WorldWideScience

Sample records for safety research unit

  1. Current researches on safety assessment of radioactive waste disposal in the United States

    International Nuclear Information System (INIS)

    Tasaka, Hiroshi; Kiyose, Ryohei

    1980-01-01

    Recently, the problem of safe disposal of radioactive waste generated from nuclear fuel cycle becomes more important in Japan. On the other hand, many researches on shallow land burial of low-level wastes and geologic isolation of high-level wastes have been carried out in the United States of America. In this report, the researches on the safety assessment of radioactive waste disposal in the United States of America were briefly introduced with emphasis on the studies on behavior and migration of radionuclide from disposed waste in geosphere. (author)

  2. 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).

  3. 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)

  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. 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)

  6. 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)

  7. Categorization of safety related motor operated valve safety significance for Ulchin Unit 3

    International Nuclear Information System (INIS)

    Kang, D. I.; Kim, K. Y.

    2002-03-01

    We performed a categorization of safety related Motor Operated Valve (MOV) safety significance for Ulchin Unit 3. The safety evaluation of MOV of domestic nuclear power plants affects the generic data used for the quantification of MOV common cause failure ( CCF) events in Ulchin Units 3 PSA. Therefore, in this study, we re-estimated the MGL(Multiple Greek Letter) parameter used for the evaluation of MOV CCF probabilities in Ulchin Units 3 Probabilistic Safety Assessment (PSA) and performed a classification of the MOV safety significance. The re-estimation results of the MGL parameter show that its value is decreased by 30% compared with the current value in Ulchin Unit 3 PSA. The categorization results of MOV safety significance using the changed value of MGL parameter shows that the number of HSSCs(High Safety Significant Components) is decreased by 54.5% compared with those using the current value of it in Ulchin Units 3 PSA

  8. A step towards positive safety culture in DAE units

    International Nuclear Information System (INIS)

    Ramprasad, K.

    2016-01-01

    Department of Atomic Energy (DAE) has considered safety as its priority, since inception in late 1950s, in all its activities. A belief in safety principles like defense-in depth, diversity, multi-tier review, etc. has laid a long path of success in safety management for decades. Multitude of DAE activities in the past few decades, especially in application of nuclear energy in scientific research, industrial, medical, agriculture and food technologies, often, poses new challenges in safety management. A good safety management system is in place in DAE units to cope up with the challenges of the evolving technologies. An opportunity is taken through this workshop to highlight extra efforts to be taken to inch forward in developing a strong safety culture

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

    International Nuclear Information System (INIS)

    Watson, P.

    1996-01-01

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

  10. 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

  11. 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.

  12. Introducing the Comprehensive Unit-based Safety Program for mechanically ventilated patients in Saudi Arabian Intensive Care Units

    Directory of Open Access Journals (Sweden)

    Raymond M Khan

    2017-01-01

    Full Text Available Over the past decade, there have been major improvements to the care of mechanically ventilated patients (MVPs. Earlier initiatives used the concept of ventilator care bundles (sets of interventions, with a primary focus on reducing ventilator-associated pneumonia. However, recent evidence has led to a more comprehensive approach: The ABCDE bundle (Awakening and Breathing trial Coordination, Delirium management and Early mobilization. The approach of the Comprehensive Unit-based Safety Program (CUSP was developed by patient safety researchers at the Johns Hopkins Hospital and is supported by the Agency for Healthcare Research and Quality to improve local safety cultures and to learn from defects by utilizing a validated structured framework. In August 2015, 17 Intensive Care Units (ICUs (a total of 271 beds in eight hospitals in the Kingdom of Saudi Arabia joined the CUSP for MVPs (CUSP 4 MVP that was conducted in 235 ICUs in 169 US hospitals and led by the Johns Hopkins Armstrong Institute for Patient Safety and Quality. The CUSP 4 MVP project will set the stage for cooperation between multiple hospitals and thus strives to create a countrywide plan for the management of all MVPs in Saudi Arabia.

  13. Finnish research programmes on nuclear power plant safety

    International Nuclear Information System (INIS)

    Puska, E. K.

    2010-01-01

    The current Finnish national research programme on nuclear power plant safety SAFIR2010 for the years 2007-2010 as well as the coming SAFIR2014 programme for the years 2011-2014 are based on the chapter 7a, 'Ensuring expertise', of the Finnish Nuclear Energy Act. The objective of this chapter is realised in the research work and education of experts in the projects of these research programmes. SAFIR2010 research programme is divided in eight research areas that are Organisation and human, Automation and control room, Fuel and reactor physics, Thermal hydraulics, Severe accidents, Structural safety of reactor circuit, Construction safety, and Probabilistic Safety Analysis (PSA). All the research areas include both projects in their own area and interdisciplinary co-operational projects. Research projects of the programme are chosen on the basis of annual call for proposals. In 2010 research is carried out in 33 projects in SAFIR2010. VTT is the responsible research organisation in 26 of these projects and VTT is also the coordination unit of SAFIR2010 and SAFIR2014. In 2007-2009 SAFIR2010 produced 497 Specified research results (Deliverables), 618 Publications, and 33 Academic degrees. SAFIR2010 programme covers approximately half of the reactor safety research volume in Finland currently. In 2010 the programme volume is EUR 7.1 million and 47 person years. The major funding partners are VYR with EUR 2.96 million, VTT with EUR 2.66 million, Fortum with EUR 0.28 million, TVO with EUR 0.19 million, NKS with EUR 0.15 million, EU with only EUR 0.03 million and other partners with EUR 0.85 million. The new decisions-in-principle on Olkiluoto unit 4 for Teollisuuden Voima and new nuclear power plant for Fennovoima ratified by the Finnish Parliament on 1 July 2010 increase the annual funding collected according to the Finnish Nuclear Energy Act from Fennovoima, Fortum and Teollisuuden Voima for the SAFIR2014 programme to EUR 5.2 million from the current level of EUR 3

  14. [Analysis of the safety culture in a Cardiology Unit managed by processes].

    Science.gov (United States)

    Raso-Raso, Rafael; Uris-Selles, Joaquín; Nolasco-Bonmatí, Andreu; Grau-Jornet, Guillermo; Revert-Gandia, Rosa; Jiménez-Carreño, Rebeca; Sánchez-Soriano, Ruth M; Chamorro-Fernández, Carlos I; Marco-Francés, Elvira; Albero-Martínez, José V

    2017-04-04

    Safety culture is one of the requirements for preventing the occurrence of adverse effects. However, this has not been studied in the field of cardiology. The aim of this study is to evaluate the safety culture in a cardiology unit that has implemented and certified an integrated quality and risk management system for patient safety. A cross-sectional observational study was conducted in 2 consecutive years, with all staff completing the Spanish version of the questionnaire, "Hospital Survey on Patient Safety Culture" of the "Agency for Healthcare Research and Quality", with 42 items grouped into 12 dimensions. The percentage of positive responses in each dimension in 2014 and 2015 were compared, as well as national data and United States data, following the established rules. The overall assessment out of a possible 5, was 4.5 in 2014 and 4.7 in 2015. Seven dimensions were identified as strengths. The worst rated were: staffing, management support and teamwork between units. The comparison showed superiority in all dimensions compared to national data, and in 8 of them compared to American data. The safety culture in a Cardiology Unit with an integrated quality and risk management patient safety system is high, and higher than nationally in all its dimensions and in most of them compared to the United States. Copyright © 2017 Instituto Nacional de Cardiología Ignacio Chávez. Publicado por Masson Doyma México S.A. All rights reserved.

  15. 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

  16. 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)

  17. Tractor Safety. Unit A-9.

    Science.gov (United States)

    Luft, Vernon D.; Backlund, Paul

    This document is a teacher's guide for a unit in tractor and machinery safety for college freshmen. It is intended to be used for 10 hours of instruction for freshmen who are intending to work on or around machinery. Safety hazards directly and indirectly related to many types of machinery are covered in addition to tractors. The objectives of the…

  18. 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

  19. A relational leadership perspective on unit-level safety climate.

    Science.gov (United States)

    Thompson, Debra N; Hoffman, Leslie A; Sereika, Susan M; Lorenz, Holly L; Wolf, Gail A; Burns, Helen K; Minnier, Tamra E; Ramanujam, Rangaraj

    2011-11-01

    This study compared nursing staff perceptions of safety climate in clinical units characterized by high and low ratings of leader-member exchange (LMX) and explored characteristics that might account for differences. Frontline nursing leaders' actions are critical to ensure patient safety. Specific leadership behaviors to achieve this goal are underexamined. The LMX perspective has shown promise in nonhealthcare settings as a means to explain safety climate perceptions. Cross-sectional survey of staff (n = 711) and unit directors from 34 inpatient units in an academic medical center was conducted. Significant differences were found between high and low LMX scoring units on supervisor safety expectations, organizational learning-continuous improvement, total communication, feedback and communication about errors, and nonpunitive response to errors. The LMX perspective can be used to identify differences in perceptions of safety climate among nursing staff. Future studies are needed to identify strategies to improve staff safety attitudes and behaviors. Copyright © 2011 Wolters Kluwer Health | Lippincott Williams & Wilkins

  20. 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

  1. 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)

  2. 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.

  3. 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)

  4. Activities on safety for the cross-cutting issue of research reactors in the IAEA

    International Nuclear Information System (INIS)

    Perrotta, J.A.; Boado Magan, H.J.

    2003-01-01

    IAEA activities in the field of research reactor safety are included in the programme of the Division of Nuclear Installations Safety and implemented by the Engineering Safety Section through its Research Reactor Safety Unit. 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 are discussed in this paper: (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 TECDOCs); (c) activities related to the Incident Reporting System for Research Reactor (IRSRR); (d) the new features implemented for the (Integrated Safety Assessment of Research Reactors) INSARR missions; (e) the Code of Conduct on the Safety of Research Reactors developed, following the General Conference Resolution GC(45)/RES/10; and (f) the survey on the safety of research reactors conducted in the year 2002 and the results obtained. (author)

  5. 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.)

  6. 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)

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

    International Nuclear Information System (INIS)

    1981-05-01

    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. 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

  8. 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)

  9. Safety Goal, Multi-unit Risk and PSA Uncertainty

    Energy Technology Data Exchange (ETDEWEB)

    Yang, Joon-Eon [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2015-10-15

    The safety goal is an answer of each country to the question 'How safe is safe enough?'. Table 1 shows some examples of the safety goal. However, many countries including Korea do not have the official safety goal for NPPs up to now since the establishment of safety goal is not just a technical issue but a very complex socio-technical issue. In establishing the safety goal for nuclear facilities, we have to consider various factors including not only technical aspects but also social, cultural ones. Recently, Korea is trying to establish the official safety goal. In this paper, we will review the relationship between the safety goal and Probabilistic Safety Assessment (PSA). We will also address some important technical issues to be considered in establishing the safety goal for NPPs from PSA point of view, i.e. a multi-unit risk issue and the uncertainty of PSA. In this paper, we reviewed some issues related to the safety goal and PSA. We believe that the safety goal is to be established in Korea considering the multi-unit risk. In addition, the relationship between the safety goal and PSA should be also defined clearly since PSA is the only way to answer to the question 'How safe is safe enough?'.

  10. Safety R and D Needs in Multi-Unit PSA from a Regulatory Viewpoint

    Energy Technology Data Exchange (ETDEWEB)

    Heo, Gyunyoung; Yoon, Ji Woong [Kyung Hee University, Yongin (Korea, Republic of); Kim, Man Cheol [Chung-Ang University, Seoul (Korea, Republic of)

    2016-10-15

    The Nuclear Safety and Security Commission (NSSC) NSSC’s recent approval of the construction permits and operation licenses of Shin Kori units 3 to 6 has brought attention to the multi-unit probabilistic safety assessment (PSA). The disaster in Fukushima revealed the risks associated with the use of spent fuel pools (SFPs), and the linear (or non-linear) consequences of radiation leaks from multi-units in particular, has raised concerns. The number of nuclear power plants (NPPs) in operation will increase to ten at the Kori and Shin Kori sites when the construction of Units 5 and 6 is complete - the highest concentration of power reactors in one region in world history. Nuclear disasters do not happen frequently, but when one does happen, its cascading effects can inflict massive human and environmental loss. Proper safety measures are needed as more nuclear installations are put in place. Nuclear regulators are forced to promptly produce a sufficient degree of realistic and objective risk assessment results to meet the rapidly-increasing demand for multi-unit PSA, while striving to achieve matching levels of technological development. The issues with the technological aspects of PSA would still be inherent even after a few years of research, and ensuring the safety of multi-units would still prove challenging. Experts are however relieved that the general public is now much more familiar with the concept of PSA than in the past, which indicates a rise in the degree of public understanding of technology. More studies should be done on multi-unit regulation and safety so as to steer the government in the proper direction for enacting policies aimed to ensure the health of local residents. In conclusion, the technical problems associated with multi-unit PSA that were not mentioned in this paper are essentially similar to their single-unit counterparts, therefore, reinforcing the base infrastructure of PSAs in general will work towards resolving such technical

  11. 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

  12. 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

  13. Safety review on unit testing of safety system software of nuclear power plant

    International Nuclear Information System (INIS)

    Liu Le; Zhang Qi

    2013-01-01

    Software unit testing has an important place in the testing of safety system software of nuclear power plants, and in the wider scope of the verification and validation. It is a comprehensive, systematic process, and its documentation shall meet the related requirements. When reviewing software unit testing, attention should be paid to the coverage of software safety requirements, the coverage of software internal structure, and the independence of the work. (authors)

  14. Safety of milrinone use in neonatal intensive care units

    NARCIS (Netherlands)

    S. Samiee-Zafarghandy; S.R. Raman (Sudha R.); J.N. van den Anker (John); K. McHutchison (Kerstin); C.P. Hornik; R.H. Clark; P.B. Smith; D.K. Benjamin (Daniel K.); K. Berezny (Katherine); J. Barrett (Jeffrey); E.V. Capparelli (Edmund); M. Cohen-Wolkowiez (Michael); G.L. Kearns (Greg); M. Laughon (Matthew); A. Muelenaer (Andre); T. Michael O'Shea; I.M. Paul (Ian M.); K. Wade (Kelly); T.J. Walsh (Thomas J.)

    2015-01-01

    textabstractBackground: Milrinone use in the neonatal intensive care unit has increased over the last 10. years despite a paucity of published safety data in infants. We sought to determine the safety of milrinone therapy among infants in the neonatal intensive care unit. Methods: We conducted a

  15. 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

  16. 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

  17. USA NRC/RSR Data Bank System and Reactor Safety Research Data Repository (RSRDR)

    International Nuclear Information System (INIS)

    Maskewitz, B.F.; Bankert, S.F.

    1979-01-01

    The United States Nuclear Regulatory Commission (NRC), through its Division of Reactor Safety Research (RSR) of the Office of Nuclear Regulatory Research, has established the NRC/RSR Data Bank Program to collect, process, and make available data from the many domestic and foreign water reactor safety research programs. An increasing number of requests for data and/or calculations generated by NRC Contractors led to the initiation of the program which allows timely and direct access to water reactor safety data in a manner most useful to the user. The program consists of three main elements: data sources, service organizations, and a data repository

  18. 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.)

  19. 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)

  20. National nuclear power plant safety research 2011-2014. SAFIR2014 framework plan

    International Nuclear Information System (INIS)

    2010-01-01

    A country utilising nuclear energy is presumed to possess a sufficient infrastructure to cover the education and research in this field, besides the operating organisations of the plants and a regulatory body. The starting point of public nuclear safety research programmes is that they provide the necessary conditions for retaining the knowledge needed for ensuring the continuance of safe and economic use of nuclear power, for development of new know-how and for participation in international cooperation. In fact, the Finnish organisations engaged in research in this sector have been an important resource which the various ministries, the Radiation and Nuclear Safety Authority (STUK) and the power companies have had at their disposal. Ministry of employment and the economy appointed a group to write the Framework Plan of the new programme. This report contains a proposal for the general outline of the programme, entitled as SAFIR2014 (SAfety of Nuclear Power Plants - Finnish National Research Programme). The plan has been made for the period 2011-2014, but it is based on safety challenges identified for a longer time span as well. Olkiluoto 3, the new nuclear power plant unit under construction and new decisions-in-principle have also been taken into account in the plan. The safety challenges set by the existing plants and the new projects, as well as the ensuing research needs do, however, converge to a great extent. The research programme is strongly based on the Chapter 7a of the Finnish Nuclear Energy Act. The construction of new power plant units will increase the need for experts in the field in Finland. At the same time, the retirement of the existing experts is continuing. These factors together will call for more education and training, in which active research activities play a key role. This situation also makes long-term safety research face a great challenge. The Framework Plan aims to define the important research needs related to the safety

  1. 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.

  2. 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

  3. 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.)

  4. 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)

  5. Safety. Unit 8: A Core Curriculum of Related Instruction for Apprentices.

    Science.gov (United States)

    New York State Education Dept., Albany. Bureau of Occupational and Career Curriculum Development.

    The safety education unit is presented to assist apprentices to acquire a general knowledge of procedures for insuring safety on the job. The unit consists of 10 modules: (1) the Occupational Safety and Health Act: safety and health bill of rights for workers; (2) accident prevention; (3) first aid; (4) accident reports; importance, use, and how…

  6. 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

  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. 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

  9. 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

  10. 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)

  11. 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)

  12. 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)

  13. 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

  14. The impact of safety organizing, trusted leadership, and care pathways on reported medication errors in hospital nursing units.

    Science.gov (United States)

    Vogus, Timothy J; Sutcliffe, Kathleen M

    2011-01-01

    Prior research has found that safety organizing behaviors of registered nurses (RNs) positively impact patient safety. However, little research exists on the joint benefits of safety organizing and other contextual factors that help foster safety. Although we know that organizational practices often have more powerful effects when combined with other mutually reinforcing practices, little research exists on the joint benefits of safety organizing and other contextual factors believed to foster safety. Specifically, we examined the benefits of bundling safety organizing with leadership (trust in manager) and design (use of care pathways) factors on reported medication errors. A total of 1033 RNs and 78 nurse managers in 78 emergency, internal medicine, intensive care, and surgery nursing units in 10 acute-care hospitals in Indiana, Iowa, Maryland, Michigan, and Ohio who completed questionnaires between December 2003 and June 2004. Cross-sectional analysis of medication errors reported to the hospital incident reporting system for the 6 months after the administration of the survey linked to survey data on safety organizing, trust in manager, use of care pathways, and RN characteristics and staffing. Multilevel Poisson regression analyses indicated that the benefits of safety organizing on reported medication errors were amplified when paired with high levels of trust in manager or the use of care pathways. Safety organizing plays a key role in improving patient safety on hospital nursing units especially when bundled with other organizational components of a safety supportive system.

  15. National Nuclear Power Plant Safety Research 2003-2006. Proposal for the Content and Organisation of a New Research Programme

    International Nuclear Information System (INIS)

    2002-11-01

    A country utilising nuclear energy is presumed to possess a sufficient infrastructure to cover the education and research in this field, besides the operating and supervisory organisations of the plants. The starting point of public nuclear safety research programmes is that they provide the necessary conditions for retaining the knowledge needed for ensuring the continuance of safe and economic use of nuclear power, for development of new know-how and for participation in international cooperation. In fact, the Finnish organisations engaged in research in this sector have been an important resource which the various ministries, the Radiation and Nuclear Safety Authority (STUK) and the power companies have had at their disposal. The Steering Group to the Finnish Research Programme on Nuclear Power Plant Safety (FINNUS), which was launched upon the assignment of the Advisory Committee on Nuclear Energy, appointed in spring 2002 a group to plan the contents of the new programme. This report contains a proposal for the general outline of the programme, preliminarily entitled as SAFIR (SAfety of Nuclear Power Plants - Finnish National Research Programme). The plan has been made for the period 2003-2006, but it is based on safety challenges identified for a longer time span as well. The favourable decision-in-principle on a new nuclear power plant unit adopted by Parliament has also been taken into account in the plan. The safety challenges set by the existing plants and the new plant unit, as well as the ensuing research needs do, however, converge to a great extent. The construction of the new power plant unit will increase the need for experts in the field in Finland. At the same time, the retirement of the existing experts is continuing. These factors together will call for more education and training, in which active research activities play a key role. This situation also makes long-term safety research face a great challenge. The general plan aims to define the

  16. 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.)

  17. Second periodic safety review of Angra Nuclear Power Station, unit 1

    Energy Technology Data Exchange (ETDEWEB)

    Martins, Carlos F.O.; Crepaldi, Roberto; Freire, Enio M., E-mail: ottoncf@tecnatom.com.br, E-mail: emfreire46@gmail.com, E-mail: robcrepaldi@hotmail.com [Tecnatom do Brasil Engenharia e Servicos Ltda, Rio de Janeiro, RJ (Brazil); Campello, Sergio A., E-mail: sacampe@eletronuclear.gov.br [Eletrobras Termonuclear S.A. (ELETRONUCLEAR), Rio de Janeiro, RJ (Brazil)

    2015-07-01

    This paper describes the second Periodic Safety Review (PSR2-A1) of Angra Nuclear Power Station, Unit 1, prepared by Eletrobras Eletronuclear S.A. and Tecnatom do Brasil Engenharia e Servicos Ltda., during Jul.2013-Aug.2014, covering the period of 2004-2013. The site, in Angra dos Reis-RJ, Brazil, comprises: Unit 1, (640 MWe, Westinghouse PWR, operating), Unit 2 (1300 MWe, KWU/Areva, operating) and Unit 3 (1405 MWe, KWU/Areva, construction). The PSR2-A1 attends the Standards 1.26-Safety in Operation of Nuclear Power Plants, Brazilian Nuclear Regulatory Commission (CNEN), and IAEA.SSG.25-Periodic Safety Review of Nuclear Power Plants. Within 18 months after each 10 years operation, the operating organization shall perform a plant safety review, to investigate the evolution consequences of safety code and standards, regarding: Plant design; structure, systems and components behavior; equipment qualification; plant ageing management; deterministic and probabilistic safety analysis; risk analysis; safety performance; operating experience; organization and administration; procedures; human factors; emergency planning; radiation protection and environmental radiological impacts. The Review included 6 Areas and 14 Safety Parameters, covered by 33 Evaluations.After document evaluations and discussions with plant staff, it was generated one General and 33 Specific Guide Procedures, 33 Specific and one Final Report, including: Description, Strengths, Deficiencies, Areas for Improvement and Conclusions. An Action Plan was prepared by Electronuclear for the recommendations. It was concluded that the Unit was operated within safety standards and will attend its designed operational lifetime, including possible life extensions. The Final Report was submitted to CNEN, as one requisite for renewal of the Unit Permanent Operation License. (author)

  18. Second periodic safety review of Angra Nuclear Power Station, unit 1

    International Nuclear Information System (INIS)

    Martins, Carlos F.O.; Crepaldi, Roberto; Freire, Enio M.; Campello, Sergio A.

    2015-01-01

    This paper describes the second Periodic Safety Review (PSR2-A1) of Angra Nuclear Power Station, Unit 1, prepared by Eletrobras Eletronuclear S.A. and Tecnatom do Brasil Engenharia e Servicos Ltda., during Jul.2013-Aug.2014, covering the period of 2004-2013. The site, in Angra dos Reis-RJ, Brazil, comprises: Unit 1, (640 MWe, Westinghouse PWR, operating), Unit 2 (1300 MWe, KWU/Areva, operating) and Unit 3 (1405 MWe, KWU/Areva, construction). The PSR2-A1 attends the Standards 1.26-Safety in Operation of Nuclear Power Plants, Brazilian Nuclear Regulatory Commission (CNEN), and IAEA.SSG.25-Periodic Safety Review of Nuclear Power Plants. Within 18 months after each 10 years operation, the operating organization shall perform a plant safety review, to investigate the evolution consequences of safety code and standards, regarding: Plant design; structure, systems and components behavior; equipment qualification; plant ageing management; deterministic and probabilistic safety analysis; risk analysis; safety performance; operating experience; organization and administration; procedures; human factors; emergency planning; radiation protection and environmental radiological impacts. The Review included 6 Areas and 14 Safety Parameters, covered by 33 Evaluations.After document evaluations and discussions with plant staff, it was generated one General and 33 Specific Guide Procedures, 33 Specific and one Final Report, including: Description, Strengths, Deficiencies, Areas for Improvement and Conclusions. An Action Plan was prepared by Electronuclear for the recommendations. It was concluded that the Unit was operated within safety standards and will attend its designed operational lifetime, including possible life extensions. The Final Report was submitted to CNEN, as one requisite for renewal of the Unit Permanent Operation License. (author)

  19. Measuring and benchmarking safety culture: application of the safety attitudes questionnaire to an acute medical admissions unit.

    Science.gov (United States)

    Relihan, E; Glynn, S; Daly, D; Silke, B; Ryder, S

    2009-12-01

    To assess the safety culture in an acute medical admissions unit (AMAU) of a teaching hospital in order to benchmark results against international data and guide a unit-based, integrated, risk management strategy. The safety attitudes questionnaire (SAQ), a validated instrument for the measurement of safety culture was applied to an AMAU. All AMAU healthcare staff (n = 92) were surveyed: doctors, nurses, healthcare assistants (HCAs) and allied healthcare professionals (AHPs). Safety attitude scores for the overall unit and individual caregiver types were assessed across six domains of safety culture. When compared against an international benchmark, the AMAU scored significantly higher for four of the six safety domains: p < 0.01 for 'teamwork climate', 'safety climate' and 'stress recognition' and p < 0.05 for 'job satisfaction'. The difference between nurse manager scores and the overall mean for the study group was statistically significant for the domains of 'teamwork climate' (p < 0.05) and 'safety climate' (p < 0.01). HCAs scored significantly lower relative to staff overall with regard to 'working conditions' (p < 0.05) and 'perceptions of management' (p < 0.01). The SAQ was successfully applied to an AMAU setting giving a valuable insight into staff issues of concern across the safety spectrum: employee and environmental safety, clinical risk management and medication safety.

  20. 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.

  1. 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

  2. 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.

  3. 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

  4. 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)

  5. Patient safety culture at neonatal intensive care units: perspectives of the nursing and medical team 1

    Science.gov (United States)

    Tomazoni, Andréia; Rocha, Patrícia Kuerten; de Souza, Sabrina; Anders, Jane Cristina; de Malfussi, Hamilton Filipe Correia

    2014-01-01

    OBJECTIVE: to verify the assessment of the patient safety culture according to the function and length of experience of the nursing and medical teams at Neonatal Intensive Care Units. METHOD: quantitative survey undertaken at four Neonatal Intensive Care Units in Florianópolis, Brazil. The sample totaled 141 subjects. The data were collected between February and April 2013 through the application of the Hospital Survey on Patient Safety Culture. For analysis, the Kruskal-Wallis and Chi-Square tests and Cronbach's Alpha coefficient were used. Approval for the research project was obtained from the Ethics Committee, CAAE: 05274612.7.0000.0121. RESULTS: differences in the number of positive answers to the Hospital Survey on Patient Safety Culture, the safety grade and the number of reported events were found according to the professional characteristics. A significant association was found between a shorter Length of work at the hospital and Length of work at the unit and a larger number of positive answers; longer length of experience in the profession represented higher grades and less reported events. The physicians and nursing technicians assessed the patient safety culture more positively. Cronbach's alpha demonstrated the reliability of the instrument. CONCLUSION: the differences found reveal a possible relation between the assessment of the safety culture and the subjects' professional characteristics at the Neonatal Intensive Care Units. PMID:25493670

  6. Nuclear safety research in HGF 2011

    International Nuclear Information System (INIS)

    Tromm, Walter

    2012-01-01

    After the events at the Japanese nuclear power plant of Fukushima Daiichi, the German federal government decided that Germany will give up electricity generation from nuclear power within a decade. The last reactor will be disconnected from the power grid in 2022. Helping to make this opt-out as safe as possible is one of the duties of the Helmholtz Association with its Nuclear Safety Research Program within the Energy Research Area. Also the demolition of nuclear power plants and the repository problem will keep society, and thus also research, busy for a number of decades to come. Giving up electricity production from nuclear power thus must not mean giving up the required nuclear technology competences. In the fields of reactor safety, demolition, final storage, radiation protection, and crisis management, in critical support of international developments, and for competent evaluation of nuclear facilities around Germany, these competences will be in demand far beyond the German opt-out. This is the reason why the final report by the Ethics Committee on 'Safe Energy Supply' emphasizes the importance of nuclear technology research. Close cooperation on national, European and international levels is indispensable in this effort. Also nuclear safety research in the Helmholtz Association is aligned with the challenges posed by the opt-out of the use of nuclear power. It is important that the high competences in the areas of plant safety and demolition, handling of radioactive waste, and safe final storage as well as radiation protection be preserved. The Nuclear Safety Research Program within the Energy Research Area of the Helmholtz Association therefore will continue studying scientific and technical aspects of the safety of nuclear reactors and the safety of nuclear waste management. These research activities are provident research conducted for society and must be preserved for a long period of time. The work is closely harmonized with the activities of the

  7. Safety improvement programme of WWER 440/230 units in Jaslovske Bohunice

    International Nuclear Information System (INIS)

    Tomek, J.

    2000-01-01

    A brief overview is given of the power sources in Slovakia which include 6 operational reactor units (4 at Jaslovske Bohunice and 2 at Mochovce) and 2 units under construction (at Mochovce). The efforts undertaken in the past 10 years and aimed at upgrading the nuclear safety of the two older (V-230 Soviet type) units at Bohunice are highlighted. The relevant regulatory decisions are dealt with and the measures already carried out are listed. Also characterized are several IAEA international safety assessment missions and safety-aimed meetings which took place in 1998 and 1999 and are of concern to the older Bohunice units. (A.K.)

  8. List of reports on reactor safety research by the BMFT and the USNRC

    International Nuclear Information System (INIS)

    1977-05-01

    This list reviews reports from the Federal Republic of Germany and from the United States of America concerning special problems in the field of Reactor Safety Research which have been collected 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 or reports appears quarterly. This edition contains all reports as registered from January through March 1977. (orig./HK) [de

  9. 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

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

    International Nuclear Information System (INIS)

    1982-02-01

    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 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

  11. 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

  12. Progress report - list of reports from BMFT, CEA, EPRI, JSTA and USNRC reactor safety research

    International Nuclear Information System (INIS)

    1982-10-01

    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. 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

  13. 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

  14. Technique for unit testing of safety software verification and validation

    International Nuclear Information System (INIS)

    Li Duo; Zhang Liangju; Feng Junting

    2008-01-01

    The key issue arising from digitalization of the reactor protection system for nuclear power plant is how to carry out verification and validation (V and V), to demonstrate and confirm the software that performs reactor safety functions is safe and reliable. One of the most important processes for software V and V is unit testing, which verifies and validates the software coding based on concept design for consistency, correctness and completeness during software development. The paper shows a preliminary study on the technique for unit testing of safety software V and V, focusing on such aspects as how to confirm test completeness, how to establish test platform, how to develop test cases and how to carry out unit testing. The technique discussed here was successfully used in the work of unit testing on safety software of a digital reactor protection system. (authors)

  15. 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.)

  16. Safety assessment of multi-unit NPP sites subject to external events

    International Nuclear Information System (INIS)

    Samaddar, Sujit; Hibino, Kenta; Coman, Ovidiu

    2014-01-01

    This paper presents a framework for conducting a probabilistic safety assessment of multi-unit sites against external events. The treatment of multiple hazard on a unit, interaction between units, implementation of severe accident measures, human reliability, environmental conditions, metric of risk for both reactor and non-reactor sources, integration of risk and responses and many such important factors need to be addressed within the context of this framework. The framework facilitates the establishment of a comprehensive methodology that can be applied internationally to the peer review of safety assessment of multi-unit sites under the impact of multiple external hazards. In summary, it can be said that the site safety assessment for a multi-unit site will be quite complex and need to start with individual unit risk assessments, these need to be combined considering the interactions between units and their responses, and the fragilities of the installations established considering the combined demands from all interactions. Using newly established risk metric the risk can then be integrated for the overall site. Fig. 2 shows schematically such a proposal. Much work has to done and the IAEA has established a working group that is systematically establishing the structure and process to incorporate the many issues that are a part of a multi-unit site safety assessment. (authors)

  17. 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.)

  18. 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.

  19. 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.

  20. 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

  1. 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

  2. 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.)

  3. 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

  4. 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

  5. Nuclear safety philosophy in the United Kingdom

    International Nuclear Information System (INIS)

    Anthony, R.D.

    1986-01-01

    Development of the United Kingdom (UK) nuclear safety philosophy is described in the context of the UK nuclear power program since 1959 and of its legislative framework. Basic to the philosophy is that the licensee is wholly responsible for nuclear safety. The licensing process and safety assessment principles used by the Nuclear Installations Inspectorate are discussed, and examples from the assessment of the proposed UK pressurized-water reactor are used to illustrate how the approach works in practice. The UK siting policy and regulatory developments since 1979 are also discussed. Recent, current, and future issues of interest to the regulatory authority are described against the development nuclear scene in the UK

  6. 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.)

  7. Changes in patient safety culture after restructuring of intensive care units: Two cross-sectional studies.

    Science.gov (United States)

    Vifladt, Anne; Simonsen, Bjoerg O; Lydersen, Stian; Farup, Per G

    2016-02-01

    Compare changes in registered nurses' perception of the patient safety culture in restructured and not restructured intensive care units during a four-year period. Two cross-sectional surveys were performed, in 2008/2009 (time 1) and 2012/2013 (time 2). During a period of 0-3 years after time 1, three of six hospitals merged their general and medical intensive care units (restructured). The other hospitals maintained their structure of the intensive care units (not restructured). Intensive care units in hospitals at one Norwegian hospital trust. The safety culture was measured with Hospital Survey on Patient Safety Culture. At times 1 and 2, 217/302 (72%) and 145/289 (50%) registered nurses participated. Restructuring was negatively associated with change in the safety culture, in particular, the dimensions of the safety culture within the unit level. The dimensions most vulnerable for restructuring were manager expectations and actions promoting safety, teamwork within hospital units and staffing. In this study, the restructuring of intensive care units was associated with a negative impact on the safety culture. When restructuring, the management should be particularly aware of changes in the safety culture dimensions manager expectations and actions promoting safety, teamwork within hospital units and staffing. Copyright © 2015 The Authors. Published by Elsevier Ltd.. All rights reserved.

  8. A web-based tool for the Comprehensive Unit-based Safety Program (CUSP).

    Science.gov (United States)

    Pronovost, Peter J; King, Jay; Holzmueller, Christine G; Sawyer, Melinda; Bivens, Shauna; Michael, Michelle; Haig, Kathy; Paine, Lori; Moore, Dana; Miller, Marlene

    2006-03-01

    An organization's ability to change is driven by its culture, which in turn has a significant impact on safety. The six-step Comprehensive Unit-Based Safety Program (CUSP) is intended to improve local culture and safety. A Web-based project management tool for CUSP was developed and then pilot tested at two hospitals. HOW ECUSP WORKS: Once a patient safety concern is identified (step 3), a unit-level interdisciplinary safety committee determines issue criticality and starts up the projects (step 4), which are managed using project management tools within eCUSP (step 5). On a project's completion, the results are disseminated through a shared story (step 6). OSF St. Joseph's Medical Center-The Medical Birthing Center (Bloomington, Illinois), identified 11 safety issues, implemented 11 projects, and created 9 shared stories--including one for its Armband Project. The Johns Hopkins Hospital (Baltimore) Medical Progressive Care (MPC4) Unit identified 5 safety issues and implemented 4 ongoing projects, including the intravenous (IV) Tubing Compliance Project. The eCUSP tool's success depends on an organizational commitment to creating a culture of safety.

  9. 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

  10. Safety of milrinone use in neonatal intensive care units.

    Science.gov (United States)

    Samiee-Zafarghandy, Samira; Raman, Sudha R; van den Anker, John N; McHutchison, Kerstin; Hornik, Christoph P; Clark, Reese H; Brian Smith, P

    2015-01-01

    Milrinone use in the neonatal intensive care unit has increased over the last 10 years despite a paucity of published safety data in infants. We sought to determine the safety of milrinone therapy among infants in the neonatal intensive care unit. We conducted a retrospective data analysis, identifying all infants who were exposed to milrinone and discharged from 322 neonatal intensive care units managed by the Pediatrix Medical Group from 1997-2010. We identified adverse events (AEs) during milrinone exposure. The unit of observation for clinical AEs was the first course of milrinone and for laboratory AEs it was an infant-day of exposure to milrinone. Overall, 1446 of 716,821 (0.2%) infants received milrinone for a total of 6894 infant-days. The proportion of infants exposed to milrinone increased from 0 in 1997 to 4/1000 infant cases in 2010. Persistent pulmonary hypertension (40%) was the most commonly reported diagnosis at the start of milrinone administration. Overall, 606/1446 (42%) of infants had at least 1 clinical AE recorded during milrinone therapy. Hypotension requiring pressors and thrombocytopenia (milrinone therapy. Among infants hospitalized in the neonatal intensive care unit, there was an increase in the use of milrinone over the past 13 years. The safety, dosing, and efficacy of milrinone in infants should be determined in prospective clinical trials. Copyright © 2014 Elsevier Ltd. All rights reserved.

  11. Review and evaluation of the Nuclear Regulatory Commission Safety Research Program for Fiscal Years 1984 and 1985

    International Nuclear Information System (INIS)

    1983-02-01

    This is the sixth report by the Advisory Committee on Reactor Safeguards (ACRS) that has been prepared in response to the Congressional requirement for an annual report on the Nuclear Regulatory Commission (NRC) Reactor Safety Research Program. Part I is a compilation of our general comments and recommendations regarding the NRC Safety Research Program, and includes budget recommendations and an identification of matters of special importance that deserve increased emphasis. It is intended to serve as an Executive Summary. Part II is divided into ten chapters, each of which represents a Decision Unit of the NRC research program. In each chapter, specific comments are included on the research involved in the Decision Unit, an assessment of priorities, and recommendations regarding new directions and levels of funding

  12. 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)

  13. Do Leadership Style, Unit Climate, and Safety Climate Contribute to Safe Medication Practices?

    Science.gov (United States)

    Farag, Amany; Tullai-McGuinness, Susan; Anthony, Mary K; Burant, Christopher

    2017-01-01

    This study aims at: examining if leadership style and unit climate predict safety climate; and testing the direct, indirect, and total effect of leadership style, unit climate, and safety climate on nurses' safe medication practices. The Institute of Medicine and nursing scholars propose that safety climate is a prerequisite to safety practices. However, there is limited empirical evidence about factors contributing to the development of safety climate and about the association with nurses' safe medication practices. This cross-sectional study used survey data from 246 RNs working in a Magnet® hospital. Leadership style and unit climate predicted 20% to 50% of variance on all safety climate dimensions. Model testing revealed the indirect impact of leadership style and unit climate on nurses' safe medication practices. Our hypothesized model explained small amount of the variance on nurses' safe medication practices. This finding suggests that nurses' safe medication practices are influenced by multiple contextual and personal factors that should be further examined.

  14. Safety Assessment for Research Reactors and Preparation of the Safety Analysis Report. Specific Safety Guide

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-11-15

    The IAEA's Statute authorizes the Agency to 'establish or adopt' standards of safety for protection of health and minimization of danger to life and property' - standards that the IAEA must use in its own operations, and which States can apply by means of their regulatory provisions for nuclear and radiation safety. The IAEA does this in consultation with the competent organs of the United Nations and with the specialized agencies concerned. A comprehensive set of high quality standards under regular review is a key element of a stable and sustainable global safety regime, as is the IAEA's assistance in their application. The IAEA commenced its safety standards programme in 1958. The emphasis placed on quality, fitness for purpose and continuous improvement has led to the widespread use of the IAEA standards throughout the world. The Safety Standards Series now includes unified Fundamental Safety Principles, which represent an international consensus on what must constitute a high level of protection and safety. With the strong support of the Commission on Safety Standards, the IAEA is working to promote the global acceptance and use of its standards. Standards are only effective if they are properly applied in practice. The IAEA's safety services encompass design, siting and engineering safety, operational safety, radiation safety, safe transport of radioactive material and safe management of radioactive waste, as well as governmental organization, regulatory matters and safety culture in organizations. These safety services assist Member States in the application of the standards and enable valuable experience and insights to be shared. Regulating safety is a national responsibility, and many States have decided to adopt the IAEA's standards for use in their national regulations. For parties to the various international safety conventions, IAEA standards provide a consistent, reliable means of ensuring the effective fulfilment of obligations under the conventions

  15. Safety Assessment for Research Reactors and Preparation of the Safety Analysis Report. Specific Safety Guide

    International Nuclear Information System (INIS)

    2011-01-01

    The IAEA's Statute authorizes the Agency to 'establish or adopt' standards of safety for protection of health and minimization of danger to life and property' - standards that the IAEA must use in its own operations, and which States can apply by means of their regulatory provisions for nuclear and radiation safety. The IAEA does this in consultation with the competent organs of the United Nations and with the specialized agencies concerned. A comprehensive set of high quality standards under regular review is a key element of a stable and sustainable global safety regime, as is the IAEA's assistance in their application. The IAEA commenced its safety standards programme in 1958. The emphasis placed on quality, fitness for purpose and continuous improvement has led to the widespread use of the IAEA standards throughout the world. The Safety Standards Series now includes unified Fundamental Safety Principles, which represent an international consensus on what must constitute a high level of protection and safety. With the strong support of the Commission on Safety Standards, the IAEA is working to promote the global acceptance and use of its standards. Standards are only effective if they are properly applied in practice. The IAEA's safety services encompass design, siting and engineering safety, operational safety, radiation safety, safe transport of radioactive material and safe management of radioactive waste, as well as governmental organization, regulatory matters and safety culture in organizations. These safety services assist Member States in the application of the standards and enable valuable experience and insights to be shared. Regulating safety is a national responsibility, and many States have decided to adopt the IAEA's standards for use in their national regulations. For parties to the various international safety conventions, IAEA standards provide a consistent, reliable means of ensuring the effective fulfilment of obligations under the conventions

  16. 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...

