, outline of organization and administrative activities of NSRI is described. In chapter 2, the following activities made by the departments in NSRI are summarized, i.e., (1) operation and maintenance of research reactors (JRR-3, JRR-4, NSRR), criticality assemblies (STACY, TRACY, FCA, TCA), hot laboratories, (BECKY, Reactor Fuel Examination Facility, WASTEF, Research Laboratory 4, Plutonium Research Laboratory 1, Tokai Hot Laboratory, etc), and large-scale facilities (Tandem accelerator, LSTF, THYNC, TPTF, etc), and (2) safety management, radiation protection, management of radioactive wastes, decommissioning of nuclear facilities, engineering services, utilities and maintenance, etc, all of which are indispensable for the stable and safe operation and utilization of the

  7. LWR safety research at EPRI: an update

    International Nuclear Information System (INIS)

    Loewenstein, W.B.; Kalra, S.P.

    1983-01-01

    The philosophy, objectives, approach, and updated status of the Electric Power Research Institute's Light-Water-Reactor Safety Research Program are presented. In light of current industry needs, the major research and development emphases are described. The program focuses on providing enhanced capability via large-scale test projects, for understanding and predicting the behavior of nuclear power plants. This leads to a realistic quantification of the safety margins and to ways of improving reliability, availability, and productivity and thus to significant economic benefits for the nuclear industry. The major accomplishments resulting from various projects in the program categories of risk assessment, code development and validation, and analysis and testing are presented with the goal of technology transfer to the nuclear industry

  8. Management of nanomaterials safety in research environment

    Directory of Open Access Journals (Sweden)

    Riediker Michael

    2010-12-01

    Full Text Available Abstract Despite numerous discussions, workshops, reviews and reports about responsible development of nanotechnology, information describing health and environmental risk of engineered nanoparticles or nanomaterials is severely lacking and thus insufficient for completing rigorous risk assessment on their use. However, since preliminary scientific evaluations indicate that there are reasonable suspicions that activities involving nanomaterials might have damaging effects on human health; the precautionary principle must be applied. Public and private institutions as well as industries have the duty to adopt preventive and protective measures proportionate to the risk intensity and the desired level of protection. In this work, we present a practical, 'user-friendly' procedure for a university-wide safety and health management of nanomaterials, developed as a multi-stakeholder effort (government, accident insurance, researchers and experts for occupational safety and health. The process starts using a schematic decision tree that allows classifying the nano laboratory into three hazard classes similar to a control banding approach (from Nano 3 - highest hazard to Nano1 - lowest hazard. Classifying laboratories into risk classes would require considering actual or potential exposure to the nanomaterial as well as statistical data on health effects of exposure. Due to the fact that these data (as well as exposure limits for each individual material are not available, risk classes could not be determined. For each hazard level we then provide a list of required risk mitigation measures (technical, organizational and personal. The target 'users' of this safety and health methodology are researchers and safety officers. They can rapidly access the precautionary hazard class of their activities and the corresponding adequate safety and health measures. We succeed in convincing scientist dealing with nano-activities that adequate safety measures and

  9. Management of nanomaterials safety in research environment.

    Science.gov (United States)

    Groso, Amela; Petri-Fink, Alke; Magrez, Arnaud; Riediker, Michael; Meyer, Thierry

    2010-12-10

    Despite numerous discussions, workshops, reviews and reports about responsible development of nanotechnology, information describing health and environmental risk of engineered nanoparticles or nanomaterials is severely lacking and thus insufficient for completing rigorous risk assessment on their use. However, since preliminary scientific evaluations indicate that there are reasonable suspicions that activities involving nanomaterials might have damaging effects on human health; the precautionary principle must be applied. Public and private institutions as well as industries have the duty to adopt preventive and protective measures proportionate to the risk intensity and the desired level of protection. In this work, we present a practical, 'user-friendly' procedure for a university-wide safety and health management of nanomaterials, developed as a multi-stakeholder effort (government, accident insurance, researchers and experts for occupational safety and health). The process starts using a schematic decision tree that allows classifying the nano laboratory into three hazard classes similar to a control banding approach (from Nano 3--highest hazard to Nano1--lowest hazard). Classifying laboratories into risk classes would require considering actual or potential exposure to the nanomaterial as well as statistical data on health effects of exposure. Due to the fact that these data (as well as exposure limits for each individual material) are not available, risk classes could not be determined. For each hazard level we then provide a list of required risk mitigation measures (technical, organizational and personal). The target 'users' of this safety and health methodology are researchers and safety officers. They can rapidly access the precautionary hazard class of their activities and the corresponding adequate safety and health measures. We succeed in convincing scientist dealing with nano-activities that adequate safety measures and management are promoting

  10. Safety management at nuclear installations with research reactors. A comparison of five European installations

    International Nuclear Information System (INIS)

    Troen, H.; Lauridsen, B.

    1997-11-01

    Five European institutions with nuclear research reactors were visited to compare safety management among institutions similar to Risoe. Risoe is a National Laboratory and the main activities are research and development. In 1996 it was decided to look into safety management at Risoe again; the last revision was in 1972. The purpose was to make it more efficient and to emphasise, that the responsibility lies in the operating organisation. Information such as nuclear facilities at the institutions, the safety management organisation, emergency preparedness, and lists of radiation doses to the employees from the years 1995 and 1996 is given in the report. Also international requirements and recommendations are given in short. Furthermore the report contains some reflections on the development in safety management organisations in resent years and the conclusions drawn from the information gathered

  11. System of institutional radioactive waste management in the Nuclear Research Institute Rez plc

    International Nuclear Information System (INIS)

    Podlaha, J.; Burian, P.

    2005-01-01

    The Nuclear Research Institute Rez plc (NRI) is a leading institution in the area of nuclear Research and Development in the Czech Republic. The NRI has had a dominant position in the nuclear programme since it was established in 1955 as a state-owned research organization and it has developed to its current status. In December 1992 the NRI has been transformed into a joint-stock company. The NRI's activity encompasses nuclear physics, chemistry, nuclear power, experiments at the research reactor and many other topics. Main issues addressed in the NRI in the past decades were concentrated on research, development and services provided to the nuclear power plants operating WWER reactors, development of chemical technologies for fuel cycle and irradiation services to research and development in the industrial sector, agriculture, food processing and medicine. At present the research activities are mainly targeted to assist the State Office for Nuclear Safety -the nuclear safety regulating body, power plant operator and nuclear facilities contractors. Significant attention is also paid to the use of nuclear technology outside the nuclear power sector, providing a wide range of services to industry , medicine and the preparation of radiopharmaceuticals. NRI operates two research nuclear reactors and another facilities such as a hot cell facility , research laboratories, technology for radioactive waste (RAW) management, 60 Co irradiators, an electron accelerator, etc. In this paper the Centre of RAW management, system of RAW management, facilities for RAW management as well as decontamination and decommissioning activities of the NRI are presented. The NRI provides complex services in the area of RAW management and has gained many experience and full qualification not only in this area but also in the area of decontamination and decommissioning and spent fuel management. The NRI guarantees safe RAW and spent fuel management. (authors)

  12. Safety of Research Reactors. Safety Requirements

    International Nuclear Information System (INIS)

    2010-01-01

    The main objective of this Safety Requirements publication is to provide a basis for safety and a basis for safety assessment for all stages in the lifetime of a research reactor. Another objective is to establish requirements on aspects relating to regulatory control, the management of safety, site evaluation, design, operation and decommissioning. Technical and administrative requirements for the safety of research reactors are established in accordance with these objectives. This Safety Requirements publication is intended for use by organizations engaged in the site evaluation, design, manufacturing, construction, operation and decommissioning of research reactors as well as by regulatory bodies

  13. Nuclear safety research collaborations between the US and Russian Federation international nuclear safety centers

    International Nuclear Information System (INIS)

    Hill, D.J; Braun, J.C; Klickman, A.E.; Bugaenko, S.E; Kabanov, L.P; Kraev, A.G.

    2000-01-01

    The Russian Federation Ministry for Atomic Energy (MINATOM) and the U.S. Department of Energy (USDOE) have formed International Nuclear Safety Centers to collaborate on nuclear safety research. USDOE established the U. S. Center at Argonne National Laboratory in October 1995. MINATOM established the Russian Center at the Research and Development Institute of Power Engineering in Moscow in July 1996. In April 1998 the Russian center became an independent, autonomous organization under MINATOM. The goals of the centers are to: cooperate in the development of technologies associated with nuclear safety in nuclear power engineering. be international centers for the collection of information important for safety and technical improvements in nuclear power engineering. maintain a base for fundamental knowledge needed to design nuclear reactors.The strategic approach that is being used to accomplish these goals is for the two centers to work together to use the resources and the talents of the scientists associated with the US Center and the Russian Center to do collaborative research to improve the safety of Russian-designed nuclear reactors

  14. Current and anticipated uses of thermal hydraulic codes at the Japan Atomic Energy Research Institute

    International Nuclear Information System (INIS)

    Akimoto, Hajime; Kukita; Ohnuki, Akira

    1997-01-01

    The Japan Atomic Energy Research Institute (JAERI) is conducting several research programs related to thermal-hydraulic and neutronic behavior of light water reactors (LWRs). These include LWR safety research projects, which are conducted in accordance with the Nuclear Safety Commission's research plan, and reactor engineering projects for the development of innovative reactor designs or core/fuel designs. Thermal-hydraulic and neutronic codes are used for various purposes including experimental analysis, nuclear power plant (NPP) safety analysis, and design assessment

  15. 29 CFR 1960.35 - National Institute for Occupational Safety and Health.

    Science.gov (United States)

    2010-07-01

    ... 29 Labor 9 2010-07-01 2010-07-01 false National Institute for Occupational Safety and Health. 1960.35 Section 1960.35 Labor Regulations Relating to Labor (Continued) OCCUPATIONAL SAFETY AND HEALTH... § 1960.35 National Institute for Occupational Safety and Health. (a) The Director of the National...

  16. New Institutional Theory and a Culture of Safety in Agriculture.

    Science.gov (United States)

    Janssen, Brandi; Nonnenmann, Matthew W

    2017-01-01

    Health and safety professionals often call for an improved safety culture in agriculture. Such a shift would result in agricultural practices that prioritize safe work habits and see safety as both an effective means to improve production and a goal worth pursuing in its own right. This article takes an anthropological approach and demonstrates the potential for new institutional theory to conceptualize broader cultural change in agriculture. New institutional theory examines the roles of organizations and the ways that they inform and support broad social institutions. Using preliminary data from the agricultural lending industry in Iowa and integrated poultry production in Texas, this article considers the ability of these organizations to contribute to systemic change and an improved culture of safety in agriculture.

  17. Rossendorf Research Center, Institute of Safety Research. Annual report 1991

    International Nuclear Information System (INIS)

    Boehmert, J.; Weiss, F.P.

    1992-08-01

    The working program covers above all topics concerning the assessment of design basis safety and the increase of operational safety of the WWER type reactors. The topics are directed to the WWER-440/213 type and to the WWER-1000 type, and are dealt with by the three departments, i.e. incident analysis, neutron embrittlement, and mechanical integrity. One paper is concerned with the determination of the neutron field of HERA. (orig.) [de

  18. Current and anticipated uses of thermal hydraulic codes at the Japan Atomic Energy Research Institute

    Energy Technology Data Exchange (ETDEWEB)

    Akimoto, Hajime; Kukita; Ohnuki, Akira [Japan Atomic Energy Research Institute, Ibaraki (Japan)

    1997-07-01

    The Japan Atomic Energy Research Institute (JAERI) is conducting several research programs related to thermal-hydraulic and neutronic behavior of light water reactors (LWRs). These include LWR safety research projects, which are conducted in accordance with the Nuclear Safety Commission`s research plan, and reactor engineering projects for the development of innovative reactor designs or core/fuel designs. Thermal-hydraulic and neutronic codes are used for various purposes including experimental analysis, nuclear power plant (NPP) safety analysis, and design assessment.

  19. Karlsruhe Nuclear Research Center, Institute of Materials Research. Progress report on research and development work in 1993

    International Nuclear Information System (INIS)

    1994-03-01

    The Institute consists of three parts IMF I, IMF II and IMF III. The tasks are divided into applied material physics (IMF I), material and structural mechanics (IMF II) and material process technology (IMF III). IMF I works preferably on the development of metallic, non-metallic and compound materials and on questions of the structure and properties of boundary surfaces and surface protection coatings. The main work of IMF II is the reliability of components, failure mechanics and the science of damage. IMF III examines process technology questions in the context of the manufacture of ceramic materials and fusion materials and the design of nuclear components. The Institute works on various main points of the Kernforschungszentrum in its research work, particularly in nuclear fusion, micro-system technique, nuclear safety research, superconductivity and in processes with little harmful substances and waste. Material and strength problems for future fusion reactors and fission reactors, in powerful micro systems and safety-related questions of nuclear technology are examined. Also, research not bound to projects in the field of metallic, ceramic and polymer materials for high stresses is carried out. (orig.) [de

  20. The 1988 progress report of the Nuclear Safety and Protection Institut

    International Nuclear Information System (INIS)

    Anon.

    1988-01-01

    The 1988 progress report of the Nuclear Safety and Protection Institut (CEA, France). The Institute's fields of action involve: The activities and technical safety of the nuclear power plants, the environmental and human radiation protection which includes technical, health and medical aspects, the nuclear materials compatibility and control and the accident intervention actions. The 1988 Institute activities are characterized by the continuity of the previous technical safety directives, by the improvement of the nuclear risk communication and of the international cooperation [fr

  1. Institut fuer Materialforschung. Research and development activities in 1994

    International Nuclear Information System (INIS)

    1995-01-01

    The IMF consists of three institutes with different tasks: IMF I works mainly on the development of metals, nonmetals and composite materials and on problems concerning the structure and properties of interfaces and protective layers. IMF II works on component reliablility, failure mechanisms and damage analysis. IMF III works on problems of process engineering in the production of ceramic powders and ceramic, metallic and polymeric microstructures, as well as on the design of nuclear components and the optimisation of corrosive materials. The IMF supports the research activities of Karlsruhe Research Center, especially in nuclear fusion research, microsystems engineering, nuclear safety, superconductivity, and low-pollution and low-waste processes. Materials and strength problems are investigated for future fusion reactors, high-performance microsystems, and safety problems in nuclear engineering. (orig./MM) [de

  2. Translating Health Services Research into Practice in the Safety Net.

    Science.gov (United States)

    Moore, Susan L; Fischer, Ilana; Havranek, Edward P

    2016-02-01

    To summarize research relating to health services research translation in the safety net through analysis of the literature and case study of a safety net system. Literature review and key informant interviews at an integrated safety net hospital. This paper describes the results of a comprehensive literature review of translational science literature as applied to health care paired with qualitative analysis of five key informant interviews conducted with senior-level management at Denver Health and Hospital Authority. Results from the literature suggest that implementing innovation may be more difficult in the safety net due to multiple factors, including financial and organizational constraints. Results from key informant interviews confirmed the reality of financial barriers to innovation implementation but also implied that factors, including institutional respect for data, organizational attitudes, and leadership support, could compensate for disadvantages. Translating research into practice is of critical importance to safety net providers, which are under increased pressure to improve patient care and satisfaction. Results suggest that translational research done in the safety net can better illuminate the special challenges of this setting; more such research is needed. © Health Research and Educational Trust.

  3. Radiation safety research information database

    International Nuclear Information System (INIS)

    Yukawa, Masae; Miyamoto, Kiriko; Takeda, Hiroshi; Kuroda, Noriko; Yamamoto, Kazuhiko

    2004-01-01

    National Institute of Radiological Sciences in Japan began to construct Radiation Safety Research Information Database' in 2001. The research information database is of great service to evaluate the effects of radiation on people by estimating exposure dose by determining radiation and radioactive matters in the environment. The above database (DB) consists of seven DB such as Nirs Air Borne Dust Survey DB, Nirs Environmental Tritium Survey DB, Nirs Environmental Carbon Survey DB, Environmental Radiation Levels, Abe, Metabolic Database for Assessment of Internal Dose, Graphs of Predicted Monitoring Data, and Nirs nuclear installation environment water tritium survey DB. Outline of DB and each DB are explained. (S.Y.)

  4. Assessment report of the Radiation protection and Nuclear Safety Institute (IRSN)

    International Nuclear Information System (INIS)

    2011-03-01

    After having recalled and commented the three main missions of the IRSN (an expertise capacity, a mission of research, a mission of public information and training), this report analyzes and comments the governance of the institute: a very much structured pyramidal organisation based on a quality approach, a human resource management policy adapted to short and middle term needs, patrimony and estate policy, financial and budgetary policy, personnel hygiene and safety policy. It analyzes and comments the different relationship and partnership maintained by the IRSN with institutions and companies. Strengths and weaknesses are outlined and some recommendations are proposed

  5. JRC-IE's research of safety of Gen IV systems

    International Nuclear Information System (INIS)

    Tsige-Tamirat, H.; Ranguelova, V.; Feutterer, M.; Ammirabile, L.; Carlsson, J.; D'Agata, E.; Laurie, M.; Magallon, D.

    2010-01-01

    The Institute for Energy (IE), one of the seven scientific Institutes of the Joint Research Centre (JRC) of the European Commission, has the mission to provide scientific and technical support for the conception, development, implementation and monitoring of community policies related to energy. To accomplish its mission, IE performs research in the areas of renewable energies, safety and sustainability of nuclear energy for current and future reactor systems, energy technic/economic assessment, and security of energy supply. The Generation IV International Forum (GIF) is a cooperative international endeavour organized to carry out R and D needed to establish the feasibility and performance capabilities of the next generation nuclear energy systems and support the progress towards their realization. The EU, represented by EURATOM and with the JRC as implementing agent, is working together with other GIF partners to perform pre-competitive R and D on key technologies to be implemented in future nuclear systems. IE is engaged in experimental research, simulation and modeling, scientific, feasibility and engineering studies on innovative nuclear reactor systems needed to support the EURATOM contribution to GEN IV initiative, in particular in assessment of innovative fuels and materials, development of new reactor core concepts and safety solutions and knowledge management and preservation. IE's research activities on Generation IV reactor systems are focused on the assessment of the potential of such systems to meet long term EU energy needs with respect to economical advantages, enhanced safety, sustainability, and proliferation resistance. IE participates in international collaborations and has bilateral research cooperation both with European and non-European partners. This paper gives an overview of IE's current research activities on the Gen IV reactor systems related to safety. (authors)

  6. Progress report on research and development in 1991, Institute of Neutron Physics and Reactor Engineering, KfK

    International Nuclear Information System (INIS)

    1992-03-01

    Progress report on research and development in 1991 Institute of Neutron Physics and Reactor Engineering. The Institute of Neutron Physics and Reactor Engineering is concerned with research work in the field of nuclear engineering related to the safety of fast and thermal reactors as well as with specific problems of fusion reactor technology. Under the project of nuclear safety research, the Institute works on concepts designed to drastically improve reactor safety. Apart from that, methods to estimate and minimize the radiological consequences of reactor accidents are developed. Under the fusion technology project, the Institute deals with neutron physics and technological questions of the breeding blanket. Basic research covers technico-physical questions of the interaction between light ion radiation of a high energy density and matter. In addition and to a small extent, questions of employing hydrogen in the transport area are studied. For all these tasks it is indispensable to use up-to-date data processing methods and equipment, from the highest capacity computer to the integrated minicomputer system. (orig./DG) [de

  7. RA research reactor in 'Vinca' Institute-approach to the decommissioning

    International Nuclear Information System (INIS)

    Ljubenov, V.Lj.; Pesic, M.P.; Sotic, O.

    2002-01-01

    In this paper short overview of decommissioning process of research reactors according to IAEA standards and world practice is given. Basic technical characteristics and details of operational history of the RA research reactor in Vinca Institute of Nuclear Sciences are present. The main nuclear and radiation safety problems related to the RA reactor facility are defined and the outlines of the future decommissioning project are proposed. (author)

  8. Peer training of safety-related skills to institutional staff: benefits for trainers and trainees.

    OpenAIRE

    van Den Pol, R A; Reid, D H; Fuqua, R W

    1983-01-01

    A peer training program, in which experienced staff trained new staff, was evaluated as a method for teaching and maintaining safety-related caregiver skills in an institutional setting for the developmentally disabled. Three sets of safety-type skills were assessed in simulated emergency situations: responding to facility fires, managing aggressive attacks by residents, and assisting residents during convulsive seizures. Using a multiple-baseline research design, results indicated that the p...

  9. Yearly program of safety research in nuclear power facilities from fiscal 1981 to 1985

    International Nuclear Information System (INIS)

    Anon.

    1984-01-01

    Nuclear safety research plans for nuclear power facilities and others from fiscal 1981 to 1985 are presented for the following areas: the safety of LWR fuel, loss-of-coolant accidents, the structural safety of LWR installations, the reduction of radioactive material release from nuclear power facilities, the stochastic safety evaluation of nuclear power facilities, the aseismicity of nuclear power facilities, the safety of nuclear fuel facilities, and the safety of nuclear fuel transport vessels. In the respective areas, the needs for research and the outline of research works are summarized. Then, about the major research works in each area, the purpose, contents, term and responsible institution of the research are given. (Mori, K.)

  10. Radiation processing project at the Institute of Nuclear Energy Research

    International Nuclear Information System (INIS)

    Tsai, C.M.; Fu, Y.K.; Yang, Y.H.; Chen, Y.T.; Wei, Y.H.; Lee, K.P.; Wang, Y.K.

    1981-01-01

    The utilization of scientific approach to preserve and sterilize the agricultural products has long been studied since 1954 and was adopted by several countries gradually since 1958. Starting from July 1977 this Institute began to study the preservation of potatoes and onions with reference to sprout inhibition which is discussed and its economical aspect is evaluated. The design concept of a megacurie 60 Co irradiator at this Institute is illustrated. The progress of construction work for the irradiator and the safety device in particular are reported. Current research project on the preservation of agricultural products in this Institute is presented. (author)

  11. Karlsruhe Nuclear Research Center, Central Safety Department. Annual report 1993

    International Nuclear Information System (INIS)

    Koelzer, W.

    1994-04-01

    The Central Safety Department is responsible for handling all tasks of radiation protection, safety and security of the institutes and departments of the Karlsruhe Nuclear Research Center, for waste water activity measurements and environmental monitoring of the whole area of the Center, and for research and development work mainly focusing on nuclear safety and radiation protection measures. The research and development work concentrates on the following aspects: behavior of trace elements in the environment and decontamination of soil, behavior of tritium in the air/soil-plant system, improvement in radiation protection measurements and personnel dosimetry. This report gives details of the different duties, indicates the results of 1993 routine tasks and reports about results of investigations and developments of the working groups of the Department. (orig.) [de

  12. International human cooperation in Japan Atomic Energy Research Institute

    International Nuclear Information System (INIS)

    Shiba, Koreyuki; Kaieda, Keisuke; Makuuchi, Keizo; Takada, Kazuo; Nomura, Masayuki

    1997-01-01

    Rearing of talented persons in the area of nuclear energy is one of the important works in Japan Atomic Energy Research Institute. In this report, the present situations and future schedules of international human cooperation in this area wsere summarized. First, the recent activities of International Nuclear Technology Center were outlined in respect of international human cooperation. A study and training course which was started in cooperation with JICA and IAEA from the middle of eighties and the international nuclear safety seminar aiming at advancing the nuclear safety level of the world are now being put into practice. In addition, a study and training for rearing talented persons was started from 1996 to improve the nuclear safety level of the neighbouring countries. The activities of the nuclear research interchange system by Science and Technology Agency established in 1985 and Bilateral Co-operation Agreement from 1984 were explained and also various difficulties in the international cooperation were pointed out. (M.N.)

  13. The European Nuclear Safety Training and Tutoring Institute

    International Nuclear Information System (INIS)

    2012-01-01

    The European Nuclear Safety Training and Tutoring Institute, ENSTTI, is an initiative of European Technical Safety Organizations (TSO) in order to provide vocational training and tutoring in the methods and practices required to perform assessment in nuclear safety, nuclear security and radiation protection. ENSTTI calls on TSOs' expertise to maximize the transmission of safety and security knowledge, practical experience and culture. Training, tutoring and courses for specialists are achieved through practical lectures, working group and technical visits and lead to a certificate after knowledge testing. ENSTTI contributes to the harmonization of nuclear safety and security practices and to the networking of today and future nuclear safety experts in Europe and beyond. (A.C.)

  14. A National Institute of Radiation Protection and Nuclear Safety?

    International Nuclear Information System (INIS)

    Hartley, B.M.

    1993-01-01

    The practice of radiation protection within Australia is fragmented on a number of different levels. Each state has its own radiation protection organisation. Within the Commonwealth there is also a large number of bodies which deal with different aspects of radiation protection or nuclear safety. There is also an interest in occupational radiation protection by Departments responsible for Occupational Health and Safety. It is estimated that this fragmentation affects the practice of radiation protection at a State level and also the role which Australia can play internationally. The establishment of a National Institute of Radiation Protection and Nuclear Safety is therefore proposed. Possible structures and organizational arrangements for such an institute are discussed. 4 refs., 4 tabs., 3 figs

  15. Annual report 2012. Institute of Resource Ecology

    International Nuclear Information System (INIS)

    Brendler, Vinzenz

    2013-01-01

    The Institute of Resource Ecology (IRE) is one of the currently eight institutes of the Helmholtz-Zentrum Dresden-Rossendorf (HZDR). The research activities are fully integrated into the program ''Nuclear Safety Research'' of the Helmholtz Association and focused on the topics ''Safety of Nuclear Waste Disposal'' and ''Safety Research for Nuclear Reactors''. With the integration of the division of ''Reactor Safety'' from the former ''Institute of Safety Research'' nuclear research at HZDR is now mainly concentrated within this institute. In addition, various activities have been started investigating chemical and environmental aspects of processing and recycling of strategic metals, namely rare earth elements. Here, a knowledge transfer from the nuclear to the non-nuclear community, branching thermodynamics and spectroscopy, has been established. This also strengthens links to the recently established ''Helmholtz-Institute Freiberg for Resource Technology''.

  16. Annual report 2012. Institute of Resource Ecology

    Energy Technology Data Exchange (ETDEWEB)

    Brendler, Vinzenz [ed.

    2013-09-01

    The Institute of Resource Ecology (IRE) is one of the currently eight institutes of the Helmholtz-Zentrum Dresden-Rossendorf (HZDR). The research activities are fully integrated into the program ''Nuclear Safety Research'' of the Helmholtz Association and focused on the topics ''Safety of Nuclear Waste Disposal'' and ''Safety Research for Nuclear Reactors''. With the integration of the division of ''Reactor Safety'' from the former ''Institute of Safety Research'' nuclear research at HZDR is now mainly concentrated within this institute. In addition, various activities have been started investigating chemical and environmental aspects of processing and recycling of strategic metals, namely rare earth elements. Here, a knowledge transfer from the nuclear to the non-nuclear community, branching thermodynamics and spectroscopy, has been established. This also strengthens links to the recently established ''Helmholtz-Institute Freiberg for Resource Technology''.

  17. 78 FR 32473 - Southwest Research Institute: Modification of Scope of Recognition

    Science.gov (United States)

    2013-05-30

    ... DEPARTMENT OF LABOR Occupational Safety and Health Administration [Docket No. OSHA-2006-0041... Administration (OSHA), Labor. ACTION: Notice. SUMMARY: In this notice, OSHA is issuing a determination deleting a...), Southwest Research Institute, based on that NRTL's voluntary request that OSHA reduce its scope of...

  18. 78 FR 12065 - National Institute for Occupational Safety and Health Personal Protective Technology for...

    Science.gov (United States)

    2013-02-21

    ... Institute for Occupational Safety and Health Personal Protective Technology for Pesticide Handlers: Stakeholder Meeting AGENCY: The National Institute for Occupational Safety and Health (NIOSH) of the Centers...: Notice of public meeting. SUMMARY: The National Institute for Occupational Safety and Health (NIOSH) of...

  19. Nuclear Research Center Karlsruhe, Central Safety Department. Annual report 1992

    International Nuclear Information System (INIS)

    Koelzer, W.

    1993-05-01

    The Central Safety Department is responsible for handling all problems of radiation protection, safety and security of the institutes and departments of the Karlsruhe Nuclear Research Center, for waste water activity measurements and environmental monitoring of the whole area of the Center, and for research and development work mainly focusing on nuclear safety and radiation protection measures. The research and development work concentrates on the following aspects: Physical and chemical behavior of trace elements in the environment, biophysics of multicellular systems, behavior of tritium in the air/soil-plant system, improvement in radiation protection measurement and personnel dosimetry. This report gives details of the different duties, indicates the results of 1992 routine tasks and reports about results of investigations and developments of the working groups of the Department. The reader is referred to the English translation of Chapter 1 describing the duties and organization of the Central Safety Department. (orig.) [de

  20. 75 FR 44967 - National Institute for Occupational Safety and Health

    Science.gov (United States)

    2010-07-30

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES National Institute for Occupational Safety and Health... Occupational Safety and Health (NIOSH), Department of Health and Human Services (HHS). ACTION: Notice. SUMMARY... Occupational Safety and Health (NIOSH), 4676 Columbia Parkway, MS C-46, Cincinnati, OH 45226, Telephone 877-222...

  1. Fuel safety research 1999

    Energy Technology Data Exchange (ETDEWEB)

    Uetsuka, Hiroshi (ed.) [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    2000-07-01

    In April 1999, the Fuel Safety Research Laboratory was newly established as a result of reorganization of the Nuclear Safety Research Center, JAERI. The laboratory was organized by combining three laboratories, the Reactivity Accident Laboratory, the Fuel Reliability Laboratory, and a part of the Sever Accident Research Laboratory. Consequently, the Fuel Safety Research Laboratory is now in charge of all the fuel safety research in JAERI. Various types of experimental and analytical researches are conducted in the laboratory by using the unique facilities such as the Nuclear Safety Research Reactor (NSRR), the Japan Material Testing Reactor (JMTR), the Japan Research Reactor 3 (JRR-3) and hot cells in JAERI. The laboratory consists of five research groups corresponding to each research fields. They are; (a) Research group of fuel behavior under the reactivity initiated accident conditions (RIA group). (b) Research group of fuel behavior under the loss-of-coolant accident conditions (LOCA group). (c) Research group of fuel behavior under the normal operation conditions (JMTR/BOCA group). (d) Research group of fuel behavior analysis (FEMAXI group). (e) Research group of FP release/transport behavior from irradiated fuel (VEGA group). This report summarizes the outline of research activities and major outcomes of the research executed in 1999 in the Fuel Safety Research Laboratory. (author)

  2. Institutional Oversight of Occupational Health and Safety for Research Programs Involving Biohazards

    OpenAIRE

    Dyson, Melissa C; Carpenter, Calvin B; Colby, Lesley A

    2017-01-01

    Research with hazardous biologic materials (biohazards) is essential to the progress of medicine and science. The field of microbiology has rapidly advanced over the years, partially due to the development of new scientific methods such as recombinant DNA technology, synthetic biology, viral vectors, and the use of genetically modified animals. This research poses a potential risk to personnel as well as the public and the environment. Institutions must have appropriate oversight and take app...

  3. Main tasks of the Nuclear Research Institute in the period till the year 2000

    International Nuclear Information System (INIS)

    Podest, M.

    1989-06-01

    The main tasks of the Nuclear Research Institute will be oriented to: safety of nuclear power installations; expert and diagnostic systems for such installations; the effect of operating medium on the life of nuclear power plants; disposal of radioactive wastes; prospective nuclear sources; research into and development of radiopharmaceuticals; radiation technologies and methods. Specific tasks are itemized. The statute of the Institute is attached. (J.B.). 1 tab

  4. Systematic impact of institutional pressures on safety climate in the construction industry.

    Science.gov (United States)

    He, Qinghua; Dong, Shuang; Rose, Timothy; Li, Heng; Yin, Qin; Cao, Dongping

    2016-08-01

    This paper explores how three types of institutional pressure (i.e., coercive, mimetic and normative pressures) systematically impact on the safety climate of construction projects. These impacts are empirically tested by survey data collected from 186 questionnaires of construction companies operating in Shanghai, China. The results, obtained by partial least squares analysis, show that organizational management commitment to safety and employee involvement is positively related to all three institutional pressures, while the perception of responsibility for safety and health is significantly influenced by coercive and mimetic pressure. However, coercive and normative pressures have no significant effect on the applicability of safety rules and work practices, revealing the importance of external organizational pressures in improving project safety climate from a systematic view. The findings also provide insights into the use of institutional forces to facilitate the improvement of safety climate in the construction industry. Copyright © 2015 Elsevier Ltd. All rights reserved.

  5. Role and position of Nuclear Power Plants Research Institute in nuclear power industry

    International Nuclear Information System (INIS)

    Metke, E.

    1984-01-01

    The Nuclear Power Plants Research Institute carries out applied and experimental research of the operating states of nuclear power plants, of new methods of surveillance and diagnosis of technical equipment, it prepares training of personnel, carries out tests, engineering and technical consultancy and the research of automated control systems. The main research programme of the Institute is the rationalization of raising the safety and operating reliability of WWER nuclear power plants. The Institute is also concerned with quality assurance of selected equipment of nuclear power plants and assembly works, with radioactive waste disposal and the decommissioning of nuclear power plants as well as with the preparation and implementation of the nuclear power plant start-up. The Research Institute is developing various types of equipment, such as equipment for the decontamination of the primary part of the steam generator, a continuous analyzer of chloride levels in water, a gas monitoring instrument, etc. The prospects are listed of the Research Institute and its cooperation with other CMEA member countries. (M.D.)

  6. Institutional ethical review and ethnographic research involving injection drug users: a case study.

    Science.gov (United States)

    Small, Will; Maher, Lisa; Kerr, Thomas

    2014-03-01

    Ethnographic research among people who inject drugs (PWID) involves complex ethical issues. While ethical review frameworks have been critiqued by social scientists, there is a lack of social science research examining institutional ethical review processes, particularly in relation to ethnographic work. This case study describes the institutional ethical review of an ethnographic research project using observational fieldwork and in-depth interviews to examine injection drug use. The review process and the salient concerns of the review committee are recounted, and the investigators' responses to the committee's concerns and requests are described to illustrate how key issues were resolved. The review committee expressed concerns regarding researcher safety when conducting fieldwork, and the investigators were asked to liaise with the police regarding the proposed research. An ongoing dialogue with the institutional review committee regarding researcher safety and autonomy from police involvement, as well as formal consultation with a local drug user group and solicitation of opinions from external experts, helped to resolve these issues. This case study suggests that ethical review processes can be particularly challenging for ethnographic projects focused on illegal behaviours, and that while some challenges could be mediated by modifying existing ethical review procedures, there is a need for legislation that provides legal protection of research data and participant confidentiality. Copyright © 2013 Elsevier Ltd. All rights reserved.

  7. Intermodal safety research needs report of the sixth workshop on national transportation problems

    Energy Technology Data Exchange (ETDEWEB)

    Warshawer, A.J. (ed.)

    1976-04-01

    This conference brought together DOT policymakers, university principal investigators and other professionals to consider the intermodal safety research requirements of the Department of Transportation. The objectives of the conference were: (1) to highlight safety problems and needed transportation safety research identified by DOT modal safety managers and to stimulate university or university/industry teams to respond with research proposals which emphasize multi-modal applicability and a system view; and (2) to provide a forum for university research groups to inform DOT safety managers of promising new directions in transportation safety research and new tools with which to address safety related problems. The conference addressed the research requirements for safety as identified by the Statement of National Transportation Policy and by the modal safety managers in three principal contexts, each a workshop panel: I, Inter-Institutional Problems of Transportation Safety. Problems were described as: Federal-State, local; Federal-Industry; Federal-Public, Consumer groups. II, Goal Setting and Planning for Transportation Safety Programs. Issues were: modifying risk behavior, safety as a social value, and involving citizens in development of standards as a way of increasing probability of achieving program objectives. III, DOT Information, Management, and Evaluation Systems Requirements. Needs were: data requirements and analytic tools for management of safety programs.

  8. Safety and regulatory researches on the SMART reactor

    International Nuclear Information System (INIS)

    Seul, Kwang Won; Kim, Wee Kyong; Chang, Moo Hee

    2000-01-01

    The 330 MW thermal power of integral pressurized water reactor, named SMART (System integrated Modular Advanced ReacTor), is under development at the Korea Atomic Energy Research Institute (KAERI) for seawater desalination application and electricity generation. The plant is expected to install near the population zone. Thus, the public around the plant should be in depth protected from the possible release of radioactive materials, and also the fresh water should be prevented from radioactivity contamination. Currently, in parallel with the design development, the regulatory research is being conducted to identify and resolve the safety concerns of the nuclear desalination plant. Until now, some general items to be considered in the safety aspects have been identified for the conceptual design of SMART. They include the use of proven technology, application of strengthening defense-in-depth, event categorization and selection, effects of desalination plant, and maintainability of major components. These cooperative researches with regulatory body in the design stage are expected to provide an opportunity to early resolve the safety concerns and eventually the licensing stability of the SMART design. (author)

  9. Safety research activities on radioactive waste management in JNES

    International Nuclear Information System (INIS)

    Otsuka, Ichiro; Aoki, Hiroomi; Suko, Takeshi; Onishi, Yuko; Masuda, Yusuke; Kato, Masami

    2010-01-01

    Research activities in safety regulation of radioactive waste management are presented. Major activities are as follows. As for the geological disposal, major research areas are, developing 'safety indicators' to judge the adequacy of site investigation results presented by an implementer (NUMO), compiling basic requirements of safety design and safety assessment needed to make a safety review of the license application and developing an independent safety assessment methodology. In proceeding research, JNES, Japan Atomic Energy Agency (JAEA) and the National Institute of Advanced Industrial Science and Technology (AIST) signed an agreement of cooperative study on geological disposal in 2007. One of the ongoing joint studies under this agreement has been aimed at investigating regional-scale hydrogeological modeling using JAEA's Horonobe Underground Research Center. In the intermediate depth disposal, JNES conducted example analysis of reference facility and submitted the result to Nuclear Safety Commission of Japan (NSC). JNES is also listing issues to be addressed in the safety review of the license application and tries to make criteria of the review. Furthermore, JNES is developing analysis tool to evaluate long term safety of the facility and conducting an experiment to investigate long term behavior of engineered barrier system. In the near surface disposal of waste package, it must be confirmed by a regulatory inspector whether each package meets safety requirements. JNES continuously updates the confirmation methodology depending on new processing technologies. The clearance system was established in 2005. Two stages of regulatory involvement were adapted, 1) approval for measurement and judgment methods developed by the nuclear operator and 2) confirmation of measurement and judgment results based on approved methods. JNES is developing verification methodology for each stage. As for decommissioning, based on the regulatory needs and a research program

  10. Stakeholder Safety in Information Systems Research

    Directory of Open Access Journals (Sweden)

    R.H. Barbour

    2006-11-01

    Full Text Available Information Communication Technology (ICT researchers adapt and use tools from reference and cognate disciplines. This application of existing tools outside the context of their development has implications beyond the immediate problem context. ICT researchers have access to a wide variety of data sources including newer ones, such as the Internet, that may bring unexpected outcomes. ICT research can impact on researchers, their institutions and the researched in unexpected ways. People so affected are the stakeholders in ICT research activities. Reputations, welfare and property may be put at risk by unplanned events described in this paper. Legal aspects of ICT research are broadly identified and linked to the tort of negligence. The Social Research Association’s Code for researcher safety is described and its application extended to include the Internet as a potential data source. A common set of underlying ethical principles is identified suggesting that the ICT researcher can refine particular research protocols for specific social contexts.

  11. China's approach to nuclear safety — From the perspective of policy and institutional system

    International Nuclear Information System (INIS)

    Mu, Ruimin; Zuo, Jian; Yuan, Xueliang

    2015-01-01

    Nuclear energy plays an important role in the energy sector in the world. It has achieved a rapid development during the past six decades and contributes to over 11% of the world's electricity supply. On the other side, nuclear accidents have triggered substantial debates with a growing public concern on nuclear facilities. Followed by the Fukushima nuclear accident, some developed countries decided to shut down the existing nuclear power plants or to abandon plans to build new ones. Given this background, accelerating the development of nuclear power on the basis of safety in China will make it a bellwether for other countries. China assigns the top priority to the nuclear safety in nuclear energy development and has maintained a good record in this field. The policy and institutional system provide the necessary guarantee for the nuclear energy development and safety management. Furthermore, China's approach to nuclear safety provides a benchmark for the safe development and utilization of nuclear power. This research draws an overall picture of the nuclear energy development and nuclear safety in China from the policy and institutional perspective. - Highlights: • China's Approach to Nuclear Safety. • Policy and Institutional System for Nuclear Energy Development. • A Benchmark for the Peaceful and Safe Utilization of Nuclear Power. • Further Efforts for Specific Laws and Administrative System

  12. Fifteen year's research activities of the INSS Institute of Nuclear Technology and future policy

    International Nuclear Information System (INIS)

    Kimura, Itsuro

    2008-01-01

    Fifteen years have passed since the Institute of Nuclear Safety System, Incorporated (INSS) was founded. This paper reviews the research activities of the Institute of Nuclear Technology in INSS over that time and proposes a policy for future research. First, a chronological table shows the major milestones over the past fifteen years. Notable events include the following. The head office was moved to Mihama-cho where laboratories and experimental facilities were installed; the Institute signed an agreement with the Kansai Electric Power Co., Inc. (KEPCO) on assistance for the preparedness of nuclear emergency; it assisted KEPCO to investigate the causes of the accident at its Mihama Nuclear Power Station Unit 3 and subsequently established the Nuclear Power Plant Aging Research Center, it began providing information on adverse events occurred at nuclear power plants in the world to Japanese electric utilities that own PWRs; it supported the Energy Research and Development Centralization Plan of Fukui Prefecture, and it embarked on a project to develop the Fukui regional cluster in the Fukui and Kinki area under the government's program for aging management of nuclear power plants. The fifteen years of research activities are shown for each research group and for each research project, and then important achievements of the major research projects are described. Finally, the status of research papers published in external Journals and in INSS over the past fifteen years is illustrated and the number of patents acquired during this period is presented. We evaluated our research activities over the fifteen years and reviewed them according to seven items under a future research policy. The plans include the enhancement of system engineering-based research efforts as the name of this Institute implies, and committing ourselves to forward-looking and creative research program focusing on not only from analysis', but also on 'synthesis'. A suitable approach to safety

  13. Learning from Fukushima: Institutional Isomorphism as Constraining and Contributing Nuclear Safety

    International Nuclear Information System (INIS)

    Ylönen, M.

    2016-01-01

    This paper is an analysis of the international institutional isomorphic pressures and lessons learned from the Fukushima accident. The recent upgrading of nuclear safety requirements at the international and national level, as well as harmonisation attempts of nuclear reactor safety by the Western European Nuclear Regulators’ Association (WENRA), show serious efforts to improve nuclear safety and implement lessons learned from the Fukushima accident. After Fukushima new requirements for the new nuclear power plants were set, such as preparedness for natural hazards, multiple failure and core melt situations. In addition, improvement of safety culture was emphasised, as well as strengthening of independence of the regulatory body from external pressures, and increasing of independence between different levels of defence in depth safety. However, learning from accidents is often affected by institutional factors, which may both contribute and hamper safety and learning.

  14. Annual report 2012. Institute of Resource Ecology

    Energy Technology Data Exchange (ETDEWEB)

    Brendler, Vinzenz (ed.)

    2013-09-01

    The Institute of Resource Ecology (IRE) is one of the currently eight institutes of the Helmholtz-Zentrum Dresden-Rossendorf (HZDR). The research activities are fully integrated into the program ''Nuclear Safety Research'' of the Helmholtz Association and focused on the topics ''Safety of Nuclear Waste Disposal'' and ''Safety Research for Nuclear Reactors''. With the integration of the division of ''Reactor Safety'' from the former ''Institute of Safety Research'' nuclear research at HZDR is now mainly concentrated within this institute. In addition, various activities have been started investigating chemical and environmental aspects of processing and recycling of strategic metals, namely rare earth elements. Here, a knowledge transfer from the nuclear to the non-nuclear community, branching thermodynamics and spectroscopy, has been established. This also strengthens links to the recently established ''Helmholtz-Institute Freiberg for Resource Technology''.

  15. Nuclear safety research collaborations between the U.S. and Russian Federation International Nuclear Safety Centers

    International Nuclear Information System (INIS)

    Hill, D. J.; Braun, J. C.; Klickman, A. E.; Bougaenko, S. E.; Kabonov, L. P.; Kraev, A. G.

