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Sample records for safety issue gsi

  1. A study for the domestic application plan of the Generic Safety Issue(GSI) for the Pressurized Heavy Water Reactor

    International Nuclear Information System (INIS)

    Lee, Un Chul; Jang, Jin Wook; Lee, Sang Kyung; Lee, Doo Yong; Park, Chang Hwan

    2002-03-01

    In this study, a base work to construct the database of the domestic and foreign GSls were done through performing the deviation of GSls for the PHWR by investigating the development trend of international joint studies and the GSls of 4 countries as the PHWR state and examined the IAEA acceptance of GSls classification for the GSls of Canada, Korea Republic of, Argentina and India. We evaluated the possibility of application of the safety Issue for PHWR by investigating causes, contents and follow-up measures of each items. To evaluate the domestic application validity of the safety issue, We made the investigation matrix for the safety issue of each countries and also are reflecting new results in investigation matrix by examining IAEA PHWR GSI development trend. We intended to derive the GSls which are most appropriate in our PHWR by examining every issues. the derived GSls are divided into the design parts and the operation parts. And they have to be solved as soon as possible

  2. A study for the domestic application plan of the Generic Safety Issue(GSI) for the Pressurized Heavy Water Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Un Chul; Jang, Jin Wook; Lee, Sang Kyung; Lee, Doo Yong; Park, Chang Hwan [Seoul National Univ., Seoul (Korea, Republic of)

    2002-03-15

    In this study, a base work to construct the database of the domestic and foreign GSls were done through performing the deviation of GSls for the PHWR by investigating the development trend of international joint studies and the GSls of 4 countries as the PHWR state and examined the IAEA acceptance of GSls classification for the GSls of Canada, Korea Republic of, Argentina and India. We evaluated the possibility of application of the safety Issue for PHWR by investigating causes, contents and follow-up measures of each items. To evaluate the domestic application validity of the safety issue, We made the investigation matrix for the safety issue of each countries and also are reflecting new results in investigation matrix by examining IAEA PHWR GSI development trend. We intended to derive the GSls which are most appropriate in our PHWR by examining every issues. the derived GSls are divided into the design parts and the operation parts. And they have to be solved as soon as possible.

  3. Generic Safety Issue (GSI) 171 -- Engineered Safety Feature (ESF) failure from a loop subsequent to LOCA: Assessment of plant vulnerability and CDF contributions

    International Nuclear Information System (INIS)

    Martinez-Guridi, G.; Samanta, P.; Chu, L.; Yang, J.

    1998-01-01

    Generic Safety Issue 171 (GSI-171), Engineered Safety Feature (ESF) from a Loss Of Offsite Power (LOOP) subsequent to a Loss Of Coolant Accident (LOCA), deals with an accident sequence in which a LOCA is followed by a LOOP. This issue was later broadened to include a LOOP followed by a LOCA. Plants are designed to handle a simultaneous LOCA and LOOP. In this paper, the authors address the unique issues that are involved i LOCA with delayed LOOP (LOCA/LOOP) and LOOP with delayed LOCA (LOOP/LOCA) accident sequences. LOCA/LOOP accidents are analyzed further by developing event-tree/fault-tree models to quantify their contributions to core-damage frequency (CDF) in a pressurized water reactor and a boiling water reactor (PWR and a BWR). Engineering evaluation and judgments are used during quantification to estimate the unique conditions that arise in a LOCA/LOOP accident. The results show that the CDF contribution of such an accident can be a dominant contributor to plant risk, although BWRs are less vulnerable than PWRs

  4. New Safety rules

    CERN Multimedia

    Safety Commission

    2008-01-01

    The revision of CERN Safety rules is in progress and the following new Safety rules have been issued on 15-04-2008: Safety Procedure SP-R1 Establishing, Updating and Publishing CERN Safety rules: http://cern.ch/safety-rules/SP-R1.htm; Safety Regulation SR-S Smoking at CERN: http://cern.ch/safety-rules/SR-S.htm; Safety Regulation SR-M Mechanical Equipment: http://cern.ch/safety-rules/SR-M.htm; General Safety Instruction GSI-M1 Standard Lifting Equipment: http://cern.ch/safety-rules/GSI-M1.htm; General Safety Instruction GSI-M2 Standard Pressure Equipment: http://cern.ch/safety-rules/GSI-M2.htm; General Safety Instruction GSI-M3 Special Mechanical Equipment: http://cern.ch/safety-rules/GSI-M3.htm. These documents apply to all persons under the Director General’s authority. All Safety rules are available at the web page: http://www.cern.ch/safety-rules The Safety Commission

  5. Review of current literature related to GSI-15

    International Nuclear Information System (INIS)

    Lipinski, R.E.