  17. 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

  18. 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

  19. Active and passive vehicle safety at Volkswagen accident research

    Energy Technology Data Exchange (ETDEWEB)

    Jungmichel, M.; Stanzel, M.; Zobel, R. [Volkswagen AG, Wolfsburg (Germany)

    2001-07-01

    Accident Analysis is an efficient means of improving vehicle passive safety and is used frequently and intensively. However, reliable data on accident causation is much more difficult to obtain. In most cases, one or more of the persons involved in an accident will face litigation and therefore are reluctant to provide the information that is essential to researchers. In addition, antilock brakes in almost every current vehicle have caused certain characteristic evidence, i.e. skid marks, to appear much less frequently than before. However, this evidence provides valuable information for assessing the reaction of the driver and his attempt to avoid the accident. In order to implement strategies of accident avoidance, accident causation must first be fully understood. Therefore, one of the assignments of the Volkswagen Accident Research Unit is to interpret global statistics, as well as to study single cases in order to come up with strategies for collision avoidance or mitigation. Currently, our primary concern is focused on active vehicle safety by researching vehicle behavior in the pre-crash phase. (orig.)

  20. 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

  1. 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

  2. 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

  3. 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

  4. 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

  5. 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

  6. Nuclear safety risk control in the outage of CANDU unit

    International Nuclear Information System (INIS)

    Wu Mingliang; Zheng Jianhua

    2014-01-01

    Nuclear fuel remains in the core during the outage of CANDU unit, but there are still nuclear safety risks such as reactor accidental criticality, fuel element failure due to inability to properly remove residual heat. Furthermore, these risks are aggravated by the weakening plant system configuration and multiple cross operations during the outage. This paper analyzes the phases where there are potential nuclear safety risks on the basis of the typical critical path arrangement of the outage of Qinshan NPP 3 and introduces a series of CANDU-specific risk control measures taken during the past plant outages to ensure nuclear safety during the unit outage. (authors)

  7. 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

  8. 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

  9. 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.)

  10. Nuclear safety research in HGF 2012

    International Nuclear Information System (INIS)

    Anon.

    2013-01-01

    After the events at the Japanese nuclear power plant of Fukushima Daiichi, the German Federal government decided that Germany will give up electricity generation from nuclear power within a decade. The last reactor will be disconnected from the power grid in 2022. Helping to make this opt-out safe is one of the duties of the Helmholtz Association with its Nuclear Safety Research Program within the Energy Research Area. Also the demolition of nuclear power plants and the repository problem will keep society, and thus also research, busy for a number of decades to come. Giving up electricity production from nuclear power thus must not mean giving up the required nuclear technology competences. In the fields of reactor safety, demolition, final storage, radiation protection, and crisis management, in critical support of international developments, and for competent evaluation of nuclear facilities around Germany, these competences will be in demand far beyond the German opt-out. This is the reason why the final report by the Ethics Committee on 'Safe Energy Supply' emphasizes the importance of nuclear technology research. Close cooperation on national, European and international levels is indispensable in this effort. Also nuclear safety research in the Helmholtz Association is aligned with the challenges posed by the opt-out of the use of nuclear power. It is important that the high competences in the areas of plant safety and demolition, handling of radioactive waste, and safe final storage as well as radiation protection be preserved. The Nuclear Safety Research Program within the Energy Research Area of the Helmholtz Association therefore will continue studying scientific and technical aspects of the safety of nuclear reactors and the safety of nuclear waste management. These research activities are provident research conducted for society and must be preserved for a long period of time. The work is closely harmonized with the activities of the partners in the

  11. The Safety Attitudes Questionnaire: psychometric properties, benchmarking data, and emerging research

    Directory of Open Access Journals (Sweden)

    Boyden James

    2006-04-01

    Full Text Available Abstract Background There is widespread interest in measuring healthcare provider attitudes about issues relevant to patient safety (often called safety climate or safety culture. Here we report the psychometric properties, establish benchmarking data, and discuss emerging areas of research with the University of Texas Safety Attitudes Questionnaire. Methods Six cross-sectional surveys of health care providers (n = 10,843 in 203 clinical areas (including critical care units, operating rooms, inpatient settings, and ambulatory clinics in three countries (USA, UK, New Zealand. Multilevel factor analyses yielded results at the clinical area level and the respondent nested within clinical area level. We report scale reliability, floor/ceiling effects, item factor loadings, inter-factor correlations, and percentage of respondents who agree with each item and scale. Results A six factor model of provider attitudes fit to the data at both the clinical area and respondent nested within clinical area levels. The factors were: Teamwork Climate, Safety Climate, Perceptions of Management, Job Satisfaction, Working Conditions, and Stress Recognition. Scale reliability was 0.9. Provider attitudes varied greatly both within and among organizations. Results are presented to allow benchmarking among organizations and emerging research is discussed. Conclusion The Safety Attitudes Questionnaire demonstrated good psychometric properties. Healthcare organizations can use the survey to measure caregiver attitudes about six patient safety-related domains, to compare themselves with other organizations, to prompt interventions to improve safety attitudes and to measure the effectiveness of these interventions.

  12. Organizational safety factors research lessons learned

    International Nuclear Information System (INIS)

    Ryan, T.G.

    1995-01-01

    This Paper reports lessons learned and state of knowledge gained from an organizational factors research activity involving commercial nuclear power plants in the United States, through the end of 1991, as seen by the scientists immediately involved in the research. Lessons learned information was gathered from the research teams and individuals using a question and answer format. The following five questions were submitted to each team and individual: (1) What organizational factors appear to influence safety performance in some systematic way, (2) Should organizational factors research focus at the plant level, or should it extend beyond the plant level to the parent company, rate setting commissions, regulatory agencies, (3) How important is having direct access to plants for doing organizational factors research, (4) What lessons have been learned to date as the result of doing organizational factors research in a nuclear regulatory setting, and (5) What organizational research topics and issues should be pursued in the future? Conclusions based on the responses provided for this report are that organizational factors research can be conducted in a regulatory setting and produce useful results. Technologies pioneered in other academic, commercial, and military settings can be adopted for use in a nuclear regulatory setting. The future success of such research depends upon the cooperation of regulators, contractors, and the nuclear industry

  13. 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

  14. Focusing on patient safety in the Neonatal Intensive Care Unit environment

    Directory of Open Access Journals (Sweden)

    Ilias Chatziioannidis

    2017-02-01

    Full Text Available Patient safety in the Neonatal Intensive Care Unit (NICU environment is an under-researched area, but recently seems to get high priority on the healthcare quality agenda worldwide. NICU, as a highly sensitive and technological driven environment, signals the importance for awareness in causation of mistakes and accidents. Adverse events and near misses that comprise the majority of human errors, cause morbidity often with devastating results, even death. Likewise in other organizations, errors causes are multiple and complex. Other high reliability organizations, such as air force and nuclear industry, offer examples of how standardized/homogenized work and removal of systems weaknesses can minimize errors. It is widely accepted that medical errors can be explained based on personal and/or system approach. The impact/effect of medical errors can be reduced when thorough/causative identification approach is followed by detailed analysis of consequences and prevention measures. NICU’s medical and nursing staff should be familiar with patient safety language, implement best practices, and support safety culture, maximizing efforts for reducing errors. Furthermore, top management commitment and support in developing patient safety culture is essential in order to assure the achievement of the desirable organizational safety outcomes. The aim of the paper is to review patient safety issues in the NICU environment, focusing on development and implementation of strategies, enhancing high quality standards for health care.

  15. Characteristics of unit-level patient safety culture in hospitals in Japan: a cross-sectional study.

    Science.gov (United States)

    Fujita, Shigeru; Seto, Kanako; Kitazawa, Takefumi; Matsumoto, Kunichika; Hasegawa, Tomonori

    2014-10-22

    Patient safety culture (PSC) has an important role in determining safety and quality in healthcare. Currently, little is known about the status of unit-level PSC in hospitals in Japan. To develop appropriate strategies, characteristics of unit-level PSC should be investigated. Work units may be classified according to the characteristics of PSC, and common problems and appropriate strategies may be identified for each work unit category. This study aimed to clarify the characteristics of unit-level PSC in hospitals in Japan. In 2012, a cross-sectional study was conducted at 18 hospitals in Japan. The Hospital Survey on Patient Safety Culture questionnaire, developed by the United States Agency for Healthcare Research and Quality, was distributed to all healthcare workers (n =12,076). Percent positive scores for 12 PSC sub-dimensions were calculated for each unit, and cluster analysis was used to categorise the units according to the percent positive scores. A generalised linear mixed model (GLMM) was used to analyse the results of the cluster analysis, and odds ratios (ORs) for categorisation as high-PSC units were calculated for each unit type. A total of 9,124 respondents (75.6%) completed the questionnaire, and valid data from 8,700 respondents (72.0%) were analysed. There were 440 units in the 18 hospitals. According to the percent positive scores for the 12 sub-dimensions, the 440 units were classified into 2 clusters: high-PSC units (n =184) and low-PSC units (n =256). Percent positive scores for all PSC sub-dimensions for high-PSC units were significantly higher than those for low-PSC units. The GLMM revealed that the combined unit type of 'Obstetrics and gynaecology ward, perinatal ward or neonatal intensive care unit' was significantly more likely to be categorised as high-PSC units (OR =9.7), and 'Long-term care ward' (OR =0.2), 'Rehabilitation unit' (OR =0.2) and 'Administration unit' (OR =0.3) were significantly less likely to be categorised as high

  16. 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

  17. 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

  18. 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

  19. Directions of ICF research in the United States

    International Nuclear Information System (INIS)

    Hogan, W.J.; Campbell, E.M.

    1997-01-01

    Inertial confinement fusion (ICF) research in the United States is in a dramatic upswing. Technical progress continues at a rapid pace and with the start of the construction of the National Ignition Facility (NIF) this year the total U.S. budget for ICF for fiscal year 1997 stands at $380 million. The NIF is being built as an essential component of the U.S. Stockpile Stewardship and Management Program which has been formulated to assure the continued safety, reliability, and performance of the downsized nuclear weapons stockpile in the absence of nuclear tests. This paper will discuss some of the directions that the ICF research is now taking. (AIP) copyright 1997 American Institute of Physics

  20. 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)

  1. Safety Assessment for transient event occurred during the ASTS test of Hanbit Unit 2

    International Nuclear Information System (INIS)

    Yang, Changkeun; Kim, Yohan; Ha, Sangjun

    2014-01-01

    Safety Injection has been actuated during the ASTS (Automatic Seismic Trip System) test of Hanbit Unit 2 on Feb. 28, 2014. It could be bad effect on system integrity. KHNP has been performed safety assessment of system for effect of Safety Injection (SI) actuation occurred during the ASTS test of hanbit Unit 2. Stable state of nuclear power plant system has been confirmed according to Safety Injection and reactor trip event occurred during the ASTS test of hanbit Unit 2. In the result of system safety assessment, major variables of nuclear power plant are located in optimal range and not exceed safety limit. It remains nuclear fuel and the integrity of the power plant is in a safe condition were conformed. After ASTS action, thermal elimination has been processed throughout the turbine until turbine signal occurrence because ASTS is connected to M-G set in the present hanbit Unit 2. Therefore, Safety Injection signal has been actuated by rapid reduction of Steam Generator pressure. In this paper, it is concluded that consideration of equipment and setpoint is needed for that Safety Injection has been not occurred under the unnecessary situation. Stable state of nuclear power plant system has been confirmed for Safety Injection and reactor trip event occurred during the ASTS test of hanbit Unit 2. In the result of system safety assessment, major variables of nuclear power plant are located in optimal range and not exceed safety limit. It remains nuclear fuel and the integrity of the plant is in a safe condition were conformed. It is concluded that consideration of equipment and setpoint is needed for that Safety Injection has been not occurred under the unnecessary situation

  2. 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.)

  3. 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)

  4. Improving nuclear safety of VVER-440 units

    International Nuclear Information System (INIS)

    Nochev, T.; Sabinov, S.

    2001-01-01

    In this paper authors deals with improvement of nuclear safety of WWER-440 units in Kozloduy NPP. Main directions for improving nuclear safety of WWER-440 units were: - to expand number of the design accident; - to increase reliability of equipment important for the safety; - to decrease the probability of initiating events; - improvements the integrity of the primary circuit (application LBB concept, qualification of the pressure safety valves to avoid pressurized thermal shock); - improvement of the fire protection; - improvement of the operation including upgrading and improvement of operational documents, implementation of new system for training the operators and etc.; - reassessment of the seismic response of the plant. Main actions were made at NPP Kozloduy to increase nuclear safety of VVER-440 units. 1. Modernization of Emergency High Pressure Safety Injection System. The modernization includes dividing of independent channels with reservation of active elements. Pumps were exchanged with more effective and reliable ones. HPSIS was increased reliability in general through decrease number of active elements and exchanged with passive. 2. For the purpose of avoiding fast cooling at the primary circuit and obtaining thermal shock of reactor vessel, Main Safety Insulation Valves are installed at NPP Kozloduy. 3. Modernization of Emergency power supplies AC. Oil breakers VMP-10 are exchanged with gas FS-4. 4. Generator breakers are installed to decrease probability of loss power supply and blackout. They provide reliable power supply to the system important for the safety in case of failure on generator. 5. I and C system has been qualified and optimized. 6. Reassessments of Limiting Conditions of Operation and new scram signals have been introduced. 7. An operators-oriented Informational System has been developed. It includes ensuring and updating of equipment data, new informational support of operator and etc. 8. A new auxiliary independent system for

  5. 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

  6. 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.)

  7. 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.)

  8. A Survey of Occupational Safety & Health Libraries in the United States.

    Science.gov (United States)

    Jensen, Karen S.

    There is very little published information available about occupational safety and health libraries. This study identified, described, and compared the occupational safety and health libraries in the United States. The questionnaire first filtered out those libraries that did not fit the definition of an occupational safety and health library;…

  9. 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

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

    International Nuclear Information System (INIS)

    1986-04-01

    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. 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 sponsored by BMFT, CEA, EPRI, JSTA and USNRC

    International Nuclear Information System (INIS)

    1986-02-01

    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. 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

  12. The relationship between patient safety climate and occupational safety climate in healthcare - A multi-level investigation.

    Science.gov (United States)

    Pousette, Anders; Larsman, Pernilla; Eklöf, Mats; Törner, Marianne

    2017-06-01

    Patient safety climate/culture is attracting increasing research interest, but there is little research on its relation with organizational climates regarding other target domains. The aim of this study was to investigate the relationship between patient safety climate and occupational safety climate in healthcare. The climates were assessed using two questionnaires: Hospital Survey on Patient Safety Culture and Nordic Occupational Safety Climate Questionnaire. The final sample consisted of 1154 nurses, 886 assistant nurses, and 324 physicians, organized in 150 work units, within hospitals (117units), primary healthcare (5units) and elderly care (28units) in western Sweden, which represented 56% of the original sample contacted. Within each type of safety climate, two global dimensions were confirmed in a higher order factor analysis; one with an external focus relative the own unit, and one with an internal focus. Two methods were used to estimate the covariation between the global climate dimensions, in order to minimize the influence of bias from common method variance. First multilevel analysis was used for partitioning variances and covariances in a within unit part (individual level) and a between unit part (unit level). Second, a split sample technique was used to calculate unit level correlations based on aggregated observations from different respondents. Both methods showed associations similar in strength between the patient safety climate and the occupational safety climate domains. The results indicated that patient safety climate and occupational safety climate are strongly positively related at the unit level, and that the same organizational processes may be important for the development of both types of organizational climate. Safety improvement interventions should not be separated in different organizational processes, but be planned so that both patient safety and staff safety are considered concomitantly. Copyright © 2017 National Safety

  13. 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)

  14. [Improving patient safety: Usefulness of safety checklists in a neonatal unit].

    Science.gov (United States)

    Arriaga Redondo, María; Sanz López, Ester; Rodríguez Sánchez de la Blanca, Ana; Marsinyach Ros, Itziar; Collados Gómez, Laura; Díaz Redondo, Alicia; Sánchez Luna, Manuel

    2017-10-01

    Due to the complexity and characteristics of their patients, neonatal units are risk areas for the development of adverse events (AE). For this reason, there is a need to introduce and implement some tools and strategies that will help to improve the safety of the neonatal patient. Safety check-lists have shown to be a useful tool in other health areas but they are not sufficiently developed in Neonatal Units. A quasi-experimental prospective study was conducted on the design and implementation of the use of a checklist and evaluation of its usefulness for detecting incidents. The satisfaction of the health professionals on using the checklist tool was also assessed. The compliance rate in the neonatal intensive care unit (NICU) was 56.5%, with 4.03 incidents per patient being detected. One incident was detected for every 5.3 checklists used. The most frequent detected incidents were those related to medication, followed by inadequate alarm thresholds, adjustments of the monitors, and medication pumps. The large majority (75%) of the NICU health professionals considered the checklist useful or very useful, and 68.75% considered that its use had managed to avoid an AE. The overall satisfaction was 83.33% for the professionals with less than 5 years working experience, and 44.4% of the professionals with more than 5 years of experience were pleased or very pleased. The checklists have shown to be a useful tool for the detection of incidents, especially in NICU, with a positive assessment from the health professionals of the unit. Copyright © 2016 Asociación Española de Pediatría. Publicado por Elsevier España, S.L.U. All rights reserved.

  15. 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

  16. 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

  17. 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

  18. International review of Kursk unit 1 in-depth safety analysis report

    International Nuclear Information System (INIS)

    Chouha, M.; Bolshov, L.; Butcher, P.; Janke, R.; Parsons, T.; Weber, J.P.

    2004-01-01

    The paper presents the objectives, organisation, main findings and conclusions of the international review of the Kursk unit 1 safety analysis report (K1IRSR). The K1IRSR was administered by RISKAUDIT IRSN/GRS international and carried out by international experts from 7 western countries plus the Russian Federation, under the supervision of the safety review group (SRG) of the European bank for reconstruction and development (EBRD). The project was financed by the nuclear safety account (NSA) administered by the EBRD. The Russian experts worked under a contract with IBRAE financed by Rosenergoatom. The main conclusions were that the SAR followed a correct approach, broadly in line with Russian and international guidance documents, but needed improvement in structure and content. It established that the safety level of the unit has been increased significantly by the modernisation programme. The important deviations of the unit from current Russian regulations and the IAEA safety issues for RBMK are either fully resolved or are being addressed to the extent possible by compensatory measures to further reduce the risk. The K1IRSR experts have made a number of recommendations for improvement of the K1SAR. The authors agreed to take the recommendations into account in future revision of the K1SAR. (orig.)

  19. Kozloduy nuclear power plant. Units 1-4. Status of safety improvements. Rev. 2

    International Nuclear Information System (INIS)

    1999-01-01

    This paper presents the results of the safety improvements activities carried out by the Kozloduy Nuclear Power Plant (KNPP) within the period 1990-1998. The steam supply system of this units is based of the reactor WWER-440/ B-230, which is a PWR of russian design developed according to the safety standards in force in USSR in late sixties. Up to now 10 reactor units of this type are in operation in four NPPs. Despite of efforts of the different plants to implement safety improvements measures during first 10-15 years of operation of this type of reactor its major safety problems were not eliminated and were a subject of international concern. The systematic evaluation of the deficiencies of the original design of this type of reactors have been initiated by IAEA in the beginning of 1990 and brought to developing a comprehensive list of safety problems which required urgent implementation of safety measures in all plants. To solve this problems in 1991 KNPP initiated implementation of so called 'short term' safety improvement program, developed with the help of WANO under agreement with Bulgarian Nuclear Safety Authority (BNSA) and consortium RISKAUDIT. The program was based on a stage approach and was foreseen to be implemented by tree stages in very tight time schedule in order to achieve significant and rapid improvements of the level of safety in operation of the units. The Short term program was implemented between from 1991 to 1997 owing to strong safety commitment of NEC and KNPP staff as well as broad international cooperation and financial support. Important part of resources were supplied under PHARE program of CEC, EBRD grant agreement and EDF support. In parallel a special assessment process started in 1995 in order to evaluate the level of safety, achieved by Short Term Program, according to current safety standards and to define the measures, which should be implemented by the Utility to complete the process of improving the safety in future

  20. 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

  1. 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...

  2. 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...

  3. A Systematic Review of Community Health Workers' Role in Occupational Safety and Health Research.

    Science.gov (United States)

    Swanberg, Jennifer E; Nichols, Helen M; Clouser, Jessica M; Check, Pietra; Edwards, Lori; Bush, Ashley M; Padilla, Yancy; Betz, Gail

    2018-03-03

    We systematically reviewed the literature to describe how community health workers (CHWs) are involved in occupational health and safety research and to identify areas for future research and research practice strategies. We searched five electronic databases from July 2015 through July 2016. Inclusion criteria were as follows: (1) study took place in the United States, (2) published as a full peer-review manuscript in English, (3) conducted occupational health and safety research, and (4) CHWs were involved in the research. The majority of 17 included studies took place in the agriculture industry (76%). CHWs were often involved in study implementation/design and research participant contact. Rationale for CHW involvement in research was due to local connections/acceptance, existing knowledge/skills, communication ability, and access to participants. Barriers to CHW involvement in research included competing demands on CHWs, recruitment and training difficulties, problems about research rigor and issues with proper data collection. Involving CHWs in occupational health and safety research has potential for improving inclusion of diverse, vulnerable and geographically isolated populations. Further research is needed to assess the challenges and opportunities of involving CHWs in this research and to develop evidence-based training strategies to teach CHWs to be lay-health researchers.

  4. 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.)

  5. 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.)

  6. 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.

  7. Team knowledge assessment of nursing on international targets patient safety in an intensive care unit

    Directory of Open Access Journals (Sweden)

    Maria Nathália da Silva Souza

    2017-08-01

    Full Text Available Background e Objectives: The quality of hospital care provided to the patient and the safety of their stay at the site triggered discussions around the world after the analysis of epidemiological studies conducted in the USA that concluded the high rate of adverse events in the hospital setting Caused by professional error, with that the theme gained strength and motivated discussions about the care models applied to the patients. Therefore the research was aimed at evaluating the knowledge of the Nursing Team of the Intensive Care Unit sector of a public hospital in Recife-PE on the International Patient Safety Goals. Methods: A cross-sectional study with descriptive quantitative approach was carried out from June to August 2016. Data collection was performed through a semi-structured questionnaire that addressed the social and professional aspects of the respondents. The studied variables: gender, age, professional category and training time. The data were analyzed in epiinfo software version 3.2.2. Results: The sample consisted of 50 professionals, 18% of whom were Nurses and 82% were Nursing technicians. Most respondents scored more than 50% of questions about international patient safety goals and had more than one employment relationship. Conclusion: It was verified that the lack of training, work overload and more of an employment relationship can contribute to a precarious professional assistance. KEYWORDS: Patient Safety. Nursing. Safety Management. Intensive Care Units

  8. 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)

  9. 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)

  10. 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)

  11. 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

  12. Technology, safety, and costs of decommissioning reference nuclear research and test reactors. Appendices

    International Nuclear Information System (INIS)

    Konzek, G.J.; Ludwick, J.D.; Kennedy, W.E. Jr.; Smith, R.I.

    1982-03-01

    Safety and Cost Information is developed for the conceptual decommissioning of two representative licensed nuclear research and test reactors. Three decommissioning alternatives are studied to obtain comparisons between costs (in 1981 dollars), occupational radiation doses, potential radiation dose to the public, and other safety impacts. The alternatives considered are: DECON (immediate decontamination), SAFSTOR (safe storage followed by deferred decontamination), and EMTOMB (entombment). The study results are presented in two volumes. Volume 2 (Appendices) contains the detailed data that support the results given in Volume 1, including unit-component data

  13. Technology, safety, and costs of decommissioning reference nuclear research and test reactors. Appendices

    Energy Technology Data Exchange (ETDEWEB)

    Konzek, G.J.; Ludwick, J.D.; Kennedy, W.E. Jr.; Smith, R.I.

    1982-03-01

    Safety and Cost Information is developed for the conceptual decommissioning of two representative licensed nuclear research and test reactors. Three decommissioning alternatives are studied to obtain comparisons between costs (in 1981 dollars), occupational radiation doses, potential radiation dose to the public, and other safety impacts. The alternatives considered are: DECON (immediate decontamination), SAFSTOR (safe storage followed by deferred decontamination), and EMTOMB (entombment). The study results are presented in two volumes. Volume 2 (Appendices) contains the detailed data that support the results given in Volume 1, including unit-component data.

  14. Intensive care unit nurses' perceptions of safety after a highly specific safety intervention.

    Science.gov (United States)

    Elder, N C; Brungs, S M; Nagy, M; Kudel, I; Render, M L

    2008-02-01

    It is unknown if successful changes in specific safety practices in the intensive care unit (ICU) generalize to broader concepts of patient safety by staff nurses. To explore perceptions of patient safety among nursing staff in ICUs following participation in a safety project that decreased hospital acquired infections. After implementation of practices that reduced catheter-related bloodstream infections in ICUs at four community hospitals, ICU nurses participated in focus groups to discuss patient safety. Audiotapes from the focus groups were transcribed, and two independent reviewers categorised the data which were triangulated with responses from selected questions of safety climate surveys and with the safety checklists used by management leadership on walk rounds. Thirty-three nurses attended eight focus groups; 92 nurses and managers completed safety climate surveys, and three separate leadership checklists were reviewed. In focus groups, nurses predominantly related patient safety to dangers in the physical environment (eg, bed rails, alarms, restraints, equipment, etc.) and to medication administration. These areas also represented 47% of checklist items from leadership walk rounds. Nurses most frequently mentioned self-initiated "double checking" as their main safety task. Focus-group participants and survey responses both noted inconsistency between management's verbal and written commitment compared with their day-to-day support of patient safety issues. ICU nurses who participated in a project to decrease hospital acquired infections did not generalize their experience to other aspects of patient safety or relate it to management's interest in patient safety. These findings are consistent with many adult learning theories, where self-initiated tasks, combined with immediate, but temporary problem-solving, are stronger learning forces than management-led activities with delayed feedback.

  15. 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.)

  16. 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.

  17. 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

  18. 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

  19. 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.

  20. 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)

  1. 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

  2. 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)

  3. 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

  4. 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

  5. Safety assessment of Olkiluoto NPP units 1 and 2. Decision of the Radiation and Nuclear Safety Authority regarding the periodic safety review of the Olkiluoto NPP

    International Nuclear Information System (INIS)

    2010-02-01

    In this safety assessment the Radiation and Nuclear Safety Authority (STUK) has evaluated the safety of the Olkiluoto Nuclear Power Plant units 1 and 2 in connection with the periodic safety review. This safety assessment provides a summary of the reviews, inspections and continuous oversight carried out by STUK. The issues addressed in the assessment and the related evaluation criteria are set forth in the nuclear energy and radiation safety legislation and the regulations issued thereunder. The provisions of the Nuclear Energy Act concerning the safe use of nuclear energy, security and emergency preparedness arrangements, and waste management are specified in more detail in the Government Decrees and Regulatory Guides issued by STUK. Based on the assessment, STUK consideres that the Olkiluoto Nuclear Power Plant units 1 and 2 meet the set safety requirements for operational nuclear power plants, the emergency preparedness arrangements are sufficient and the necessary control to prevent the proliferation of nuclear weapons has been appropriately arranged. The physical protection of the Olkiluoto nuclear power plant is not yet completely in compliance with the requirements of Government Decree 734/2008, which came into force in December 2008. Further requirements concerning this issue based also on the principle of continuous improvement were included in the decision relating to the periodic safety review. The safety of the Olkiluoto nuclear power plant was assessed in compliance with the Government Decree on the Safety of Nuclear Power Plants (733/2008), which came into force in 2008. The decree notes that existing nuclear power plants need not meet all the requirements set out for new plants. Most of the design bases pertaining to the Olkiluoto 1 and 2 nuclear power plant units were set in the 1970s. Substantial modernisations have been carried out at the Olkiluoto 1 and 2 nuclear power plant units since their commissioning to improve safety. This is in line with

  6. 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

  7. Safety analysis report for decommissioning of KNPP units 1 and 2

    International Nuclear Information System (INIS)

    Ivanova, A.; Ovcharova, I.

    2008-01-01

    At present units 1 and 2 possess a license for operation in mode „E‟ – storage of the spent fuel in the spent fuel pools. According to the order of BNSA, from the beginning of December 2006 the licenses for operation of KNPP units 1 and 2 have been modified; this does not change the current status – operation of the units in mode „E‟ , but allows for dismantling of the systems and equipment, which are not important for safety and do not contain radioactive substances above the free release levels. The next step is obtaining a licence for Stage 1 decommissioning activities – Safe enclosure (SE) and dismantling in Turbine hall. The development of Decommissioning Safety Analysis Report (DSAR) is one of the documents needed for this license. The specific features of the units and decommitioning options are described

  8. 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)

  9. 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)

  10. 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.)

  11. 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.)

  12. 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)

  13. Nuclear safety improvement activities related to WWER-440 units in Bulgaria

    International Nuclear Information System (INIS)

    Gantchev, T.

    1998-01-01

    The systematic evaluation of the deficiencies of the original design of the WWER reactors brought to the development of a Short Term Programme for Safety Upgrading and Modernisation of Kozloduy WWER-440 units. The implementation of this Programme was completed in 1997. The strive for continuos improvement of Kozloduy Nuclear Power Plant (NPP) safety level, the new requirements of the Bulgarian Nuclear Safety Authority and the public concern initiated the development of new Complex Programme for Safety Improvement (PRG'97), now in a process of implementation. (author)

  14. 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

  15. 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)

  16. 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...

  17. Seismic safety margins research program. Project I SONGS 1 AFWS Project

    International Nuclear Information System (INIS)

    Chuang, T.Y.; Smith, P.D.; Dong, R.G.; Bernreuter, D.L.; Bohn, M.P.; Cummings, G.E.; Wells, J.E.

    1981-01-01

    The seismic qualification requirements of auxiliary feedwater systems (AFWS) of Pressurized Water Reactors (PWR) were developed over a number of years. These are formalized in the publication General Design Criteria (Appendix A to 10CFR50). The full recognition of the system as an engineered safety feature did not occur until publication of the Standard Review Plan (1975). Efforts to determine how to backfit seismic requirements to earlier plants has been undertaken primarily in the Systematic Evaluation Program (SEP) for a limited number of operating reactors. Nuclear Reactor Research (RES) and NRR have requested LLNL to perform a probabilistic study on the AFWS of San Onofre Nuclear Generating Station (SONGS) Unit 1 utilizing the tools developed by the Seismic Safety Margins Research Program (SSMRP). The main objectives of this project are to: identify the weak links of AFWS; compare the failure probabilities of SONGS 1 and Zion 1 AFWS: and compare the seismic responses due to different input spectra and design values

  18. 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

  19. 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)

  20. Industrial safety management with emphasis on construction safety

    International Nuclear Information System (INIS)

    Bhattacharya, R.

    2016-01-01

    Safety professionals, line managers, team leaders and concerned workers today eagerly discuss to find out the best safety approach for their workplace. Some research suggested that behaviour based and comprehensive ergonomics approaches lead in average reduction of injuries. This article discusses 'the science and engineering' behind improvement in industrial safety aspects particularly at construction sites through various safety approaches. A high degree of commitment to safety by the project management and rigorous and proactive measures are essential to prevent accidents at construction sites particularly in DAE units because of its sensitivity. Persistent efforts by the project management are needed for sustainable and committed safety at work place. The number of fatalities occurring from construction work in DAE units is sometimes disturbing and fall of person from height and through openings are the major causes for serious accidents

  1. Differences in Perceptions of Patient Safety Culture between Charge and Noncharge Nurses: Implications for Effectiveness Outcomes Research

    Directory of Open Access Journals (Sweden)

    Deleise Wilson

    2012-01-01

    Full Text Available The implementation of evidence-based practice guidelines can be influenced by nurses’ perceptions of the organizational safety culture. Shift-by-shift management of each nursing unit is designated to a subset of staff nurses (charge nurses, whom are often recruited as champions for change. The findings indicate that compared to charge nurses, noncharge nurses were more positive about overall perceptions of safety (=.05 and teamwork (<.05. Among charge nurses, significant differences were observed based on the number of years’ experience in charge: perception of teamwork within units [(3,365=3.52, <.01]; overall perceptions of safety, [(3,365=4.20, <.05]; safety grade for work area [(3,360=2.61, <.05]; number of events reported within the last month [(3,362=3.49, <.05]. These findings provide important insights to organizational contextual factors that may impact effectiveness outcomes research in the future.

  2. SAFIR. The Finnish research programme on nuclear power plant safety 2003-2006. Executive summary

    International Nuclear Information System (INIS)

    Puska, E.

    2006-12-01

    Major part of Finnish public research on nuclear power plant safety during the years 2003-2006 has been carried out in the SAFIR programme. The programme has been administrated by the steering group that was nominated by the Ministry of Trade and Industry (KTM). The steering group of SAFIR has consisted of representatives from Radiation and Nuclear Safety Authority (STUK), Ministry of Trade and Industry (KTM), Technical Research Centre of Finland (VTT), Teollisuuden Voima Oy (TVO), Fortum Power and Heat Oy, Fortum Nuclear Services Oy (Fortum), Finnish Funding Agency for Technology and Innovation (Tekes), Helsinki University of Technology (TKK) and Lappeenranta University of Technology (LTY). The key research areas of SAFIR have been (1) reactor fuel and core, (2) reactor circuit and structural safety, (3) containment and process safety functions, that was divided in 2005 into (3a) thermal hydraulics and (3b) severe accidents, (4) automation, control room and IT, (5) organisations and safety management and (6) risk-informed safety management. The research programme has included annually from 20 up to 24 research projects, whose volume has varied from a few person months to several person years. The total volume of the programme during the four year period 2003-2006 has been 19.7 million euros and 148 person years. The research in the programme has been carried out primarily by Technical Research Centre of Finland (VTT). Other research units responsible for the projects include Lappeenranta University of Technology, Fortum Nuclear Services Oy, Helsinki University of Technology and RAMSE Consulting Oy. In addition, there have been a few minor subcontractors in some projects. The programme management structure has consisted of the steering group, a reference group in each of the seven research areas and a number of ad hoc groups in the various research areas. This report gives a short summary of the results of the SAFIR programme for the period January 2003 - November

  3. 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.

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

    International Nuclear Information System (INIS)

    1981-09-01

    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 Saftety Research Program of the BMFT, reporting organization. The list of reports appears quarterly. (orig./HP) [de

  5. 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)

  6. Review of nuclear regulatory activities associated with safety culture and the management of safety in the United Kingdom

    International Nuclear Information System (INIS)

    Woodhouse, P.A.

    1995-01-01

    This paper describes some of the key regulatory activities which have taken place in the United Kingdom in recent years in the areas of safety culture and management of safety. It explains how the UK's nuclear licensing regime, regulated and enforced by the Nuclear Installations Inspectorate, (NII), provides the framework for a viable safety management system and identifies a management of safety model which a NII Task Force has developed. It finally identifies further work which is being undertaken by the NII. (author). 4 refs, 2 figs

  7. 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

  8. Safety climate in Swiss hospital units: Swiss version of the Safety Climate Survey

    Science.gov (United States)

    Gehring, Katrin; Mascherek, Anna C.; Bezzola, Paula

    2015-01-01

    Abstract Rationale, aims and objectives Safety climate measurements are a broadly used element of improvement initiatives. In order to provide a sound and easy‐to‐administer instrument for the use in Swiss hospitals, we translated the Safety Climate Survey into German and French. Methods After translating the Safety Climate Survey into French and German, a cross‐sectional survey study was conducted with health care professionals (HCPs) in operating room (OR) teams and on OR‐related wards in 10 Swiss hospitals. Validity of the instrument was examined by means of Cronbach's alpha and missing rates of the single items. Item‐descriptive statistics group differences and percentage of ‘problematic responses’ (PPR) were calculated. Results 3153 HCPs completed the survey (response rate: 63.4%). 1308 individuals were excluded from the analyses because of a profession other than doctor or nurse or invalid answers (n = 1845; nurses = 1321, doctors = 523). Internal consistency of the translated Safety Climate Survey was good (Cronbach's alpha G erman = 0.86; Cronbach's alpha F rench = 0.84). Missing rates at item level were rather low (0.23–4.3%). We found significant group differences in safety climate values regarding profession, managerial function, work area and time spent in direct patient care. At item level, 14 out of 21 items showed a PPR higher than 10%. Conclusions Results indicate that the French and German translations of the Safety Climate Survey might be a useful measurement instrument for safety climate in Swiss hospital units. Analyses at item level allow for differentiating facets of safety climate into more positive and critical safety climate aspects. PMID:25656302

  9. 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

  10. 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

  11. 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

  12. 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.

  13. Twenty-second water reactor safety information meeting. Volume 2: Severe accident research, thermal hydraulic research for advanced passive LWRs, high-burnup fuel behavior

    Energy Technology Data Exchange (ETDEWEB)

    Monteleone, S. [comp.

    1995-04-01

    This three-volume report contains papers presented at the Twenty-Second Water Reactor Safety Information Meeting held at the Bethesda Marriott Hotel, Bethesda, Maryland, during the week of October 24-26, 1994. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included papers presented by researchers from Finland, France, Italy, Japan, Russia, and United Kingdom. The titles of the papers and the names of the authors have been updated and may differ from those that appeared in the final program of the meeting.

  14. Twenty-second water reactor safety information meeting. Volume 2: Severe accident research, thermal hydraulic research for advanced passive LWRs, high-burnup fuel behavior

    International Nuclear Information System (INIS)

    Monteleone, S.

    1995-04-01

    This three-volume report contains papers presented at the Twenty-Second Water Reactor Safety Information Meeting held at the Bethesda Marriott Hotel, Bethesda, Maryland, during the week of October 24-26, 1994. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included papers presented by researchers from Finland, France, Italy, Japan, Russia, and United Kingdom. The titles of the papers and the names of the authors have been updated and may differ from those that appeared in the final program of the meeting

  15. 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

  16. 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

  17. 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)

  18. Report by the AERES on the unit: Research Unit on Reactor Safety under the supervision of the establishments and bodies: Radioprotection and Nuclear Safety Institute

    International Nuclear Information System (INIS)

    2010-10-01

    This report is a kind of audit report on a research laboratory whose activity is organized according to the following themes: behaviour of nuclear fuel under accidental conditions, core fusion accidents, fire in confined environment, and civil engineering and structure behaviour. The authors discuss an assessment of the unit activities in terms of strengths and opportunities, aspects to be improved and recommendations, productions and publications. A more detailed assessment is presented in terms of scientific quality, influence and attractiveness (awards, recruitment capacity, capacity to obtain financing and to tender, participation to international programs), strategy and governance, and project. Each research theme is analyzed in the same way

  19. Relationship between the Quality of Educational Facilities, School Climate, and School Safety of High School Tenth Graders in the United States

    Science.gov (United States)

    Bell, Darnell Brushawn

    2011-01-01

    The purpose of the study was to understand the relationships among facility conditions, school climate, and school safety of high school tenth graders in the United States. Previous research on the quality of educational facilities influence on student achievement has varied. Recent research has suggested that the quality of educational facilities…

  20. 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)

  1. 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

  2. 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

  3. 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

  4. 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)

  5. 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

  6. 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...