    2000-01-01

    The Russian Federation Ministry for Atomic Energy (MINATOM) and the US Department of Energy (USDOE) have formed International Nuclear Safety Centers to collaborate on nuclear safety research. USDOE established the US Center (ISINSC) at Argonne National Laboratory (ANL) in October 1995. MINATOM established the Russian Center (RINSC) at the Research and Development Institute of Power Engineering (RDIPE) in Moscow in July 1996. In April 1998 the Russian center became a semi-independent, autonomous organization under MINATOM. The goals of the center are to: Cooperate in the development of technologies associated with nuclear safety in nuclear power engineering; Be international centers for the collection of information important for safety and technical improvements in nuclear power engineering; and Maintain a base for fundamental knowledge needed to design nuclear reactors. The strategic approach is being used to accomplish these goals is for the two centers to work together to use the resources and the talents of the scientists associated with the US Center and the Russian Center to do collaborative research to improve the safety of Russian-designed nuclear reactors. The two centers started conducting joint research and development projects in January 1997. Since that time the following ten joint projects have been initiated: INSC databases--web server and computing center; Coupled codes--Neutronic and thermal-hydraulic; Severe accident management for Soviet-designed reactors; Transient management and advanced control; Survey of relevant nuclear safety research facilities in the Russian Federation; Computer code validation for transient analysis of VVER and RBMK reactors; Advanced structural analysis; Development of a nuclear safety research and development plan for MINATOM; Properties and applications of heavy liquid metal coolants; and Material properties measurement and assessment. Currently, there is activity in eight of these projects. Details on each of these

  16. Fuel safety research 2000

    Energy Technology Data Exchange (ETDEWEB)

    Uetsuka, Hiroshi (ed.) [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    2001-03-01

    In April 1999, the Fuel Safety Research Laboratory was newly established as a part of reorganization of the Nuclear Safety Research Center, JAERI. The new laboratory was organized by combining three pre-existing laboratories, Reactivity Accident Laboratory, Fuel Reliability Laboratory, and a part of Severe Accident Research Laboratory. The Fuel Safety Research Laboratory becomes to be in charge of all fuel safety research in JAERI. Various experimental and analytical researches are conducted in the laboratory by using the unique facilities such as the Nuclear Safety Research Reactor (NSRR), the Japan Material Testing Reactor (JMTR), the Japan Research Reactor 3 (JRR-3) and hot cells in JAERI. The laboratory consists of following five research groups corresponding to each research fields; (a) Research group of fuel behavior under the reactivity initiated accident conditions (RIA group). (b) Research group of fuel behavior under the loss-of-coolant accident conditions (LOCA group). (c) Research group of fuel behavior under the normal operation conditions (JMTR/BOCA group). (d) Research group of fuel behavior analysis (FEMAXI group). (e) Research group of FP release/transport behavior from irradiated fuel (VEGA group). The research activities in year 2000 produced many important data and information. They are, for example, failure of high burnup BWR fuel rod under RIA conditions, data on the behavior of hydrided Zircaloy cladding under LOCA conditions and FP release data from VEGA experiments at very high temperature/pressure condition. This report summarizes the outline of research activities and major outcomes of the research executed in 2000 in the Fuel Safety Research Laboratory. (author)

  17. 78 FR 64504 - Safety and Occupational Health Study Section (SOHSS), National Institute for Occupational Safety...

    Science.gov (United States)

    2013-10-29

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES Centers for Disease Control and Prevention Safety and Occupational Health Study Section (SOHSS), National Institute for Occupational Safety and Health (NIOSH or..., Number 177, Pages 56235-56236. Contact Person for More Information: Price Connor, Ph.D., NIOSH Health...

  18. Status and prospects of safety research about fuel cycle facilities in France

    International Nuclear Information System (INIS)

    Auchere, H.; Mercier, J.P.

    1996-01-01

    Although there is a good knowledge of the risks and no major accident occurred in France, as in other OECD countries, it remains useful to complete basic knowledge and to allow the quality of fuel cycle plants safety assessments to be improved further, particularly in countries equipped with a 'complete' nuclear fuel cycle (France, Japan and U.K.). The scope of the current and future IPSN ('Institut de Protection et de Surete Nucleaire': institute for protection and nuclear safety) research deals with the whole fuel cycle. The overview presented here in NUCEF'95 symposium contains a number of specific themes, some of which have already been started. Successful conclusion of the safety researches will allow the IPSN to have a more precise understanding about specific phenomena and notably to replace 'engineer judgements', though they may be based on a lot of experience and competence, by more scientifically established basic data. (J.P.N.)

  19. Safety of Research Reactors. Specific Safety Requirements (French Edition)

    International Nuclear Information System (INIS)

    2017-01-01

    This Safety Requirements publication establishes requirements for all main areas of safety for research reactors, with particular emphasis on requirements for design and operation. It explains the safety objectives and concepts that form the basis for safety and safety assessment for all stages in the lifetime of a research reactor. Technical and administrative requirements for the safety of new research reactors are established in accordance with these objectives and concepts, and they are to be applied to the extent practicable for existing research reactors. The safety requirements established in this publication for the management of safety and regulatory supervision apply to site evaluation, design, manufacturing, construction, commissioning, operation (including utilization and modification), and planning for decommissioning of research reactors (including critical assemblies and subcritical assemblies). The publication is intended for use by regulatory bodies and other organizations with responsibilities in these areas and in safety analysis, verification and review, and the provision of technical support.

  20. Remodeling Strategic Staff Safety and Security Risks Management in Nigerian Tertiary Institutions

    Directory of Open Access Journals (Sweden)

    Sunday S. AKPAN

    2015-10-01

    Full Text Available This paper examined safety and security risk management in tertiary institutions in Nigeria. The frequent attacks at workplace, especially schools, have placed safety and security in the front burner of discussion in both business and political circles. This therefore, forms the imperative for the conduct of this study. The work adopted a cross sectional survey research design and collected data from respondents who are security personnel of the University of Uyo. Analysis of data was done with simple percentage statistics while the research hypotheses were tested with mean and simple regression and correlation statistics. The findings of the study revealed that assassination, kidnappings and bombings were principal risk incidents threatening the safety and security of staff in University of Uyo. A significant positive relationship was found between the funding of security management and workers’ performance. It was discovered specifically that employment screening, regular training of security personnel, regular safety and security meetings and strategic security policy formation were the main strategies for managing safety and security in University of Uyo. The paper concluded that safety and security management and control involves every worker (management and staff of University of Uyo. It was recommended, among others, that management should be more committed to safety and security management in the University by means of making safety and security issues an integral part of University’s strategic plan and also by adopting the management line model – one form of management structure-where safety and security are located, with other general management responsibilities. This way, the resurgent cases of kidnapping, hired assassination, etc. would be reduced if not completely eradicated in the University.

  1. Karlsruhe Research Center, Nuclear Safety Research Project (PSF). Annual report 1994; Forschungszentrum Karlsruhe, Projekt Nukleare Sicherheitsforschung. Jahrsbericht 1994

    Energy Technology Data Exchange (ETDEWEB)

    Hueper, R. [ed.

    1995-08-01

    The reactor safety R and D work of the Karlsruhe Research Centre (FZKA) has been part of the Nuclear Safety Research Projet (PSF) since 1990. The present annual report 1994 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 1995. An abstract in English precedes each of them, whenever the respective article is written in German. (orig.) [Deutsch] Seit Beginn 1990 sind die F+E-Arbeiten des Forschungszentrum Karlsruhe (FZKA) zur Reaktorsicherheit im Projekt Nukleare Sicherheitsforschung (PSF) zusammengefasst. Der vorliegende Jahresbericht 1994 enthaelt Beitraege zu aktuellen Fragen der Sicherheit von Leichtwasserreaktoren und innovativen Systemen sowie der Umwandlung von minoren Aktiniden. Die konkreten Forschungsthemen und -vorhaben werden mit internen und externen Fachgremien laufend abgestimmt. An den beschriebenen Arbeiten sind die folgenden Institute und Abteilungen des FZKA beteiligt: Institut fuer Materialforschung IMF I, II, III; Institut fuer Neutronenphysik und Reaktortechnik INR; Institut fuer Angewandte Thermo- und Fluiddynamik IATF; Institut fuer Reaktorsicherheit IRS; Hauptabteilung Ingenieurtechnik HIT; Hauptabteilung Versuchstechnik HVT sowie vom KfK beauftragte externe Institutionen. Die einzelnen Beitraege stellen den Stand der Arbeiten zum Fruehjahr 1995 dar und sind entsprechend dem F+E-Programm 1994 numeriert. Den in deutscher Sprache verfassten Beitraege sind Kurzfassungen in englischer Sprache vorangestellt. (orig.)

  2. Safety culture of complex risky systems: the Nuclear Engineering Institute case study

    International Nuclear Information System (INIS)

    Obadia, Isaac Jose; Vidal, Mario Cesar Rodriguez; Melo, Paulo Fernando F. Frutuoso e

    2002-01-01

    Analysis of industrial accidents have demonstrated that safe and reliable operation of complex industrial processes that use risky technology and/or hazard material depends not only on technical factors but on human and organizational factors as well. After the Chernobyl nuclear accident in 1986, the International Atomic Energy Agency established the safety culture concept and started a safety culture enhancement program within nuclear organizations worldwide. The Nuclear Engineering Institute, IEN, is a research and technological development unit of the Brazilian Nuclear Energy Commission, CNEN, characterized as a nuclear and radioactive installation where processes presenting risks to operators and to the environment are executed. In 1999, IEN started a management change program, aiming to achieve excellence of performance, based on the Model of Excellence of the National Quality Award. IEN's safety culture project is based on IAEA methodology and has been incorporated to the organizational management process. This work presents IEN's safety culture project; the results obtained on the initial safety culture assessment and the following project actions. (author)

  3. Harish-Chandra Research Institute, Allahabad

    Indian Academy of Sciences (India)

    The Harish-Chandra Research Institute (known as the Mehta Research Institute of Math- ematics and Mathematical Physics until October 2000) came into existence in 1975, with a donation of some land and Rs. 40 lakhs from the B S Mehta Trust in Calcutta. With the aim of converting it into a top-class research Institute in ...

  4. Research program on nuclear technology and nuclear safety

    International Nuclear Information System (INIS)

    Dreier, J.

    2010-04-01

    This paper elaborated for the Swiss Federal Office of Energy (SFOE) presents the synthesis report for 2009 made by the SFOE's program leader on the research program concerning nuclear technology and nuclear safety. Work carried out, knowledge gained and results obtained in the various areas are reported on. These include projects carried out in the Laboratory for Reactor Physics and System Behaviour LRS, the LTH Thermohydraulics Laboratory, the Laboratory for Nuclear Materials LNM, the Laboratory for Final Storage Safety LES and the Laboratory for Energy Systems Analysis LEA of the Paul Scherrer Institute PSI. Work done in 2009 and results obtained are reported on, including research on transients in Swiss reactors, risk and human reliability. Work on the 'Proteus' research reactor is reported on, as is work done on component safety. International co-operation in the area of serious accidents and the disposal of nuclear wastes is reported on. Future concepts for reactors and plant life management are discussed. The energy business in general is also discussed. Finally, national and international co-operation is noted and work to be done in 2010 is reviewed

  5. VVER operational safety improvements: lessons learnt from European co-operation and future research needs

    International Nuclear Information System (INIS)

    Pazdera, F.; Vasa, I.; Zd'arek, J.

    2003-01-01

    The paper summarises involvement of Nuclear Research Institute Rez (NRI) in the areas which are directly related to Reactor Operational Safety and Plant Life Management, it also gives an idea how results of the research projects can be used to enhance safety of VVER reactors. These issues are for many years subject of a wide international co-operation effort, covered by such programmes as PHARE, OECD/NEA TACIS, 5th Framework Programme. Nuclear Research Institute participated in the majority of these programmes and projects, which allowed us to evaluate benefits (especially for VVER reactors) of the projects already finalised or running, as well as to formulate so-called 'future research needs', which possibly may be pursued within 6th Framework Programme. The paper highlights the main features of some projects our Institute was and is involved in, emphasising the most important results, expectations and future needs. It also very briefly, deals with some general and particular lessons learnt within these projects and their application to VVER reactors, especially as to their safety improvement. The paper also mentions VVER-focused projects and activities, co-ordinated by the OECD, which should enable to extend multilateral contacts already existing between organisations of the EU countries to include organisations from Russia, USA, Japan and possibly some other countries

  6. Complementary Safety Assessments for Research Reactors for the French Nuclear Safety Authority

    International Nuclear Information System (INIS)

    Kassiotis, Christophe; Rigaud, Antoine; Evrard, Lydie

    2013-01-01

    The 'Autorite de surete nucleaire' (ASN) requested licensees to undertake stress tests, called complementary safety assessments (CSA), of their installations on May 5th 2011, following the accident that occurred in Japan on March 11th 2011. Their mission consisted in providing feedback on the consequences of potential extreme events. In this process, all the French facilities were divided into three categories of decreasing priority, depending on two main factors: on the one hand, their vulnerability to the various phenomena that led to the Fukushima accident, and on the other hand, the amount of radioactive elements that would be dispersed in the event of a failure of the safety functions. On the 79 high-priority facilities, only five of them are research or experimental reactors (including two currently shutdown or in decommissioning) and their operators (the 'Comissariat a l'energie atomique et aux energies alternatives' (CEA) and the 'Institut Laue Langevin') submitted their reports to the ASN on September 15 th 2011. Concerning the lower-priority facilities, including three other facilities (two research reactors operated by the CEA and a facility operated by ITER Organization) the deadline was September 15 th 2012. Finally, the remaining facilities were not asked to submit a report yet, but they will have to do it later, mainly on the occasion of their next periodic safety review. The analyses of the cliff-edge effects, that may occur in extreme situations (exceptional scale event, combination of several disasters...), led to the definition of a hardened safety core concept by the 'Institut de radioprotection et de surete nucleaire' (IRSN). This hardened safety core of structures, equipment and organizational measures must ensure the ultimate protection of the concerned facilities in extreme situations : it is designed to prevent severe accidents (or curb their progression), limit large scale releases for extreme accidents, and enables the operating teams to

  7. Annual report of the Japan Atomic Energy Research Institute for fiscal 2003

    International Nuclear Information System (INIS)

    2004-01-01

    The Japan Atomic Energy Research Institute (JAERI) is comprehensively promoting the research and development (R and D) activities to make the best use of variety of potentials of atomic energy. In the field of nuclear energy, researches on advanced nuclear engineering systems, high-temperature engineering experimentation and nuclear fusion are forwarded to realize long-range stable supply of energy. Researches on safety of nuclear facilities, nuclear fuel cycles, radioactive waste processing/management and environmental radioactivities have been conducted in the safety category according to 'Annual Plan for Safety Research'. And researches on health physics have been implemented to establish the fundamentals of scientific and rational radiation protection. As a diversification of nuclear science and technology, various radiation application activities such as neutron science, advanced photon science and synchrotron radiation science and application research of charged particles and radioisotopes have been promoted, which contribute to drastic advance in the fields of materials and life science etc. and to establishment of new industries. Along with these activities, basic and fundamental researches including advanced basic research, materials science research, nuclear environmental science research and advanced computational science and engineering are in progress. In addition, operation management of JMTR, JRR-3 and JRR-4 were performed. And JAERI also implemented safety management and research information management activities etc. in the peaceful use of nuclear energy. The research activities for FY 2003 are reviewed in this issue. (J.P.N.)

  8. Pilot research on a pupil’s psychological safety in the multicultural educational environment

    Directory of Open Access Journals (Sweden)

    Kulikova, Tatyana I.

    2016-09-01

    Full Text Available In the modern world, the environment of any educational institution represents a spectrum of ethnic groups and subcultures: a multicultural educational environment. Pupils who are aware of their national identity often demonstrate intolerance toward students of other nationalities, which threatens pupils’ psychological safety. In this article, we present the results of pilot research examining the level of a pupil’s psychological safety in the multicultural educational environment and identifying the criteria that influence a pupil’s psychological safety. The research sample comprised 127 pupils aged 13–14 years from different schools living in various places that differed by the type of settlement, industrial development and level of science and culture. We isolated the following criteria for a pupil’s psychological safety in the multicultural educational environment: satisfaction with the educational environment, protection from psychological abuse and self-confidence. According to pupils, the essential characteristics of safety in the educational environment, regardless of school category and type, are being able to ask for help, protection of personal dignity, interactions with other students, and self-respect. Empirical data reveal the current status of the psychological safety of the entire sample group (n = 127 and compare indices of psychological safety in the educational institutions under study. Analysis of the results of our research indicates that protecting a pupil’s personality in the multicultural educational environment has the greatest influence on his/her psychological safety. In addition, a comfortable psychological atmosphere, mutual aid and support of pupils and low levels of classmates’ and coevals’ aggression positively influence the protection experience.

  9. Results of research and development activities in 1989 of the Institute for Neutron Physics and Reactor Technology

    International Nuclear Information System (INIS)

    1990-03-01

    The Institute for Neutron Physics and Reactor Technology treats research problems of nuclear engineering, mainly those that are related to the development of sodium-cooled fast breeder reactors and fusion reactor technology. The activities are in approximately equal parts of an experimental and theoretical nature. A great part of the research activities is performed in co-operation with other institutes and industrial groups in the framework of projects. For the Fast Breeder Reactor Project the Institute works on reactor physical design and safety problems by the core of large-scale fast breeder reactors. Questions concerning the consequences of accidents in light water reactors upon the environment and the population are treated as part of the Nuclear Safety Project. The Institute contributes to the Reprocessing Project with theoretical investigations on the physics of the fuel cycle and by developing control devices for a reprocessing plant. In the framework of the Fusion Project the Institute is concerned with neutron physical and technological questions of the breeder blanket. (orig.) [de

  10. HSE Nuclear Safety Research Program

    Energy Technology Data Exchange (ETDEWEB)

    Bagley, M.J. [Health and Safety Executive, Sheffield (United Kingdom)

    1995-12-31

    HSE funds two programmes of nuclear safety research: a programme of {approx} 2.2M of extramural research to support the Nuclear Safety Division`s regulatory activities and a programme of {approx} 11M of generic safety research managed by the Nuclear Safety Research Management Unit (NSRMU) in Sheffield, UK. This paper is concerned only with the latter programme; it describes how it is planned and procured and outlines some of the work on structural integrity problems. It also describes the changes that are taking place in the way nuclear safety research is procured in the UK. (author).

  11. HSE Nuclear Safety Research Program

    International Nuclear Information System (INIS)

    Bagley, M.J.

    1995-01-01

    HSE funds two programmes of nuclear safety research: a programme of ∼ 2.2M of extramural research to support the Nuclear Safety Division's regulatory activities and a programme of ∼ 11M of generic safety research managed by the Nuclear Safety Research Management Unit (NSRMU) in Sheffield, UK. This paper is concerned only with the latter programme; it describes how it is planned and procured and outlines some of the work on structural integrity problems. It also describes the changes that are taking place in the way nuclear safety research is procured in the UK. (author)

  12. KfK, Institute for Reactor Development. Results of research and development activities in 1990

    International Nuclear Information System (INIS)

    1991-03-01

    R and D activities at IRE (Institut fuer Reaktorentwicklung-Institute for Reactor Development) are dedicated to power engineering and handling processes in the framework of the point-of-main-effort projects 'nuclear fusion', 'solid-state and materials research', 'handling', 'nuclear safety' and 'miscellaneous research'. Nuclear fusion contributions deal with special vacuum system design problems, heavy-duty design and materials selection and safety aspects. Specimens from 30 different carbon-based materials were subjected to comparative tests in a plasma spraying plant. In the framework of solid-state and materials research activities a viscoplastic model for mechanical component analysis was investigated for its compatibility with elementary physical laws under complex loads. The handling project was dedicated to the specific requirements of nuclear fusion with regard to JET and NET uses, the development of system solutions for flexible industrial techniques, and to standardization. A study on the control system of a work station for NET remote handling tasks was completed. In the framework of the nuclear safety project one currently investigates the dynamics of fast reactors under failure conditions, the possible propagation of local cooling failures in the reactor core, and core monitoring problems. (orig./GL) [de

  13. Annual safety research report, JFY 2010

    International Nuclear Information System (INIS)

    2011-09-01

    In the safety infrastructure research working group report, 'the effective conducting of nuclear safety infrastructure research', published by METI in March 2010, the roles of regulatory agencies and JNES and their cooperation, and the research road map for nuclear safety regulation researches were summarized. As for the regulatory issues the governments or JNES considered necessary, JNES had compiled' safety research plan' in respective research areas necessary for solving the regulatory issues (safety research needs) and was conducting safety research to obtain the results, etc. Safety research areas, subjects and research projects were as follows: design review of nuclear power plant (4 subjects and each subject having several research projects totaled 19), control management of nuclear power plant (3 subjects and each subject having several research projects totaled 11), nuclear fuel cycle (2 subjects and each subject having several research projects totaled 5), nuclear fuel cycle backend (2 subjects and each subject having several research projects totaled 6), nuclear emergency preparedness and response (3 subjects and each subject having several research projects totaled 5) and bases of nuclear safety technology (3 subjects and each subject having several research projects totaled 7). In JFY 2010, JNES worked on the 53 research projects of 17 subjects in 6 areas as safety researches. This annual safety research report summarized respective achievements and stage of regulatory tools necessary for solving regulatory issues according to the safety research plan, JFY 2010 Edition as well as the situation of the reflection for the safety regulations. (T. Tanaka)

  14. Materials of the Annual Scientific Conference of the Institute for Nuclear Research

    International Nuclear Information System (INIS)

    Vishnevs'kij, Yi.M.

    1998-01-01

    The Proceedings contain reports which were presented at current Annual scientific conference of the Institute for Nuclear Research, National Academy of Sciences (Kiev, January 27-30, 1998). The articles are presented in the sections which corresponds to the main scientific directions of the Institute activity: Nuclear Physics, Nuclear Reactor Safety, Radiation physics, Plasma Physics, Radioecology and Radiobiology. Each Proceedings Sections contain the following sequence of the works: theoretical, experimental, applied and methodological. The Proceeding are printed by means of direct reproduction

  15. Fuel safety research 2001

    Energy Technology Data Exchange (ETDEWEB)

    Uetsuka, Hiroshi (ed.) [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    2002-11-01

    The Fuel Safety Research Laboratory is in charge of research activity which covers almost research items related to fuel safety of water reactor in JAERI. Various types of experimental and analytical researches are being conducted by using some unique facilities such as the Nuclear Safety Research Reactor (NSRR), the Japan Material Testing Reactor (JMTR), the Japan Research Reactor 3 (JRR-3) and the Reactor Fuel Examination Facility (RFEF) of JAERI. The research to confirm the safety of high burn-up fuel and MOX fuel under accident conditions is the most important item among them. The laboratory consists of following five research groups corresponding to each research fields; Research group of fuel behavior under the reactivity initiated accident conditions (RIA group). Research group of fuel behavior under the loss-of-coolant accident conditions (LOCA group). Research group of fuel behavior under the normal operation conditions (JMTR/BOCA group). Research group of fuel behavior analysis (FEMAXI group). Research group of radionuclides release and transport behavior from irradiated fuel under severe accident conditions (VEGA group). The research conducted in the year 2001 produced many important data and information. They are, for example, the fuel behavior data under BWR power oscillation conditions in the NSRR, the data on failure-bearing capability of hydrided cladding under LOCA conditions and the FP release data at very high temperature in steam which simulate the reactor core condition during severe accidents. This report summarizes the outline of research activities and major outcomes of the research executed in 2001 in the Fuel Safety Research Laboratory. (author)

  16. Proceedings of JAERI-JNC joint conference on nuclear safety research. March 7, 2003, Tokyo

    International Nuclear Information System (INIS)

    Sugimoto, Jun; Anoda, Yoshinari; Araya, Fumimasa; Yamaguchi, Toshio

    2003-08-01

    The JAERI-JNC Joint Conference on Nuclear Safety Research was held on March 7, 2003 in Tokyo with 188 participants, ahead of planned unification of JAERI and JNC in 2005. The objectives of the conference are to present recent results of safety research conducted in both institutes in accordance with the Five-Year Safety Research Plan by the Nuclear Safety Commission (NSC), and to reflect suggestions from the participants for future research program. Prof. Matsubara, Vice Chairperson of NSC, first presented a special lecture entitled 'Expectation on Future Nuclear Safety Research in Japan'. Twelve papers were then presented on the overview of research results and those of individual research activities in the fields of nuclear facilities, radioactive waste and environmental radioactivity. In the final session, a panel discussion was conducted with a title of 'Expectation on Future Nuclear Safety Research' chaired by Prof. Kimura, Chairperson of Special Committee on Nuclear Safety Research under NSC. Through the presentations and discussions, consensus has almost been obtained among participants for several key issues on safety research to be conducted by a unified new organization, such as giving priority to safety research as one of major missions, assurance of independence of safety research with the governmental funds, assurance of transparency of the planning process of safety research, separation and harmonization between safety research and developmental research, importance of maintaining fundamental research and research facilities, promotion of cooperation with relevant organizations considering the needs from industries, and importance of dissemination of research results and personnel training. The present report compiles the summaries of special lecture, papers, questions and comments, panel discussions, and OHPs presented in the conference. (author)

  17. IAEA safety standards for research reactors

    International Nuclear Information System (INIS)

    Abou Yehia, H.

    2007-01-01

    The general structure of the IAEA Safety Standards and the process for their development and revision are briefly presented and discussed together with the progress achieved in the development of Safety Standards for research reactor. These documents provide the safety requirements and the key technical recommendations to achieve enhanced safety. They are intended for use by all organizations involved in safety of research reactors and developed in a way that allows them to be incorporated into national laws and regulations. The author reviews the safety standards for research reactors and details their specificities. There are 4 published safety standards: 1) Safety assessment of research reactors and preparation of the safety analysis report (35-G1), 2) Safety in the utilization and modification of research reactors (35-G2), 3) Commissioning of research reactors (NS-G-4.1), and 4) Maintenance, periodic testing and inspection of research reactors (NS-G-4.2). There 5 draft safety standards: 1) Operational limits and conditions and operating procedures for research reactors (DS261), 2) The operating organization and the recruitment, training and qualification of personnel for research reactors (DS325), 3) Radiation protection and radioactive waste management in the design and operation of research reactors (DS340), 4) Core management and fuel handling at research reactors (DS350), and 5) Grading the application of safety requirements for research reactors (DS351). There are 2 planned safety standards, one concerning the ageing management for research reactor and the second deals with the control and instrumentation of research reactors

  18. Results of research and development activities in 1983 of the Institut fuer Neutronenphysik und Reaktortechnik

    International Nuclear Information System (INIS)

    1984-02-01

    The Institute for Neutron Physics and Reactor Technology treats research problems of nuclear engineering mainly those that are related to the development of sodium-cooled fast breeder reactors and fusion reactor technology. The activities are in approximately equal parts of an experimental and theoretical nature. A great part of the research activities is performed in co-operation with other institutes and industrial groups in the framework of projects. For the Fast Breeder Reactor Project the Institute works on reactor physical design and safety problems by the core of large-scale fast breeder reactors. Questions concerning the consequences of accidents in lightwater reactors upon the environment and the population are treated as part of the Nuclear Safety project. The Institute contributes to the Reprocessing Project with theoretical investigations on the physics of the fuel cycle and by developing control devices for a reprocessing plant. In the framework of the Fusion Projekt the Institute is concerned with neutron physical and technological questions of the the breeder blanket. Independent institutional work concerns technical and physical questions on the interaction between light ion beams of a high energy density and substances. Apart from this, investigations are carried out on the application of nuclear energy in the field of traffic with hydrogen as energy carrier. (RW) [de

  19. 78 FR 78362 - National Institute for Occupational Safety and Health Personal; Notice of public meeting in...

    Science.gov (United States)

    2013-12-26

    ... Institute for Occupational Safety and Health Personal; Notice of public meeting in Endicott, New York AGENCY: The National Institute for Occupational Safety and Health (NIOSH) of the Centers for Disease Control.... SUMMARY: The National Institute for Occupational Safety and Health (NIOSH) of the Centers for Disease...

  20. Research program on regulatory safety research

    International Nuclear Information System (INIS)

    Mailaender, R.

    2010-02-01

    This paper elaborated for the Swiss Federal Office of Energy (SFOE) presents the synthesis report for 2009 made by the SFOE's program leader on the research program concerning regulatory nuclear safety research, as co-ordinated by the Swiss Nuclear Safety Inspectorate ENSI. Work carried out in various areas is reviewed, including that done on reactor safety, radiation protection and waste disposal as well as human aspects, organisation and safety culture. Work done concerning materials, pressure vessel integrity, transient analysis, the analysis of serious accidents in light-water reactors, fuel and material behaviour, melt cooling and concrete interaction is presented. OECD data bank topics are discussed. Transport and waste disposal research at the Mont Terri rock laboratory is looked at. Requirements placed on the personnel employed in nuclear power stations are examined and national and international co-operation is reviewed

  1. The first symposium of Research Center for Radiation Safety, NIRS. Perspective of future studies of radiation safety

    International Nuclear Information System (INIS)

    Shimo, Michikuni

    2002-03-01

    This paper summarizes presentations given in the title symposium, held at the Conference Room of National Institute of Radiological Sciences (NIRS) on November 29 and 30, 2001. Contained are Introductory remarks: Basic presentations concerning exposure dose in man; Environmental levels of radiation and radioactivity, environmental radon level and exposure dose, and radiation levels in the specific environment (like in the aircraft): Special lecture (biological effects given by space environment) concerning various needs for studies of radiation safety; Requirement for open investigations, from the view of utilization, research and development of atomic energy, from the clinical aspect, and from the epidemiological aspect: Special lecture (safety in utilization of atomic energy and radiation-Activities of Nuclear Safety Commission of Japan) concerning present state and perspective of studies of radiation safety; Safety of radiation and studies of biological effects of radiation-perspective, and radiation protection and radiation safety studies: Studies in the Research Center for Radiation Safety; Summary of studies in the center, studies of the biological effects of neutron beam, carcinogenesis by radiation and living environmental factors-complicated effects, and studies of hereditary effects: Panel discussion (future direction of studies of radiation safety for the purpose of the center's direction): and concluding remarks. (N.I.)

  2. Safety analysis for research reactors

    International Nuclear Information System (INIS)

    2008-01-01

    The aim of safety analysis for research reactors is to establish and confirm the design basis for items important to safety using appropriate analytical tools. The design, manufacture, construction and commissioning should be integrated with the safety analysis to ensure that the design intent has been incorporated into the as-built reactor. Safety analysis assesses the performance of the reactor against a broad range of operating conditions, postulated initiating events and other circumstances, in order to obtain a complete understanding of how the reactor is expected to perform in these situations. Safety analysis demonstrates that the reactor can be kept within the safety operating regimes established by the designer and approved by the regulatory body. This analysis can also be used as appropriate in the development of operating procedures, periodic testing and inspection programmes, proposals for modifications and experiments and emergency planning. The IAEA Safety Requirements publication on the Safety of Research Reactors states that the scope of safety analysis is required to include analysis of event sequences and evaluation of the consequences of the postulated initiating events and comparison of the results of the analysis with radiological acceptance criteria and design limits. This Safety Report elaborates on the requirements established in IAEA Safety Standards Series No. NS-R-4 on the Safety of Research Reactors, and the guidance given in IAEA Safety Series No. 35-G1, Safety Assessment of Research Reactors and Preparation of the Safety Analysis Report, providing detailed discussion and examples of related topics. Guidance is given in this report for carrying out safety analyses of research reactors, based on current international good practices. The report covers all the various steps required for a safety analysis; that is, selection of initiating events and acceptance criteria, rules and conventions, types of safety analysis, selection of

  3. Analysis of conditions to safety and radiological protection of Brazilian research particle accelerators facilities

    International Nuclear Information System (INIS)

    Lourenco, Manuel Jacinto Martins

    2010-01-01

    Eleven institutions of education and research in Brazil use particle accelerators, which fulfill different functions and activities. Currently, these institutions employ a total of fifteen accelerators. In this paper, the object of study is the radiological protection of occupationally exposed individuals, the general public and the radiation safety of particle accelerators. Research facilities with accelerators are classified in categories I and II according to the International Atomic Energy Agency or groups IX and X in accordance with the Brazilian National Commission of Nuclear Energy. Of the 15 accelerators in use for research in Brazil, four belong to category I or group X and eleven belong to category II or group IX. The methodology presented and developed in this work was made through the inspection and assessment of safety and radiological protection of thirteen particle accelerators facilities, and its main purpose was to promote safer use of this practice by following established guidelines for safety and radiological protection. The results presented in this work showed the need to create a program, in our country, for the control of safety and radiological protection of this ionizing radiation practice. (author)

  4. Progress of nuclear safety research. 2001

    Energy Technology Data Exchange (ETDEWEB)

    Anoda, Yoshinari; Sasajima, Hideo; Nishiyama, Yutaka (eds.) [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment] [and others

    2001-10-01

    JAERI is conducting nuclear safety research primarily at the Nuclear Safety Research Center in close cooperation with the related departments in accordance with the Long Term Plan for Development and Utilization of Nuclear Energy or the Safety Research Annual Plan issued by the Japanese government. The safety research at JAERI concerns the engineering safety of nuclear power plants and nuclear fuel cycle facilities, and radioactive waste management as well as advanced technology for safety improvement or assessment. Also, JAERI has conducted international collaboration to share the information on common global issues of nuclear safety. This report summarizes the nuclear safety research activities of JAERI from April 1999 through March 2001. (author)

  5. Institute of Energy and Climate Research IEK-6. Nuclear waste management and reactor safety report 2009/2010. Material science for nuclear waste management

    International Nuclear Information System (INIS)

    Klinkenberg, M.; Neumeier, S.; Bosbach, D.

    2011-01-01

    Due to the use of nuclear energy about 17.000 t (27.000 m 3 ) of high level waste and about 300.000 m 3 of low and intermediated level waste will have accumulated in Germany until 2022. Research in the Institute of Energy and Climate Research (IEK-6), Nuclear Waste Management and Reactor Safety Division focuses on fundamental and applied aspects of the safe management of nuclear waste - in particular the nuclear aspects. In principle, our research in Forschungszentrum Juelich is looking at the material science/solid state aspects of nuclear waste management. It is organized in several research areas: The long-term safety of nuclear waste disposal is a key issue when it comes to the final disposal of high level nuclear waste in a deep geological formation. We are contributing to the scientific basis for the safety case of a nuclear waste repository in Germany. In Juelich we are focusing on a fundamental understanding of near field processes within a waste repository system. The main research topics are spent fuel corrosion and the retention of radionuclides by secondary phases. In addition, innovative waste management strategies are investigated to facilitate a qualified decision on the best strategy for Germany. New ceramic waste forms for disposal in a deep geological formation are studied as well as the partitioning of long-lived actinides. These research areas are supported by our structure research group, which is using experimental and computational approaches to examine actinide containing compounds. Complementary to these basic science oriented activities, IEK-6 also works on rather applied aspects. The development of non-destructive methods for the characterisation of nuclear waste packages has a long tradition in Juelich. Current activities focus on improving the segmented gamma scanning technique and the prompt gamma neutron activation analysis. Furthermore, the waste treatment group is developing concepts for the safe management of nuclear graphite

  6. Institute of Energy and Climate Research IEK-6. Nuclear waste management and reactor safety report 2009/2010. Material science for nuclear waste management

    Energy Technology Data Exchange (ETDEWEB)

    Klinkenberg, M; Neumeier, S; Bosbach, D [eds.

    2011-07-01

    Due to the use of nuclear energy about 17.000 t (27.000 m{sup 3}) of high level waste and about 300.000 m{sup 3} of low and intermediated level waste will have accumulated in Germany until 2022. Research in the Institute of Energy and Climate Research (IEK-6), Nuclear Waste Management and Reactor Safety Division focuses on fundamental and applied aspects of the safe management of nuclear waste - in particular the nuclear aspects. In principle, our research in Forschungszentrum Juelich is looking at the material science/solid state aspects of nuclear waste management. It is organized in several research areas: The long-term safety of nuclear waste disposal is a key issue when it comes to the final disposal of high level nuclear waste in a deep geological formation. We are contributing to the scientific basis for the safety case of a nuclear waste repository in Germany. In Juelich we are focusing on a fundamental understanding of near field processes within a waste repository system. The main research topics are spent fuel corrosion and the retention of radionuclides by secondary phases. In addition, innovative waste management strategies are investigated to facilitate a qualified decision on the best strategy for Germany. New ceramic waste forms for disposal in a deep geological formation are studied as well as the partitioning of long-lived actinides. These research areas are supported by our structure research group, which is using experimental and computational approaches to examine actinide containing compounds. Complementary to these basic science oriented activities, IEK-6 also works on rather applied aspects. The development of non-destructive methods for the characterisation of nuclear waste packages has a long tradition in Juelich. Current activities focus on improving the segmented gamma scanning technique and the prompt gamma neutron activation analysis. Furthermore, the waste treatment group is developing concepts for the safe management of nuclear

  7. List of reports on reactor safety research from BMFT, CEA, EPRI, JSTA and USNRC

    International Nuclear Information System (INIS)

    1985-08-01

    This list reviews reports from the Federal Republic of Germany, from France, from Japan and from the United States of America concerning special problems in the field of reactor safety research. According to the cooperation of the Federal Ministry for Research and Technology (BMFT) with the Commissariat a l'Energie Atomique (CEA), the Japan Science and Technology Agency (JSTA), the Electric Power Research Institute (EPRI) and the United States Nuclear Regulatory Commission, these reports are available from the Society for Reactor Safety (GRS). The list pursues the following order: Country of origin, problem area concerned, according to the Reactor Safety Research Program of the BMFT, reporting organization. The list of reports appears quarterly. (orig./HP) [de

  8. Safety Research Opportunities Post-Fukushima. Initial Report of the Senior Expert Group

    International Nuclear Information System (INIS)

    Baek, Won-Pil; Yang, Joon-Eon; Ball, Joanne; Glowa, Glenn; Bisconti, Giulia; Peko, Damian; Bolshov, Leonid; Burgazzi, Luciano; De Rosa, Felice; Conde, Jose M.; Cook, Gary; Evrard, Jean-Michel; Jacquemain, Didier; Funaki, Kentaro; Uematsu, Mari Marianne; Miyoshi, Katsumasa; Tatematsu, Atsushi; Hirano, Masashi; Hoshi, Harutaka; Kawaragi, Chie; Kobayashi, Youko; Sakamoto, Kazunobu; Journeau, Christophe; Kim, Han-Chul; Klein-Hessling, Walter; Sonnenkalb, Martin; Koganeya, Toshiyuki; White, Andrew; ); Lind, Terttaliisa; Zimmermann, Martin; Lindholm, Ilona; Castelo Lopez, Carlos; Nagase, Fumihisa; Washiya, Tadahiro; Oima, Hirofumi; Okada, Hiro; Richards, Stuart; West, Steven; Sandberg, Nils; Suzuki, Shunichi; Vitanza, Carlo; Yamanaka, Yasunori

    2017-02-01

    One of the imperatives following the accident at the Fukushima Daiichi nuclear power station is for the nuclear science and industry communities to ensure that knowledge gaps in nuclear safety are identified and that research programs to address these gaps are being instituted. In recognition of broad international interest in additional information that could be gained from post-accident examinations related to Fukushima Daiichi, Japan recommended to the Committee on the Safety of Nuclear Installations (CSNI) in June 2013 that a process be developed to identify and follow up on opportunities to address safety research gaps. Consequently, a Senior Expert Group (SEG) on Safety Research Opportunities post-Fukushima (SAREF) was formed. The members of the group are senior technical experts from technical support organisations, nuclear regulatory authorities and Japanese organisations responsible for planning and execution of Fukushima Daiichi decommissioning. The domain of interest for the group is activities that address safety research knowledge gaps and also the needs of Fukushima Daiichi decommissioning. SEG on SAREF identified areas where these two interests intersect or overlap, and activities that could be undertaken to generate information of common benefit. The group's output is documented in this report; Chapter 2 describes the current status of the damaged units at Fukushima Daiichi NPS; Chapter 3 summarises safety research areas of common interest; Chapter 4 summarises the safety research activities recommended as short-term projects; Chapter 5 summarises those as long-term considerations; Chapter 6 supplies conclusions and recommendations. The appendix contains detailed information compiled by the SEG members on all safety research areas of interest

  9. Nuclear safety research master plan

    Energy Technology Data Exchange (ETDEWEB)

    Ha, Jae Joo; Yang, J. U.; Jun, Y. S. and others

    2001-06-01

    The SRMP (Safety Research Master Plan) is established to cope with the changes of nuclear industry environments. The tech. tree is developed according to the accident progress of the nuclear reactor. The 11 research fields are derived to cover the necessary technologies to ensure the safety of nuclear reactors. Based on the developed tech. tree, the following four main research fields are derived as the main safety research areas: 1. Integrated nuclear safety enhancement, 2. Thermal hydraulic experiment and assessment, 3. Severe accident management and experiment, and 4. The integrity of equipment and structure. The research frame and strategies are also recommended to enhance the efficiency of research activity, and to extend the applicability of research output.

  10. List of BMFT, USNRC, EPRI, and STA reports on reactor safety research

    International Nuclear Information System (INIS)

    1980-07-01

    This list reviews reports from the Federal Republic of Germany, from the United States of America and from Japan concerning special problems in the field of Reactor Safety Research. According to the cooperation of the Bundesminister fuer Forschung und Technologie (BMFT) with the United States Nuclear Regulatory Commission (USNRC), the Electric Power Research Institute (EPRI), and the Japan Science and Technology Agency (JSTA) these reports are available in the Gesellschaft fuer Reaktorsicherheit. The list pursues the following order : Country of origin, problem area concerned, according to the Reactor Safety Research Program of BMFT, reporting organisation. The list of reports appears quarterly. (orig./HP) [de

  11. Reports covering research projects in the field of reactor safety supported by the German Federal Ministry for Research and Technology

    International Nuclear Information System (INIS)

    1976-03-01

    Investigations on the safety of Light Water Reactors (LWR) being performed in the framework of the safety program 'Reactor Safety' are sponsored by the Bundesminister fuer Forschung und Technologie (BMFT - Secretary of State for Research and Technology). Objective of this program is to continue improving the safety of LWR, in order to minimize the risk for the environment. With grant assistance from the Bundesminister des Innern. (BMI - Secretary of State for Home Affairs) research cont racts in the field of reactor safety are being performed. Results of these projects should contribute to resolve questions arising nuclear licensing procedures. The Forschungsbetreuung (FB - research supervision department) at the Institute for Reactor Safety (IRS), as consultants to BMFT and BMI, provides information about the progress of investigations. Individual reports will be prepared and put into standard forms by the research contractors. Each report gives information on: 1) the work accomplished, 2) the results obtained, 3) the work planned to be continued. Initial reports of research projects describe in addition the purpose of the work. A BMFT-research program on the safety of Fast Breeders (Schneller Brutreaktor - SBR) is presently under discussion. In order to define several problems, investigations included in the present compilation (RS 139, 140, 143, 162) will be previously performed. (orig.) [de

  12. Annual report of the Japan Atomic Energy Research Institute for fiscal 2002

    International Nuclear Information System (INIS)

    2003-01-01

    The Japan Atomic Energy Research Institute (JAERI) is comprehensively promoting the research and development (R and D) activities to make the best use of variety of potentials of atomic energy. In the field of nuclear energy, researches on advanced nuclear engineering systems, high-temperature engineering experimentation and nuclear fusion are forwarded to realize long-range stable supply of energy. Researches on safety of nuclear facilities, health physics and science and technology for society have been conducted in the safety category mainly according to 'Annual Plan for Safety Research' to play and important part in long-range utilization of power generation by LWRs and to meet the expectations of people by maintaining reliability and openness associated with 'safety and confidence'. As a diversification of nuclear science and technology, various radiation application activities such as neutron science, advanced photon science and synchrotron radiation science and application research of charged particles and radioisotopes have been promoted, which contribute to drastic advance in the fields of materials and life science etc. and to establishment of new industries. Along with these activities, basic and fundamental researches including advanced basic research, materials science research, nuclear environmental science research and advanced computational science and engineering are in progress. In addition, JAERI is devoted to the technology development in radioactive waste management and nuclear facility dismantling and also to international cooperation and training activities etc. in the peaceful use of nuclear energy. The research activities for FY 2002 are reviewed in this issue. (J.P.N.)

  13. Safety research plan, JFY 2013 edition

    International Nuclear Information System (INIS)

    2013-09-01

    As for the regulatory issues the governments or JNES considered necessary, JNES had updated every year 'safety research plan' in respective research areas necessary for solving the regulatory issues (safety research needs) and was conducting safety research to obtain the results, etc. 'Safety research plan, JFY 2013 Edition' was compiled aiming at promotion of appropriate reflection and flexible application of research achievements for tacking the regulatory issues taking account of importance and urgency dependent on trend of nuclear safety regulations as well as collective management of safety research and safety survey. 5 new research projects were established with 4 unified research projects and 6 terminated research projects. Finally modified safety research areas, subjects and research projects, JFY 2013 Edition were as follows: design review of nuclear power plant (7 subjects and each subject having several research projects totaled 19), control management of nuclear power plant (one subject having 4 research projects), nuclear fuel cycle (2 subjects and each subject having several research projects totaled 4), nuclear fuel cycle backend (2 subjects and each subject having several research projects totaled 5), nuclear emergency preparedness and response (3 subjects and each subject having several research projects totaled 7) and bases of nuclear safety technology (3 subjects and each subject having several research projects totaled 6). Safety reviews consisted of 6 projects in 3 areas extracting the regulatory issues. As for urgent research projects on the basis of the disaster at Fukushima Daiichi NPP accident, 7 research projects in 4 urgent subjects were as follows: examination for new safety regulation (4 research projects generalized in the above research projects), development of newly necessary evaluation methods (one research project generalized in the above research project), evaluation of the validity for the work for convergence at Fukushima

  14. Institutional glovebox safety committee (IGSC) annual report FY2010

    Energy Technology Data Exchange (ETDEWEB)

    Cournoyer, Michael E [Los Alamos National Laboratory; Roybal, Richard F [Los Alamos National Laboratory; Lee, Roy J [Los Alamos National Laboratory

    2011-01-04

    The Institutional Glovebox Safety Committee (IGSC) was chartered to minimize and/or prevent glovebox operational events. Highlights of the IGSC's third year are discussed. The focus of this working committee is to address glovebox operational and safety issues and to share Lessons Learned, best practices, training improvements, and glovebox glove breach and failure data. Highlights of the IGSC's third year are discussed. The results presented in this annual report are pivotal to the ultimate focus of the glovebox safety program, which is to minimize work-related injuries and illnesses. This effort contributes to the LANL Continuous Improvement Program by providing information that can be used to improve glovebox operational safety.