    1991-01-01

    EG and G Idaho is evaluating the structural integrity of Reactor Pressure Vessel Supports as part of its resolution of NRC Generic Safety Issue (GSI) 15, 'Radiation effects on Reactor Vessel Supports'. Structural analyses have been performed by the NRC, ORNL, LLNL, Portland General Electric Co., and several consultants. Two methods of analyses were used. This paper contains a short discussion of the analyses and the merits of the two analysis methods. (author)

  6. New set of Chemical Safety rules

    CERN Multimedia

    HSE Unit

    2011-01-01

    A new set of four Safety Rules was issued on 28 March 2011: Safety Regulation SR-C ver. 2, Chemical Agents (en); General Safety Instruction GSI-C1, Prevention and Protection Measures (en); General Safety Instruction GSI-C2, Explosive Atmospheres (en); General Safety Instruction GSI-C3, Monitoring of Exposure to Hazardous Chemical Agents in Workplace Atmospheres (en). These documents form part of the CERN Safety Rules and are issued in application of the “Staff Rules and Regulations” and of document SAPOCO 42. These documents set out the minimum requirements for the protection of persons from risks to their occupational safety and health arising, or likely to arise, from the effects of hazardous chemical agents that are present in the workplace or used in any CERN activity. Simultaneously, the HSE Unit has published seven Safety Guidelines and six Safety Forms. These documents are available from the dedicated Web page “Chemical, Cryogenic and Biological Safety&...

  7. QCD spectroscopy at GSI: exotica and charmonia

    International Nuclear Information System (INIS)

    Barnes, T.; Tennessee Univ., Knoxville, TN

    2001-01-01

    In this talk I give a short summary of the basics of conventional and exotic meson spectroscopy, and consider in particular those issues in the charmonium and charmonium hybrid sectors which can be addressed by a future antiproton facility at GSI. (orig.)

  8. GSI: Annual report 1979/80

    International Nuclear Information System (INIS)

    1980-12-01

    The present 'annual report of the GSI' in German language contains together with general information about the GSI first some articles which yield an introduction into selected topics of research. Thereafter some summarizing report from all fields of research are presented. The presented scientific results originate for the most part in collaborations at researchers at universities and scientist of the GSI. This collaboration is especially documented in the last part of the appendix. (HSI)

  9. INDRA at GSI; INDRA au GSI

    Energy Technology Data Exchange (ETDEWEB)

    Bougault, R.; Bocage, F.; Durand, D.; Lopez, O.; Steckmeyer, J.C.; Tamain, B.; Vient, E. [Lab. de Physique Corpusculaire, Caen Univ., 14 (France); Collaboration INDRA: IPN-Orsay, DAPNIA-Saclay, SUBATECH-Nantes, IPN- Lyon, GANIL-Caen

    1997-12-31

    In connection to the decision of installing the INDRA detector by the SIS synchrocyclotron at GSI (Darmstadt, Germany) the report presents the tasks taken into account by the LPC-Caen. These refer to the detector displacement and (mechanical) installation at GSI, the tests before beam (i.e. electronics acquisition software, detectors, etc.) as well as the data acquisition and processing. The physical pro-arguments mention the possibility of disposing of heavy ion beams in a range from 50 MeV to several GeV/nucleon so extending the study of multifragmentation done at GANIL between 30 and 90 MeV/nucleon. More specific, the scientific program of INDRA at GSI inserts studies between those done at around Fermi energy, were the reaction mechanisms are of type of deep inelastic scattering/incomplete fusion, and the studies in the relativistic energy domain where the individual properties of nucleons and transparency of nuclear matter implies mechanisms of the participant-spectator type (fire-ball creation). Also mentioned as fields of extensive studies are: the multifragmentation and its fundamental relation with the nuclear matter equation of state, the role of reaction dynamics in the appearance of collective effects of the radial flow type and its relations with the nuclear compressibility and phase transitions and the thermodynamics of nuclear matter. It appeared that the heavy systems Xe + Sn and Au + Au are the best compromise for the different topics to be approached. The bombarding energies extend from 50 to 150 MeV/nucleon. The report ends with the table giving for six heavy systems (Xe + Sn, Au + Au, C + Au, Ar + Au and P + Au) the required bombarding energies 15 refs.