  7. 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)

  8. 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

  9. 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

  10. Food Safety at Farmers' Markets: A Knowledge Synthesis of Published Research.

    Science.gov (United States)

    Young, Ian; Thaivalappil, Abhinand; Reimer, Danielle; Greig, Judy

    2017-12-01

    Farmers' markets are increasingly popular venues in North America for the sale of fresh produce and other foods. However, the nature of their operation can present possible food safety issues, challenges, and risks to consumers. A knowledge synthesis was conducted to identify, characterize, and summarize published research on the microbial food safety issues and implications associated with farmers' markets. A scoping review was conducted using the following steps: comprehensive search strategy, relevance screening of abstracts, and characterization of relevant articles. Two subsets of data were prioritized for more detailed systematic review (data extraction and risk-of-bias assessment) and meta-analysis: (i) studies comparing the microbial safety of foods from farmers' markets versus other sources and (ii) studies evaluating the use of food safety practices at farmers' markets. Overall, 83 relevant studies were identified. The majority of studies were published as journal articles (64%), used a cross-sectional design (81%), and were conducted in the United States (78%). Most studies (39%; n = 32) investigated stakeholder, mostly consumer (n = 22), attitudes toward food safety at farmers' markets. Limited but heterogeneous evidence indicated a higher prevalence of Campylobacter and Salmonella in chicken meat from farmers' markets versus other retail sources, but there was no difference in the microbial contamination of fresh produce. Studies evaluating the use of food safety practices at farmers' markets identified some gaps; for example, the average prevalence of vendor hand washing was 4% (95% confidence interval: 0 to 11%; I 2 = 27%; n = 5 studies). Twelve foodborne outbreaks and case reports were identified, resulting in a total of 411 illnesses, 38 hospitalizations, and two deaths from 1994 to 2016. Only five intervention studies were identified. Key knowledge gaps and areas warranting future research, training, and education are highlighted and discussed.

  11. 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

  12. 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

  13. 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

  14. Research on the Effects of Hydropneumatic Parameters on Tracked Vehicle Ride Safety Based on Cosimulation

    Directory of Open Access Journals (Sweden)

    Shousong Han

    2017-01-01

    Full Text Available Ride safety of a tracked vehicle is the key focus of this research. The factors that affect the ride safety of a vehicle are analyzed and evaluation parameters with their criteria are proposed. A multibody cosimulation approach is used to investigate the effects of hydropneumatic parameters on the ride safety and aid with design optimization and tuning of the suspension system. Based on the cosimulation environment, the vehicle multibody dynamics (MBD model and the road model are developed using RecurDyn, which is linked to the hydropneumatic suspension model developed in Lab AMESim. Test verification of a single suspension unit is accomplished and the suspension parameters are implemented within the hydropneumatic model. Virtual tests on a G class road at different speeds are conducted. Effects of the accumulator charge pressure, damping diameter, and the track tensioning pressure on the ride safety are analyzed and quantified. This research shows that low accumulator charge pressure, improper damping diameter, and insufficient track tensioning pressure will deteriorate the ride safety. The results provide useful references for the optimal design and control of the parameters of a hydropneumatic suspension.

  15. Patient Safety Culture in Intensive Care Units from the Perspective of Nurses: A Cross-Sectional Study.

    Science.gov (United States)

    Farzi, Sedigheh; Moladoost, Azam; Bahrami, Masoud; Farzi, Saba; Etminani, Reza

    2017-01-01

    One of the goals of nursing is providing safe care, prevention of injury, and health promotion of patients. Patient safety in intensive care units is threatened for various reasons. This study aimed to survey patient safety culture from the perspective of nurses in intensive care units. This cross-sectional study was conducted in 2016. Sampling was done using the convenience method. The sample consisted of 367 nurses working in intensive care units of teaching hospitals affiliated to Isfahan University of Medical Sciences. Data collection was performed using a two-part questionnaire that included demographic and hospital survey on Patient Safety Culture (HSOPSC) questionnaire. Data analysis was done using descriptive statistics (mean and standard deviation). Among the 12 dimensions of safety culture, the nurses assigned the highest score to "team work within units" (97.3%) and "Organizational learning-continuous improvement" (84%). They assigned the least score to "handoffs and transitions"(21.1%), "non-punitive response to errors" (24.7%), "Staffing" (35.6%), "Communication openness" (47.5%), and "Teamwork across units" (49.4%). The patient safety culture dimensions have low levels that require adequate attention and essential measures of health care centers including facilitating teamwork, providing adequate staff, and developing a checklist of handoffs and transitions. Furthermore, to increase reporting error and to promote a patient safety culture in intensive care units, some strategies should be adopted including a system-based approach to deal with the error.

  16. 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.

  17. The regulation and licensing of research reactors and associated facilities in the United Kingdom

    International Nuclear Information System (INIS)

    Weightman, M.W.; Willby, C.R.

    1990-01-01

    In the United Kingdom, the Nuclear Installations Inspectorate (NII) licenses nuclear facilities, including research reactors, on behalf of the Health and Safety Executive (HSE). The legislation, the regulatory organizations and the methods of operation that have been developed over the last 30 years result in a largely non-prescriptive form of control that is well suited to research reactors. The most important part of the regulatory system is the license and the attachment of conditions which it permits. These conditions require the licensee to prepare arrangements to control the safety of the facility. In doing so the licensee is encouraged to develop a 'safety culture' within its organization. This is particularly important for research reactors which may have limited staff resources and where the ability, and at times the need, to have access to the core is much greater than for nuclear power plants. Present day issues such as the ageing of nuclear facilities, public access to the rationale behind regulatory decisions, and the emergence of more stringent safety requirements, which include a need for quantified safety criteria, have been addressed by the NII. This paper explores the relevance of such issues to the regulation of research reactors. In particular, it discusses some of the factors associated with research reactors that should be considered in developing criteria for the tolerability of risk from these nuclear facilities. From a consideration of these factors, it is the authors' view that the range of tolerable risk to the public from the operation of new research reactors may be expected to be more stringent than similar criteria for new nuclear power plants, whereas the criteria for tolerable risk for research reactor workers are expected to be about the same as those for power reactor workers

  18. 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.

  19. Safety and security considerations for the transport of spent teletherapy units

    International Nuclear Information System (INIS)

    Mallaupoma, Mario; Paez, Jose; Huatay, Luis; Cruz, Walter

    2008-01-01

    Among the applications of nuclear technology, a practice widely used and generates many benefits to society are teletherapy applications. Many of the teletherapy units used contain a source of cobalt-60 and after their useful life they have to be dismantled and transported to a safe place. In this case were transported two units with an activity of more than 75 TBq . This paper presents safety and security considerations for the transport of the teletherapy units according to the recommendations of actual state of art. It is described all facets of safe transport by means of a set of technical and administrative safety requirements and controls, including the actions required by the consignor and carrier. The main emphasis was put on the stages of transport operations that give rise to exposure to radiation like packing, preparation, loading, handling, storage in transit and movement of packages of radioactive material. On the other side some security actions were considered in order to prevent theft, sabotage or other malicious acts during the transport of the packages. As a conclusion it must be mentioned that both safety and security considerations are very important aspects that must be taking in account for the transport of high activity radioactive material. (author)

  20. 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)

  1. 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

  2. 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)

  3. 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).

  4. 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)

  5. 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)

  6. 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)

  7. 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.)

  8. Organizational and safety culture in Canadian intensive care units: relationship to size of intensive care unit and physician management model.

    Science.gov (United States)

    Dodek, Peter M; Wong, Hubert; Jaswal, Danny; Heyland, Daren K; Cook, Deborah J; Rocker, Graeme M; Kutsogiannis, Demetrios J; Dale, Craig; Fowler, Robert; Ayas, Najib T

    2012-02-01

    The objectives of this study are to describe organizational and safety culture in Canadian intensive care units (ICUs), to correlate culture with the number of beds and physician management model in each ICU, and to correlate organizational culture and safety culture. In this cross-sectional study, surveys of organizational and safety culture were administered to 2374 clinical staff in 23 Canadian tertiary care and community ICUs. For the 1285 completed surveys, scores were calculated for each of 34 domains. Average domain scores for each ICU were correlated with number of ICU beds and with intensivist vs nonintensivist management model. Domain scores for organizational culture were correlated with domain scores for safety culture. Culture domain scores were generally favorable in all ICUs. There were moderately strong positive correlations between number of ICU beds and perceived effectiveness at recruiting/retaining physicians (r = 0.58; P organizational and safety culture. Differences in perceptions between staff in larger and smaller ICUs highlight the importance of teamwork across units in larger ICUs. Copyright © 2012 Elsevier Inc. All rights reserved.

  9. Joint nuclear safety research projects between the US and Russian Federation International Nuclear Safety Centers

    International Nuclear Information System (INIS)

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

    1998-01-01

    The Russian Federation Ministry for Atomic Energy (MINATOM) and the US Department of Energy (USDOE) formed international Nuclear Safety Centers in October 1995 and July 1996, respectively, to collaborate on nuclear safety research. Since January 1997, the two centers have initiated the following nine joint research projects: (1) INSC web servers and databases; (2) Material properties measurement and assessment; (3) Coupled codes: Neutronic, thermal-hydraulic, mechanical and other; (4) Severe accident management for Soviet-designed reactors; (5) Transient management and advanced control; (6) Survey of relevant nuclear safety research facilities in the Russian Federation; (8) Advanced structural analysis; and (9) Development of a nuclear safety research and development plan for MINATOM. The joint projects were selected on the basis of recommendations from two groups of experts convened by NEA and from evaluations of safety impact, cost, and deployment potential. The paper summarizes the projects, including the long-term goals, the implementing strategy and some recent accomplishments for each project

  10. Improving Research Reactor Accident Response Capability at the Hungarian Nuclear Safety Authority

    International Nuclear Information System (INIS)

    Vegh, J.; Gajdos, F.; Horvath, Cs.; Matisz, A.; Nyisztor, D.

    2013-06-01

    The paper describes the design and implementation of an on-line operation monitoring and accident response support system to be used at the CERTA emergency response centre of Hungarian Atomic Energy Authority (HAEA). The monitored facility is the Budapest Research Reactor (BRR), which is a tank-type thermal reactor having 10 MW thermal power. The basic reason for the development of the on-line safety information system is to extend the emergency response capability of the CERTA crisis centre to include emergencies related to BRR, as well. CERTA is operated by HAEA at its Budapest headquarters and the centre already has an on-line system for monitoring the state of the four units of Paks NPP, Hungary. The system is called CERTA VITA and it is able to monitor the four VVER-440/V213 units during their normal operation, and during emergencies (including severe accidents). Ensuring appropriate emergency response capabilities, as well as improving the presently available systems and tools was one of the important recommendations resulting from the analyses following the severe accident at Fukushima. This task is valid not only for the operators of the nuclear facilities but also for the nuclear safety authorities, therefore HAEA decided to launch a project - together with the Centre for Energy Research, the operator of BRR - to establish an on-line information system similar to the CERTA VITA used for monitoring the four units of the Paks NPP. It is believed that by the introduction of this new on-line system the accident response capabilities of HAEA will be further enhanced and the BRR emergencies will be handled at the same professional level as potential emergencies at Paks NPP. (authors)

  11. NRC safety research in support of regulation--FY 1989

    International Nuclear Information System (INIS)

    1990-04-01

    This report, the fifth 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 FY 1989. 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

  12. NRC safety research in support of regulation, FY 1991

    International Nuclear Information System (INIS)

    1992-04-01

    This report, the seventh 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 FY 1991. 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

  13. NRC safety research in support of regulation, FY 1990

    International Nuclear Information System (INIS)

    1991-04-01

    This report, the sixth 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 FY 1990. 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

  14. Reactor Safety Research: Semiannual report, July-December 1986

    Energy Technology Data Exchange (ETDEWEB)

    1987-11-01

    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 the accident conditions and the development of analytical models, verified by experiment, which can be used to predict reactor and safety systems performance and 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 tehcnology base supporting licensing decisions.

  15. Reactor Safety Research: Semiannual report, July-December 1986

    International Nuclear Information System (INIS)

    1987-11-01

    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 the accident conditions and the development of analytical models, verified by experiment, which can be used to predict reactor and safety systems performance and 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 tehcnology base supporting licensing decisions

  16. 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...

  17. List of reports in the field of reactor safety research sponsored by BMFT, CEA, EPRI, JSTA and USNRC. Reported period: April 1 - June 30, 1987

    International Nuclear Information System (INIS)

    1987-08-01

    The 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 Programme of the BMFT, reporting organization. The list of reports appears quarterly. (orig.) [de

  18. Advancing perinatal patient safety through application of safety science principles using health IT.

    Science.gov (United States)

    Webb, Jennifer; Sorensen, Asta; Sommerness, Samantha; Lasater, Beth; Mistry, Kamila; Kahwati, Leila

    2017-12-19

    The use of health information technology (IT) has been shown to promote patient safety in Labor and Delivery (L&D) units. The use of health IT to apply safety science principles (e.g., standardization) to L&D unit processes may further advance perinatal safety. Semi-structured interviews were conducted with L&D units participating in the Agency for Healthcare Research and Quality's (AHRQ's) Safety Program for Perinatal Care (SPPC) to assess units' experience with program implementation. Analysis of interview transcripts was used to characterize the process and experience of using health IT for applying safety science principles to L&D unit processes. Forty-six L&D units from 10 states completed participation in SPPC program implementation; thirty-two (70%) reported the use of health IT as an enabling strategy for their local implementation. Health IT was used to improve standardization of processes, use of independent checks, and to facilitate learning from defects. L&D units standardized care processes through use of electronic health record (EHR)-based order sets and use of smart pumps and other technology to improve medication safety. Units also standardized EHR documentation, particularly related to electronic fetal monitoring (EFM) and shoulder dystocia. Cognitive aids and tools were integrated into EHR and care workflows to create independent checks such as checklists, risk assessments, and communication handoff tools. Units also used data from EHRs to monitor processes of care to learn from defects. Units experienced several challenges incorporating health IT, including obtaining organization approval, working with their busy IT departments, and retrieving standardized data from health IT systems. Use of health IT played an integral part in the planning and implementation of SPPC for participating L&D units. Use of health IT is an encouraging approach for incorporating safety science principles into care to improve perinatal safety and should be incorporated

  19. List of reports in the field of reactor safety research from BMFT, CEA, EPRI, JSTA and USNRC. Reported period: January 1 to June 30, 1994

    International Nuclear Information System (INIS)

    1994-01-01

    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 Bundesministerium fuer Forschung und Technologie (BMFT) with the Commissariat a l'Energie Atomique (CEA), the Japan Science and Technologie Agency (ISTA), the Electric Power Research Institute (EPRI) and the United States Nuclear Regulatory Commission, these reports are available in the Gesellschaft fuer Anlagen- und 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. (orig./HP) [de

  20. List of reports in the field of reactor safety research from BMFT, CEA, EPRI, JSTA and USNRC. Reported period: July 1 to December 31, 1993

    International Nuclear Information System (INIS)

    1993-01-01

    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 Bundesministerium fuer Forschung und Technologie (BMFT) with the Commissariat a l'Energie Atomique (CEA), the Japan Science and Technologie Agency (ISTA), the Electric Power Research Institute (EPRI) and the United States Nuclear Regulatory Commission, these reports are available in the Gesellschaft fuer Anlagen- und 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. (orig./HP) [de

  1. Kozloduy nuclear power plant. Units 1-4. Status of safety assessment activities. Rev. 2

    International Nuclear Information System (INIS)

    1999-01-01

    This paper presents the results of the status of safety assessment activities carried out by the Kozloduy Nuclear Power Plant (KNPP) in order to evaluate the current status of the safety of its reactor units 1-4. The steam supply system of this units is based of the reactor WWER-440/ B-230, which is a PWR of Russian design developed according to the safety standards in force in USSR in late 60-s. Now a days 10 reactor units of this type are in operation in four NPPs. Despite of efforts of the different plants to implement safety improvements measures during first 10-15 years of operation of this type of reactor its major safety problems were not eliminated and were a subject of international concern. The systematic evaluation of the deficiencies of the original design of this type of reactors have been initiated by IAEA in the beginning of 1990 and brought to developing a comprehensive list of safety problems which required urgent implementation of safety measures in all plants. To solve this problems in 1991 KNPP initiated implementation of so called 'short term' safety improvement program, developed with the help of WANO under agreement with Bulgarian Nuclear Safety Authority (BNSA) and consortium RISKAUDIT. The program was based on a stage approach and was foreseen to be implemented by tree stages in very tight time schedule in order to achieve significant and rapid improvements of the level of safety in operation of the units. The Short Tenn Program was implemented between the years 1991 and 1997 thanks of the strong safety commitment of NEK and KNPP staff and the broad international cooperation and financial support. Important part of resources were supplied under PHARE program of CEC, EBRD grant agreement and EDF support. The plant current safety level analysis has been performed using IAEA analytical methodology according to 50-SG-O12 standard 'Periodic safety review of operational nuclear power plants'. The approach and criteria for acceptable safety level

  2. Refurbishment and safety upgradation of research reactor Cirus

    International Nuclear Information System (INIS)

    Marik, S.K.; Rao, D.V.H.; Bhatnagar, A.; Pant, R.C.; Tikku, A.C.; Sankar, S.

    2006-01-01

    Cirus, a 40 MW t, vertical tank type research reactor, having wide range of research facilities, was commissioned in the year 1960. This research reactor, situated at Mumbai, India has been operated and utilized extensively for isotope production, material testing and neutron beam research for nearly four decades. With a view to assess the residual life of the reactor, detailed ageing studies were carried out during the early 1990s. Based on these studies, refurbishment of Cirus for its life extension was taken up. During refurbishment, additional safety features were incorporated in various systems to qualify them for the current safety standards. This paper gives the details of the operating experiences, utilization of the reactor along with methodologies followed for carrying out detailed ageing studies, refurbishment and safety upgradation for its life extension

  3. Current safety issues related to research reactor operation

    International Nuclear Information System (INIS)

    Alcala-Ruiz, F.

    2000-01-01

    The Agency has included activities on research reactor safety in its Programme and Budget (P and B) since its inception in 1957. Since then, these activities have traditionally been oriented to fulfil the Agency's functions and obligations. At the end of the decade of the eighties, the Agency's Research Reactor Safety Programme (RRSP) consisted of a limited number of tasks related to the preparation of safety related publications and the conduct of safety missions to research reactor facilities. It was at the beginning of the nineties when the RRSP was upgraded and expanded as a subprogramme of the Agency's P and B. This subprogramme continued including activities related to the above subjects and started addressing an increasing number of issues related to the current situation of research reactors (in operation and shut down) around the world such as reactor ageing, modifications and decommissioning. The present paper discusses some of the above issues as recognised by various external review or advisory groups (e.g., Peer Review Groups under the Agency's Performance Programme Appraisal System (PPAS) or the standing International Nuclear Safety Advisory Group (INSAG)) and the impact of their recommendations on the preparation and implementation of the part of the Agency's P and B relating to the above subject. (author)

  4. Code of Conduct on the Safety of Research Reactors

    International Nuclear Information System (INIS)

    2006-09-01

    The Board of Governors of the International Atomic Energy Agency (IAEA) adopted the Code of Conduct on the Safety of Research Reactors on 8 March 2004. The Board's action was the culmination of several years of work to develop the Code and obtain a consensus on its provisions. The process leading to the Code began in 1998, when the International Nuclear Safety Advisory Group (INSAG) informed the Director General of concerns about the safety of research reactors. In 2000, INSAG recommended that the Secretariat begin developing an international protocol or a similar legal instrument to address those concerns. In September 2000, in resolution GC(44)/RES/14, the General Conference requested the Secretariat ''within its available resources, to continue work on exploring options to strengthen the international nuclear safety arrangements for civil research reactors, taking due account of input from INSAG and the views of other relevant bodies''. A working group convened by the Secretariat pursuant to that request recommended that ''the Agency consider establishing an international action plan for research reactors'' and that the action plan include preparation of a Code of Conduct ''that would clearly establish the desirable attributes for management of research reactor safety''. In September 2001, the Board requested that the Secretariat develop and implement, in conjunction with Member States, an international research reactor safety enhancement plan which included preparation of a Code of Conduct on the Safety of Research Reactors. Subsequently, in resolution GC(45)/RES/10.A, the General Conference endorsed the Board's request. Pursuant to that request, a Code of Conduct on the Safety of Research Reactors was drafted at two meetings of an Open-ended Working Group of Legal and Technical Experts. This draft Code of Conduct was circulated to all Member States for comment. On the basis of the responses received, a revised draft of the Code was prepared by the Secretariat

  5. Nirex safety assessment research programme: 1987/88

    International Nuclear Information System (INIS)

    George, D.; Hodgkinson, D.P.

    1987-01-01

    The Nirex Safety Assessment Research programme's objective is to provide information for the radiological safety case for disposing low-level and intermediate-level radioactive wastes in underground repositories. The programme covers a wide range of experimental studies and mathematical modelling for the near and far field. It attempts to develop a quantitative understanding of events and processes which have an impact on the safety of radioactive waste disposal. (U.K.)

  6. Emerging research methods and their application to road safety.

    Science.gov (United States)

    Tarko, Andrew; Boyle, Linda Ng; Montella, Alfonso

    2013-12-01

    The study of road safety has seen great strides over the past few decades with advances in analytical methods and research tools that allow researchers to provide insights into the complex interactions of the driver, vehicle, and roadway. Data collection methods range from traditional traffic and roadway sensors to instrumented vehicles and driving simulators, capable of providing detailed data on both the normal driving conditions and the circumstances surrounding a safety critical event. In September 2011, the Third International Conference on Road Safety and Simulation was held in Indianapolis, Indiana, USA, which was hosted by the Purdue University Center for Road Safety and sponsored by the Transportation Research Board and its three committees: ANB20 Safety Data, Analysis and Evaluation, AND30 Simulation and Measurement of Vehicle and Operator Performance, and ABJ95 Visualization in Transportation. The conference brought together two hundred researchers from all over the world demonstrating some of the latest research methods to quantify crash causality and associations, and model road safety. This special issue is a collection of 14 papers that were presented at the conference and then peer-reviewed through this journal. These papers showcase the types of analytical tools needed to examine various crash types, the use of naturalistic and on-road data to validate the use of surrogate measures of safety, and the value of driving simulators to examine high-risk situations. Copyright © 2013 Elsevier Ltd. All rights reserved.

  7. Safety and Security Concerns of Nurses Working in the Intensive Care Unit: A Qualitative Study.

    Science.gov (United States)

    Keys, Yolanda; Stichler, Jaynelle F

    Intensive care units (ICUs) exist to serve as a safe place for critically ill patients to receive care from skilled practitioners. In this qualitative study, ICU nurses shared their perspectives on elements that promote safety and security on their units. After obtaining institutional review board approval, participants participated in telephone interviews with a nurse researcher who has experience as a bedside ICU nurse. Five categories and 14 themes were identified and then confirmed using member checking. Results indicate that participants prefer to provide care in ICUs with no more than 12 to 14 beds and provide the following: visibility of patients and coworkers; more than 1 way to exit; and can be locked in case of emergency or threat. Nearly all respondents mentioned adequate staffing as the most important attribute of a safe, secure care environment for patients and families. More research is needed to identify design features that make the most impact on providing a safe, secure ICU environment.

  8. 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

  9. Russian Minatom nuclear safety research strategic plan. An international review

    International Nuclear Information System (INIS)

    Royen, J.

    1999-01-01

    An NEA study on safety research needs of Russian-designed reactors, carried out in 1996, strongly recommended that a strategic plan for safety research be developed with respect to Russian nuclear power plants. Such a plan was developed at the Russian International Nuclear Safety Centre (RINSC) of the Russian Ministry of Atomic Energy (Minatom). The Strategic Plan is designed to address high-priority safety-research needs, through a combination of domestic research, the application of appropriate foreign knowledge, and collaboration. It represents major progress toward developing a comprehensive and coherent safety-research programme for Russian nuclear power plants (NPPs). The NEA undertook its review of the Strategic Plan with the objective of providing independent verification on the scope, priority, and content of the research described in the Plan based upon the experience of the international group of experts. The principal conclusions of the review and the general comments of the NEA group are presented. (K.A.)

  10. Safety upgrades to the NRU research reactor

    International Nuclear Information System (INIS)

    DeAbreu, B.; Mark, J.M.; Mutterback, E.J.

    1998-01-01

    The NRU (National Research Universal) Reactor is a 135 MW thermal research facility located at Chalk River Laboratories, and is owned and operated by Atomic Energy of Canada Limited. One of the largest and most versatile research reactors in the world, it serves as the R and D workhorse for Canada's CANDU business while at the same time filling the role as one of the world's major producers of medical radioisotopes. AECL plans to extend operation of the NRU reactor to approximately the year 2005 when a new replacement, the Irradiation Research Facility (IRF) will be available. To achieve this, AECL has undertaken a program of safety reassessment and upgrades to enhance the level of safety consistent with modem requirements. An engineering assessment/inspection of critical systems, equipment and components was completed and seven major safety upgrades are being designed and installed. These upgrades will significantly reduce the reactor's vulnerability to common mode failures and external hazards, with particular emphasis on seismic protection. The scheduled completion date for the project is 1999 December at a cost approximately twice the annual operating cost. All work on the NRU upgrade project is planned and integrated into the regular operating cycles of the reactor; no major outages are anticipated. This paper describes the safety upgrades and discusses the technical and managerial challenges involved in extending the operating life of the NRU reactor. (author)

  11. Review of current status of LWR safety research in Japan

    International Nuclear Information System (INIS)

    Yamada, Tasaburo; Mishima, Yoshitsugu; Ando, Yoshio; Miyazono, Shohachiro; Takashima, Yoichi.

    1977-01-01

    The Japan Atomic Energy Commission has exerted efforts on the research of the safety of nuclear plants in Japan, and ''Nuclear plant safety research committees'' was established in August 1974, which is composed of the government and the people. The philosophy of safety research, research and development plan, the forwarding procedure of the plan, international cooperation, for example LOFT program, and the effective feed back of the experimental results concerning nuclear safety are reviewed in this paper at first. As for the safety of nuclear reactors the basic philosophy that radio active fission products are contained in fuel or reactors with multiple barriers, (defence in depth) and almost no fission product is released outside reactor plants even at the time of hypothetical accident, is kept, and the research and development history and the future plan are described in this paper with the related technical problems. The structural safety is also explained, for example, on the philosophy ''leak before break'', pipe rupture, pipe restraint and stress analysis. The release of radioactive gas and liquid is decreased as the philosophy ''ALAP''. And probability safety evaluation method, LOCA, reactivity, accident and aseismatic design in nuclear plants in Japan are described. (Nakai, Y.)

  12. NRC/DAE reactor safety research Data Bank

    International Nuclear Information System (INIS)

    Laats, E.T.

    1982-01-01

    In 1976, the United States Nuclear Regulatory Commission (NRC) established the NRC/Division of Accident Evaluation (DAE) Data Bank to collect, store, and make available data from the many domestic and foreign water reactor safety research programs. This program has since grown from the conceptual stage to a useful, usable service for computer code development, code assessment, and experimentation groups in meeting the needs of the nuclear industry. Data from 20 facilities are now processed and permanently stored in the Data Bank, which utilizes the Control Data Corporation (CDC) CYBER 176 computer system located at the Idaho National Engineering Laboratory (INEL). New data and data sources are continually being added to the Data Bank. In addition to providing data storage and access software, the Data Bank program supplies data entry, documentation, and training and advisory services to users and the NRC. Management of the NRC/DAE Data Bank is provided by EG and G Idaho, Inc

  13. Safety Management and Safety Culture Self Assessment of Kartini Research Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Syarip, S., E-mail: syarip@batan.go.id [Centre for Accelerator and Material Process Technology, National Nuclear Energy Agency (BATAN), Yogyakarta (Indonesia)

    2014-10-15

    The self-assessment of safety culture and safety management status of Kartini research reactor is a step to foster safety culture and management by identifying good practices and areas for improvement, and also to improve reactor safety in a whole. The method used in this assessment is based on questionnaires provided by the Forum for Nuclear Cooperation in Asia (FNCA), then reviewed by experts. Based on the assessment and evaluation results, it can be concluded that there were several good practices in maintaining the safety status of Kartini reactor such as: reactor operators and radiation protection workers were aware and knowledgeable of the safety standards and policies that apply to their operation, readily accept constructive criticism from their management and from the inspectors of regulatory body that address safety performance. As a proof, for the last four years the number of inspection/audit findings from Regulatory Body (BAPETEN) tended to decrease while the reactor utilization and its operating hour increased. On the other hands there were also some comments and recommendations for improvement of reactor safety culture, such as that there should be more frequent open dialogues between employees and managers, to grow and attain a mutual support to achieve safety goals. (author)

  14. Patient safety culture in obstetrics and gynecology and neonatology units: the nurses' and the midwives' opinion.

    Science.gov (United States)

    Ribeliene, Janina; Blazeviciene, Aurelija; Nadisauskiene, Ruta Jolanta; Tameliene, Rasa; Kudreviciene, Ausrele; Nedzelskiene, Irena; Macijauskiene, Jurate

    2018-04-22

    Patients treated in health care facilities that provide services in the fields of obstetrics, gynecology, and neonatology are especially vulnerable. Large multidisciplinary teams of physicians, multiple invasive and noninvasive diagnostic and therapeutic procedures, and the use of advanced technologies increase the probability of adverse events. The evaluation of knowledge about patient safety culture among nurses and midwives working in such units and the identification of critical areas at a health care institution would reduce the number of adverse events and improve patient safety. The aim of the study was to evaluate the opinion of nurses and midwives working in clinical departments that provide services in the fields of obstetrics, gynecology, and neonatology about patient safety culture and to explore potential predictors for the overall perception of safety. We used the Hospital Survey on Patient Safety Culture (HSOPSC) to evaluate nurses' and midwives' opinion about patient safety issues. The overall response rate in the survey was 100% (n = 233). The analysis of the dimensions of safety on the unit level showed that the respondents' most positive evaluations were in the Organizational Learning - Continuous Improvement (73.2%) and Feedback and Communication about Error (66.8%) dimensions, and the most negative evaluations in the Non-punitive Response to Error (33.5%) and Staffing (44.6%) dimensions. On the hospital level, the evaluation of the safety dimensions ranged between 41.4 and 56.8%. The percentage of positive responses in the outcome dimensions Frequency of Events Reported was 82.4%. We found a significant association between the outcome dimension Frequency of Events Reported and the Hospital Management Support for Patient Safety and Feedback and Communication about Error Dimensions. On the hospital level, the critical domains in health care facilities that provide services in the fields of obstetrics, gynecology, and neonatology were Teamwork

  15. Current safety practices in nano-research laboratories in China.

    Science.gov (United States)

    Zhang, Can; Zhang, Jing; Wang, Guoyu

    2014-06-01

    China has become a key player in the global nanotechnology field, however, no surveys have specifically examined safety practices in the Chinese nano-laboratories in depth. This study reports results of a survey of 300 professionals who work in research laboratories that handle nanomaterials in China. We recruited participants at three major nano-research laboratories (which carry out research in diverse fields such as chemistry, material science, and biology) and the nano-chemistry session of the national meeting of the Chinese Chemical Society. Results show that almost all nano-research laboratories surveyed had general safety regulations, whereas less than one third of respondents reported having nanospecific safety rules. General safety measures were in place in most surveyed nano-research laboratories, while nanospecific protective measures existed or were implemented less frequently. Several factors reported from the scientific literature including nanotoxicology knowledge gaps, technical limitations on estimating nano-exposure, and the lack of nano-occupational safety legislation may contribute to the current state of affairs. With these factors in mind and embracing the precautionary principle, we suggest strengthening or providing nanosafety training (including raising risk awareness) and establishing nanosafety guidelines in China, to better protect personnel in the nano-workplace.

  16. Status of criticality safety research at NUCEF

    Energy Technology Data Exchange (ETDEWEB)

    Nakajima, Ken [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    1998-03-01

    Two critical facilities, named STACY (Static Experiment Critical Facility) and TRACY (Transient Experiment Critical Facility), at the Nuclear Fuel Cycle Safety Engineering Research Facility (NUCEF) started their hot operations in 1995. Since then, basic experimental data for criticality safety research have been accumulated using STACY, and supercritical experiments for the study of criticality accident in a reprocessing plant have been performed using TRACY. In this paper, the outline of those critical facilities and the main results of TRACY experiments are presented. (author)

  17. 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.

  18. Summary of fuel safety research meeting 2005

    International Nuclear Information System (INIS)

    Fuketa, Toyoshi; Nakamura, Takehiko; Nagase, Fumihisa; Nakamura, Jinichi; Suzuki, Motoe; Sasajima, Hideo; Sugiyama, Tomoyuki; Amaya, Masaki; Kudo, Tamotsu; Chuto, Toshinori; Tomiyasu, Kunihiko; Udagawa, Yutaka; Ikehata, Hisashi; Kida, Mitsuko; Ikatsu, Nobuhiko; Hosoyamada, Ryuji; Hamanishi, Eizou; Iwasaki, Ryo; Ozawa, Masaaki

    2006-03-01

    Fuel Safety Research Meeting 2005, which was organized by the Japan Atomic Energy Agency (Establishment of the new organization in Oct. 1, 2005 integrated of JAERI and JNC) was held on March 2-3, 2005 at Toshi Center Hotel, 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 meting covered the status of fuel safety research activities, fuel behavior under Reactivity Initiated Accident (RIA) and Loss of coolant accident (LOCA) conditions, high fuel behavior, and radionuclide release under severe accident conditions. This summary contains all the abstracts and sheets of viewgraph presented in the meeting. (author)

  19. 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.

  20. Structural empowerment and patient safety culture among registered nurses working in adult critical care units.

    Science.gov (United States)

    Armellino, Donna; Quinn Griffin, Mary T; Fitzpatrick, Joyce J

    2010-10-01

    The aim of the present study was to examine the relationship between structural empowerment and patient safety culture among staff level Registered Nurses (RNs) within adult critical care units (ACCU). There is literature to support the value of RNs' structurally empowered work environments and emerging literature towards patient safety culture; the link between empowerment and patient safety culture is being discovered. A sample of 257 RNs, working within adult critical care of a tertiary hospital in the United States, was surveyed. Instruments included a background data sheet, the Conditions of Workplace Effectiveness and the Hospital Survey on Patient Safety Culture. Structural empowerment and patient safety culture were significantly correlated. As structural empowerment increased so did the RNs' perception of patient safety culture. To foster patient safety culture, nurse leaders should consider providing structurally empowering work environments for RNs. This study contributes to the body of knowledge linking structural empowerment and patient safety culture. Results link structurally empowered RNs and increased patient safety culture, essential elements in delivering efficient, competent, quality care. They inform nursing management of key factors in the nurses' environment that promote safe patient care environments. © 2010 The Authors. Journal compilation © 2010 Blackwell Publishing Ltd.

  1. 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.

  2. 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

  3. Time series modeling in traffic safety research.

    Science.gov (United States)

    Lavrenz, Steven M; Vlahogianni, Eleni I; Gkritza, Konstantina; Ke, Yue

    2018-08-01

    The use of statistical models for analyzing traffic safety (crash) data has been well-established. However, time series techniques have traditionally been underrepresented in the corresponding literature, due to challenges in data collection, along with a limited knowledge of proper methodology. In recent years, new types of high-resolution traffic safety data, especially in measuring driver behavior, have made time series modeling techniques an increasingly salient topic of study. Yet there remains a dearth of information to guide analysts in their use. This paper provides an overview of the state of the art in using time series models in traffic safety research, and discusses some of the fundamental techniques and considerations in classic time series modeling. It also presents ongoing and future opportunities for expanding the use of time series models, and explores newer modeling techniques, including computational intelligence models, which hold promise in effectively handling ever-larger data sets. The information contained herein is meant to guide safety researchers in understanding this broad area of transportation data analysis, and provide a framework for understanding safety trends that can influence policy-making. Copyright © 2017 Elsevier Ltd. All rights reserved.

  4. Safety culture in the maternity unit of hospitals in Ilam province, Iran: a census survey using HSOPSC tool.

    Science.gov (United States)

    Akbari, Nahid; Malek, Marzieh; Ebrahimi, Parvin; Haghani, Hamid; Aazami, Sanaz

    2017-01-01

    Improving quality of maternal care as well as patients' safety are two important issues in health-care service. Therefore, this study aimed to assess the culture of patient safety at maternity units. This cross-sectional study was conducted among staffs working at maternity units in seven hospitals of Ilam city, Iran. The staffs included in this study were gynecologists and midwifes working in different positions including matron, supervisors, head of departments and staffs. Data were collected using the Hospital Survey on Patient Safety Culture (HSOPSC). This study indicated that 59.1% of participants reported fair level of overall perceptions of safety and 67.1% declared that no event was reported during the past 12 months. The most positively perceived dimension of safety culture was teamwork within departments in view of managers (79.41) and personnel (81.10). However, the least positively perceived dimensions of safety culture was staffing levels. The current study revealed areas of strength (teamwork within departments) and weakness (staffing, punitive responses to error) among managers and personnel. In addition, we found that staffs in Ilam's hospitals accept the patient safety culture in maternity units, but, still are far away from excellent culture of patient safety. Therefore, it is necessary to promote culture of patient's safety among professions working in the maternity units of Ilam's hospitals.

  5. 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

  6. 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

  7. 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

  8. 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.

  9. Yearly plan of safety research on environmental radioactivity for 1996 - 2000

    International Nuclear Information System (INIS)

    1996-01-01

    'Yearly Plan of Safety Research on Environmental Radioactivity' proposed from the special meeting for safety research of environmental radioactivity on December 14, 1995 was investigated by Nuclear Safety Commission. And the safety research of environmental radioactivity in Japan was decided to be pursued according to the plan. The contents of this plan consisted of the purpose and the contents of research as well as the research period and the facilities to be done for each theme. The following themes were included; 1) study on environment·radiation dose and study on radiation exposure reduction. 2) study on biological effects of radiation. 3) study on internal exposure by specified nuclides. 4) study on medical measures for acute radiation exposure. 5) study on assessment of nuclear safety. 6) investigation on radioactivities released from various nuclear facilities in Japan to demonstrate their safety. (M.N.)

  10. List of reports on reactor safety research by BMFT, USNRC, EPRI and JSTA. Period under review: 1st January until 31st March 1978

    International Nuclear Information System (INIS)

    1978-05-01

    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 Regulatory Commisssion (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.) [de

  11. Code on the safety of nuclear research reactors: Design

    International Nuclear Information System (INIS)

    1992-01-01

    The main objective of this publication is to provide a safety basis for the design of a research reactor and for the assessment of the design. Another objective is to cover certain aspects related to regulatory supervision, siting and quality assurance, as far as these are related to activities for the design of a research reactor. These objectives are expressed in terms of requirements and recommendations for the design of research reactors. Emphasis is placed on the safety requirements that shall be met rather than on ways in which they can be met. The requirements and recommendations may form the foundation necessary for a Member State to develop specific regulations and safety criteria for its research reactor programme.

  12. Buff book 1: status summary report, water reactor safety research

    International Nuclear Information System (INIS)

    1980-01-01

    This Management Report, to provide information for monitoring and controlling the progress of LWR Safety Research Projects Associated with the Office of Nuclear Regulatory Research and other agencies and organizations engaged in nuclear safety research. It utilizes data pertaining to project schedules, cost, and status which have been integrated into a network-based management information system, The purpose of this publication is to provide a vehicle for review of the current status and overall progress of the safety Research Program from a managerial point of view

  13. Sociotechnical approaches to workplace safety: Research needs and opportunities

    Science.gov (United States)

    Robertson, Michelle M.; Hettinger, Lawrence J.; Waterson, Patrick E.; Ian Noy, Y.; Dainoff, Marvin J.; Leveson, Nancy G.; Carayon, Pascale; Courtney, Theodore K.

    2015-01-01

    The sociotechnical systems perspective offers intriguing and potentially valuable insights into problems associated with workplace safety. While formal sociotechnical systems thinking originated in the 1950s, its application to the analysis and design of sustainable, safe working environments has not been fully developed. To that end, a Hopkinton Conference was organised to review and summarise the state of knowledge in the area and to identify research priorities. A group of 26 international experts produced collaborative articles for this special issue of Ergonomics, and each focused on examining a key conceptual, methodological and/or theoretical issue associated with sociotechnical systems and safety. In this concluding paper, we describe the major conference themes and recommendations. These are organised into six topic areas: (1) Concepts, definitions and frameworks, (2) defining research methodologies, (3) modelling and simulation, (4) communications and decision-making, (5) sociotechnical attributes of safe and unsafe systems and (6) potential future research directions for sociotechnical systems research. Practitioner Summary: Sociotechnical complexity, a characteristic of many contemporary work environments, presents potential safety risks that traditional approaches to workplace safety may not adequately address. In this paper, we summarise the investigations of a group of international researchers into questions associated with the application of sociotechnical systems thinking to improve worker safety. PMID:25728246

  14. Licensing procedures and safety criteria for research reactors in France

    International Nuclear Information System (INIS)

    Berry, J.L.; Lerouge, B.