  15. [German research institute/Max-Planck Institute for psychiatry].

    Science.gov (United States)

    Ploog, D

    1999-12-01

    The Deutsche Forschungsanstalt für Psychiatrie (DFA, German Institute for Psychiatric Research) in Munich was founded in 1917 bel Emil Kraepelin. For a long time it was the only institution in Germany entirely devoted to psychiatric research. Because of its strictly science-oriented and multidisciplinary approach it also became a model for institutions elsewhere. Kraepelin's ideas have certainly had a strong influence on psychiatry in the twentieth century. The fascinating and instructive history of the DFA reflects the central issues and determinants of psychiatric research. First, talented individuals are needed to conduct such research, and there was no lack in this regard. Second, the various topics chosen are dependent on the available methods and resources. And finally, the issues addressed and the ethical standards of the researchers are heavily dependent on the zeitgeist, as is evident in the three epochs of research at the DFA, from 1917 to 1933, from 1933 to 1945, and from the postwar period to the present. With the introduction of molecular biology and neuroimaging techniques into psychiatric research a change in paradigm took place and a new phase of the current epoch began.

  16. Report of test and research results on atomic energy obtained in national institutes in fiscal 1986

    International Nuclear Information System (INIS)

    1988-01-01

    The test and research regarding the utilization of atomic energy carried out in national institutions have produced many valuable results in diverse fields so far, such as nuclear fusion, safety research, food irradiation and medicine, since the budget had been appropriated for the first time in 1956. It has accomplished large role in the promotion of atomic energy utilization in Japan. This report is volume 27, in which the results of the test and research on atomic energy utilization carried out by national institutions in fiscal year 1986 are summarized. It is hoped that the understanding about the recent trend and the results of the test and research on atomic energy utilization is further promoted by this report. The contents of this report are nuclear fusion; the research on engineering safety and environmental radioactivity safety; food irradiation; the countermeasures against cancer; fertilized soil, the improvement of quality, the protection of plants and the improvement of breeding in agriculture and fishery fields; diagnosis and medical treatment, pharmaceuticals, environmental hygiene and the application to physiology and pathology in medical field; radiation chemistry and radiation measurement in mining and industry fields; nuclear reactor materials and nuclear-powered ships; civil engineering; radioactivation analysis; and the research on the prevention of injuries. (Kako, I.)

  17. Report of test and research results on atomic energy obtained in national institutes in fiscal 1984

    International Nuclear Information System (INIS)

    1985-01-01

    The test and research regarding the utilization of atomic energy carried out in national institutions have produced many valuable results in diverse fields so far, such as nuclear fusion, safety research, food irradiation and medicine, since the budget had been appropriated for the first time in 1956. It has accomplished large role in the promotion of atomic energy utilization in Japan. This report is Volume 25, in which the results of the test and research on atomic energy utilization carried out by national institutions in fiscal year 1984 are summarized. It is hoped that the understanding about the recent trend and the results of the test and research on atomic energy utilization is further promoted by this report. The contents of this report are nuclear fusion; the research on engineering safety and environmental radioactivity safety; food irradiation; the countermeasures against cancer; fertilized soil, the improvement of quality, the protection of plants and the improvement of breeding in agriculture and fishery fields; diagnosis and medical treatment, pharmaceuticals, environmental hygiene and the application to physiology and pathology in medical field; radiation chemistry and radiation measurement in mining and industry fields; nuclear reactor materials and nuclear-powered ships; civil engineering; radioactivation analysis; and the research on the prevention of injuries. (Kako, I.)

  18. Safety Culture and Best Practices at Japan's Fusion Research Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Rule, Keith [PPPL

    2014-05-01

    The Safety Monitor Joint Working Group (JWG) is one of the magnetic fusion research collaborations between the US Department of Energy and the government of Japan. Visits by occupational safety personnel are made to participating institutions on a biennial basis. In the 2013 JWG visit of US representatives to Japan, the JWG members noted a number of good safety practices in the safety walkthroughs. These good practices and safety culture topics are discussed in this paper. The JWG hopes that these practices for worker safety can be adopted at other facilities. It is a well-known, but unquantified, safety principle that well run, safe facilities are more productive and efficient than other facilities (Rule, 2009). Worker safety, worker productivity, and high quality in facility operation all complement each other (Mottel, 1995).

  19. Survey and analysis of radiation safety management systems at medical institutions. Initial report. Radiation protection supervisor, radiation safety organization, and education and training

    International Nuclear Information System (INIS)

    Ohba, Hisateru; Ogasawara, Katsuhiko; Aburano, Tamio

    2005-01-01

    In this study, a questionnaire survey was carried out to determine the actual situation of radiation safety management systems in Japanese medical institutions with nuclear medicine facilities. The questionnaire consisted of questions concerning the Radiation Protection Supervisor license, safety management organizations, and problems related to education and training in safety management. Analysis was conducted according to region, type of establishment, and number of beds. The overall response rate was 60%, and no significant difference in response rate was found among regions. Medical institutions that performed nuclear medicine practices without a radiologist participating accounted for 10% of the total. Medical institutions where nurses gave patients intravenous injections of radiopharmaceuticals as part of the nuclear medicine practices accounted for 28% of the total. Of these medical institutions, 59% provided education and training in safety management for nurses. The rate of acquisition of Radiation Protection Supervisor licenses was approximately 70% for radiological technologists and approximately 20% for physicians (regional difference, p=0.02). The rate of medical institutions with safety management organizations was 71% of the total. Among the medical institutions (n=208) without safety management organizations, approximately 56% had 300 beds or fewer. In addition, it became clear that 35% of quasi-public organizations and 44% of private organizations did not provide education and training in safety management (p<0.001, according to establishment). (author)

  20. Reactor safety research program. A description of current and planned reactor safety research sponsored by the Nuclear Regulatory Commission's Division of Reactor Safety Research

    International Nuclear Information System (INIS)

    1975-06-01

    The reactor safety research program, sponsored by the Nuclear Regulatory Commission's Division of Reactor Safety Research, is described in terms of its program objectives, current status, and future plans. Elements of safety research work applicable to water reactors, fast reactors, and gas cooled reactors are presented together with brief descriptions of current and planned test facilities. (U.S.)

  1. Annual report for FY 2007 on the activities of radiation control in Nuclear Science Research Institute etc. April 1, 2007 - March 31, 2008

    International Nuclear Information System (INIS)

    2009-01-01

    This annual report describes the activities of Radiation Protection Sector in Department of Radiation Protection in Nuclear Science Research Institute, Safety Section in Takasaki Advanced Radiation Research Institute, Safety Section in Kansai Photon Science Institute and Operation Safety Administration Section in Aomori Research and Development Center. The report covers environmental monitoring around the facilities, radiation protection of workplace and workers, individual monitoring, maintenance of monitoring instruments, and research and development of radiation protection technologies, which were performed at the Radiation Protection Sector. There were no occupational or public exposures exceeding the prescribed dose limits. No effluent releases were recorded exceeding the prescribed limits on the amount and concentration of radioactivity for gaseous release and liquid waste. As for the research and development activities, studies were conducted continuously focusing mainly on the following themes: technological developments on operational radiation protection and establishment of calibration fields for various energy types of neutrons. (author)

  2. Status of nuclear safety research - 2000

    International Nuclear Information System (INIS)

    Sobajima, Makoto; Sasajima, Hideo; Umemoto, Michitaka; Yamamoto, Toshihiro; Tanaka, Tadao; Togashi, Yoshihiro; Nakata, Masahito

    2000-11-01

    The nuclear safety research at JAERI is performed in accordance with the long term plan on nuclear research, development and use and the safety research yearly plan determined by the government and under close relationship to the related departments in and around the Nuclear Safety Research Center. The criticality accident having occurred in Tokai-mura in 1999 has been the highest level nuclear accident in Japan and ensuring safety in whole nuclear cycle is severely questioned. The causes of such an accident have to be clarified not only technical points but also organizational points, and it is extremely important to make efforts in preventing recurrence, to fulfill emergency plan and to improve the safety of whole nuclear fuel cycle for restoring the reliability by the people to nuclear energy system. The fields of conducting safety research are engineering safety research on reactor facilities and nuclear fuel cycle facilities including research on radioactive waste processing and disposal and research and development on future technology for safety improvement. Also, multinational cooperation and bilateral cooperation are promoted in international research organizations in the center to internationally share the recognition of world-common issues of nuclear safety and to attain efficient promotion of research and effective utilization of research resources. (author)

  3. Reactor Safety Research: Semiannual report, January-June 1986: Reactor Safety Research Program

    International Nuclear Information System (INIS)

    1987-05-01

    Sandia National Laboratories is conducting, under USNRC sponsorship, phenomenological research related to the safety of commercial nuclear power reactors. The research includes experiments to simulate the phenomenology of accident conditions and the development of analytical models, verified by experiment, which can be used to predict reactor and safety systems performance behavior under abnormal conditions. The objective of this work is to provide NRC requisite data bases and analytical methods to (1) identify and define safety issues, (2) understand the progression of risk-significant accident sequences, and (3) conduct safety assessments. The collective NRC-sponsored effort at Sandia National Laboratories is directed at enhancing the technology base supporting licensing decisions

  4. Nuclear safety research

    International Nuclear Information System (INIS)

    1996-01-01

    The topics 'Large-sized PWR-NPP Safety Techniques Research',and 'The Key Techniques Research on the Safety Supervision and Control for Operation of Nuclear Installations' have been adopted as an apart of 'the National 9th five Year Programs for Tacking the Key Scientific and Technical Topics' which are organized by the State Planning Commission (SPC) and State Science and Technology Commission (SSTC) respectively, and have obtained a financial support from them. To play a better role with the limited fund, the NNSA laid special stress on selecting key sub-topics on nuclear safety, and carefully choosing units which would undertake sub-topics and signing technical contracts with them

  5. Technical and institutional safety features of nuclear power plants in Brazil

    International Nuclear Information System (INIS)

    Rosa, L.P.

    1986-01-01

    This work reports technical, political and institutional safety features of nuclear power plants in Brazil. It is mainly concerned with reactor accidents and personnel safety. The three mile Island and Chernobyl accidents are also discussed and taken as examples. (A.C.A.S.)

  6. List of reports in reactor safety research by BMFT, USNRC, EPRI and JSTA

    International Nuclear Information System (INIS)

    1981-01-01

    This list reviews reports from the Federal Republic of Germany, from the United States of America and from Japan concerning special problems in the field of Reactor Safety research. According to the cooperation of the Bundesminister fuer Forschung und Technologie (BMFT) with the United States Nuclear Regulatory Commission (USNRC), the Electric Power Research Institute (EPRI), and the Japan Science and Technology Agency (JSTA) these reports are available in the Gesellschaft fuer Reaktorsicherheit. The list pursues the following order: Country of origin, problem area concerned, according to the Reactor Safety Research Program of BMFT, reporting organisation. The list of reports appears quarterly. (orig.) [de

  7. Commissioning of research reactors. Safety guide

    International Nuclear Information System (INIS)

    2006-01-01

    The objective of this Safety Guide is to provide recommendations on meeting the requirements for the commissioning of research reactors on the basis of international best practices. Specifically, it provides recommendations on fulfilling the requirements established in paras 6.44 and 7.42-7.50 of International Atomic Energy Agency, Safety of Research Reactors, IAEA Safety Standards Series No. NS-R-4, IAEA, Vienna (2005) and guidance and specific and consequential recommendations relating to the recommendations presented in paras 615-621 of International Atomic Energy Agency, Safety in the Utilization and Modification of Research Reactors, Safety Series No. 35-G2, IAEA, Vienna (1994) and paras 228-229 of International Atomic Energy Agency, Safety Assessment of Research Reactors and Preparation of the Safety Analysis Report, Safety Series No. 35-G1, IAEA, Vienna (1994). This Safety Guide is intended for use by all organizations involved in commissioning for a research reactor, including the operating organization, the regulatory body and other organizations involved in the research reactor project

  8. Institutional Researchers' Use of Qualitative Research Methods for Institutional Accountability at Two Year Colleges in Texas

    Science.gov (United States)

    Sethna, Bishar M.

    2011-01-01

    This study examined institutional researchers' use of qualitative methods to document institutional accountability and effectiveness at two-year colleges in Texas. Participants were Institutional Research and Effectiveness personnel. Data were collected through a survey consisting of closed and open ended questions which was administered…

  9. Annual report of Nuclear Science Research Institute, JFY2006

    International Nuclear Information System (INIS)

    2008-03-01

    Nuclear Science Research Institute (NSRI) is composed of Planning and Coordination Office and seven departments such as Department of Operational Safety Administration, Department of Radiation Protection, Department of Research Reactor and Tandem Accelerator, Department of Hot Laboratories and Facilities, Department of Criticality and Fuel Cycle Research Facilities, Department of Decommissioning and Waste Management, and Engineering Services Department. This annual report of JFY2006 summarizes the activities of NSRI, the R and D activities of the Research and Development Directorates and human resources development at site, and is expected to be referred to and utilized by R and D departments and project promotion sectors at NSRI site for the enhancement of their own research and management activities to attain their goals according to 'Middle-term Plan' successfully and effectively. In chapter 1, outline of JFY2006 activities of NSRI is described. In chapter 2, the following activities made by the departments in NSRI are summarized, i.e., (1) operation and maintenance of research reactors (JRR-3, JRR-4, NSRR), criticality assemblies (STACY, TRACY, FCA, TCA), hot laboratories (BECKY, Reactor Fuel Examination Facility, WASTEF, Research Laboratory 4, Plutonium Research Laboratory 1, Tokai Hot Laboratory, etc), and large-scale facilities (Tandem accelerator, LSTF, THYNC, TPTF, etc), and (2) safety management, radiation protection, management of radioactive wastes, decommissioning of nuclear facilities, engineering services, utilities and maintenance, etc, all of which are indispensable for the stable and safe operation and utilization of the research facilities. The technical developments for the advancement of the related technologies are also summarized. In chapter 3, the R and D and human resources development activities are described including the topics of the research works and projects performed by the Research and Development Directorates at site, such as

  10. The role of simulation in mixed-methods research: a framework & application to patient safety.

    Science.gov (United States)

    Guise, Jeanne-Marie; Hansen, Matthew; Lambert, William; O'Brien, Kerth

    2017-05-04

    Research in patient safety is an important area of health services research and is a national priority. It is challenging to investigate rare occurrences, explore potential causes, and account for the complex, dynamic context of healthcare - yet all are required in patient safety research. Simulation technologies have become widely accepted as education and clinical tools, but have yet to become a standard tool for research. We developed a framework for research that integrates accepted patient safety models with mixed-methods research approaches and describe the performance of the framework in a working example of a large National Institutes of Health (NIH)-funded R01 investigation. This worked example of a framework in action, identifies the strengths and limitations of qualitative and quantitative research approaches commonly used in health services research. Each approach builds essential layers of knowledge. We describe how the use of simulation ties these layers of knowledge together and adds new and unique dimensions of knowledge. A mixed-methods research approach that includes simulation provides a broad multi-dimensional approach to health services and patient safety research.

  11. Progress of nuclear safety research-2004

    International Nuclear Information System (INIS)

    Anoda, Yoshinari; Ebine, Noriya; Chuto, Toshinori; Sato, Satoshi; Ishikawa, Jun; Yamamoto, Toshihiro; Munakata, Masahiro; Asakura, Toshihide; Yamaguchi, Tetsuji; Kida, Takashi; Matsui, Hiroki; Haneishi, Akihiro; Araya, Fumimasa

    2005-03-01

    JAERI is conducting nuclear safety research primarily at the Nuclear Safety Research Center in close cooperation with the related departments in accordance with the Long Term Plan for Development and Utilization of Nuclear Energy and Annual Plan for Safety Research issued by the Japanese government. The fields of conducting safety research at JAERI are the engineering safety of nuclear power plants and nuclear fuel cycle facilities, and radioactive waste management as well as advanced technology for safety improvement or assessment. Also, JAERI has conducted international collaboration to share the information on common global issues of nuclear safety and to supplement own research. Moreover, when accidents occurred at nuclear facilities, JAERI has taken a responsible role by providing technical experts and investigation for assistance to the government or local public body. This report summarizes the nuclear safety research activities of JAERI from April 2002 through March 2004 and utilized facilities. (author)

  12. Annual safety research report, JFY 2012

    International Nuclear Information System (INIS)

    2013-08-01

    As for the regulatory issues the governments or JNES considered necessary, JNES had compiled 'safety research plan' in respective research areas necessary for solving the regulatory issues (safety research needs) and was conducting safety research to obtain the results, etc. Safety research areas, subjects and research projects were as follows: design review of nuclear power plant (5 subjects and each subject having several research projects totaled 20), control management of nuclear power plant (3 subjects and each subject having several research projects totaled 6), nuclear fuel cycle (2 subjects and each subject having several research projects totaled 4), nuclear fuel cycle backend (2 subjects and each subject having several research projects totaled 6), nuclear emergency preparedness and response (3 subjects and each subject having several research projects totaled 7) and bases of nuclear safety technology (3 subjects and each subject having several research projects totaled 6). In addition to these 49 research projects of 18 subjects in 6 areas, JNES worked on 19 research projects of 7 subjects in added areas (specific research projects on of the disaster at Fukushima Daiichi NPP accident and other challenges JNES considered necessary) in JFY 2012. This annual safety research report summarized respective achievements and state of regulatory tools necessary for solving regulatory issues according to the safety research plan, JFY 2012 Edition as well as the situation of the reflection for the safety regulations, and also described 16 research projects of 4 subjects: examination for new safety regulation (8 research projects), development of newly necessary evaluation methods (one research project), evaluation of the validity for the work for convergence at Fukushima Daiichi NPP accident (4 research project) and horizontal development to other nuclear power plants (3 research projects), and 3 research projects of 3 subjects as other challenges. A list of JNES

  13. Annual report 1995 of the Central Safety Department, Research Center Karlsruhe

    International Nuclear Information System (INIS)

    Koelzer, W.

    1996-04-01

    The Central Safety Department is responsible for supervising, monitoring and, to some extent, also executing measures of radiation protection, industrial health and safety as well as physical protection and security at and for the institutes and departments of the Karlsruhe Research Center (Forschungszentrum Karlsruhe GmbH), and for monitoring liquid effluents and the environment of all facilities and nuclear installations on the premises of the Research Center. In addition, research and development work is carried out in the fields of behavior of tritium in the air/soil/plant system, tritium balances for nuclear fusion fuel cycles, and assessments of mining and ore dressing spoils. This report gives details of the different duties and reports the results of 1995 routine tasks, investigations and developments of the working groups of the Department. The reader is referred to the English translation of Chapter 1 describing the duties and organization of the Central Safety Department. (orig.) [de

  14. Annual report of the Institute of Physical and Chemical Research, for fiscal 1979

    International Nuclear Information System (INIS)

    1980-01-01

    In this annual report, the summary of the researches carried out in the Institute in 1979, and the reports of the researches published as the achievements of the Institute are described, being classified into every laboratory. In addition, the summary of specific researches, special researches and the researches made with subsidies, entrusted researches and the list of patents acquired in 1979 are written. The gists of the lectures given in international conferences and the symposia in the Institute held in 1979 are also included at the end. The laboratories are divided into those concerned with atomic nuclei, material science, applied physics, fundamental technologies, inorganic chemistry, organic chemistry, biochemistry and agricultural chemicals, the research group on laser science, and eight other facilities. The specific researches are related to laser science, solar light energy, mathematical formula treating system and biology. The special researches are integrated researches, important researches, industrialization researches, and the researches on cosmic ray, agricultural chemicals and atomic energy. 31 subjects from 20 companies were entrusted, and 70 researchers were accepted from 48 companies, in 1979. The eight facilities are those of organic microanalysis, inorganic analysis, electronic computer, helium liquefaction, beam analysis, animal test, safety control and workmanship. (Kako, I.)

  15. Trends in fuel reprocessing safety research

    International Nuclear Information System (INIS)

    Tsujino, Takeshi

    1981-01-01

    With the operation of a fuel reprocessing plant in the Power Reactor and Nuclear Fuel Development Corporation (PNC) and the plan for a second fuel reprocessing plant, the research on fuel reprocessing safety, along with the reprocessing technology itself, has become increasingly important. As compared with the case of LWR power plants, the safety research in this field still lags behind. In the safety of fuel reprocessing, there are the aspects of keeping radiation exposure as low as possible in both personnel and local people, the high reliability of the plant operation and the securing of public safety in accidents. Safety research is then required to establish the safety standards and to raise the rate of plant operation associated with safety. The following matters are described: basic ideas for the safety design, safety features in fuel reprocessing, safety guideline and standards, and safety research for fuel reprocessing. (J.P.N.)

  16. Annual report of the Japan Atomic Energy Research Institute for fiscal 1992

    International Nuclear Information System (INIS)

    1993-01-01

    Japan Atomic Energy Research Institute has promoted the research on high temperature engineering, the research and development of nuclear fusion, the research on radiation utilization and the research and development of nuclear powered ships as the advanced project researches which bring about the breakthrough of atomic energy technology as well as the research on the safety, following the long term plan of atomic energy development and utilization which was decided in 1987, as the general research institute in Japanese atomic energy field. The progress of the above mentioned researches in fiscal 1992 is reported. The operation of JRR-2, JRR-3M, JRR-4 and JMTR was carried out as scheduled. 9 cases of the medical irradiation on brain tumors were performed at JRR-2. As to the practical test of the disassembling of JPDR, the machinery and equipment in the reactor containment vessel were removed, and the development of a high performance decontamination testing device and others was advanced. The efficient operation of the large computer system, the production and sales of radioisotopes and radioactive waste business were continued. (K.I.)

  17. Institutional failure: are safety management systems the answer?

    Energy Technology Data Exchange (ETDEWEB)

    Waddington, J.G.; Lafortune, J.F. [International Safety Research, Ottawa, Ontario (Canada); Duffey, R.B. [Atomic Energy of Canada Limited, Chalk River, Ontario (Canada)

    2009-07-01

    In spite of an overwhelming number of safety management programs, incidents and accidents that could seemingly, in hindsight, have been prevented, still occur. Institutional failure is seen as a major contributor in almost all cases. With the anticipated significant increase in the number of nuclear plants around the world, a drastic step in the way we manage safety is deemed essential to further reduce the currently already very low rate of accidents to levels that will not cause undue public concern and threaten the success of the nuclear 'renaissance'. To achieve this, many industries have already started implementing a Safety Management System (SMS) approach, aimed at harmonizing, rationalizing and integrating management processes, safety culture and operational risk assessment. This paper discusses the origins and the nature of SMS based in part on the experience of the aviation industry, and shows how SMS is poised to be the next generation in the way the nuclear industry manages safety. It also discusses the need for better direct measures of risk to demonstrate the success of SMS implementation. (author)

  18. Institutional failure: are safety management systems the answer?

    International Nuclear Information System (INIS)

    Waddington, J.G.; Lafortune, J.F.; Duffey, R.B.

    2009-01-01

    In spite of an overwhelming number of safety management programs, incidents and accidents that could seemingly, in hindsight, have been prevented, still occur. Institutional failure is seen as a major contributor in almost all cases. With the anticipated significant increase in the number of nuclear plants around the world, a drastic step in the way we manage safety is deemed essential to further reduce the currently already very low rate of accidents to levels that will not cause undue public concern and threaten the success of the nuclear 'renaissance'. To achieve this, many industries have already started implementing a Safety Management System (SMS) approach, aimed at harmonizing, rationalizing and integrating management processes, safety culture and operational risk assessment. This paper discusses the origins and the nature of SMS based in part on the experience of the aviation industry, and shows how SMS is poised to be the next generation in the way the nuclear industry manages safety. It also discusses the need for better direct measures of risk to demonstrate the success of SMS implementation. (author)

  19. Report of test and research results on atomic energy obtained in national institutes in fiscal 1987

    International Nuclear Information System (INIS)

    1989-01-01

    The test and research regarding the utilization of atomic energy carried out in national institutions have produced many valuable results in diverse fields so far, such as nuclear fusion, safety research, food irradiation and medicine, since the budget had been appropriated for the first time in 1956. It has accomplished large role in the promotion of atomic energy utilization in Japan. This report is volume 28, in which the results of the test and research on atomic energy utilization carried out by national institutions in fiscal year 1987 are summarized. It is hoped that the understanding about the recent trend and the results of the test and research on atomic energy utilization is further promoted by this report. The contents of this report are nuclear fusion; the research on engineering safety and environmental radioactivity safety; food irradiation; the countermeasures against cancer; fertilized soil, the improvement of quality, the protection of plants and the improvement of breeding in agriculture and fishery fields; diagnosis and medical treatment, pharmaceuticals, environmental hygiene and the application to physiology and pathology in medical field; radiation measurement and process analysis in mining and industry fields; nuclear reactor materials and nuclear-powered ships; civil engineering; radioactivation analysis; the research on the prevention of injuries; and the basic researches on materials and acessment and reduction of irradiation risk. (J.P.N.)

  20. Report of test and research results on atomic energy obtained in national institutes in fiscal 1985

    International Nuclear Information System (INIS)

    1986-01-01

    As for the test and research on the utilization of atomic energy in national institutes, the budget was appropriated for the first time in fiscal year 1956, and since then, the many valuable results of research have been obtained so far in the diversified fields of nuclear fusion, safety research, the irradiation of foods, medicine and others, thus the test and research accomplished the large role for promoting the utilization of atomic energy in Japan. In this report, the gists of the results of the test and research on the utilization of atomic energy carried out by national institutes in fiscal year 1985 are collected. No.1 of this report was published in 1960, and this is No.26. It is desired to increase the understanding about the recent trend and the results of the test and research on atomic energy utilization with this book. The researches on nuclear fusion, engineering safety and environmental radioactivity safety, the irradiation of foods, the countermeasures against cancer, fertilized soil, the quality improvement of brewing and farm products, the protection of farm products and the improvement of breeding, diagnosis and medical treatment, pharmaceuticals, environmental hygiene, the application to physiology and pathology, radiochemistry, radiation measurement, process analysis, nuclear reactor materials, nuclear powered ships, civil engineering, radioactivation analysis and injury prevention are reported. (Kako, I.)

  1. Institutional Support : Kenya Institute for Public Policy Research and ...

    International Development Research Centre (IDRC) Digital Library (Canada)

    In 2006 the Government of Kenya passed an Act of Parliament making the Kenya Institute for Public Policy Research and Analysis (KIPPRA) the government's lead socioeconomic research institute. The Act exerts enormous demands on KIPPRA at a time when it is trying to recover from the senior staff turnover suffered in ...

  2. Guidelines for PWR safety research and development at NUCLEBRAS - Brazil

    International Nuclear Information System (INIS)

    Pinheiro, R.B.

    1980-06-01

    NUCLEBRAS research into different areas of pressurized light-water reactor technology, is one of the aims of its Research and Development Center, Centro de Desenvolvimento da Tecnologia Nuclear (CDTN), in Belo Horizonte. The main effort of the center is now directed to give technical support to the industrial activities of the Nuclear Program, and to carry out R and D work in strainght connection with these activities. As a consequence few work on safety research is actualy being performed, although the number of activities in this field increases steadily, not as a function but strong related to the development of our industrial program. Basic training and qualification of personnel at CDTN for different research and development activities of NUCLEBRAS has high priority. This is covered either by agreements with national institutions (e.g. universities) or using the various possibilities offered by special agreements and cooperation programs with research centers and other institutions, not only but mainly in Germany, F.R. (Author) [pt

  3. Using institutional theory in enterprise systems research

    DEFF Research Database (Denmark)

    Svejvig, Per

    2013-01-01

    This paper sets out to examine the use of institutional theory as a conceptually rich lens to study social issues of enterprise systems (ES) research. More precisely, the purpose is to categorize current ES research using institutional theory to develop a conceptual model that advances ES research...... model that advocates multi-level and multi-theory approaches and applies newer institutional aspects such as institutional logics. The findings show that institutional theory in ES research is in its infancy and adopts mainly traditional institutional aspects like isomorphism, with the organization....... Key institutional features are presented such as isomorphism, rationalized myths, and bridging macro and micro structures, and institutional logics and their implications for ES research are discussed. Through a literature review of 181 articles, of which 18 papers are selected, we build a conceptual...

  4. Institute of Energy and Climate Research IEK-6. Nuclear waste management and reactor safety report 2009/2010. Material science for nuclear waste management

    Energy Technology Data Exchange (ETDEWEB)

    Klinkenberg, M.; Neumeier, S.; Bosbach, D. (eds.)

    2011-07-01

    Due to the use of nuclear energy about 17.000 t (27.000 m{sup 3}) of high level waste and about 300.000 m{sup 3} of low and intermediated level waste will have accumulated in Germany until 2022. Research in the Institute of Energy and Climate Research (IEK-6), Nuclear Waste Management and Reactor Safety Division focuses on fundamental and applied aspects of the safe management of nuclear waste - in particular the nuclear aspects. In principle, our research in Forschungszentrum Juelich is looking at the material science/solid state aspects of nuclear waste management. It is organized in several research areas: The long-term safety of nuclear waste disposal is a key issue when it comes to the final disposal of high level nuclear waste in a deep geological formation. We are contributing to the scientific basis for the safety case of a nuclear waste repository in Germany. In Juelich we are focusing on a fundamental understanding of near field processes within a waste repository system. The main research topics are spent fuel corrosion and the retention of radionuclides by secondary phases. In addition, innovative waste management strategies are investigated to facilitate a qualified decision on the best strategy for Germany. New ceramic waste forms for disposal in a deep geological formation are studied as well as the partitioning of long-lived actinides. These research areas are supported by our structure research group, which is using experimental and computational approaches to examine actinide containing compounds. Complementary to these basic science oriented activities, IEK-6 also works on rather applied aspects. The development of non-destructive methods for the characterisation of nuclear waste packages has a long tradition in Juelich. Current activities focus on improving the segmented gamma scanning technique and the prompt gamma neutron activation analysis. Furthermore, the waste treatment group is developing concepts for the safe management of nuclear

  5. Measuring patient safety culture in maternal and child health institutions in China: a qualitative study.

    Science.gov (United States)

    Wang, Yuanyuan; Liu, Weiwei; Shi, Huifeng; Liu, Chaojie; Wang, Yan

    2017-07-12

    Patient safety culture (PSC) plays a critical role in ensuring safe and quality care. Extensive PSC studies have been undertaken in hospitals. However, little is known about PSC in maternal and child health (MCH) institutions in China, which provide both population-based preventive services as well as individual care for patients. This study aimed to develop a theoretical framework for conceptualising PSC in MCH institutions in China. The study was undertaken in six MCH institutions (three in Hebei and three in Beijing). Participants (n=118) were recruited through stratified purposive sampling: 20 managers/administrators, 59 care providers and 39 patients. In-depth interviews were conducted with the participants. The interview data were coded using both inductive (based on the existing PSC theory developed by the Agency for Healthcare Research and Quality) and deductive (open coding arising from data) approaches. A PSC framework was formulated through axial coding that connected initial codes and selective coding that extracted a small number of themes. The interviewees considered patient safety in relation to six aspects: safety and security in public spaces, safety of medical services, privacy and information security, financial security, psychological safety and gap in services. A 12-dimensional PSC framework was developed, containing 69 items. While the existing PSC theory was confirmed by this study, some new themes emerged from the data. Patients expressed particular concerns about psychological safety and financial security. Defensive medical practices emerged as a PSC dimension that is associated with not only medical safety but also financial security and psychological safety. Patient engagement was also valued by the interviewees, especially the patients, as part of PSC. Although there are some common features in PSC across different healthcare delivery systems, PSC can also be context specific. In MCH settings in China, the meaning of 'patient safety

  6. 34 CFR 668.49 - Institutional fire safety policies and fire statistics.

    Science.gov (United States)

    2010-07-01

    ... 34 Education 3 2010-07-01 2010-07-01 false Institutional fire safety policies and fire statistics... fire statistics. (a) Additional definitions that apply to this section. Cause of fire: The factor or...; however, it does not include indirect loss, such as business interruption. (b) Annual fire safety report...

  7. The Knowledge Management Research of Agricultural Scientific Research Institution

    Institute of Scientific and Technical Information of China (English)

    2010-01-01

    Based on the perception of knowledge management from experts specializing in different fields,and experts at home and abroad,the knowledge management of agricultural scientific research institution can build new platform,offer new approach for realization of explicit or tacit knowledge,and promote resilience and innovative ability of scientific research institution.The thesis has introduced functions of knowledge management research of agricultural science.First,it can transform the tacit knowledge into explicit knowledge.Second,it can make all the scientific personnel share knowledge.Third,it is beneficial to the development of prototype system of knowledge management.Fourth,it mainly researches the realization of knowledge management system.Fifth,it can manage the external knowledge via competitive intelligence.Sixth,it can foster talents of knowledge management for agricultural scientific research institution.Seventh,it offers the decision-making service for leaders to manage scientific program.The thesis also discusses the content of knowledge management of agricultural scientific research institution as follows:production and innovation of knowledge;attainment and organizing of knowledge;dissemination and share of knowledge;management of human resources and the construction and management of infrastructure.We have put forward corresponding countermeasures to further reinforce the knowledge management research of agricultural scientific research institution.

  8. Prospects for nuclear safety research

    Energy Technology Data Exchange (ETDEWEB)

    Beckjord, E.S.

    1995-04-01

    This document is the text of a paper presented by Eric S. Beckjord (Director, Nuclear Regulatory Research/NRC) at the 22nd Water Reactor Safety Meeting in Bethesda, MD in October 1994. The following topics are briefly reviewed: (1) Reactor vessel research, (2) Probabilistic risk assessment, (3) Direct containment heating, (4) Advanced LWR research, (5) Nuclear energy prospects in the US, and (6) Future nuclear safety research. Subtopics within the last category include economics, waste disposal, and health and safety.

  9. Progress of experimental research on nuclear safety in NPIC

    Energy Technology Data Exchange (ETDEWEB)

    Gong, Houjun; Zan, Yuanfeng; Peng, Chuanxin; Xi, Zhao; Zhang, Zhen; Wang, Ying; He, Yanqiu; Huang, Yanping [Nuclear Power Institute of China, Chengdu (China)

    2016-05-15

    Two kinds of Generation III commercial nuclear power plants have been developed in CNNC (China National Nuclear Corporation), one is a small modular reactor ACP100 having an equivalent electric power 100 MW, and the other is HPR1000 (once named ACP1000) having an equivalent electric power 1 000 MW. Both NPPs widely adopted the design philosophy of advanced passive safety systems and considered the lessons from Fukushima Daichi nuclear accident. As the backbone of the R and D of ACP100 and HPR1000, NPIC (Nuclear power Institute of China) has finished the engineering verification test of main safety systems, including passive residual heat removal experiments, reactor cavity injection experiments, hydrogen combustion experiments, and passive autocatalytic recombiner experiments. Above experimental work conducted in NPIC and further research plan of nuclear safety are introduced in this paper.

  10. 78 FR 51729 - Board of Scientific Counselors, National Institute for Occupational Safety and Health (BSC, NIOSH)

    Science.gov (United States)

    2013-08-21

    ... Scientific Counselors, National Institute for Occupational Safety and Health (BSC, NIOSH) In accordance with... demonstrations relating to occupational safety and health and to mine health. The Board of Scientific Counselors shall provide guidance to the Director, National Institute for Occupational Safety and Health on...

  11. Researchers' Roles in Patient Safety Improvement.

    Science.gov (United States)

    Pietikäinen, Elina; Reiman, Teemu; Heikkilä, Jouko; Macchi, Luigi

    2016-03-01

    In this article, we explore how researchers can contribute to patient safety improvement. We aim to expand the instrumental role researchers have often occupied in relation to patient safety improvement. We reflect on our own improvement model and experiences as patient safety researchers in an ongoing Finnish multi-actor innovation project through self-reflective narration. Our own patient safety improvement model can be described as systemic. Based on the purpose of the innovation project, our improvement model, and the improvement models of the other actors in the project, we have carried out a wide range of activities. Our activities can be summarized in 8 overlapping patient safety improvement roles: modeler, influencer, supplier, producer, ideator, reflector, facilitator, and negotiator. When working side by side with "practice," researchers are offered and engage in several different activities. The way researchers contribute to patient safety improvement and balance between different roles depends on the purpose of the study, as well as on the underlying patient safety improvement models. Different patient safety research paradigms seem to emphasize different improvement roles, and thus, they also face different challenges. Open reflection on the underlying improvement models and roles can help researchers with different backgrounds-as well as other actors involved in patient safety improvement-in structuring their work and collaborating productively.

  12. Progress of nuclear safety research. 2002

    Energy Technology Data Exchange (ETDEWEB)

    Anoda, Yoshinari; Kudo, Tamotsu; Tobita, Tohru (eds.) [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment] (and others)

    2002-11-01

    JAERI is conducting nuclear safety research primarily at the Nuclear Safety Research Center in close cooperation with the related departments in accordance with the Long Term Plan for Development and Utilization of Nuclear Energy and Annual Plan for Safety Research issued by the Japanese government. The fields of conducting safety research at JAERI are the engineering safety of nuclear power plants and nuclear fuel cycle facilities, and radioactive waste management as well as advanced technology for safety improvement or assessment. Also, JAERI has conducted international collaboration to share the information on common global issues of nuclear safety and to supplement own research. Moreover, when accidents occurred at nuclear facilities, JAERI has taken a responsible role by providing technical experts and investigation for assistance to the government or local public body. This report summarizes the nuclear safety research activities of JAERI from April 2000 through April 2002 and utilized facilities. This report also summarizes the examination of the ruptured pipe performed for assistance to the Nuclear and Industrial Safety Agency (NISA) for investigation of the accident at the Hamaoka Nuclear Power Station Unit-1 on November, 2001. (author)

  13. Research and development on reduced-moderation light water reactor with passive safety features (Contract research)

    International Nuclear Information System (INIS)

    Iwamura, Takamichi; Okubo, Tsutomu; Akie, Hiroshi; Kugo, Teruhiko; Yonomoto, Taisuke; Kureta, Masatoshi; Ishikawa, Nobuyuki; Nagaya, Yasunobu; Araya, Fumimasa; Okajima, Shigeaki; Okumura, Keisuke; Suzuki, Motoe; Mineo, Hideaki; Nakatsuka, Toru

    2004-06-01

    The present report contains the achievement of 'Research and Development on Reduced-moderation Light Water Reactor with Passive Safety Features', which was performed by Japan Atomic Energy Research Institute (JAERI), Hitachi Ltd., Japan Atomic Power Company and Tokyo Institute of Technology in FY2000-2002 as the innovative and viable nuclear energy technology (IVNET) development project operated by the Institute of Applied Energy (IAE). In the present project, the reduced-moderation water reactor (RMWR) has been developed to ensure sustainable energy supply and to solve the recent problems of nuclear power and nuclear fuel cycle, such as economical competitiveness, effective use of plutonium and reduction of spent fuel storage. The RMWR can attain the favorable characteristics such as high burnup, long operation cycle, multiple recycling of plutonium (Pu) and effective utilization of uranium resources based on accumulated LWR technologies. Our development target is 'Reduced-moderation Light Water Reactor with Passive Safety Features' with innovative technologies to achieve above mentioned requirement. Electric power is selected as 300 MWe considering anticipated size required for future deployment. The reactor core consists of MOX fuel assemblies with tight lattice arrangement to increase the conversion ratio. Design targets of the core specification are conversion ratio more than unity, negative void reactivity feedback coefficient to assure safety, discharged burnup more than 60 GWd/t and operation cycle more than 2 years. As for the reactor system, a small size natural circulation BWR with passive safety systems is adopted to increase safety and reduce construction cost. The results obtained are as follows: As regards core design study, core design was performed to meet the goal. Sequence of startup operation was constructed for the RMWR. As the plant design, plant system was designed to achieve enhanced economy using passive safety system effectively. In

  14. Activities of Nuclear Research Institute Rez in the area of hydrogen technologies

    International Nuclear Information System (INIS)

    Doucek, A.; Janik, L.; Misak, J.

    2010-01-01

    NRI is a research institution established in 1955. Nowadays, the Institute provides wide range of expertise and services for operators of the nuclear power plants in the Czech Republic and abroad, supports Czech central state institutions in the domains of strategic energy planning and development, management of radioactive waste (for the Ministry of Trade and Industry), provides independent expertise for the State Office of Nuclear Safety, performs activities in the area of exploitation of ionising radiation and irradiation services for basic and applied research, health service and industry, performs research and provides services for radioactive waste disposal, production of radiopharmaceuticals, education and training of experts and scientific specialists and performs many other activities. With the gradual changes in energy policy, hydrogen economy becomes one of the important topics related to nuclear energy. NRI is participating in the research and development in this area and as a member of the Czech Hydrogen Technology Platform is currently the leader in this area in the country. To promote hydrogen economy, NRI prepared and participated in several demonstration projects. Studies on production of hydrogen in current and future nuclear power plants are performed as well. (authors)

  15. Guidelines for the review research reactor safety. Reference document for IAEA Integrated Safety Assessment of Research Reactors (INSARR)

    International Nuclear Information System (INIS)

    1997-01-01

    In 1992, the IAEA published new safety standards for research reactors as part of the set of publications considered by its Research Reactor Safety Programme (RRSP). This set also includes publications giving guidance for all safety aspects related to the lifetime of a research reactor. In addition, the IAEA has also revised the Safety Standards for radiation protection. Consequently, it was considered advisable to revise the Integrated Safety Assessment of Research Reactors (INSARR) procedures to incorporate the new requirements and guidance as well as to extend the scope of the safety reviews to currently operating research reactors. The present report is the result of this revision. The purpose of this report is to give guidance on the preparation, execution, reporting and follow-up of safety review mission to research reactors as conducted by the IAEA under its INSARR missions safety service. However, it will also be of assistance to operators and regulators in conducting: (a) ad hoc safety assessments of research reactors to address individual issues such as ageing or safety culture; and (b) other types of safety reviews such as internal and peer reviews and regulatory inspections

  16. Vision of the Training Department of the National Institute of Nuclear Research

    International Nuclear Information System (INIS)

    Dominguez A, C. E.

    2008-12-01

    The availability of skilled personnel is an essential element of the national infrastructure, to ensure the safety and security through the strong principles of management and good technology, quality assurance, training and qualification of new personnel, thorough safety evaluations and building on lessons of experience and research. In the national case the General Regulation of Radiation Safety requires that the Radiation Safety Responsible (RSR) must be experienced in issues of radiation safety of the facility in which employed. As experience has been found by chance that some people who have attended courses offered by the National Institute of Nuclear Research and have not achieved a result approval, obtain approval at the respective courses offered by other entities, which may have a potential dilemma (not at all cases since then), in the sense that the aspiration to become experts in the safety basic standards, can be addressed only after ensuring that there is an acceptance at the level of the course and evaluation ways of the present courses to RSR. Viewed another way, one can consider the formation of RSR experience in planning for better training of experts in the safety basic standards. It happens that the courses offered to RSR some of them do not cover the requirements of time, content and practices established in the regulations. The Mexican Society of Radiological Safety can affect as a partner to improve the courses quality. (Author)

  17. IAEA programme on research reactor safety

    International Nuclear Information System (INIS)

    Alcala, F.; Di Meglio, A.F.

    1995-01-01

    This paper describes the IAEA programme on research reactor safety and includes the safety related areas of conversions to the use of low enriched uranium (LEU) fuel. The program is based on the IAEA statutory responsibilities as they apply to the requirements of over 320 research reactors operating around the world. The programme covers four major areas: (a) the development of safety documents; (b) safety missions to research reactor facilities; (c) support of research programmes on research reactor safety; (d) support of Technical Cooperation projects on research reactor safety issues. The demand for these activities by the IAEA member states has increased substantially in recent years especially in developing countries with increasing emphasis being placed on LEU conversion matters. In response to this demand, the IAEA has undertaken an extensive programme for each of the four areas above. (author)

  18. Do Research Participants Trust Researchers or Their Institution?

    Science.gov (United States)

    Guillemin, Marilys; Barnard, Emma; Allen, Anton; Stewart, Paul; Walker, Hannah; Rosenthal, Doreen; Gillam, Lynn

    2018-07-01

    Relationships of trust between research participants and researchers are often considered paramount to successful research; however, we know little about participants' perspectives. We examined whom research participants trusted when taking part in research. Using a qualitative approach, we interviewed 36 research participants, including eight Indigenous participants. Thematic analysis was used to analyze the data. This article focuses on findings related to non-Indigenous participants. In contrast to Indigenous participants, non-Indigenous participants placed their trust in research institutions because of their systems of research ethics, their reputation and prestige. Researchers working in non-Indigenous contexts need to be cognizant that the trust that participants place in them is closely connected with the trust that participants have in the institution.

  19. Low Vision Research at the Schepens Eye Research Institute

    National Research Council Canada - National Science Library

    D'Amore, Patricia

    2003-01-01

    This research proposal, Low Vision at the Schepens Eye Research Institute, is a collaborative effort on the part of four Investigators at the Institute whose goal is to advance the studies on low vision...

  20. Progress of nuclear safety research. 2003

    International Nuclear Information System (INIS)

    Anoda, Yoshinari; Amagai, Masaki; Tobita, Tohru

    2004-03-01

    JAERI is conducting nuclear safety research primarily at the Nuclear Safety Research Center in close cooperation with the related departments in accordance with the Long Term Plan for Development and Utilization of Nuclear Energy and Annual Plan for Safety Research issued by the Japanese government. The fields of conducting safety research at JAERI are the engineering safety of nuclear power plants and nuclear fuel cycle facilities, and radioactive waste management as well as advanced technology for safety improvement or assessment. Also, JAERI has conducted international collaboration to share the information on common global issues of nuclear safety and to supplement own research. Moreover, when accidents occurred at nuclear facilities, JAERI has taken a responsible role by providing technical experts and investigation for assistance to the government or local public body. This report summarizes the nuclear safety research activities of JAERI from April 2001 through March 2003 and utilized facilities. This report also summarizes the examination of the ruptured pipe performed for assistance to the Nuclear and Industrial Safety Agency (NISA) for investigation of the accident at the Hamaoka Nuclear Power Station Unit-1 on November, 2001, and the integrity evaluation of cracked core shroud of BWRs of the Tokyo Electric Power Company performed for assistance to the Nuclear Safety Commission in reviewing the evaluation reports by the licensees. (author)

  1. SAFIR2014. The Finnish Research Programme on Nuclear Power Plant Safety 2011-2014. Interim Report

    Energy Technology Data Exchange (ETDEWEB)

    Simola, K. [ed.