  10. GSI DARMSTADT: 25 years

    International Nuclear Information System (INIS)

    Anon.

    1995-01-01

    Full text: On May 12, Hans J. Specht, Scientific Director of the Geseilschaft fur Schwerionenforschung (GSI), welcomed an audience of more than 500 to celebrate the 25th anniversary of the Darmstadt heavy ion research Laboratory. Warm greetings and best wishes from Jürgen Ruttgers, Federal Minister for Education, Science, Research and Technology were presented by Hartmut Grubei, Chairman of the GSI Board. The Hessian Minister for Science and Art, Christine Hohmann-Dennhardt, pointed out that the promotion of various fields of research cannot be judged only by the expected return for everyday life. Joachim Treusch, the Chairman of the Association of National Research Centres, went further by stating that basic research, driven by curiosity and not aiming at short term applications, is a necessity. Darmstadt Mayor Peter Benz expressed his pride in having such a prestigious Laboratory in the city and looked forward to a new element named after it. CERN Director General Chris Llewellyn Smith underlined the growing importance of international and inter-regional scientific collaboration and paid tribute to the role of German physicists in general and GSI in particular in CERN's work. GSI is a major partner in the international lead ion programme at CERN which came into operation last year, a scientific and technological success which provides a useful role model for future international partnerships. After pointing to interesting parallels between the two Laboratories - both basing new projects on existing facilities, and both serving large user communities - he thanked GSI for its valuable contributions to CERN. Highlights from the 25 years of GSI were summarized in a talk by Dirk Schwalm, Managing Director of the Max Planck Institute for Nuclear Physics in Heidelberg. Among other points he presented the unique accelerator facility and the discovery of the five heaviest elements. He stated that many dreams from the founding period of GSI had become a reality, and

  11. CERN's new safety policy

    CERN Multimedia

    2014-01-01

    The documents below, published on 29 September 2014 on the HSE website, together replace the document SAPOCO 42 as well as Safety Codes A1, A5, A9, A10, which are no longer in force. As from the publication date of these documents any reference made to the document SAPOCO 42 or to Safety Codes A1, A5, A9 and A10 in contractual documents or CERN rules and regulations shall be deemed to constitute a reference to the corresponding provisions of the documents listed below.   "The CERN Safety Policy" "Safety Regulation SR-SO - Responsibilities and organisational structure in matters of Safety at CERN" "General Safety Instruction GSI-SO-1 - Departmental Safety Officer (DSO)" "General Safety Instruction GSI-SO-2 - Territorial Safety Officer (TSO)" "General Safety Instruction GSI-SO-3 - Safety Linkperson (SLP)" "General Safety Instruction GSI-SO-4 - Large Experiment Group Leader In Matters of Safety (LEXGLI...

  12. Status of safety issues at licensed power plants: TMI Action Plan requirements, unresolved safety issues, generic safety issues, other multiplant action issues

    International Nuclear Information System (INIS)

    1992-12-01

    This report is to provide a comprehensive description of the implementation and verification status of Three Mile Island (TMI) Action Plan requirements, safety issues designated as Unresolved Safety Issues (USIs), Generic Safety Issues(GSIs), and other Multiplant Actions (MPAs) that have been resolved and involve implementation of an action or actions by licensees. This report makes the information available to other interested parties, including the public. An additional purpose of this NUREG report is to serve as a follow-on to NUREG-0933, ''A Prioritization of Generic Safety Issues,'' which tracks safety issues up until requirements are approved for imposition at licensed plants or until the NRC issues a request for action by licensees

  13. Status of safety issues at licensed power plants: TMI action plan requirements, unresolved safety issues, generic safety issues

    International Nuclear Information System (INIS)