    1983-01-01

    From the very beginning of the CEA up to now, a great deal of work has been devoted to the development and utilization of research reactors in France for the needs of fundamental and applied research, production of radioisotopes, and training. In recent years, new reactors were commissioned while others were decommissioned. Moreover some of the existing facilities underwent important modifications to comply with more severe safety criteria, increase the experimental capabilities or qualify new low-enrichment fuels for research reactors (Osiris and Isis). This paper summarizes the recent evolution of the French research reactor capacity, describes the licensing process, the main safety criteria which are taken into consideration, and associated safety research. At the end, a few considerations are given to the consequences of the Osiris core conversion. Safety of research reactors has been studied in detail and many improvements have been brought due to: implementation of a specific experimental program, and adaptation of safety principles and rules elaborated for power reactors. Research reactors in operation in France have been built within a 22 year period. Meanwhile, safety rules have been improved. Old reactors do not comply with all the new rules but modifications are continuously made: after analysis of incidents, when replacement of equipment has to be carried out, when an important modification (fuel conversion for example) is decided upon

  15. Licensing procedures and safety criteria for research reactors in France

    Energy Technology Data Exchange (ETDEWEB)

    Berry, J L; Lerouge, B [Centre d' Etudes Nucleaires de Saclay (France)

    1983-08-01

    From the very beginning of the CEA up to now, a great deal of work has been devoted to the development and utilization of research reactors in France for the needs of fundamental and applied research, production of radioisotopes, and training. In recent years, new reactors were commissioned while others were decommissioned. Moreover some of the existing facilities underwent important modifications to comply with more severe safety criteria, increase the experimental capabilities or qualify new low-enrichment fuels for research reactors (Osiris and Isis). This paper summarizes the recent evolution of the French research reactor capacity, describes the licensing process, the main safety criteria which are taken into consideration, and associated safety research. At the end, a few considerations are given to the consequences of the Osiris core conversion. Safety of research reactors has been studied in detail and many improvements have been brought due to: implementation of a specific experimental program, and adaptation of safety principles and rules elaborated for power reactors. Research reactors in operation in France have been built within a 22 year period. Meanwhile, safety rules have been improved. Old reactors do not comply with all the new rules but modifications are continuously made: after analysis of incidents, when replacement of equipment has to be carried out, when an important modification (fuel conversion for example) is decided upon.

  16. 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)

  17. 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

  18. Licensing procedures and safety criteria for research reactors in France

    International Nuclear Information System (INIS)

    Berry, J.L.; Lerouge, B.

    1980-11-01

    This paper summarizes the recent evolution of the French research reactor capacity, describes the licensing process, the main safety criteria which are taken into consideration, and associated safety research. Some of the existing facilities underwent important modifications to comply with more severe safety criteria, increase the experimental capabilities or qualify new low-enrichment fuels for research reactors. At the end, a few considerations are given to the consequences of the Osiris core conversion

  19. Psychometric model for safety culture assessment in nuclear research facilities

    Energy Technology Data Exchange (ETDEWEB)

    Nascimento, C.S. do, E-mail: claudio.souza@ctmsp.mar.mil.br [Centro Tecnológico da Marinha em São Paulo (CTMSP), Av. Professor Lineu Prestes 2468, 05508-000 São Paulo, SP (Brazil); Andrade, D.A., E-mail: delvonei@ipen.br [Instituto de Pesquisas Energéticas e Nucleares (IPEN/CNEN – SP), Av. Professor Lineu Prestes 2242, 05508-000 São Paulo, SP (Brazil); Mesquita, R.N. de, E-mail: rnavarro@ipen.br [Instituto de Pesquisas Energéticas e Nucleares (IPEN/CNEN – SP), Av. Professor Lineu Prestes 2242, 05508-000 São Paulo, SP (Brazil)

    2017-04-01

    Highlights: • A psychometric model to evaluate ‘safety climate’ at nuclear research facilities. • The model presented evidences of good psychometric qualities. • The model was applied to nuclear research facilities in Brazil. • Some ‘safety culture’ weaknesses were detected in the assessed organization. • A potential tool to develop safety management programs in nuclear facilities. - Abstract: A safe and reliable operation of nuclear power plants depends not only on technical performance, but also on the people and on the organization. Organizational factors have been recognized as the main causal mechanisms of accidents by research organizations through USA, Europe and Japan. Deficiencies related with these factors reveal weaknesses in the organization’s safety culture. A significant number of instruments to assess the safety culture based on psychometric models that evaluate safety climate through questionnaires, and which are based on reliability and validity evidences, have been published in health and ‘safety at work’ areas. However, there are few safety culture assessment instruments with these characteristics (reliability and validity) available on nuclear literature. Therefore, this work proposes an instrument to evaluate, with valid and reliable measures, the safety climate of nuclear research facilities. The instrument was developed based on methodological principles applied to research modeling and its psychometric properties were evaluated by a reliability analysis and validation of content, face and construct. The instrument was applied to an important nuclear research organization in Brazil. This organization comprises 4 research reactors and many nuclear laboratories. The survey results made possible a demographic characterization and the identification of some possible safety culture weaknesses and pointing out potential areas to be improved in the assessed organization. Good evidence of reliability with Cronbach's alpha

  20. Psychometric model for safety culture assessment in nuclear research facilities

    International Nuclear Information System (INIS)

    Nascimento, C.S. do; Andrade, D.A.; Mesquita, R.N. de

    2017-01-01

    Highlights: • A psychometric model to evaluate ‘safety climate’ at nuclear research facilities. • The model presented evidences of good psychometric qualities. • The model was applied to nuclear research facilities in Brazil. • Some ‘safety culture’ weaknesses were detected in the assessed organization. • A potential tool to develop safety management programs in nuclear facilities. - Abstract: A safe and reliable operation of nuclear power plants depends not only on technical performance, but also on the people and on the organization. Organizational factors have been recognized as the main causal mechanisms of accidents by research organizations through USA, Europe and Japan. Deficiencies related with these factors reveal weaknesses in the organization’s safety culture. A significant number of instruments to assess the safety culture based on psychometric models that evaluate safety climate through questionnaires, and which are based on reliability and validity evidences, have been published in health and ‘safety at work’ areas. However, there are few safety culture assessment instruments with these characteristics (reliability and validity) available on nuclear literature. Therefore, this work proposes an instrument to evaluate, with valid and reliable measures, the safety climate of nuclear research facilities. The instrument was developed based on methodological principles applied to research modeling and its psychometric properties were evaluated by a reliability analysis and validation of content, face and construct. The instrument was applied to an important nuclear research organization in Brazil. This organization comprises 4 research reactors and many nuclear laboratories. The survey results made possible a demographic characterization and the identification of some possible safety culture weaknesses and pointing out potential areas to be improved in the assessed organization. Good evidence of reliability with Cronbach's alpha

  1. A measurement tool to assess culture change regarding patient safety in hospital obstetrical units.

    Science.gov (United States)

    Kenneth Milne, J; Bendaly, Nicole; Bendaly, Leslie; Worsley, Jill; FitzGerald, John; Nisker, Jeff

    2010-06-01

    Clinical error in acute care hospitals can only be addressed by developing a culture of safety. We sought to develop a cultural assessment survey (CAS) to assess patient safety culture change in obstetrical units. Interview prompts and a preliminary questionnaire were developed through a literature review of patient safety and "high reliability organizations," followed by interviews with members of the Managing Obstetrical Risk Efficiently (MOREOB) Program of the Society of Obstetricians and Gynaecologists of Canada. Three hundred preliminary questionnaires were mailed, and 21 interviews and 9 focus groups were conducted with the staff of 11 hospital sites participating in the program. To pilot test the CAS, 350 surveys were mailed to staff in participating hospitals, and interviews were conducted with seven nurses and five physicians who had completed the survey. Reliability analysis was conducted on four units that completed the CAS prior to and following the implementation of the first MOREOB module. Nineteen values and 105 behaviours, practices, and perceptions relating to patient safety were identified and included in the preliminary questionnaire, of which 143 of 300 (47.4%) were returned. Among the 220 cultural assessment surveys returned (62.9%), six cultural scales emerged: (1) patient safety as everyone's priority; (2) teamwork; (3) valuing individuals; (4) open communication; (5) learning; and (6) empowering individuals. The reliability analysis found all six scales to have internal reliability (Cronbach alpha), ranging from 0.72 (open communication) to 0.84 (valuing individuals). The CAS developed for this study may enable obstetrical units to assess change in patient safety culture.

  2. 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

  3. Water cooled reactor technology: Safety research abstracts no. 1

    International Nuclear Information System (INIS)

    1990-01-01

    The Commission of the European Communities, the International Atomic Energy Agency and the Nuclear Energy Agency of the OECD publish these Nuclear Safety Research Abstracts within the framework of their efforts to enhance the safety of nuclear power plants and to promote the exchange of research information. The abstracts are of nuclear safety related research projects for: pressurized light water cooled and moderated reactors (PWRs); boiling light water cooled and moderated reactors (BWRs); light water cooled and graphite moderated reactors (LWGRs); pressurized heavy water cooled and moderated reactors (PHWRs); gas cooled graphite moderated reactors (GCRs). Abstracts of nuclear safety research projects for fast breeder reactors are published independently by the Nuclear Energy Agency of the OECD and are not included in this joint publication. The intention of the collaborating international organizations is to publish such a document biannually. Work has been undertaken to develop a common computerized system with on-line access to the stored information

  4. Safety culture and quality management of Kartini research reactor

    International Nuclear Information System (INIS)

    Syarip; Hauptmanns, Ulrich

    1999-01-01

    The evaluation for assessing the safety culture and quality of safety management of Kartini research reactor is presented. The method is based on the concept of management control of safety (audit) as well as by using the developed method i.e. the questionnaires concerning areas of relevance which have to be answered with value statements. There are seven statements or qualifiers in answering the questions. Since such statements are vague, they are represented by fuzzy numbers. The weaknesses can be identified from the different areas contemplated. The evaluation result show that the quality of safety management of Kartini research reactor is globally rated as 'Average'. The operator behavior in the implementation of 'safety culture' concept is found as a weakness, therefore this area should be improved. (author)

  5. Overview of the Nuclear Regulatory Commission's safety research program

    International Nuclear Information System (INIS)

    Beckjord, E.S.

    1989-01-01

    Accomplishments during 1988 of the Office of Nuclear Regulatory Research and the program of safety research are highlighted, and plans, expections, and needs of the next year and beyond are discussed. Topics discussed include: ECCS Appendix K Revision; pressurized thermal shock; NUREG-1150, or the PRA method performance document; resolution of station blackout; severe accident integration plan; nuclear safety research review committee; and program management

  6. Study of system safety evaluation on LTO of national project. NISA safety research project on system safety of nuclear power plants

    International Nuclear Information System (INIS)

    Takizawa, Masayuki; Sekimura, Naoto; Miyano, Hiroshi; Aoyama, Katsunobu

    2012-01-01

    Japanese safety regulatory body, that is, Nuclear and Industrial Safety Agency (NISA) started a 5-year national safety research project as 'the first stage' from 2006 FY to 2010 FY whose objective is 'Improve the technical information basis in order to utilize knowledge as well as information related to ageing management and maintenance of NPPs. Fukushima disaster happened in March 2011, and the priority of research needs for ageing management dramatically changed in Japan. The second-stage national project started in October 2011 with the concept of 'system safety' of NNPs where not only ageing management on degradation phenomena of important components but also safety management on total plant systems are paid attention to. The second-stage project is so called 'Japanese Ageing Management Program for System Safety (JAMPSS)'. (author)

  7. Introduction to Safety Analysis Approach for Research Reactors

    International Nuclear Information System (INIS)

    Park, Suki

    2016-01-01

    The research reactors have a wide variety in terms of thermal powers, coolants, moderators, reflectors, fuels, reactor tanks and pools, flow direction in the core, and the operating pressure and temperature of the cooling system. Around 110 research reactors have a thermal power greater than 1 MW. This paper introduces a general approach to safety analysis for research reactors and deals with the experience of safety analysis on a 10 MW research reactor with an open-pool and open-tank reactor and a downward flow in the reactor core during normal operation. The general approach to safety analysis for research reactors is described and the design features of a typical open-pool and open-tank type reactor are discussed. The representative events expected in research reactors are investigated. The reactor responses and the thermal hydraulic behavior to the events are presented and discussed. From the minimum CHFR and the maximum fuel temperature calculated, it is ensured that the fuel is not damaged in the step insertion of reactivity by 1.8 mk and the failure of all primary pumps for the reactor with a 10 MW thermal power and downward core flow

  8. 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)

  9. Core competencies for patient safety research: a cornerstone for global capacity strengthening

    Science.gov (United States)

    Andermann, Anne; Ginsburg, Liane; Norton, Peter; Arora, Narendra; Bates, David; Wu, Albert

    2011-01-01

    Background Tens of millions of patients worldwide suffer disabling injuries or death every year due to unsafe medical care. Nonetheless, there is a scarcity of research evidence on how to tackle this global health priority. The shortage of trained researchers is a major limitation, particularly in developing and transitional countries. Objectives As a first step to strengthen capacity in this area, the authors developed a set of internationally agreed core competencies for patient safety research worldwide. Methods A multistage process involved developing an initial framework, reviewing the existing literature relating to competencies in patient safety research, conducting a series of consultations with potential end users and international experts in the field from over 35 countries and finally convening a global consensus conference. Results An initial draft list of competencies was grouped into three themes: patient safety, research methods and knowledge translation. The competencies were considered by the WHO Patient Safety task force, by potential end users in developing and transitional countries and by international experts in the field to be relevant, comprehensive, clear, easily adaptable to local contexts and useful for training patient safety researchers internationally. Conclusions Reducing patient harm worldwide will require long-term sustained efforts to build capacity to enable practical research that addresses local problems and improves patient safety. The first edition of Competencies for Patient Safety Researchers is proposed by WHO Patient Safety as a foundation for strengthening research capacity by guiding the development of training programmes for researchers in the area of patient safety, particularly in developing and transitional countries, where such research is urgently needed. PMID:21228081

  10. Implementing the Comprehensive Unit-Based Safety Program (CUSP) to Improve Patient Safety in an Academic Primary Care Practice.

    Science.gov (United States)

    Pitts, Samantha I; Maruthur, Nisa M; Luu, Ngoc-Phuong; Curreri, Kimberly; Grimes, Renee; Nigrin, Candace; Sateia, Heather F; Sawyer, Melinda D; Pronovost, Peter J; Clark, Jeanne M; Peairs, Kimberly S

    2017-11-01

    While there is growing awareness of the risk of harm in ambulatory health care, most patient safety efforts have focused on the inpatient setting. The Comprehensive Unit-based Safety Program (CUSP) has been an integral part of highly successful safety efforts in inpatient settings. In 2014 CUSP was implemented in an academic primary care practice. As part of CUSP implementation, staff and clinicians underwent training on the science of safety and completed a two-question safety assessment survey to identify safety concerns in the practice. The concerns identified by team members were used to select two initial safety priorities. The impact of CUSP on safety climate and teamwork was assessed through a pre-post comparison of results on the validated Safety Attitudes Questionnaire. Ninety-six percent of staff completed science of safety training as part of CUSP implementation, and 100% of staff completed the two-question safety assessment. The most frequently identified safety concerns were related to medications (n = 11, 28.2), diagnostic testing (n = 9, 25), and communication (n = 5, 14). The CUSP team initially prioritized communication and infection control, which led to standardization of work flows within the practice. Six months following CUSP implementation, large but nonstatistically significant increases were found for the percentage of survey respondents who reported knowledge of the proper channels for questions about patient safety, felt encouraged to report safety concerns, and believed that the work setting made it easy to learn from the errors of others. CUSP is a promising tool to improve safety climate and to identify and address safety concerns within ambulatory health care. Copyright © 2017 The Joint Commission. Published by Elsevier Inc. All rights reserved.

  11. Safety analysis of the CSTR-1 bench-scale coal liquefaction unit

    Energy Technology Data Exchange (ETDEWEB)

    Hulburt, D.A.

    1981-05-01

    The objective of the program reported herein was to provide a Safety Analysis of the CSTR-1 bench scale unit located in Building 167 at the Pittsburgh Energy Technology Center. It was apparent that considerable effort was expended in the design and construction of the unit, and in the development of operating procedures, with regard to safety. Exhaust ventilation, H/sub 2/ and H/sub 2/S monitoring, overpressure protection, overtemperature protection, and interlock systems have been provided. Present settings on the pressure and temperature safety systems are too high, however, to insure prevention of vessel deformation or damage in all cases. While the occurrence of catastrophic rupture of a system pressure vessel (e.g., reactor, high pressure separators) is unlikely, the potential consequences to personnel are severe. Feasibility of providing shielding for these components should be considered. A more probable mode of vessel failure in the event of overpressure or overtemperature and failure of the safety system is yielding of the closure bolts followed by high pressure flow across the mating surfaces. As a minimum, shielding should be designed to restrict travel of resultant spray. The requirements for personal protective equipment are presently stated in rather broad and general terms in the operating procedures. Safe practices and procedures would be more assured if specific requirements were stated and included for each operational step. Recommendations were developed for all hazards triggered by the guidelines.

  12. Use of a Graded Approach in the Application of the Safety Requirements for Research Reactors. Specific Safety Guide

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-11-15

    The IAEA's Statute authorizes the Agency to 'establish or adopt? standards of safety for protection of health and minimization of danger to life and property' - standards that the IAEA must use in its own operations, and which States can apply by means of their regulatory provisions for nuclear and radiation safety. The IAEA does this in consultation with the competent organs of the United Nations and with the specialized agencies concerned. A comprehensive set of high quality standards under regular review is a key element of a stable and sustainable global safety regime, as is the IAEA's assistance in their application. The IAEA commenced its safety standards programme in 1958. The emphasis placed on quality, fitness for purpose and continuous improvement has led to the widespread use of the IAEA standards throughout the world. The Safety Standards Series now includes unified Fundamental Safety Principles, which represent an international consensus on what must constitute a high level of protection and safety. With the strong support of the Commission on Safety Standards, the IAEA is working to promote the global acceptance and use of its standards. Standards are only effective if they are properly applied in practice. The IAEA's safety services encompass design, siting and engineering safety, operational safety, radiation safety, safe transport of radioactive material and safe management of radioactive waste, as well as governmental organization, regulatory matters and safety culture in organizations. These safety services assist Member States in the application of the standards and enable valuable experience and insights to be shared. Regulating safety is a national responsibility, and many States have decided to adopt the IAEA's standards for use in their national regulations. For parties to the various international safety conventions, IAEA standards provide a consistent, reliable means of ensuring the effective fulfilment of obligations under the conventions

  13. The Nordic Nuclear Safety Research (NKS) programme. Nordic cooperation on nuclear safety

    Energy Technology Data Exchange (ETDEWEB)

    Andersson, Kasper G. [Technical Univ. of Denmark, Roskilde (Denmark). National Lab. for Sustainable Energy; Ekstroem, Karoliina [Fortum Power and Heat, Fortum (Finland); Gwynn, Justin P. [Norwegian Radiation Protection Authority, Tromsoe (Norway). Fram Centre; Magnusson, Sigurdur M. [Icelandic Radiation Safety Authority, Reykjavik (Iceland); Physant, Finn C. [NKS-Sekretariatet, Roskilde (Denmark)

    2012-07-01

    The roots of the current Nordic Nuclear Safety Research (NKS) programme can be traced back to the recommendation by the Nordic Council in the late 1950s for the establishment of joint Nordic committees on the issues of nuclear research and radiation protection. One of these joint Nordic committees, the 'Kontaktorgan', paved the way over its 33 years of existence for the future of Nordic cooperation in the field of nuclear safety, through the formation of Nordic groups on reactor safety, nuclear waste and environmental effects of nuclear power in the late 1960s and early 1970s. With an increased focus on developing nuclear power in the wake of the energy crisis on the 1970s, the NKS was established by the Nordic Council to further develop the previous strands of Nordic cooperation in nuclear safety. NKS started its first programme in 1977, funding a series of four year programmes over the next 24 years covering the areas of reactor safety, waste management, emergency preparedness and radioecology. Initially funded directly from the Nordic Council, ownership of NKS was transferred from the political level to the national competent authorities at the beginning of the 1990s. This organizational and funding model has continued to the present day with additional financial support from a number of co-sponsors in Finland, Norway and Sweden. (orig.)

  14. Safety culture and quality management of Kartini research reactor

    Energy Technology Data Exchange (ETDEWEB)

    Syarip [Yogyakarta Nuclear Research Centre, Yogyakarta (Indonesia); Hauptmanns, Ulrich [Department of Plant Design and Safety, Otto-Von-Guericke-University, Magdeburg (Germany)

    1999-10-01

    The evaluation for assessing the safety culture and quality of safety management of Kartini research reactor is presented. The method is based on the concept of management control of safety (audit) as well as by using the developed method i.e. the questionnaires concerning areas of relevance which have to be answered with value statements. There are seven statements or qualifiers in answering the questions. Since such statements are vague, they are represented by fuzzy numbers. The weaknesses can be identified from the different areas contemplated. The evaluation result show that the quality of safety management of Kartini research reactor is globally rated as 'Average'. The operator behavior in the implementation of 'safety culture' concept is found as a weakness, therefore this area should be improved. (author)

  15. 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

  16. HTGR safety research concerns at NRC

    International Nuclear Information System (INIS)

    Minogue, R.B.

    1982-01-01

    A general discussion of HTGR technical and safety-related problems is given. The broad areas of current research programs specific to the Fort St. Vrain reactor and applicable to HTGR technology are summarized

  17. Assessing flight safety differences between the United States regional and major airlines

    Science.gov (United States)

    Sharp, Broderick H.

    During 2008, the U.S. domestic airline departures exceeded 28,000 flights per day. Thirty-nine or less than 0.2 of 1% of these flights resulted in operational incidents or accidents. However, even a low percentage of airline accidents and incidents continue to cause human suffering and property loss. The charge of this study was the comparison of U.S. major and regional airline safety histories. The study spans safety events from January 1982 through December 2008. In this quantitative analysis, domestic major and regional airlines were statistically tested for their flight safety differences. Four major airlines and thirty-seven regional airlines qualified for the safety study which compared the airline groups' fatal accidents, incidents, non-fatal accidents, pilot errors, and the remaining six safety event probable cause types. The six other probable cause types are mechanical failure, weather, air traffic control, maintenance, other, and unknown causes. The National Transportation Safety Board investigated each airline safety event, and assigned a probable cause to each event. A sample of 500 events was randomly selected from the 1,391 airlines' accident and incident population. The airline groups' safety event probabilities were estimated using the least squares linear regression. A probability significance level of 5% was chosen to conclude the appropriate research question hypothesis. The airline fatal accidents and incidents probability levels were 1.2% and 0.05% respectively. These two research questions did not reach the 5% significance level threshold. Therefore, the airline groups' fatal accidents and non-destructive incidents probabilities favored the airline groups' safety differences hypothesis. The linear progression estimates for the remaining three research questions were 71.5% for non-fatal accidents, 21.8% for the pilot errors, and 7.4% significance level for the six probable causes. These research questions' linear regressions are greater than

  18. Patient safety culture in intensive care units from the perspective of nurses: A cross-sectional study

    Directory of Open Access Journals (Sweden)

    Sedigheh Farzi

    2017-01-01

    Full Text Available Background: One of the goals of nursing is providing safe care, prevention of injury, and health promotion of patients. Patient safety in intensive care units is threatened for various reasons. This study aimed to survey patient safety culture from the perspective of nurses in intensive care units. Materials and Methods: This cross-sectional study was conducted in 2016. Sampling was done using the convenience method. The sample consisted of 367 nurses working in intensive care units of teaching hospitals affiliated to Isfahan University of Medical Sciences. Data collection was performed using a two-part questionnaire that included demographic and hospital survey on Patient Safety Culture (HSOPSC questionnaire. Data analysis was done using descriptive statistics (mean and standard deviation. Results: Among the 12 dimensions of safety culture, the nurses assigned the highest score to “team work within units” (97.3% and “Organizational learning-continuous improvement” (84%. They assigned the least score to “handoffs and transitions”(21.1%, “non-punitive response to errors” (24.7%, “Staffing” (35.6%, “Communication openness” (47.5%, and “Teamwork across units” (49.4%. Conclusions: The patient safety culture dimensions have low levels that require adequate attention and essential measures of health care centers including facilitating teamwork, providing adequate staff, and developing a checklist of handoffs and transitions. Furthermore, to increase reporting error and to promote a patient safety culture in intensive care units, some strategies should be adopted including a system-based approach to deal with the error.

  19. A research agenda on patient safety in primary care. Recommendations by the LINNEAUS collaboration on patient safety in primary care

    Science.gov (United States)

    Verstappen, Wim; Gaal, Sander; Bowie, Paul; Parker, Diane; Lainer, Miriam; Valderas, Jose M.; Wensing, Michel; Esmail, Aneez

    2015-01-01

    ABSTRACT Background: Healthcare can cause avoidable serious harm to patients. Primary care is not an exception, and the relative lack of research in this area lends urgency to a better understanding of patient safety, the future research agenda and the development of primary care oriented safety programmes. Objective: To outline a research agenda for patient safety improvement in primary care in Europe and beyond. Methods: The LINNEAUS collaboration partners analysed existing research on epidemiology and classification of errors, diagnostic and medication errors, safety culture, and learning for and improving patient safety. We discussed ideas for future research in several meetings, workshops and congresses with LINNEAUS collaboration partners, practising GPs, researchers in this field, and policy makers. Results: This paper summarizes and integrates the outcomes of the LINNEAUS collaboration on patient safety in primary care. It proposes a research agenda on improvement strategies for patient safety in primary care. In addition, it provides background information to help to connect research in this field with practicing GPs and other healthcare workers in primary care. Conclusion: Future research studies should target specific primary care domains, using prospective methods and innovative methods such as patient involvement. PMID:26339841

  20. A research agenda on patient safety in primary care. Recommendations by the LINNEAUS collaboration on patient safety in primary care.

    Science.gov (United States)

    Verstappen, Wim; Gaal, Sander; Bowie, Paul; Parker, Diane; Lainer, Miriam; Valderas, Jose M; Wensing, Michel; Esmail, Aneez

    2015-09-01

    Healthcare can cause avoidable serious harm to patients. Primary care is not an exception, and the relative lack of research in this area lends urgency to a better understanding of patient safety, the future research agenda and the development of primary care oriented safety programmes. To outline a research agenda for patient safety improvement in primary care in Europe and beyond. The LINNEAUS collaboration partners analysed existing research on epidemiology and classification of errors, diagnostic and medication errors, safety culture, and learning for and improving patient safety. We discussed ideas for future research in several meetings, workshops and congresses with LINNEAUS collaboration partners, practising GPs, researchers in this field, and policy makers. This paper summarizes and integrates the outcomes of the LINNEAUS collaboration on patient safety in primary care. It proposes a research agenda on improvement strategies for patient safety in primary care. In addition, it provides background information to help to connect research in this field with practicing GPs and other healthcare workers in primary care. Future research studies should target specific primary care domains, using prospective methods and innovative methods such as patient involvement.

  1. Evaluation of the Community's nuclear reactor safety research programme

    International Nuclear Information System (INIS)

    Brandstetter, A.; Goedkoop, J.A.; Jaumotte, A.; Malhouitre, G.; Tomkins, B.; Zorzoli, G.B.

    1986-01-01

    This report describes an evaluation of the 1980-85 CEC reactor safety programme prepared, at the invitation of the Commission, by a panel of six independent experts by means of examining the relevant document and by holding hearings with the responsible CEC staff. It contains the recommendations made by the panel on the following topics: the need for the JRC to continue to make its competence in the reactor safety field available to the Community; the importance of continuity in the JRC and shared-cost action programmes; the difficulty of developing reactor safety research programmes which satisfy the needs of users with diverse needs; the monitoring of the utilization of the research results; the maintenance of the JRC computer codes used by the Member States; the spin-off from research results being made available to other industrial sectors; the continued contact between the JRC researchers and the national experts; the coordination of LWR safety research with that of the Member States; and, the JRC work on fast breeders to be planned with regard to the R and D programmes of the Fast Reactor European Consortium

  2. Patterns of research utilization on patient care units

    Directory of Open Access Journals (Sweden)

    Lander Janice

    2008-06-01

    Full Text Available Abstract Background Organizational context plays a central role in shaping the use of research by healthcare professionals. The largest group of professionals employed in healthcare organizations is nurses, putting them in a position to influence patient and system outcomes significantly. However, investigators have often limited their study on the determinants of research use to individual factors over organizational or contextual factors. Methods The purpose of this study was to examine the determinants of research use among nurses working in acute care hospitals, with an emphasis on identifying contextual determinants of research use. A comparative ethnographic case study design was used to examine seven patient care units (two adult and five pediatric units in four hospitals in two Canadian provinces (Ontario and Alberta. Data were collected over a six-month period by means of quantitative and qualitative approaches using an array of instruments and extensive fieldwork. The patient care unit was the unit of analysis. Drawing on the quantitative data and using correspondence analysis, relationships between various factors were mapped using the coefficient of variation. Results Units with the highest mean research utilization scores clustered together on factors such as nurse critical thinking dispositions, unit culture (as measured by work creativity, work efficiency, questioning behavior, co-worker support, and the importance nurses place on access to continuing education, environmental complexity (as measured by changing patient acuity and re-sequencing of work, and nurses' attitudes towards research. Units with moderate research utilization clustered on organizational support, belief suspension, and intent to use research. Higher nursing workloads and lack of people support clustered more closely to units with the lowest research utilization scores. Conclusion Modifiable characteristics of organizational context at the patient care unit

  3. The experiences of research reactor accident to safety improvement

    International Nuclear Information System (INIS)

    Wiranto, S.

    1999-01-01

    The safety of reactor operation is the main factor in order that the nuclear technology development program can be held according the expected target. Several experience with research reactor incidents must be learned and understood by the nuclear program personnel, especially for operators and supervisors of RSG-GA. Siwabessy. From the incident experience of research reactor in the world, which mentioned in the book 'Experience with research reactor incidents' by IAEA, 1995, was concluded that the main cause of research reactor accidents is understandless about the safety culture by the nuclear installation personnel. With learn, understand and compare between this experiences and the condition of RSG GA Siwabessy is expended the operators and supervisors more attention about the safety culture, so that RSG GA Siwabessy can be operated successfull, safely according the expected target

  4. Research on the improvement of nuclear safety -Thermal hydraulic tests for reactor safety system-

    Energy Technology Data Exchange (ETDEWEB)

    Jung, Moon Kee; Park, Choon Kyung; Yang, Sun Kyoo; Chun, Se Yung; Song, Chul Hwa; Jun, Hyung Kil; Jung, Heung Joon; Won, Soon Yun; Cho, Yung Roh; Min, Kyung Hoh; Jung, Jang Hwan; Jang, Suk Kyoo; Kim, Bok Deuk; Kim, Wooi Kyung; Huh, Jin; Kim, Sook Kwan; Moon, Sang Kee; Lee, Sang Il [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1995-06-01

    The present research aims at the development of the thermal hydraulic verification test technology for the safety system of the conventional and advanced nuclear power plant and the development of the advanced thermal hydraulic measuring techniques. In this research, test facilities simulating the primary coolant system and safety system are being constructed for the design verification tests of the existing and advanced nuclear power plant. 97 figs, 14 tabs, 65 refs. (Author).

  5. Safety infrastructure for countries establishing their first research reactor

    International Nuclear Information System (INIS)

    Abou Yehia, H.; Shokr, A.M.

    2010-01-01

    Establishment of a research reactor is a major project requiring careful planning, preparation, implementation, and investment in time and human resources. The implementation of such a project requires establishment of sustainable infrastructures, including legal and regulatory, safety, technical, and economic. An analysis of the needs for a new research reactor facility should be performed including the development of a utilization plan and evaluation of site availability and suitability. All these elements should be covered by a feasibility study of the project. This paper discusses the elements of such a study with the main focus on the specific activities and steps for developing the necessary safety infrastructure. Progressive involvement of the main organizations in the project, and application of the IAEA Code of Conduct on the Safety of Research Reactors and IAEA Safety Standards in different phases of the project are presented and discussed. (author)

  6. German Light-Water-Reactor Safety-Research Program

    International Nuclear Information System (INIS)

    Seipel, H.G.; Lummerzheim, D.; Rittig, D.

    1977-01-01

    The Light-Water-Reactor Safety-Research Program, which is part of the energy program of the Federal Republic of Germany, is presented in this article. The program, for which the Federal Minister of Research and Technology of the Federal Republic of Germany is responsible, is subdivided into the following four main problem areas, which in turn are subdivided into projects: (1) improvement of the operational safety and reliability of systems and components (projects: quality assurance, component safety); (2) analysis of the consequences of accidents (projects: emergency core cooling, containment, external impacts, pressure-vessel failure, core meltdown); (3) analysis of radiation exposure during operation, accident, and decommissioning (project: fission-product transport and radiation exposure); and (4) analysis of the risk created by the operation of nuclear power plants (project: risk and reliability). Various problems, which are included in the above-mentioned projects, are concurrently studied within the Heiss-Dampf Reaktor experiments

  7. Design of Safety Parameter Monitoring Function in a Research Reactor Facility

    Energy Technology Data Exchange (ETDEWEB)

    Park, Jaekwan; Suh, Yongsuk [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2014-05-15

    The primary purpose of the safety parameter monitoring system (SPDS) is to help operating personnel in the control room make quick assessments of the plant safety status. Thus, the basic function of the SPDS is a provision of a continuous indication of plant parameters or derived variables representative of the safety status of the plant. NUREG-0737 Supplement 1 provides details of the functional criteria for the SPDS, as one of the action plan requirements from TMI accident. The system provides various functions as follows: · Alerting based on safety function decision logics, · Success path analysis to achieve the integrity of the safety functions, · 3 layer display architecture - safety function, success path display for each safety function, system summary and equipment details for each safety function, · Integration with computer-based procedure. According to a Notice of the NSSC No. 2012-31, a research reactor facility generating more than 2 MW of power should also be furnished with the SPDS for emergency preparedness. Generally, a research reactor is a small size facility, and its number of instrumentations is fewer than that of NPPs. In particular, it is actually hard to have various and powerful functions from an economic perspective. Therefore, a safety parameter display system optimized for a research reactor facility must be proposed. This paper provides the requirement analysis results and proposes the design of safety parameter monitoring function for a research reactor. The safety parameter monitoring function supporting control room personnel during emergency conditions should be designed in a research reactor facility. The facility size and number of signals are smaller than that of the power plants. Also, it is actually hard to have various and powerful functions of nuclear power plants from an economic perspective. Thus, a safety parameter display system optimized to a research reactor must be proposed. First, we found important design items

  8. Design of Safety Parameter Monitoring Function in a Research Reactor Facility

    International Nuclear Information System (INIS)

    Park, Jaekwan; Suh, Yongsuk

    2014-01-01

    The primary purpose of the safety parameter monitoring system (SPDS) is to help operating personnel in the control room make quick assessments of the plant safety status. Thus, the basic function of the SPDS is a provision of a continuous indication of plant parameters or derived variables representative of the safety status of the plant. NUREG-0737 Supplement 1 provides details of the functional criteria for the SPDS, as one of the action plan requirements from TMI accident. The system provides various functions as follows: · Alerting based on safety function decision logics, · Success path analysis to achieve the integrity of the safety functions, · 3 layer display architecture - safety function, success path display for each safety function, system summary and equipment details for each safety function, · Integration with computer-based procedure. According to a Notice of the NSSC No. 2012-31, a research reactor facility generating more than 2 MW of power should also be furnished with the SPDS for emergency preparedness. Generally, a research reactor is a small size facility, and its number of instrumentations is fewer than that of NPPs. In particular, it is actually hard to have various and powerful functions from an economic perspective. Therefore, a safety parameter display system optimized for a research reactor facility must be proposed. This paper provides the requirement analysis results and proposes the design of safety parameter monitoring function for a research reactor. The safety parameter monitoring function supporting control room personnel during emergency conditions should be designed in a research reactor facility. The facility size and number of signals are smaller than that of the power plants. Also, it is actually hard to have various and powerful functions of nuclear power plants from an economic perspective. Thus, a safety parameter display system optimized to a research reactor must be proposed. First, we found important design items

  9. Safety Committees for Argentinean Research Reactor - Regulatory Issues

    International Nuclear Information System (INIS)

    Perrin, Carlos D.

    2009-01-01

    In the field of radiological and nuclear safety, the Nuclear Regulatory Authority (ARN) of Argentina controls three research reactors and three critical assemblies, by means of evaluations, audits and inspections, in order to ensure the fulfillment of the requirements established in the Licenses, in the Regulatory Standards and in the Mandatory Documentation in general. From the Nuclear Regulatory Authority's point of view, within the general process of research reactors safety management, the Operational Organization self verification of radiological and nuclear safety plays an outstanding role. In this aspect the ARN has established specific requirements in the Regulatory Standards, in the Operation Licenses and in the Operational Limits and Conditions. These requirements include the figure of different safety committees, which act as reviewers or advisers in diverse situations. This paper describes the main characteristics of the committees, their function, scope and the regulatory documents where the requirements are included. (author)

  10. Nuclear Safety Research and Facilities Department. Annual report 1999

    International Nuclear Information System (INIS)

    Majborn, B.; Damkjaer, A.; Hedemann Jensen, P.; Nielsen, S.P.; Nonboel, E.

    2000-04-01

    The report presents a summary of the work of the Nuclear Safety Research and Facilities Department in 1999. The department's research and development activities were organized in two research programmes: 'Radiation Protection and Reactor Safety' and 'Radioecology and Tracer Studies'. The nuclear facilities operated by the department include the research reactor DR 3, the Isotope Laboratory, the Waste Management Plant, and the educational reactor DR 1. Lists of staff and publications are included together with a summary of the staff's participation in national and international committees. (au)

  11. Nuclear Safety Research and Facilities Department annual report 1997

    International Nuclear Information System (INIS)

    Majborn, B.; Aarkrog, A.; Brodersen, K.

    1998-04-01

    The report presents a summary of the work of the Nuclear Safety Research and Facilities Department in 1997. The department's research and development activities were organized in four research programmes: Reactor Safety, Radiation protection, Radioecology, and Radioanalytical Chemistry. The nuclear facilities operated by the department include the research reactor DR3, the Isotope Laboratory, the Waste Treatment Plant, and the educational reactor DR1. Lists of staff and publications are included together with a summary of the staff's participation in national and international committees. (au)

  12. Nuclear Safety Research and Facilities Department annual report 1998

    International Nuclear Information System (INIS)

    Majborn, B.; Brodersen, K.; Damkjaer, A.; Hedemann Jensen, P.; Nielsen, S.P.; Nonboel, E.

    1999-04-01

    The report present a summary of the work of the Nuclear Safety Research and Facilities Department in 1998. The department's research and development activities were organized in two research programmes: 'Radiation Protection and Reactor Safety' and 'Radioecology and Tracer Studies'. The nuclear facilities operated by the department include the research reactor DR3, the Isotope Laboratory, the Waste Treatment plant, and the educational reactor DR1. Lsits of staff and publications are included together with a summary of the staff's participation in national and international committees. (au)

  13. Health, safety and environmental research program

    International Nuclear Information System (INIS)

    Dinner, P.J.

    1983-01-01

    This report outlines the Health, Safety and Environmental Research Program being undertaken by the CFFTP. The Program objectives, relationship to other CFFTP programs, implementation plans and expected outputs are stated. Opportunities to build upon the knowledge and experience gained in safely managing tritium in the CANDU program, by addressing generic questions pertinent to tritium safety for fusion facilities, are identified. These opportunities exist across a broad spectrum of issues covering the anticipated behaviour of tritium in fusion facilities, the surrounding environment and in man

  14. Proceedings of the international symposium on research reactor safety operations and modifications

    International Nuclear Information System (INIS)

    1990-03-01

    The International Symposium on Research Reactor Safety, Operations and Modifications was organized by the International Atomic Energy Agency in cooperation with Atomic Energy of Canada Limited-Research Company. The main objectives of this Symposium were: (1) to exchange information and to discuss current perspectives and concerns relating to all aspects to research reactor safety, operations, and modifications; and, (2) to present views and to discuss future initiatives and directions for research reactor design, operations, utilization, and safety. The symposium topics included: research reactor programmes and experience; research reactor design safety and analysis; research reactor modifications and decommissioning; research reactor licensing; and new research reactors. These topics were covered during eight oral sessions and three poster sessions. These Proceedings include the full text of the 93 papers presented. The subject of Symposium was quite wide-ranging in that it covered essentially all aspects of research reactor safety, operations, and modifications. This was considered to be appropriate and timely given the 326 research reactors currently in operation in some 56 countries; given the degree of their utilization which ranges from pure and applied research to radioisotopes production to basic training and manpower development; and given that many of these reactors are undergoing extensive modifications, core conversions, power upratings, and are becoming the subject of safety reassessment and regulatory reviews. Although the Symposium covered many topics, the majority of papers and discussions tended to focus mainly on research reactor safety. This was seen as a clear sign of the continuing recognition of the fundamental importance of identifying and addressing, particularly through international cooperation, issues and concerns associated with research reactor safety

  15. Perceived organizational support for safety and employee safety voice: the mediating role of coworker support for safety.

    Science.gov (United States)

    Tucker, Sean; Chmiel, Nik; Turner, Nick; Hershcovis, M Sandy; Stride, Chris B

    2008-10-01

    In the present study, we modeled 2 sources of safety support (perceived organizational support for safety and perceived coworker support for safety) as predictors of employee safety voice, that is, speaking out in an attempt to change unsafe working conditions. Drawing on social exchange and social impact theories, we hypothesized and tested a mediated model predicting employee safety voice using a cross-sectional survey of urban bus drivers (n = 213) in the United Kingdom. Hierarchical regression analysis showed that perceived coworker support for safety fully mediated the relationship between perceived organizational support for safety and employee safety voice. This study adds to the employee voice literature by evaluating the important role that coworkers can play in encouraging others to speak out about safety issues. Implications for research and practice related to change-oriented safety communication are discussed.