    2013-02-15

    The Finnish Nuclear Power Plant Safety Research Programme 2011-2014, SAFIR2014, is a 4-year publicly funded national technical and scientific research programme on the safety of nuclear power plants. The programme is funded by the State Nuclear Waste Management Fund (VYR), as well as other key organisations operating in the area of nuclear energy. The programme provides the necessary conditions for retaining knowledge needed for ensuring the continuance of safe use of nuclear power, for developing new know-how and for participation in international co-operation. The SAFIR2014 Steering Group, responsible of the strategic alignements of the programme, consists of representatives of the Finnish Nuclear Safety Authority (STUK), Ministry of Employment and the Economy (MEE), Technical Research Centre of Finland (VTT), Teollisuuden Voima Oyj (TVO), Fortum Power and Heat Oy (Fortum), Fennovoima Oy, Lappeenranta University of Technology (LUT), Aalto University (Aalto), Finnish Funding Agency for Technology and Innovation (Tekes), Finnish Institute of Occupational Health (TTL) and the Swedish Radiation Safety Authority (SSM). The research programme is divided into nine areas: Man, organisation and society, Automation and control room, Fuel research and reactor analysis, Thermal hydraulics, Severe accidents, Structural safety of reactor circuits, Construction safety, Probabilistic risk analysis (PRA), and Development of research infrastructure. A reference group is assigned to each of these areas to respond for the strategic planning and to supervise the projects in its respective field. Research projects are selected annually based on a public call for proposals. Most of the projects are planned for the entire duration of the programme, but there can also be shorter one- or two-year projects. The annual volume of the SAFIR2014 programme in 2011-2012 has been 9,5-9,9 M euro. Main funding organisations were the State Nuclear Waste Management Fund (VYR) with over 5 M euro and

  2. SAFIR2014. The Finnish Research Programme on Nuclear Power Plant Safety 2011-2014. Interim Report

    International Nuclear Information System (INIS)

    Simola, K.

    2013-02-01

    The Finnish Nuclear Power Plant Safety Research Programme 2011-2014, SAFIR2014, is a 4-year publicly funded national technical and scientific research programme on the safety of nuclear power plants. The programme is funded by the State Nuclear Waste Management Fund (VYR), as well as other key organisations operating in the area of nuclear energy. The programme provides the necessary conditions for retaining knowledge needed for ensuring the continuance of safe use of nuclear power, for developing new know-how and for participation in international co-operation. The SAFIR2014 Steering Group, responsible of the strategic alignements of the programme, consists of representatives of the Finnish Nuclear Safety Authority (STUK), Ministry of Employment and the Economy (MEE), Technical Research Centre of Finland (VTT), Teollisuuden Voima Oyj (TVO), Fortum Power and Heat Oy (Fortum), Fennovoima Oy, Lappeenranta University of Technology (LUT), Aalto University (Aalto), Finnish Funding Agency for Technology and Innovation (Tekes), Finnish Institute of Occupational Health (TTL) and the Swedish Radiation Safety Authority (SSM). The research programme is divided into nine areas: Man, organisation and society, Automation and control room, Fuel research and reactor analysis, Thermal hydraulics, Severe accidents, Structural safety of reactor circuits, Construction safety, Probabilistic risk analysis (PRA), and Development of research infrastructure. A reference group is assigned to each of these areas to respond for the strategic planning and to supervise the projects in its respective field. Research projects are selected annually based on a public call for proposals. Most of the projects are planned for the entire duration of the programme, but there can also be shorter one- or two-year projects. The annual volume of the SAFIR2014 programme in 2011-2012 has been 9,5-9,9 M euro. Main funding organisations were the State Nuclear Waste Management Fund (VYR) with over 5 M euro and

  3. Selecting of key safety parameters in reactor nuclear safety supervision

    International Nuclear Information System (INIS)

    He Fan; Yu Hong

    2014-01-01

    The safety parameters indicate the operational states and safety of research reactor are the basis of nuclear safety supervision institution to carry out effective supervision to nuclear facilities. In this paper, the selecting of key safety parameters presented by the research reactor operating unit to National Nuclear Safety Administration that can express the research reactor operational states and safety when operational occurrence or nuclear accident happens, and the interrelationship between them are discussed. Analysis shows that, the key parameters to nuclear safety supervision of research reactor including design limits, operational limits and conditions, safety system settings, safety limits, acceptable limits and emergency action level etc. (authors)

  4. IRSN safety research carried out for reviewing safety cases

    International Nuclear Information System (INIS)

    Serres, Ch.

    2010-01-01

    Christophe Serres from IRSN (France) described the independent role of the IRSN regarding research related to nuclear safety in the context of the French Planning Act of 28 June 2006 foreseeing a licence application to be submitted in 2015 for the creation of a deep geological repository. IRSN research programme is organised along research activities devoted to addressing independently-identified k ey safety issues . These 'key issues' should also be of prime concern for the implementer since they relate to the demonstration of the overall safety of the repository, and the level of funding that the implementer should afford to research activities of concern for safety. He explained that the quality and independency of the research programme carried out by IRSN allow building and improving a set of scientific knowledge and technical skills that serves the public mission of delivering technical appraisal and advice, e.g., on behalf of the national safety authority. In particular they contribute to improving the decisional process by making possible scientific dialogue with stakeholders independently from regulator or implementer. The current IRSN R and D programme is developed along the following lines: - Test the adequacy of experimental methods for which feedback is not sufficient. - Develop basic scientific knowledge in the fields where there is a need for better understanding of complex phenomena and interactions. - Develop and use numerical modelling tools to support studies on complex phenomena and interactions. - Perform specific experimental tests aiming at assessing the key parameters that may warrant the performances of the different components of the repository. These studies are carried out by means of experiments performed either at IRSN surface laboratories, or in the Tournemire Experimental Station (TES), an underground facility operated by IRSN in the south-east of France. Targeted actions on research related to operational safety and reversibility

  5. Environment and safety research status report: 1993

    International Nuclear Information System (INIS)

    1993-03-01

    The 1993 status report discusses ongoing and planned research activities in the GRI Environment and Safety Program. The objectives and goals, accomplishments, and strategy along with the basis for each project area are presented for the supply, end use, and gas operations subprograms. Within the context of these subprograms, contract status summaries under their conceptual titles are given for the following project areas: Gas Supply Environmental and Safety Research, Air Quality Research, End Use Equipment Safety Research, Gas Operations Safety Research, Liquefied Natural Gas, Safety Research, and Gas Operations Environmental Research

  6. Reactor safety research and safety technology. Pt. 2

    International Nuclear Information System (INIS)

    Theenhaus, R.; Wolters, J.

    1987-01-01

    The state of HTR safety research work reached permits a comprehensive and reliable answer to be given to questions which have been raised by the reactor accident at Chernobyl, regarding HTR safety. Together with the probability safety analyses, the way to a safety concept suitable for an HTR is cleared; instructions are given for design optimisation with regard to safety technique and economy. The consequences of a graphite fire, the neutron physics design and the consequenes of the lack of a safety containment are briefly described. (DG) [de

  7. Report on results of research and development work carried out in 1979 by the Institut fuer Neutronenphysik und Reaktortechnik

    International Nuclear Information System (INIS)

    1980-02-01

    The activities of the INR concentrate on problems in nuclear technology, especially on problems encountered in the development of sodium-cooled fast reactors. Most of the work is carried out under the roof of projects in cooperation with other institutes or industrial research groups. The studies performed within the fast-breeder project (PSB) relate to reactor physics, design data and safety problems of fast reactors. The environmental impacts of nuclear reactors in case of accidents are investigated by the Institute within the framework of the nuclear safety project (PNS), whereas the problems to be studied for the reprocessing project (PWA) relate to the activity inventary and to instrument development. Another main field of interest is nuclear safeguards, the Institute being concerned with the isotope correlation technique and its application. For the fusion reactor technology project, the research work carried out by the Institute deals with fusion techniques using inertial confinement. (orig./HP) [de

  8. Results on safety research for five years (from fiscal year 1996 to 2000). A field of power reactors

    International Nuclear Information System (INIS)

    2001-10-01

    This safety research carried out by the Japan Nuclear Cycle Development Institute (JNC) for five years ranged from 1996 to 2000 fiscal year, was performed according to the safety research basic plan (from 1996 to 2000 fiscal year) established on March, 1996 (revised again on May, 2000). This report was arranged on a field on power reactors (all subjects on fields of advanced conversion reactor and a subject on power reactor in a field of seismic resistant and probability theoretical safety evaluation) by combining its research results for five years ranged from 1996 to 2000 fiscal year with general outlines on the safety research basic plan. Here were shown outlines on the safety research basic plan, aims and subjects on safety research at a field of power reactors, a list of survey sheets on safety research result, and survey sheets on safety research results. The survey sheets containing research field, title, organization, researcher name, researching period, names of cooperative organization, using facilities, research outline, research results, established contents, application, and research trends, are ranged to 5 items on advanced conversion reactor, 29 items on high breeder reactor, 1 item on seismic resistance, and 5 items on probability theoretical safety evaluation. (G.K.)

  9. Institutional Support : Ethiopian Development Research Institute ...

    International Development Research Centre (IDRC) Digital Library (Canada)

    The Ethiopian Development Research Institute (EDRI) was established in 1999 and became operational in 2003 as a semi-autonomous organization accountable to ... International Water Resources Association, in close collaboration with IDRC, is holding a webinar titled “Climate change and adaptive water management: ...

  10. List of reports from reactor safety research of BMFT, USNRC, EPRI and JSTA

    International Nuclear Information System (INIS)

    1979-01-01

    This list reviews reports from the Federal Republic of Germany, from the USA and from Japan concerning special problems in the field of Reactor Safety Research. According to the cooperation of the Bundesminister fuer Forschung und Technologie (BMFT) with the USNRC, the Electric Power Research Institute (EPRI), and the Japan Science and Technology Agency (JSTA) these reports are available in the Gesellschaft fuer Reaktorsicherheit. The list pursues the following order: Country of origin, problem area concerned, according to the Reactor Safety Research Program of BMFT, reporting organisation. The list of reports appears quarterly. Requests for reports should be adressed to GRS, Forschungsbetreuung. Contractual view points have to be considered for the distribution of the reports. (orig./HP) [de

  11. List of reports from reactor safety research of BMFT, USNRC, EPRI and JSTA

    International Nuclear Information System (INIS)

    1978-12-01

    This list reviews reports from the Federal Republic of Germany, from the USA and from Japan concerning special problems in the field of Reactor Safety Research. According to the cooperation of the Bundesminister fuer Forschung und Technologie (BMFT) with the USNRC, the Electric Power Research Institute (EPRI), and the Japan Science and Technology Agency (JSTA) these reports are available in the Gesellschaft fuer Reaktorsicherheit. The list pursues the following order: Country of origin, problem area concerned, according to the Reactor Safety Research Program of BMFT, reporting organisation. The list of reports appears quarterly. Requests for reports should be addressed to GRS, Forschungsbetreuung. Contractual view points have to be considered for the distribution of the reports. (orig./HP) [de

  12. List of reactor safety research reports from BMFT, CEA, EPRI, JSTA and USNRC

    International Nuclear Information System (INIS)

    1982-07-01

    This list reviews reports from the Federal Republic of Germany, from France, from Japan and from the United States of America concerning special Problems in the field of Reactor Safety Research. According to the cooperation of the Bundesminister fuer Forschung und Technologie (BMFT) with the Commissariat a l'Energie Atomique (CEA), the Japan Science and Technologie Agency (JSTA), the Electric Power Research Institute (EPRI) and the United States Nuclear Regulatory Commission, these Reports are available in the Gesellschaft fuer Reaktorsicherheit (GRS). The list pursues the following order: Country of origin, problem area concerned, according to the Reactor Safety Research Program of the BMFT, reporting organization. The list of reports appears quarterly. (orig./HP) [de

  13. Road safety knowledge and policy : a historical institutional analysis of the Netherlands.

    NARCIS (Netherlands)

    Bax, C. Leroy, P. & Hagenzieker, M.P.

    2014-01-01

    This paper explores the institutional development of Dutch road safety policy over the last century and the role of knowledge therein. After a theoretical exploration of the concept of institutionalization, the article sketches an overview of the institutionalization of road safety policy in the

  14. Research misconduct definitions adopted by U.S. research institutions.

    Science.gov (United States)

    Resnik, David B; Neal, Talicia; Raymond, Austin; Kissling, Grace E

    2015-01-01

    In 2000, the U.S. federal government adopted a uniform definition of research misconduct as fabrication, falsification, or plagiarism (FFP), which became effective in 2001. Institutions must apply this definition of misconduct to federally-funded research to receive funding. While institutions are free to adopt definitions of misconduct that go beyond the federal standard, it is not known how many do. We analyzed misconduct policies from 183 U.S. research institutions and coded them according to thirteen different types of behavior mentioned in the misconduct definition. We also obtained data on the institution's total research funding and public vs. private status, and the year it adopted the definition. We found that more than half (59%) of the institutions in our sample had misconduct policies that went beyond the federal standard. Other than FFP, the most common behaviors included in definitions were "other serious deviations" (45.4%), "significant or material violations of regulations" (23.0%), "misuse of confidential information" (15.8%), "misconduct related to misconduct" (14.8%), "unethical authorship other than plagiarism" (14.2%), "other deception involving data manipulation" (13.1%), and "misappropriation of property/theft" (10.4%). Significantly more definitions adopted in 2001 or later went beyond the federal standard than those adopted before 2001 (73.2% vs. 26.8%), and significantly more definitions adopted by institutions in the lower quartile of total research funding went beyond the federal standard than those adopted by institutions in the upper quartiles. Public vs. private status was not significantly associated with going beyond the federal standard.

  15. Experimental research progress on passive safety systems of Chinese advanced PWR

    International Nuclear Information System (INIS)

    Xiao Zejun; Zhuo Wenbin; Zheng Hua; Chen Bingde; Zong Guifang; Jia Dounan

    2003-01-01

    TMI and Chernobyl accidents, having pronounced impact on nuclear industries, triggered the governments as well as interested institutions to devote much attention to the safety of nuclear power plant and public's requirements on nuclear power plant safety were also going to be stricter and stricter. It is obvious that safety level of an ordinary light water reactor is no longer satisfactory to these requirements. Recently, the safety authorities have recommended the implementation of passive system to improve the safety of nuclear reactors. Passive safety system is one of the main differences between Chinese advanced PWR and other conventional PWR. The working principle of passive safety system is to utilize the gravity, natural convection (natural circulation) and stored energy to implement the system's safety function. Reactors with passive safety systems are not only safer, but also more economical. The passive safety system of Chinese advanced PWR is composed of three independent systems, i.e. passive containment cooling system, passive residual heat removal system and passive core makeup tank injection system. This paper is a summary of experimental research progress on passive containment cooling system, passive residual heat removal system and passive core makeup tank injection system

  16. Causes of extended shutdown state of 'RA' research reactor in Vinca Institute

    International Nuclear Information System (INIS)

    Pesic, M.; Kolundzija, V.; Ljubenov, V.; Cupac, S.

    2001-01-01

    This paper describes the causes and reasons for extended shutdown state of RA research reactor in the 'Vinca' Institute of Nuclear Sciences. Technical and legal matters that led to decision to stop RA reactor operation in 1984 and further problems related to maintenance and preparation for continuation of operation are given. Influence of nuclear policy of Yugoslav government and the 'Vinca' Institute at prolongation of the reactor shutdown state, as consequence of changing of nuclear programme in the country and the world are discussed and underlined. An overview of the legislation in the field of nuclear safety and regulatory control of radiation sources and radioactive materials in Yugoslavia is presented. (author)

  17. Developing the Safety of Atrial Fibrillation Ablation Registry Initiative (SAFARI) as a collaborative pan-stakeholder critical path registry model: a Cardiac Safety Research Consortium "Incubator" Think Tank.

    Science.gov (United States)

    Al-Khatib, Sana M; Calkins, Hugh; Eloff, Benjamin C; Kowey, Peter; Hammill, Stephen C; Ellenbogen, Kenneth A; Marinac-Dabic, Danica; Waldo, Albert L; Brindis, Ralph G; Wilbur, David J; Jackman, Warren M; Yaross, Marcia S; Russo, Andrea M; Prystowsky, Eric; Varosy, Paul D; Gross, Thomas; Pinnow, Ellen; Turakhia, Mintu P; Krucoff, Mitchell W

    2010-10-01

    Although several randomized clinical trials have demonstrated the safety and efficacy of catheter ablation of atrial fibrillation (AF) in experienced centers, the outcomes of this procedure in routine clinical practice and in patients with persistent and long-standing persistent AF remain uncertain. Brisk adoption of this therapy by physicians with diverse training and experience highlights potential concerns regarding the safety and effectiveness of this procedure. Some of these concerns could be addressed by a national registry of AF ablation procedures such as the Safety of Atrial Fibrillation Ablation Registry Initiative that was initially proposed at a Cardiac Safety Research Consortium Think Tank meeting in April 2009. In January 2010, the Cardiac Safety Research Consortium, in collaboration with the Duke Clinical Research Institute, the US Food and Drug Administration, the American College of Cardiology, and the Heart Rhythm Society, held a follow-up meeting of experts in the field to review the construct and progress to date. Other participants included the National Heart, Lung, and Blood Institute; the Centers for Medicare and Medicaid Services; the Agency for Healthcare Research and Quality; the AdvaMed AF working group; and additional industry representatives. This article summarizes the discussions that occurred at the meeting of the state of the Safety of Atrial Fibrillation Ablation Registry Initiative, the identification of a clear pathway for its implementation, and the exploration of solutions to potential issues in the execution of this registry. Copyright © 2010 Mosby, Inc. All rights reserved.

  18. Research at the Paul Scherrer Institut

    International Nuclear Information System (INIS)

    Walter, H.K.

    1996-01-01

    The Paul Scherrer Institut (PSI) is a multidisciplinary research institute for natural sciences and technology. In national and international collaboration with universities, other research institutes and industry, PSI is active in elementary particle physics, life sciences, solid-state physics, material sciences, nuclear and non-nuclear energy research, and energy-related ecology. PSI's priorities lie in research fields which are relevant to sustainable development, serve educational needs and are beyond the possibilities of a single university department. PSI develops and operates complex research installations open of the world's most powerful cyclotron, allowing to operate high intensity secondary pion and muon beams, a neutron spallation source and various applications in medicine and materials research. A short review on research at PSI is presented, with special concentration on particle physics experiments. (author)

  19. 78 FR 40146 - Patient Safety Organizations: Voluntary Relinquishment From Northern Metropolitan Patient Safety...

    Science.gov (United States)

    2013-07-03

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES Agency for Healthcare Research and Quality Patient Safety Organizations: Voluntary Relinquishment From Northern Metropolitan Patient Safety Institute AGENCY: Agency for Healthcare Research and Quality (AHRQ), HHS. ACTION: Notice of Delisting. SUMMARY: The Patient Safety and...

  20. Reviewing the impact of organisational factors on nuclear power plants safety. A Spanish research initiative

    International Nuclear Information System (INIS)

    Sola, R.; Garces, M.I.; Vaquero, C.; Sendio, F.; De la Cal, C.; Villadoniga, J.I.

    2000-01-01

    This paper describes the Spanish R and D project 'Development of methods to evaluate and model the impact of organisation on nuclear power plants safety' framed in an specific agreement among UNESA (Association of Spanish Utilities), CSN (Spanish Nuclear Safety Council) and CIEMAT (Research Centre for Energy, Environment and Technology), being this last one the institution in charge of the development of the research activities. The main goal of the proposed project is to increase the knowledge related the way nuclear power plants organise and manage their activities to enhance safety. This goal will be achieved through three perspectives: the development of preventive and corrective methodologies and the development of models to incorporate the organisation and management in the probabilistic safety assessment, PSA. (author)

  1. Safety in the Utilization and Modification of Research Reactors. Specific Safety Guide

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2012-07-15

    This Safety Guide is a revision of Safety Series No. 35-G2 on safety in the utilization and modification of research reactors. It provides recommendations on meeting the requirements for the categorization, safety assessment and approval of research reactor experiments and modification projects. Specific safety considerations in different phases of utilization and modification projects are covered, including the pre-implementation, implementation and post-implementation phases. Guidance is also provided on the operational safety of experiments, including in the handling, dismantling, post-irradiation examination and disposal of experimental devices. Examples of the application of the safety categorization process for experiments and modification projects and of the content of the safety analysis report for an experiment are also provided. Contents: 1. Introduction; 2. Management system for the utilization and modification of a research reactor; 3. Categorization, safety assessment and approval of an experiment or modification; 4. Safety considerations for the design of an experiment or modification; 5. Pre-implementation phase of a modification or utilization project; 6. Implementation phase of a modification or utilization project; 7. Post-implementation phase of a utilization or modification project; 8. Operational safety of experiments at a research reactor; 9. Safety considerations in the handling, dismantling, post-irradiation examination and disposal of experimental devices; 10. Safety aspects of out-of-reactor-core installations; Annex I: Example of a checklist for the categorization of an experiment or modification at a research reactor; Annex II: Example of the content of the safety analysis report for an experiment at a research reactor; Annex III: Examples of reasons for a modification at a research reactor.

  2. Safety in the Utilization and Modification of Research Reactors. Specific Safety Guide

    International Nuclear Information System (INIS)

    2012-01-01

    This Safety Guide is a revision of Safety Series No. 35-G2 on safety in the utilization and modification of research reactors. It provides recommendations on meeting the requirements for the categorization, safety assessment and approval of research reactor experiments and modification projects. Specific safety considerations in different phases of utilization and modification projects are covered, including the pre-implementation, implementation and post-implementation phases. Guidance is also provided on the operational safety of experiments, including in the handling, dismantling, post-irradiation examination and disposal of experimental devices. Examples of the application of the safety categorization process for experiments and modification projects and of the content of the safety analysis report for an experiment are also provided. Contents: 1. Introduction; 2. Management system for the utilization and modification of a research reactor; 3. Categorization, safety assessment and approval of an experiment or modification; 4. Safety considerations for the design of an experiment or modification; 5. Pre-implementation phase of a modification or utilization project; 6. Implementation phase of a modification or utilization project; 7. Post-implementation phase of a utilization or modification project; 8. Operational safety of experiments at a research reactor; 9. Safety considerations in the handling, dismantling, post-irradiation examination and disposal of experimental devices; 10. Safety aspects of out-of-reactor-core installations; Annex I: Example of a checklist for the categorization of an experiment or modification at a research reactor; Annex II: Example of the content of the safety analysis report for an experiment at a research reactor; Annex III: Examples of reasons for a modification at a research reactor.

  3. Research for enhancing reactor safety

    International Nuclear Information System (INIS)

    1989-05-01

    Recent research for enhanced reactor safety covers extensive and numerous experiments and computed modelling activities designed to verify and to improve existing design requirements. The lectures presented at the meeting report GRS research results and the current status of reactor safety research in France. The GRS experts present results concerning expert systems and their perspectives in safety engineering, large-scale experiments and their significance in the development and verification of computer codes for thermohydraulic modelling of safety-related incidents, the advanced system code ATHLET for analysis of thermohydraulic processes of incidents, the analysis simulator which is a tool for fast evaluation of accident management measures, and investigations into event sequences and the required preventive emergency measures within the German Risk Study. (DG) [de

  4. Teaching and Research at Undergraduate Institutions

    Science.gov (United States)

    Garg, Shila

    2006-03-01

    My own career path has been non-traditional and I ended up at a primarily undergraduate institution by pure accident. However, teaching at a small college has been extremely rewarding to me, since I get to know and interact with my students, have an opportunity to work with them one-on-one and promote their intellectual growth and sense of social responsibility. One of the growing trends at undergraduate institutions in the past decade has been the crucial role of undergraduate research as part of the teaching process and the training of future scientists. There are several liberal arts institutions that expect research-active Faculty who can mentor undergraduate research activities. Often faculty members at these institutions consider their roles as teacher-scholars with no boundary between these two primary activities. A researcher who is in touch with the developments in his/her own field and contributes to new knowledge in the field is likely to be a more exciting teacher in the classroom and share the excitement of discovery with the students. At undergraduate institutions, there is generally very good support available for faculty development projects in both teaching and research. Often, there is a generous research leave program as well. For those who like advising and mentoring undergraduates and a teaching and learning centered paradigm, I will recommend a career at an undergraduate institution. In my presentation, I will talk about how one can prepare for such a career.

  5. The ICRP 66 Internal Radiation Exposure Control and Dose Evaluation of The Institute of Nuclear Energy Research

    Energy Technology Data Exchange (ETDEWEB)

    Pang, H. F.; Hwang, W. S.; Chiu, J. H.

    2004-07-01

    The Atomic Energy Council (AEC) is the regulatory body of ionization radiation protection in Taiwan. To effectively control the safety in ionization radiation, AEC brought into force the Ionization Radiation Protection Act on 1 February, 2003 with clear statements of the penalty for violating the Law. The Article 5 of the Act provides: In order to limit the radiation exposure from radiation sources or practices, the Competent Authority shall refer to the latest standards of the International Commission on Radiological Protection to lay down the Safety Standards for Protection against Ionizing Radiation. Thus, AEC is going to draft new safety standards of ionization radiation protection of Taiwan according to ICRP Publication 60. The Institute of Nuclear Energy Research (INER), the governmental institute working on ionization radiation research in Taiwan, took the responsibility of assisting AEC in establishing guidelines on the control of internal radiation exposure and responding to the regulations in the new standards as soon as possible. So, according to the recommendations of ICRP Publications 60, 66,67,68,69,71,78,88, and IAEA Safety Standard Series No. RS-G- 1.1 and 1.2, INER undertook researches on the internal radiation exposure control and dose evaluations for INER's radiation workers as well as dose evaluations for the general public. The research accomplishments not only can be the reference of AEC when making new standards, but also can be followed by other radiation protection businesses. (Author) 23 refs.

  6. The ICRP 66 Internal Radiation Exposure Control and Dose Evaluation of The Institute of Nuclear Energy Research

    International Nuclear Information System (INIS)

    Pang, H. F.; Hwang, W. S.; Chiu, J. H.

    2004-01-01

    The Atomic Energy Council (AEC) is the regulatory body of ionization radiation protection in Taiwan. To effectively control the safety in ionization radiation, AEC brought into force the Ionization Radiation Protection Act on 1 February, 2003 with clear statements of the penalty for violating the Law. The Article 5 of the Act provides: In order to limit the radiation exposure from radiation sources or practices, the Competent Authority shall refer to the latest standards of the International Commission on Radiological Protection to lay down the Safety Standards for Protection against Ionizing Radiation. Thus, AEC is going to draft new safety standards of ionization radiation protection of Taiwan according to ICRP Publication 60. The Institute of Nuclear Energy Research (INER), the governmental institute working on ionization radiation research in Taiwan, took the responsibility of assisting AEC in establishing guidelines on the control of internal radiation exposure and responding to the regulations in the new standards as soon as possible. So, according to the recommendations of ICRP Publications 60, 66,67,68,69,71,78,88, and IAEA Safety Standard Series No. RS-G- 1.1 and 1.2, INER undertook researches on the internal radiation exposure control and dose evaluations for INER's radiation workers as well as dose evaluations for the general public. The research accomplishments not only can be the reference of AEC when making new standards, but also can be followed by other radiation protection businesses. (Author) 23 refs

  7. Researches in nuclear safety

    International Nuclear Information System (INIS)

    Souchet, Y.

    2009-01-01

    This article comprises three parts: 1 - some general considerations aiming at explaining the main motivations of safety researches, and at briefly presenting the important role of some organisations in the international conciliation, and the most common approach used in safety researches (analytical experiments, calculation codes, global experiments); 2 - an overview of some of the main safety problems that are the object of worldwide research programs (natural disasters, industrial disasters, criticality, human and organisational factors, fuel behaviour in accidental situation, serious accidents: core meltdown, corium spreading, failure of the confinement building, radioactive releases). Considering the huge number of research topics, this part cannot be exhaustive and many topics are not approached; 3 - the presentation of two research programs addressing very different problems: the evaluation of accidental releases in the case of a serious accident (behaviour of iodine and B 4 C, air infiltration, fission products release) and the propagation of a fire in a facility (PRISME program). These two programs belong to an international framework involving several partners from countries involved in nuclear energy usage. (J.S.)

  8. Research on review technology for three key safety factors of periodic safety review (PSR) and its application to Qinshan Nuclear Power Plant

    International Nuclear Information System (INIS)

    Xu Shoulv; Yao Weida; Dou Yikang; Lin Shaoxuan; Cao Yenan; Zhou Quanfu; Zheng Jiong; Zhang Ming

    2009-04-01

    In 2001, after 10 years' operation, Qinshan Nuclear Power Plant (Q1) started to carry out periodic safety review (PSR) based on a nuclear safety guideline, Periodic Safety Review for Operational Nuclear Power Plants (HAF0312), issued by National Nuclear Safety Administration of China (NNSA). Entrusted by the owner of Q1, Shanghai Nuclear Engineering Research and Design Institute (SNERDI) implemented reviews of three key safety factors including safety analysis, equipment qualification and ageing. PSR was a challenging work in China at that time and through three years' research and practice, SNERDI summarized a systematic achievement for the review including review methodology, scoping, review contents and implementation steps, etc.. During the process of review for the three safety factors, totally 148 review reports and 341 recommendations for corrections were submitted to Q1. These reports and recommendations have provided guidance for correction actions as follow-up of PSR. This paper focuses on technical aspects to carry out PSR for the above-mentioned three safety factors, including review scoping, contents, methodology and main steps. The review technology and relevant experience can be taken for reference for other NPPs to carry out PSR. (authors)

  9. Guidelines for the Review of Research Reactor Safety: Revised Edition. Reference Document for IAEA Integrated Safety Assessment of Research Reactors (INSARR)

    International Nuclear Information System (INIS)

    2013-01-01

    The Integrated Safety Assessment of Research Reactors (INSARR) is an IAEA safety review service available to Member States with the objective of supporting them in ensuring and enhancing the safety of their research reactors. This service consists of performing a comprehensive peer review and an assessment of the safety of the respective research reactor. The reviews are based on IAEA safety standards and on the provisions of the Code of Conduct on the Safety of Research Reactors. The INSARR can benefit both the operating organizations and the regulatory bodies of the requesting Member States, and can include new research reactors under design or operating research reactors, including those which are under a Project and Supply Agreement with the IAEA. The first IAEA safety evaluation of a research reactor operated by a Member State was completed in October 1959 and involved the Swiss 20 MW DIORIT research reactor. Since then, and in accordance with its programme on research reactor safety, the IAEA has conducted safety review missions in its Member States to enhance the safety of their research reactor facilities through the application of the Code of Conduct on the Safety of Research Reactors and the relevant IAEA safety standards. About 320 missions in 51 Member States were undertaken between 1972 and 2012. The INSARR missions and other limited scope safety review missions are conducted following the guidelines presented in this publication, which is a revision of Guidelines for the Review of Research Reactor Safety (IAEA Services Series No. 1), published in December 1997. This publication details those IAEA safety standards and guidance publications relevant to the safety of research reactors that have been revised or published since 1997. The purpose of this publication is to give guidance on the preparation, implementation, reporting and follow-up of safety review missions. It is also intended to be of assistance to operators and regulators in conducting

  10. Institutional Repositories in Indian Universities and Research Institutes: A Study

    Science.gov (United States)

    Krishnamurthy, M.; Kemparaju, T. D.

    2011-01-01

    Purpose: The purpose of this paper is to report on a study of the institutional repositories (IRs) in use in Indian universities and research institutes. Design/methodology/approach: Repositories in various institutions in India were accessed and described in a standardised way. Findings: The 20 repositories studied covered collections of diverse…

  11. Nuclear safety research

    International Nuclear Information System (INIS)

    1999-01-01

    The NNSA checked and coordinated in 1999 the research project of the Surveillance Technology on Nuclear Installations under the National 9th-Five-Year Program to promote the organizations that undertake the research work on schedule and lay a foundation of obtaining achievements and effectiveness for the 9th-five-year plan on nuclear safety research

  12. Report on research and development activities in 1983 of the Institut fuer Reaktorentwicklung

    International Nuclear Information System (INIS)

    1984-02-01

    The main points of investigations are the Fast Breeder Project (PSB), the Nuclear Fusion Project (PKF) and the Nuclear Safety Project (PNS). The contributions to the Fast Breeder Reactor Project comprise theoretical and experimental work on the dynamic behaviour of fast breeder reactors during operational and hypothetical incidents, investigations on consequences of local cooling incidents in the reactor core in consideration of possible damage propagation mechanisms, the detection of such events as well as the performance of risk-oriented analyses. As part of the Nuclear Fusion Project the Institute contributes to the evaluation of plant concepts, to the design and improvement of highly loaded components, to the development of handling techniques as well as to safety investigations. The work for the Project Nuclear Safety of lightwater reactors concern in particular analyses of containment structures under incident conditions, investigations on the fuel rod behaviour during incidents, as well as investigations on two-phase flows. The independent institutional research projects have a fundamental character and are oriented towards application, too. They concentrate on the special fields of applied computer science and continuum mechanics. (orig./GL) [de

  13. Financial Support for Institutional Research, 1969-70.

    Science.gov (United States)

    Pieper, W. C., Jr.

    The Association for Institutional Research conducted a survey of all institutions of higher education in the U.S. and Canada in order to assess the number, size, and financial support of institutional research offices. Data were requested for the 1969-70 academic year. This report is based on the responses of 1,444 institutions that returned the…

  14. Results on safety research for five years (from fiscal year 1996 to 2000). A field of nuclear fuel cycle

    International Nuclear Information System (INIS)

    2001-10-01

    This safety research carried out by the Japan Nuclear Cycle Development Institute (JNC) for five years ranged from fiscal year 1996 to 2000, was performed according to the safety research basic plan (from fiscal year 1996 to 2000) established on March, 1996 (revised again on May, 2000). This report was arranged on a field on nuclear fuel cycle (all subjects on fields of nuclear fuel facility, environmental radioactivity and radioactive wastes and a subject on nuclear fuel cycle in a field of seismic resistant and probabilistic safety assessment) by combining its research results for five years ranged from 1996 to 2000 fiscal year with general outlines on the safety research basic plan. Here were shown outlines on the safety research basic plan, aims and subjects on safety research at a field of nuclear fuel cycle, a list of survey sheets on safety research result, and survey sheets on safety research results. The survey sheets containing research field, title, organization, researcher name, researching period, names of cooperative organization, using facilities, research outline, research results, established contents, application, and research trends, are ranged to 21 items on nuclear fuel facility, 1 item on seismic resistance, 2 items on probabilistic safety assessment, 8 items on environmental radioactivity, and 20 items on radioactive wastes. (G.K.)

  15. Risk as a target of safety research

    International Nuclear Information System (INIS)

    Krueger, W.

    1986-01-01

    Job creation is not the idea behind the demand for risk studies to be intensified in safety research. Risks are not only a target safety research should investigate, they are a subject that actually can be most adequately investigated by safety research. Assuming a neutral position between irrational fears and interest-minded problem minimization, that is the central approach and the ethics of a safety scientist. The Babylonian confusion of terminology experienced after the Chernobyl accident is a good example proving the necessity of fostering the neutral professionalism in safety research. (orig./DG) [de

  16. Annual report 1991 on R and D work by the Institute for Materials and Solid State Research (IMF), Karlsruhe Nuclear Research Center

    International Nuclear Information System (INIS)

    1992-03-01

    The annual report summarises the activities of the IMF in the following subject areas: 1) Contributions to the PKF (fusion technology project (refewing to structural materials, superconducting magnets, blanket development); 2) PSU, project for the management of pollutants in the environment (treatment and recycling of hazardous waste); 3) solid state and materials research (high-temperature materials, ceramic materials as protective coatings, polymer materials, high-performance ceramics, high-TC superconducting materials; biomechanics, laser technology); 4) microtechnology (development and testing of compact or layered materials in microtechnology); 5) PSF project, nuclear safety, research (safety and materials aspects of fast breeder reactors, transient behaviour of fuel elements in fact breeder reactors, LWR-specific safety research, containment design concepts for the next generation of PWR-type reactors); 6) NE project, nuclear waste management (analysis of solid wastes from the dissolution of spent LWR fuels, materials testing in nitric acid). The primary reports and other publications of the Institute issued in 1991 are listed in an annex. (orig./MM) [de

  17. 29 CFR 1902.6 - Consultation with the National Institute for Occupational Safety and Health.

    Science.gov (United States)

    2010-07-01

    ... Safety and Health. 1902.6 Section 1902.6 Labor Regulations Relating to Labor (Continued) OCCUPATIONAL... Occupational Safety and Health. The Assistant Secretary will consult, as appropriate, with the Director of the National Institute for Occupational Safety and Health with regard to plans submitted by the States under...

  18. A Proposed Framework of Institutional Research Development Phases

    Science.gov (United States)

    Bosch, Anita; Taylor, John

    2011-01-01

    Globally, research has become a key driver for the achievement of status and the procurement of funding for higher education institutions. Although there is mounting pressure on institutions to become research active, many institutions are rooted in a strong tradition of teaching. These institutions find it challenging to develop research capacity…

  19. Homogeneous group, research, institution

    Directory of Open Access Journals (Sweden)

    Francesca Natascia Vasta

    2014-09-01

    Full Text Available The work outlines the complex connection among empiric research, therapeutic programs and host institution. It is considered the current research state in Italy. Italian research field is analyzed and critic data are outlined: lack of results regarding both the therapeutic processes and the effectiveness of eating disorders group analytic treatment. The work investigates on an eating disorders homogeneous group, led into an eating disorder outpatient service. First we present the methodological steps the research is based on including the strong connection among theory and clinical tools. Secondly clinical tools are described and the results commented. Finally, our results suggest the necessity of validating some more specifical hypothesis: verifying the relationship between clinical improvement (sense of exclusion and painful emotions reduction and specific group therapeutic processes; verifying the relationship between depressive feelings, relapses and transition trough a more differentiated groupal field.Keywords: Homogeneous group; Eating disorders; Institutional field; Therapeutic outcome

  20. The structure and emerging trends of construction safety management research: a bibliometric review.

    Science.gov (United States)

    Liang, Huakang; Zhang, Shoujian; Su, Yikun

    2018-03-29

    Recently, construction safety management (CSM) practices and systems have become important topics for stakeholders to take care of human resources. However, few studies have attempted to map the global research on CSM. A comprehensive bibliometric review was conducted in this study based on multiple methods. In total, 1172 CSM-related papers from the Web of Science Core Collection database were examined. The analyses focused on publication year, country-institute, publication source, author and research topics. The results indicated that the USA, China, Australia and the UK took leading positions in CSM research. Two branches of journals were identified, namely the branch of engineering science and that of safety science and social science. Additionally, seven themes together with 28 specific topics were detected to allow researchers to track the main structure and temporal evolution of CSM research. Finally, the main research trends and potential research directions were discussed to guide the future research.

  1. Institutional implications of establishing safety goals for nuclear power plants

    International Nuclear Information System (INIS)

    Morris, F.A.; Hooper, R.L.

    1983-07-01

    The purpose of this project is to anticipate and address institutional problems that may arise from the adoption of NRC's proposed Policy Statement on Safety Goals for Nuclear Power Plants. The report emphasizes one particular category of institutional problems: the possible use of safety goals as a basis for legal challenges to NRC actions, and the resolution of such challenges by the courts. Three types of legal issues are identified and analyzed. These are, first, general legal issues such as access to the legal system, burden of proof, and standard of proof. Second is the particular formulation of goals. Involved here are such questions as sustainable rationale, definitions, avoided issues, vagueness of time and space details, and degree of conservatism. Implementation brings up the third set of issues which include interpretation and application, linkage to probabilistic risk assessment, consequences as compared to events, and the use of results

  2. List of reports on reactor safety research from BMFT, CEA, EPRI, JSTA and USNRC

    International Nuclear Information System (INIS)

    1985-01-01

    This list reviews reports from the Federal Republic of Germany, from France, from Japan and from the United States of America concerning special Problems in the field of Reactor Safety Research. According to the cooperation of the Bundesminister fuer Forschung und Technologie (BMFT) with the Commissariat a l' Energie Atomique (CEA), the Japan Science and Technologie Agency (JSTA), the Electric Power Research Institute (EPRI) and the United States Nuclear Regulatory Commission, these Reports are available in the Gesellschaft fuer Reaktorsicherheit (GRS). The list pursues the following order: Country of origin, problem area concerned, according to the Reactor Safety Research Programm of the BMFT, reporting organization. The list of reports appears quarterly. (orig./HP) [de

  3. List of reports concerning reactor safety research from BMFT, CEA, EPRI, JSTA, and USNRC

    International Nuclear Information System (INIS)

    1982-12-01

    This list reviews reports from the Federal Republic of Germany, from France, from Japan and from the United States of America concerning special problems in the field of Reactor Safety Research. According to the cooperation of the Bundesminister fuer Forschung und Technologie (BMFT) with the Commissariat a l'Energie Atomique (CEA), the Japan Science and Technologie Agency (JSTA), the Electric Power Research Institute (EPRI) and the United States Nuclear Regulatory Commission, these Reports are available in the Gesellschaft fuer Reaktorsicherheit (GRS). The list pursues the following order: Country of origin, problem area concerned, according to the Reactor Safety Research Programm of the BMFT, reporting organization. The list of reports appears quarterly. (orig./HP) [de

  4. Institutional Response to Ohio's Campus Safety Initiatives: A Post-Virginia Tech Analysis

    Science.gov (United States)

    Jackson, Natalie Jo

    2009-01-01

    The purpose of this study was to examine how institutions of higher education were responding to unprecedented state involvement in campus safety planning and policymaking in the aftermath of the Virginia Tech tragedy. Focused on Ohio, a state in which a state-level task force was convened and charged to promulgate campus safety recommendations…

  5. Control system of labour safety measures in the higher educational institution

    Directory of Open Access Journals (Sweden)

    O. G. Feoktistova

    2015-01-01

    Full Text Available The article examines a system of labour safety measures control. With the introduction of the integrated system of management the competitive ability of production and organization, the effectiveness of its activity rise, and sinnergicheskiy effect is also reached and the savings of all forms of resources are ensured. Objectives and methods of control system of labour safety measures in enterprises are developed, including in the educational institutions.

  6. Self-assessment of application of the Code of Conduct on the safety of research reactors - Mexico

    International Nuclear Information System (INIS)

    Mamani-Alegria, Y.R.; Salgado-Gonzalez, J.R.; Miranda-Aldaco, J.

    2009-01-01

    In Mexico, the nuclear regulatory body is the National Commission on Nuclear Safety and Safeguards (CNSNS), and there is one research reactor, a TRIGA MARK III, operated by the National Institute for Nuclear Research (ININ). The main aspects of the Self-assessment of application of The Code of Conduct on the Safety of Research Reactor are given for the case of the TRIGA reactor. Furthermore, in this paper we give a brief description of the legal framework of the licensing process, for nuclear activities in a research reactor, there are also highlights of the major reactor features, the uses of the reactor for isotope production, the management and verification of safety, the radiation protection management program, the emergency planning and the training and qualification of the operation personnel. (author)

  7. Safety Research and Experimental Coal Mines

    Data.gov (United States)

    Federal Laboratory Consortium — Safety Research and Experimental Coal MinesLocation: Pittsburgh SiteThe Safety Research Coal Mine and Experimental Mine complex is a multi-purpose underground mine...

  8. The NASA Electronic Parts and Packaging (NEPP) Program - Presentation to Korean Aerospace Research Institute

    Science.gov (United States)

    LaBel, Kenneth A.; Sampson, Michael J.

    2016-01-01

    This presentation will provide basic information about NASA's Electronic Parts and Packaging Program (NEPP), for sharing with representatives of the South Korean Aerospace Research Institute (KARI) as part of a larger presentation by Headquarters Office of Safety and Mission Assurance. The NEPP information includes mission and goals, history of the program, basic focus areas, strategies, deliverables and some examples of current tasks.

  9. Institutional failures and transaction costs of Bulgarian private research institutes

    OpenAIRE

    Nozharov, Shteryo

    2016-01-01

    The paper analyses the reasons for poor performance of private research institutes in Bulgaria. In this regard the Institutional Economics methods are used. A connection between smart growth policy goals and Bulgarian membership in EU is made. The gaps in the institutional environment are identified as well as measures for their elimination are proposed. The main accent of the study is put on the identification of transaction costs, arisen as a result of the failures of the institutional envi...

  10. Perspectives from the Aldo Leopold Wilderness Research Institute: The Wildland Research institute

    Science.gov (United States)

    J. M. Bowker; H. Ken Cordell; Neelam C. Poudyal

    2014-01-01

    The Wildland Research Institute (WRi) at the University of Leeds (UK) came into being in October 2009. Its origins go back to a United Kingdom research councilfunded seminar series called Wilderness Britain? which ran between 1998 and 2000 and was coordinated from the University of Leeds. This opened up the wider debate on wilderness and rewilding in the UK and later...