    1991-12-01

    As part of ongoing US Nuclear Regulatory Commission (NRC) efforts to ensure the quality and accountability of safety issue information, a program was established whereby an annual NUREG report would be published on the status of licensee implementation and NRC verification of safety issues in major NRC requirements areas. This information was compiled and reported in three NUREG volumes. Volume 1, published in March 1991, addressed the status of of Three Mile Island (TMI) Action Plan Requirements. Volume 2, published in May 1991, addressed the status of unresolved safety issues (USIs). Volume 3, published in June 1991, addressed the implementation and verification status of generic safety issues (GSIs). This annual NUREG report combines these volumes into a single report and provides updated information as of September 30, 1991. The data contained in these NUREG reports are a product of the NRC's Safety Issues Management System (SIMS) database, which is maintained by the Project Management Staff in the Office of Nuclear Reactor Regulation and by NRC regional personnel. This report is to provide a comprehensive description of the implementation and verification status of TMI Action Plan Requirements, safety issues designated as USIs, and GSIs that have been resolved and involve implementation of an action or actions by licensees. This report makes the information available to other interested parties, including the public. An additional purpose of this NUREG report is to serve as a follow-on to NUREG-0933, ''A Prioritization of Generic Safety Issues,'' which tracks safety issues up until requirements are approved for imposition at licensed plants or until the NRC issues a request for action by licensees

  14. Official News relating to CERN Safety Rules

    CERN Multimedia

    HSE Unit

    2015-01-01

    The CERN Safety Rules listed below have been published on the HSE website (see here) and entered into force on the 9 June 2015:   Safety Regulation SR-M “Mechanical equipment”: http://cern.ch/safety-rules/SR-M_ENv2.htm; this SR-M (version 2) cancels and replaces SR-M (version 1) and the corresponding provisions of General Safety Instruction GSI-M3 “Special Equipment” (version 1).   General Safety Instruction GSI-M-1 “Lifting equipment and accessories”: http://cern.ch/safety-rules/GSI-M-1_ENv2.htm; this GSI-M-1 (version 2) cancels and replaces GSI-M1 (version 1). Specific Safety Instruction SSI-M-1-1 “Slings and lifting chains”: http://cern.ch/safety-rules/SSI-M-1-1_EN.htm; Specific Safety Instruction SSI-M-1-2 “Cranes, bridge cranes, gantry cranes and power-driven hoists”: http://cern.ch/safety-rules/SSI-M-1-2_EN.htm; Specific Safety Instruction SSI-M-1-3 “Non-f...

  15. Status of safety issues at licensed power plants: TMI Action Plan requirements; unresolved safety issues; generic safety issues; other multiplant action issues

    International Nuclear Information System (INIS)

    1993-12-01

    As part of ongoing US Nuclear Regulatory Commission (NRC) efforts to ensure the quality and accountability of safety issue information, the NRC established a program for publishing an annual report on the status of licensee implementation and NRC verification of safety issues in major NRC requirements areas. This information was initially compiled and reported in three NUREG-series volumes. Volume 1, published in March 1991, addressed the status of Three Mile Island (TMI) Action Plan Requirements. Volume 2, published in May 1991, addressed the status of unresolved safety issues (USIs). Volume 3, published in June 1991, addressed the implementation and verification status of generic safety issues (GSIs). The first annual supplement, which combined these volumes into a single report and presented updated information as of September 30, 1991, was published in December 1991. The second annual supplement, which provided updated information as of September 30, 1992, was published in December 1992. Supplement 2 also provided the status of licensee implementation and NRC verification of other multiplant action (MPA) issues not related to TMI Action Plan requirements, USIs, or GSIs. This third annual NUREG report, Supplement 3, presents updated information as of September 30, 1993. This report gives a comprehensive description of the implementation and verification status of TMI Action Plan requirements, safety issues designated as USIs, GSIs, and other MPAs that have been resolved and involve implementation of an action or actions by licensees. This report makes the information available to other interested parties, including the public. Additionally, this report serves as a follow-on to NUREG-0933, ''A Prioritization of Generic Safety Issues,'' which tracks safety issues until requirements are approved for imposition at licensed plants or until the NRC issues a request for action by licensees

  16. Status of safety issues at licensed power plants: TMI Action Plan requirements, unresolved safety issues, generic safety issues, other multiplant action issues. Supplement 4

    International Nuclear Information System (INIS)