  16. Establishing research priorities for patient safety in emergency medicine: a multidisciplinary consensus panel.

    Science.gov (United States)

    Plint, Amy C; Stang, Antonia S; Calder, Lisa A

    2015-01-01

    Patient safety in the context of emergency medicine is a relatively new field of study. To date, no broad research agenda for patient safety in emergency medicine has been established. The objective of this study was to establish patient safety-related research priorities for emergency medicine. These priorities would provide a foundation for high-quality research, important direction to both researchers and health-care funders, and an essential step in improving health-care safety and patient outcomes in the high-risk emergency department (ED) setting. A four-phase consensus procedure with a multidisciplinary expert panel was organized to identify, assess, and agree on research priorities for patient safety in emergency medicine. The 19-member panel consisted of clinicians, administrators, and researchers from adult and pediatric emergency medicine, patient safety, pharmacy, and mental health; as well as representatives from patient safety organizations. In phase 1, we developed an initial list of potential research priorities by electronically surveying a purposeful and convenience sample of patient safety experts, ED clinicians, administrators, and researchers from across North America using contact lists from multiple organizations. We used simple content analysis to remove duplication and categorize the research priorities identified by survey respondents. Our expert panel reached consensus on a final list of research priorities through an in-person meeting (phase 3) and two rounds of a modified Delphi process (phases 2 and 4). After phases 1 and 2, 66 unique research priorities were identified for expert panel review. At the end of phase 4, consensus was reached for 15 research priorities. These priorities represent four themes: (1) methods to identify patient safety issues (five priorities), (2) understanding human and environmental factors related to patient safety (four priorities), (3) the patient perspective (one priority), and (4) interventions for

  17. 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.

  18. NRC safety research in support of regulation

    International Nuclear Information System (INIS)

    1994-06-01

    This report, the ninth 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 FY 1993. A special emphasis on accomplishments in nuclear power plant aging research reflects recognition that number of plants are entering the final portion of their original 40-year operating licenses and that, in addition to current aging effects, a focus on safety considerations for license renewal becomes timely. The primary purpose of performing regulatory research is to develop and provide the Commission and its staff with sound technical bases for regulatory decisions on the safe operation of licensed nuclear reactors and facilities, to find unknown or unexpected safety problems, and to develop data and related information for the purpose of revising the Commission's rules, regulatory guides, or other guidance

  19. Nuclear Safety Research Review Committee

    International Nuclear Information System (INIS)

    Todreas, N.E.

    1990-01-01

    The Nuclear Safety Research Review Committee has had a fundamental difficulty because of the atmosphere that has existed since it was created. It came into existence at a time of decreasing budgets. For any Committee the easiest thing is to tell the Director what additional to do. That does not really help him a lot in this atmosphere of reduced budgets which he reviewed for you on Monday. Concurrently the research arm of Nuclear Regulatory Commission has recognized that the scope of its activity needed to be increased rather than decreased. In the last two-and-a-half-year period, human factors work was reinstated, radiation and health effects investigations were reinvigorated, research in the waste area was given significant acceleration. Further, accident management came into being, and the NRC finally got back into the TMI-2 area. So with all of those activities being added to the program at the same time that the research budget was going down, the situation has become very strained. What that leads to regarding Committee membership is a need for technically competent generalists who will be able to sit as the Division Directors come in, as the contractors come in, and sort the wheat from the chaff. The Committee needs people who are interested in and have a broad perspective on what regulatory needs are and specifically how safety research activities can contribute to them. The author summarizes the history of the Committee, the current status, and plans for the future

  20. Nuclear Safety Research and Facilities Department. Annual report 1999

    Energy Technology Data Exchange (ETDEWEB)

    Majborn, B.; Damkjaer, A.; Hedemann Jensen, P.; Nielsen, S.P.; Nonboel, E. [eds.

    2000-04-01

    The report presents a summary of the work of the Nuclear Safety Research and Facilities Department in 1999. The department's research and development activities were organized in two research programmes: 'Radiation Protection and Reactor Safety' and 'Radioecology and Tracer Studies'. The nuclear facilities operated by the department include the research reactor DR 3, the Isotope Laboratory, the Waste Management Plant, and the educational reactor DR 1. Lists of staff and publications are included together with a summary of the staff's participation in national and international committees. (au)

  1. Nuclear Safety Research and Facilities Department annual report 1999

    DEFF Research Database (Denmark)

    Majborn, B.; Damkjær, A.; Jensen, Per Hedemann

    2000-01-01

    The report presents a summary of the work of the Nuclear Safety Research and Facilities Department in 1999. The department´s research and development activities were organized in two research programmes: "Radiation Protection and Reactor Safety" and"Radioecology and Tracer Studies". The nuclear...... facilities operated by the department include the research reactor DR 3, the Isotope Laboratory, the Waste Management Plant, and the educational reactor DR 1. Lists of staff and publications are includedtogether with a summary of the staff´s participation in national and international committees....

  2. Nuclear Safety Research and Facilities Department annual report 1997

    Energy Technology Data Exchange (ETDEWEB)

    Majborn, B.; Aarkrog, A.; Brodersen, K. [and others

    1998-04-01

    The report presents a summary of the work of the Nuclear Safety Research and Facilities Department in 1997. The department`s research and development activities were organized in four research programmes: Reactor Safety, Radiation protection, Radioecology, and Radioanalytical Chemistry. The nuclear facilities operated by the department include the research reactor DR3, the Isotope Laboratory, the Waste Treatment Plant, and the educational reactor DR1. Lists of staff and publications are included together with a summary of the staff`s participation in national and international committees. (au) 11 tabs., 39 ills.; 74 refs.

  3. Nuclear Safety Research and Facilities Department annual report 1998

    Energy Technology Data Exchange (ETDEWEB)

    Majborn, B.; Brodersen, K.; Damkjaer, A.; Hedemann Jensen, P.; Nielsen, S.P.; Nonboel, E

    1999-04-01

    The report present a summary of the work of the Nuclear Safety Research and Facilities Department in 1998. The department`s research and development activities were organized in two research programmes: `Radiation Protection and Reactor Safety` and `Radioecology and Tracer Studies`. The nuclear facilities operated by the department include the research reactor DR3, the Isotope Laboratory, the Waste Treatment plant, and the educational reactor DR1. Lsits of staff and publications are included together with a summary of the staff`s participation in national and international committees. (au)

  4. Nuclear Safety Research and Facilities department annual report 1996

    International Nuclear Information System (INIS)

    Majborn, B.; Brodersen, K.; Damkjaer, A.; Floto, H.; Heydorn, K.; Oelgaard, P.L.

    1997-04-01

    The report presents a summary of the work of the Nuclear Safety Research and Facilities Department in 1996. The Department's research and development activities are organized in three research programmes: Radiation Protection, Reactor Safety, and Radioanalytical Chemistry. The nuclear facilities operated by the department include the Research Reactor DR3, the Isotope Laboratory, the Waste Treatment Plant, and the Educational Reactor DR1. Lists of staff and publications are included together with a summary of the staff's participation in national and international committees. (au) 2 tabs., 28 ills

  5. MAPLE research reactor safety uncertainty assessment methodology

    International Nuclear Information System (INIS)

    Sills, H.E.; Duffey, R.B.; Andres, T.H.

    1999-01-01

    The MAPLE (multipurpose Applied Physics Lattice Experiment) reactor is a low pressure, low temperature, open-tank-in pool type research reactor that operates at a power level of 5 to 35 MW. MAPLE is designed for ease of operation, maintenance, and to meet today's most demanding requirements for safety and licensing. The emphasis is on the use of passive safety systems and environmentally qualified components. Key safety features include two independent and diverse shutdown systems, two parallel and independent cooling loops, fail safe operation, and a building design that incorporates the concepts of primary containment supported by secondary confinement

  6. HTGR safety research program. Progress report, April--June 1975

    International Nuclear Information System (INIS)

    Kirk, W.L.

    1975-09-01

    Progress in HTGR safety research is reported under the following headings: fission product technology; primary coolant impurities; structural investigation; safety instrumentation and control systems; phenomena modeling and systems analysis. (JWR)

  7. Researching safety culture: deliberative dialogue with a restorative lens.

    Science.gov (United States)

    Lorenzini, Elisiane; Oelke, Nelly D; Marck, Patricia Beryl; Dall'agnol, Clarice Maria

    2017-10-01

    Safety culture is a key component of patient safety. Many patient safety strategies in health care have been adapted from high-reliability organizations (HRO) such as aviation. However, to date, attempts to transform the cultures of health care settings through HRO approaches have had mixed results. We propose a methodological approach for safety culture research, which integrates the theory and practice of restoration science with the principles and methods of deliberative dialogue to support active engagement in critical reflection and collective debate. Our aim is to describe how these two innovative approaches in health services research can be used together to provide a comprehensive effective method to study and implement change in safety culture. Restorative research in health care integrates socio-ecological theory of complex adaptive systems concepts with collaborative, place-sensitive study of local practice contexts. Deliberative dialogue brings together all stakeholders to collectively develop solutions on an issue to facilitate change. Together these approaches can be used to actively engage people in the study of safety culture to gain a better understanding of its elements. More importantly, we argue that the synergistic use of these approaches offers enhanced potential to move health care professionals towards actionable strategies to improve patient safety within today's complex health care systems. © The Author 2017. Published by Oxford University Press in association with the International Society for Quality in Health Care. All rights reserved. For permissions, please e-mail: journals.permissions@oup.com.

  8. Handbook of nuclear power plant seismic fragilities, Seismic Safety Margins Research Program

    International Nuclear Information System (INIS)

    Cover, L.E.; Bohn, M.P.; Campbell, R.D.; Wesley, D.A.

    1983-12-01

    The Seismic Safety Margins Research Program (SSMRP) has a gola to develop a complete fully coupled analysis procedure (including methods and computer codes) for estimating the risk of an earthquake-induced radioactive release from a commercial nuclear power plant. As part of this program, calculations of the seismic risk from a typical commercial nuclear reactor were made. These calculations required a knowledge of the probability of failure (fragility) of safety-related components in the reactor system which actively participate in the hypothesized accident scenarios. This report describes the development of the required fragility relations and the data sources and data reduction techniques upon which they are based. Both building and component fragilities are covered. The building fragilities are for the Zion Unit 1 reactor which was the specific plant used for development of methodology in the program. Some of the component fragilities are site-specific also, but most would be usable for other sites as well

  9. 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)

  10. Integrated safety assessment report: Integrated Safety Assessment Program: Millstone Nuclear Power Station, Unit 1 (Docket No. 50-245): Draft report

    International Nuclear Information System (INIS)

    1987-04-01

    The Integrated Safety Assessment Program (ISAP) was initiated in November 1984, by the US Nuclear Regulatory Commission to conduct integrated assessments for operating nuclear power reactors. The integrated assessment is conducted in a plant-specific basis to evaluate all licensing actions, licensee initiated plant improvements and selected unresolved generic/safety issues to establish implementation schedules for each item. In addition, procedures will be established to allow for a periodic updating of the schedules to account for licensing issues that arise in the future. This report documents the review of Millstone Nuclear Power Station, Unit No. 1, operated by Northeast Nuclear Energy Company (located in Waterford, Connecticut). Millstone Nuclear Power Station, Unit No. 1, is one of two plants being reviewed under the pilot program for ISAP. This report indicates how 85 topics selected for review were addressed. This report presents the staff's recommendations regarding the corrective actions to resolve the 85 topics and other actions to enhance plant safety. The report is being issued in draft form to obtain comments from the licensee, nuclear safety experts, and the Advisory Committee for Reactor Safeguards (ACRS). Once those comments have been resolved, the staff will present its positions, along with a long-term implementation schedule from the licensee, in the final version of this report

  11. Using the Human Systems Simulation Laboratory at Idaho National Laboratory for Safety Focused Research

    Energy Technology Data Exchange (ETDEWEB)

    Joe, Jeffrey .C; Boring, Ronald L.

    2016-07-01

    Under the United States (U.S.) Department of Energy (DOE) Light Water Reactor Sustainability (LWRS) program, researchers at Idaho National Laboratory (INL) have been using the Human Systems Simulation Laboratory (HSSL) to conduct critical safety focused Human Factors research and development (R&D) for the nuclear industry. The LWRS program has the overall objective to develop the scientific basis to extend existing nuclear power plant (NPP) operating life beyond the current 60-year licensing period and to ensure their long-term reliability, productivity, safety, and security. One focus area for LWRS is the NPP main control room (MCR), because many of the instrumentation and control (I&C) system technologies installed in the MCR, while highly reliable and safe, are now difficult to replace and are therefore limiting the operating life of the NPP. This paper describes how INL researchers use the HSSL to conduct Human Factors R&D on modernizing or upgrading these I&C systems in a step-wise manner, and how the HSSL has addressed a significant gap in how to upgrade systems and technologies that are built to last, and therefore require careful integration of analog and new advanced digital technologies.

  12. Radiological safety design considerations for fusion research experiments

    International Nuclear Information System (INIS)

    Crase, K.W.; Singh, M.S.

    1979-01-01

    A wide variety of fusion research experiments are in the planning or construction stages. Two such experiments, the Nova Laser Fusion Facility and the Mirror Fusion Test Facility (MFTF), are currently under construction at Lawrence Livermore Laboratory. Although the plasma chamber vault for MFTF and the Nova target room will have thick concrete walls and roofs, the radiation safety problems are made complex by the numerous requirements for shield wall penetrations. This paper addresses radiation safety considerations for the MFTF and Nova experiments, and the need for integrated safety considerations and safety technology development during the planning stages of fusion experiments

  13. Safety balance: Analysis of safety systems

    International Nuclear Information System (INIS)

    Delage, M.; Giroux, C.

    1990-12-01

    Safety analysis, and particularly analysis of exploitation of NPPs is constantly affected by EDF and by the safety authorities and their methodologies. Periodic safety reports ensure that important issues are not missed on daily basis, that incidents are identified and that relevant actions are undertaken. French safety analysis method consists of three principal steps. First type of safety balance is analyzed at the normal start-up phase for each unit including the final safety report. This enables analysis of behaviour of units ten years after their licensing. Second type is periodic operational safety analysis performed during a few years. Finally, the third step consists of safety analysis of the oldest units with the aim to improve the safety standards. The three steps of safety analysis are described in this presentation in detail with the aim to present the objectives and principles. Examples of most recent exercises are included in order to illustrate the importance of such analyses

  14. Sodium Fast Reactor Safety and Licensing Research Plan

    International Nuclear Information System (INIS)

    Denman, Matthew; Lachance, Jeff; Sofu, Tanju; Wigeland, Roald; Flanagan, George; Bari, Robert

    2013-01-01

    Conclusions: The Sodium Fast Reactor Safety and Licensing Research Plan reports conclude a multi-year expert elicitation process. All information included in the studies are publicly available and the reports are UUR. These reports are intended to guide SFR researchers in the safety and licensing arena to important and outstanding issues Two (and a half) projects have been funded based on the recommendations in this report: • Modernization of SAS4A; • Incorporation of Contain/LMR with MELCOR; • (Data recovery at INL and PNNL)

  15. Seismic safety margins research program. Phase I final report - Overview

    International Nuclear Information System (INIS)

    Smith, P.D.; Dong, R.G.; Bernreuter, D.L.; Bohn, M.P.; Chuang, T.Y.; Cummings, G.E.; Johnson, J.J.; Mensing, R.W.; Wells, J.E.

    1981-04-01

    The Seismic Safety Margins Research Program (SSMRP) is a multiyear, multiphase program whose overall objective is to develop improved methods for seismic safety assessments of nuclear power plants, using a probabilistic computational procedure. The program is being carried out at the Lawrence Livermore National Laboratory and is sponsored by the U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research. Phase I of the SSMRP was successfully completed in January 1981: A probabilistic computational procedure for the seismic risk assessment of nuclear power plants has been developed and demonstrated. The methodology is implemented by three computer programs: HAZARD, which assesses the seismic hazard at a given site, SMACS, which computes in-structure and subsystem seismic responses, and SEISIM, which calculates system failure probabilities and radioactive release probabilities, given (1) the response results of SMACS, (2) a set of event trees, (3) a family of fault trees, (4) a set of structural and component fragility descriptions, and (5) a curve describing the local seismic hazard. The practicality of this methodology was demonstrated by computing preliminary release probabilities for Unit 1 of the Zion Nuclear Power Plant north of Chicago, Illinois. Studies have begun aimed at quantifying the sources of uncertainty in these computations. Numerous side studies were undertaken to examine modeling alternatives, sources of error, and available analysis techniques. Extensive sets of data were amassed and evaluated as part of projects to establish seismic input parameters and to produce the fragility curves. (author)

  16. 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.)

  17. Collection and accumulation of seismic safety research findings, and considerations for information dissemination

    International Nuclear Information System (INIS)

    2013-01-01

    Seismic Safety Division of JNES is collecting and analyzing the findings of seismic safety research, and is developing a system to organize and disseminate the information internally and internationally. These tasks have been conducted in response to the lessons learned from Fukushima Daiichi NPP accident. The overview of the tasks is as follows; 1) Collection of the knowledge and findings from seismic safety research. JNES collects information on seismic safety researches including the 2011 off the Pacific coast of Tohoku Earthquake. The information is analyzed whether it is important for regulation to increase seismic safety of NPP. 2) Constructing database of seismic safety research. JNES collects information based on documents published by committee and constructs database of active faults around NPP sites in order to incorporate in the seismic safety review. 3) Dissemination of information related to seismic safety. JNES disseminates outcomes of own researches internally and internationally. (author)

  18. Collection and accumulation of seismic safety research findings, and considerations for information dissemination

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2013-08-15

    Seismic Safety Division of JNES is collecting and analyzing the findings of seismic safety research, and is developing a system to organize and disseminate the information internally and internationally. These tasks have been conducted in response to the lessons learned from Fukushima Daiichi NPP accident. The overview of the tasks is as follows; 1) Collection of the knowledge and findings from seismic safety research. JNES collects information on seismic safety researches including the 2011 off the Pacific coast of Tohoku Earthquake. The information is analyzed whether it is important for regulation to increase seismic safety of NPP. 2) Constructing database of seismic safety research. JNES collects information based on documents published by committee and constructs database of active faults around NPP sites in order to incorporate in the seismic safety review. 3) Dissemination of information related to seismic safety. JNES disseminates outcomes of own researches internally and internationally. (author)

  19. Safety research programs sponsored by Office of Nuclear Regulatory Research

    International Nuclear Information System (INIS)

    Weiss, A.J.; Azarm, A.; Baum, J.W.

    1989-07-01

    This progress report describes current activities and technical progress in the programs at Brookhaven National Laboratory sponsored by the Division of Regulatory Applications, Division of Engineering, Division of Safety Issue Resolution, and Division of Systems Research of the US Nuclear Regulatory Commission, Office of Nuclear Regulatory Research following the reorganization in July 1988. The previous reports have covered the period October 1, 1976 through September 30, 1988

  20. Firefighters United for Safety, Ethics, and Ecology (FUSEE): Torchbearers for a new fire management paradigm

    Science.gov (United States)

    Timothy Ingalsbee; Joseph Fox; Patrick Withen

    2007-01-01

    Firefighters United for Safety, Ethics, and Ecology (FUSEE) is a nonprofit organization promoting safe, ethical, ecological wildland fire management. FUSEE believes firefighter and community safety are ultimately interdependent with ethical public service, wildlands protection, and ecological restoration of fire-adapted ecosystems. Our members include current, former,...

  1. Two sides of the safety coin?: How patient engagement and safety climate jointly affect error occurrence in hospital units.

    Science.gov (United States)

    Schiffinger, Michael; Latzke, Markus; Steyrer, Johannes

    2016-01-01

    Safety climate (SC) and more recently patient engagement (PE) have been identified as potential determinants of patient safety, but conceptual and empirical studies combining both are lacking. On the basis of extant theories and concepts in safety research, this study investigates the effect of PE in conjunction with SC on perceived error occurrence (pEO) in hospitals, controlling for various staff-, patient-, and hospital-related variables as well as the amount of stress and (lack of) organizational support experienced by staff. Besides the main effects of PE and SC on error occurrence, their interaction is examined, too. In 66 hospital units, 4,345 patients assessed the degree of PE, and 811 staff assessed SC and pEO. PE was measured with a new instrument, capturing its core elements according to a recent literature review: Information Provision (both active and passive) and Activation and Collaboration. SC and pEO were measured with validated German-language questionnaires. Besides standard regression and correlational analyses, partial least squares analysis was employed to model the main and interaction effects of PE and SC on pEO, also controlling for stress and (lack of) support perceived by staff, various staff and patient attributes, and potential single-source bias. Both PE and SC are associated with lower pEO, to a similar extent. The joint effect of these predictors suggests a substitution rather than mutually reinforcing interaction. Accounting for control variables and/or potential single-source bias slightly attenuates some effects without altering the results. Ignoring PE potentially amounts to forgoing a potential source of additional safety. On the other hand, despite the abovementioned substitution effect and conjectures of SC being inert, PE should not be considered as a replacement for SC.

  2. Safety Evaluation Report on Tennessee Valley Authority: Browns Ferry Nuclear Performance Plan: Browns Ferry Unit 2 restart

    International Nuclear Information System (INIS)

    1989-04-01

    This safety evaluation report (SER) on the information submitted by the Tennessee Valley Authority (TVA) in its Nuclear Performance Plan, through Revision 2, for the Browns Ferry Nuclear Power Station and in supporting documents has been prepared by the US Nuclear Regulatory Commission staff. The plan addresses the plant-specific concerns requiring resolution before startup of Unit 2. The staff will inspect implementation of those programs. Where systems are common to Units 1 and 2 or to Units 2 and 3, the staff safety evaluations of those systems are included herein. 3 refs

  3. Research at the Dairy and Functional Foods Research Unit

    Science.gov (United States)

    Dr. Peggy Tomasula is Research Leader of the Dairy and Functional Foods Research Unit (DFFRU), ARS, USDA, Wyndmoor, PA, a group that includes 11 Research Scientists, 4 of whom are Lead Scientists (LS), 13 support scientists, and 3 Retired Collaborators. The mission of the DFFRU is to solve critical ...

  4. The Uranium Chemistry Research Unit

    International Nuclear Information System (INIS)

    Anon.

    1983-01-01

    The article discusses the research work done at the Uranium Chemistry Research Unit of the University of Port Elizabeth. The initial research programme dealt with fundamental aspects of uranium chemistry. New uranium compounds were synthesized and their chemical properties were studied. Research was also done to assist the mining industry, as well as on nuclear medicine. Special mentioning is made of the use of technetium for medical diagnosis and therapy

  5. Safety classification of systems, structures, and components for pool-type research reactors

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Tae Ryong [KEPCO International Nuclear Graduate School, Ulsan (Korea, Republic of)

    2016-08-15

    Structures, systems, and components (SSCs) important to safety of nuclear facilities shall be designed, fabricated, erected, and tested to quality standards commensurate with the importance of the safety functions. Although SSC classification guidelines for nuclear power plants have been well established and applied, those for research reactors have been only recently established by the International Atomic Energy Agency (IAEA). Korea has operated a pool-type research reactor (the High Flux Advanced Neutron Application Reactor) and has recently exported another pool-type reactor (Jordan Research and Training Reactor), which is being built in Jordan. Korea also has a plan to build one more pool-type reactor, the Kijang Research Reactor, in Kijang, Busan. The safety classification of SSCs for pool-type research reactors is proposed in this paper based on the IAEA methodology. The proposal recommends that the SSCs of pool-type research reactors be categorized and classified on basis of their safety functions and safety significance. Because the SSCs in pool-type research reactors are not the pressure-retaining components, codes and standards for design of the SSCs following the safety classification can be selected in a graded approach.

  6. Yearly program of safety research for nuclear facilities and others

    International Nuclear Information System (INIS)

    1987-01-01

    The development of FBRs in Japan has steadily progressed, and subsequently to the experimental reactor 'Joyo' and the prototype reactor 'Monju', by promoting the construction of a demonstration reactor, the stage of verifying and acquiring skill of the electricity generation plant technology of practical scale, improving the performance and establishing the economical efficiency is about to begin. The development of FBRs in Japan has been advanced independently as a national project, and the method of preventing accidents in the actual reactors has been thoroughly taken. 'On the way of thinking in the safety evaluation of FBRs' was decided by the Nuclear Safety Commission. When the safety research from 1987 is systematized, as the constituents of safety logic, the way of thinking of the defense in depth, the way of thinking of the classification according to importance, the way of thinking of multilayer barriers against radioactive substances, and the way of thinking on severe accidents were investigated. The research concerning the decision of safety design and evaluation policy, and the safety research regarding accident prevention and relaxation, accident evaluation and severe accidents are reported. (Kako, I.)

  7. 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.)

  8. TU-EF-BRD-01: Topics in Quality and Safety Research and Level of Evidence

    Energy Technology Data Exchange (ETDEWEB)

    Pawlicki, T. [UCSD Medical Center (United States)

    2015-06-15

    Research related to quality and safety has been a staple of medical physics academic activities for a long time. From very early on, medical physicists have developed new radiation measurement equipment and analysis techniques, created ever increasingly accurate dose calculation models, and have vastly improved imaging, planning, and delivery techniques. These and other areas of interest have improved the quality and safety of radiotherapy for our patients. With the advent of TG-100, quality and safety is an area that will garner even more research interest in the future. As medical physicists pursue quality and safety research in greater numbers, it is worthwhile to consider what actually constitutes research on quality and safety. For example, should the development of algorithms for real-time EPID-based in-vivo dosimetry be defined as “quality and safety” research? How about the clinical implementation of such as system? Surely the application of failure modes and effects analysis to a clinical process would be considered quality and safety research, but is this type of research that should be included in the medical physics peer-reviewed literature? The answers to such questions are of critical importance to set researchers in a direction that will provide the greatest benefit to our field and the patients we serve. The purpose of this symposium is to consider what constitutes research in the arena of quality and safety and differentiate it from other research directions. The key distinction here is developing the tool itself (e.g. algorithms for EPID dosimetry) vs. studying the impact of the tool with some quantitative metric. Only the latter would I call quality and safety research. Issues of ‘basic’ versus ‘applied’ quality and safety research will be covered as well as how the research results should be structured to provide increasing levels of support that a quality and safety intervention is effective and sustainable. Examples from existing

  9. TU-EF-BRD-04: Summing It Up: The Future of Quality and Safety Research

    Energy Technology Data Exchange (ETDEWEB)

    Ford, E. [University of Washington (United States)

    2015-06-15

    Research related to quality and safety has been a staple of medical physics academic activities for a long time. From very early on, medical physicists have developed new radiation measurement equipment and analysis techniques, created ever increasingly accurate dose calculation models, and have vastly improved imaging, planning, and delivery techniques. These and other areas of interest have improved the quality and safety of radiotherapy for our patients. With the advent of TG-100, quality and safety is an area that will garner even more research interest in the future. As medical physicists pursue quality and safety research in greater numbers, it is worthwhile to consider what actually constitutes research on quality and safety. For example, should the development of algorithms for real-time EPID-based in-vivo dosimetry be defined as “quality and safety” research? How about the clinical implementation of such as system? Surely the application of failure modes and effects analysis to a clinical process would be considered quality and safety research, but is this type of research that should be included in the medical physics peer-reviewed literature? The answers to such questions are of critical importance to set researchers in a direction that will provide the greatest benefit to our field and the patients we serve. The purpose of this symposium is to consider what constitutes research in the arena of quality and safety and differentiate it from other research directions. The key distinction here is developing the tool itself (e.g. algorithms for EPID dosimetry) vs. studying the impact of the tool with some quantitative metric. Only the latter would I call quality and safety research. Issues of ‘basic’ versus ‘applied’ quality and safety research will be covered as well as how the research results should be structured to provide increasing levels of support that a quality and safety intervention is effective and sustainable. Examples from existing

  10. TU-EF-BRD-04: Summing It Up: The Future of Quality and Safety Research

    International Nuclear Information System (INIS)

    Ford, E.

    2015-01-01

    Research related to quality and safety has been a staple of medical physics academic activities for a long time. From very early on, medical physicists have developed new radiation measurement equipment and analysis techniques, created ever increasingly accurate dose calculation models, and have vastly improved imaging, planning, and delivery techniques. These and other areas of interest have improved the quality and safety of radiotherapy for our patients. With the advent of TG-100, quality and safety is an area that will garner even more research interest in the future. As medical physicists pursue quality and safety research in greater numbers, it is worthwhile to consider what actually constitutes research on quality and safety. For example, should the development of algorithms for real-time EPID-based in-vivo dosimetry be defined as “quality and safety” research? How about the clinical implementation of such as system? Surely the application of failure modes and effects analysis to a clinical process would be considered quality and safety research, but is this type of research that should be included in the medical physics peer-reviewed literature? The answers to such questions are of critical importance to set researchers in a direction that will provide the greatest benefit to our field and the patients we serve. The purpose of this symposium is to consider what constitutes research in the arena of quality and safety and differentiate it from other research directions. The key distinction here is developing the tool itself (e.g. algorithms for EPID dosimetry) vs. studying the impact of the tool with some quantitative metric. Only the latter would I call quality and safety research. Issues of ‘basic’ versus ‘applied’ quality and safety research will be covered as well as how the research results should be structured to provide increasing levels of support that a quality and safety intervention is effective and sustainable. Examples from existing

  11. Health and safety at the Whiteshell Nuclear Research Establishment

    International Nuclear Information System (INIS)

    LeNeveu, D.M.

    1982-04-01

    This report outlines the health and safety program at the Whiteshell Nuclear Research Establishment. It describes the procedures in place to ensure that a high standard of conventional industrial and radiation safety is maintained in the workplace

  12. Mapping a Research Agenda for Home Care Safety: Perspectives from Researchers, Providers, and Decision Makers

    Science.gov (United States)

    Macdonald, Marilyn; Lang, Ariella; MacDonald, Jo-Anne

    2011-01-01

    The purpose of this qualitative interpretive design was to explore the perspectives of researchers, health care providers, policy makers, and decision makers on key risks, concerns, and emerging issues related to home care safety that would inform a line of research inquiry. Defining safety specifically in this home care context has yet to be…

  13. Machine-related injuries in the US mining industry and priorities for safety research.

    Science.gov (United States)

    Ruff, Todd; Coleman, Patrick; Martini, Laura

    2011-03-01

    Researchers at the National Institute for Occupational Safety and Health studied mining accidents that involved a worker entangled in, struck by, or in contact with machinery or equipment in motion. The motivation for this study came from the large number of severe accidents, i.e. accidents resulting in a fatality or permanent disability, that are occurring despite available interventions. Accident descriptions were taken from an accident database maintained by the United States Department of Labor, Mine Safety and Health Administration, and 562 accidents that occurred during 2000-2007 fit the search criteria. Machine-related accidents accounted for 41% of all severe accidents in the mining industry during this period. Machinery most often involved in these accidents included conveyors, rock bolting machines, milling machines and haulage equipment such as trucks and loaders. The most common activities associated with these accidents were operation of the machine and maintenance and repair. The current methods to safeguard workers near machinery include mechanical guarding around moving components, lockout/tagout of machine power during maintenance and backup alarms for mobile equipment. To decrease accidents further, researchers recommend additional efforts in the development of new control technologies, training materials and dissemination of information on best practices.

  14. Application of Code Of Conduct on the Safety of Research Reactor (RTP)

    International Nuclear Information System (INIS)

    Ligam, A.S.; Ahmad Nabil Abd Rahim; Zarina Masood

    2014-01-01

    The implementation and the practices of the effective safety system at research reactors are important to ensure that the worker, public and environment do not receive any abnormal causes. Many international safety related support agencies for research reactor such as International Atomic Energy Agency (IAEA) providing guidelines that can be applied to enhance and strengthen the enforcement of safety namely Code of Conduct on the Safety of Research Reactor (IAEA/CODEOC/RR/2006). The excellent safety management, reliability, and maintainability of RTP reactor structures, coupled with personnel numerous lessons and experiences learned, Reactor TRIGA PUSPATI research reactor providing Nuclear Malaysia personnel and visitor the very safe working and visiting environment. This paper will discuss the status, practices and improvement strategies over the past few years. (author)

  15. TRIGA Research Reactor Conversion to LEU and Modernization of Safety Related Systems

    Energy Technology Data Exchange (ETDEWEB)

    Sanda, R. M. [Institute for Nuclear Research Piteşti (SCN-Piteşti), Piteşti (Romania)

    2014-08-15

    The USA and IAEA proposed an international programme to reduce the enrichment of uranium in research reactors by converting nuclear fuel containing HEU into fuel containing 20% enriched uranium. The Government of Romania joined the programme and actively supported political, scientific, technical and economic actions that led to the conversion of the active area of the 14 MW TRIGA reactor at the Institute for Nuclear Research in Piteşti in May 2006. This confirmed the continuity of the Romanian Government’s non-proliferation policy and their active support of international cooperation. Conversion of the Piteşti research reactor was made possible by completion of milestones in the Research Agreement for Reactor Conversion, a contract signed with the US Department of Energy and Argonne National Laboratory. This agreement provided scientific and technical support and the possibility of delivery of all HEU TRIGA fuel to the United States. Additionally, about 65% of the fresh LEU fuel needed to start the conversion was delivered in the period 1992–1994. Furthermore, conversion was promoted through IAEA Technical Cooperation project ROM/4/024 project funded primarily by the United States that supported technical and scientific efforts and the delivery of the remaining required LEU nuclear fuel to complete the conversion. Nuclear fuel to complete the conversion was made by the French company CERCA with a tripartite contract among the IAEA, CERCA and Romania. The contract was funded by the US Department of Energy with a voluntary contribution by the Romanian Government. The contract stipulated manufacturing and delivery of LEU fuel by CERCA with compliance measures for quality, delivery schedule and safety requirements set by IAEA standards and Romanian legislation. The project was supported by the ongoing technical cooperation, safeguards, legal and procurement assistance of the IAEA, in particular its Department of Nuclear Safety. For Romanian research, the

  16. Licensing decisions and safety research related to LMFBR accidents

    International Nuclear Information System (INIS)

    Denise, R.P.; Speis, T.P.; Kelber, C.N.; Curtis, R.T.

    1977-01-01

    The licensing approach which ensures adequate protection of the public health and safety against serious accidents is described. This paper describes the role of core melt and core disruptive accidents in the design, safety research, and licensing processes, using the Clinch River Breeder Reactor (CRBR) as a focal point. Major design attention is placed on the prevention of these accidents so that the probability of core melt accidents is reduced to a sufficiently low level that they are not treated as design basis accidents. Additional requirements are placed upon the design to further reduce residual risk. This licensing process is supported by a confirmatory research program designed to provide an independent basis for licensing judgements. It has as a goal the resolution of generic safety issues prior to the establishment of a commercial LMFBR industry. The program includes accident analysis, experiments in materials interactions, aerosol transport and system integrity and planning for new safety test facilities. The problems are approached in a multi-disciplinary functional manner that identifies key safety issues and centralizes efforts to resolve them. The near term objectives of the program support the licensing of the Clinch River Breeder Reactor (CRBR) and the proposed Prototype Large Breeder Reactor (PLBR). The long term objectives of the program support the licensing of commercial LMFBRs during the late 1980's and beyond. This safety research is designed to provide an independent basis for the licensing judgements which must be made by the Nuclear Regulatory Commission

  17. Decommissioning of Medical, Industrial and Research Facilities. Safety Guide

    International Nuclear Information System (INIS)

    2010-01-01

    Radioactive waste is produced in the generation of nuclear power and the use of radioactive materials in industry, research and medicine. The importance of the safe management of radioactive waste for the protection of human health and the environment has long been recognized, and considerable experience has been gained in this field. The IAEA's Radioactive Waste Safety Standards Programme aimed at establishing a coherent and comprehensive set of principles and requirements for the safe management of waste and formulating the guidelines necessary for their application. This is accomplished within the IAEA Safety Standards Series in an internally consistent set of publications that reflect an international consensus. The publications will provide Member States with a comprehensive series of internationally agreed publications to assist in the derivation of, and to complement, national criteria, standards and practices. The Safety Standards Series consists of three categories of publications: Safety Fundamentals, Safety Requirements and Safety Guides. With respect to the Radioactive Waste Safety Standards Programme, the set of publications is currently undergoing review to ensure a harmonized approach throughout the Safety Standards Series. This Safety Guide addresses the subject of decommissioning of medical, industrial and research facilities where radioactive materials and sources are produced, received, used and stored. It is intended to provide guidance to national authorities and operating organizations, particularly to those in developing countries (as such facilities are predominant in these countries), for the planning and safe management of the decommissioning of such facilities. The Safety Guide has been prepared through a series of Consultants meetings and a Technical Committee meeting

  18. Decommissioning of medical, industrial and research facilities. Safety guide

    International Nuclear Information System (INIS)

    2005-01-01

    Radioactive waste is produced in the generation of nuclear power and the use of radioactive materials in industry, research and medicine. The importance of the safe management of radioactive waste for the protection of human health and the environment has long been recognized, and considerable experience has been gained in this field. The IAEA's Radioactive Waste Safety Standards Programme aimed at establishing a coherent and comprehensive set of principles and requirements for the safe management of waste and formulating the guidelines necessary for their application. This is accomplished within the IAEA Safety Standards Series in an internally consistent set of publications that reflect an international consensus. The publications will provide Member States with a comprehensive series of internationally agreed publications to assist in the derivation of, and to complement, national criteria, standards and practices. The Safety Standards Series consists of three categories of publications: Safety Fundamentals, Safety Requirements and Safety Guides. With respect to the Radioactive Waste Safety Standards Programme, the set of publications is currently undergoing review to ensure a harmonized approach throughout the Safety Standards Series. This Safety Guide addresses the subject of decommissioning of medical, industrial and research facilities where radioactive materials and sources are produced, received, used and stored. It is intended to provide guidance to national authorities and operating organizations, particularly to those in developing countries (as such facilities are predominant in these countries), for the planning and safe management of the decommissioning of such facilities. The Safety Guide has been prepared through a series of Consultants meetings and a Technical Committee meeting

  19. Safety system upgrades to a research reactor: A regulatory perspective

    International Nuclear Information System (INIS)

    Lamarre, G.B.; Martin, W.G.

    2003-01-01

    The NRU (National Research Universal) reactor, located at the Chalk River Laboratories of Atomic Energy of Canada Limited (AECL), first achieved criticality November 3, 1957. AECL continues to operate NRU for research to support safety and reliability studies for CANDU reactors and as a major supplier of medical radioisotopes. Following a detailed systematic review and assessment of NRU's design and the condition of its primary systems, AECL formally notified the Canadian Nuclear Safety Commission's (CNSC) predecessor - the Atomic Energy Control Board - in 1992 of its intention to upgrade NRU's safety systems. AECL proposed seven major upgrades to provide improvements in shutdown capability, heat removal, confinement, and reactor monitoring, particularly during and after a seismic event. From a CNSC perspective, these upgrades were necessary to meet modern safety standards. From the start of the upgrades project, the CNSC provided regulatory oversight aimed at ensuring that AECL maintained a structured approach to the upgrades. The elements of the approach include, but are not limited to, the determination of project milestones and target dates; the formalization of the design process and project quality assurance requirements; the requirements for updated documentation, including safety reports, safety notes and commissioning reports; and the approval and authorization process. This paper details, from a regulatory perspective, the structured approach used in approving the design, construction, commissioning and subsequent operation of safety system upgrades for an existing and operating research reactor, including the many challenges faced when attempting to balance the requirements of the upgrades project with AECL's need to keep NRU operating to meet its important research and production objectives. (author)

  20. Disposition of recommendations of the National Research Council in the report ''Revitalizing Nuclear Safety Research''

    International Nuclear Information System (INIS)

    1988-06-01

    On December 8, 1986, the Committee on Nuclear Safety Research of the National Research Council submitted its report, ''Revitalizing Nuclear Safety Research,'' to the US Nuclear Regulatory Commission (NRC). The Commission and its staff have carefully reviewed the Committee's report and have extensively examined the planning, implementation, and management of NRC research programs in order to respond most effectively to the Committee's recommendations. This report presents the Commission's view of the Committee's report and describes the actions that are under way in response to its recommendations

  1. Power reactor core safety research

    International Nuclear Information System (INIS)

    Rim, C.S.; Kim, W.C.; Shon, D.S.; Kim, J.

    1981-01-01

    As a part of nuclear safety research program, a project was launched to develop a model to predict fuel failure, to produce the data required for the localizaton of fuel design and fabrication technology, to establish safety limits for regulation of nuclear power plants and to develop reactor operation method to minimize fuel failure through the study of fuel failure mechanisms. During 1980, the first year of this project, various fuel failure mechanisms were analyzed, an experimental method for out-of-pile tests to study the stress corrosion cracking (SCC) behaviour of Zircaloy cladding underiodine environment was established, and characteristics of PWR and CANDU Zircaloy specimens were examined. Also developed during 1980 were the methods and correlations to evaluate fuel failures in the reactor core based on operating data from power reactors

  2. 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)

  3. Enabling social listening for cardiac safety monitoring: Proceedings from a drug information association-cardiac safety research consortium cosponsored think tank.