  11. 25 years TNO Road-Vehicles Research Institute

    NARCIS (Netherlands)

    1995-01-01

    Since the founding of the TNO Road-Vehicles Research Institute 25years ago, the institute has managed to develop a leading position in automotive research in several disciplines. A steady growth of the institute during the first 20 years has turned into a strong growth during the last 5 years. A

  12. Progress report on safety research of high-level waste management for the period April 1986 to March 1987

    International Nuclear Information System (INIS)

    Nakamura, Haruto; Tashiro, Shingo

    1987-08-01

    Researches on high-level waste management at the High Level Waste Management Laboratory and the Waste Safety Testing Facility Operation Division of the Japan Atomic Energy Research Institute in the fiscal year of 1986 are reviewed in the report. Topics in the three sections are as follows: 1) Non-radioactive research has been continued on Synroc irradiation and modellings of waste form leaching. 2) Research results are described in the section of Safety Evaluation for Geological Disposal on engineered barriers, field tests, safety assessment models, migration, natural analogue, seabed disposal and conceptual design of a repository. 3) Adsorption behaviour of plutonium on leach-containers and migration of leached cesium in a rock column are described in the section of Safety Examination of Vitrified Forms in the Hot Cells of WASTEF. (author)

  13. Annual report 90. Institute for advanced materials

    International Nuclear Information System (INIS)

    1991-01-01

    The Annual Report 1990 of the Institute for Advanced Materials of the JRC highlights the Scientific Technical Achievements and presents in the Annex the Institute's Competence and Facilities available to industry for services and research under contract. The Institute executed in 1990 the R and D programme on advanced materials of the JRC and contributed to the programmes: reactor safety, radio-active waste management, fusion technology and safety, nuclear fuel and actinide research. The supplementary programme: Operation of the High Flux Reactor is presented in condensed form. A full report is published separately

  14. Annual report of the Japan Atomic Energy Research Institute

    International Nuclear Information System (INIS)

    1993-01-01

    JAERI has conducted nuclear safety research in conformity with the national five year plan for safety research on nuclear installations, radioactive waste management and environmental radiation, and the research on engineering safety and environmental safety is described. In the research on high temperature engineering, the construction of the high temperature test reactor, the research on its fuel and materials, the reactor engineering, high temperature structures, safety and heat transfer, and nuclear heat application are reported. On the research and development of nuclear fusion, core plasma, core engineering technology and so on have been studied, and the engineering design activities for the international thermonuclear experimental reactor are in progress. On the research and development of radiation application, radiation processing, advanced radiation application and radioisotope production have been researched. The experiment on the nuclear ship 'Mutsu' was completed, and the research on the design of improved marine reactors has been advanced. Fundamental and related researches on various subjects are also reported. (K.I.)

  15. Implementation of radiation safety program in a medical institution

    International Nuclear Information System (INIS)

    Palanca, Elena D.

    1999-01-01

    A medical institution that utilizes radiation for the diagnosis and treatment of diseases of malignancies develops and implements a radiation safety program to keep occupational exposures of radiation workers and exposures of non-radiation workers and the public to the achievable and a more achievable minimum, to optimize the use of radiation, and to prevent misadministration. The hospital radiation safety program is established by a core medical radiation committee composed of trained radiation safety officers and head of authorized users of radioactive materials and radiation machines from the different departments. The radiation safety program sets up procedural guidelines of the safe use of radioactive material and of radiation equipment. It offers regular training to radiation workers and radiation safety awareness courses to hospital staff. The program has a comprehensive radiation safety information system or radsis that circularizes the radiation safety program in the hospital. The radsis keeps the drafted and updated records of safety guides and policies, radioactive material and equipment inventory, personnel dosimetry reports, administrative, regulatory and licensing activity document, laboratory procedures, emergency procedures, quality assurance and quality control program process, physics and dosimetry procedures and reports, personnel and hospital staff training program. The medical radiation protection committee is tasked to oversee the actual implementation of the radiation safety guidelines in the different radiation facilities in the hospital, to review personnel exposures, incident reports and ALARA actions, operating procedures, facility inspections and audit reports, to evaluate the existing radiation safety procedures, to make necessary changes to these procedures, and make modifications of course content of the training program. The effective implementation of the radiation safety program provides increased confidence that the physician and

  16. Perceptions about safety and risks in gender-based violence research: implications for the ethics review process.

    Science.gov (United States)

    Sikweyiya, Yandisa; Jewkes, Rachel

    2011-10-01

    Does research on gender-based violence (GBV) pose greater than minimal risk to researchers and participants? This question needs to be understood particularly in light of hesitancy by Institutional Review Boards to approve research on GBV. The safety and risks of doing GBV studies and the implications for the ethical review process have not been a focus of much research. This qualitative study collected data through in-depth interviews with 12 experienced GBV researchers from various countries and a desk review. This paper explores researchers' interpretation of and meanings of the safety recommendations as provided in the WHO guidelines and whether there is empirical evidence on the presence of risks and safety concerns unique to GBV research. Informants raised a number of safety concerns about GBV research, yet in the interviews there were very few examples of problems having occurred, possibly because of the precautions applied. This paper argues that the notion that GBV studies carry greater than minimal risk when ethics precautions are followed is based on speculation, not evidence. It highlights the need for empirical evidence to support assertions of risk in research.

  17. Korea Atomic Energy Research Institute (KAERI) in the 21st century

    International Nuclear Information System (INIS)

    Chang, In Soon; Lee, Mun-Ki

    2001-01-01

    Abstract. KAERI (Korea Atomic Energy Research Institute), a national nuclear research institute in the Republic of Korea, celebrated its fortieth anniversary last April. It has played a key role in the Korean nuclear history such that it: initiated and promoted the peaceful uses of nuclear energy in the Republic of Korea; maintained nuclear expertise on whole spectrum of nuclear field through conducting nuclear R and D programs, operating nuclear research facilities, and training and educating specialized nuclear personnel; founded a cornerstone of Korean nuclear industry by participating in the establishment of a nuclear engineering company and a nuclear fuel company and localizing nuclear fuel and reactor technology; and contributed to nuclear safety regulation by incubating a specialized nuclear regulatory body. Recently, to concentrate on nuclear R and D on advanced technology, KAERI went through management reform such as: the transfer of nuclear engineering divisions responsible for NSSS design and nuclear fuel design to nuclear industry in 1996; and the downsizing of manpower in 1998. Currently KAERI is in the challenging stage in terms of its missions and manpower. In the coming 21st century, KAERI is required to maintain the current R and D momentum and also to conduct priority-based research requiring concentrated effort. (author)

  18. Swedish Nuclear Power Inspectorate, Office of Reactor Safety. Research plans for the period 1997-1999

    International Nuclear Information System (INIS)

    1997-02-01

    Office of Reactor Safety research is carried out within the following areas: Safety evaluation, Safety analysis, MTO, Materials and chemistry, Non-Destructive Testing, Strength of materials, Thermohydraulics, Nuclear fuel, Serious accidents and Process control. Research is carried out to fulfill SKIs overall goals in accordance with the directives from the Swedish government and parliament, in particular to be a driving force in safety related work when justified by operating experience, research results and technical progress, towards licensees as well as in international cooperation in safety; to promote the maintenance and development of competence in the safety related work at the SKI as well as the licensees and generally in the country, and as a specific role for the Office of Reactor Safety as designated in the internal routines to take initiative to encourage and carry out research into areas of importance for the Office as well as ensuring that research results are disseminated and used both within SKI and in the general work concerning nuclear safety. Research efforts within the Office of Reactor safety are carried out in the form of separate projects which form part of the priority work plans. Project managers, the necessary personnel resources and the budget for each year are included in the Annual Plan and the work is followed up in the same manner as other efforts. Research is performed in different ways, that can vary from laboratory studies to more consultative efforts, and be organised in many different ways such as examination projects, post-graduate studies, work sponsored at research institutes and companies in Sweden and abroad, collaboration in larger international projects, and participation in conferences which provide an important contribution to keeping SKI personnel informed within their specialist areas

  19. Joint Global Change Research Institute (JGCRI)

    Data.gov (United States)

    Federal Laboratory Consortium — The Joint Global Change Research Institute (JGCRI) is dedicated to understanding the problems of global climate change and their potential solutions. The Institute...

  20. Multi-Institution Research Centers: Planning and Management Challenges

    Science.gov (United States)

    Spooner, Catherine; Lavey, Lisa; Mukuka, Chilandu; Eames-Brown, Rosslyn

    2016-01-01

    Funding multi-institution centers of research excellence (CREs) has become a common means of supporting collaborative partnerships to address specific research topics. However, there is little guidance for those planning or managing a multi-institution CRE, which faces specific challenges not faced by single-institution research centers. We…

  1. Proceedings of the twenty-fifth annual institute on mining health, safety and research

    Energy Technology Data Exchange (ETDEWEB)

    Tinney, G.R.; Bacho, A.; Karmis, M. [eds.

    1994-12-31

    The keynote session included papers on the US Bureau of Mines - a vision for the future; clean, green and lean; and the psychology of occupational safety. The technical sessions include panel discussions on Virginia`s revised mine safety regulations, and on independent contractors. Other papers covered: criminal enforcement of regulatory violations; accidents during surface mine mobile equipment; Federal Mine Safety and Health Review Commission; safety, technological and productivity potentials of highwall mining; and accidents caused by falls of unsupported roof.

  2. Role of nuclear safety research and future plan

    International Nuclear Information System (INIS)

    Kim, W. S.; Lee, J. I.; Kang, S. C.; Park, Y. W.; Lee, J. H.; Kim, M. W.; Lee, C. J.; Park, Y. I.

    2000-01-01

    For promoting and improving nuclear safety research activities, this report gives an insight on the scope of safety research and its role in the safety management of nuclear installations, and suggests measures to adequately utilize the research results through taking an optimized role share among research organizations. Several measures such as cooperative planning of common research areas and proper role assignment, improvement of the interfaces among researchers, and reflection of end-users' opinion in the course of planning and conducting research to promote application of research results are identified. It is expected that the identified measures will contribute to enhancing the efficiency and effectiveness of nuclear safety research, if they are implemented after deliberating with the government and safety research organizations

  3. Establishment of Management System for Korea Institute of Nuclear Safety

    Energy Technology Data Exchange (ETDEWEB)

    Han, Soon-Kyoo; Ha, Jong-Tae; Chung, Ku-Young; Lee, Je-Hang; Kim, Kyung-Im [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

    2015-05-15

    In order to optimize of nuclear safety regulation in the rapidly changing nuclear safety environment, Korea government determined that the existing safety standards needed to be reviewed from Integrated Regulatory Review Service(IRRS) team of International Atomic Energy Agency(IAEA). For optimizations of nuclear safety regulation, the reviews were performed by IAEA IRRS team from July 10-22, 2011. In the results of 2011 IRRS mission, 12 suggestion and 10 recommendation were found. To confirm follow-up measures, IRRS follow-up mission would be also performed by IRRS team 18-24 months later after the mission was over. In order to prepare the IRRS follow-up mission, the establishment of MS of Korea Institute of Nuclear Safety(KINS) had been initiated by reflecting the 4 found supplement items in module 4 and IAEA GS-R-3 requirements. As a result of the initiation, MS of KINS was established. To introduce the MS of KINS and gather another suggestions for its enhancement, the MS was considered as a theme.

  4. Ageing Management for Research Reactors. Specific Safety Guide

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2010-10-15

    This Safety Guide was developed under the IAEA programme for safety standards for research reactors, which covers all the important areas of research reactor safety. It supplements and elaborates upon the safety requirements for ageing management of research reactors that are established in paras 6.68-6.70 and 7.109 of the IAEA Safety Requirements publication, Safety of Research Reactors. The safety of a research reactor requires that provisions be made in its design to facilitate ageing management. Throughout the lifetime of a research reactor, including its decommissioning, ageing management of its structures, systems and components (SSCs) important to safety is required, to ensure continued adequacy of the safety level, reliable operation of the reactor, and compliance with the operational limits and conditions. Managing the safety aspects of research reactor ageing requires implementation of an effective programme for the monitoring, prediction, and timely detection and mitigation of degradation of SSCs important to safety, and for maintaining their integrity and functional capability throughout their service lives. Ageing management is defined as engineering, operation, and maintenance strategy and actions to control within acceptable limits the ageing degradation of SSCs. Ageing management includes activities such as repair, refurbishment and replacement of SSCs, which are similar to other activities carried out at a research reactor in maintenance and testing or when a modification project takes place. However, it is important to recognize that effective management of ageing requires the use of a methodology that will detect and evaluate ageing degradation as a consequence of the service conditions, and involves the application of countermeasures for prevention and mitigation of ageing degradation. The objective of this Safety Guide is to provide recommendations on managing ageing of SSCs important to safety at research reactors on the basis of international

  5. Ageing Management for Research Reactors. Specific Safety Guide

    International Nuclear Information System (INIS)

    2010-01-01

    This Safety Guide was developed under the IAEA programme for safety standards for research reactors, which covers all the important areas of research reactor safety. It supplements and elaborates upon the safety requirements for ageing management of research reactors that are established in paras 6.68-6.70 and 7.109 of the IAEA Safety Requirements publication, Safety of Research Reactors. The safety of a research reactor requires that provisions be made in its design to facilitate ageing management. Throughout the lifetime of a research reactor, including its decommissioning, ageing management of its structures, systems and components (SSCs) important to safety is required, to ensure continued adequacy of the safety level, reliable operation of the reactor, and compliance with the operational limits and conditions. Managing the safety aspects of research reactor ageing requires implementation of an effective programme for the monitoring, prediction, and timely detection and mitigation of degradation of SSCs important to safety, and for maintaining their integrity and functional capability throughout their service lives. Ageing management is defined as engineering, operation, and maintenance strategy and actions to control within acceptable limits the ageing degradation of SSCs. Ageing management includes activities such as repair, refurbishment and replacement of SSCs, which are similar to other activities carried out at a research reactor in maintenance and testing or when a modification project takes place. However, it is important to recognize that effective management of ageing requires the use of a methodology that will detect and evaluate ageing degradation as a consequence of the service conditions, and involves the application of countermeasures for prevention and mitigation of ageing degradation. The objective of this Safety Guide is to provide recommendations on managing ageing of SSCs important to safety at research reactors on the basis of international

  6. Human factors research in Central Research Institute of Electric Power Industry creation of safety culture

    International Nuclear Information System (INIS)

    Horie, Yasuo

    2002-01-01

    To prevent accident of nuclear power plant, Human Factors Center was built in the Central Research Institute of Electric Power Industry in July 1987. It developed an evaluation method of human error cases and an application method of human factors information. Now it continues analysis and application of human factors information, development of training/work support tools and research/experiment of human behavior. Japan-Human Performance Evaluation System (J-HPES) was developed as an analytical system for analysis and evaluation of human factors related to the trouble and for using the result as the common property by storage the analytical results. J-HPES has a standard procedure consisted of collecting and analyzing data and proposing the countermeasures. The analytical results are arranged by 4 kinds of charts by putting into the form of a diagram. Moreover, it tries to find the causes with indirect and potential causes. Two kinds of materials, Caution Report and Human Factors Precept by means of Illustrations, are published. People can gain access to HFC database by URL http://criepi.denken.or.jp/CRIEPI/HFC/DB. To prevent these accidents, creation of human factors culture has been required. Five kinds of teaching materials and the training method are developed. (S.Y.)

  7. Overview of LWR severe accident research activities at the Karlsruhe Institute of Technology

    International Nuclear Information System (INIS)

    Miassoedov, Alexei; Albrecht, Giancarlo; Foit, Jerzy-Jan; Jordan, Thomas; Steinbrück, Martin; Stuckert, Juri; Tromm, Walter

    2012-01-01

    The research activities in the light water reactor (LWR) severe accidents domain at Karlsruhe Institute of Technology (KIT) are concentrated on the in- and ex-vessel core melt behavior. The overall objective is to investigate the core melt scenarios from the beginning of core degradation to melt formation and relocation in the vessel, possible melt dispersion to the reactor cavity and to the containment, corium concrete interaction and corium coolability in the reactor cavity, and hydrogen behaviour in reactor systems. The results of the experiments contribute to a better understanding of the core melt sequences and thus improve safety of existing and, in the long-term, of future reactors by severe accident mitigation measures and by safety installations where required. This overview paper describes the experimental facilities used at KIT for severe accident research and gives an overview of the main directions and objectives of the R&D work. (author)

  8. Research program on regulatory safety research - Synthesis report 2008

    International Nuclear Information System (INIS)

    Mailaender, R

    2009-06-01

    This report for the Swiss Federal Office of Energy (SFOE) summarises the program's main points of interest, work done in the year 2008 and the results obtained. The main points of the research program, which is co-ordinated by the Swiss Federal Nuclear Safety Inspectorate ENSI, are discussed. Topics covered concern reactor safety as well as human, organisational and safety aspects. Work done in several areas concerning reactor safety and materials as well as interactions in severe accidents in light-water reactors is described. Radiation protection, the transport and disposal of radioactive wastes and safety culture are also looked at. Finally, national and international co-operation is briefly looked at and work to be done in 2009 is reviewed. The report is completed with a list of research and development projects co-ordinated by ENSI

  9. Development of disposal technologies for radioactive waste generated from radioisotope users and research institutes

    International Nuclear Information System (INIS)

    Sakai, Akihiro; Yoshimori, Michiro

    2001-01-01

    In order to safely dispose of a radioactive waste, which is generated from radioisotope users and research institutes, investigation of characteristics of the waste and conceptual design of disposal facility were carried out. As a result of investigating JAERI that the waste has mainly been stored, it became clear that radioactivities of 19 nuclides are important from the viewpoint of the safety of the disposal. And the result of the conceptual design of disposal facilities on the assumption of 3 kinds of sites, the differences on the safety could not be recognized in either case, though the installation depth to construct the facilities influenced the economical efficiency. (author)

  10. Cost effective safety enhancements for research reactors in Uzbekistan and Kazakhstan - results of a joint program with US DOE

    International Nuclear Information System (INIS)

    Earle, O.K.; Carlson, R.B.; Rakhmanov, A.; Salikhbaev, U.S.; Chernyaev, V.; Chakrov, P.

    2004-01-01

    Full text: The US Department of Energy's Office of International Nuclear Safety and Cooperation established the Integrated Research Reactor Safety Enhancement Program (IRRSEP) in February 2002 to support U.S. nonproliferation goals by (1) implementing safety upgrades, or (2) assisting with the safe shutdown and decommissioning of foreign test and research reactors which present security concerns. IRRSEP's key program components are: Phase I: Self-evaluation by facility using provided checklists followed by prioritization to identify the 20 highest risk facilities; Phase II: Site visits with technical evaluation to finalize a list of projects that will enhance safety consistent with IAEA observations; Phase III: Corrective measures to implement the projects. Phases I, II and III are accomplished on a rolling basis, such that work is ongoing at three or four reactors per year. IRRSEP's key objective is to resolve the highest-priority nuclear safety issues at the most vulnerable foreign research reactors as quickly as possible. The prioritization methodology employed identified which research reactors fell into this category. The corrective measures mutually developed with the host facility are based on the premise of developing a sustainable infrastructure within each country to deal with its own nuclear material safety, security, and response issues in the future. IRRSEP also assists in creating an international framework of cooperation and openness between research and test reactor operators, and national and international regulators. The initial projects under IRRSEP are underway at research reactors in Kazakhstan, Uzbekistan, and Romania. This paper focuses on the projects undertaken at the WWR-K research reactor at the Institute of Nuclear Physics in Alatau, Kazakhstan and the WWR-SM research reactor at the Institute of Nuclear Physics in Ulugbek, Uzbekistan. These projects demonstrate the success and cost effectiveness of the IRRSEP program

  11. Cost effective safety enhancements for research reactors in Uzbekistan and Kazakhstan - results of a joint program with US DOE

    International Nuclear Information System (INIS)

    Earle, O.K.; Carlson, R.B.; Rakhmanov, A.; Salikhbaev, U.S.; Chernyaev, V.; Chakrov, P.

    2004-01-01

    The US Department of Energy's Office of International Nuclear Safety and Cooperation established the Integrated Research Reactor Safety Enhancement Program (IRRSEP) in February 2002 to support U.S. nonproliferation goals by implementing safety upgrades, or assisting with the safe shutdown and decommissioning of foreign test and research reactors which present security concerns. IRRSEP's key program components are: Phase I: Self-evaluation by facility using provided checklists followed by prioritization to identify the 20 highest risk facilities; Phase II: Site visits with technical evaluation to finalize a list of projects that will enhance safety consistent with IAEA observations; Phase III: Corrective measures to implement the projects. Phases I, II and III are accomplished on a rolling basis, such that work is ongoing at three or four reactors per year. IRRSEP's key objective is to resolve the highest-priority nuclear safety issues at the most vulnerable foreign research reactors as quickly as possible. The prioritization methodology employed identified which research reactors fell into this category. The corrective measures mutually developed with the host facility are based on the premise of developing a sustainable infrastructure within each country to deal with its own nuclear material safety, security, and response issues in the future. IRRSEP also assists in creating an international framework of cooperation and openness between research and test reactor operators, and national and international regulators. The initial projects under IRRSEP are underway at research reactors in Kazakhstan, Uzbekistan, and Romania. This paper focuses on the projects undertaken at the WWR-K research reactor at the Institute of Nuclear Physics in Alatau, Kazakhstan and the WWR-SM research reactor at the Institute of Nuclear Physics in Ulugbek, Uzbekistan. These projects demonstrate the success and cost effectiveness of the IRRSEP program

  12. The OpenAIRE Guide for Research Institutions

    Directory of Open Access Journals (Sweden)

    Gültekin Gürdal

    2013-11-01

    Full Text Available This text is transcript of OpenAIRE Guide which is prepared in order to help research institutions was released on 13.04.2011and translated with the cooperation of ANKOS Open Access and Institutional Repositories Grup members and OpenAIREplus project team of Turkey which is coordinated from Izmir Institute of Technology Library. OpenAIRE Project aims to support researchers in complying with the European Commission Seventh Framework Programme Open Access Pilot through a European Helpdesk System; support researchers in depositing their research publications in an institutional or disciplinary repository; build up an OpenAIRE portal and e-infrastructure for repository networks. The project will work in tadem with OpeanAIREplus Project which has the principal goal of creating a robust, participatory service for the cross-linking of peer-reviewed scientific publications and associated datasets.

  13. IAEA activities on research reactor safety

    International Nuclear Information System (INIS)

    Alcala-Ruiz, F.

    1995-01-01

    Since its inception in 1957, the International Atomic Energy Agency (IAEA) has included activities in its programme to address aspects of research reactors such as safety, utilization and fuel cycle considerations. These activities were based on statutory functions and responsibilities, and on the current situation of research reactors in operation around the world; they responded to IAEA Member States' general or specific demands. At present, the IAEA activities on research reactors cover the above aspects and respond to specific and current issues, amongst which safety-related are of major concern to Member States. The present IAEA Research Reactor Safety Programme (RRSP) is a response to the current situation of about 300 research reactors in operation in 59 countries around the world. (orig.)

  14. First Ph.D. Student Workshop of the Hermann von Helmholtz Association of National Research Centers (HGF) on ''Nuclear Safety Research''

    International Nuclear Information System (INIS)

    Knebel, J.U.; Sanchez Espinoza, V.H.

    2006-03-01

    The First Ph.D. Student Workshop ''Nuclear Safety Research'' of the Helmholtz Association of National Research Centers (HGF)'' was jointly organized by the Research Center Karlsruhe GmbH and the Energie Baden-Wuerttemberg AG (EnBW) from Wednesday 9th to Friday 11th March 2005. The workshop was opened with welcome greetings by Dr. Peter Fritz, Forschungszentrum Karlsruhe. Subsequently Dr. Joachim U. Knebel explained the main goals and the content of the workshop. The young scientists reported in 28 high-level presentations about their research work which covered a wide spectrum from reactor safety, partitions and transmutation, and innovative reactor systems, to safety research for nuclear waste disposal. The junior researchs showed excellent professional competence and demonstrated presentation qualities at the highest level. The successful funding of two Virtual Institutes, namely: the ''Competence in Nuclear Technologies'' and ''Functional Characteristics of Aquatic Interfaces both co-ordinated by Forschungszentrum Karlsruhe'', by the President of the Helmholtz Association Prof. Walter Kroell was the motivation for the organization of this first Ph.D. Student Workshop. Thanks to these two Virtual Institutes, the Reseach Center Karlsruhe and Juelich together with several univer-sities i.e. RWTH Aachen, Heidelberg, Karlsruhe, Muenster, and Stuttgart, have successfully financed eight Ph.D. and two post-doctoral students. Moreover, young scientists of the European Institute for Transuranium Elements (ITU) and additional seven Ph.D. Students, who are sponsored by the German nuclear industry (Framatome ANP, RWE Power, EnBW) in the frame of the Alliance Competence in on Nuclear Technology, and who are trained at Forschungszentrum Karlsruhe, actively contributed to this workshop. The EnBW-Award was handed over by Dr. Hans-Josef Zimmer, member of the board of directors of the EnBW-Kraftwerksgesellschaft, to Mrs. Ayelet Walter from the University of Stuttgart for the best

  15. Legal status of minister's notices and technology standards of 'Korea institute of nuclear safety'(KINS) to regulate nuclear safety

    International Nuclear Information System (INIS)

    Jung, S. K.; Jung, M. M.; Kim, S. W.; Jang, K. H.; Oh, B. J.

    2003-01-01

    Concerning nuclear safety or technology standards, each of 'notices' issued by minister of science and technology(MOST) empowered by law of its regulation is obviously forceful as a law, if not all. But the standards made by the chief of Korea institute of nuclear safety(KINS) to meet the tasks entrusted to KINS by MOST is only conditionally forceful as a law, that is, on the condition that law or regulation empowered the chief of KINS to make nuclear safety and/or technology standards

  16. Safety status of Russian research reactors

    International Nuclear Information System (INIS)

    Morozov, S.I.

    2001-01-01

    Gosatomnadzor of Russia is conducting the safety regulation and inspection activity related to nuclear and radiation safety at nuclear research facilities, including research reactors, critical assemblies and sub-critical assemblies. It implies implementing three major activities: 1) establishing the laws and safety standards in the field of research reactors nuclear and radiation safety; 2) research reactors licensing; and 3) inspections (or license conditions tracking and inspection). The database on nuclear research facilities has recently been updated based on the actual status of all facilities. It turned out that many facilities have been shutdown, whether temporary or permanently, waiting for the final decision on their decommissioning. Compared to previous years the situation has been inevitably changing. Now we have 99 nuclear research facilities in total under Gosatomnadzor of Russia supervision (compared to 113 in previous years). Their distribution by types and operating organizations is presented. The licensing and conduct of inspection processes are briefly outlined with emphasis being made on specific issues related to major incidents that happened in 2000, spent fuel management, occupational exposure, effluents and emissions, emergency preparedness and physical protection. Finally, a summary of problems at current Russian research facilities is outlined. (author)

  17. KfK, Institute for Radiochemistry. Report on the results of research and development performances 1989

    International Nuclear Information System (INIS)

    1990-03-01

    In 1989 the Institute for Radiochemistry became involved with research and development tasks in the context of the following projects: 'Reprocessing and Waste Treatment' (PWA), 'Fast Breeder' (PSB), 'Nuclear Fusion' (PKF) and 'Terminal Storage' (ELA). Environmental analysis and water technology within the Institute were amongst the programmes collected together in the project 'Environment and Safety'. Problems to do with surface chemistry and analysis were dealt with under 'Microtechnology'. Within the 'Reprocessing and Waste Treatment Project', the studies carried out in the Institute concentrated chiefly on investigating ways of simplifying the reprocessing process, especially in the reprocessing of fast-breeder fuels and waste reduction and treatment. In the 'Fast Breeder' project, further investigations were carried out on oxide fuel rods. In the 'Nuclear Fusion' project, the subject of investigation was chemical problems in the field of tritium technology as they arise during the recovery of tritium from tritium compounds in the internal or external fuel cycle of a fusion reactor. To this end, studies were carried out on the physical-chemical analysis of ceramic breeder materials. Research were carried out on the analysis and description of surfaces and on the reactions occurring on these surfaces and on the reactions occurring on these surfaces with regard to the application of knowledge gained from this programme to problems within environmental research, nuclear technology and microtechnology. The Water Chemistry Department working mainly on 'Environment and Safety' carried out chemical research and method development in the following subject areas: New technologies for the removal of problem constituents from water, the production of useable water and sewage recycling and the analysis and description of water pollutants. (orig./HK) [de

  18. Nuclear Safety Project

    International Nuclear Information System (INIS)

    1978-11-01

    The 13th semi-annual report 1/78 is a description of work within the Nuclear Safety Project performed in the first six months of 1978 in the nuclear safety field by KFK institutes and departments and by external institutions on behalf of KfK. It includes for each individual research activity short summaries on - work completed, - essential results, - plans for the near future. (orig./RW) [de

  19. Auditing as Institutional Research: A Qualitative Focus.

    Science.gov (United States)

    Fetterman, David M.

    1991-01-01

    Internal institutional auditing can improve effectiveness and efficiency and protect an institution's assets. Many of the concepts and techniques used to analyze higher education institutions are qualitative in nature and suited to institutional research, including fiscal, operational, data-processing, investigative, management consulting,…

  20. Materials of the Annual Scientific Conference at the Institute for Nuclear Research. (Collected reports)

    International Nuclear Information System (INIS)

    Vishnevs'kij, Yi.M.; Ostashko, V.V.

    1995-01-01

    The proceeding contain contributed papers submitted to the annual Scientific conference of the Institute for Nuclear Research, Ukraine (kiev, January 1996). The proceedings include reports have been presented on the following sections: Nuclear physics, Solid State physics, Plasma physics, Radio ecology, Reactor safety, Radiation and reactor materials Study. The book is a direct reproduction of the print-ready manuscripts presented by the authors. No corrections have been made in the texts

  1. The IAEA programme on research reactor safety

    International Nuclear Information System (INIS)

    Abou Yehia, H.

    2007-01-01

    According to the research reactor database of IAEA (RRDB), 250 reactors are operating worldwide, 248 have been shut down and 170 have been decommissioned. Among the 248 reactors that do not run, some will resume their activities, others will be dismantled and the rest do not face a clear future. The analysis of reported incidents shows that the ageing process is a major cause of failures, more than two thirds of operating reactors are over 30 years old. It also appears that the lack of adequate regulations or safety standards for research reactors is an important issue concerning reactor safety particularly when reactors are facing re-starting or upgrading or modifications. The IAEA has launched a 4-axis program: 1) to set basic safety regulations and standards for research reactors, 2) to provide IAEA members with an efficient help for the application of these safety regulations to their reactors, 3) to foster international exchange of information on research reactor safety, and 4) to provide IAEA members with a help concerning safety issues linked to malicious acts or sabotage on research reactors

  2. AEC sets five year nuclear safety research program

    International Nuclear Information System (INIS)

    Anon.

    1976-01-01

    The research by the government for the establishment of means of judging the adequacy of safety measures incorporated in nuclear facilities, including setting safety standards and collecting documents of general criteria, and the research by the industry on safety measures and the promotion of safety-related technique are stated in the five year program for 1976-80 reported by subcommittees, Atomic Energy Commission (AEC). Four considerations on the research items incorporated in the program are 1) technical programs relating to the safety of nuclear facilities and the necessary criteria, 2) priority of the relevant items decided according to their impact on circumstances, urgency, the defence-indepth concept and so on, 3) consideration of all relevant data and documents collected, and research subjects necessary to quantify safety measurement, and 4) consideration of technological actualization, the capability of each research body, the budget and the time schedule. In addition, seven major themes decided on the basis of these points are 1) reactivity-initiated accident, 2) LOCA, 3) fuel behavior, 4) structural safety, 5) radioactive release, 6) statistical method of safety evaluation, and 7) seismic characteristics. The committee has deliberated the appropriate division of researches between the government and the industry. A set of tables showing the nuclear safety research plan for 1976-80 are attached. (Iwakiri, K.)

  3. Food safety knowledge, attitudes and practices of institutional food-handlers in Ghana

    Directory of Open Access Journals (Sweden)

    Fortune Akabanda

    2017-01-01

    Full Text Available Abstract Background In large scale cooking, food is handled by many individuals, thereby increasing the chances of food contamination due to improper handling. Deliberate or accidental contamination of food during large scale production might endanger the health of consumers, and have very expensive repercussions on a country. The purpose of this study was to evaluate the food safety knowledge, attitudes, and practices among institutional food- handlers in Ghana. Methods The study was conducted using a descriptive, cross-sectional survey of 29 institutions by conducting face to face interview and administration of questionnaire to two hundred and thirty-five (235 institutional food-handlers. The questionnaire was peer-reviewed and pilot tested in three institutions in the Upper East Region of Ghana, before the final version was distributed to food-handlers. The questionnaire was structured into five distinctive parts to collect information on (i demographic characteristics, (ii employees’ work satisfaction, (iii knowledge on food safety, (iv attitudes towards food safety and (v food hygiene practices. Results Majority of the food-handlers were between 41–50 years (39.1%. Female respondents were (76.6%. In our study, the food-handlers were knowledgeable about hygienic practices, cleaning and sanitation procedures. Almost all of the food-handlers were aware of the critical role of general sanitary practices in the work place, such as hand washing (98.7% correct answers, using gloves (77.9%, proper cleaning of the instruments/utensils (86.4% and detergent use (72.8%. On disease transmission, the results indicates that 76.2% of the food- handlers did not know that Salmonella is a food borne pathogens and 70.6% did not know that hepatitis A is a food borne pathogen. However, 81.7% handlers agreed that typhoid fever is transmitted by food and 87.7% agreed that bloody diarrhea is transmitted by food. Logistic regression analysis testing four models

  4. Progress report on research and development activities of the Institut fuer Neutronenphysik und Reaktortechnik in 1980

    International Nuclear Information System (INIS)

    1981-02-01

    The Institut fuer Neutronenphysik und Reaktortechnik carries out research in nuclear enginering especially in the context of the development of sodium-cooled fast breeder reactors. The institute does theoretical and experimental work in equal shares. Most of the work is done in cooperation with other institutes and industrial groups. In the framework of the Projekt Schneller Brueter , the institute investigates the layout and safety problems, from a reactor physics point of view of large fast breeder cores. Problems concerning the effects of LWR accidents on population and environment are investigated in the Projekt Nukleare Sicherheit . To the Projekt Wiederaufarbeitung , the institute is contributing work on fuel cycle physics and the development of a suitable instrumentation. In the field of nuclear safeguards, the implementation of monitoring systems is being investigated. Research outside projects is being done on technical and physical problems of fusion by inertial confinement and application of nuclear power on the transportation sector with hydrogen as an energy source. The main results obtained in 1980 in the various projects are presented. (orig./RW) [de

  5. USNRC HTGR safety research program overview

    International Nuclear Information System (INIS)

    Foulds, R.B.

    1982-01-01

    An overview is given of current activities and planned research efforts of the US Nuclear Regulatory Commission (NRC) HTGR Safety Program. On-going research at Brookhaven National Laboratory, Oak Ridge National Laboratory, Los Alamos National Laboratory, and Pacific Northwest Laboratory are outlined. Tables include: HTGR Safety Issues, Program Tasks, HTGR Computer Code Library, and Milestones for Long Range Research Plan

  6. National Nuclear Research Institute Annual Report 2013

    International Nuclear Information System (INIS)

    2014-01-01

    The report highlights the activities of the National Nuclear Research Institute (NNRI) of the Ghana Atomic Energy Commission for the year 2013, grouped under the following headings: Centres under the institute namely Nuclear Reactors Research Centre (NRRC); Accelerator Research Centre (ARC); Engineering Services Centre (ESC); National Radioactive Waste Management Centre (NRWMC); Nuclear Chemistry and Environmental Research Centre (NCERC); Nuclear Applications Centre (NAC) and National Data Centre (NDC). (A. B.)

  7. Safety of research reactors - A regulator's perspective

    International Nuclear Information System (INIS)

    Rahman, M.S.

    2001-01-01

    Due to historical reasons research reactors have received less regulatory attention in the world than nuclear power plants. This has given rise to several safety issues which, if not addressed immediately, may result in an undesirable situation. However, in Pakistan, research reactors and power reactors have received due attention from the regulatory authority. The Pakistan Research Reactor-1 has been under regulatory surveillance since 1965, the year of its commissioning. The second reactor has also undergone all the safety reviews and checks mandated by the licensing procedures. A brief description of the regulatory framework, the several safety reviews carried out have been briefly described in this paper. Significant activities of the regulatory authority have also been described in verifying the safety of research reactors in Pakistan along with the future activities. The views of the Pakistani regulatory authority on the specific issues identified by the IAEA have been presented along with specific recommendations to the IAEA. We are of the opinion that there are more Member States operating nuclear research reactors than nuclear power plants. Therefore, there should be more emphasis on the research reactor safety, which somehow has not been the case. In several recommendations made to the IAEA on the specific safety issues the emphasis has been, in general, to have a similar documentation and approach for maintaining and verifying operational safety at research reactors as is currently available for nuclear power reactors and may be planned for nuclear fuel cycle facilities. (author)

  8. Institutional support for the Utah Consortium for Energy Research and Education. Annual report

    Energy Technology Data Exchange (ETDEWEB)

    1979-06-01

    The Utah Consortium for Energy Research and Education is made up of three colleges and universities in Utah. The scope of the Consortium plan is the marshalling of the academic research resources, as well as the appropriate non-academic resources within Utah to pursue, as appropriate, energy-related research activities. The heart of this effort has been the institutional contract between DOE and the University of Utah, acting as fiscal agent for the Consortium. Sixteen programs are currently being funded, but only ten of the projects are described in this report. Three projects are on fission/fusion; three on environment and safety; four on fossil energy; three on basic energy sciences; one each on conservation, geothermal, and solar.

  9. [Managing a health research institute: towards research excellence through continuous improvement].

    Science.gov (United States)

    Olmedo, Carmen; Buño, Ismael; Plá, Rosa; Lomba, Irene; Bardinet, Thierry; Bañares, Rafael

    2015-01-01

    Health research institutes are a strategic commitment considered the ideal environment to develop excellence in translational research. Achieving quality research requires not only a powerful scientific and research structure but also the quality and integrity of management systems that support it. The essential instruments in our institution were solid strategic planning integrated into and consistent with the system of quality management, systematic evaluation through periodic indicators, measurement of key user satisfaction and internal audits, and implementation of an innovative information management tool. The implemented management tools have provided a strategic thrust to our institute while ensuring a level of quality and efficiency in the development and management of research that allows progress towards excellence in biomedical research. Copyright © 2015 SESPAS. Published by Elsevier Espana. All rights reserved.

  10. Termination of past nuclear activities at the nuclear research institute

    International Nuclear Information System (INIS)

    Janzekovic, H.; Krizman, M.

    2006-01-01

    Many countries, particularly in Europe, started with nuclear programs in the fifties of the last century. As a consequence nuclear research institutes were established, among them also the Institute Jozef Stefan (IJS) in Slovenia. The nuclear activities at the IJS were related to the development of uranium ore processing technology and technologies comprising uranium oxide and hexafluoride. After very intensive period of nuclear activities the decline began step by step due to different reasons. Various approaches of the termination and decommissioning of facilities were used. The inspectors of the Slovenian Nuclear Safety Administration (SNSA), the responsible authority, started intensive activities at the IJS at the end of 2004. All together 22 research laboratories or research units were included in the inspection program and around 50 researchers of the IJS were involved into the inspection procedures. The inspection was very intensive in the laboratories and storages where past nuclear activities took place and were later on abandoned. As a result several contaminated equipments and sites in addition to around 200 unregistered sources were found. The majority of these sources is related to past nuclear activities. The inspection program related to the terminated research activities is still in progress. The IJS immediately started with the remediation activities including the development of methodology related to decontamination of radioactive liquids. The decontamination of two nuclear laboratories and three different storages of radioactive waste at its sites is in progress. Sixty of the above mentioned sources have been already stored in the Central Interim Storage for Radioactive Waste. (author)

  11. Final Report: Performance Engineering Research Institute

    Energy Technology Data Exchange (ETDEWEB)

    Mellor-Crummey, John [Rice Univ., Houston, TX (United States)

    2014-10-27

    This document is a final report about the work performed for cooperative agreement DE-FC02-06ER25764, the Rice University effort of Performance Engineering Research Institute (PERI). PERI was an Enabling Technologies Institute of the Scientific Discovery through Advanced Computing (SciDAC-2) program supported by the Department of Energy's Office of Science Advanced Scientific Computing Research (ASCR) program. The PERI effort at Rice University focused on (1) research and development of tools for measurement and analysis of application program performance, and (2) engagement with SciDAC-2 application teams.

  12. 76 FR 28790 - Board of Scientific Counselors, National Institute for Occupational Safety and Health (BSC, NIOSH)

    Science.gov (United States)

    2011-05-18

    ... Hearing Loss Prevention; Personal Protective Technologies; Health Hazard Evaluations; Construction Safety... Scientific Counselors, National Institute for Occupational Safety and Health (BSC, NIOSH) In accordance with... relating to occupational safety and health and to mine health. The Board of Scientific Counselors shall...

  13. Safety assessment of research reactors and preparation of the safety analysis report

    International Nuclear Information System (INIS)

    1994-01-01

    This Safety Guide presents guidelines, approved by international consensus, for the preparation, review and assessment of safety documentation for research reactors such as the Safety Analysis Report. While the Guide is most applicable to research reactors in the design and construction stage, it is also recommended for use during relicensing or reassessment of existing reactors

  14. Safety-related LWR research. Annual report 1993

    International Nuclear Information System (INIS)

    Hueper, R.

    1994-06-01

    The reactor safety R and D work of the Karlsruhe Nuclear Research Centre (KfK) has been part of the Nuclear Safety Research Project (PSF) since 1990. The present annual report 1993 summarizes the results on LWR safety. The research tasks are coordinated in agreement with internal and external working groups. The contributions to this report correspond to the status at the end of 1993. (orig./HP) [de

  15. Reactor safety research - results and perspectives

    International Nuclear Information System (INIS)

    Banaschik, M.

    1989-01-01

    The work performed so far is an essential contribution to the determination of the safety margins of nuclear facilities and their systems and to the further development of safety engineering. The further development of safety engineering involves a shift of emphasis in reactor safety research towards event sequences beyond the design basis. The aim of this shift in emphasis is the further development of the preventive level. This is based on the fact that the conservative design of the operating and safety systems involves and essential safety potential. The R and D work is intended to help develop accident management measures and to take the plant back into the safe state even after severe accidents. In this context, it is necessary to make full use of the safety margins of the plant and to include the operating systems for coping with accidents. As a result of the aims, the research work approaches operating and plant-specific processes. (orig./DG) [de

  16. Evaluation of the state water-resources research institutes

    Science.gov (United States)

    Ertel, M.O.

    1988-01-01

    Water resources research institutes, as authorized by the Water Resources Research Act of 1984 (Public Law 98-242), are located in each state and in the District of Columbia, Guam, Puerto Rico , and the Virgin Islands. Public Law 98-242 mandated an onsite evaluation of each of these institutes to determine whether ' . . .the quality and relevance of its water resources research and its effectiveness as an institution for planning, conducting, and arranging for research warrant its continued support in the national interest. ' The results of these evaluations, which were conducted between September 1985 and June 1987, are summarized. The evaluation teams found that all 54 institutes are meeting the basic objectives of the authorizing legislation in that they: (1) use the grant funds to support research that addresses water problems of state and regional concern; (2) provide opportunities for training of water scientists through student involvement on research projects; and (3) promote the application of research results through preparation of technical reports and contributions to the technical literature. The differences among institutes relate primarily to degrees of effectiveness, and most often are determined by the financial, political, and geographical contexts in which the institutes function and by the quality of their leadership. (Lantz-PTT)

  17. NRC review of Electric Power Research Institute's Advanced Light Reactor Utility Requirements Document - Program summary, Project No. 669

    International Nuclear Information System (INIS)

    1992-08-01

    The staff of the US Nuclear Regulatory Commission has prepared Volume 1 of a safety evaluation report (SER), ''NRC Review of Electric Power Research Institute's Advanced Light Water Reactor Utility Requirements Document -- Program Summary,'' to document the results of its review of the Electric Power Research Institute's ''Advanced Light Water Reactor Utility Requirements Document.'' This SER provides a discussion of the overall purpose and scope of the Requirements Document, the background of the staff's review, the review approach used by the staff, and a summary of the policy and technical issues raised by the staff during its review

  18. Food safety knowledge, attitudes and practices of institutional food-handlers in Ghana.

    Science.gov (United States)

    Akabanda, Fortune; Hlortsi, Eli Hope; Owusu-Kwarteng, James

    2017-01-06

    In large scale cooking, food is handled by many individuals, thereby increasing the chances of food contamination due to improper handling. Deliberate or accidental contamination of food during large scale production might endanger the health of consumers, and have very expensive repercussions on a country. The purpose of this study was to evaluate the food safety knowledge, attitudes, and practices among institutional food- handlers in Ghana. The study was conducted using a descriptive, cross-sectional survey of 29 institutions by conducting face to face interview and administration of questionnaire to two hundred and thirty-five (235) institutional food-handlers. The questionnaire was peer-reviewed and pilot tested in three institutions in the Upper East Region of Ghana, before the final version was distributed to food-handlers. The questionnaire was structured into five distinctive parts to collect information on (i) demographic characteristics, (ii) employees' work satisfaction, (iii) knowledge on food safety, (iv) attitudes towards food safety and (v) food hygiene practices. Majority of the food-handlers were between 41-50 years (39.1%). Female respondents were (76.6%). In our study, the food-handlers were knowledgeable about hygienic practices, cleaning and sanitation procedures. Almost all of the food-handlers were aware of the critical role of general sanitary practices in the work place, such as hand washing (98.7% correct answers), using gloves (77.9%), proper cleaning of the instruments/utensils (86.4%) and detergent use (72.8%). On disease transmission, the results indicates that 76.2% of the food- handlers did not know that Salmonella is a food borne pathogens and 70.6% did not know that hepatitis A is a food borne pathogen. However, 81.7% handlers agreed that typhoid fever is transmitted by food and 87.7% agreed that bloody diarrhea is transmitted by food. Logistic regression analysis testing four models showed statistically significant differences

  19. A Milestone of Aeromedical Research Contributions to Civil Aviation Safety: The 1000th Report in the CARI/OAM Series

    National Research Council Canada - National Science Library

    Collins, William E; Wade, Katherine

    2005-01-01

    .... Additional, theme-related sections provide an indication of some of the varied research contributions and safety achievements of the Institute and cite some of the many individuals who contributed...