    1994-12-01

    As part of ongoing US Nuclear Regulatory Commission (NRC) efforts to ensure the quality and accountability of safety issue information, the NRC established a program for publishing an annual report on the status of licensee implementation and NRC verification of safety issues in major NRC requirements areas. This information was initially compiled and reported in three NUREG-series volumes. Volume 1, published in March 1991, addressed the status of Three Mile Island (TMI) Action Plan Requirements. Volume 2, published in May 1991, addressed the status of unresolved safety issues (USIs). Volume 3, published in June 1991, addressed the implementation and verification status of generic safety issues (GSIs). The first annual supplement, which combined these volumes into a single report and presented updated information as of September 30, 1991, was published in December 1991. The second annual supplement, which provided updated information as of September 30, 1992, was published in December 1992. Supplement 2 also provided the status of licensee implementation and NRC verification of other multiplant action (MPA) issues not related to TMI Action Plan requirements, USIs, or GSIs. Supplement 3 gives status as of September 30, 1993. This annual report, Supplement 4, presents updated information as of September 30, 1994. This report gives a comprehensive description of the implementation and verification status of TMI Action Plan requirements, safety issues designated as USIs, GSIs, and other MPAs that have been resolved and involve implementation of an action or actions by licensees. This report makes the information available to other interested parties, including the public. Additionally, this report serves as a follow-on to NUREG-0933, ''A Prioritization of Generic Safety Issues,'' which tracks safety issues until requirements are approved for imposition at licensed plants or until the NRC issues a request for action by licensees

  17. Nuclear safety - Topical issues

    International Nuclear Information System (INIS)

    1995-01-01

    The following topical issues related to nuclear safety are discussed: steam generators; maintenance strategies; control rod drive nozzle cracks; core shrouds cracks; sump strainer blockage; fire protection; computer software important for safety; safety during shutdown; operational safety experience; external hazards and other site related issues. 5 figs, 5 tabs

  18. Aviation Safety Issues Database

    Science.gov (United States)

    Morello, Samuel A.; Ricks, Wendell R.

    2009-01-01

    The aviation safety issues database was instrumental in the refinement and substantiation of the National Aviation Safety Strategic Plan (NASSP). The issues database is a comprehensive set of issues from an extremely broad base of aviation functions, personnel, and vehicle categories, both nationally and internationally. Several aviation safety stakeholders such as the Commercial Aviation Safety Team (CAST) have already used the database. This broader interest was the genesis to making the database publically accessible and writing this report.

  19. Prioritization of generic safety issues

    International Nuclear Information System (INIS)

    Emrit, R.; Minners, W.; VanderMolen, H.

    1983-12-01

    This report presents the priority rankings for generic safety issues related to nuclear power plants. The purpose of these rankings is to assist in the timely and efficient allocation of NRC resources for the resolution of those safety issues that have a significant potential for reducing risk. The report focuses on the prioritization of generic safety issues. Issues primarily concerned with the licensing process or environmental protection and not directly related to safety have been excluded from prioritization. The prioritized issues include: TMI Action Plan items under development; previously proposed issues covered by Task Action Plans, except issues designated at Unresolved Safety Issues (USIs) which had already been assigned high priority; and newly-proposed issues. Future supplements to this report will include the prioritization of additional issues. The safety priority rankings are HIGH, MEDIUM, LOW, and DROP and have been assigned on the basis of risk significance estimates, the ratio of risk to costs and other impacts estimated to result if resolutions of the safety issues were implemented, and the consideration of uncertainties and other quantitative or qualitative factors. To the extent practical, estimates are quantitative

  20. Insights into location dependent loss-of-coolant-accident (LOCA) frequency assessment for GSI-191 risk-informed applications

    Energy Technology Data Exchange (ETDEWEB)

    Fleming, K.N., E-mail: KarlFleming@comcast.net [KNF Consulting LLC, Spokane, WA (United States); Lydell, B.O.Y. [SIGMA-PHASE INC., Vail, AZ (United States)

    2016-08-15

    Highlights: • Role of operating experience in loss-of-coolant-accident (LOCA) frequency assessment. • Plant-to-plant variability in calculated LOCA frequency. • Frequency of double-ended-guillotine-break (DEGB). • Uncertainties in LOCA frequencies. • Risk management insights. - Abstract: As a tribute to the published work by S.H. Bush, S. Beliczey and H. Schulz, this paper assesses the progress with methods and techniques for quantifying the reliability of piping systems in commercial nuclear power plants on the basis of failure rate estimates derived from field experience data in combination with insights and results from probabilistic fracture mechanics analyses and expert elicitation exercises. This status assessment is made from a technical perspective obtained through development of location-specific loss-of-coolant-accident (LOCA) frequencies for input to risk-informed resolution of the generic safety issue (GSI) 191. The methods and techniques on which these GSI-191 applications are based build on a body of work developed by the authors during a period spanning more than two decades. The insights that are presented and discussed in this paper cover today’s knowledge base concerning how to utilize a risk-informed approach to the assessment of piping reliability in the context of probabilistic risk assessment (PRA) in general and the resolution of GSI-191 in particular. Specifically the paper addresses the extent to which LOCA frequencies vary from location to location within a reactor coolant system pressure boundary (RCPB) for a given plant as well as vary from plant to plant, and the reasons for these variabilities. Furthermore, the paper provides the authors’ perspectives on interpretations and applications of information extracted from an expert elicitation process to obtain LOCA frequencies as documented in NUREG-1829 and how to apply this information to GSI-191. Finally, this paper documents technical insights relative to mitigation of