    Science.gov (United States)

    Seifert, Harry A; Malik, Raleigh E; Bhattacharya, Mondira; Campbell, Kevin R; Okun, Sally; Pierce, Carrie; Terkowitz, Jeffrey; Turner, J Rick; Krucoff, Mitchell W; Powell, Gregory E

    2017-12-01

    This white paper provides a summary of the presentations and discussions from a think tank on "Enabling Social Listening for Cardiac Safety Monitoring" trials that was cosponsored by the Drug Information Association and the Cardiac Safety Research Consortium, and held at the White Oak headquarters of the US Food and Drug Administration on June 3, 2016. The meeting's goals were to explore current methods of collecting and evaluating social listening data and to consider their applicability to cardiac safety surveillance. Social listening is defined as the act of monitoring public postings on the Internet. It has several theoretical advantages for drug and device safety. First, these include the ability to detect adverse events that are "missed" by traditional sources and the ability to detect adverse events sooner than would be allowed by traditional sources, both by affording near-real-time access to data from culturally and geographically diverse sources. Social listening can also potentially introduce a novel patient voice into the conversation about drug safety, which could uniquely augment understanding of real-world medication use obtained from more traditional methodologies. Finally, it can allow for access to information about drug misuse and diversion. To date, the latter 2 of these have been realized. Although regulators from the Food and Drug Administration and the United Kingdom's Medicines and Healthcare Products Regulatory Agency participated in the think tank along with representatives from industry, academia, and patient groups, this article should not be construed to constitute regulatory guidance. Copyright © 2017 Elsevier Inc. All rights reserved.

  4. Organisation of safety research programmes and infrastructure for existing reactors

    International Nuclear Information System (INIS)

    Micaelli, J.C.

    2008-01-01

    The author reviewed the main drivers of safety research, noting that challenging research is an excellent means to preserve know-how and professional skills. International efforts such the NEA-CSNI joint projects are an efficient means to support experimental infrastructure for safety research, while providing useful experimental results. Other initiatives, e.g. within the EU, aimed at developing networks of international expertise and infrastructure were also mentioned. (author)

  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

    After the events at the Japanese nuclear power plant of Fukushima Daiichi, the German federal government decided that Germany will give up electricity generation from nuclear power within a decade. The last reactor will be disconnected from the power grid in 2022. Helping to make this opt-out as safe as possible is one of the duties of the Helmholtz Association with its Nuclear Safety Research Program within the Energy Research Area. Also the demolition of nuclear power plants and the repository problem will keep society, and thus also research, busy for a number of decades to come. Giving up electricity production from nuclear power thus must not mean giving up the required nuclear technology competences. In the fields of reactor safety, demolition, final storage, radiation protection, and crisis management, in critical support of international developments, and for competent evaluation of nuclear facilities around Germany, these competences will be in demand far beyond the German opt-out. This is the reason why the final report by the Ethics Committee on 'Safe Energy Supply' emphasizes the importance of nuclear technology research. Close cooperation on national, European and international levels is indispensable in this effort. Also nuclear safety research in the Helmholtz Association is aligned with the challenges posed by the opt-out of the use of nuclear power. It is important that the high competences in the areas of plant safety and demolition, handling of radioactive waste, and safe final storage as well as radiation protection be preserved. The Nuclear Safety Research Program within the Energy Research Area of the Helmholtz Association therefore will continue studying scientific and technical aspects of the safety of nuclear reactors and the safety of nuclear waste management. These research activities are provident research conducted for society and must be preserved for a long period of time. The work is closely harmonized with the activities

  6. 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

  7. 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

  8. Research and development program in reactor safety for NUCLEBRAS

    International Nuclear Information System (INIS)

    Pinheiro, R.B.; Resende Lobo, A.A. de; Horta, J.A.L.; Avelar Esteves, F. de; Lepecki, W.P.S.; Mohr, K.; Selvatici, E.

    1984-01-01

    With technical assistance from the IAEA, it was established recently an analytical and experimental Research and Development Program for NUCLEBRAS in the area of reactor safety. The main objectives of this program is to make possible, with low investments, the active participation of NUCLEBRAS in international PWR safety research. The analytical and experimental activities of the program are described with some detail, and the main results achieved up to now are presented. (Author) [pt

  9. Collective statement on major nuclear safety research facilities and programmes at risk

    International Nuclear Information System (INIS)

    2001-01-01

    Nuclear safety research remains necessary, since nuclear power programmes are dynamic. In addition to maintaining in-depth competencies, its aim is to provide information to plant designers, operators and regulators in support of the resolution of safety issues, to strengthen confidence in their solution and their implementation, and also to anticipate problems of potential significance. New fields of research open up as a result of plant ageing, plant life extension, plant up-rating, optimisation of plant economics and the associated need to further reduce uncertainties in safety margins quantification. The safety evaluation of future reactor systems being developed or considered in several Member countries also requires new research efforts. Accordingly, Member countries are encouraged to support efforts to maintain key research data, facilities and programmes through national support of international co-operation and funding. This should be under-pinned by development of short-, medium- and long-term strategic visions of the needs of the nuclear safety research community, including a strong component of international collaboration given the international nature of nuclear safety issues. (author)

  10. 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

  11. Dimensions of patient safety culture in family practice.

    Science.gov (United States)

    Palacios-Derflingher, Luz; O'Beirne, Maeve; Sterling, Pam; Zwicker, Karen; Harding, Brianne K; Casebeer, Ann

    2010-01-01

    Safety culture has been shown to affect patient safety in healthcare. While the United States and United Kingdom have studied the dimensions that reflect patient safety culture in family practice settings, to date, this has not been done in Canada. Differences in the healthcare systems between these countries and Canada may affect the dimensions found to be relevant here. Thus, it is important to identify and compare the dimensions from the United States and the United Kingdom in a Canadian context. The objectives of this study were to explore the dimensions of patient safety culture that relate to family practice in Canada and to determine if differences and similarities exist between dimensions found in Canada and those found in previous studies undertaken in the United States and the United Kingdom. A qualitative study was undertaken applying thematic analysis using focus groups with family practice offices and supplementary key stakeholders. Analysis of the data indicated that most of the dimensions from the United States and United Kingdom are appropriate in our Canadian context. Exceptions included owner/managing partner/leadership support for patient safety, job satisfaction and overall perceptions of patient safety and quality. Two unique dimensions were identified in the Canadian context: disclosure and accepting responsibility for errors. Based on this early work, it is important to consider differences in care settings when understanding dimensions of patient safety culture. We suggest that additional research in family practice settings is critical to further understand the influence of context on patient safety culture.

  12. Organizational culture and climate for patient safety in Intensive Care Units.

    Science.gov (United States)

    Santiago, Thaiana Helena Roma; Turrini, Ruth Natalia Teresa

    2015-02-01

    Objective To assess the perception of health professionals about patient safety climate and culture in different intensive care units (ICUs) and the relationship between scores obtained on the Hospital Survey on Patient Safety Culture (HSOPSC) and the Safety Attitudes Questionnaire (SAQ). Method A cross-sectional study conducted at a teaching hospital in the state of São Paulo, Brazil, in March and April 2014. As data gathering instruments, the HSOPSC, SAQ and a questionnaire with sociodemographic and professional information about the staff working in an adult, pediatric and neonatal ICU were used. Data analysis was conducted with descriptive statistics. Results The scales presented good reliability. Greater weaknesses in patient safety were observed in the Working conditions andPerceptions of management domains of the SAQ and in the Nonpunitive response to error domain of the HSOPSC. The strengths indicated by the SAQ wereTeamwork climate and Job satisfactionand by the HSOPC, Supervisor/manager expectations and actions promoting safety and Organizational learning-continuous improvement. Job satisfaction was higher among neonatal ICU workers when compared with the other ICUs. The adult ICU presented lower scores for most of the SAQ and HSOPSC domains. The scales presented moderate correlation between them (r=0.66). Conclusion There were differences in perception regarding patient safety among ICUs, which corroborates the existence of local microcultures. The study did not demonstrate equivalence between the SAQ and the HSOPSC.

  13. Outline of the safety research results, in the power reactor field, fiscal year 1996

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-11-01

    The Power Reactor and Nuclear Fuel Development Corporation (PNC) has promoted the safety research in fiscal year of 1996 according to the Fundamental Research on Safety Research (fiscal year 1996 to 2000) prepared on March, 1996. Here is described on the research results in fiscal year 1996, the first year of the 5 years programme, and whole outline of the fundamental research on safety research, on the power reactor field (whole problems on the new nuclear converter and the fast breeder reactor field and problems relating to the power reactor in the safety for earthquake and probability theoretical safety evaluation field). (G.K.)

  14. Physics and safety of advanced research reactors

    International Nuclear Information System (INIS)

    Boening, K.; Hardt, P. von der

    1987-01-01

    Advanced research reactor concepts are presently being developed in order to meet the neutron-based research needs of the nineties. Among these research reactors, which are characterized by an average power density of 1-10 MW per liter, highest priority is now generally given to the 'beam tube reactors'. These provide very high values of the thermal neutron flux (10 14 -10 16 cm -2 s -1 ) in a large volume outside of the reactor core, which can be used for sample irradiations and, in particular, for neutron scattering experiments. The paper first discusses the 'inverse flux trap concept' and the main physical aspects of the design and optimization of beam tube reactors. After that two examples of advanced research reactor projects are described which may be considered as two opposite extremes with respect to the physical optimization principle just mentioned. The present situation concerning cross section libraries and neutronic computer codes is more or less satisfactory. The safety analyses of advanced research reactors can largely be updated from those of current new designs, partially taking advantage of the immense volume of work done for power reactors. The paper indicates a few areas where generic problems for advanced research reactor safety are to be solved. (orig.)

  15. Energy research and development in the United Kingdom: a discussion document. [Monograph

    Energy Technology Data Exchange (ETDEWEB)

    1976-01-01

    This paper provides a framework for the future planning of United Kingdom research and development in energy technologies. It contains the first steps in the formulation of a national energy R and D strategy. Decision on energy R and D must be taken in the light of the overall aims of energy policies. The main objectives of energy policy are to meet the energy needs of the country at minimum cost in real resources over time, while paying due regard to security of supply, to public safety, to protection of the environment and, where major change is in prospect, to the social consequences of change.

  16. 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)

  17. 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.)

  18. Current state of research on pressurized water reactor safety

    International Nuclear Information System (INIS)

    Couturier, Jean; Schwarz, Michel; Roubaud, Sebastien; Lavarenne, Caroline; Mattei, Jean-Marie; Rigollet, Laurence; Scotti, Oona; Clement, Christophe; Lancieri, Maria; Gelis, Celine; Jacquemain, Didier; Bentaib, Ahmed; Nahas, Georges; Tarallo, Francois; Guilhem, Gilbert; Cattiaux, Gerard; Durville, Benoit; Mun, Christian; Delaval, Christine; Sollier, Thierry; Stelmaszyk, Jean-Marc; Jeffroy, Francois; Dechy, Nicolas; Chanton, Olivier; Tasset, Daniel; Pichancourt, Isabelle; Barre, Francois; Bruna, Gianni; Evrard, Jean-Michel; Gonzalez, Richard; Loiseau, Olivier; Queniart, Daniel; Vola, Didier; Goue, Georges; Lefevre, Odile

    2018-03-01

    For more than 40 years, IPSN then IRSN has conducted research and development on nuclear safety, specifically concerning pressurized water reactors, which are the reactor type used in France. This publication reports on the progress of this research and development in each area of study - loss-of-coolant accidents, core melt accidents, fires and external hazards, component aging, etc. -, the remaining uncertainties and, in some cases, new measures that should be developed to consolidate the safety of today's reactors and also those of tomorrow. A chapter of this report is also devoted to research into human and organizational factors, and the human and social sciences more generally. All of the work is reviewed in the light of the safety issues raised by feedback from major accidents such as Chernobyl and Fukushima Daiichi, as well as the issues raised by assessments conducted, for example, as part of the ten-year reviews of safety at French nuclear reactors. Finally, through the subjects it discusses, this report illustrates the many partnerships and exchanges forged by IRSN with public, industrial and academic bodies both within Europe and internationally

  19. The Bohunice NPP V-1 units nuclear safety upgrading

    International Nuclear Information System (INIS)

    Mlcuch, M.

    2000-01-01

    Safety upgrading and operational reliability improvement was carried out by the Bohunice NPP V-1 staff continuously since the plant commissioning. By now, more than 1200 minor or major modifications have been implemented, either by the NPP maintenance staff or by the contractors. Based on findings of safety assessment missions invited by Bohunice NPP in 1990 - 1991, the Czecho-slovak Nuclear Regulatory Authority (CSKAE) issued the decision No. 5/91 of 81 safety upgrading measures to be taken in different areas. These improvements are referred to as the 'Small Reconstruction of the Bohunice V-1 NPP'. Realization of measures during Small reconstruction of the Bohunice NPP V-1 became a power plant, which further operation is acceptable from safety point of view, but it is also necessary further safety improvement. During the period of the Small Reconstruction the development of a Safety Report for the Gradual reconstruction has been completed. Based on this report the SR Nuclear Regulatory Authority issued the Decision No. 1/94, in which requires 59 upgrading measures in different areas to be addressed. The development of Basic Engineering of the Gradual Reconstruction has been contracted to the Siemens AG. Implementation of safety measures are provided through contract with the consortium REKON (which consists of Siemens AG company and Nuclear Power Plants Research Institute Trnava) and other Czech, Russian and Slovak companies. The Gradual Reconstruction of Bohunice NPP V-1 will be finished in 2000. By implementation of the measures carried out during Gradual Reconstruction achievement of an internationally acceptable nuclear safety level will be reached. (author)

  20. Food safety and organic meats.

    Science.gov (United States)

    Van Loo, Ellen J; Alali, Walid; Ricke, Steven C

    2012-01-01

    The organic meat industry in the United States has grown substantially in the past decade in response to consumer demand for nonconventionally produced products. Consumers are often not aware that the United States Department of Agriculture (USDA) organic standards are based only on the methods used for production and processing of the product and not on the product's safety. Food safety hazards associated with organic meats remain unclear because of the limited research conducted to determine the safety of organic meat from farm-to-fork. The objective of this review is to provide an overview of the published results on the microbiological safety of organic meats. In addition, antimicrobial resistance of microbes in organic food animal production is addressed. Determining the food safety risks associated with organic meat production requires systematic longitudinal studies that quantify the risks of microbial and nonmicrobial hazards from farm-to-fork.

  1. The Medical Research Council (UK)/Uganda Virus Research Institute Uganda Research Unit on AIDS--'25 years of research through partnerships'.

    Science.gov (United States)

    Kaleebu, P; Kamali, A; Seeley, J; Elliott, A M; Katongole-Mbidde, E

    2015-02-01

    For the past 25 years, the Medical Research Council/Uganda Virus Research Institute Uganda Research Unit on AIDS has conducted research on HIV-1, coinfections and, more recently, on non-communicable diseases. Working with various partners, the research findings of the Unit have contributed to the understanding and control of the HIV epidemic both in Uganda and globally, and informed the future development of biomedical HIV interventions, health policy and practice. In this report, as we celebrate our silver jubilee, we describe some of these achievements and the Unit's multidisciplinary approach to research. We also discuss the future direction of the Unit; an exemplar of a partnership that has been largely funded from the north but led in the south. © 2014 The Authors. Tropical Medicine & International Health Published by John Wiley & Sons Ltd.

  2. Role of in-house safety analysis and research activities in regulatory decision making

    International Nuclear Information System (INIS)

    Pradhan, Santosh K.; Nagrale, Dhanesh B.; Gaikwad, Avinash J.

    2015-01-01

    Achievement of an acceptable level of nuclear safety is an essential requirement for the peaceful utilization of nuclear energy. The success of Global Nuclear Safety Regime is built upon a foundation of research. Such research has been sponsored by Governments and industry and has led to improved designs, safer and more reliable plant operation, and improvements in operating plant efficiency. A key element of this research has been the nuclear safety research performed or sponsored by regulatory organizations. In part, it has been the safety research performed or sponsored by regulatory organizations that has contributed to improved safety and has laid the foundation for activities such as risk-informed regulation, plant life extension, improved plant performance (e.g. power uprates) and new plant designs. The regulatory research program is meant to improve the regulatory authority’s knowledge where uncertainty exists, where safety margins are not well-characterized, and where regulatory decisions need to be confirmed in existing or new designs and technologies. The regulatory body get research initiated either in-house or by the licensee or through technical support organizations (TSOs). Research and analysis carried out within the regulatory body is of immense value in this context. This could be in the form of analysis of safety significant events, analysis of severe accidents, review of operating experience, independent checks of critical designs and even review of operator responses under different situations towards arriving at modifications to training programmes and licensing procedures for operating personnel. A latent benefit of regulatory research carried out by the regulators themselves is that it improves their technical competence considerably which in turn leads to high quality safety reviews and improved regulation in general. The aim of the present paper is to provide an overview of role of regulatory research and the in-house regulatory safety

  3. Thirteenth water reactor safety research information meeting: proceedings Volume 1

    International Nuclear Information System (INIS)

    Weiss, A.J.

    1986-02-01

    This six-volume report contains 151 papers out of the 178 that were presented at the Thirteenth Water Reactor Safety Research Information Meeting held at the National Bureau of Standards, Gaithersburg, Maryland, during the week of October 22-25, 1985. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included thirty-one different papers presented by researchers from Japan, Canada and eight European countries. The title of the papers and the names of the authors have been updated and may differ from those that appeared in the final program of the meeting. This volume presents information on: risk analysis PRA application; severe accident sequence analysis; risk analysis/dependent failure analysis; and industry safety research

  4. Application of fuzzy set theory for safety culture and safety management assessment of Kartini research reactor

    International Nuclear Information System (INIS)

    Syarip; Hauptmanns, U.

    2000-01-01

    The safety culture status of nuclear power plant is usually assessed through interview and/or discussions with personnel and management in plant, and an assessment of the pertinent documentation. The approach for safety culture assessment described in IAEA Safety Series, make uses of a questionnaire composed of questions which require 'Yes' or 'No' as an answer. Hence, it is basically a check-list approach which is quite common for safety assessments in industry. Such a procedure ignores the fact that the expert answering the question usually has knowledge which goes far beyond a mere binary answer. Additionally, many situations cannot readily be described in such restricted terms. Therefore, it was developed a checklist consisting of questions which are formulated such that they require more than a simple 'yes' or 'no' as an answer. This allows one to exploit the expert knowledge of the analyst appropriately by asking him to qualify the degree of compliance of each of the topics examined. The method presented has proved useful in assessing the safety culture and quality of safety management of the research reactor. The safety culture status and the quality of safety management of Kartini research reactor is rated as 'average'. The method is also flexible and allows one to add questions to existing areas or to introduce new areas covering related topics

  5. 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.)

  6. Operating experience feedback from safety significant events at research reactors

    Energy Technology Data Exchange (ETDEWEB)

    Shokr, A.M. [Atomic Energy Authority, Abouzabal (Egypt). Egypt Second Research Reactor; Rao, D. [Bhabha Atomic Research Centre, Mumbai (India)

    2015-05-15

    Operating experience feedback is an effective mechanism to provide lessons learned from the events and the associated corrective actions to prevent recurrence of events, resulting in improving safety in the nuclear installations. This paper analyzes the events of safety significance that have been occurred at research reactors and discusses the root causes and lessons learned from these events. Insights from literature on events at research reactors and feedback from events at nuclear power plants that are relevant to research reactors are also presented along with discussions. The results of the analysis showed the importance of communication of safety information and exchange of operating experience are vital to prevent reoccurrences of events. The analysis showed also the need for continued attention to human factors and training of operating personnel, and the need for establishing systematic ageing management programmes of reactor facilities, and programmes for safety management of handling of nuclear fuel, core components, and experimental devices.

  7. Operating experience feedback from safety significant events at research reactors

    International Nuclear Information System (INIS)

    Shokr, A.M.

    2015-01-01

    Operating experience feedback is an effective mechanism to provide lessons learned from the events and the associated corrective actions to prevent recurrence of events, resulting in improving safety in the nuclear installations. This paper analyzes the events of safety significance that have been occurred at research reactors and discusses the root causes and lessons learned from these events. Insights from literature on events at research reactors and feedback from events at nuclear power plants that are relevant to research reactors are also presented along with discussions. The results of the analysis showed the importance of communication of safety information and exchange of operating experience are vital to prevent reoccurrences of events. The analysis showed also the need for continued attention to human factors and training of operating personnel, and the need for establishing systematic ageing management programmes of reactor facilities, and programmes for safety management of handling of nuclear fuel, core components, and experimental devices.

  8. Advanced nuclear reactor safety issues and research needs

    International Nuclear Information System (INIS)

    2002-01-01

    On 18-20 February 2002, the OECD Nuclear Energy Agency (NEA) organised, with the co-sponsorship of the International Atomic Energy Agency (IAEA) and in collaboration with the European Commission (EC), a Workshop on Advanced Nuclear Reactor Safety Issues and Research Needs. Currently, advanced nuclear reactor projects range from the development of evolutionary and advanced light water reactor (LWR) designs to initial work to develop even further advanced designs which go beyond LWR technology (e.g. high-temperature gas-cooled reactors and liquid metal-cooled reactors). These advanced designs include a greater use of advanced technology and safety features than those employed in currently operating plants or approved designs. The objectives of the workshop were to: - facilitate early identification and resolution of safety issues by developing a consensus among participating countries on the identification of safety issues, the scope of research needed to address these issues and a potential approach to their resolution; - promote the preservation of knowledge and expertise on advanced reactor technology; - provide input to the Generation IV International Forum Technology Road-map. In addition, the workshop tried to link advancement of knowledge and understanding of advanced designs to the regulatory process, with emphasis on building public confidence. It also helped to document current views on advanced reactor safety and technology, thereby contributing to preserving knowledge and expertise before it is lost. (author)

  9. Advances in operational safety and severe accident research

    Energy Technology Data Exchange (ETDEWEB)

    Simola, K. [VTT Automation (Finland)

    2002-02-01

    A project on reactor safety was carried out as a part of the NKS programme during 1999-2001. The objective of the project was to obtain a shared Nordic view of certain key safety issues related to the operating nuclear power plants in Finland and Sweden. The focus of the project was on selected central aspects of nuclear reactor safety that are of common interest for the Nordic nuclear authorities, utilities and research bodies. The project consisted of three sub-projects. One of them concentrated on the problems related to risk-informed deci- sion making, especially on the uncertainties and incompleteness of probabilistic safety assessments and their impact on the possibilities to use the PSA results in decision making. Another sub-project dealt with questions related to maintenance, such as human and organisational factors in maintenance and maintenance management. The focus of the third sub-project was on severe accidents. This sub-project concentrated on phenomenological studies of hydrogen combustion, formation of organic iodine, and core re-criticality due to molten core coolant interaction in the lower head of reactor vessel. Moreover, the current status of severe accident research and management was reviewed. (au)

  10. Decommissioning of nuclear power plants and research reactors. Safety guide

    International Nuclear Information System (INIS)

    1999-01-01

    Radioactive waste is produced in the generation of nuclear power and the use of radioactive materials in industry, research and medicine. The importance of the safe management of radioactive waste for the protection of human health and the environment has long been recognized, and considerable experience has been gained in this field. The IAEA's Radioactive Waste Safety Standards Programme aimed at establishing a coherent and comprehensive set of principles and requirements for the safe management of waste and formulating the guidelines necessary for their application. This is accomplished within the IAEA Safety Standards Series in an internally consistent set of publications that reflect an international consensus. The publications will provide Member States with a comprehensive series of internationally agreed publications to assist in the derivation of, and to complement, national criteria, standards and practices. The Safety Standards Series consists of three categories of publications: Safety Fundamentals, Safety Requirements and Safety Guides. With respect to the Radioactive Waste Safety Standards Programme, the set of publications is currently undergoing review to ensure a harmonized approach throughout the Safety Standards Series. This Safety Guide addresses the subject of decommissioning of nuclear power plants and research reactors. It is intended to provide guidance to national authorities and operating organizations for the planning and safe management of the decommissioning of such installations. This Safety Guide has been prepared through a series of Consultants and Technical Committee meetings. It supersedes former Safety Series publications Nos 52, 74 and 105

  11. Decommissioning of nuclear power plants and research reactors. Safety guide

    International Nuclear Information System (INIS)

    2004-01-01

    Radioactive waste is produced in the generation of nuclear power and the use of radioactive materials in industry, research and medicine. The importance of the safe management of radioactive waste for the protection of human health and the environment has long been recognized, and considerable experience has been gained in this field. The IAEA's Radioactive Waste Safety Standards Programme aimed at establishing a coherent and comprehensive set of principles and requirements for the safe management of waste and formulating the guidelines necessary for their application. This is accomplished within the IAEA Safety Standards Series in an internally consistent set of publications that reflect an international consensus. The publications will provide Member States with a comprehensive series of internationally agreed publications to assist in the derivation of, and to complement, national criteria, standards and practices. The Safety Standards Series consists of three categories of publications: Safety Fundamentals, Safety Requirements and Safety Guides. With respect to the Radioactive Waste Safety Standards Programme, the set of publications is currently undergoing review to ensure a harmonized approach throughout the Safety Standards Series. This Safety Guide addresses the subject of decommissioning of nuclear power plants and research reactors. It is intended to provide guidance to national authorities and operating organizations for the planning and safe management of the decommissioning of such installations. This Safety Guide has been prepared through a series of Consultants and Technical Committee meetings. It supersedes former Safety Series publications Nos 52, 74 and 105

  12. Decommissioning of nuclear power plants and research reactors. Safety guide

    International Nuclear Information System (INIS)

    2001-01-01

    Radioactive waste is produced in the generation of nuclear power and the use of radioactive materials in industry, research and medicine. The importance of the safe management of radioactive waste for the protection of human health and the environment has long been recognized, and considerable experience has been gained in this field. The IAEA's Radioactive Waste Safety Standards Programme aimed at establishing a coherent and comprehensive set of principles and requirements for the safe management of waste and formulating the guidelines necessary for their application. This is accomplished within the IAEA Safety Standards Series in an internally consistent set of publications that reflect an international consensus. The publications will provide Member States with a comprehensive series of internationally agreed publications to assist in the derivation of, and to complement, national criteria, standards and practices. The Safety Standards Series consists of three categories of publications: Safety Fundamentals, Safety Requirements and Safety Guides. With respect to the Radioactive Waste Safety Standards Programme, the set of publications is currently undergoing review to ensure a harmonized approach throughout the Safety Standards Series. This Safety Guide addresses the subject of decommissioning of nuclear power plants and research reactors. It is intended to provide guidance to national authorities and operating organizations for the planning and safe management of the decommissioning of such installations. This Safety Guide has been prepared through a series of Consultants and Technical Committee meetings. It supersedes former Safety Series publications Nos 52, 74 and 105

  13. 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.)

  14. Safety research needs for Russian-designed reactors / report by an OECD Support Group

    International Nuclear Information System (INIS)

    1996-01-01

    Seven Task Teams were formed within the OECD Support Group, addressing the following 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. Each Task Team prepared and presented its report to the Support Group as a whole for review and approval. Consequently, the report represents a consensus of the Support Group that outlines the arguments for the safely research needs with the focus on the main technical issues that justify the need and urgency. The written text addresses three basic questions: What is the safety concern? What are the open issues? What are the safety research needs? The safety research needs as identified by the seven Task Teams, and approved by the Support Group, are reflected in the structure of the report. The chapter on the Uses of Safety Research provides examples on how Western research has been applied to improve the safety of nuclear power plants. In addition, the chapter emphasises the need for a national safety research policy

  15. 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

  16. 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

  17. 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.

  18. Advanced research workshop: nuclear materials safety

    International Nuclear Information System (INIS)

    Jardine, L J; Moshkov, M M.

    1999-01-01

    The Advanced Research Workshop (ARW) on Nuclear Materials Safety held June 8-10, 1998, in St. Petersburg, Russia, was attended by 27 Russian experts from 14 different Russian organizations, seven European experts from six different organizations, and 14 U.S. experts from seven different organizations. The ARW was conducted at the State Education Center (SEC), a former Minatom nuclear training center in St. Petersburg. Thirty-three technical presentations were made using simultaneous translations. These presentations are reprinted in this volume as a formal ARW Proceedings in the NATO Science Series. The representative technical papers contained here cover nuclear material safety topics on the storage and disposition of excess plutonium and high enriched uranium (HEU) fissile materials, including vitrification, mixed oxide (MOX) fuel fabrication, plutonium ceramics, reprocessing, geologic disposal, transportation, and Russian regulatory processes. This ARW completed discussions by experts of the nuclear materials safety topics that were not covered in the previous, companion ARW on Nuclear Materials Safety held in Amarillo, Texas, in March 1997. These two workshops, when viewed together as a set, have addressed most nuclear material aspects of the storage and disposition operations required for excess HEU and plutonium. As a result, specific experts in nuclear materials safety have been identified, know each other from their participation in t he two ARW interactions, and have developed a partial consensus and dialogue on the most urgent nuclear materials safety topics to be addressed in a formal bilateral program on t he subject. A strong basis now exists for maintaining and developing a continuing dialogue between Russian, European, and U.S. experts in nuclear materials safety that will improve the safety of future nuclear materials operations in all the countries involved because of t he positive synergistic effects of focusing these diverse backgrounds of

  19. 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)

  20. Nirex Safety Assessment Research Programme bibliography, 1990

    International Nuclear Information System (INIS)

    Cooper, M.J.

    1990-10-01

    This bibliography lists reports and papers written as part of the Nirex Safety Assessment Research Programme, which is concerned with disposal of low-level and intermediate-level waste (LLW and ILW) and associated radiological assessments. (author)

  1. Research on the improvement of nuclear safety -The development of LOCA analysis codes for nuclear power plant-

    Energy Technology Data Exchange (ETDEWEB)

    Jang, Won Pyo; Jung, Yung Jong; Kim, Kyung Doo; Jung, Jae Joon; Kim, Won Suk; Han, Doh Heui; Hah, Kooi Suk; Jung, Bub Dong; Lee, Yung Jin; Hwang, Tae Suk; Lee, Sang Yong; Park, Chan Uk; Choi, Han Rim; Lee, Sang Jong; Choi, Jong Hoh; Ban, Chang Hwan; Bae, Kyoo Hwan [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1995-07-01

    The present research aims at development of both a best estimate methodology on LOCA analysis and, as an application, performance analyses of safety systems. SBLOCA analyses have been continued to examine the capacity reduction effect of ECCS since the second project year. As a results, core uncovery, which is requirement of URD has not been occurred in 6`` cold leg break. Although core uncovery has been predicted when DVI line has been broken for DVI+4-Train HPIS, the calculated PCT has lied well within the criterion. The effect of safety injection position and SIT characteristics are also analyzed for LBLOCA. The results show that cold leg injection is the most effective way and the adaption of advanced SIT could lead to elimination of LPSI pump from the safety system. On the other hand, the quantified uncertainties obtained from THTF and FLECHT/SEASET which represents blowdown and reflood phenomena, respectively, have been confirmed using IET(LOFT test). The application uncertainty for Kori unit 3 has been analyzed. Finally, application of the best estimate methodology using the uncertainties concerned with the code, the bais, and the application, leads to overall uncertainty of about 200K for Kori unit 3. 244 figs, 22 tabs, 92 refs. (Author).

  2. Research on the improvement of nuclear safety -The development of LOCA analysis codes for nuclear power plant-

    International Nuclear Information System (INIS)

    Jang, Won Pyo; Jung, Yung Jong; Kim, Kyung Doo; Jung, Jae Joon; Kim, Won Suk; Han, Doh Heui; Hah, Kooi Suk; Jung, Bub Dong; Lee, Yung Jin; Hwang, Tae Suk; Lee, Sang Yong; Park, Chan Uk; Choi, Han Rim; Lee, Sang Jong; Choi, Jong Hoh; Ban, Chang Hwan; Bae, Kyoo Hwan

    1995-07-01

    The present research aims at development of both a best estimate methodology on LOCA analysis and, as an application, performance analyses of safety systems. SBLOCA analyses have been continued to examine the capacity reduction effect of ECCS since the second project year. As a results, core uncovery, which is requirement of URD has not been occurred in 6'' cold leg break. Although core uncovery has been predicted when DVI line has been broken for DVI+4-Train HPIS, the calculated PCT has lied well within the criterion. The effect of safety injection position and SIT characteristics are also analyzed for LBLOCA. The results show that cold leg injection is the most effective way and the adaption of advanced SIT could lead to elimination of LPSI pump from the safety system. On the other hand, the quantified uncertainties obtained from THTF and FLECHT/SEASET which represents blowdown and reflood phenomena, respectively, have been confirmed using IET(LOFT test). The application uncertainty for Kori unit 3 has been analyzed. Finally, application of the best estimate methodology using the uncertainties concerned with the code, the bais, and the application, leads to overall uncertainty of about 200K for Kori unit 3. 244 figs, 22 tabs, 92 refs. (Author)

  3. Code on the safety of nuclear research reactors: Operation

    International Nuclear Information System (INIS)

    1992-01-01

    The purpose of this publication is to provide the essential requirements and recommendations for the safe operation of research reactors, with emphasis on the supervisory and managerial aspects. However, the publication also provides some guidance and information on topics concerning all the organizations involved in operation. These objectives are expressed in terms of requirements and recommendations for the safe operation of research reactors. Emphasis is placed on the safety requirements that shall be met rather than on the ways in which they can be met. The requirements and recommendations may form the foundation necessary for a Member State to develop regulations and safety criteria for its research reactor programme.

  4. Progress of the United States foreign research reactor spent nuclear fuel acceptance program

    International Nuclear Information System (INIS)

    Huizenga, D.G.; Clapper, M.; Thrower, A.W.

    2002-01-01

    The United States Department of Energy (DOE), in consultation with the Department of State (DOS), adopted the Nuclear Weapons Nonproliferation Policy Concerning Foreign Research Reactor Spent Nuclear Fuel in May 1996. To date, the Foreign Research Reactor (FRR) Spent Nuclear Fuel (SNF) Acceptance Program has completed 23 shipments. Almost 5000 spent fuel assemblies from eligible research reactors throughout the world have been accepted into the United States under this program. Over the past year, another cross-country shipment of fuel was accomplished, as well as two additional shipments in the fourth quarter of calendar year 2001. These shipments attracted considerable safeguards oversight since they occurred post September 11. Recent guidance from the Nuclear Regulatory Commission (NRC) pertaining to security and safeguards issues deals directly with the transport of nuclear material. Since the Acceptance Program has consistently applied above regulatory safety enhancements in transport of spent nuclear fuel, this guidance did not adversely effect the Program. As the Program draws closer to its termination date, an increased number of requests for program extension are received. Currently, there are no plans to extend the policy beyond its current expiration date; therefore, eligible reactor operators interested in participating in this program are strongly encouraged to evaluate their inventory and plan for future shipments as soon as possible. (author)

  5. Plan of Nordic research in nuclear safety 1994-97

    International Nuclear Information System (INIS)

    1993-04-01

    A new four-year Nordic research programme in the field of nuclear safety and radiation protection is to start in 1994 as a followup of several preceding Nordic programmes. It will include seven projects and a joint coordination function. The programme is intended to sustain a common understanding among safety authorities in the Nordic countries with respect to reactor safety and radiation protection. It mainly deals with questions that are actual within the Nordic region, but it may also include problems of concern to its eastern neighbours. Two of the projects deal with reactor safety, and one with radioactive waste. The other four projects are on environmental aspects: two of them deal with radioecology, and two with questions related to emergency preparedness. The programme is managed by the Nordic Committee for Safety Research, NKS, consisting of representatives from regulatory authorities, research bodies, and industry. Basic financing is provided by one consortium member from each of the five Nordic countries, whereby an annual budget of approximately 8 million Danish Kroner will be provided. Additional financing comes from sponsors interested in the programme as well as from those organizations taking part in the project work. Definite project plans are to be elaborated within the more general frames described in the present outline. The flexibility of the programme is enhanced by limiting the duration of individual activities to one or two years. This will make it possible to adjust the programme to actual needs in the Nordic countries. (au)

  6. CONCEPTUALIZATION OF IDEAS OF PSYCHOLOGICAL SAFETY IN SPORTS: PROBLEMS OF EXPERIMENTAL RESEARCH

    Directory of Open Access Journals (Sweden)

    Yulia Vladimirovna Vardanyan

    2013-09-01

    Full Text Available This article is devoted to the research of the concept “psychological safety in sports”. On the basis of analysis of ideas about psychological safety in sports and their representation in printed or verbal form the necessity of overcoming the fragmentation and lack of system is substantiated. The authors state that one and the same sports situation can constructively or destructively affect the psychological safety of direct or indirect participants of sports events. In this context, it is important to create the psycholinguistic basis of experimental research of psychological safety in sports. Great attention is paid to systematization of the content of the concept “psychological safety in sports”. The created models of words and expressions that convey ideas about this phenomenon are of particular value. In the structure of the concept the dominant meanings, expressed in the nucleus, and additional meanings, related to the periphery of the concept are distinguished.Purpose: to explore the ideas of psychological safety in sports and their representation in printed or verbal form; to determine ways of overcoming the conceptual psycholinguistic problems in the process of experimental research of psychological safety in sports; to create the model of words and expressions which are used to verbalize the concept “psychological safety in sports”.Methodology: theoretical analysis of psychological and linguistic literature, creation of the psycholinguistic basis of experimental research, modeling of the conceptual ideas of psychological safety in sports.Results: psycholinguistic basis of experimental research of psychological safety in sports, the model of content and structure of the corresponding concept.Practical implications: Pedagogical Psychology, Sports Psychology, Philology, Psycholinguistics.DOI: http://dx.doi.org/10.12731/2218-7405-2013-8-11

  7. 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.)

  8. Development and Pilot Implementation of a Search Protocol to Improve Patient Safety on a Psychiatric Inpatient Unit.

    Science.gov (United States)

    Abela-Dimech, Frances; Johnston, Kim; Strudwick, Gillian

    A mental health organization in Ontario, Canada, noted an increase in unsafe items entering locked inpatient units. The purpose of this project was to develop and implement a search protocol to improve patient, staff, and visitor safety by preventing unsafe items from entering a locked inpatient unit. Under the guidance of a clinical nurse specialist, an interprofessional team used the Failure Mode and Effects Analysis framework to identify what items were considered unsafe, how these unsafe items were entering the unit, and what strategies could be used to prevent these items from entering the unit. A standardized search protocol was identified as a strategy to prevent items from entering the unit. The standardized search protocol was developed and piloted on 1 unit. To support the search protocol, an interprofessional team created a poster using a mnemonic aid to educate patients, staff, and visitors about which items could not be brought onto the unit. Educational sessions on the search protocol were provided for staff. The difference between the number of incidents before and after the implementation of the search protocol was statistically significant. Safety on an inpatient unit was increased as incidents of unsafe items entering the unit decreased.

  9. Empirical Bayes methods in road safety research.

    NARCIS (Netherlands)

    Vogelesang, R.A.W.

    1997-01-01

    Road safety research is a wonderful combination of counting fatal accidents and using a toolkit containing prior, posterior, overdispersed Poisson, negative binomial and Gamma distributions, together with positive and negative regression effects, shrinkage estimators and fiercy debates concerning

  10. RATU2, research for safety and operability

    International Nuclear Information System (INIS)

    Solin, J.

    1998-01-01

    The Finnish research programme on the structural integrity of nuclear power plants, RATU2 was launched in 1995 for four years to coordinate the independent national research and development work aiming for structural safety in NPP's. The general planning and goal setting of the programme was based on the research need assessment and evaluation of the previous RATU programme. The research plans have been updated and refined annually on the basis of available funding. The RATU2 programme is briefly introduced in this paper. The role of RATU2 in the national nuclear energy research field, the research areas, administrative data, main objectives and future plans are reported in this paper

  11. 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)

  12. Review of TSOs technical needs in safety research and development

    International Nuclear Information System (INIS)

    Rintamaa, R.; Bruna, G.

    2012-01-01

    ETSON is the network of European Technical Safety Organizations. The ETSON members have elaborated together a position paper which identifies and ranks the main research and development fields of endeavor in a short, mid and long term perspective. The main research areas and major needs are grouped in 7 areas: 1) safety assessment methods, 2) multi-physics safety approach (several disciplines, macroscopic and microscopic level), 3) Ageing of materials, 4) fuel behaviour, 5) human and organisational factors, 6) instrumentation and control, 7) Severe accidents: phenomenology and methodology, and severe accidents: crisis preparedness and major needs. ETSON has coordinated the activities with other European platforms and has widely contributed to the NUGENIA (Nuclear Generation 2 and 3 Association) topic research and development areas. The next step will be a prioritization of these needs

  13. [Real-time safety audits in a neonatal unit].