  20. Radiant Research. Institute for Energy Technology 1948-98

    International Nuclear Information System (INIS)

    Njoelstad, Olav

    1999-01-01

    Institutt for Atomenergi (IFA), or Institute for Atomic Energy, at Kjeller, Norway, was founded in 1948. The history of the institute as given in this book was published in 1999 on the occasion of the institute's 50th anniversary. The scope of the institute was to do research and development as a foundation for peaceful application of nuclear energy and radioactive substances in Norway. The book tells the story of how Norway in 1951 became the first country after the four superpowers and Canada to have its own research reactor. After the completion of the reactor, the institute experienced a long and successful period and became the biggest scientific and technological research institute in Norway. Three more reactors were built, one in Halden and two at Kjeller. Plans were developed to build nuclear powered ships and nuclear power stations. It became clear, however, in the 1970s, that there was no longer political support for nuclear power in Norway, and it was necessary for the institute to change its research profile. In 1980, the institute changed its name to Institutt for energiteknikk (IFE), or Institute for energy technology, to signal the broadened scope. The book describes this painful but successful readjustment and shows how IFE in the 1980s and 1990s succeeded in using its special competence from the nuclear field to establish special competence in new research fields with great commercial potential

  1. 76 FR 11765 - Education Research and Special Education Research Grant Programs; Institute of Education Sciences...

    Science.gov (United States)

    2011-03-03

    ... DEPARTMENT OF EDUCATION Education Research and Special Education Research Grant Programs; Institute of Education Sciences; Overview Information; Education Research and Special Education Research.... SUMMARY: The Director of the Institute of Education Sciences (Institute) announces the Institute's FY 2012...

  2. Institutional radioactive waste management in the Nuclear Research Institute Rez plc

    International Nuclear Information System (INIS)

    Kovarik, P.; Svoboda, K.; Podlaha, J.

    2008-01-01

    Nuclear research institute Rez, plc. (mentioned below as NRI) has had a dominant position in the area of the nuclear research and development in the Czech Republic, the Central and the Eastern Europe. Naturally, the radioactive waste management is an integral part of the nuclear industry, research and development. For that reason, there is Centre of the radioactive waste management (mentioned below as Centre) in the NRI. This Centre is engaged in the radioactive waste treatment, decontamination, characterisation, decommissioning and other relevant activities. This paper describes the system of technology and other information about institutional radioactive waste management in the NRI. (authors)

  3. Nuclear reactor safety research in Idaho

    International Nuclear Information System (INIS)

    Zeile, H.J.

    1983-01-01

    Detailed information about the performance of nuclear reactor systems, and especially about the nuclear fuel, is vital in determining the consequences of a reactor accident. Fission products released from the fuel during accidents are the ultimate safety concern to the general public living in the vicinity of a nuclear reactor plant. Safety research conducted at the Idaho National Engineering Laboratory (INEL) in support of the U.S. Nuclear Regulatory Commission (NRC) has provided the NRC with detailed data relating to most of the postulated nuclear reactor accidents. Engineers and scientists at the INEL are now in the process of gathering data related to the most severe nuclear reactor accident - the core melt accident. This paper describes the focus of the nuclear reactor safety research at the INEL. The key results expected from the severe core damage safety research program are discussed

  4. Seminar series on Safety matters

    CERN Multimedia

    HSE

    2010-01-01

    The HSE - Occupational Health & Safety and Environmental Protection - Unit is starting a seminar series on Safety matters. The aim is to invite colleagues from Universities, Industries or Government Agencies to share their experience. The seminars will take place in intervals of several months. Part of the Seminars will be held in the form of a Forum where participants can discuss and share views with persons who manage, teach or research Safety matters elsewhere. You are invited to the first Safety Seminar on 22nd September 2010 at 10h00 in building 40 S2 A1 "Salle Andersson" L’Ecole Polytechnique Fédérale de Lausanne (EPFL) will present the way safety is managed in their research institution. Some aspects of research in physics and chemical laboratories will also be presented. The seminar will be given by Dr Thierry Meyer, Head of OHS at FSB-EPFL and Dr Amela Groso, responsible for the safety of the physics institutes

  5. Nuclear Safety Research Department annual report 2000

    DEFF Research Database (Denmark)

    Majborn, B.; Nielsen, Sven Poul; Damkjær, A.

    2001-01-01

    The report presents a summary of the work of the Nuclear Safety Research Department in 2000. The department's research and development activities were organized in two research programmes: "Radiation Protection and Reactor Safety" and "Radioecology andTracer Studies". In addtion the department...

  6. Nuclear Safety Research Department annual report 2001

    DEFF Research Database (Denmark)

    Majborn, B.; Damkjær, A.; Nielsen, Sven Poul

    2002-01-01

    The report presents a summary of the work of the Nuclear Safety Research Department in 2001. The department's research and development activities were organized in two research programmes: "Radiation Protection and Reactor Safety" and "Radioecology andTracer Studies". In addition the department...

  7. 75 FR 51818 - National Institute for Occupational Safety and Health; Final Effect of Designation of a Class of...

    Science.gov (United States)

    2010-08-23

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES National Institute for Occupational Safety and Health...: National Institute for Occupational Safety and Health (NIOSH), Department of Health and Human Services (HHS... a number of work days aggregating at least 250 work days, occurring either solely under this...

  8. 75 FR 74733 - National Institute for Occupational Safety and Health; Final Effect of Designation of a Class of...

    Science.gov (United States)

    2010-12-01

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES National Institute for Occupational Safety and Health...: National Institute for Occupational Safety and Health (NIOSH), Department of Health and Human Services (HHS... aggregating at least 250 work days, occurring either solely under this employment, or in combination with work...

  9. 75 FR 51816 - National Institute for Occupational Safety and Health; Final Effect of Designation of a Class of...

    Science.gov (United States)

    2010-08-23

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES National Institute for Occupational Safety and Health...: National Institute for Occupational Safety and Health (NIOSH), Department of Health and Human Services (HHS... number of work days aggregating at least 250 work days, occurring either solely under this employment or...

  10. Research for the safety of existing nuclear facilities

    International Nuclear Information System (INIS)

    Teschendorff, Victor; Bruna, Giovanni B.; Gelder, Pieter de

    2007-01-01

    The essential role of research for maintaining the high safety standard for the existing nuclear installations is outlined in the context of internationally agreed needs. The three co-authoring Technical Safety Organisations are committed to continued safety research, recognising operational experience and new technologies as the main driving forces. The safety margin concept is introduced and new trends in traditional and new areas of safety research are identified. The importance of a sufficient experimental infrastructure and international co-operation in sustainable networks is highlighted. (orig.)

  11. Dynamic design load of type 2 water-flow capsule in Nuclear Safety Research Reactor in Tokai Research Establishment of Japan Atomic Energy Research Institute, and its reuse test

    International Nuclear Information System (INIS)

    1981-01-01

    A report by the Nuclear Safety Bureau of the Science and Technology Agency to the Nuclear Safety Commission was presented on the validity of the dynamic design load of type 2 water-flow capsule and the method of its reuse test. The safety in both aspects of the capsule was confirmed. The Nuclear Safety Research Reactor (NSRR), in which the water-flow capsule is set, is a swimming pool type reactor, fueled with enriched uranium, having heat output of 300 kW in normal operation and maximum instantaneous heat output of 23,000 MW in pulse operation. The type 2 water-flow capsule, with the initial conditions simulating a power generating LWR plant and being appropriately set, is used to acquire the data on fuel behavior and destructive power in pulse irradiation. (J.P.N.)

  12. Dynamic design load of type 2 water-flow capsule in Nuclear Safety Research Reactor in Tokai Research Establishment of Japan Atomic Energy Research Institute, and its reuse test

    Energy Technology Data Exchange (ETDEWEB)

    1981-01-01

    A report by the Nuclear Safety Bureau of the Science and Technology Agency to the Nuclear Safety Commission was presented on the validity of the dynamic design load of type 2 water-flow capsule and the method of its reuse test. The safety in both aspects of the capsule was confirmed. The Nuclear Safety Research Reactor (NSRR), in which the water-flow capsule is set, is a swimming pool type reactor, fueled with enriched uranium, having heat output of 300 kW in normal operation and maximum instantaneous heat output of 23,000 MW in pulse operation. The type 2 water-flow capsule, with the initial conditions simulating a power generating LWR plant and being appropriately set, is used to acquire the data on fuel behavior and destructive power in pulse irradiation.

  13. A research framework of organizational factors on safety in the Republic of Korea

    International Nuclear Information System (INIS)

    Kwang Seok Lee

    1997-01-01

    Korean nuclear society is yet unfamiliar with the topic, 'organizational factors on safety', while having shown lots of accomplishments in the area of physical and human factors on safety. However, recent large-scale accidents in other technological areas illustrate the importance of managing organization factors on safety. Recently Korea Atomic Energy Research Institute (KAERI) started paying attention to this topic and is trying to establish a future research framework of organizational factors on safety. This paper tries to explain overall direction of the framework. Our framework, as managing organizational factors on safety, considers two kinds of areas: design of management systems, which implies a feed-forward system including organizational models; and operation of those systems, which implies a feedback system including management information and implementation systems. Our framework also considers the evolution stage of a management system. Management systems evolve from visibility stage to optimization stage. To optimize a management system, we should be able to control the system. To control the system, we should be able to see how the system is going. In addition, this paper tries to share some experience of KAERI on how organizational structure and culture affects organizational performance in R and D perspective. (author). 2 refs, 1 fig

  14. Chinese Road Safety and Driver Behavior Research

    OpenAIRE

    Wang, Junhua

    2015-01-01

    The seminar will begin with a brief overview of the Chinese road safety situation, including current safety problems, and then move on to discuss safety research including driver behavior, freeway operational safety, and infrastructure development.

  15. 76 FR 62409 - National Institute for Occupational Safety and Health; Final Effect of Designation of a Class of...

    Science.gov (United States)

    2011-10-07

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES National Institute for Occupational Safety and Health...: National Institute for Occupational Safety and Health (NIOSH), Department of Health and Human Services (HHS..., from January 1, 1961 through June 30, 1970, for a number of work days aggregating at least 250 work...

  16. Danish Space Research Institute

    International Nuclear Information System (INIS)

    1991-01-01

    The present report presents a description of the activities and finances of the Danish Space Reserach Institute during 1989 and 1990. The research deals with infrared astronomy (ISOPHOT), X-ray astronomy (EXPECT/SODART), hard X-ray astronomy (WATCH), satellite projects and sounding rocket experiments. (CLS)

  17. Booklet of the Research Institute of Clinical Medicine

    International Nuclear Information System (INIS)

    Todua, F.; Jgamadze, N.; Todua, N.; Beriashvili, Z.; Chelishvili, M.; Todua, I.; Chovelidze, Sh. et al.

    2012-01-01

    Research Institute of Clinical Medicine is one of the biggest university diagnostic and treatment centre in Georgia with unique modern diagnostic and treatment apparatus. The institute is acknowledged as a leader in various trends of radiology and surgery. The Research Institute of Clinical Medicine was founded in 1991. It is the leading scientific establishment in the field of medicine. The scientific-research work of the Institute is coordinated by the National Academy of Sciences of Georgia. The main scientific trend of the Institute is the Early Complex Diagnostics and Treatment. The scientific activity of the Institute is led by the Scientific Council. Institute achieved remarkable success since its foundation: It has been defended 56 theses for Candidate of Medical Sciences and 16 for Doctor of Medical Sciences; About 30 post-graduate students and more than 200 radiologists have taken training courses in radiology. Nowadays they work in different regions of Georgia, 21 inventions took out patents. It has been published 2000 scientific works and 9 monographs. (authors)

  18. Reactor safety research. The CEC contribution

    International Nuclear Information System (INIS)

    Krischer, W.

    1990-01-01

    The involvement of the EC Commission in the reactor safety research dates back almost to the implementation of the EURATOM Treaty and has thus lasted for thirty years. The need for close collaboration and for general consensus on some crucial problems of concern to the public, has made the role of international organizations and, as far as Europe is concerned, the role of the European Community particularly important. The areas in which the CEC has been active during the last five years are widespread. This is partly due to the fact that, after TMI and Chernobyl, the effort and the interest of the different countries in reactor safety was considerable. Reactor Safety Research represents the proceedings of a seminar held by the Commission at the end of its research programme 1984-88 on reactor safety. As such it gives a comprehensive overview of the recent activities and main results achieved in the CEC Joint Research Centre and in national laboratories throughout Europe on the basis of shared cost actions. In a concluding chapter the book reports on the opinions, expressed during a panel by a group of major exponents, on the needs for future research. The main topics addressed are, with particular reference to Light Water Reactors (LWRS): reliability and risk evaluation, inspection of steel components, primary circuit components end-of-life prediction, and abnormal behaviour of reactor cooling systems. As far as LMFBRs are concerned, the topics covered are: severe accident modelling, material properties and structural behaviour studies. There are 67 pages, all of which are indexed separately. Reactor Safety Research will be of particular interest to reliability and safety engineers, nuclear engineers and technicians, and mechanical and structural engineers. (author)

  19. Probabilistic safety assessment for research reactors

    International Nuclear Information System (INIS)

    1986-12-01

    Increasing interest in using Probabilistic Safety Assessment (PSA) methods for research reactor safety is being observed in many countries throughout the world. This is mainly because of the great ability of this approach in achieving safe and reliable operation of research reactors. There is also a need to assist developing countries to apply Probabilistic Safety Assessment to existing nuclear facilities which are simpler and therefore less complicated to analyse than a large Nuclear Power Plant. It may be important, therefore, to develop PSA for research reactors. This might also help to better understand the safety characteristics of the reactor and to base any backfitting on a cost-benefit analysis which would ensure that only necessary changes are made. This document touches on all the key aspects of PSA but placed greater emphasis on so-called systems analysis aspects rather than the in-plant or ex-plant consequences

  20. An overview of IPSN research on the evolution of the natural systems in support of the French methodology for the safety evaluation of radwaste disposal in deep geological formations

    International Nuclear Information System (INIS)

    Escalier des Orres, P.; Granier, T.; Mohammadioun, B.

    1992-01-01

    A regulatory guidance has been recently set up in France for the safety assessment of radwaste deep geological disposal: the present paper concerns the requirements related to bedrock stability issues and their technical background. This regulation relies in particular on a long term effort of the Protection and Nuclear Safety Institute (IPSN) of the French Atomic Energy Commission (CEA), which ensures two main duties: it carries out research programs in the area of protection and nuclear safety and provides expertise to the safety authorities. It should be noted that ANDRA (the French National Radioactive Waste Management Agency) is responsible for the safety of radioactive waste management and relies, for safety demonstration purposes, on its research programs. IPSN, in support of the safety authorities, is in charge of the verification of the applicant's safety demonstration and develops its own research programs in order to achieve an independent capability in safety analysis expertise. We present here the major axes of the Institute research program devoted to the assessment of seismic events consequences on the groundwater system. 19 refs., 8 figs

  1. An overview of IPSN research on the evolution of the natural systems in support of the French methodology for the safety evaluation of radwaste disposal in deep geological formations

    International Nuclear Information System (INIS)

    Escalier des Orres, P.; Granier, T.; Mohammadioun, B.

    1992-01-01

    A regulatory guidance has been recently set up in France for the safety assessment of radwaste deep in geological disposal: the present paper concerns the requirements related to bedrock stability issues and their technical background. This regulation relies in particular on a long term effort of the Protection and Nuclear Safety Institute (IPSN) of the French Atomic Energy Commission (CEA), which ensures two main duties: it carries out research programs in the area of protection and nuclear safety and provides expertise to the safety authorities. It should be noted that ANDRA (the French National Radioactive Waste Management Agency) is responsible for the safety of radioactive waste management and relies, for safety demonstration purposes, on its research programs. IPSN, in support of the safety authorities, is in charge of the verification of the applicant's safety demonstration and develops its own research programs in order to achieve an independent capability in safety analysis expertise. We present here the major axes of the Institute research program devoted to the assessment of seismic events consequences on the groundwater system. 19 refs., 8 figs

  2. Institutional shared resources and translational cancer research

    Directory of Open Access Journals (Sweden)

    De Paoli Paolo

    2009-06-01

    Full Text Available Abstract The development and maintenance of adequate shared infrastructures is considered a major goal for academic centers promoting translational research programs. Among infrastructures favoring translational research, centralized facilities characterized by shared, multidisciplinary use of expensive laboratory instrumentation, or by complex computer hardware and software and/or by high professional skills are necessary to maintain or improve institutional scientific competitiveness. The success or failure of a shared resource program also depends on the choice of appropriate institutional policies and requires an effective institutional governance regarding decisions on staffing, existence and composition of advisory committees, policies and of defined mechanisms of reporting, budgeting and financial support of each resource. Shared Resources represent a widely diffused model to sustain cancer research; in fact, web sites from an impressive number of research Institutes and Universities in the U.S. contain pages dedicated to the SR that have been established in each Center, making a complete view of the situation impossible. However, a nation-wide overview of how Cancer Centers develop SR programs is available on the web site for NCI-designated Cancer Centers in the U.S., while in Europe, information is available for individual Cancer centers. This article will briefly summarize the institutional policies, the organizational needs, the characteristics, scientific aims, and future developments of SRs necessary to develop effective translational research programs in oncology. In fact, the physical build-up of SRs per se is not sufficient for the successful translation of biomedical research. Appropriate policies to improve the academic culture in collaboration, the availability of educational programs for translational investigators, the existence of administrative facilitations for translational research and an efficient organization

  3. Institutional shared resources and translational cancer research.

    Science.gov (United States)

    De Paoli, Paolo

    2009-06-29

    The development and maintenance of adequate shared infrastructures is considered a major goal for academic centers promoting translational research programs. Among infrastructures favoring translational research, centralized facilities characterized by shared, multidisciplinary use of expensive laboratory instrumentation, or by complex computer hardware and software and/or by high professional skills are necessary to maintain or improve institutional scientific competitiveness. The success or failure of a shared resource program also depends on the choice of appropriate institutional policies and requires an effective institutional governance regarding decisions on staffing, existence and composition of advisory committees, policies and of defined mechanisms of reporting, budgeting and financial support of each resource. Shared Resources represent a widely diffused model to sustain cancer research; in fact, web sites from an impressive number of research Institutes and Universities in the U.S. contain pages dedicated to the SR that have been established in each Center, making a complete view of the situation impossible. However, a nation-wide overview of how Cancer Centers develop SR programs is available on the web site for NCI-designated Cancer Centers in the U.S., while in Europe, information is available for individual Cancer centers. This article will briefly summarize the institutional policies, the organizational needs, the characteristics, scientific aims, and future developments of SRs necessary to develop effective translational research programs in oncology.In fact, the physical build-up of SRs per se is not sufficient for the successful translation of biomedical research. Appropriate policies to improve the academic culture in collaboration, the availability of educational programs for translational investigators, the existence of administrative facilitations for translational research and an efficient organization supporting clinical trial recruitment

  4. Nuclear safety project

    International Nuclear Information System (INIS)

    1982-06-01

    The Annual Report 1981 is a detailed description (in German language) of work within the Nuclear Safety Project performed in 1981 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 - results obtained - plans for future work. This report was compiled by the project management. (orig.) [de

  5. List of reports on reactor safety research of BMFT, CEA, EPRI, JSTA and USNRC

    International Nuclear Information System (INIS)

    1984-07-01

    This list reviews reports from the Federal Republic of Germany, from France, from Japan and from the United States of America concerning special problems in the field of reactor safety research. According to the cooperation of the Bundesminister fuer Forschung und Technologie (BMFT) with the Commissariat a l'Energie Atomique (CEA), the Japan Science and Technology Agency (JSTA), the Electric Power Research Institute (EPRI) and the United States Nuclear Regulatory Commission, these reports are available in the Gesellschaft fuer Reaktorsicherheit (GRS). The list pursues the following order: Country of origin, problem area concerned, according to the Reactor Safety Research Programm of the BMFT, reporting organization. The list of reports appears quarterly. Requests for reports should be addressed to GRS, Forschungsbetreuung. Contractual points of view have to be considered for the distribitution of the reports. (orig.) [de

  6. KfK, Institute for Reactor Components. Results of research and development activities in 1989

    International Nuclear Information System (INIS)

    1990-03-01

    R and D activities at IRB (Institut fuer Reaktorbauelemente - Institute for Reactor Components) are dedicated to thermodynamics and fluid dynamics. Emphasis is on the design of nuclear reactor and fusion reactor components. Environmental engineering was added recently. Most activities are applications-oriented. Fundamental investigations focus on energy research and energy technology. The activities are carried out in the framework of different projects (PKF/nuclear fusion, PSF/nuclear safety, PSU/pollution control). Points of main effort are the development of basic liquid-metal-cooled blanket solutions, investigations on natural convection in reactor tanks, and the cooling properties of future containments for pressurized water reactors in the case of nuclear fusion accidents. (orig./GL) [de

  7. Reactor safety research in times of change

    International Nuclear Information System (INIS)

    Zipper, Reinhard

    2013-01-01

    Since the early 1970ies reactor safety research sponsored by the German Ministry of Economics an Technology and its predecessors and pursued independently from interests of industry or industrial associations as well as from current licensing issues significantly contributed to the extension of knowledge regarding risks and possible threats associated with the operation of nuclear power plants. The results of these research activities triggered several measures taken by industry and utilities to further enhance the internationally recognized high safety standards of nuclear power plants in Germany. Furthermore, by including especially universities in the distinguished research activities a large number of young scientists were given the opportunity to qualify in the field of nuclear reactor technology and safety thus contributing to the preservation of competence during the demographic change. The nuclear phase out in Germany affects also issues of reactor safety research in Germany. While Germany will progressively decrease and terminate the use of nuclear energy for public power supply other countries in Europe and in other parts of the world are continuing, expanding and even starting the use of nuclear power. As generally recognized, nuclear safety is an international issue and in the wake of the Fukushima disaster there are several initiatives to launch a system of internationally binding safety rules and guide lines. The German Competence Alliance therefore has elaborated a framework of areas were future reactor safety research will still be needed to support German efforts based on own and independent expertise to continuously develop and establish highest safety standards for the use of nuclear power supply domestic and abroad.

  8. Report of the review committee on evaluation of the R and D subjects in the field of nuclear safety research

    International Nuclear Information System (INIS)

    2000-09-01

    On the basis of the JAERI's Basic Guidelines for the Research Evaluation Methods and the Practices Manuals of the Institution Evaluation Committee and Research Evaluation Committee, the Ad Hoc Review Committee on Nuclear Safety Research composed of twelve experts was set up under the Research Evaluation Committee of the JAERI in order to review the R and D subjects to be implemented for five years starting in FY2000 in the Nuclear Safety Research Center (Department of Reactor Safety Research, Department of Fuel Cycle Safety Research and Department of Safety Research Technical Support). The Ad Hoc Review Committee meeting was held on January 20, 2000. According to the review methods including review items, points of review and review criteria, determined by the Research Evaluation Committee, the review was conducted based on the research plan documents submitted in advance and presentations by the Department Directors. The review report was submitted to the Research Evaluation Committee for further review and discussions in its meeting held on August 31, 2000. The Research Evaluation Committee recognized the review results as appropriate. This report describes the review results. (author)

  9. Water reactor safety research program. A description of current and planned research

    International Nuclear Information System (INIS)

    1978-07-01

    The U.S. Nuclear Regulatory Commission (NRC) sponsors confirmatory safety research on lightwater reactors in support of the NRC regulatory program. The principal responsibility of the NRC, as implemented through its regulatory program is to ensure that public health, public safety, and the environment are adequately protected. The NRC performs this function by defining conditions for the use of nuclear power and by ensuring through technical review, audit, and follow-up that these conditions are met. The NRC research program provides technical information, independent of the nuclear industry, to aid in discharging these regulatory responsibilities. The objectives of NRC's research program are the following: (1) to maintain a confirmatory research program that supports assurance of public health and safety, and public confidence in the regulatory program, (2) to provide objectively evaluated safety data and analytical methods that meet the needs of regulatory activities, (3) to provide better quantified estimates of the margins of safety for reactor systems, fuel cycle facilities, and transportation systems, (4) to establish a broad and coherent exchange of safety research information with other Federal agencies, industry, and foreign organization. Current and planned research toward these goals is described

  10. Keeping nurse researchers safe: workplace health and safety issues.

    Science.gov (United States)

    Barr, Jennieffer; Welch, Anthony

    2012-07-01

    This article is a report of a qualitative study of workplace health and safety issues in nursing research. Researcher health and safety have become increasing concerns as there is an increased amount of research undertaken in the community and yet there is a lack of appropriate guidelines on how to keep researchers safe when undertaking fieldwork. This study employed a descriptive qualitative approach, using different sources of data to find any references to researcher health and safety issues. A simple descriptive approach to inquiry was used for this study. Three approaches to data collection were used: interviews with 15 researchers, audits of 18 ethics applications, and exploration of the literature between 1992 and 2010 for examples of researcher safety issues. Data analysis from the three approaches identified participant comments, narrative descriptions or statements focused on researcher health and safety. Nurse researchers' health and safety may be at risk when conducting research in the community. Particular concern involves conducting sensitive research where researchers are physically at risk of being harmed, or being exposed to the development of somatic symptoms. Nurse researchers may perceive the level of risk of harm as lower than the actual or potential harm present in research. Nurse researchers do not consistently implement risk assessment before and during research. Researcher health and safety should be carefully considered at all stages of the research process. Research focusing on sensitive data and vulnerable populations need to consider risk minimization through strategies such as appropriate researcher preparation, safety during data collection, and debriefing if required. © 2012 Blackwell Publishing Ltd.

  11. Safety of research reactors (Design and Operation)

    International Nuclear Information System (INIS)

    Dirar, H. M.

    2012-06-01

    The primary objective of this thesis is to conduct a comprehensive up-to-date literature review on the current status of safety of research reactor both in design and operation providing the future trends in safety of research reactors. Data and technical information of variety selected historical research reactors were thoroughly reviewed and evaluated, furthermore illustrations of the material of fuel, control rods, shielding, moderators and coolants used were discussed. Insight study of some historical research reactors was carried with considering sample cases such as Chicago Pile-1, F-1 reactor, Chalk River Laboratories,. The National Research Experimental Reactor and others. The current status of research reactors and their geographical distribution, reactor category and utilization is also covered. Examples of some recent advanced reactors were studied like safety barriers of HANARO of Korea including safety doors of the hall and building entrance and finger print identification which prevent the reactor from sabotage. On the basis of the results of this research, it is apparent that a high quality of safety of nuclear reactors can be attained by achieving enough robust construction, designing components of high levels of efficiency, replacing the compounds of the reactor in order to avoid corrosion and degradation with age, coupled with experienced scientists and technical staffs to operate nuclear research facilities.(Author)

  12. Central Institute for Nuclear Research (1956 - 1979)

    International Nuclear Information System (INIS)

    Flach, G.; Bonitz, M.

    1979-12-01

    The Central Institute for Nuclear Research (ZfK) of the Academy of Sciences of the GDR is presented. This first overall survey covers the development of the ZfK since 1956, the main research activities and results, a description of the departments responsible for the complex implementation of nuclear research, the social services for staff and the activities of different organizations in the largest central institute of the Academy of Sciences of the GDR. (author)

  13. Institutional Research's Role in Strategic Planning

    Science.gov (United States)

    Voorhees, Richard A.

    2008-01-01

    Institutions that have organized and centralized their data enjoy an obvious advantage in grappling with strategic planning and other issues. As the drumbeat for accountability, planning, and demonstrating effectiveness to internal and external stakeholders intensifies, the stature and importance of institutional research offices on most campuses…

  14. Research on the improvement of nuclear safety

    International Nuclear Information System (INIS)

    Yoo, Keon Joong; Kim, Dong Soo; Kim, Hui Dong; Park, Chang Kyu

    1993-06-01

    To improve the nuclear safety, this project is divided into three areas which are the development of safety analysis technology, the development of severe accident analysis technology and the development of integrated safety assessment technology. 1. The development of safety analysis technology. The present research aims at the development of necessary technologies for nuclear safety analysis in Korea. Establishment of the safety analysis technologies enables to reduce the expenditure both by eliminating excessive conservatisms incorporated in nuclear reactor design and by increasing safety margins in operation. It also contributes to improving plant safety through realistic analyses of the Emergency Operating Procedures (EOP). 2. The development of severe accident analysis technology. By the computer codes (MELCOR and CONTAIN), the in-vessel and the ex-vessel severe accident phenomena are simulated. 3. The development of integrated safety assessment technology. In the development of integrated safety assessment techniques, the included research areas are the improvement of PSA computer codes, the basic study on the methodology for human reliability analysis (HRA) and common cause failure (CCF). For the development of the level 2 PSA computer code, the basic research for the interface between level 1 and 2 PSA, the methodology for the treatment of containment event tree are performed. Also the new technologies such as artificial intelligence, object-oriented programming techniques are used for the improvement of computer code and the assessment techniques

  15. Research reactor safety - an overview of crucial aspects

    International Nuclear Information System (INIS)

    Laverie, M.

    1998-01-01

    Chronology of the commissioning orders of the French research reactors illustrates the importance of the time factor. When looking at older reactors, one must, on one hand, demonstrate, not only the absence of risks tied to the reactor's ageing, but, on the other hand, adapt the reactor's original technical designs to today's safety practices and standards. The evolution of reactor safety requirements over the last twenty years sometimes makes this adaptation difficult. The design of the next research reactors, after a one to two decades pause in construction, will require to set up new safety assessment bases that will have to take into account the nuclear power plant safety evolution. As a general statement, research reactor safety approaches will require the incorporation of specific design rules for research reactors: experience feedback for one of a kind design, frequent modifications required by research programmes, special operational requirements with operators/researchers interfaces. (author)

  16. Organising a manuscript reporting quality improvement or patient safety research.

    Science.gov (United States)

    Holzmueller, Christine G; Pronovost, Peter J

    2013-09-01

    Peer-reviewed publication plays important roles in disseminating research findings, developing generalisable knowledge and garnering recognition for authors and institutions. Nonetheless, many bemoan the whole manuscript writing process, intimidated by the arbitrary and somewhat opaque conventions. This paper offers practical advice about organising and writing a manuscript reporting quality improvement or patient safety research for submission to a peer-reviewed journal. Each section of the paper discusses a specific manuscript component-from title, abstract and each section of the manuscript body, through to reference list and tables and figures-explaining key principles, offering content organisation tips and providing an example of how this section may read. The paper also offers a checklist of common mistakes to avoid in a manuscript.

  17. Recent innovations in IFR safety research

    International Nuclear Information System (INIS)

    Wade, D.C.

    1994-01-01

    Recent progress in IFR safety research suggests potential for two extensions of passive features to improve the robustness of safety response. This report provides a discussion of these recent innovations

  18. Safety evaluation of the Dalat research reactor operation

    International Nuclear Information System (INIS)

    Long, V.H.; Lam, P.V.; An, T.K.

    1989-01-01

    After an introduction presenting the essential characteristics of the Dalat Nuclear Research Reactor, the document presents i) The safety assurance condition of the reactor, ii) Its safety behaviour after 5 years of operation, iii) Safety research being realized on the reactor. Following is questionnaire of safety evaluation and a list of attachments, which concern the reactor

  19. Alligator Rivers Region Research Institute: annual research summary 1989-1990

    International Nuclear Information System (INIS)

    1991-01-01

    The Alligator Rivers Region Research Institute (ARRRI) research activities are associated with an assessment of environmental effect of mining in the region. While emphasis on baseline research is now much reduced, some projects are still necessary because of significant changes in the Magela Creek system, because new areas of proposed mining have been identified (e.g. Coronation Hill) and because the emphasis now being placed on rehabilitation research requires a sound knowledge of the Region's flora. The ARRRI rehabilitation research program has concentrated on the Ranger mine site, principally because it is at a critical planning stage where detailed research information is required. With regard to the development of techniques, research at the Institute has led to the development of specific analytical methods or protocols that can be used in assessing environmental impact. 39 tabs., 42 figs

  20. [Hospital biomedical research through the satisfaction of a Health Research Institute professionals].

    Science.gov (United States)

    Olmedo, C; Plá, R; Bellón, J M; Bardinet, T; Buño, I; Bañares, R

    2015-01-01

    A Health Research Institute is a powerful strategic commitment to promote biomedical research in hospitals. To assess user satisfaction is an essential quality requirement. The aim of this study is to evaluate the professional satisfaction in a Health Research Institute, a hospital biomedical research centre par excellence. Observational study was conducted using a satisfaction questionnaire on Health Research Institute researchers. The explored dimensions were derived from the services offered by the Institute to researchers, and are structured around 4 axes of a five-year Strategic Plan. A descriptive and analytical study was performed depending on adjustment variables. Internal consistency was also calculated. The questionnaire was completed by 108 researchers (15% response). The most valued strategic aspect was the structuring Areas and Research Groups and political communication and dissemination. The overall rating was 7.25 out of 10. Suggestions for improvement refer to the need for help in recruitment, and research infrastructures. High internal consistency was found in the questionnaire (Cronbach alpha of 0.9). So far research policies in health and biomedical environment have not been sufficiently evaluated by professionals in our field. Systematic evaluations of satisfaction and expectations of key stakeholders is an essential tool for analysis, participation in continuous improvement and advancing excellence in health research. Copyright © 2015 SECA. Published by Elsevier Espana. All rights reserved.

  1. Seismic safety research program plan

    International Nuclear Information System (INIS)

    1985-06-01

    This plan describes the safety issues, regulatory needs, and the research necessary to address these needs. The plan also discusses the relationship between current and proposed research within the NRC and research sponsored by other government agencies, universities, industry groups, professional societies, and foreign sources

  2. Research reactor safety - an overview of crucial aspects

    Energy Technology Data Exchange (ETDEWEB)

    Laverie, M. [Atomic Energy Commission, Saclay, F-91191 Gif sur Yvette (France)

    1998-07-01

    Chronology of the commissioning orders of the French research reactors illustrates the importance of the time factor. When looking at older reactors, one must, on one hand, demonstrate, not only the absence of risks tied to the reactor's ageing, but, on the other hand, adapt the reactor's original technical designs to today's safety practices and standards. The evolution of reactor safety requirements over the last twenty years sometimes makes this adaptation difficult. The design of the next research reactors, after a one to two decades pause in construction, will require to set up new safety assessment bases that will have to take into account the nuclear power plant safety evolution. As a general statement, research reactor safety approaches will require the incorporation of specific design rules for research reactors: experience feedback for one of a kind design, frequent modifications required by research programmes, special operational requirements with operators/researchers interfaces. (author)

  3. Does lean management improve patient safety culture? An extensive evaluation of safety culture in a radiotherapy institute.

    Science.gov (United States)

    Simons, Pascale A M; Houben, Ruud; Vlayen, Annemie; Hellings, Johan; Pijls-Johannesma, Madelon; Marneffe, Wim; Vandijck, Dominique

    2015-02-01

    The importance of a safety culture to maximize safety is no longer questioned. However, achieving sustainable culture improvements are less evident. Evidence is growing for a multifaceted approach, where multiple safety interventions are combined. Lean management is such an integral approach to improve safety, quality and efficiency and therefore, could be expected to improve the safety culture. This paper presents the effects of lean management activities on the patient safety culture in a radiotherapy institute. Patient safety culture was evaluated over a three year period using triangulation of methodologies. Two surveys were distributed three times, workshops were performed twice, data from an incident reporting system (IRS) was monitored and results were explored using structured interviews with professionals. Averages, chi-square, logistical and multi-level regression were used for analysis. The workshops showed no changes in safety culture, whereas the surveys showed improvements on six out of twelve dimensions of safety climate. The intention to report incidents not reaching patient-level decreased in accordance with the decreasing number of reports in the IRS. However, the intention to take action in order to prevent future incidents improved (factorial survey presented β: 1.19 with p: 0.01). Due to increased problem solving and improvements in equipment, the number of incidents decreased. Although the intention to report incidents not reaching patient-level decreased, employees experienced sustained safety awareness and an increased intention to structurally improve. The patient safety culture improved due to the lean activities combined with an organizational restructure, and actual patient safety outcomes might have improved as well. Copyright © 2014 Elsevier Ltd. All rights reserved.

  4. Amendment of the Order of 2 November 1976 setting up an Institute for Protection and Nuclear Safety (29 October 1981)

    International Nuclear Information System (INIS)

    1981-01-01

    The Institute for Protection and Nuclear Safety was set up within the Atomic Energy Commission by an Order of 2 November 1976 now amended by this new Order, which specifies that, in connection with nuclear safety, the Institute provides direct technical support to the Central Service for the Safety of Nuclear Installations. (NEA) [fr

  5. The RA nuclear research reactor at VINCA Institute as an engineering and scientific challenge

    International Nuclear Information System (INIS)

    Mesarovic, M.

    1997-01-01

    The RA nuclear research at the Vinca Institute of Nuclear Sciences is the largest nuclear research facility in Yugoslavia and belongs to that generation of research reactors which have had an important contribution to nuclear technology development. As these older reactors were generally not built to specific nuclear standards, new safety systems had to be installed at the RA reactor for a renewal of its operating licence in 1984 and it was shut down, after 25 years of operation. Although all the required and several additional systems were built for the restart of the RA reactor, a disruption of foreign delivery of new control equipment caused its conversion to a 'dormant' facility, and it is still out of operation. Therefore, the future status of the RA reactor presents an engineering and scientific challenge to the engineers and scientists from Yugoslavia and other countries that may be interested to participate. To attract their attention on the subject, principal features of the RA reactor and its present status are described in detail, based on a recent engineering economic and safety evaluation. A comparative review of the world research reactors is also presented.(author)

  6. IAEA activities in the field of research reactors safety

    International Nuclear Information System (INIS)

    Ciuculescu, C.; Boado Magan, H.J.

    2004-01-01

    IAEA activities in the field of research reactor safety are included in the programme of the Division of Nuclear Installations Safety. Following the objectives of the Division, the results of the IAEA missions and the recommendations from International Advisory Groups, the IAEA has conducted in recent years a certain number of activities aiming to enhance the safety of research reactors. The following activities will be presented: (a) the new Requirements for the Safety of Research Reactors, main features and differences with previous standards (SS-35-S1 and SS-35-S2) and the grading approach for implementation; (b) new documents being developed (safety guides, safety reports and TECDOC's); (c) activities related to the Incident Reporting System for Research Reactor (IRSRR); (d) the new features implemented for the INSARR missions; (e) the Code of Conduct on the Safety of Research Reactors adopted by the Board of Governors on 8 March 2004, following the General Conference Resolution GC(45)/RES/10; and (f) the survey on the safety of research reactors published on the IAEA website on February 2003 and the results obtained. (author)

  7. Safety research needs for Russian-designed reactors

    International Nuclear Information System (INIS)

    1998-01-01

    In June 1995, an OECD Support Group was set up to perform a broad study of the safety research needs of Russian-designed reactors. This Support Group was endorsed by the CSNI. The Support Group, which is composed of senior experts on safety research from several OECD countries and from Russia, prepared this Report. The Group reviewed the safety research performed to support Russian-designed reactors and set down its views on future needs. The review concentrates on the following main topics: Thermal-Hydraulics/Plant Transients for VVERs; Integrity of Equipment and Structures for VVERs; Severe Accidents for VVERs; Operational Safety Issues; Thermal-Hydraulics/Plant Transients for RBMKs; Integrity of Equipment and Structures for RBMKs; Severe Accidents for RBMKs. (K.A.)

  8. The organization of research reactor safety in the UKAEA

    International Nuclear Information System (INIS)

    Redpath, W.

    1983-01-01

    The present state of organization and development of research reactor safety in the UKAEA are outlined by addressing the fundamental safety principles which have been adopted in keeping with national health and safety requirement. The organisation, assessment and monitoring of research reactor safety on complex multi-discipline and multi-activity nuclear research and development site are discussed. Methods of safety assessment, such as probabilistic risk assessment and risk acceptance criteria, which have been developed and applied in practice are explained, and some indication of the directions in which some of the current developments in the safety of UKAEA research reactors is also included. (A.J.)

  9. List of reports in the field of reactor safety research of BMFT, CEA, EPRI, JSTA and USNRC

    International Nuclear Information System (INIS)

    1990-05-01

    This list reviews reports from the Federal Republic of Germany, from France, from Japan and from the United States of America concerning single problems in the field of Reactor Safety Research. According to the cooperation of the Bundesminister fuer Forschung und Technologie (BMFT) with the Commissariat a l'Energie Atomique (CEA), the Japan Science and Technology Agency (JSTA), the Electric Power Research Institute (EPRI) and the United States Nuclear Regulatory Commission, these reports are available in the Gesellschaft fuer Reaktorsicherheit (GRS). The list pursues the following order: Country of origin, problem area concerned, according to the Reactor Safety Research Programme of the BMFT, reporting organization. The list of reports appears quarterly. (orig.) [de

  10. List of reports in the field of reactor safety research from BMFT, CEA, EPRI, JSTA and USNRC

    International Nuclear Information System (INIS)

    1991-08-01

    This list reviews reports from the Federal Republic of Germany, from France, from Japan and from the United States of America concerning single problems in the field of reactor safety research. According to the cooperation of the Bundesminister fuer Forschung und Technologie (BMFT) with the Commissariat a l'Energie Atomique (CEA), the Japan Science and Technology Agency (JSTA), the Electric Power Research Institute (EPRI) and the United States Nuclear Regulatory Commission, these reports are available in the Gesellschaft fuer Reaktorsicherheit (GRS). The list pursues the following order: Country of origin, problem area concerned, according to the Reactor Safety Research Program of the BMFT, reporting organization. The list of reports appears quarterly. (orig./HP) [de

  11. List of reports in the field of reactor safety research of BMFT, CEA, EPRI, JSTA and USNRC

    International Nuclear Information System (INIS)

    1990-02-01

    This list reviews reports from the Federal Republic of Germany, from France, from Japan and from the United States of America concerning single problems in the field of Reactor Safety Research. According to the cooperation of the Bundesminister fuer Forschung und Technologie (BMFT) with the Commissariat a l'Energie Atomique (CEA), the Japan Science and Technology Agency (JSTA), the Electric Power Research Institute (EPRI) and the United States Nuclear Regulatory Commission, these reports are available in the Gesellschaft fuer Reaktorsicherheit (GRS). The list pursues the following order: Country of origin, problem area concerned, according to the Reactor Safety Research Programm of the BMFT, reporting organization. The list of reports appears quarterly. (orig.) [de

  12. List of reports in the field of reactor safety research of BMFT, CEA, EPRI, JSTA and USNRC

    International Nuclear Information System (INIS)

    1989-05-01

    This list reviews reports from the Federal Republic of Germany, from France, from Japan and from the United States of America concerning single problems in the field of Reactor Safety Research. According to the cooperation of the Bundesminister fuer Forschung und Technologie (BMFT) with the Commissariat a l'Energie Atomique (CEA), the Japan Science and Technology Agency (JSTA), the Electric Power Research Institute (EPRI) and the United States Nuclear Regulatory Commission, these reports are available in the Gesellschaft fuer Reaktorsicherheit (GRS). The list pursues the following order: Country of origin, problem area concerned, according to the Reactor Safety Research Programme of the BMFT, reporting organization. The list of reports appears quarterly. (orig.) [de

  13. List of reports in the field of reactor safety research of BMFT, CEA, EPRI, JSTA und USNRC

    International Nuclear Information System (INIS)

    1989-11-01

    This list reviews reports from the Federal Republic of Germany, from France, from Japan and from the United States of America concerning single problems in the field of Reactor Safety Research. According to the cooperation of the Bundesminister fuer Forschung und Technologie (BMFT) with the Commissariat a l'Engergie Atomique (CEA), the Japan Science and Technology Agency (JSTA), the Electric Power Research Institute (EPRI) and the United States Nuclear Regulatory Commission, these reports are available in the Gesellschaft fuer Reaktorsicherheit (GRS). The list pursues the following order: Country of origin, problem area concerned, according to the Reactor Safety Research Programme of the BMFT, reporting organization. The list of reports appears quarterly. (orig.) [de

  14. List of reports of BMFT, CEA, EPRI, JSTA and USNRC in the field of reactor safety research

    International Nuclear Information System (INIS)

    1985-04-01

    This list reviews reports from the Federal Republic of Germany, from France, from Japan and from the United States of America concerning special problems in the field of Reactor Safety Research. According to the cooperation of the Bundesminister fuer Forschung und Technologie (BMFT) with the Commisariat a l'Energie Atomique (CEA), the Japan Science and Technology Agency (JSTA), the Electrical Power Research Institute (EPRI) and the United States Nuclear Regulatory Commision, these reports are available in the Gesellschaft fuer Reaktorsicherheit (GRS). The list pursues the following order: Country of origin, problem area concerned, according to the Reactor Safety Research Programm of the BMFT, reporting organization. The list of reports appears quaterly. (orig./HP) [de

  15. Academic Libraries’ Role in Improving Institutions Research Impact

    KAUST Repository

    Tamarkin, Molly

    2015-11-11

    In the changing landscape of scientific research and scholarly communication, importance of “quality in research”, “reviewed research” and “reviewed publications” in qualifying for the ratings and rankings are widely discussed. While publishing the research pieces in peer-reviewed and highly ranked journals are increasingly important, there are different methods and tools to be in place at Institutional level to increase researchers’ profile and the ranking of the institutions. As a young research based university created in 2009, King Abdullah University of Science and Technology (KAUST) focuses on the bibliometrics and altemetrics tools, author affiliations, author naming and plug-ins to different search engines, research evaluation systems as well as to research repositories. The University has launched an institutional repository in September 2012 as a home for the intellectual outputs of KAUST researchers, and then adopted the first institutional open access mandate in the Arab region effective June 31, 2014. Integration with ORCID became a key element in this process and the best way to ensure data quality for researcher’s scientific contributions systematically. We will present the inclusion and creation of ORCID identifiers in the existing systems as an institutional member to ORCID, and the creation of dedicated integration tools with Current Research Information System (CRIS) as a standardized common resource to monitor KAUST research outputs. We will also present our experiences in awareness programs, trainings, outreach, implementation of systems and tools like PlumX, as well as our approach in improving the research impact and profiling our Institution’s research to the world.