  1. Insights into location dependent loss-of-coolant-accident (LOCA) frequency assessment for GSI-191 risk-informed applications

    International Nuclear Information System (INIS)

    Fleming, K.N.; Lydell, B.O.Y.

    2016-01-01

    Highlights: • Role of operating experience in loss-of-coolant-accident (LOCA) frequency assessment. • Plant-to-plant variability in calculated LOCA frequency. • Frequency of double-ended-guillotine-break (DEGB). • Uncertainties in LOCA frequencies. • Risk management insights. - Abstract: As a tribute to the published work by S.H. Bush, S. Beliczey and H. Schulz, this paper assesses the progress with methods and techniques for quantifying the reliability of piping systems in commercial nuclear power plants on the basis of failure rate estimates derived from field experience data in combination with insights and results from probabilistic fracture mechanics analyses and expert elicitation exercises. This status assessment is made from a technical perspective obtained through development of location-specific loss-of-coolant-accident (LOCA) frequencies for input to risk-informed resolution of the generic safety issue (GSI) 191. The methods and techniques on which these GSI-191 applications are based build on a body of work developed by the authors during a period spanning more than two decades. The insights that are presented and discussed in this paper cover today’s knowledge base concerning how to utilize a risk-informed approach to the assessment of piping reliability in the context of probabilistic risk assessment (PRA) in general and the resolution of GSI-191 in particular. Specifically the paper addresses the extent to which LOCA frequencies vary from location to location within a reactor coolant system pressure boundary (RCPB) for a given plant as well as vary from plant to plant, and the reasons for these variabilities. Furthermore, the paper provides the authors’ perspectives on interpretations and applications of information extracted from an expert elicitation process to obtain LOCA frequencies as documented in NUREG-1829 and how to apply this information to GSI-191. Finally, this paper documents technical insights relative to mitigation of

  2. Development of nuclear safety issues program

    Energy Technology Data Exchange (ETDEWEB)

    Cho, J. C.; Yoo, S. O.; Yoon, Y. K.; Kim, H. J.; Jeong, M. J.; Noh, K. W.; Kang, D. K

    2006-12-15

    The nuclear safety issues are defined as the cases which affect the design and operation safety of nuclear power plants and also require the resolution action. The nuclear safety issues program (NSIP) which deals with the overall procedural requirements for the nuclear safety issues management process is developed, in accordance with the request of the scientific resolution researches and the establishment/application of the nuclear safety issues management system for the nuclear power plants under design, construction or operation. The NSIP consists of the following 4 steps; - Step 1 : Collection of candidates for nuclear safety issues - Step 2 : Identification of nuclear safety issues - Step 3 : Categorization and resolution of nuclear safety issues - Step 4 : Implementation, verification and closure The NSIP will be applied to the management directives of KINS related to the nuclear safety issues. Through the identification of the nuclear safety issues which may be related to the potential for accident/incidents at operating nuclear power plants either directly or indirectly, followed by performance of regulatory researches to resolve the safety issues, it will be possible to prevent occurrence of accidents/incidents as well as to cope with unexpected accidents/incidents by analyzing the root causes timely and scientifically and by establishing the proper flow-up or remedied regulatory actions. Moreover, the identification and resolution of the safety issues related to the new nuclear power plants completed at the design stage are also expected to make the new reactor licensing reviews effective and efficient as well as to make the possibility of accidents/incidents occurrence minimize. Therefore, the NSIP developed in this study is expected to contribute for the enhancement of the safety of nuclear power plants.