    Science.gov (United States)

    Bergon-Sendin, Elena; Perez-Grande, María Del Carmen; Lora-Pablos, David; Melgar-Bonis, Ana; Ureta-Velasco, Noelia; Moral-Pumarega, María Teresa; Pallas-Alonso, Carmen Rosa

    2017-09-01

    Random audits are a safety tool to help in the prevention of adverse events, but they have not been widely used in hospitals. The aim of the study was to determine, through random safety audits, whether the information and material required for resuscitation were available for each patient in a neonatal intensive care unit and determine if factors related to the patient, time or location affect the implementation of the recommendations. Prospective observational study conducted in a level III-C neonatal intensive care unit during the year 2012. The evaluation of written information on the endotracheal tube, mask and ambu bag prepared of each patient and laryngoscopes of the emergency trolley were included within a broader audit of technological resources and study procedures. The technological resources and procedures were randomly selected twice a week for audit. Appropriate overall use was defined when all evaluated variables were correctly programmed in the same procedure. A total of 296 audits were performed. The kappa coefficient of inter-observer agreement was 0.93. The rate of appropriate overall use of written information and material required for resuscitation was 62.50% (185/296). Mask and ambu bag prepared for each patient was the variable with better compliance (97.3%, P=.001). Significant differences were found with improved usage during weekends versus working-day (73.97 vs. 58.74%, P=.01), and the rest of the year versus 3 rd quarter (66.06 vs. 52%, P=.02). Only in 62.5% of cases was the information and the material necessary to attend to a critical situation urgently easily available. Opportunities for improvement were identified through the audits. Copyright © 2016 Asociación Española de Pediatría. Publicado por Elsevier España, S.L.U. All rights reserved.

  14. Reports on research programs in the field of reactor safety sponsored by the Federal Ministry for Research and Technology

    International Nuclear Information System (INIS)

    1986-11-01

    Investigations on the safety of Light Water Reactors (LWR) being performed in the framework of the research program on reactor safety (RS-projects) are sponsored by the Federal Ministry for Research and Technology (BMFT). Objective of this program is to investigate in greater detail the safety margins of nuclear power plants and their systems and the further development of safety technology. Besides the investigations of LWR tasks also projects on the safety of advanced reactors are sponsored by the BMFT. The individual reports are classified according to the research program on the safety of LWRs 1977-1980 of the BMFT. Another table of contents uses the same classification system as applied in the nuclear safety index of the CEC (Commission of the European Communities) and the OECD (Organization for Economic Cooperation and Development). The reports are arranged in the sequence of their project numbers. (orig./HP) [de

  15. Reports of research programs in the field of reactor safety sponsored by the Federal Ministry for Research and Technology

    International Nuclear Information System (INIS)

    1986-06-01

    Investigations on the safety of Light Water Reactors (LWR) being performed in the framework of his research program on reactor safety (RS-projects) are sponsored by the Federal Ministry for Research and Technology (BMFT). Objective of this program is to investigate in greater detail the safety margins of nuclear power plants and their systems and the further development of safety technology. Besides the investigations of LWR tasks also projects on the safety of advanced reactors are sponsored by the BMFT. The individual reports are classified according to the research program on the safety of LWRs 1977-1980 of the BMFT. Another table of contents uses the same classification system as applied in the nuclear safety index of the CEC (Commission of the European Communities) and the OECD (Organization for Economic Cooperation and Development). The reports are arranged in the sequence of their project numbers. (orig./HP) [de

  16. Safety first!

    CERN Multimedia

    2016-01-01

    Among the many duties I assumed at the beginning of the year was the ultimate responsibility for Safety at CERN: the responsibility for the physical safety of the personnel, the responsibility for the safe operation of the facilities, and the responsibility to ensure that CERN acts in accordance with the highest standards of radiation and environmental protection.   The Safety Policy document drawn up in September 2014 is an excellent basis for the implementation of Safety in all areas of CERN’s work. I am happy to commit during my mandate to help meet its objectives, not least by ensuring the Organization makes available the necessary means to achieve its Safety objectives. One of the main objectives of the HSE (Occupational Health and Safety and Environmental Protection) unit in the coming months is to enhance the measures to minimise CERN’s impact on the environment. I believe CERN should become a role model for an environmentally-aware scientific research laboratory. Risk ...

  17. Patient Drug Safety Reporting: Diabetes Patients' Perceptions of Drug Safety and How to Improve Reporting of Adverse Events and Product Complaints.

    Science.gov (United States)

    Patel, Puja; Spears, David; Eriksen, Betina Østergaard; Lollike, Karsten; Sacco, Michael

    2018-03-01

    Global health care manufacturer Novo Nordisk commissioned research regarding awareness of drug safety department activities and potential to increase patient feedback. Objectives were to examine patients' knowledge of pharmaceutical manufacturers' responsibilities and efforts regarding drug safety, their perceptions and experiences related to these efforts, and how these factors influence their thoughts and behaviors. Data were collected before and after respondents read a description of a drug safety department and its practices. We conducted quantitative survey research across 608 health care consumers receiving treatment for diabetes in the United States, Germany, United Kingdom, and Italy. This research validated initial, exploratory qualitative research (across 40 comparable consumers from the same countries) which served to guide design of the larger study. Before reading a drug safety department description, 55% of respondents were unaware these departments collect safety information on products and patients. After reading the description, 34% reported the department does more than they expected to ensure drug safety, and 56% reported "more confidence" in the industry as a whole. Further, 66% reported themselves more likely to report an adverse event or product complaint, and 60% reported that they were more likely to contact a drug safety department with questions. The most preferred communication methods were websites/online forums (39%), email (27%), and telephone (25%). Learning about drug safety departments elevates consumers' confidence in manufacturers' safety efforts and establishes potential for patients to engage in increased self-monitoring and reporting. Study results reveal potentially actionable insights for the industry across patient and physician programs and communications.

  18. Research and technology in the Federal Motor Carrier Safety Administration

    Science.gov (United States)

    2002-01-01

    As the Federal Government's chief commercial vehicle safety agency, the Federal Motor Carrier Safety Administration's (FMCSA), Office of Research and Technology (R&T) focuses on saving lives and reducing injuries by helping to prevent crashes involvi...

  19. Outline of results of safety research (in nuclear fuel cycle field in fiscal year 1996)

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-12-01

    The safety research in Power Reactor and Nuclear Fuel Development Corporation in fiscal year 1996 has been carried out based on the basic plan of safety research (from fiscal year 1996 to 2000) which was decided in March, 1996. In this report, on nuclear fuel cycle field, namely all the subjects in the fields of nuclear fuel facilities, environmental radioactivity and waste disposal, and the subjects related to nuclear fuel facilities among the fields of aseismatic and probabilistic safety assessments, the results of research in fiscal year 1996, the first year of the 5-year project, are summarized together with the outline of the basic plan of safety research. The basic policy, objective and system for promotion of the safety research are described. The objectives of the safety research are the advancement of safety technology, the safety of facilities, stable operation techniques, the safety design and the evaluation techniques of next generation facilities, and the support of transferring nuclear fuel cycle to private businesses. The objects of the research are uranium enrichment, fuel fabrication and reprocessing, and waste treatment and storage. 52 investigation papers of the results of the safety research in nuclear fuel cycle field in fiscal year 1996 are collected in this report. (K.I.)

  20. Patient safety climate (PSC) perceptions of frontline staff in acute care hospitals: examining the role of ease of reporting, unit norms of openness, and participative leadership.

    Science.gov (United States)

    Zaheer, Shahram; Ginsburg, Liane; Chuang, You-Ta; Grace, Sherry L

    2015-01-01

    Increased awareness regarding the importance of patient safety issues has led to the proliferation of theoretical conceptualizations, frameworks, and articles that apply safety experiences from high-reliability industries to medical settings. However, empirical research on patient safety and patient safety climate in medical settings still lags far behind the theoretical literature on these topics. The broader organizational literature suggests that ease of reporting, unit norms of openness, and participative leadership might be important variables for improving patient safety. The aim of this empirical study is to examine in detail how these three variables influence frontline staff perceptions of patient safety climate within health care organizations. A cross-sectional study design was used. Data were collected using a questionnaire composed of previously validated scales. The results of the study show that ease of reporting, unit norms of openness, and participative leadership are positively related to staff perceptions of patient safety climate. Health care management needs to involve frontline staff during the development and implementation stages of an error reporting system to ensure staff perceive error reporting to be easy and efficient. Senior and supervisory leaders at health care organizations must be provided with learning opportunities to improve their participative leadership skills so they can better integrate frontline staff ideas and concerns while making safety-related decisions. Finally, health care management must ensure that frontline staff are able to freely communicate safety concerns without fear of being punished or ridiculed by others.

  1. Identifying research priorities for patient safety in mental health: an international expert Delphi study

    Science.gov (United States)

    Murray, Kevin; Thibaut, Bethan; Ramtale, Sonny Christian; Adam, Sheila; Darzi, Ara; Archer, Stephanie

    2018-01-01

    Objective Physical healthcare has dominated the patient safety field; research in mental healthcare is not as extensive but findings from physical healthcare cannot be applied to mental healthcare because it delivers specialised care that faces unique challenges. Therefore, a clearer focus and recognition of patient safety in mental health as a distinct research area is still needed. The study aim is to identify future research priorities in the field of patient safety in mental health. Design Semistructured interviews were conducted with the experts to ascertain their views on research priorities in patient safety in mental health. A three-round online Delphi study was used to ascertain consensus on 117 research priority statements. Setting and participants Academic and service user experts from the USA, UK, Switzerland, Netherlands, Ireland, Denmark, Finland, Germany, Sweden, Australia, New Zealand and Singapore were included. Main outcome measures Agreement in research priorities on a five-point scale. Results Seventy-nine statements achieved consensus (>70%). Three out of the top six research priorities were patient driven; experts agreed that understanding the patient perspective on safety planning, on self-harm and on medication was important. Conclusions This is the first international Delphi study to identify research priorities in safety in the mental field as determined by expert academic and service user perspectives. A reasonable consensus was obtained from international perspectives on future research priorities in patient safety in mental health; however, the patient perspective on their mental healthcare is a priority. The research agenda for patient safety in mental health identified here should be informed by patient safety science more broadly and used to further establish this area as a priority in its own right. The safety of mental health patients must have parity with that of physical health patients to achieve this. PMID:29502096

  2. Environment Health & Safety Research Program. Organization and 1979-1980 Publications

    Energy Technology Data Exchange (ETDEWEB)

    None

    1981-01-01

    This document was prepared to assist readers in understanding the organization of Pacific Northwest Laboratory, and the organization and functions of the Environment, Health and Safety Research Program Office. Telephone numbers of the principal management staff are provided. Also included is a list of 1979 and 1980 publications reporting on work performed in the Environment, Health and Safety Research Program, as well as a list of papers submitted for publication.

  3. 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)

  4. 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.

  5. Panel plenary session: Status and future needs in the field of reactor safety research

    International Nuclear Information System (INIS)

    Finzi, S.; Cicognani, G.; Heusener, G.; Geijzers, H.F.G.; Alonso-Santos, A.; Holtbecker, H.F.

    1990-01-01

    Status and future needs in the field of reactor safety research. Overviews are given of the nuclear programme in France and the Netherlands. Spanish and Italian reactor safety research both current and for the future is outlined. LWR safety and the continuation of the establishment of safety standards particularly for LMFBR reactors is discussed. The new framework for the research in reactor safety by the Commission of the European Communities for 1990-1994 is outlined. The discussion which followed is reported. (UK)

  6. 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.

  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. Reactor safety research and development in Chalk River Laboratories

    Energy Technology Data Exchange (ETDEWEB)

    Nitheanandan, T. [Atomic Energy of Canada Limited, Chalk River, ON (Canada)

    2014-07-01

    Atomic Energy of Canada Limited's Chalk River Laboratories provides three different services to stakeholders and customers. The first service provided by the laboratory is the implementation of Research and Development (R&D) programs to provide the underlying technological basis of safe nuclear power reactor designs. A significant portion of the Canadian R&D capability in reactor safety resides at Atomic Energy of Canada Limited's Chalk River Laboratories, and this capability was instrumental in providing the science and technology required to aid in the safety design of CANDU power reactors. The second role of the laboratory has been in supporting nuclear facility licensees to ensure the continued safe operation of nuclear facilities, and to develop safety cases to justify continued operation. The licensing of plant life extension is a key industry objective, requiring extensive research on degradation mechanisms, such that safety cases are based on the original safety design data and valid and realistic assumptions regarding the effect of ageing and management of plant life. Recently, Chalk River Laboratories has been engaged in a third role in research to provide the technical basis and improved understanding for decision making by regulatory bodies. The state-of-the-art test facilities in Chalk River Laboratories have been contributing to the R&D needs of all three roles, not only in Canada but also in the international community, thorough Canada's participation in cooperative programs lead by International Atomic Energy Agency and the OECD's Nuclear Energy Agency. (author)

  9. Human Factors Evaluation of Man-Machine Interface for Periodic Safety Review of Yonggwang Unit no. 1, 2

    International Nuclear Information System (INIS)

    Lee, Yong Hee; Lee, Jung Woon; Park, Jae Chang

    2006-01-01

    This report describes the research results of human factors assessment on the MMI(Man Machine Interface) equipment as part of Periodic Safety Review(PSR) of Yonggwang Unit no. 1, 2. As MMI is a key factor among human factors to be reviewed in PSR, we reviewed the MMI components of nuclear power plants in aspect of human factors engineering. The availability, suitability, and effectiveness of the MMI devices were chosen to be reviewed. The MMI devices were investigated through the review of design documents related to the MMI, survey of control panels, evaluation of experts, and experimental assessment. Checklists were used to perform this assessment and record the review results. The items mentioned by the expert comments to review in detail in relation with task procedures were tested by experiments with operators' participation. For some questionable issues arisen during this MMI review, operator workload and possibility of errors in operator actions were analysed. The reviewed MMI devices contain MCR(Main Control Room), SPDS(Safety Parameter Display System), RSP(Remote Shutdown Panel), and the selected LCBs(Local Control Boards) importantly related to safety. As results of the assessments, any significant problem challenging the safety was not found on human factors in the MMI devices. However, several small items to be changed and improved in suitability of MMI devices were discovered. An action plan is recommended to accommodate the suggestions and review comments. It will enhance the plant safety on MMI area

  10. Human Factors Evaluation of Man-Machine Interface for Periodic Safety Review of Yonggwang Unit no. 1, 2

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Yong Hee; Lee, Jung Woon; Park, Jae Chang (and others)

    2006-01-15

    This report describes the research results of human factors assessment on the MMI(Man Machine Interface) equipment as part of Periodic Safety Review(PSR) of Yonggwang Unit no. 1, 2. As MMI is a key factor among human factors to be reviewed in PSR, we reviewed the MMI components of nuclear power plants in aspect of human factors engineering. The availability, suitability, and effectiveness of the MMI devices were chosen to be reviewed. The MMI devices were investigated through the review of design documents related to the MMI, survey of control panels, evaluation of experts, and experimental assessment. Checklists were used to perform this assessment and record the review results. The items mentioned by the expert comments to review in detail in relation with task procedures were tested by experiments with operators' participation. For some questionable issues arisen during this MMI review, operator workload and possibility of errors in operator actions were analysed. The reviewed MMI devices contain MCR(Main Control Room), SPDS(Safety Parameter Display System), RSP(Remote Shutdown Panel), and the selected LCBs(Local Control Boards) importantly related to safety. As results of the assessments, any significant problem challenging the safety was not found on human factors in the MMI devices. However, several small items to be changed and improved in suitability of MMI devices were discovered. An action plan is recommended to accommodate the suggestions and review comments. It will enhance the plant safety on MMI area.

  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. Measuring patient safety culture: an assessment of the clustering of responses at unit level and hospital level

    NARCIS (Netherlands)

    Smits, M.; Wagner, C.; Spreeuwenberg, P.; Wal, van der G.

    2009-01-01

    OBJECTIVES: To test the claim that the Hospital Survey on Patient Safety Culture (HSOPS) measures patient safety culture instead of mere individual attitudes and to determine the most appropriate level (individual, unit or hospital level) for interventions aimed at improving the culture of patient

  13. Measuring patient safety culture : an assessment of the clustering of responses at unit level and hospital level

    NARCIS (Netherlands)

    Smits, M.; Wagner, C.; Spreeuwenberg, P.; Wal, G. van der; Groenewegen, P.P.

    2009-01-01

    Objectives: To test the claim that the Hospital Survey on Patient Safety Culture (HSOPS) measures patient safety culture instead of mere individual attitudes and to determine the most appropriate level (individual, unit or hospital level) for interventions aimed at improving the culture of patient

  14. Improving nuclear safety at international research reactors: The Integrated Research Reactor Safety Enhancement Program (IRRSEP)

    International Nuclear Information System (INIS)

    Huizenga, David; Newton, Douglas; Connery, Joyce

    2002-01-01

    Nuclear energy continues to play a major role in the world's energy economy. Research and test reactors are an important component of a nation's nuclear power infrastructure as they provide training, experiments and operating experience vital to developing and sustaining the industry. Indeed, nations with aspirations for nuclear power development usually begin their programs with a research reactor program. Research reactors also are vital to international science and technology development. It is important to keep them safe from both accident and sabotage, not only because of our obligation to prevent human and environmental consequence but also to prevent corresponding damage to science and industry. For example, an incident at a research reactor could cause a political and public backlash that would do irreparable harm to national nuclear programs. Following the accidents at Three Mile Island and Chernobyl, considerable efforts and resources were committed to improving the safety posture of the world's nuclear power plants. Unsafe operation of research reactors will have an amplifying effect throughout a country or region's entire nuclear programs due to political, economic and nuclear infrastructure consequences. (author)

  15. Calculating the cost of research and Development in nuclear and radiation safety

    International Nuclear Information System (INIS)

    Matsulevich, N.Je.; Nosovs'ka, A.A.

    2010-01-01

    Methodological support assessing the cost of research and development in the area of nuclear and radiation safety regulation is considered. Basic methodological recommendations for determining labor expenditures for research and development in nuclear and radiation safety are provided.

  16. Safety management procedures and practices at Indira Gandhi Centre for Atomic Research

    Energy Technology Data Exchange (ETDEWEB)

    Rodriguez, P.; Lee, S.M.; Kapoor, R.P.; Raghunath, V.M.; Karthikeyan, S.V. [Indira Gandhi Centre for Atomic Research, Kalpakkam 603 102 (India)]. E-mail: kapoor@igcar.ernet.in

    2004-07-01

    The Indira Gandhi Centre for Atomic Research (IGCAR) operates FBTR (Fast Breeder Test Reactor), KAMINI (neutron source reactor), radiometallurgical laboratory, radiochemical laboratory, reprocessing plant, industrial scale sodium loops, advanced research laboratories, workshops, etc. Codified safety management procedures with systematic surveillance are essential for safe and reliable operations and these are described under the classifications of radiation safety, industrial safety and reactor operations with special emphasis on the human factor. Health physics teams, independent of the plant facility, supervise the radioactive facilities of the centre. Industrial safety standards are maintained by another independent section. Safety management for the reactors include a clear organisational structure, adequate documentation, compulsory training and licencing, safe working methods taking into account human factors and review by independent safety authorities. (author)

  17. Safety management procedures and practices at Indira Gandhi Centre for Atomic Research

    International Nuclear Information System (INIS)

    Rodriguez, P.; Lee, S.M.; Kapoor, R.P.; Raghunath, V.M.; Karthikeyan, S.V.

    2004-01-01

    The Indira Gandhi Centre for Atomic Research (IGCAR) operates FBTR (Fast Breeder Test Reactor), KAMINI (neutron source reactor), radiometallurgical laboratory, radiochemical laboratory, reprocessing plant, industrial scale sodium loops, advanced research laboratories, workshops, etc. Codified safety management procedures with systematic surveillance are essential for safe and reliable operations and these are described under the classifications of radiation safety, industrial safety and reactor operations with special emphasis on the human factor. Health physics teams, independent of the plant facility, supervise the radioactive facilities of the centre. Industrial safety standards are maintained by another independent section. Safety management for the reactors include a clear organisational structure, adequate documentation, compulsory training and licencing, safe working methods taking into account human factors and review by independent safety authorities. (author)

  18. Accomplishment of 10-year research in NUCEF and future development. Criticality safety research

    International Nuclear Information System (INIS)

    Miyoshi, Yoshinori

    2005-01-01

    Since 1995, static and transient critical experiments on low enriched uranyl nitrate solution have been performed using two solution type criticality facilities, STACY and TRACY constructed in NUCEF. The obtained fundamental and systematic data on aqueous solution were used to validate the criticality safety calculation codes and to develop the transient analyses codes for criticality accident evaluation. This paper describes the outline of the criticality safety research conducted in NUCEF. (author)

  19. 76 FR 17808 - Final Vehicle Safety Rulemaking and Research Priority Plan 2011-2013

    Science.gov (United States)

    2011-03-31

    ... [Docket No. NHTSA-2009-0108] Final Vehicle Safety Rulemaking and Research Priority Plan 2011- 2013 AGENCY... availability. SUMMARY: This document announces the availability of the Final NHTSA Vehicle Safety and Fuel.... This Priority Plan is an update to the Final Vehicle Safety Rulemaking and Research Priority Plan 2009...

  20. Status of electrical safety in Indira Gandhi Centre for Atomic Research

    International Nuclear Information System (INIS)

    Kandasamy, S.; Karthikeyan, S.V.; Senthilkumar, B.; Shunmugam, U.; Kannan, S.E.

    1999-01-01

    Electrical Systems in Indira Gandhi Centre for Atomic Research (IGCAR), comprising of facilities such as Fast Breeder Test Reactor (FBTR) and various Research and Development laboratories form a complex network providing practically uninterrupted power supply to all the facilities meeting their energy demands. The safety record of the Centre for the past 25 years has been very good and the number of electrical accidents in the Centre has been less. This paper brings out the status of the electrical safety in IGCAR and indicates the steps to be taken to improve the safety culture. It also utilizes the measure to be provided for improving the electrical safety in the works executed by contractors

  1. 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

  2. Research study about the establishment of safety culture. Effects of organizational factors in construction industry's safety indices

    International Nuclear Information System (INIS)

    Kojima, Mitsuhiro; Hirose, Humiko; Takano, Kenichi; Hasegawa, Naoko

    1999-01-01

    To find the relationships between safety related activities (such as safety patrol' or '4s/5s activities') and accidents rate in the workplace, questionnaires were sent to 965 construction companies and 120 answers were returned. In this questionnaire, safety activities, safety regulations and safety policies of the companies were asked and organizational climates, company policies, philosophies and the number of accidents in workplace were also asked. There seems some relationships between accidents rate and safety activities, safety regulations and safety policies in the companies, but the deviations between estimate values and observed values are so great that it seems impossible to estimate the accidents rate in the working place from the safety activities, safety regulations and safety policies of the companies. On the other hand, some characteristics of safety activities and organizational climates in the construction industry were identified using multi variants analysis. More detailed researches using sophisticated questionnaire will be conducted in the construction industry and petrochemical industry and relationships between the accidents rate and the safety activities will be compared between different industries. (author)

  3. Research on application of system of neutron, thermohydraulic and safety analysis codes in order to simulation of the Dalat Nuclear Research Reactor

    International Nuclear Information System (INIS)

    Pham Van Lam; Le Vinh Vinh; Huynh Ton Nghiem

    2004-01-01

    Requirements of neutron, thermohydraulic and safety analysis calculation are very important because of issuing new version of SAR for DNRR, research on construction of new research reactor and nuclear power plant. Research on application of system of neutron, thermohydraulic and safety analysis codes in order to simulation of the Dalat Nuclear Research Reactor has been done in the frame work of research theme in the year 2002-2003. The purposes of the research are maintaining safety operation of the DNRR and enhancement of man power and calculation and safety analysis tool potential. (author)

  4. Monitoring and reviewing research reactor safety in Australia

    International Nuclear Information System (INIS)

    Cairns, R.C.; Greenslade, G.K.

    1990-01-01

    Th research reactors operated by the Australian Nuclear Science and Technology Organization (ANSTO) comprise the 10 MW reactor HIFAR and the 100 kW reactor Moata. Although there are no power reactors in Australia the problems and issues of public concern which arise in the operation of research reactors are similar to those of power reactors although on a smaller scale. The need for independent safety surveillance has been recognized by the Australian Government and the ANSTO Act, 1987, required the Board of ANSTO to establish a Nuclear Safety Bureau (NSB) with responsibility to the Minister for monitoring and reviewing the safety of nuclear plant operated by ANSTO. The Executive Director of ANSTO operates HIFAR subject to compliance with requirements and arrangements contained in a formal Authorization from the Board of ANSTO. A Ministerial Direction to the Board of ANSTO requires the NSB to report to him, on a quarterly basis, matters relating to its functions of monitoring and reviewing the safety of ANSTO's nuclear plant. Experience has shown that the Authorization provides a suitable framework for the operational requirements and arrangements to be organised in a disciplined and effective manner, and also provides a basis for audits by the NSB by which compliance with the Board's safety requirements are monitored. Examples of the way in which the NSB undertakes its monitoring and reviewing role are given. Moata, which has a much lower operating power level and fission product inventory than HIFAR, has not been subject to a formal Authorization to date but one is under preparation

  5. Reports of reactor safety research projects sponsored by the Federal Ministry for Research and Technology (BMFT)

    International Nuclear Information System (INIS)

    1984-04-01

    Each progress report represents a compilation of individual reports about objectives, the work performed, the results, the next steps of the work etc. the individual reports are prepared in a standard form by the contractors themselves as a documentation of their progress in work and published by he FB (Research Coordination Department), Forschungsbetreuung at the GRS, within the framework of general information of progress in reactor safety research. The individual reports are classified according to the research program on the safety of LWRS 1977-1980 of the BMFT. Another table of contents uses the same classification system as applied in the nuclear safety index of the CEC (Commission of the European Communities) and the OECD (Organization for Economic Cooperation and Development). The reports are arranged in the sequence of their project numbers. (orig.) [de

  6. Conducting Clinically Based Intimate Partner Violence Research: Safety Protocol Recommendations.

    Science.gov (United States)

    Anderson, Jocelyn C; Glass, Nancy E; Campbell, Jacquelyn C

    Maintaining safety is of utmost importance during research involving participants who have experienced intimate partner violence (IPV). Limited guidance on safety protocols to protect participants is available, particularly information related to technology-based approaches to informed consent, data collection, and contacting participants during the course of a study. The purpose of the article is to provide details on the safety protocol developed and utilized with women receiving care at an urban HIV clinic and who were taking part in an observational study of IPV, mental health symptoms, and substance abuse and their relationship to HIV treatment adherence. The protocol presents the technological strategies to promote safety and allow autonomy in participant decision-making throughout the research process, including Voice over Internet Protocol telephone numbers, and tablet-based eligibility screening and data collection. Protocols for management of participants at risk for suicide and/or intimate partner homicide that included automated high-risk messaging to participants and research staff and facilitated disclosure of risk to clinical staff based on participant preferences are discussed. Use of technology and partnership with clinic staff helped to provide an environment where research regarding IPV could be conducted without undue burden or risk to participants. Utilizing tablet-based survey administration provided multiple practical and safety benefits for participants. Most women who screened into high-risk categories for suicide or intimate partner homicide did not choose to have their results shared with their healthcare providers, indicating the importance of allowing participants control over information sharing whenever possible.

  7. 75 FR 15611 - Safety Zone; United Portuguese SES Centennial Festa, San Diego Bay, San Diego, CA

    Science.gov (United States)

    2010-03-30

    ...-AA00 Safety Zone; United Portuguese SES Centennial Festa, San Diego Bay, San Diego, CA AGENCY: Coast... navigable waters of the San Diego Bay in support of the United Portuguese SES Centennial Festa. This... Centennial Festa, which will include a fireworks presentation originating from a tug and barge combination in...

  8. 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

  9. Proceedings of the research conference on post-accident waste management safety (RCWM2016) and the technical seminar on safety research for radioactive waste storage

    International Nuclear Information System (INIS)

    Motooka, Takafumi; Yamagishi, Isao

    2017-03-01

    Collaborative Laboratories for Advanced Decommissioning Science (CLADS) is responsible to promote international cooperation in the R and D activities on the decommissioning of Fukushima Daiichi Nuclear Power Station and to develop the necessary human resources. CLADS held the Research Conference on Post-accident Waste Management Safety (RCWM2016) on 7th November, 2016 and the Technical Seminar on Safety Research for Radioactive Waste Storage on 8th November, 2016. This report compiles the abstracts and the presentation materials in the above conference and seminar. (author)

  10. Department of Nuclear Safety Research and Nuclear Facilities annual report 1995

    International Nuclear Information System (INIS)

    Majborn, B.; Brodersen, K.; Damkjaer, A.; Floto, H.; Jacobsen, U.; Oelgaard, P.L.

    1996-03-01

    The report presents a summary of the work of the Department of Nuclear Safety Research and Nuclear Facilities in 1995. The department's research and development activities are organized in three research programmes: Radiation Protection, Reactor Safety, and Radioanalytical Chemistry. The nuclear facilities operated by the department include the Research Reactor DR3, the Isotope Laboratory, the Waste Treatment Plant, and the Educational Reactor DR1. Lists of staff and publications are included together with a summary of the staff's participation in national and international committees. (au) 5 tabs., 21 ills

  11. Department of Nuclear Safety Research and Nuclear Facilities annual report 1995

    Energy Technology Data Exchange (ETDEWEB)

    Majborn, B.; Brodersen, K.; Damkjaer, A.; Floto, H.; Jacobsen, U.; Oelgaard, P.L. [eds.

    1996-03-01

    The report presents a summary of the work of the Department of Nuclear Safety Research and Nuclear Facilities in 1995. The department`s research and development activities are organized in three research programmes: Radiation Protection, Reactor Safety, and Radioanalytical Chemistry. The nuclear facilities operated by the department include the Research Reactor DR3, the Isotope Laboratory, the Waste Treatment Plant, and the Educational Reactor DR1. Lists of staff and publications are included together with a summary of the staff`s participation in national and international committees. (au) 5 tabs., 21 ills.

  12. Research on the Evaluation System for Rural Public Safety Planning

    Institute of Scientific and Technical Information of China (English)

    Ming; SUN; Jianxin; YAN

    2014-01-01

    The indicator evaluation system is introduced to the study of rural public safety planning in this article.By researching the current rural public safety planning and environmental carrying capacity,we select some carrying capacity indicators influencing the rural public safety,such as land,population,ecological environment,water resources,infrastructure,economy and society,to establish the environmental carrying capacity indicator system.We standardize the indicators,use gray correlation analysis method to determine the weight of indicators,and make DEA evaluation of the indicator system,to obtain the evaluation results as the basis for decision making in rural safety planning,and provide scientific and quantified technical support for rural public safety planning.

  13. Self Assessment for the Safety of Research Reactor in Indonesia

    International Nuclear Information System (INIS)

    Melani, Ai; Chang, Soon Heung

    2008-01-01

    At the present Indonesia has no nuclear power plant in operation yet, although it is expected that the first nuclear power plant will be operated and commercially available in around the year of 2016 to 2017 in Muria Peninsula. National Nuclear Energy Agency (BATAN) has three research reactor; which are: Reactor Triga Mark II at Bandung, Reactor Kartini at Yogyakarta and Reactor Serbaguna (Multi Purpose Reactor) at Serpong. The Code of Conduct on the Safety of Research Reactors establishes 'best practice' guidelines for the licensing, construction and operation of research reactors. In this paper the author use the requirement in code of conduct to review the safety of research reactor in Indonesia

  14. Nursing assessment of continuous vital sign surveillance to improve patient safety on the medical/surgical unit.

    Science.gov (United States)

    Watkins, Terri; Whisman, Lynn; Booker, Pamela

    2016-01-01

    Evaluate continuous vital sign surveillance as a tool to improve patient safety in the medical/surgical unit. Failure-to-rescue is an important measure of hospital quality. Patient deterioration is often preceded by changes in vital signs. However, continuous multi-parameter vital sign monitoring may decrease patient safety with an abundance of unnecessary alarms. Prospective observational study at two geographically disperse hospitals in a single hospital system. A multi-parameter vital sign monitoring system was installed in a medical/surgical unit in Utah and one in Alabama providing continuous display of SpO2, heart rate, blood pressure and respiration rate on a central station. Alarm thresholds and time to alert annunciations were set based on prior analysis of the distribution of each vital sign. At the end of 4 weeks, nurses completed a survey on their experience. An average alert per patient, per day was determined retrospectively from the saved vital signs data and knowledge of the alarm settings. Ninety-two per cent of the nurses agreed that the number of alarms and alerts were appropriate; 54% strongly agreed. On average, both units experienced 10·8 alarms per patient, per day. One hundred per cent agreed the monitor provided valuable patient data that increased patient safety; 79% strongly agreed. Continuous, multi-parameter patient monitoring could be performed on medical/surgical units with a small and appropriate level of alarms. Continuous vital sign assessment may have initiated nursing interventions that prevented failure-to-rescue events. Nurses surveyed unanimously agreed that continuous vital sign surveillance will help enhance patient safety. Nursing response to abnormal vital signs is one of the most important levers in patient safety, by providing timely recognition of early clinical deterioration. This occurs through diligent nursing surveillance, involving assessment, interpretation of data, recognition of a problem and meaningful

  15. 33 CFR 3.40-15 - Sector New Orleans Marine Inspection Zone and Captain of the Port Zone; Marine Safety Unit Morgan...

    Science.gov (United States)

    2010-07-01

    ... 33 Navigation and Navigable Waters 1 2010-07-01 2010-07-01 false Sector New Orleans Marine....40-15 Sector New Orleans Marine Inspection Zone and Captain of the Port Zone; Marine Safety Unit Morgan City. Sector New Orleans' office is located in New Orleans, LA. A subordinate unit, Marine Safety...

  16. State of arts and outlook of research reactor safety management promoted by IAEA

    International Nuclear Information System (INIS)

    Hao Xiaofeng

    2005-01-01

    This paper presents the recent activities of IAEA on the research reactor safety, and the trends in the future. According to the present situation of national research reactors, some suggestions are proposed for the cooperation with IAEA on research reactor safety. (author)

  17. Annual plan of research on safety techniques against low level radioactive wastes, FY1994-FY1999

    International Nuclear Information System (INIS)

    1994-01-01

    The safety research on the disposal of low level radioactive waste has been promoted based on the annual plan decided by the committee on radiative waste safety regulation of the Nuclear Safety Commission. Hereafter, the disposal of low level radioactive waste in ocean is never selected. As to the subjects of the safety research which should be carried out for five years from 1994, the necessity, the contents of research, the organs that carry out the research and so on were deliberated, and the results are made into the annual plan, therefore, it is reported. The way of thinking on the safety research, the contents for which efforts should be exerted as the safety research, and the matters to which attention should be paid are shown. As for the annual plan of safety research, the necessity and the outline of the safety research on the disposal in strata, the concrete subjects and their contents, and the necessity and the outline of the safety research on the reuse, the concrete subjects and their contents are reported. The radioactive waste is those produced by the operation of nuclear reactor facilities, those containing TRU nuclides and RI waste. (K.I.)

  18. Contribution of the Retrovirus Epidemiology Donor Study (REDS to research on blood transfusion safety in Brazil

    Directory of Open Access Journals (Sweden)

    Paula Loureiro

    2014-04-01

    Full Text Available The Retrovirus Epidemiology Donor Study (REDS program was established in the United States in 1989 with the purpose of increasing blood transfusion safety in the context of the HIV/AIDS and human T-lymphotropic virus epidemics. REDS and its successor, REDS-II were at first conducted in the US, then expanded in 2006 to include international partnerships with Brazil and China. In 2011, a third wave of REDS renamed the Recipient Epidemiology and Donor Evaluation Study-III (REDS-III was launched. This seven-year research program focuses on both blood banking and transfusion medicine research in the United States of America, Brazil, China, and South Africa. The main goal of the international programs is to reduce and prevent the transmission of HIV/AIDS and other known and emerging infectious agents through transfusion, and to address research questions aimed at understanding global issues related to the availability of safe blood. This article describes the contribution of REDS-II to transfusion safety in Brazil. Articles published from 2010 to 2013 are summarized, including database analyses to characterize blood donors, deferral rates, and prevalence, incidence and residual risk of the main blood-borne infections. Specific studies were developed to understand donor motivation, the impact of the deferral questions, risk factors and molecular surveillance among HIV-positive donors, and the natural history of Chagas disease. The purpose of this review is to disseminate the acquired knowledge and briefly summarize the findings of the REDS-II studies conducted in Brazil as well as to introduce the scope of the REDS-III program that is now in progress and will continue through 2018.

  19. Periodical safety review of units 1 and 2 of PAKS NPP. Examples from summary report

    International Nuclear Information System (INIS)

    Hammar, K.

    1998-01-01

    On the basis of American practice of qualification and relevant IAEA recommendations detailed guidelines of the qualification procedure were developed and executed on the Units 1 and 2 of the Paks NPP. Periodic safety supervision will be performed by evaluation of the following reports to be submitted by NPP: real technical conditions of the facility; existing practice and proposals for equipment qualification; evaluation of the existing safety reports estimating their validity up to the plant lifetime; ageing and ageing management; procedures of operation, maintenance, supervision; organisation and administration; safety impact of human factor, training, education, qualification of personnel

  20. Ignalina Safety Analysis Group's report for the year 1998

    International Nuclear Information System (INIS)

    Uspuras, E.; Augutis, J.; Bubelis, E.; Cesna, B.; Kaliatka, A.

    1999-02-01

    Results of Ignalina NPP Safety Analysis Group's research are presented. The main fields of group's activities in 1998 were following: safety analysis of reactor's cooling system, safety analysis of accident localization system, investigation of the problem graphite - fuel channel, reactor core modelling, assistance to the regulatory body VATESI in drafting regulations and reviewing safety reports presented by Ignalina NPP during the process of licensing of unit 1

  1. 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.)

  2. NRC safety research in support of regulation, FY 1992

    International Nuclear Information System (INIS)

    1993-05-01

    This report, the eighth 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 FY 1992. A special emphasis on accomplishments in nuclear power plant aging research reflects recognition that a number of plants are entering the final portion of their original 40-year operating licenses and that, in addition to current aging effects, a focus on safety considerations for license renewal becomes timely. The primary purpose of performing regulatory research is to develop and provide the Commission and its staff with the technical bases for regulatory decisions on the safe operation of licensed nuclear reactors and facilities, to find unknown or unexpected safety problems, and to develop data and related information for the purpose of revising the Commission's rules, regulatory guides, or other guidance

  3. Dissemination and Implementation Research for Occupational Safety and Health.

    Science.gov (United States)

    Dugan, Alicia G; Punnett, Laura

    2017-12-01

    The translation of evidence-based health innovations into real-world practice is both incomplete and exceedingly slow. This represents a poor return on research investment dollars for the general public. U.S. funders of health sciences research (e.g., NIH, CDC, NIOSH) are increasingly calling for dissemination plans, and to a lesser extent for dissemination and implementation (D&I) research, which are studies that examine the effectiveness of D&I efforts and strategies and the predictors of D&I success. For example, rather than merely broadcasting information about a preventable hazard, D&I research in occupational safety and health (OSH) might examine how employers or practitioners are most likely to receive and act upon that information. We propose here that D&I research should be seen as a dedicated and necessary area of study within OSH, as a way to generate new knowledge that can bridge the research-to-practice gap. We present D&I concepts, frameworks, and examples that can increase the capacity of OSH professionals to conduct D&I research and accelerate the translation of research findings into meaningful everyday practice to improve worker safety and health.

  4. New control and safety rod unit for the training reactor of the Dresden Technical University

    International Nuclear Information System (INIS)

    Adam, E.; Schab, J.; Knorr, J.

    1983-01-01

    The extension of the experimental training of students at the training reactor AKR of the Dresden Technical University requires the reconstruction of the reactor with a new control and safety rod unit. The specific conditions at the AKR led to a new variant. Results of preliminary experiments, design and mode of operation of the first unit as well as hitherto gained operation experiences are presented. (author)

  5. Safety Design Requirements for The Interior Architecture of Scientific Research Laboratories

    International Nuclear Information System (INIS)

    ElDib, A.A.

    2014-01-01

    The paper discusses one of the primary objectives of interior architecture design of research laboratories (specially those using radioactive materials) where it should provide a safe, accessible environment for laboratory personnel to conduct their work. A secondary objective is to allow for maximum flexibility for safe research. Therefore, health and safety hazards must be anticipated and carefully evaluated so that protective measures can be incorporated into the interior architectural design of these facilities wherever possible. The interior architecture requirements discussed in this paper illustrate some of the basic health and safety design features required for new and remodeled laboratories.The paper discusses one of the primary objectives of interior architecture design of research laboratories (specially those using radioactive materials) where it should provide a safe, accessible environment for laboratory personnel to conduct their work. A secondary objective is to allow for maximum flexibility for safe research. Therefore, health and safety hazards must be anticipated and carefully evaluated so that protective measures can be incorporated into the interior architectural design of these facilities wherever possible. The interior architecture requirements discussed in this paper illustrate some of the basic health and safety design features required for new and remodeled laboratories.