  16. Academic Libraries’ Role in Improving Institutions Research Impact

    KAUST Repository

    Tamarkin, Molly; Vijayakumar, J.K.; Baessa, Mohamed A.; Grenz, Daryl M.

    2015-01-01

    In the changing landscape of scientific research and scholarly communication, importance of “quality in research”, “reviewed research” and “reviewed publications” in qualifying for the ratings and rankings are widely discussed. While publishing the research pieces in peer-reviewed and highly ranked journals are increasingly important, there are different methods and tools to be in place at Institutional level to increase researchers’ profile and the ranking of the institutions. As a young research based university created in 2009, King Abdullah University of Science and Technology (KAUST) focuses on the bibliometrics and altemetrics tools, author affiliations, author naming and plug-ins to different search engines, research evaluation systems as well as to research repositories. The University has launched an institutional repository in September 2012 as a home for the intellectual outputs of KAUST researchers, and then adopted the first institutional open access mandate in the Arab region effective June 31, 2014. Integration with ORCID became a key element in this process and the best way to ensure data quality for researcher’s scientific contributions systematically. We will present the inclusion and creation of ORCID identifiers in the existing systems as an institutional member to ORCID, and the creation of dedicated integration tools with Current Research Information System (CRIS) as a standardized common resource to monitor KAUST research outputs. We will also present our experiences in awareness programs, trainings, outreach, implementation of systems and tools like PlumX, as well as our approach in improving the research impact and profiling our Institution’s research to the world.

  17. List of reports in the field of reactor safety research sponsored by BMFT, CEA, EPRI, JSTA and USNRC

    International Nuclear Information System (INIS)

    1987-05-01

    This list reviews reports from the Federal Republic of Germany, from France, from Japan and from the United States of America concerning single problems in the field of reactor safety research. According to the cooperation of the Federal Minister for Research and Technology (BMFT) with the Commissariat a l'Energie Atomique (CEA), the Japan Science and Technology Agency (JSTA), the Electric Power Research Institute (EPRI) and the United States Nuclear Regulatory Commission, these reports are available in the Gesellschaft fuer Reaktorsicherheit (GRS). The list pursues the following order: Country of origin, problem area concerned, according to the Reactor Safety Research Programm of the BMFT, reporting organization. The list of reports appears quarterly. (orig./HP) [de

  18. List of reports in the field of reactor safety research sponsored by BMFT, CEA, EPRI, JSTA and USNRC

    International Nuclear Information System (INIS)

    1987-02-01

    This list reviews reports from the Federal Republic of Germany, from France, from Japan and from the United States of America concerning single problems in the field of reactor safety research. According to the cooperation of the Federal Minister for Research and Technology (BMFT) with the Commissariat a l'Energie Atomique (CEA), the Japan Science and Technology Agency (JSTA), the Electric Power Research Institute (EPRI) and the United States Nuclear Regulatory Commission, these reports are available in the Gesellschaft fuer Reaktorsicherheit (GRS). The list pursues the following order: Country of origin, problem area concerned, according to the Reactor Safety Research Programm of the BMFT, reporting organization. The list of reports appears quarterly. (orig./HP) [de

  19. Institutional research and development, FY 1987

    International Nuclear Information System (INIS)

    Struble, G.L.; Lawler, G.M.; Crawford, R.B.; Kirvel, R.D.; Peck, T.M.; Prono, J.K.; Strack, B.S.

    1987-01-01

    The Institutional Research and Development program at Lawrence Livermore National Laboratory fosters exploratory work to advance science and technology, disciplinary research to develop innovative solutions to problems in various scientific fields, and long-term interdisciplinary research in support of defense and energy missions. This annual report describes research funded under this program for FY87

  20. Information Science Research Institute. Quarterly progress report

    Energy Technology Data Exchange (ETDEWEB)

    Nartker, T.A.

    1994-06-30

    This is a second quarter 1194 progress report on the UNLV Information Science Research Institute. Included is symposium activity; staff activity; document analysis program; text retrieval program; institute activity; and goals.

  1. Research program on nuclear technology and nuclear safety - Synthesis report 2008

    International Nuclear Information System (INIS)

    Dreier, J.

    2009-06-01

    This report for the Swiss Federal Office of Energy (SFOE) summarises the program's main points of interest, work done in the year 2008 and the results obtained. Four main projects at the Paul Scherrer Institute's Laboratory for Reactor Physics and System Behaviour LRS are noted, and work done at the Laboratories for Thermohydraulics LTH, Nuclear Materials LNM, Final Depository Safety LES and Energy System Analyses LEA are discussed. The results obtained in thirteen areas of research in 2008 are discussed in some detail. Finally, national and international co-operation is briefly looked at and work to be done in 2009 is reviewed. The report is completed with a list of the PSI research and development projects referred to

  2. Nuclear safety research in HGF 2012; Fortschrittsbericht 2012. Programm 'Nukleare Sicherheitsforschung' Helmholtz-Gemeinschaft

    Energy Technology Data Exchange (ETDEWEB)

    Anon.

    2013-06-15

    in the Nuclear Competence Association. The Forschungszentrum Juelich GmbH, HZDR Helmholtz-Zentrum Dresden-Rossendorf and the KIT Karlsruhe Institute of Technology are involved in the Nuclear Safety Research Program within the Helmholtz Association. The work and results in 2012 are presented. (orig.)

  3. Institutional research and development, FY 1987

    Energy Technology Data Exchange (ETDEWEB)

    Struble, G.L.; Lawler, G.M.; Crawford, R.B.; Kirvel, R.D.; Peck, T.M.; Prono, J.K.; Strack, B.S. (eds.)

    1987-01-01

    The Institutional Research and Development program at Lawrence Livermore National Laboratory fosters exploratory work to advance science and technology, disciplinary research to develop innovative solutions to problems in various scientific fields, and long-term interdisciplinary research in support of defense and energy missions. This annual report describes research funded under this program for FY87. (DWL)

  4. Reports on the research projects in the field of reactor safety sponsored by the Federal Ministry of Science and Technology

    International Nuclear Information System (INIS)

    1975-12-01

    Investigations on the safety of Light Water Reactors (LWR) being performed in the framework of the safety program 'Reactor Safety' are sponsored by the Bundesminister fuer Forschung und Technologie (BMFT - Secretary of State for Research and Technology). Objective of this program is to continue improving the safety of LWR, in order to minimize the risk for the environment. With grant assistance from the Bundesminister des Innern (BMI - Secretary of State for Home Affairs) research contracts in the field of reactor safety are being performed. Results of these projects should contribute to resolve questions arising nuclear licensing procedures. The Forschungsbetreuung (FB - research supervision department) at the Institute for Reactor Safety (IRS), as consultants to BMFT and BMI, provides information about the progress of investigations. Individual reports will be prepared and put into standard forms by the research contractors. Each report gives information on: 1) the work accomplished, 2) the results obtained, 3) the work planned to be continued. Initial reports of research projects describe in addition the purpose of the work. A BMFT-research program on the safety of Fast Breeders (Schneller Brutreaktor - SBR) is presently under discussion. In order to define several problems, investigations included in the present compilation (RS 139, 140, 143, 162) will be previously performed. (orig.) [de

  5. Reports on the research projects in the field of reactor safety sponsored by the Federal Ministry of Science and Technology

    International Nuclear Information System (INIS)

    1976-12-01

    Investigations on the safety of light water reactors (LWR) being performed in the framework of the safety program 'Reactor Safety' are sponsored by the Bundesminister fuer Forschung und Technologie (BMFT - Secretary of State for Research and Technology). Objective of this program is to continue improving the safety of LWR, in order to minimize the risk for the environment. With grant assistance from the Bundesminister des Innern (BMI - Secretary of State for Home Affairs) research contrcts in the field of reactor safety are being performed. Results of these projects should contribute to resolve questions arising nuclear licensing procedures. The Forschungsbetreuung (FB - research supervision department) at the Institute for Reactor Safety (IRS), as consultants to BMFT and BMI, provides information about the progress of investigations. Individual reports will be prepared and put into standard forms by the research contractors. Each report gives information on: 1) the work accomplished, 2) the results obtained, 3) the work planned to be continued. Initial reports of research projects describe in addition the purpose of the work. A BMFT-research program on the safety of Fast Breeders (Schneller Brutreaktor - SRB) is presently under discussion. In order to define several problems, investigations included in the present compilation (RS 139, 140, 143, 162) will be previously performed. (orig.) [de

  6. Report of the evaluation by the Ad Hoc Review Committee on Nuclear Safety Research. Result evaluation in fiscal year 2000

    International Nuclear Information System (INIS)

    2001-06-01

    The Research Evaluation Committee, which consisted of 14 members from outside of the Japan Atomic Energy Research Institute (JAERI), set up an Ad Hoc Review Committee on Nuclear Safety Research in accordance with the Fundamental Guideline for the Evaluation of Research and Development (R and D) at JAERI' and its subsidiary regulations in order to evaluate the R and D accomplishments achieved for five years from Fiscal Year 1995 to Fiscal Year 1999 at Department of Reactor Safety Research, Department of Fuel Cycle Safety Research, Department of Environmental Safety Research and Department of Safety Research Technical Support in Tokai Research Establishment at JAERI. The Ad Hoc Review Committee consisted of 11 specialists from outside of JAERI. The Ad Hoc Review Committee conducted its activities from December 2000 to February 2001. The evaluation was performed on the basis of the materials submitted in advance and of the oral presentations made at the Ad Hoc Review Committee meeting which was held on December 11, 2000, in line with the items, viewpoints, and criteria for the evaluation specified by the Research Evaluation Committee. The result of the evaluation by the Ad Hoc Review Committee was submitted to the Research Evaluation Committee, and was judged to be appropriate at its meeting held on March 16, 2001. This report describes the result of the evaluation by the Ad Hoc Review Committee on Nuclear Safety Research. (author)

  7. Development of Safety Review Guidance for Research and Training Reactors

    International Nuclear Information System (INIS)

    Oh, Kju-Myeng; Shin, Dae-Soo; Ahn, Sang-Kyu; Lee, Hoon-Joo

    2007-01-01

    The KINS already issued the safety review guidance for pressurized LWRs. But the safety review guidance for research and training reactors were not developed. So, the technical standard including safety review guidance for domestic research and training reactors has been applied mutates mutandis to those of nuclear power plants. It is often difficult for the staff to effectively perform the safety review of applications for the permit by the licensee, based on peculiar safety review guidance. The NRC and NSC provide the safety review guidance for test and research reactors and European countries refer to IAEA safety requirements and guides. The safety review guide (SRG) of research and training reactors was developed considering descriptions of the NUREG- 1537 Part 2, previous experiences of safety review and domestic regulations for related facilities. This study provided the safety review guidance for research and training reactors and surveyed the difference of major acceptance criteria or characteristics between the SRG of pressurized light water reactor and research and training reactors

  8. Marketing based on knowledge as a basis for strategy of research institution – on the example of the Packaging Research Institute

    Directory of Open Access Journals (Sweden)

    Stanislaw Tkaczyk

    2013-09-01

    Full Text Available Basis for marketing activities of COBRO – Packaging Research Institute are two main issues. First of all, as a small research and development centre, COBRO has no funds to carry out specialized marketing department. On the other hand, due to huge growth of packaging market, all needs of stakeholders – companies but also other research institutions seeking consortium members – cannot be entirely identified or forecasted, and practical solutions are created in the course of cooperation. For all that reasons Institute has developed its own concept of the knowledge-based marketing, which means more flexible use of the potential of academics and research employees.

  9. THE CONTRIBUTION OF RESEARCH INSTITUTES IN EUREKA PROJECTS

    NARCIS (Netherlands)

    VANROSSUM, W; CABO, PG

    1995-01-01

    Technological cooperation between industrial firms and research institutes is studied at the project level. The various forms of cooperation, and the instances in which they are advantageous, are discussed. The authors then focus on situations in which the research institute acts as 'knowledge

  10. Research Networking Systems: The State of Adoption at Institutions Aiming to Augment Translational Research Infrastructure.

    Science.gov (United States)

    Obeid, Jihad S; Johnson, Layne M; Stallings, Sarah; Eichmann, David

    Fostering collaborations across multiple disciplines within and across institutional boundaries is becoming increasingly important with the growing emphasis on translational research. As a result, Research Networking Systems that facilitate discovery of potential collaborators have received significant attention by institutions aiming to augment their research infrastructure. We have conducted a survey to assess the state of adoption of these new tools at the Clinical and Translational Science Award (CTSA) funded institutions. Survey results demonstrate that most CTSA funded institutions have either already adopted or were planning to adopt one of several available research networking systems. Moreover a good number of these institutions have exposed or plan to expose the data on research expertise using linked open data, an established approach to semantic web services. Preliminary exploration of these publically-available data shows promising utility in assessing cross-institutional collaborations. Further adoption of these technologies and analysis of the data are needed, however, before their impact on cross-institutional collaboration in research can be appreciated and measured.

  11. Example of a SWOV (Institute for Road Safety Research) safety study : "Avenida Marginal", Lisbon 1989.

    NARCIS (Netherlands)

    Janssen, S.T.M.C.

    1991-01-01

    This paper describes the accident study on the Marginal Road between Alges and Cascais in Portugal. The aim of this study was to produce a philosophy for a strategy to select the best safety measures out of several which had already been proposed. The general point of departure in this philosophy is

  12. Planning the Safety of Atrial Fibrillation Ablation Registry Initiative (SAFARI) as a Collaborative Pan-Stakeholder Critical Path Registry Model: a Cardiac Safety Research Consortium "Incubator" Think Tank.

    Science.gov (United States)

    Al-Khatib, Sana M; Calkins, Hugh; Eloff, Benjamin C; Packer, Douglas L; Ellenbogen, Kenneth A; Hammill, Stephen C; Natale, Andrea; Page, Richard L; Prystowsky, Eric; Jackman, Warren M; Stevenson, William G; Waldo, Albert L; Wilber, David; Kowey, Peter; Yaross, Marcia S; Mark, Daniel B; Reiffel, James; Finkle, John K; Marinac-Dabic, Danica; Pinnow, Ellen; Sager, Phillip; Sedrakyan, Art; Canos, Daniel; Gross, Thomas; Berliner, Elise; Krucoff, Mitchell W

    2010-01-01

    Atrial fibrillation (AF) is a major public health problem in the United States that is associated with increased mortality and morbidity. Of the therapeutic modalities available to treat AF, the use of percutaneous catheter ablation of AF is expanding rapidly. Randomized clinical trials examining the efficacy and safety of AF ablation are currently underway; however, such trials can only partially determine the safety and durability of the effect of the procedure in routine clinical practice, in more complex patients, and over a broader range of techniques and operator experience. These limitations of randomized trials of AF ablation, particularly with regard to safety issues, could be addressed using a synergistically structured national registry, which is the intention of the SAFARI. To facilitate discussions about objectives, challenges, and steps for such a registry, the Cardiac Safety Research Consortium and the Duke Clinical Research Institute, Durham, NC, in collaboration with the US Food and Drug Administration, the American College of Cardiology, and the Heart Rhythm Society, organized a Think Tank meeting of experts in the field. Other participants included the National Heart, Lung and Blood Institute, the Centers for Medicare and Medicaid Services, the Agency for Healthcare Research and Quality, the Society of Thoracic Surgeons, the AdvaMed AF working group, and additional industry representatives. The meeting took place on April 27 to 28, 2009, at the US Food and Drug Administration headquarters in Silver Spring, MD. This article summarizes the issues and directions presented and discussed at the meeting. Copyright 2010 Mosby, Inc. All rights reserved.

  13. Alligator Rivers Regions Research Institute research report 1983-84

    International Nuclear Information System (INIS)

    1984-01-01

    The Institute undertakes and coordinates research required to ensure the protection of the environment in the Alligator Rivers Region from any consequences resulting from the mining and processing of uranium ore. Research projects outlined are in aquatic biology, terrestrial ecology, analytical chemistry, environmental radioactivity and geomorphology

  14. Anthropology in Agricultural Health and Safety Research and Intervention.

    Science.gov (United States)

    Arcury, Thomas

    2017-01-01

    Agriculture remains a dangerous industry, even as agricultural science and technology continue to advance. Research that goes beyond technological changes to address safety culture and policy are needed to improve health and safety in agriculture. In this commentary, I consider the potential for anthropology to contribute to agricultural health and safety research by addressing three aims: (1) I briefly consider what the articles in this issue of the Journal of Agromedicine say about anthropologists in agricultural health and safety; (2) I discuss what anthropologists can add to agricultural health and safety research; and (3) I examine ways in which anthropologists can participate in agricultural health and safety research. In using their traditions of rigorous field research to understand how those working in agriculture perceive and interpret factors affecting occupational health and safety (their "emic" perspective), and translating this perspective to improve the understanding of occupational health professionals and policy makers (an "etic" perspective), anthropologists can expose myths that limit improvements in agricultural health and safety. Addressing significant questions, working with the most vulnerable agricultural communities, and being outside establishment agriculture provide anthropologists with the opportunity to improve health and safety policy and regulation in agriculture.

  15. Results of 1989/90 research and development activities at KfK Institute for Reactor Components

    International Nuclear Information System (INIS)

    1991-03-01

    R and D activities at IRB (Institut fuer Reaktorbauelemente - Institute for Reactor Components) are dedicated to thermodynamics and fluid dynamics. Emphasis is on the design of nuclear reactor and fusion reactor components. Environmental engineering was added recently. Most activities are applications-oriented. Fundamental investigations focus on energy research and energy technology. The activities are carried out in the framework of different projects (PKF/nuclear fusion, PSF/nuclear safety, PSU/pollution control). Points of main effort are the development of basic liquid-metal-cooled blanket solutions, investigations on natural convection in reactor ranks, and the cooling properties of future containments for pressurized water reactors in the case of nuclear fusion accidents. (orig./GL) [de

  16. 76 FR 65729 - Board of Scientific Counselors, National Institute for Occupational Safety and Health (BSC, NIOSH)

    Science.gov (United States)

    2011-10-24

    ... Recommendations for Respiratory Diseases, Hearing Loss Prevention, Personal Protective Technologies, and Health... Scientific Counselors, National Institute for Occupational Safety and Health (BSC, NIOSH) In accordance with..., and demonstrations relating to occupational safety and health and to mine health. The Board of...

  17. Current state of the auto-evaluation process of the behaviour code in the safety of research reactors in Mexico

    International Nuclear Information System (INIS)

    Mamani A, Y. R.; Salgado G, J. R.

    2011-11-01

    In Mexico, the regulator organism in nuclear matter is the National Commission of Nuclear Safety and Safeguards, and a nuclear research reactor exists, the TRIGA Mark III, operated by the National Institute of Nuclear Research. In this work the main aspects of the current state and the future challenges are presented with relationship to the installation of the auto-evaluation process of the behaviour code in the safety of research reactors for the TRIGA reactor case. Additionally, the legal mark of the licensing process for the nuclear activities in a research reactor is described in a brief way, and the main characteristics of the reactor, the uses for the isotopes production, the administration and the verification of the safety, the administration program of the radiological protection, the emergency plan and the operation personnel qualification are emphasized. (Author)

  18. Research on fuzzy comprehensive assessment method of nuclear power plant safety culture

    International Nuclear Information System (INIS)

    Xiang Yuanyuan; Chen Xukun; Xu Rongbin

    2012-01-01

    Considering the traits of safety culture in nuclear plant, 38 safety culture assessment indexes are established from 4 aspects such as safety values, safety institution, safety behavior and safety sub- stances. Based on it, a comprehensive assessment method for nuclear power plant safety culture is constructed by using AHP (Analytic Hierarchy Process) approach and fuzzy mathematics. The comprehensive assessment method has the quality of high precision and high operability, which can support the decision making of safety culture development. (authors)

  19. An overview-probabilistic safety analysis for research reactors

    International Nuclear Information System (INIS)

    Liu Jinlin; Peng Changhong

    2015-01-01

    For long-term application, Probabilistic Safety Analysis (PSA) has proved to be a valuable tool for improving the safety and reliability of power reactors. In China, 'Nuclear safety and radioactive pollution prevention 'Twelfth Five Year Plan' and the 2020 vision' raises clearly that: to develop probabilistic safety analysis and aging evaluation for research reactors. Comparing with the power reactors, it reveals some specific features in research reactors: lower operating power, lower coolant temperature and pressure, etc. However, the core configurations may be changed very often and human actions play an important safety role in research reactors due to its specific experimental requirement. As a result, there is a necessary to conduct the PSA analysis of research reactors. This paper discusses the special characteristics related to the structure and operation and the methods to develop the PSA of research reactors, including initiating event analysis, event tree analysis, fault tree analysis, dependent failure analysis, human reliability analysis and quantification as well as the experimental and external event evaluation through the investigation of various research reactors and their PSAs home and abroad, to provide the current situation and features of research reactors PSAs. (author)

  20. Safety evaluation for instrumentation and control system upgrading project of Malaysian TRIGA MARK II PUSPATI Research reactor

    International Nuclear Information System (INIS)

    Ridha Roslan; Nik Mohd Faiz Khairuddin

    2013-01-01

    Full-text: Malaysian TRIGA MARK II research reactor has been in safe operation since its first criticality in 1982. The reactor is licensed to be operated by Malaysian Nuclear Agency to perform training and research development related activities. Due to its extensive operation since last three decades, the option of modifications for safety and safety-related item and component become a necessary to replace the outdated equipment to a stat-of-art, reliable technologies. This paper will present the current regulatory activities performed by Atomic Energy Licensing Board (AELB) to ensure the upgrading of analogue to digital instrumentation and control system is implemented in safe manner. The review activity includes documentation review, manufacturer quality audit and on-site inspection for commissioning. The review performed by AELB is based on The International Atomic Energy Agency (IAEA) Safety Requirements NS-R-4, entitled Safety of Research Reactors. During this endeavour, AELB seeks technical cooperation from Korea Institute of Nuclear Safety (KINS), the nuclear experts organization of the country of origin of the instrumentation and control technology. The regulatory activity is still on-going and is expected to be completed by issuance of Authorization for Restart on December 2013. (author)

  1. Experts' discussion on reactor safety research

    International Nuclear Information System (INIS)

    1980-01-01

    The experts' discussion on reactor safety research deals with risk analysis, political realization, man and technics, as well as with the international state of affairs. Inspite of a controversy on individual issues and on the proportion of governmental and industrial involvment in reactor safety research, the continuation and intensification of corresponding research work is said to be necessary. Several participants demanded to consider possible 'conventional accidents' as well as a stronger financial commitment by the industry in this sector. The ratio 'man and technics' being an interface decisive for the proper functioning or failure of complex technical systems requires even more research work to be done. (GL) [de

  2. Engineered nanomaterials: toward effective safety management in research laboratories.

    Science.gov (United States)

    Groso, Amela; Petri-Fink, Alke; Rothen-Rutishauser, Barbara; Hofmann, Heinrich; Meyer, Thierry

    2016-03-15

    It is still unknown which types of nanomaterials and associated doses represent an actual danger to humans and environment. Meanwhile, there is consensus on applying the precautionary principle to these novel materials until more information is available. To deal with the rapid evolution of research, including the fast turnover of collaborators, a user-friendly and easy-to-apply risk assessment tool offering adequate preventive and protective measures has to be provided. Based on new information concerning the hazards of engineered nanomaterials, we improved a previously developed risk assessment tool by following a simple scheme to gain in efficiency. In the first step, using a logical decision tree, one of the three hazard levels, from H1 to H3, is assigned to the nanomaterial. Using a combination of decision trees and matrices, the second step links the hazard with the emission and exposure potential to assign one of the three nanorisk levels (Nano 3 highest risk; Nano 1 lowest risk) to the activity. These operations are repeated at each process step, leading to the laboratory classification. The third step provides detailed preventive and protective measures for the determined level of nanorisk. We developed an adapted simple and intuitive method for nanomaterial risk management in research laboratories. It allows classifying the nanoactivities into three levels, additionally proposing concrete preventive and protective measures and associated actions. This method is a valuable tool for all the participants in nanomaterial safety. The users experience an essential learning opportunity and increase their safety awareness. Laboratory managers have a reliable tool to obtain an overview of the operations involving nanomaterials in their laboratories; this is essential, as they are responsible for the employee safety, but are sometimes unaware of the works performed. Bringing this risk to a three-band scale (like other types of risks such as biological, radiation

  3. Materials of the Annual Scientific Conference of the Institute for Nuclear Research; Materyiali shchoryichnoyi naukovoyi konferentsyiyi Yinstitutu Yadernikh Doslyidzhen`

    Energy Technology Data Exchange (ETDEWEB)

    Vishnevs` kij, Yi M [ed.

    1999-12-31

    The Proceedings contain reports which were presented at current Annual scientific conference of the Institute for Nuclear Research, National Academy of Sciences (Kiev, January 27-30, 1998). The articles are presented in the sections which corresponds to the main scientific directions of the Institute activity: Nuclear Physics, Nuclear Reactor Safety, Radiation physics, Plasma Physics, Radioecology and Radiobiology. Each Proceedings Sections contain the following sequence of the works: theoretical, experimental, applied and methodological. The Proceeding are printed by means of direct reproduction.

  4. Operational safety reliability research

    International Nuclear Information System (INIS)

    Hall, R.E.; Boccio, J.L.

    1986-01-01

    Operating reactor events such as the TMI accident and the Salem automatic-trip failures raised the concern that during a plant's operating lifetime the reliability of systems could degrade from the design level that was considered in the licensing process. To address this concern, NRC is sponsoring the Operational Safety Reliability Research project. The objectives of this project are to identify the essential tasks of a reliability program and to evaluate the effectiveness and attributes of such a reliability program applicable to maintaining an acceptable level of safety during the operating lifetime at the plant

  5. Safety research needs for Russian-designed reactors. Requirements situation

    International Nuclear Information System (INIS)

    Brown, R. Allan; Holmstrom, Heikki; Reocreux, Michel; Schulz, Helmut; Liesch, Klaus; Santarossa, Giampiero; Hayamizu, Yoshitaka; Asmolov, Vladimir; Bolshov, Leonid; Strizhov, Valerii; Bougaenko, Sergei; Nikitin, Yuri N.; Proklov, Vladimir; Potapov, Alexandre; Kinnersly, Stephen R.; Voronin, Leonid M.; Honekamp, John R.; Frescura, Gianni M.; Maki, Nobuo; Reig, Javier; ); Bekjord, Eric S.; Rosinger, Herbert E.

    1998-01-01

    In June 1995, an OECD Support Group was set up to perform a broad study of the safety research needs of Russian-designed reactors. The emphasis of the study is on the VVER-type reactors in part because of the larger base of knowledge within the NEA Member countries related to LWRs. For the RBMKs, the study does not make the judgement that such reactors can be brought to acceptable levels of safety but focuses on near term efforts that can contribute to reducing the risk to the public. The need for the safety research must be evaluated in context of the lifetime of the reactors. The principal outcome of the work of the Support Group is the identification of a number of research topics which the members believe should receive priority attention over the next several years if risk levels are to be reduced and public safety enhanced. These appear in the Conclusions and Recommendations section of the report, and are the following: - The most important near-term need for VVER and RBMK safety research is to establish a sound technical basis for the emergency operating procedures used by the plant staff to prevent or halt the progression of accidents (i.e., Accident Management) and for plant safety improvements. - Co-operation of Western and Eastern experts should help to avoid East-West know-how gaps in the future, as safety technology continues to improve. - Safety research in Eastern countries will make an important contribution to public safety as it has in OECD countries. - RBMK safety research, including verification of codes, starts from a smaller base of experience than VVER, and is at an earlier stage of development. Technical Conclusions: - Research to improve human performance and operational safety of VVER and RBMK plants is extremely important. - VVER thermal-hydraulic and reactor physics research should focus on full validation of codes to VVER-specific features, and on extension of experimental data base. - Methods of assessing VVER pressure boundary

  6. Nuclear power reactor safety research activities in CIAE

    International Nuclear Information System (INIS)

    Pu Shendi; Huang Yucai; Xu Hanming; Zhang Zhongyue

    1994-01-01

    The power reactor safety research activities in CIAE are briefly reviewed. The research work performed in 1980's and 1990's is mainly emphasised, which is closely related to the design, construction and licensing review of Qinshan Nuclear Power Plant and the safety review of Guangdong Nuclear Power Station. Major achievements in the area of thermohydraulics, nuclear fuel, probabilistic safety assessment and severe accident researches are summarized. The foreseeable research plan for the near future, relating to the design and construction of 600 MWe PWR NPP at Qinshan Site (phase II development) is outlined

  7. Report on research and development work 1981 of the Institut fuer Reaktorentwicklung

    International Nuclear Information System (INIS)

    1982-02-01

    The Institute for Reactor Development works chiefly on technical problems as a function of the development and safety evidence of nuclear installations. The tasks that are for a greater part performed together with other internal and external institutions, are both theoretical- and experimental-natured and concentrate mainly on problems out of the reactor safety. The works are in the main concentrated in the 'Fast Breeder Project' (PSB) and in the 'Nuclear Safety Project' (PNS). The PSB-contributions to design and safety of sodium-cooled breeding reactors comprise above all investigations on the thermohydraulic and neutronkinetic behaviour of the core as a result of incidents with very low probability to occur, as well as on the effects of local cooling failures in the reactor core in particular consideration of possible failure propagation mechanisms and of the detectability of such processes. The works in the field of safety of lightwater reactors concern in particular investigations on the dynamic load of component parts of reactor pressure vessels related with the HDR-blowdown-tests and containment structures, as well as investigations on the fuel rod behaviour in the loss of coolant incident. (orig./RW) [de

  8. NASA's aviation safety research and technology program

    Science.gov (United States)

    Fichtl, G. H.

    1977-01-01

    Aviation safety is challenged by the practical necessity of compromising inherent factors of design, environment, and operation. If accidents are to be avoided these factors must be controlled to a degree not often required by other transport modes. The operational problems which challenge safety seem to occur most often in the interfaces within and between the design, the environment, and operations where mismatches occur due to ignorance or lack of sufficient understanding of these interactions. Under this report the following topics are summarized: (1) The nature of operating problems, (2) NASA aviation safety research, (3) clear air turbulence characterization and prediction, (4) CAT detection, (5) Measurement of Atmospheric Turbulence (MAT) Program, (6) Lightning, (7) Thunderstorm gust fronts, (8) Aircraft ground operating problems, (9) Aircraft fire technology, (10) Crashworthiness research, (11) Aircraft wake vortex hazard research, and (12) Aviation safety reporting system.

  9. Institute of Nuclear Physics, mission and scientific research activities

    International Nuclear Information System (INIS)

    Zoto, J.; Zaganjori, S.

    2004-01-01

    The Institute of Nuclear Physics (INP) was established in 1971 as a scientific research institution with main goal basic scientific knowledge transmission and transfer the new methods and technologies of nuclear physics to the different economy fields. The organizational structure and main research areas of the Institute are described. The effects of the long transition period of the Albanian society and economy on the Institution activity are also presented

  10. NRC safety research in support of regulation, 1988

    International Nuclear Information System (INIS)

    1989-05-01

    This report, the fourth in a series of annual reports, was prepared in response to Congressional inquiries concerning how nuclear regulatory research is used. It summarizes the accomplishments of the Office of Nuclear Regulatory Research during 1988. The goal of this office is to ensure that safety-related research provides the technical bases for rulemaking and for related decisions in support of NRC licensing and inspection activities. This research is necessary to make certain that the regulations that are imposed on licensees provide an adequate margin of safety so as to protect the health and safety of the public. This report describes both the direct contributions to scientific and technical knowledge with regard to nuclear safety and their regulatory applications

  11. An overview of criticality safety research at the All-Russian Research Institute of Experimental Physics

    Energy Technology Data Exchange (ETDEWEB)

    Kuvshinov, M.I.; Voinov, A.M.; Yuferev, V.I. [All-Russian Research Institute of Experimental Physics, Arzamas (Russian Federation)] [and others

    1997-06-01

    This paper presents a summary of experimental and calculational activities conducted at VNIIEF from the late 1940s to now to study the critical conditions of systems as part of a nuclear safety program. 9 refs., 1 tab.

  12. An overview of criticality safety research at the All-Russian Research Institute of Experimental Physics

    International Nuclear Information System (INIS)

    Kuvshinov, M.I.; Voinov, A.M.; Yuferev, V.I.

    1997-01-01

    This paper presents a summary of experimental and calculational activities conducted at VNIIEF from the late 1940s to now to study the critical conditions of systems as part of a nuclear safety program. 9 refs., 1 tab

  13. Comprehensive School Safety Initiative Report

    Science.gov (United States)

    National Institute of Justice, 2014

    2014-01-01

    The National Institute of Justice (NIJ) developed the Comprehensive School Safety Initiative in consultation with federal partners and Congress. It is a research-focused initiative designed to increase the safety of schools nationwide through the development of knowledge regarding the most effective and sustainable school safety interventions and…

  14. Studies of glass waste form performance at Japan Atomic Energy Research Institute

    International Nuclear Information System (INIS)

    Banba, Tsunetaka; Kamizono, Hiroshi; Nakayama, Shinichi; Tashiro, Shingo

    1989-08-01

    The recent studies of glass waste form performance at Japan Atomic Energy Research Institute can be classified into the following three categories; (1) Study on the volatilization of radionuclides from the waste glass, which is necessary to estimate the safety in relation to operation of a storage facility. (2) Study on the radiation (alpha-radiation) effects which have relation to the long-term stability of the waste glass. (3) Study on the leaching behavior of actinides under the repository conditions, which is necessary to predict the long-term release rate of radionuclides from the waste glass. In the present report, the recent results corresponding to the above categories are described. (author)

  15. Annual report 1991. Institute for Advanced Materials

    International Nuclear Information System (INIS)

    1992-01-01

    The Institute executed in 1991 the R and D programme on advanced materials of the Joint Research Centre and contributed to the programmes: reactor safety, radio-active waste management, fusion technology and safety, nuclear fuel and actinide research. The supplementary programme: Operation of the High Flux Reactor is presented in condensed form. A full report is published separately. (Author). refs., figs., tabs

  16. Dissemination research: the University of Wisconsin Population Health Institute.

    Science.gov (United States)

    Remington, Patrick L; Moberg, D Paul; Booske, Bridget C; Ceraso, Marion; Friedsam, Donna; Kindig, David A

    2009-08-01

    Despite significant accomplishments in basic, clinical, and population health research, a wide gap persists between research discoveries (ie, what we know) and actual practice (ie, what we do). The University of Wisconsin Population Health Institute (Institute) researchers study the process and outcomes of disseminating evidence-based public health programs and policies into practice. This paper briefly describes the approach and experience of the Institute's programs in population health assessment, health policy, program evaluation, and education and training. An essential component of this dissemination research program is the active engagement of the practitioners and policymakers. Each of the Institute's programs conducts data collection, analysis, education, and dialogue with practitioners that is closely tied to the planning, implementation, and evaluation of programs and policies. Our approach involves a reciprocal exchange of knowledge with non-academic partners, such that research informs practice and practice informs research. Dissemination research serves an important role along the continuum of research and is increasingly recognized as an important way to improve population health by accelerating the translation of research into practice.

  17. Nuclear safety research in France

    International Nuclear Information System (INIS)

    Tanguy, P.

    1976-01-01

    As a consequence of the decision of choosing light water reactors (PWR) for the French nuclear plants of the next ten years, a large safety program has been launched referring to three physical barriers against fission product release: the fuel element cladding, main primary system boundary and the containment. The parallel development of French-designed fast breeder reactors involved safety studies on: sodium boiling, accidental fuel behavior, molten fuel-sodium interaction, core accident and protection, and external containment. The rapid development of nuclear energy resulted in a corresponding development of safety studies relating to nuclear fuel facilities. French regulations also required a special program to be developed for the realistic evaluation of the consequences of external agressions, the French cooperation to multinational safety research being also intensive

  18. HTGR safety research program

    International Nuclear Information System (INIS)

    Barsell, A.W.; Olsen, B.E.; Silady, F.A.

    1981-01-01

    An HTGR safety research program is being performed supporting and guided in priorities by the AIPA Probabilistic Risk Study. Analytical and experimental studies have been conducted in four general areas where modeling or data assumptions contribute to large uncertainties in the consequence assessments and thus, in the risk assessment for key core heat-up accident scenarios. Experimental data have been obtained on time-dependent release of fission products from the fuel particles, and plateout characteristics of condensible fission products in the primary circuit. Potential failure modes of primarily top head PCRV components as well as concrete degradation processes have been analyzed using a series of newly developed models and interlinked computer programs. Containment phenomena, including fission product deposition and potential flammability of liberated combustible gases have been studied analytically. Lastly, the behaviour of boron control material in the core and reactor subcriticality during core heatup have been examined analytically. Research in these areas has formed the basis for consequence updates in GA-A15000. Systematic derivation of future safety research priorities is also discussed. (author)

  19. Open Access Publishing in Indian Premier Research Institutions

    Science.gov (United States)

    Bhat, Mohammad Hanief

    2009-01-01

    Introduction: Publishing research findings in open access journals is a means of enhancing visibility and consequently increasing the impact of publications. This study provides an overview of open access publishing in premier research institutes of India. Method: The publication output of each institution from 2003 to 2007 was ascertained through…

  20. EUMENES, a computer software for managing the radiation safety program information at an institutional level

    International Nuclear Information System (INIS)

    Hernandez Saiz, Alejandro; Cornejo Diaz, Nestor; Valdes Ramos, Maryzury; Martinez Gonzalez, Alina; Gonzalez Rodriguez, Niurka; Vergara Gil, Alex

    2008-01-01

    The correct application of national and international regulations in the field of Radiological Safety requires the implementation of Radiation Safety Programs appropriate to the developed practice. These Programs demand the preparation and keeping of an important number of records and data, the compliance with working schedules, systematic quality controls, audits, delivery of information to the Regulatory Authority, the execution of radiological assessments, etc. Therefore, it is unquestionable the necessity and importance of having a computer tool to support the management of the information related to the Radiation Safety Program in any institution. The present work describes a computer program that allows the efficient management of these data. Its design was based on the IAEA International Basic Safety Standards recommendations and on the requirements of the Cuban national standards, with the objective of being flexible enough to be applied in most of the institutions using ionizing radiations. The most important records of Radiation Safety Programs were incorporated and reports can be generated by the users. An additional tools-module allows the user to access to a radionuclide data library, and to carry out different calculations of interest in radiological protection. The program has been developed in Borland Delphi and manages Microsoft Access databases. It is a user friendly code that aims to support the optimization of Radiation Safety Programs. The program contributes to save resources and time, as the generated information is electronically kept and transmitted. The code has different security access levels according to the user responsibility at the institution and also provides for the analysis of the introduced data, in a quick and efficient way, as well as to notice deadlines, the exceeding of reference levels and situations that require attention. (author)

  1. Paul Scherrer Institute Scientific Report 2000. Volume IV: Nuclear Energy and Safety

    International Nuclear Information System (INIS)

    Smith, Brian; Gschwend, Beatrice

    2001-03-01

    Nuclear energy related research in Switzerland is concentrated at PSI's Nuclear Energy and Safety Research Department (NES). The activities of the department are concentrated on three main domains of: Safety and related problems of operating plants; safety features of future reactor and fuel cycles; waste management. Comprehensive assessments of energy systems are carried out in cooperation with PSI's General Energy Research Department. Many of the programs are part of collaborations with universities, industry, or international organisations. Progress in 2000 in these topical areas is described in this report. A list of scientific publications in 2000 is also provided

  2. Paul Scherrer Institute Scientific Report 2000. Volume IV: Nuclear Energy and Safety

    Energy Technology Data Exchange (ETDEWEB)

    Smith, Brian; Gschwend, Beatrice [eds.

    2001-03-01

    Nuclear energy related research in Switzerland is concentrated at PSI's Nuclear Energy and Safety Research Department (NES). The activities of the department are concentrated on three main domains of: Safety and related problems of operating plants; safety features of future reactor and fuel cycles; waste management. Comprehensive assessments of energy systems are carried out in cooperation with PSI's General Energy Research Department. Many of the programs are part of collaborations with universities, industry, or international organisations. Progress in 2000 in these topical areas is described in this report. A list of scientific publications in 2000 is also provided.

  3. Report of the evaluation by the Ad Hoc Review Committee on Nuclear Safety Research. Result evaluation in fiscal year 2000

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-06-01

    The Research Evaluation Committee, which consisted of 14 members from outside of the Japan Atomic Energy Research Institute (JAERI), set up an Ad Hoc Review Committee on Nuclear Safety Research in accordance with the Fundamental Guideline for the Evaluation of Research and Development (R and D) at JAERI' and its subsidiary regulations in order to evaluate the R and D accomplishments achieved for five years from Fiscal Year 1995 to Fiscal Year 1999 at Department of Reactor Safety Research, Department of Fuel Cycle Safety Research, Department of Environmental Safety Research and Department of Safety Research Technical Support in Tokai Research Establishment at JAERI. The Ad Hoc Review Committee consisted of 11 specialists from outside of JAERI. The Ad Hoc Review Committee conducted its activities from December 2000 to February 2001. The evaluation was performed on the basis of the materials submitted in advance and of the oral presentations made at the Ad Hoc Review Committee meeting which was held on December 11, 2000, in line with the items, viewpoints, and criteria for the evaluation specified by the Research Evaluation Committee. The result of the evaluation by the Ad Hoc Review Committee was submitted to the Research Evaluation Committee, and was judged to be appropriate at its meeting held on March 16, 2001. This report describes the result of the evaluation by the Ad Hoc Review Committee on Nuclear Safety Research. (author)

  4. Research on Integration of NPP Operational Safety Management Performance Systems

    International Nuclear Information System (INIS)

    Chi, Miao; Shi, Liping

    2014-01-01

    The operational safety management of Nuclear Power Plants demands systematic planning and integrated control. NPPs are following the well-developed safety indicator systems proposed by IAEA Operational Safety Performance Indicator Programme, NRC Reactor Oversight Process or the other institutions. Integration of the systems is proposed to benefiting from the advantages of both systems and avoiding improper application into the real world. The authors analyzed the possibility and necessity for system integration, and propose an indicator system integrating method

  5. Present status of nuclear power safety studies in JAERI

    International Nuclear Information System (INIS)

    1989-01-01

    Japan Atomic Energy Research Institute carries out the safety research required for ensuring safety accompanying the development and utilization of atomic energy, dividing the roles with industrial circules, universities and other public research institutes. First, it carries out the research based on the yearly program of safety research, in which the subjects of safety research that the state should execute are decided. Next, it carries out a series of the safety verification test on atomic energy facilities entrusted by the state using the special account for power source development promotion countermeasures. Besides, it carries out the safety research on the specific subjects entrusted by outside organizations. The object and range of atomic energy safety at present are roughly divided into four fields, that is, nuclear power stations, nuclear fuel facilities, waste treatment and disposal, and environmental radioactivity. In order to advance the research effectively, in addition to the generalization department and the execution department, various committees are organized. In 1988, about 260 persons engaged in these four research fields, and the budget for fiscal year 1988 was about 17.4 billion yen. (K.I.)

  6. Safety management in research and development organisation

    International Nuclear Information System (INIS)

    Nivedha, T.

    2016-01-01

    Health and safety is one of the most important aspects of an organizations smooth and effective functioning. It depends on the safety management, health management, motivation, leadership and training, welfare facilities, accident statistics, policy, organization and administration, hazard control and risk analysis, monitoring, statistics and reporting. Workplace accidents are increasingly common, main causes are untidiness, noise, too hot or cold environments, old or poorly maintained machines, and lack of training or carelessness of employees. One of the biggest issues facing employers today is the safety of their employees. This study aims at analyzing the occupational health and safety of Research organization in Indira Gandhi Centre for Atomic Research by gathering information on health management, safety management, motivation, leadership and training, welfare facilities, accident statistics, organization and administration, hazard control and risk analysis, monitoring, statistics and reporting. Data were collected by using questionnaires which were developed on health and safety management system. (author)

  7. Summary of NRC LWR safety research programs on fuel behavior, metallurgy/materials and operational safety

    International Nuclear Information System (INIS)

    Bennett, G.L.

    1979-09-01

    The NRC light-water reactor safety-research program is part of the NRC regulatory program for ensuring the safety of nuclear power plants. This paper summarizes the results of NRC-sponsored research into fuel behavior, metallurgy and materials, and operational safety. The fuel behavior research program provides a detailed understanding of the response of nuclear fuel assemblies to postulated off-normal or accident conditions. Fuel behavior research includes studies of basic fuel rod properties, in-reactor tests, computer code development, fission product release and fuel meltdown. The metallurgy and materials research program provides independent confirmation of the safe design of reactor vessels and piping. This program includes studies on fracture mechanics, irradiation embrittlement, stress corrosion, crack growth, and nondestructive examination. The operational safety research provides direct assistance to NRC officials concerned with the operational and operational-safety aspects of nuclear power plants. The topics currently being addressed include qualification testing evaluation, fire protection, human factors, and noise diagnostics

  8. Safety research basic plan of JNC

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-03-01

    Japan Nuclear Cycle Development Institute (JNC) formally succeeded to Power Reactor and Nuclear Fuel Development Corporation (PNC) on October, 1 1998. This report describes the basic plan for major program of JNC which consists of two parts: management philosophy of the new institute and the latest revised medium term program. In the first part, the primary mission of JNC is to perform its R and D concentrating on fast breeder reactor and its fuel cycle, and treatment and disposal of high-level radioactive wastes, while at the same time giving special consideration to safety. In the second, individual programs in the new basic plan are discussed in detail. The outline and schedule of each program are also attached in the table form. (H. Itami)

  9. Summary of LWR safety research in the USA

    International Nuclear Information System (INIS)

    Murley, T.E.; Tong, L.S.; Bennett, G.L.

    1977-01-01

    The U.S. Nuclear Regulatory Commission's water reactor safety research program is described and the basic results are presented. The USNRC water reactor safety research program consists of five basic research areas: integrity of vessel and piping, thermal-hydraulic test, fuel rod behaviour, code development and verification, and reactor operational safety. Results from the vessel and piping integrity research have demonstrated the high safety margins in scaled vessels and the analytical procedures for calculating vessel behaviour under pressure. Non-destructive examination techniques are being improved. Work is also proceeding to define the material constituents to reduce the susceptibility of irradiation embrittlement and stress corrosion cracking. The thermal-hydraulic tests have covered the various phases of a hypothetical loss of coolant accident (LOCA) and activation of the emergency core cooling system (ECCS). These tests have led to the development of engineering correlations to describe the phenomena to further quantify the safety margins in commercial nuclear power plants. Specifically, this paper presents selected experimental data and analytical predictions from the initial tests in LOFT and SEMISCALE. Comparisons and evaluations are made between the data and analytical predictions. Significant results and conclusions are presented regarding the behaviour of emergency core cooling systems in a LOCA environment: the ability to predict LOCA-type experiments over a scaling range of thirty and the thermal-hydraulic behaviour of components such as pumps in an integral system LOCA environment. The fuel behaviour research has provided valuable information on decay heat, cladding oxidation, fuel rod behaviour and fuel metling. Both the decay heat and the cladding oxidation have been shown to be lower than assumed in the licensing evaluations. The fuel behaviour and thermo-hydraulic research is being integrated into computer codes to be used to provide additional

  10. Nuclear Safety Research Department annual report 2000

    International Nuclear Information System (INIS)

    Majborn, B.; Damkjaer, A.; Nielsen, S.P.; Nonboel, E.

    2001-08-01

    The report presents a summary of the work of the Nuclear Safety Research Department in 2000. The department's research and development activities were organized in two research programmes: 'Radiation Protection and Reactor Safety' and 'Radioecology and Tracer Studies'. In addition the department was responsible for the tasks 'Applied Health Physics and Emergency Preparedness', 'Dosimetry', 'Environmental Monitoring', and Irradiation and Isotope Services'. Lists of publications, committee memberships and staff members are included. (au)

  11. Water and Environmental Research Institute of the Western Pacific

    Science.gov (United States)

    Water and Environmental Research Institute of the Western Pacific - University of Guam Skip to main entered the website of the Water and Environmental Research Institute of the Western Pacific (WERI) at the CNMI and the FSM. Research Programs Weather and Climate Surface Water & Watersheds Groundwater &

  12. Developing institutional repository at National Institute for Materials Science : Researchers directory service “SAMURAI” and Research Collection Library

    Science.gov (United States)

    Takaku, Masao; Tanifuji, Mikiko

    National Institute for Materials Science (NIMS) has developed an institutional repository “NIMS eSciDoc” since 2008. eSciDoc is an open source repository software made in Germany, and provides E-Science infrastructures through its flexible data model and rich Web APIs. NIMS eScidoc makes use of eSciDoc functions to benefit for NIMS situations. This article also focuses on researchers directory service “SAMURAI” in addition to NIMS eSciDoc. Successfully launched in October 2010, SAMURAI provides approximately 500 researchers' profile and publication information.

  13. Karlsruhe Research Center, Nuclear Safety Research Project (PSF). Annual report 1994

    International Nuclear Information System (INIS)

    Hueper, R.

    1995-08-01

    The reactor safety R and D work of the Karlsruhe Research Centre (FZKA) has been part of the Nuclear Safety Research Projet (PSF) since 1990. The present annual report 1994 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 1995. An abstract in English precedes each of them, whenever the respective article is written in German. (orig.) [de

  14. Institutional Support : Institute for Research on Political Economy in ...

    International Development Research Centre (IDRC) Digital Library (Canada)

    The Institut de recherche empirique en économie politique (IREEP) is an independent nonprofit organization established in 2004 with a view to contributing to the education of the next generation of teachers and researchers in political economy in Bénin and West Africa. IREEP has successfully integrated academic training ...

  15. The 10 years of history on the Korea Institute of Nuclear Safety

    International Nuclear Information System (INIS)

    2000-02-01

    This book reports the 10 years of history of Korea Institute of Nuclear Safety which is divided into three part. The first part includes summary, beginning and launching of KINS and establishment and development of KINS. The second deals with inspection safety on nuclear power facilities, protection of radiation and surveillance for environment, safe criterion and development of safe regulation and providing assistance of safe regulation. The third part mentions direction of safe regulation on nuclear power, long term vision and innovation of management, future for KINS. It has appendixes such as a chronological table current condition of budget and human resources.

  16. TTI Phase 2 Institutional Support: Economic Policy Research Centre ...

    International Development Research Centre (IDRC) Digital Library (Canada)

    TTI Phase 2 Institutional Support: Economic Policy Research Centre ... the Economic Policy Research Centre's (EPRC) role as a credible public policy institution in ... IWRA/IDRC webinar on climate change and adaptive water management.

  17. Annual report of the Japan Atomic Energy Research Institute for fiscal 2000

    International Nuclear Information System (INIS)

    2001-01-01

    The Japan Atomic Energy Research Institute (JAERI) promotes some researches such as neutron science research, light quantum/synchrotron radiation science research, radiation application research, science research, advanced basic research, and so on, based on nuclear energy R and D and contributing to general development on scientific technology, along the Long-term program on research, development and application of nuclear energy' established on June, 1994, as a general organization on nuclear energy R and D in Japan. And, as an R and D on advanced energy system bringing breakthrough on nuclear energy technology, JAERI also promotes research on future type energy system, R and D on nuclear fusion, and trial research on high temperature engineering. Furthermore, JAERI progresses research on safety and health physics, as occupying both fields of general nuclear energy science and nuclear energy. In addition, by carrying out not only interdisciplinary cooperation in Japan but also versatile international one, various research assisting business and effective R and D are promoted. Here were described in details in fiscal year 2000, on 6 items on the neutron science research (SR), 13 items on light quantum/radiation light SR, 13 items on radiation application SR, 6 items on matter SR, 3 items on environment SR, 19 items on advanced basic SR, and so on. (G.K.)

  18. Annual report 1991. Environment Institute

    International Nuclear Information System (INIS)

    1992-01-01

    This is the annual report of the Environment Institute of the Joint Research Centre - Ispra Site - of the Commission of the European Communities. The report summarizes the progress accomplished in the course of 1991 - i.e. the last of the four year (1988-91) Specific Research Programme of the Joint Research Centre - in the projects tackled by the Institute. The activities were mainly focused on the areas of environmental chemicals, air pollution, water pollution, chemical waste and food and drug analysis, included in the programme Environmental Protection, and of safety assessment of nuclear waste disposal in geological formation as a part of the Radioactive Waste Management programme. The scientific support provided to different Commission Services is also described, proper emphasis being given to that provided to the Directorate General Xl (Environment, Nuclear Safety and Civil Protection) in the field of chemicals, air pollution, water pollution, chemical waste and radioactive environmental monitoring (REM). The above activities are aimed at the implementation of EC directives in the related fields. The work for third parties and the contribution of the Institute to various EUREKA and COST projects are also shortly described. Lastly the report provides essential data concerning the Institute structure and the human and financial resources

  19. Gas Research Institute research program summary: Goals and accomplishments

    International Nuclear Information System (INIS)

    1991-07-01

    Gas Research Institute's research and development programs pursue technologies that maximize the value of gas energy services while minimizing the cost of supplying and delivering gaseous fuels. Four program areas, Supply Options, End Use, Gas Operations, and Crosscutting Research, are described in the report, together with related project titles and numbers. Also included are summaries of 1990 research results, research collaboration and supported work, and patents and licensing agreements. Glossaries of budget and program terms and of acronyms and abbreviations often used in the GRI literature are added

  20. An outcome of nuclear safety research in JAERI. Predominance of research

    International Nuclear Information System (INIS)

    Yanagisawa, Kazuaki; Kawashima, Kei; Ito, Keishiro; Katsuki, Chisato

    2010-02-01

    Bibliometric study by means of research papers revealed the followings; (1) Nuclear Safety Research (NSR) performed in Japan is the 2nd highest in the world followed by USA. The share of JAERI for safety paper publication is about 25% in Japan (2) During past 25 years, JAERI is predominant at 39 safety fields out of 97, that is, 40% to the total. This is the fact revealed from comparison of published number of research papers with those of other organizations. (3) JAERI is recently changing its stress point from reactor-oriented accidents to the down stream of nuclear fuel cycling. There existed impact of TMI-2 accident on NSR-JAERI, especially in the field of thermal hydraulics, LOCA, severe accident and risk analysis. (author)

  1. Low-level tritium research facility for the University of Toronto Institute for Aerospace Studies

    International Nuclear Information System (INIS)

    Kherani, N.P.; Shmayda, W.T.

    1984-06-01

    The objective of the Low-level Tritium Research Facility for the University of Toronto Institute for Aerospace Studies (UTIAS) is to investigate tritium-material interactions and how they differ with respect to protium and deuterium. The tritium laboratory will also be employed to study tritium retention, tritium imaging, and the effect of tritium on diagnostic devices. This report is a preliminary design document of the UTIAS Low-Level Tritium Research Facility including the fundamentals of tritium, a description of the facility, tritium laboratory requirements and the safety analysis of the laboratory. The facility is designed to handle a total elemental tritium inventory of 10 Ci, though it will initially commence operation with 1 Ci and later increased to the maximum value. In the event of an instantaneous emission of the total tritium inventory within the laboratory, the working personnel would be exposed to an airborne tritium concentration less than the maximum permissible. Moreover, with all the safety features included in this design the likelihood of such an accident is very remote. Thus, the tritium laboratory design is intrinsically safe

  2. Seismic safety margins research program overview

    International Nuclear Information System (INIS)

    Tokarz, F.J.; Smith, P.D.

    1978-01-01

    A multiyear seismic research program has been initiated at the Lawrence Livermore Laboratory. This program, the Seismic Safety Margins Research Program (SSMRP) is funded by the U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research. The program is designed to develop a probabilistic systems methodology for determining the seismic safety margins of nuclear power plants. Phase I, extending some 22 months, began in July 1978 at a funding level of approximately $4.3 million. Here we present an overview of the SSMRP. Included are discussions on the program objective, the approach to meet the program goal and objectives, end products, the probabilistic systems methodology, and planned activities for Phase I

  3. Research Review of the Institute of African Studies

    African Journals Online (AJOL)

    Please note: As of 2013 the Research Review of the Institute of African Studies is now publishing under the title Contemporary Journal of African Studies. You can view the CJAS pages on AJOL here: http://www.ajol.info/index.php/contjas/index. The Research Review of the Institute of African Studies at the University of ...

  4. 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

  5. Status and some safety philosophies of the China advanced research reactor CARR

    International Nuclear Information System (INIS)

    Luzheng Yuan

    2001-01-01

    The existing two research reactors, HWRR (heavy water research reactor) and SPR (swimming pool reactor), have been operated by China Institute of Atomic Energy (CIAE) since, respectively, 1958 and 1964, and are both in extending service and facing the aging problem. It is expected that they will be out of service successively in the beginning decade of the 21 st century. A new, high performance and multipurpose research reactor called China advanced research reactor (CARR) will replace these two reactors. This new reactor adopts the concept of inverse neutron trap compact core structure with light water as coolant and heavy water as the outer reflector. Its design goal is as follows: under the nuclear power of 60MW, the maximum unperturbed thermal neutron flux in peripheral D 2 O reflector not less than 8 x 10 14 n/cm 2 . s while in central experimental channel, if the central cell to be replaced by an experimental channel, the corresponding value not less than 1 x 10 15 n/cm 2 . s. The main applications for this research reactor will cover RI production, neutron scattering experiments, NAA and its applications, neutron photography, NTD for monocrystaline silicon and applications on reactor engineering technology. By the end of 1999, the preliminary design of CARR was completed, then the draft of preliminary safety analysis report (PSAR) was submitted to the relevant authority at the end of 2000 for being reviewed. Now, the CARR project has entered the detail design phase and safety reviewing procedure for obtaining the construction permit from the relevant licensing authority. This paper will only briefly introduce some aspects of safety philosophy of CARR design and PSAR. (orig.)

  6. Safety of research reactors. Topical issues paper no. 4

    International Nuclear Information System (INIS)

    Alcala-Ruiz, F.; Ferraz-Bastos, J.L.; Kim, S.C.; Voth, M.; Boeck, H.; Dimeglio, F.; Litai, D.

    2001-01-01

    Assessment of Research Reactors (INSARR) missions. The prime objective of these missions has been to conduct a comprehensive operational safety review of the research reactor facility and to verify compliance with the IAEA Safety Standards. The methods used during an INSARR mission have been collected and analysed. Some of the important issues identified are the following: general ageing of the facility; uncertain status of many research reactors (in extended shutdown); indefinite deferral of return to operation or decommissioning; inadequate regulatory supervision; insufficient systematic (periodic) reassessment of safety; lack of quality assurance (QA) programmes; lack of an international safety convention or arrangement; lack of financial support for safety measures (e.g. safety reassessment, safety upgrading, decommissioning) and utilization; lack of clear utilization programmes; inadequate emergency preparedness; inadequate safety documentation (e.g. safety analysis report, operating rules and procedures, emergency plan); inadequate funding of shutdown reactors; weak safety culture; loss of expertise and corporate memory; loss of information concerning radioactive materials contained in retired experimental devices stored in the facility indefinitely; obsolescence of equipment and lack of spare parts; inadequate training and qualifications of regulators and operators; safety implications of new fuel types. These issues have been addressed by the IAEA Secretariat and the chairman of the International Nuclear Safety Advisory Group (INSAG). INSAG has identified three major safety issues that are: the increasing age of research reactors, the number of research reactors that are not operating anymore but have not been decommissioned, and the number of research reactors in countries that do not have appropriate regulatory authorities. This issue paper discusses the concerns generated by an analysis of the results of INSARR missions and those expressed by INSAG. The

  7. The emphasis is on reactor safety research

    International Nuclear Information System (INIS)

    Anon.

    1982-01-01

    For the second time the Association for Reactor Safety mbH (GRS), Koeln, organised on behalf of the BMFT the conference 'Reactor safety research'. About 400 visitors took part. The public who were interested were given a review of the activities which are being undertaken by the BMFT in the programme 'Research and safety of light-water reactors'. The series of conference papers initiated by the BMFT is to be developed into a permanent information source which will be of interest to those working on nuclear questions such as official quarters, industry and high schools, and experts who have to give judgements. The most important statements by various research groups in industry, high schools and also associations of experts, are summarised. (orig.) [de

  8. Guidelines for Self-assessment of Research Reactor Safety

    International Nuclear Information System (INIS)

    2018-01-01

    Self-assessment is an organization’s internal process to review its current status, processes and performance against predefined criteria and thereby to provide key elements for the organization’s continual development and improvement. Self-assessment helps the organization to think through what it is expected to do, how it is performing in relation to these expectations, and what it needs to do to improve performance, fulfil the expectations and achieve better compliance with the predefined criteria. This publication provides guidelines for a research reactor operating organization to perform a self-assessment of the safety management and the safety of the facility and to identify gaps between the current situation and the IAEA safety requirements for research reactors. These guidelines also provide a methodology for Member States, regulatory bodies and operating organizations to perform a self-assessment of their application of the provisions of the Code of Conduct on the Safety of Research Reactors. This publication also addresses planning, implementation and follow-up of actions to enhance safety and strengthen application of the Code. The guidelines are applicable to all types of research reactor and critical and subcritical assemblies, at all stages in their lifetimes, and to States, regulatory bodies and operating organizations throughout all phases of research reactor programmes. Research reactor operating organizations can use these guidelines at any time to support self-assessments conducted in accordance with the organization’s integrated management system. These guidelines also serve as a tool for an organization to prepare to receive an IAEA Integrated Safety Assessment of Research Reactors (INSARR) mission. An important result of this is the opportunity for an operating organization to identify focus areas and make safety improvements in advance of an INSARR mission, thereby increasing the effectiveness of the mission and efficiency of the

  9. Decommissioning of the research reactors at the Russian Research Centre Kurchatov Institute

    International Nuclear Information System (INIS)

    Ponomarev-Stepnoy, N.N.; Ryantsev, E.P.; Kolyadin, V.I.; Kucharkin, N.E.; Melkov, E.S.; Gorlinsky, Yu.E.; Kyznetsova, T.I.; Bulkin, B.K.

    2002-01-01

    The Kurchatov Institute is the largest research center of Russia in the field of nuclear science and engineering. It comprises more than 10 research institutes and scientific-technological complexes carrying out research work in the field of safe development of atomic engineering, controlled thermonuclear fusion, and plasma physics, nuclear physics and elementary particle physics, research reactors, radiation materials technology, solid state physics and superconductivity, molecular and chemical physics, and also perspective know-how's, information science and ecology. This report is basically devoted to the decommissioning of the research reactor installations, in particular to the reactor MR because of the volume and complexity of actions involved. (author)

  10. The impact of regulations, safety considerations and physical limitations on research progress at maximum biocontainment.

    Science.gov (United States)

    Shurtleff, Amy C; Garza, Nicole; Lackemeyer, Matthew; Carrion, Ricardo; Griffiths, Anthony; Patterson, Jean; Edwin, Samuel S; Bavari, Sina

    2012-12-01

    We describe herein, limitations on research at biosafety level 4 (BSL-4) containment laboratories, with regard to biosecurity regulations, safety considerations, research space limitations, and physical constraints in executing experimental procedures. These limitations can severely impact the number of collaborations and size of research projects investigating microbial pathogens of biodefense concern. Acquisition, use, storage, and transfer of biological select agents and toxins (BSAT) are highly regulated due to their potential to pose a severe threat to public health and safety. All federal, state, city, and local regulations must be followed to obtain and maintain registration for the institution to conduct research involving BSAT. These include initial screening and continuous monitoring of personnel, controlled access to containment laboratories, accurate and current BSAT inventory records. Safety considerations are paramount in BSL-4 containment laboratories while considering the types of research tools, workflow and time required for conducting both in vivo and in vitro experiments in limited space. Required use of a positive-pressure encapsulating suit imposes tremendous physical limitations on the researcher. Successful mitigation of these constraints requires additional time, effort, good communication, and creative solutions. Test and evaluation of novel vaccines and therapeutics conducted under good laboratory practice (GLP) conditions for FDA approval are prioritized and frequently share the same physical space with important ongoing basic research studies. The possibilities and limitations of biomedical research involving microbial pathogens of biodefense concern in BSL-4 containment laboratories are explored in this review.

  11. The Impact of Regulations, Safety Considerations and Physical Limitations on Research Progress at Maximum Biocontainment

    Directory of Open Access Journals (Sweden)

    Jean Patterson

    2012-12-01

    Full Text Available We describe herein, limitations on research at biosafety level 4 (BSL-4 containment laboratories, with regard to biosecurity regulations, safety considerations, research space limitations, and physical constraints in executing experimental procedures. These limitations can severely impact the number of collaborations and size of research projects investigating microbial pathogens of biodefense concern. Acquisition, use, storage, and transfer of biological select agents and toxins (BSAT are highly regulated due to their potential to pose a severe threat to public health and safety. All federal, state, city, and local regulations must be followed to obtain and maintain registration for the institution to conduct research involving BSAT. These include initial screening and continuous monitoring of personnel, controlled access to containment laboratories, accurate and current BSAT inventory records. Safety considerations are paramount in BSL-4 containment laboratories while considering the types of research tools, workflow and time required for conducting both in vivo and in vitro experiments in limited space. Required use of a positive-pressure encapsulating suit imposes tremendous physical limitations on the researcher. Successful mitigation of these constraints requires additional time, effort, good communication, and creative solutions. Test and evaluation of novel vaccines and therapeutics conducted under good laboratory practice (GLP conditions for FDA approval are prioritized and frequently share the same physical space with important ongoing basic research studies. The possibilities and limitations of biomedical research involving microbial pathogens of biodefense concern in BSL-4 containment laboratories are explored in this review.

  12. The Impact of Regulations, Safety Considerations and Physical Limitations on Research Progress at Maximum Biocontainment

    Science.gov (United States)

    Shurtleff, Amy C.; Garza, Nicole; Lackemeyer, Matthew; Carrion, Ricardo; Griffiths, Anthony; Patterson, Jean; Edwin, Samuel S.; Bavari, Sina

    2012-01-01

    We describe herein, limitations on research at biosafety level 4 (BSL-4) containment laboratories, with regard to biosecurity regulations, safety considerations, research space limitations, and physical constraints in executing experimental procedures. These limitations can severely impact the number of collaborations and size of research projects investigating microbial pathogens of biodefense concern. Acquisition, use, storage, and transfer of biological select agents and toxins (BSAT) are highly regulated due to their potential to pose a severe threat to public health and safety. All federal, state, city, and local regulations must be followed to obtain and maintain registration for the institution to conduct research involving BSAT. These include initial screening and continuous monitoring of personnel, controlled access to containment laboratories, accurate and current BSAT inventory records. Safety considerations are paramount in BSL-4 containment laboratories while considering the types of research tools, workflow and time required for conducting both in vivo and in vitro experiments in limited space. Required use of a positive-pressure encapsulating suit imposes tremendous physical limitations on the researcher. Successful mitigation of these constraints requires additional time, effort, good communication, and creative solutions. Test and evaluation of novel vaccines and therapeutics conducted under good laboratory practice (GLP) conditions for FDA approval are prioritized and frequently share the same physical space with important ongoing basic research studies. The possibilities and limitations of biomedical research involving microbial pathogens of biodefense concern in BSL-4 containment laboratories are explored in this review. PMID:23342380

  13. Fifty years of driving safety research.

    Science.gov (United States)

    Lee, John D

    2008-06-01

    This brief review covers the 50 years of driving-related research published in Human Factors, its contribution to driving safety, and emerging challenges. Many factors affect driving safety, making it difficult to assess the impact of specific factors such as driver age, cell phone distractions, or collision warnings. The author considers the research themes associated with the approximately 270 articles on driving published in Human Factors in the past 50 years. To a large extent, current and past research has explored similar themes and concepts. Many articles published in the first 25 years focused on issues such as driver impairment, individual differences, and perceptual limits. Articles published in the past 25 years address similar issues but also point toward vehicle technology that can exacerbate or mitigate the negative effect of these issues. Conceptual and computational models have played an important role in this research. Improved crash-worthiness has contributed to substantial improvements in driving safety over the past 50 years, but future improvements will depend on enhancing driver performance and perhaps, more important, improving driver behavior. Developing models to guide this research will become more challenging as new technology enters the vehicle and shifts the focus from driver performance to driver behavior. Over the past 50 years, Human Factors has accumulated a large base of driving-related research that remains relevant for many of today's design and policy concerns.

  14. Japan Atomic Energy Research Institute in the 21st century

    International Nuclear Information System (INIS)

    Sato, Y.

    2001-01-01

    Major nuclear research institutes in Japan are the Japan Atomic Energy Research Institute (JAERI), Nuclear Cycle Development Institute (JNC), National Research Institute of Radiological Science (NIRS), and the Institute of Physical and Chemical Research (RIKEN). In the 50s and 60s JAERI concentrated on the introduction of nuclear technology from overseas. Energy security issues led to the development of a strong nuclear power programme in the next two decades resulting in Japan having 50 light water cooled nuclear power plants in operation. Japan also worked on other reactor concepts. The current emphasis of JAERI is on advanced reactors and nuclear fusion. Its budget of 270 million US$ supports five research establishments. JAERI has strong collaboration with industry and university system on nuclear and other advanced research topics (neutron science, photon science). In many areas Japan has strong international links. JAERI has also been transferring know-how on radioisotope and radiation applications to the developing countries particularly through IAEA-RCA mechanisms. (author)

  15. Achievements and future directions in the reactors physics and nuclear safety research

    International Nuclear Information System (INIS)

    Dumitrache, Ion

    2001-01-01

    A historical overlook is presented with respect to inception and development of reactor physics research and on the job training in Romania. First these activities were carried out at the Institute for Atomic Physics and Institute for Power Reactors (IRNE) in Bucharest and afterward at the Institute for Nuclear Technologies, later on transformed in the Institute of Nuclear Research at Pitesti. CYBER Computer installed at Pitesti allowed formation in as early as 1971 reactor specialists who worked out computer programs for neutron physics calculations. These specialists were able to assimilate the characteristic of CANDU 6 type reactor as well as the AECL methodology of simulating processes of CANDU reactor physics. At present four programs are under way. These are: 1. The nuclear reactor physics; 2. The nuclear facility safety; 3. Safety analyses for the transport and radioactive waste disposal; 4. Analyses for radiation shielding and biological protection. There are presented results of the work associated to the CANDU type reactor: 1. Adapting and improving the code system for neutron and thermohydraulic calculation for CANDU type reactor, as supplied by AECL; 2. The IRNE manual for CANDU reactor neutron designing; 3. Final sizing of shim rods of Cernavoda NPP Unit 2; 4. Tests and measurements of reactor physics at the Cernavoda NPP Unit 1 commissioning; 5. Simulation and independent analysis of thermosiphoning carried out at Cernavoda NPP Unit 1 commissioning; 6. Static and dynamical response of the detectors in the CANDU reactor core and their time evolution following the burnup in the neutron flux and their ageing effects; 7. PSA studies at Unit 1; 8. Safety analyses for the radioactive waste disposal at Saligny repository. Also, reported are the results of the work associated to the TRIGA reactor, as follows: 1. Flux measurements and neutron computations necessary in the reactor commissioning; 2. Cleaning up controversial issues relating to neutron flux

  16. 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

  17. Institute for Nuclear Waste Disposal. Annual Report 2011

    International Nuclear Information System (INIS)

    Geckeis, H.; Stumpf, T.

    2012-01-01

    The R and D at the Institute for Nuclear Waste Disposal, INE, (Institut fuer Nukleare Entsorgung) of the Karlsruhe Institute of Technology (KIT) focuses on (i) long term safety research for nuclear waste disposal, (ii) immobilization of high level radioactive waste (HLW), (iii) separation of minor actinides from HLW and (iv) radiation protection.

  18. An Analysis of Canadian Institute for Health Research Funding for Research on Autism Spectrum Disorder

    Directory of Open Access Journals (Sweden)

    R. Deonandan

    2016-01-01

    Full Text Available We examined patterns of Canadian Institute for Health Research (CIHR funding on autism spectrum disorder (ASD research. From 1999 to 2013, CIHR funded 190 ASD grants worth $48 million. Biomedical research received 43% of grants (46% of dollars, clinical research 27% (41%, health services 10% (7%, and population health research 8% (3%. The greatest number of grants was given in 2009, but 2003 saw the greatest amount. Funding is clustered in a handful of provinces and institutions, favouring biomedical research and disfavouring behavioural interventions, adaptation, and institutional response. Preference for biomedical research may be due to the detriment of clinical research.

  19. IAEA Mission Sees High Commitment to Safety at Ghana's Research Reactor After HEU to LEU Fuel Conversion

    International Nuclear Information System (INIS)

    2018-01-01

    An International Atomic Energy Agency (IAEA) team of experts said the operator of Ghana’s research reactor has demonstrated a high commitment to safety following the conversion of the reactor core to use low enriched uranium (LEU) as fuel instead of high enriched uranium (HEU). The team also made recommendations for further safety enhancements. The Integrated Safety Assessment for Research Reactors (INSARR) team concluded a five-day mission today to assess the safety of the GHARR-1 research reactor, originally commissioned in 1994. The 30 kW reactor, operated by the Ghana Atomic Energy Commission (GAEC) at the National Nuclear Research Institute in the capital Accra, is used primarily for trace element analysis for industrial or agricultural purposes, research, education and training. In 2017, the reactor core was converted in a joint effort by Ghana, the United States and China, with assistance from the IAEA. The IAEA supported the operation to eliminate proliferation risks associated with HEU, while maintaining important scientific research. The team made recommendations for improvements to the GAEC, including: • Completing the revision of reactor safety and operating documents to reflect the results of the commissioning of the reactor after the core fuel conversion. • Enhancing the training and qualification programme for operating personnel. • Improving the capability for monitoring operational safety parameters under all conditions. • Strengthening radiation protection by establishing an effective radiation monitoring of workplace. The GAEC said it will request a follow-up INSARR mission by 2020.

  20. Research Ethics: Institutional Review Board Oversight of Art Therapy Research

    Science.gov (United States)

    Deaver, Sarah P.

    2011-01-01

    By having their research proposals reviewed and approved by Institutional Review Boards (IRBs), art therapists meet important ethical principles regarding responsibility to research participants. This article provides an overview of the history of human subjects protections in the United States; underlying ethical principles and their application…

  1. Research in Institutional Economics in Management Science

    DEFF Research Database (Denmark)

    Foss, Kirsten; Foss, Nicolai Juul

    This report maps research in institutional economics in management science in the European Union for the 1995 to 2002 period. The reports applies Internet search based on a university listing, search on journal databases, key informants and an internet-based survey. 195 researchers are identified....... In (sub-)disciplinary terms, organization, strategy, corporate governance, and international business are the major areas of application of institutional economics ideas. In terms of countries, the EU strongholds are Holland, Denmark, UK, and Germany. There is apparently no or very little relevant...... research in Ireland, Portugal, Luxembourg and Greece. Based on the findings of the report, it seems warranted to characterize the EU research effort in the field as being rather dispersed and uncoordinated. Thus, there are no specialized journals, associations or PhD courses. This state of affairs...

  2. Safety research colloquium 2013-2014. Vol. 10

    International Nuclear Information System (INIS)

    Pieper, Ralf

    2015-01-01

    Volume 10 of the safety research colloquium 2013-2014 covers the following issues: Design, ergonomics and safety in product development; Germany is searching a final repository site: concepts and status of the final disposal of nuclear waste; collaborating robots - status of research, standardization and validation; psychological workloads - empirical indications; psychological workloads - actual challenges; expert security by occupational health management - challenges to operational practice; expert security by occupational health management - example of a demographic program in the practical realization; challenges in employment legislation - reduction of the key staff; consideration of human factors in hazard assessment a a challenge for every safety engineer, innovative technologies for work equipment and working systems in the context of ambient intelligence and industry 4.0; challenges of functional safety in the automotive sector; nanotechnology - an example for successful technology assessment.

  3. Nuclear Safety Research Department annual report 2000

    Energy Technology Data Exchange (ETDEWEB)

    Majborn, B.; Damkjaer, A.; Nielsen, S.P.; Nonboel, E

    2001-08-01

    The report presents a summary of the work of the Nuclear Safety Research Department in 2000. The department's research and development activities were organized in two research programmes: 'Radiation Protection and Reactor Safety' and 'Radioecology and Tracer Studies'. In addition the department was responsible for the tasks 'Applied Health Physics and Emergency Preparedness', 'Dosimetry', 'Environmental Monitoring', and Irradiation and Isotope Services'. Lists of publications, committee memberships and staff members are included. (au)

  4. Annual report 2011. Institute of Radiochemistry

    International Nuclear Information System (INIS)

    Bernhard, G.

    2011-01-01

    The Institute of Radiochemistry (IRC) IS one of the seven institutes of the Helmholtz- Zentrum Dresden-Rossendorf (HZDR). The research activities are fully integrated into the ''Nuclear Safety Research Program'' of the Helmholtz Association and focused on the topic ''Safety of Nuclear Waste Disposal''. The research objectives are to generate better process understanding and data for the long-term safety analysis of a nuclear waste disposal in the deep geological underground. A better knowledge about the dominating processes essential for radionuclide (actinide) mobilization and immobilization on the molecular level is needed for the assessment of the macroscopic processes which determine the transport and distribution of radioactivity in the environment. Special emphasis is put on the biological mediated transport of long-lived radionuclides in the geosphere and their interaction with different biosystems like biota and human organism for a better calculation of environmental and health risks. Advanced knowledge is needed for description of the processes dominating at the interfaces between geo- and bio-systems related to the distribution of long-lived radionuclides in various bio-systems along the food chain. More than 120 scientists, technicians, and students, working on their Ph.D., diploma, master, or bachelor thesis, were employed at the Institute of Radiochemistry in 2011. About 20 Ph.D. students are working at the institute. Promotion of young scientists is an important requirement to ensure the competence and further excellent scientific results in the discipline of radiochemistry in future times. We accomplished many new scientific results in the past year, which are presented in this Annual Report, and about 50 original papers were published in peer-reviewed international scientific journals. In 2011, the future research profile of the HZDR was under discussion with the aim to focus the research fields and programs. One result of this process was the

  5. Annual report 2011. Institute of Radiochemistry

    Energy Technology Data Exchange (ETDEWEB)

    Bernhard, G [ed.

    2011-07-01

    The Institute of Radiochemistry (IRC) IS one of the seven institutes of the Helmholtz- Zentrum Dresden-Rossendorf (HZDR). The research activities are fully integrated into the ''Nuclear Safety Research Program'' of the Helmholtz Association and focused on the topic ''Safety of Nuclear Waste Disposal''. The research objectives are to generate better process understanding and data for the long-term safety analysis of a nuclear waste disposal in the deep geological underground. A better knowledge about the dominating processes essential for radionuclide (actinide) mobilization and immobilization on the molecular level is needed for the assessment of the macroscopic processes which determine the transport and distribution of radioactivity in the environment. Special emphasis is put on the biological mediated transport of long-lived radionuclides in the geosphere and their interaction with different biosystems like biota and human organism for a better calculation of environmental and health risks. Advanced knowledge is needed for description of the processes dominating at the interfaces between geo- and bio-systems related to the distribution of long-lived radionuclides in various bio-systems along the food chain. More than 120 scientists, technicians, and students, working on their Ph.D., diploma, master, or bachelor thesis, were employed at the Institute of Radiochemistry in 2011. About 20 Ph.D. students are working at the institute. Promotion of young scientists is an important requirement to ensure the competence and further excellent scientific results in the discipline of radiochemistry in future times. We accomplished many new scientific results in the past year, which are presented in this Annual Report, and about 50 original papers were published in peer-reviewed international scientific journals. In 2011, the future research profile of the HZDR was under discussion with the aim to focus the research fields and programs. One result of this process was the

  6. Potsdam Institute for Climate Impact Research: Computer simulation -climate impact research. Final report

    International Nuclear Information System (INIS)

    1993-07-01

    Climate impact assessment is a new field of research which, owing to international and national efforts to understand and cope with the impending global climate changes on a global, regional and local level, has rapidly become a central field of research of the Federal Ministry of Research and Technology. In contrast to other countries, Germany had no research facilities and infrastructure that could be used. The Potsdam Institute for Climate Impact Research was to provide the infrastructure basis for climate impact research in Germany. The Institute was founded by the BMFT and the Land of Brandenburg. (orig.) [de

  7. Transport safety research abstracts. No. 1

    International Nuclear Information System (INIS)

    1991-07-01

    The Transport Safety Research Abstracts is a collection of reports from Member States of the International Atomic Energy Agency, and other international organizations on research in progress or just completed in the area of safe transport of radioactive material. The main aim of TSRA is to draw attention to work that is about to be published, thus enabling interested parties to obtain further information through direct correspondence with the investigators. Information contained in this issue covers work being undertaken in 6 Member States and contracted by 1 international organization; it is hoped with succeeding issues that TSRA will be able to widen this base. TSRA is modelled after other IAEA publications describing work in progress in other programme areas, namely Health Physics Research Abstracts (No. 14 was published in 1989), Waste Management Research Abstracts (No. 20 was published in 1990), and Nuclear Safety Research Abstracts (No. 2 was published in 1990)

  8. 75 FR 65018 - National Institute for Occupational Safety and Health; Designation of a Class of Employees for...

    Science.gov (United States)

    2010-10-21

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES National Institute for Occupational Safety and Health... Occupational Safety and Health (NIOSH), Department of Health and Human Services (HHS). ACTION: Notice. SUMMARY... aggregating at least 250 work days, occurring either solely under this employment, or in combination with work...

  9. 75 FR 57024 - National Institute for Occupational Safety and Health; Designation of a Class of Employees for...

    Science.gov (United States)

    2010-09-17

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES National Institute for Occupational Safety and Health... Occupational Safety and Health (NIOSH), Department of Health and Human Services (HHS). ACTION: Notice. SUMMARY... number of work days aggregating at least 250 work days, occurring either solely under this employment or...

  10. 75 FR 32783 - National Institute for Occupational Safety and Health; Designation of a Class of Employees for...

    Science.gov (United States)

    2010-06-09

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES National Institute for Occupational Safety and Health... Occupational Safety and Health (NIOSH), Department of Health and Human Services (HHS). ACTION: Notice. SUMMARY... aggregating at least 250 work days, occurring either solely under this employment or in combination with work...

  11. Main research results in the field of nuclear power engineering of the Nuclear Reactors and Thermal Physics Institute in 2014

    International Nuclear Information System (INIS)

    Trufanov, A.A.; Orlov, Yu.I.; Sorokin, A.P.; Chernonog, V.L.

    2015-01-01

    The main results of scientific and technological activities for last years of the Nuclear Reactors and Thermal Physics Institute FSUE SSC RF - IPPE in solving problems of nuclear power engineering are presented. The work have been carried out on the following problems: justification of research and development solutions and safety of NPPs with fast reactors of new generation with sodium (BN-1200, MBIR) and lead (BREST-OD-300) coolants, justification of safety of operating and advanced NPPs with WWER reactor facilities (WWER-1000, AEhS 2006, WWER-TOI), development and benchmarking of computational codes, research and development support of Beloyarsk-3 (BN-600) and Bilibino (BN-800) NPPs operation, decommissioning of AM and BR-10 research reactors, pilot scientific studies (WWER-SKD, ITER), international scientific and technical cooperation. Problems for further investigations are charted [ru

  12. Reactor safety research - visible demonstrations and credible computations

    Energy Technology Data Exchange (ETDEWEB)

    Loewenstein, W B; Divakaruni, S M

    1985-11-01

    EPRI has been conducting nuclear safety research for a number of years with the primary goal of assuring the safety and reliability of the nuclear plants. The visibility is emphasized by sponsoring or participating in large scale test demonstrations to credibly support the complex computations that are the basis for quantification of safety margins. Recognizing the success of the airline industry in receiving favorable public perception, the authors compare the design and operation practices of the airline industry with those of the nuclear industry practices to identify the elements contributing to public concerns and unfavorable perceptions. In this paper, authors emphasize the importance of proper communications of research results to the public in a manner that non-specialists understand. Further, EPRI supported research and results in the areas of source term, seismic and structural engineering research, analysis using probabilistic risk assessment (PRA), quantification of safety margins, digital technology development and implementation, and plant transient and performance evaluations are discussed in the paper. (orig./HP).

  13. Reactor safety research - visible demonstrations and credible computations

    International Nuclear Information System (INIS)

    Loewenstein, W.B.; Divakaruni, S.M.

    1985-01-01

    EPRI has been conducting nuclear safety research for a number of years with the primary goal of assuring the safety and reliability of the nuclear plants. The visibility is emphasized by sponsoring or participating in large scale test demonstrations to credibly support the complex computations that are the basis for quantification of safety margins. Recognizing the success of the airline industry in receiving favorable public perception, the authors compare the design and operation practices of the airline industry with those of the nuclear industry practices to identify the elements contributing to public concerns and unfavorable perceptions. In this paper, authors emphasize the importance of proper communications of research results to the public in a manner that non-specialists understand. Further, EPRI supported research and results in the areas of source term, seismic and structural engineering research, analysis using probabilistic risk assessment (PRA), quantification of safety margins, digital technology development and implementation, and plant transient and performance evaluations are discussed in the paper. (orig./HP)

  14. NRC review of Electric Power Research Institute's Advanced Light Water Reactor Utility Requirements Document - Evolutionary plant designs, Chapter 1, Project No. 669

    International Nuclear Information System (INIS)

    1992-08-01

    The staff of the US Nuclear Regulatory Commission has prepared Volume 2 (Parts 1 and 2) of a safety evaluation report (SER), ''NRC Review of Electric Power Research Institute's Advanced Light Water Reactor Utility Requirements Document -- Evolutionary Plant Designs,'' to document the results of its review of the Electric Power Research Institute's ''Advanced Light Water Reactor Utility Requirements Document.'' This SER gives the results of the staff's review of Volume II of the Requirements Document for evolutionary plant designs, which consists of 13 chapters and contains utility design requirements for an evolutionary nuclear power plant (approximately 1300 megawatts-electric)

  15. The Aldo Leopold Wilderness Research Institute: a national wilderness research program in support of wilderness management

    Science.gov (United States)

    Vita Wright

    2000-01-01

    The Aldo Leopold Wilderness Research Institute strives to provide scientific leadership in developing and applying the knowledge necessary to sustain wilderness ecosystems and values. Since its 1993 dedication, researchers at this federal, interagency Institute have collaborated with researchers and managers from other federal, academic and private institutions to...

  16. Nuclear safety research at the European Commission's Joint Research Centre

    International Nuclear Information System (INIS)

    Toerroenen, K.

    2003-01-01

    Nuclear power plants currently generate some 35 % of electricity used in the European Union and applicant countries. Nuclear safety will therefore remain a priority for the EU, particularly in view of enlargement, the need to monitor ageing nuclear installations and the licencing of advanced new reactor systems. The European Commission's Joint Research Centre (JRC), with its long involvement and recognised competence in nuclear safety related activities, provides direct support to the European Commission services responsible for nuclear safety and civil protection. (author)

  17. The Health and Safety Executive's strategy for nuclear safety research 1996

    International Nuclear Information System (INIS)

    1996-01-01

    This brochure illustrates HSE's nuclear safety research strategy for 1996. It is divided into two parts. The first part presents HSE's overall strategy. The second contains short strategy statements for the individual areas detailed above, providing a rationale and objectives for the particular safety issues in the NRI, where greater detail can be found. (author)

  18. Progress report concerning safety research for nuclear reactor facilities

    International Nuclear Information System (INIS)

    1978-01-01

    Examination and evaluation of safety research results for nuclear reactor facilities have been performed, as more than a year has elapsed since the plan had been initiated in April, 1976, by the special sub-committee for the safety of nuclear reactor facilities. The research is carried out by being divided roughly into 7 items, and seems to be steadily proceeding, though it does not yet reach the target. The above 7 items include researches for (1) criticality accident, (2) loss of coolant accident, (3) safety for light water reactor fuel, (4) construction safety for reactor facilities, (5) reduction of release of radioactive material, (6) safety evaluation based on the probability theory for reactor facilities, and (7) aseismatic measures for reactor facilities. With discussions on the progress and the results of the research this time, research on the behaviour on fuel in abnormal transients including in-core and out-core experiments has been added to the third item, deleting the power-cooling mismatch experiment in Nuclear Safety Research Reactor of JAERI. Also it has been decided to add two research to the seventh item, namely measured data collection, classification and analysis, and probability assessment of failures due to an earthquake. For these 7 items, the report describes the concrete contents of research to be performed in fiscal years of 1977 and 1978, by discussing on most rational and suitable contents conceivable at present. (Wakatsuki, Y.)

  19. FZR Institute of Radiochemistry. Annual report 1991

    International Nuclear Information System (INIS)

    Bernhard, G.

    1992-04-01

    The Research Center Rossendorf Inc. was founded on 1 January 1992 as an Institute of the Blue List. It is financed in equal shares by the Free State of Saxony and the Federal Republic of Germany. The Research Center Rossendorf (FZR) carries out its scientific work in five institutes: Institute of Ion Beam Physics and Materials Research; Institute of Nuclear and Hadronic Physics; Institute of Safety Research; Institute of Bioanorganic and Radiopharmaceutical Chemistry; Institute of Radiochemistry. The presentation of the Institute of Radiochemistry is to be considered a description of working tasks from today's angle. In the course of the formation process up to the end of the year specifications and partly also substantial changes will have to be considered. Although the Research Center Rossendorf has been recently founded, its plans are based of course on the scientific experiences of its staff. The said experiences form the basis for the status report on the lines of work. The last part compiles abridged versions of individual results achieved in 1991, documenting for specialists the work done by the groups of scientists. (orig./BBR) [de

  20. UNLV Information Science Research Institute. Quarterly progress report

    International Nuclear Information System (INIS)

    Nartker, T.A.

    1994-01-01

    This document summarizes the activities and progress for the 1994 Fall quarter for the UNLV Information Science Research Institute. Areas covered include: Symposium activity, Staff activity, Document analysis program, Text-retrieval program, and Institute activity