  6. Fiscal 2000 pioneering research report on the research on advanced safety helicopter; 2000 nendo advanced safety helicopter no chosa kenkyu hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-03-01

    A survey was conducted concerning helicopter operating environments and the trends of related technologies in Japan and abroad, and the needs and seeds were grasped. Research was made to study technical problems and measures to solve them for the development of a safe, low-noise, and low-cost next-generation advanced safety helicopter (ASH). A market research was conducted on traffic systems in the future, state of aviation-related infrastructures and their future, current state of people's daily life which centers about locomotion, and the effect that ASH would impose on society. A technical research was carried out relative to flight safety, which involved EVS (enhanced vision system), information display system for helicopters, collision avoidance advisory for pilots, air collision prevention system/surveillance system for helicopters, obstacle detection/warning system for helicopters, blade deicing system for helicopters, and so forth. Detailed investigations were also conducted for technologies for reduction in the manufacturing, maintenance, and development costs, and for reduction in noise. (NEDO)

  7. Health and Safety Research Division progress report for period ending April 30, 1978

    Energy Technology Data Exchange (ETDEWEB)

    Kaye, S.V.

    1978-08-01

    The research goal of the Health and Safety Research Division is to conduct basic and applied research that contributes new scientific knowledge with emphasis in biophysical areas that lead to a better understanding of how alternative energy-related technologies affect man. Included in the basic research are fundamental processes that are important to understand formation, mobility, toxicity, detection, and characterization of pollutants. The applied research includes the integration of data from basic and applied studies through development of concepts and methodologies that can be used for energy-related assessments with primary focus on the health and safety of man. The division has no responsibilities for on-site health and safety.

  8. Safety Culture Evaluation at Research Reactors of Pakistan Atomic Energy Commission

    International Nuclear Information System (INIS)

    Qamar, M.A.; Saeed, A.; Shah, J.H.

    2016-01-01

    The concept of safety culture was presented by IAEA in document INSAG-4 (1991), delineated as “assembly of characteristics and attitudes in organizations and individuals which establish that, as an overriding priority, nuclear plant safety issues receive the attention warranted by their significance”. The purpose of this paper is to describe the evaluation of safety culture at research reactors of the Pakistan Atomic Energy Commission (PAEC). Evaluating the safety culture of a particular organization poses some challenges which can be resolved by using safety culture evaluation models like those of Sachein (1992) and Harber-Barrier(1998). In PAEC, safety culture is the integral part of management system which not only promotes safety culture throughout the organization but also enhances its significance. To strengthen the safety culture, PAEC is also participating in a number of international and regional meetings of IAEA regarding safety culture. PAEC and the national regulator Pakistan Nuclear Regulatory Authority (PNRA) are also arranging workshops, peer reviews, sharing operational experiences and interacting with IAEA missions to enhance its capabilities in the field of safety culture. The Directorate General of Safety (DOS) is a corporate office of PAEC for safety and regulatory matters. DOS is in the process of implementing a program to evaluate safety culture at nuclear installations of PAEC to ensure that safety culture is included as a vital segment of the Integral Management System of the establishment. In this regard, training sessions and lectures on safety culture evaluation are normally conducted in PAEC for awareness and enhancement of the safety culture program. Safety culture is also addressed in PNRA Regulations like PAK-909 and PAK-913. In this paper we will focus on the safety culture evaluation in our research reactors, i.e., PARR-1 and PARR-2. The evaluation results will be based on observations, interviews of employees, group discussions

  9. A Review of Research on Driving Styles and Road Safety.

    Science.gov (United States)

    Sagberg, Fridulv; Selpi; Piccinini, Giulio Francesco Bianchi; Engström, Johan

    2015-11-01

    The aim of this study was to outline a conceptual framework for understanding driving style and, on this basis, review the state-of-the-art research on driving styles in relation to road safety. Previous research has indicated a relationship between the driving styles adopted by drivers and their crash involvement. However, a comprehensive literature review of driving style research is lacking. A systematic literature search was conducted, including empirical, theoretical, and methodological research, on driving styles related to road safety. A conceptual framework was proposed whereby driving styles are viewed in terms of driving habits established as a result of individual dispositions as well as social norms and cultural values. Moreover, a general scheme for categorizing and operationalizing driving styles was suggested. On this basis, existing literature on driving styles and indicators was reviewed. Links between driving styles and road safety were identified and individual and sociocultural factors influencing driving style were reviewed. Existing studies have addressed a wide variety of driving styles, and there is an acute need for a unifying conceptual framework in order to synthesize these results and make useful generalizations. There is a considerable potential for increasing road safety by means of behavior modification. Naturalistic driving observations represent particularly promising approaches to future research on driving styles. Knowledge about driving styles can be applied in programs for modifying driver behavior and in the context of usage-based insurance. It may also be used as a means for driver identification and for the development of driver assistance systems. © 2015, Human Factors and Ergonomics Society.

  10. United Kingdom health research analyses and the benefits of shared data.

    Science.gov (United States)

    Carter, James G; Sherbon, Beverley J; Viney, Ian S

    2016-06-24

    To allow research organisations to co-ordinate activity to the benefit of national and international funding strategies requires assessment of the funding landscape; this, in turn, relies on a consistent approach for comparing expenditure on research. Here, we discuss the impact and benefits of the United Kingdom's Health Research Classification System (HRCS) in national landscaping analysis of health research and the pros and cons of performing large-scale funding analyses. The first United Kingdom health research analysis (2004/2005) brought together the 11 largest public and charity funders of health research to develop the HRCS and use this categorisation to examine United Kingdom health research. The analysis was revisited in 2009/2010 and again in 2014. The most recent quinquennial analysis in 2014 compiled data from 64 United Kingdom research organisations, accounting for 91% of all public/charitable health research funding in the United Kingdom. The three analyses summarise the United Kingdom's health research expenditure in 2004/2005, 2009/2010 and 2014, and can be used to identify changes in research activity and disease focus over this 10 year period. The 2004/2005 analysis provided a baseline for future reporting and evidence for a United Kingdom Government review that recommended the co-ordination of United Kingdom health research should be strengthened to accelerate the translation of basic research into clinical and economic benefits. Through the second and third analyses, we observed strategic prioritisation of certain health research activities and disease areas, with a strong trend toward increased funding for more translational research, and increases in specific areas such as research on prevention. The use of HRCS in the United Kingdom to analyse the research landscape has provided benefit both to individual participatory funders and in coordinating initiatives at a national level. A modest amount of data for each project is sufficient for a

  11. Research on advanced system safety assessment procedures (4)

    International Nuclear Information System (INIS)

    Suzuki, Kazuhiko; Shimada, Yukiyasu

    2001-03-01

    The past research reports in the area of safety engineering proposed the Computer-aided HAZOP system to be applied to Nuclear Reprocessing Facilities. Automated HAZOP system has great advantage compared with human analysts in terms of accuracy of the results, and time required to conduct HAZOP studies. This report surveys the literature on risk assessment and safety design based on the concept of independent protection layers (IPLs). Furthermore, to improve HAZOP System, tool is proposed to construct the basic model and the internal state model. Such HAZOP system is applied to analyze two kinds of processes, where the ability of the proposed system is verified. In addition, risk assessment support system is proposed to integrate safety design environment and assessment result to be used by other plants as well as to enable the underline plant to use other plants' information. This technique can be implemented using web-based safety information systems. (author)

  12. Methodology for the application of probabilistic safety assessment techniques (PSA) to the cobalt-therapy units in Cuba

    International Nuclear Information System (INIS)

    Vilaragut Llanes, J.J.; Ferro Fernandez, R.; Troncoso Fleitas, M.; Lozano Lima, B.; Fuente Puch, A. de la; Perez Reyes, Y.; Dumenigo Gonzalez, C.

    2001-01-01

    The applications of PSA techniques in the nuclear power plants during the last two decades and the positive results obtained for decision making in relation with safety, as a complement to deterministic methods, have increased their use in the rest of the nuclear applications. At present a large set of documents from international institutions can be found summarizing the investigations carried out in this field and promoting their use in radioactive facilities. Although still without a mandatory character, the new regulations on radiological safety also promote the complete or partial application of the PSA techniques in the safety assessment of the radiological practices. Also the IAEA, through various programs in which Cuba has been inserted, is taking a group of actions so that the nuclear community will encourage the application of the probabilistic risk methods for the evaluations and decision making with respect to safety. However, the fact that in no radioactive installation has a complete PSA study been carried out, makes that certain methodological aspects require to be improved and modified for the application of these techniques. This work presents the main elements for the use of PSA in the evaluation of the safety of cobalt-therapy units in Cuba. Also presented, as part of the results of the first stage of the Study, are the Guidelines that are being applied in a Research Contract with the Agency by the authors themselves, who belong to the CNSN, together with other specialists from the Cuban Ministry of Public Health. (author) [es

  13. Maintaining and Researching Port Safety: A Case Study of the Port of Kaohsiung

    OpenAIRE

    Tseng, Po-Hsing.; Pilcher, Nick.

    2017-01-01

    Maintaining port safety in full conformity with IMO standards is a requisite for every port and country. To do this, understanding the challenges and human factors involved is key. To date, much research has shed valuable light on these factors and considered how to address them. One aspect that is often noted is that both maintaining port safety and researching port safety presents numerous challenges. This paper considers both these aspects in the context of a case study of port safety in K...

  14. US nuclear safety. Review and experience

    International Nuclear Information System (INIS)

    Hanauer, S.H.

    1977-01-01

    The paper deals with the evolution of reactor safety principles, design bases, regulatory requirements, and experience in the United States. Safety concerns have evolved over the years, from reactivity transients and shut-down systems, to blowdowns and containment, to severe design basis accidents and mitigating systems, to the performance of actual materials, systems and humans. The primary safety concerns of one epoch have been superseded in considerable measure by those of later times. Successive plateaus of technical understanding are achieved by solutions being found to earlier problems. Design studies, research, operating experience and regulatory imperatives all contribute to the increased understanding and thus to the safety improvements adopted and accepted. The improvement of safety with time, and the ability of existing reactors to operate safely in the face of new concerns, has confirmed the correctness and usefulness of the defence-in-depth approach and safety margins used in safety design in the United States of America. A regulatory programme such as the one in the United States justifies its great cost by its important contributions to safety. Yet only the designers, constructors and operators of nuclear power plants can actually achieve public safety. The regulatory programme audits, assesses and spot-checks the actual work. Since neither materials nor human beings are flawless, mistakes will be made; that is why defence-in-depth and safety margins are provided. The regulatory programme should enhance safety by decreasing the frequency of uncorrected mistakes. Maintenance of public safety also requires technical and managerial competence and attention in the organizations responsible for nuclear plants as well as regulatory organizations. (author)

  15. Nuclear regulatory guides for LWR (PWR) fuel in Japan and some related safety research

    International Nuclear Information System (INIS)

    Ichikawa, M.

    1994-01-01

    The general aspects of licensing procedure for NPPs in Japan and regulatory guides are described. The expert committee reports closely related to PWR fuel are reviewed. Some major results of reactor safety research experiments at NSPR (Nuclear Safety Research Reactor of JAERI) used for establishment of related guide, are discussed. It is pointed out that the reactor safety research in Japan supports the regularity activities by establishing and revising guides and preparing the necessary regulatory data as well as improving nuclear safety. 10 figs., 4 refs

  16. Nuclear regulatory guides for LWR (PWR) fuel in Japan and some related safety research

    Energy Technology Data Exchange (ETDEWEB)

    Ichikawa, M [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan)

    1994-12-31

    The general aspects of licensing procedure for NPPs in Japan and regulatory guides are described. The expert committee reports closely related to PWR fuel are reviewed. Some major results of reactor safety research experiments at NSPR (Nuclear Safety Research Reactor of JAERI) used for establishment of related guide, are discussed. It is pointed out that the reactor safety research in Japan supports the regularity activities by establishing and revising guides and preparing the necessary regulatory data as well as improving nuclear safety. 10 figs., 4 refs.

  17. Nordic reactor safety research 1981-85

    International Nuclear Information System (INIS)

    Micheelsen, B.

    1986-01-01

    National resources in Denmark, Finland, Norway, and Sweden were put together with Nordic funds in the four-year research programme 1981-85 on selected areas of nuclear safety. The outcome of the programme, edited in four separate reports, is summarized, and important findings are listed in the areas of probabilistic risk assessment (PRA), loss-of-coolant accidents with small breaks, heat-transfer correlations, and corrosion in the nuclear industry. (author)

  18. Annual report on reactor safety research projects. Reporting period 2011. Progress report

    International Nuclear Information System (INIS)

    2011-01-01

    Within its competence for energy research the Federal Ministry of Economics and Technology (BMWi) sponsors research projects on the safety of nuclear power plants currently in operation. The objective of these projects is to provide fundamental knowledge, procedures and methods to contribute to realistic safety assessments of nuclear installations, to the further development of safety technology and to make use of the potential of innovative safety-related approaches. The Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS)mbH, by order of the BMWi, continuously issues information on the status of such research projects by publishing semi-annual and annual progress reports within the series of GRSF- Fortschrittsberichte (GRS-F-Progress Reports). Each progress report represents a compilation of individual reports about the objectives, work performed, results achieved, next steps of the work etc. The individual reports are prepared in a standard form by the research organisations themselves as documentation of their progress in work. The progress reports are published by the Project Management Agency/Authority Support Division of GRS. The reports as of the year 2000 are available in the Internet-based information system on results and data of reactor safety research (http://www.grs-fbw.de). The compilation of the reports is classified according to the classification system ''Joint Safety Research Index (JSRI)''. The reports are arranged in sequence of their project numbers. It has to be pointed out that the authors of the reports are responsible for the contents of this compilation. The BMWi does not take any responsibility for the correctness, exactness and completeness of the information nor for the observance of private claims of third parties. (orig.)

  19. Annual report on reactor safety research projects. Reporting period 2014. Progress report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2014-07-01

    Within its competence for energy research the Federal Ministry for Economic Affairs and Energy (BMWi) sponsors research projects on the safety of nuclear power plants currently in operation. The objective of these projects is to provide fundamental knowledge, procedures and methods to contribute to realistic safety assessments of nuclear installations, to the further development of safety technology and to make use of the potential of innovative safety-related approaches. The Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) gGmbH, by order of the BMWi, continuously issues information on the status of such research projects by publishing semi-annual and annual progress reports within the series of GRS-F-Fortschrittsberichte (GRS-F-Progress Reports). Each progress report represents a compilation of individual reports about the objectives, work performed, results achieved, next steps of the work etc. The individual reports are prepared in a standard form by the research organisations themselves as documentation of their progress in work. The progress reports are published by the Project Management Agency/Authority Support Division of GRS. The reports as of the year 2000 are available in the lnternet-based information system on results and data of reactor safety research (http://www.grs-fbw.de). The compilation of the reports is classified according to the classification system ''Joint Safety Research Index (JSRI)''. The reports are arranged in sequence of their project numbers. lt has to be pointed out that the authors of the reports are responsible for the contents of this compilation. The BMWi does not take any responsibility for the correctness, exactness and completeness of the information nor for the observance of private claims of third parties.

  20. Annual report on reactor safety research projects. Reporting period 2013. Progress report

    International Nuclear Information System (INIS)

    2013-01-01

    Within its competence for energy research the Federal Ministry of Economics and Technology (BMWi) sponsors research projects on the safety of nuclear power plants currently in operation. The objective of these projects is to provide fundamental knowledge, procedures and methods to contribute to realistic safety assessments of nuclear installations, to the further development of safety technology and to make use of the potential of innovative safety-related approaches. The Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS)mbH, by order of the BMWi, continuously issues information on the status of such research projects by publishing semi-annual and annual progress reports within the series of GRSF- Fortschrittsberichte (GRS-F-Progress Reports). Each progress report represents a compilation of individual reports about the objectives, work performed, results achieved, next steps of the work etc. The individual reports are prepared in a standard form by the research organisations themselves as documentation of their progress in work. The progress reports are published by the Project Management Agency/Authority Support Division of GRS. The reports as of the year 2000 are available in the Internet-based information system on results and data of reactor safety research (http://www.grs-fbw.de). The compilation of the reports is classified according to the classification system ''Joint Safety Research Index (JSRI)''. The reports are arranged in sequence of their project numbers. It has to be pointed out that the authors of the reports are responsible for the contents of this compilation. The BMWi does not take any responsibility for the correctness, exactness and completeness of the information nor for the observance of private claims of third parties. (orig.)

  1. Annual report on reactor safety research projects. Reporting period 2015. Progress report

    International Nuclear Information System (INIS)

    2015-01-01

    Within its competence for energy research the Federal Ministry for Economic Affairs and Energy (BMWi) sponsors research projects on the safety of nuclear power plants currently in operation. The objective of these projects is to provide fundamental knowledge, procedures and methods to contribute to realistic safety assessments of nuclear installations, to the further development of safety technology and to make use of the potential of innovative safety-related approaches. The Gesellschaft tor Anlagen- und Reaktorsicherheit (GRS) gGmbH, by order of the BMWi, continuously issues information on the status of such research projects by publishing semi-annual and annual progress reports within the series of GRS-F-Fortschrittsberichte (GRS-F-Progress Reports). Each progress report represents a compilation of individual reports about the objectives, work performed, results achieved, next steps of the work etc. The individual reports are ·' prepared in a standard form by the research organisations themselves as documentation of their progress in work. The progress reports are published by the Project Management Agency/Authority Support Division of GRS. The reports as of the year 2000 are available in the lnternet-based information system on results and data of reactor safety research (http://www.grs-fbw.de). The compilation of the reports is classified according to the classification system ''Joint Safety Research Index (JSRI)''. The reports are arranged in sequence of their project numbers. it has to be pointed out that the authors of the reports are responsible for the contents of this compilation. The BMWi does not take any responsibility for the correctness, exactness and completeness of the information nor for the observance of private claims of third parties.

  2. Reports on research projects sponsored by the Federal Minister for Research and Technology in the field of reactor safety

    International Nuclear Information System (INIS)

    1979-03-01

    Investigations on the safety of Light Water Reactors (LWR) being performed in the framework of the Research Program Reactor Safety (RS - Projects) are sponsored by the BMFT (Federal Minister for Research and Technology), Bundesminister fuer Forschung und Technologie. Objective of this program is to investigate in greater detail the safety margins of nuclear power plants and their systems and the further development of safety technology. Besides the investigations of LWR tasks first projects on the safety of FBR type reactors are sponsored by the BMFT. The GRS (Reactor Safety Association), Gesellschaft fuer Reaktorsicherheit mbH, by order of the BMFT, informs continuously of the status of such investigations by means of quarterly and annually publication of progress reports within the series GRS - F - Fortschrittsberichte (GRS - F - Progress Reports). Each progress report represents a compilation of individual reports about objectives, the work performed, the results, the next steps of the work etc. The individual reports are prepared in a standard form by the contractors themselves as a documentation of their progress in work. The individual reports are arranged according to the amended LWR Safety Research Program of the BMFT. Another table contents uses the same classification system as applied in the Nuclear Safety Index of the CEC European Communities and the OECD. (orig./HP) [de

  3. Twenty-second water reactor safety information meeting: Proceedings. Volume 3: Primary systems integrity; Structural and seismic engineering; Aging research, products and applications

    Energy Technology Data Exchange (ETDEWEB)

    Monteleone, S. [comp.] [Brookhaven National Lab., Upton, NY (United States)

    1995-04-01

    This three-volume report contains papers presented at the Twenty-Second Water Reactor Safety Information Meeting held at the Bethesda Marriott Hotel, Bethesda, Maryland, during the week of October 24--26, 1994. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included papers presented by researchers from Finland, France, Italy, Japan, Russia, and United Kingdom. The titles of the papers and the names of the authors have been updated and may differ from those that appeared in the final program of the meeting. Selected papers are indexed separately for inclusion in the Energy Science and Technology Database.

  4. Twenty-second water reactor safety information meeting: Proceedings. Volume 3: Primary systems integrity; Structural and seismic engineering; Aging research, products and applications

    International Nuclear Information System (INIS)

    Monteleone, S.

    1995-04-01

    This three-volume report contains papers presented at the Twenty-Second Water Reactor Safety Information Meeting held at the Bethesda Marriott Hotel, Bethesda, Maryland, during the week of October 24--26, 1994. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included papers presented by researchers from Finland, France, Italy, Japan, Russia, and United Kingdom. The titles of the papers and the names of the authors have been updated and may differ from those that appeared in the final program of the meeting. Selected papers are indexed separately for inclusion in the Energy Science and Technology Database

  5. KHNP special safety review

    International Nuclear Information System (INIS)

    Lee, Tae-Ho; Lee, Bang-Jin; Lee, Soung-Hee; Park, Goon-Cherl

    2009-01-01

    Commemorating the 30 year anniversary of commercial nuclear power plant operation in KOREA, Korea Hydro and Nuclear Power Co., Ltd. (KHNP) has conducted a Special Safety Review (SSR) of its 20 operating units to understand their safety performance and to identify any areas that need improvement. The SSR reviewed all 20 operating units for 2 weeks per site. Areas that were reviewed are Safety Margins, Plant Performance, Employee Safety, Employee Performance and Performance Improvement Process. Each review team consisted of international and domestic members. The international reviewers were from IAEA, WANO and INPO. The domestic reviewers consisted of professors, Engineering Company, Research Institute and KHNP experts. The review confirmed safe and reliable operations of the 20 nuclear units. The common understanding resulted from the SSR is as follows. Firstly, KHNP corporate and its plants confirmed and shared mutual understanding on recurring areas for improvements, especially in the areas of Organizational Effectiveness, Industrial Safety, Human Performance, Configuration Management, Operations, Equipment Performance and Material Condition. Secondly, KHNP understood that plant and department level performances are directly related to the leadership and competency of the management team including supervisors. Thirdly, the strengths of individual stations that consistently have produced good results need to be shared with the other KHNP stations. Finally, KHNP learned that strong corporate leadership and support are needed to resolve most of the areas for improvement since they are common to all KHNP stations. (author)

  6. Implementing evidence in an onco-haematology nursing unit: a process of change using participatory action research.

    Science.gov (United States)

    Abad-Corpa, Eva; Delgado-Hito, Pilar; Cabrero-García, Julio; Meseguer-Liza, Cristobal; Zárate-Riscal, Carmen Lourdes; Carrillo-Alcaraz, Andrés; Martínez-Corbalán, José Tomás; Caravaca-Hernández, Amor

    2013-03-01

    To implement evidence in a nursing unit and to gain a better understanding of the experience of change within a participatory action research. Study design of a participatory action research type was use from the constructivist paradigm. The analytical-methodological decisions were inspired by Checkland Flexible Systems for evidence implementation in the nursing unit. The study was carried out between March and November 2007 in the isolation unit section for onco-haematological patients in a tertiary level general university hospital in Spain. Accidental sampling was carried out with the participation of six nurses. Data were collected using five group meetings and individual reflections in participants' dairies. The participant observation technique was also carried out by researchers. Data analysis was carried out by content analysis. The rigorous criteria were used: credibility, confirmability, dependence, transferability and reflexivity. A lack of use of evidence in clinical practice is the main problem. The factors involved were identified (training, values, beliefs, resources and professional autonomy). Their daily practice (complexity in taking decisions, variability, lack of professional autonomy and safety) was compared with an ideal situation (using evidence it will be possible to normalise practice and to work more effectively in teams by increasing safety and professional recognition). It was decided to create five working areas about several clinical topics (mucositis, pain, anxiety, satisfaction, nutritional assessment, nauseas and vomiting, pressure ulcers and catheter-related problems) and seven changes in clinical practice were agreed upon together with 11 implementation strategies. Some reflections were made about the features of the study: the changes produced; the strategies used and how to improve them; the nursing 'subculture'; attitudes towards innovation; and the commitment as participants in the study and as healthcare professionals. The

  7. HTGR safety research at the Los Alamos National Laboratory

    International Nuclear Information System (INIS)

    Stroh, K.R.; Anderson, C.A.; Kirk, W.L.

    1982-01-01

    This paper summarizes activities undertaken at the Los Alamos National Laboratory as part of the High-Temperature Gas-Cooled Reactor (HTGR) Safety Research Program sponsored by the US Nuclear Regulatory Commission. Technical accomplishments and analysis capabilities in six broad-based task areas are described. These tasks are: fission-product technology, primary-coolant impurities, structural investigations, safety instrumentation and control systems, accident delineation, and phenomena modeling and systems analysis

  8. Nuclear safety requirements for operation licensing of Egyptian research reactors

    International Nuclear Information System (INIS)

    Ahmed, E.E.M.; Rahman, F.A.

    2000-01-01

    From the view of responsibility for health and nuclear safety, this work creates a framework for the application of nuclear regulatory rules to ensure safe operation for the sake of obtaining or maintaining operation licensing for nuclear research reactors. It has been performed according to the recommendations of the IAEA for research reactor safety regulations which clearly states that the scope of the application should include all research reactors being designed, constructed, commissioned, operated, modified or decommissioned. From that concept, the present work establishes a model structure and a computer logic program for a regulatory licensing system (RLS code). It applies both the regulatory inspection and enforcement regulatory rules on the different licensing process stages. The present established RLS code is then applied to the Egyptian Research Reactors, namely; the first ET-RR-1, which was constructed and still operating since 1961, and the second MPR research reactor (ET-RR-2) which is now in the preliminary operation stage. The results showed that for the ET-RR-1 reactor, all operational activities, including maintenance, in-service inspection, renewal, modification and experiments should meet the appropriate regulatory compliance action program. Also, the results showed that for the new MPR research reactor (ET-RR-2), all commissioning and operational stages should also meet the regulatory inspection and enforcement action program of the operational licensing safety requirements. (author)

  9. Towards harmonised self assessment of research reactor safety status in operating organisations

    International Nuclear Information System (INIS)

    Kirchsteiger, C.; Boeck, H.

    2006-01-01

    The objective of this paper is to describe the development of a methodology and corresponding web-based tool for mapping and cross-comparing the safety approaches in European and other Research Reactor (RR) facilities in order to detect the principal similarities and differences. As an example, the performance of a Probabilistic Safety Assessment (PSA) for RRs is mapped, as follows: is PSA performed at all? (Yes/No); if so, is PSA mandatory or just recommended? (Yes/No); what is the scope of PSA?, its objective? and practical use? (set of more detailed questions), etc. In this way, information on different types of safety verification practices and requirements for RRs from Europe, Argentina, Australia, Canada, South Africa and the USA has been collected in a systematic way and included in the web-based benchmarking tool DARES (DAtabase for REsearch Reactor Safety). DARES has been developed and filled with sample data by the European Commission's Joint Research Centre (JRC) together with members of the European Research Reactors Operator Group (RROG). A systematic mapping by using DARES in parallel to an international Working Group, consisting of both operators and authorities could be the starting point towards harmonisation of RR safety verification on an international level. In addition, the availability of a user-friendly Information System on the Internet such as DARES containing this information is considered a useful mechanism to exchange international experiences and practices in the area among qualified users. This approach is currently considered to be proposed to the International Atomic Energy Agency (IAES) as one possible application of the recently adopted IAEA Code of Conduct on the Safety of Research Reactors. The resulting process would be a self-assessment of the RR safety status in regulatory bodies and operating organisations relative to the guidance in the Code, practically realised and monitored by an Information System similar to DARES. (orig.)

  10. Research priorities for coordinating management of food safety and water quality.

    Science.gov (United States)

    Crohn, David M; Bianchi, Mary L

    2008-01-01

    Efforts to exclude disease organisms from farms growing irrigated lettuce and leafy vegetables on California's central coast are conflicting with traditionally accepted strategies to protect surface water quality. To begin resolving this dilemma, over 100 officials, researchers, and industry representatives gathered in April 2007 to set research priorities that could lead to effective co-management of both food safety and water quality. Following the meeting, research priorities were refined and ordered by way of a Delphi process completed by 35 meeting participants. Although water quality and food safety experts conceptualized the issues differently, there were no deep disagreements with respect to research needs. Top priority was given to investigating the fate of pathogens potentially present on farms. Intermediate priorities included characterizing the influence of specific farm management practices on food safety and improving our understanding of vector processes. A scientific subdiscipline focusing on competing risks is needed to characterize and resolve conflicts between human and environmental health.

  11. Optimal inspection and replacement periods of the safety system in Wolsung Nuclear Power Plant Unit 1 with an optimized cost perspective

    International Nuclear Information System (INIS)

    Jinil Mok; Poong Hyun Seong

    1996-01-01

    In this work, a model for determining the optimal inspection and replacement periods of the safety system in Wolsung Nuclear Power Plant Unit 1 is developed, which is to minimize economic loss caused by inadvertent trip and the system failure. This model uses cost benefit analysis method and the part for optimal inspection period considers the human error. The model is based on three factors as follows: (i) The cumulative failure distribution function of the safety system, (ii) The probability that the safety system does not operate due to failure of the system or human error when the safety system is needed at an emergency condition and (iii) The average probability that the reactor is tripped due to the failure of system components or human error. The model then is applied to evaluate the safety system in Wolsung Nuclear Power Plant Unit 1. The optimal replacement periods which are calculated with proposed model differ from those used in Wolsung NPP Unit 1 by about a few days or months, whereas the optimal inspection periods are in about the same range. (author)

  12. Safety requirements in the design of research reactors: A Canadian perspective

    International Nuclear Information System (INIS)

    Lee, A.G.; Langman, V.J.

    2000-01-01

    In Canada, the formal development of safety requirements for the design of research reactors in general began under an inter-organizational Small Reactor Criteria Committee. This committee developed safety and licensing criteria for use by several small reactor projects in their licensing discussions with the Atomic Energy Control Board. The small reactor projects or facilities represented included the MAPLE-X10 reactor, the proposed SES-10 heating reactor and its prototype, the SDR reactor at the Whiteshell Laboratories, the Korea Multipurpose Research Reactor (a.k.a., HANARO) in Korea, the SCORE project, and the McMaster University Nuclear Reactor. The top level set of criteria which form a safety philosophy and serve as a framework for more detailed developments was presented at an IAEA Conference in 1989. AECL continued this work to develop safety principles and design criteria for new small reactors. The first major application of this work has been to the design, safety analysis and licensing of the MAPLE 1 and 2 reactors for the MDS Nordion Medical Isotope Reactor Project. This paper provides an overview of the safety principles and design criteria. Examples of an implementation of these safety principles and design criteria are drawn from the work to design the MAPLE 1 and 2 reactors. (author)

  13. SAFETY

    CERN Multimedia

    Niels Dupont

    2013-01-01

    CERN Safety rules and Radiation Protection at CMS The CERN Safety rules are defined by the Occupational Health & Safety and Environmental Protection Unit (HSE Unit), CERN’s institutional authority and central Safety organ attached to the Director General. In particular the Radiation Protection group (DGS-RP1) ensures that personnel on the CERN sites and the public are protected from potentially harmful effects of ionising radiation linked to CERN activities. The RP Group fulfils its mandate in collaboration with the CERN departments owning or operating sources of ionising radiation and having the responsibility for Radiation Safety of these sources. The specific responsibilities concerning "Radiation Safety" and "Radiation Protection" are delegated as follows: Radiation Safety is the responsibility of every CERN Department owning radiation sources or using radiation sources put at its disposition. These Departments are in charge of implementing the requi...

  14. Proceedings of the Twenty-First Water Reactor Safety Information Meeting: Volume 1, Plenary session; Advanced reactor research; advanced control system technology; advanced instrumentation and control hardware; human factors research; probabilistic risk assessment topics; thermal hydraulics; thermal hydraulic research for advanced passive LWRs

    International Nuclear Information System (INIS)

    Monteleone, S.

    1994-04-01

    This three-volume report contains 90 papers out of the 102 that were presented at the Twenty-First Water Reactor Safety Information Meeting held at the Bethesda Marriott Hotel, Bethesda, Maryland, during the week of October 25--27, 1993. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included papers presented by researchers from France, Germany, Japan, Russia, Switzerland, Taiwan, and United Kingdom. The titles of the papers and the names of the authors have been updated and may differ from those that appeared in the final program of the meeting. Individual papers have been cataloged separately. This document, Volume 1 covers the following topics: Advanced Reactor Research; Advanced Instrumentation and Control Hardware; Advanced Control System Technology; Human Factors Research; Probabilistic Risk Assessment Topics; Thermal Hydraulics; and Thermal Hydraulic Research for Advanced Passive Light Water Reactors

  15. Proceedings of the Twenty-First Water Reactor Safety Information Meeting: Volume 1, Plenary session; Advanced reactor research; advanced control system technology; advanced instrumentation and control hardware; human factors research; probabilistic risk assessment topics; thermal hydraulics; thermal hydraulic research for advanced passive LWRs

    Energy Technology Data Exchange (ETDEWEB)

    Monteleone, S. [Brookhaven National Lab., Upton, NY (United States)] [comp.

    1994-04-01

    This three-volume report contains 90 papers out of the 102 that were presented at the Twenty-First Water Reactor Safety Information Meeting held at the Bethesda Marriott Hotel, Bethesda, Maryland, during the week of October 25--27, 1993. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included papers presented by researchers from France, Germany, Japan, Russia, Switzerland, Taiwan, and United Kingdom. The titles of the papers and the names of the authors have been updated and may differ from those that appeared in the final program of the meeting. Individual papers have been cataloged separately. This document, Volume 1 covers the following topics: Advanced Reactor Research; Advanced Instrumentation and Control Hardware; Advanced Control System Technology; Human Factors Research; Probabilistic Risk Assessment Topics; Thermal Hydraulics; and Thermal Hydraulic Research for Advanced Passive Light Water Reactors.

  16. Safety Experts Complete IAEA Nuclear Regulatory Review of the United States

    International Nuclear Information System (INIS)

    2010-01-01

    Full text: An international team of senior nuclear safety experts today completed a two-week International Atomic Energy Agency (IAEA) review of the governmental and regulatory framework for nuclear safety in the United States. The team identified good practices within the U.S. system and offered suggestions for ways the U.S. Nuclear Regulatory Commission (NRC) could improve. The IAEA has conveyed the team's main conclusions to the NRC, and a final report will be submitted to the NRC in about two months. At the request of the United States, the IAEA assembled a team of 19 international experts to conduct an Integrated Regulatory Review Service (IRRS) mission. This mission was a peer review based on the IAEA Safety Standards. It was not an inspection, nor an audit. The experts came from 14 different countries: Canada, China, the Czech Republic, Finland, France, Italy, Japan, Mexico, the Republic of Korea, Slovenia, Spain, Sweden, Switzerland, and the United Kingdom. Team leader Jukka Laaksonen of Finland said: ''We found a comprehensive, consistent, and mature regulatory system run by the NRC, which has a strong drive for continuous improvement.' The scope of the mission included the U.S. regulatory framework and the regulation of the nuclear plant operation. The mission was conducted from 18 to 29 October, mainly at NRC headquarters outside of Washington, D.C. To study U.S. regulatory activities, the mission conducted a series of interviews and discussions with NRC staff and other organizations to help assess the effectiveness of the regulatory system. In addition, the team observed regulatory activities at two operating nuclear power reactors and an emergency preparedness exercise. The IAEA's IRRS coordinator Gustavo Caruso said, ''This mission represents a milestone for the IRRS program because the U.S. regulatory system is the largest in the world and many nations look to it. The IRRS is a useful tool that allows host nations to gain guidance from experienced

  17. Safety re-assessment of AECL test and research reactors

    International Nuclear Information System (INIS)

    Winfield, D.J.

    1990-01-01

    Atomic Energy of Canada Limited currently has four operating engineering test/research reactors of various sizes and ages; a new isotope-production reactor Maple-X10, under construction at Chalk River Nuclear Laboratories (CRNL), and a heating demonstration reactor, SDR, undergoing high-power commissioning at Whiteshell Nuclear Research Establishment (WNRE). The company is also performing design studies of small reactors for hot water and electricity production. The older reactors are ZED-2, PTR, NRX, and NRU; these range in age from 42 years (NRX) to 29 years (ZED-2). Since 1984, limited-scope safety re-assessments have been underway on three of these reactors (ZED-2, NRX AND NRU). ZED-2 and PTR are operated by the Reactor Physics Branch; all other reactors are operated by the respective site Reactor Operations Branches. For the older reactors the original safety reports produced were entirely deterministic in nature and based on the design-basis accident concept. The limited scope safety re-assessments for these older reactors, carried out over the past 5 years, have comprised both quantitative probabilistic safety-assessment techniques, such as event tree and fault analysis, and/or qualitative techniques, such as failure mode and effect analysis. The technique used for an individual assessment was dependent upon the specific scope required. This paper discusses the types of analyses carried out, specific insights/recommendations resulting from the analysis, and the plan for future analysis. In addition, during the last four years safety assessments have been carried out on the new isotope-, heat-, and electricity-producing reactors, as part of the safety design review, commissioning and licensing activities

  18. International symposium on research reactor utilization, safety and management. Book of extended synopses

    International Nuclear Information System (INIS)

    1999-01-01

    The Symposium, considered as an important meeting of the owners and operators of research reactors as well as scientists concerned with problems of research reactors operation, management and safety covered the following topics: global and regional overview of research reactors, research reactors utilisation, research reactors safety, research reactors management, research reactors engineering. IAEA Research Reactors Database (RRDB) contains data concerning 291 operational research reactors, 247 shutdown reactors, 106 decommissioned reactors, 15 under construction and 15 new reactors planned. There is quite an even distribution of operational research reactors among 58 countries. Although about 66% of operational research reactors described in the RRDB are over 30 years old, the number of research reactors under construction or planned appears to have increased in recent years. According to the RRDB, the major applications of research reactors are in the field of neutron activation analysis, isotope production and neutron scattering work. Great concern was shown for several aspects of research reactors safety, especially since the average age of the operating research reactors is almost 30 years. Ageing problems involve more than the degradation of properties of the materials. Issues such as outdated equipment, lack of spare parts, outdating of the control and documentation systems related to the reactor, as well as budgetary limitations, affect the safety of some reactors. There are serious problems related to the spent fuel condition and the ageing of fuel storage facilities, in particular corrosion and leakage. The outstanding issues of concern are life extension of the spent fuel storage facilities and the future of take-back programmes of foreign research reactor fuels that will not be continued. A number of discussions related to safety requirements were focused on licensing and regulatory issues, especially in the case of older research reactors and those

  19. International symposium on research reactor utilization, safety and management. Book of extended synopses

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-11-01

    The Symposium, considered as an important meeting of the owners and operators of research reactors as well as scientists concerned with problems of research reactors operation, management and safety covered the following topics: global and regional overview of research reactors, research reactors utilisation, research reactors safety, research reactors management, research reactors engineering. IAEA Research Reactors Database (RRDB) contains data concerning 291 operational research reactors, 247 shutdown reactors, 106 decommissioned reactors, 15 under construction and 15 new reactors planned. There is quite an even distribution of operational research reactors among 58 countries. Although about 66% of operational research reactors described in the RRDB are over 30 years old, the number of research reactors under construction or planned appears to have increased in recent years. According to the RRDB, the major applications of research reactors are in the field of neutron activation analysis, isotope production and neutron scattering work. Great concern was shown for several aspects of research reactors safety, especially since the average age of the operating research reactors is almost 30 years. Ageing problems involve more than the degradation of properties of the materials. Issues such as outdated equipment, lack of spare parts, outdating of the control and documentation systems related to the reactor, as well as budgetary limitations, affect the safety of some reactors. There are serious problems related to the spent fuel condition and the ageing of fuel storage facilities, in particular corrosion and leakage. The outstanding issues of concern are life extension of the spent fuel storage facilities and the future of take-back programmes of foreign research reactor fuels that will not be continued. A number of discussions related to safety requirements were focused on licensing and regulatory issues, especially in the case of older research reactors and those

  20. Integrated plant safety assessment, Systematic Evaluation Program: Dresden Nuclear Power Station, Unit 2 (Docket No. 50-237)

    International Nuclear Information System (INIS)

    1989-10-01

    The US Nuclear Regulatory Commission (NRC) has prepared Supplement 1 to the final Integrated Plant Safety Assessment Report (IPSAR) (NUREG-0823), under the scope of the Systematic Evaluation Program (SEP), for the Commonwealth Edison Company (CECo) Dresden Nuclear Power Station, Unit 2 located in Grundy County, Illinois. The NRC initiated the SEP to provide the framework for reviewing the design of older operating nuclear reactor plants to reconfirm and document their safety. This report documents the review completed by means of the SEP for those issues that required refined engineering evaluations or the continuation of ongoing evaluations subsequent to issuing the final IPSAR for Dresden Unit 2. The review was provided for (1) an assessment of the significance of differences between current technical positions on selected issues and those that existed when Dresden Unit 2 was licensed, (2) a basis for deciding on how these differences should be resolved in an integrated plant review, and (3) a documented evaluation of plant safety. The final IPSAR and this supplement forms part of the bases for considering the conversion of the existing provisional operating license to a full-term operating license. 83 refs., 9 tabs