  3. Development of nuclear safety issues program

    International Nuclear Information System (INIS)

    Cho, J. C.; Yoo, S. O.; Yoon, Y. K.; Kim, H. J.; Jeong, M. J.; Noh, K. W.; Kang, D. K.

    2006-12-01

    The nuclear safety issues are defined as the cases which affect the design and operation safety of nuclear power plants and also require the resolution action. The nuclear safety issues program (NSIP) which deals with the overall procedural requirements for the nuclear safety issues management process is developed, in accordance with the request of the scientific resolution researches and the establishment/application of the nuclear safety issues management system for the nuclear power plants under design, construction or operation. The NSIP consists of the following 4 steps; - Step 1 : Collection of candidates for nuclear safety issues - Step 2 : Identification of nuclear safety issues - Step 3 : Categorization and resolution of nuclear safety issues - Step 4 : Implementation, verification and closure The NSIP will be applied to the management directives of KINS related to the nuclear safety issues. Through the identification of the nuclear safety issues which may be related to the potential for accident/incidents at operating nuclear power plants either directly or indirectly, followed by performance of regulatory researches to resolve the safety issues, it will be possible to prevent occurrence of accidents/incidents as well as to cope with unexpected accidents/incidents by analyzing the root causes timely and scientifically and by establishing the proper flow-up or remedied regulatory actions. Moreover, the identification and resolution of the safety issues related to the new nuclear power plants completed at the design stage are also expected to make the new reactor licensing reviews effective and efficient as well as to make the possibility of accidents/incidents occurrence minimize. Therefore, the NSIP developed in this study is expected to contribute for the enhancement of the safety of nuclear power plants

  4. A prioritization of generic safety issues

    International Nuclear Information System (INIS)

    Emrit, R.; Riggs, R.; Milstead, W.; Pittman, J.

    1991-07-01

    This report presents the priority rankings for generic safety issues and related to nuclear power plants. The purpose of these rankings is to assist in the timely and efficient allocation of NRC resources for the resolution of those safety issues that have a significant potential for reducing risk. The report focuses on the prioritization of generic safety issues. Issues primarily concerned with the licensing process or environmental protection and not directly related to safety have been excluded from prioritization. The prioritized issues include: TMI Action Plan items under development; previously proposed issues covered by Task Action Plans, except issues designated as Un-resolved Safety Issues (USIs) which had already been assigned high priority; and newly-proposed issues. Future supplements to this report will include the prioritization of additional issues. The safety priority rankings are High, Medium, Low, and Drop and have been assigned on the basis of risk significance estimates, the ratio of risk to costs and other impacts estimated to result if resolutions of the safety issues were implemented, and the consideration of uncertainties and other quantitative or qualitative factors. To the extent practical, estimates are quantitative. 1310 refs

  5. Transient analysis for resolving safety issues

    International Nuclear Information System (INIS)

    Chao, J.; Layman, W.

    1987-01-01

    The Nuclear Safety Analysis Center (NSAC) has a Generic Safety Analysis Program to help resolve high priority generic safety issues. This paper describes several high priority safety issues considered at NSAC and how they were resolved by transient analysis using thermal hydraulics and neutronics codes. These issues are pressurized thermal shock (PTS), anticipated transients without scram (ATWS), steam generator tube rupture (SGTR), and reactivity transients in light of the Chernobyl accident

  6. Extended data acquisition support at GSI

    International Nuclear Information System (INIS)

    Marinescu, D.C.; Busch, F.; Hultzsch, H.; Lowsky, J.; Richter, M.

    1984-01-01

    The Experiment Data Acquisition and Analysis System (EDAS) of GSI, designed to support the data processing associated with nuclear physics experiments, provides three modes of operation: real-time, interactive replay and batch replay. The real-time mode is used for data acquisition and data analysis during an experiment performed at the heavy ion accelerator at GSI. An experiment may be performed either in Stand Alone Mode, using only the Experiment Computers, or in Extended Mode using all computing resources available. The Extended Mode combines the advantages of the real-time response of a dedicated minicomputer with the availability of computing resources in a large computing environment. This paper first gives an overview of EDAS and presents the GSI High Speed Data Acquisition Network. Data Acquisition Modes and the Extended Mode are then introduced. The structure of the system components, their implementation and the functions pertinent to the Extended Mode are presented. The control functions of the Experiment Computer sub-system are discussed in detail. Two aspects of the design of the sub-system running on the mainframe are stressed, namely the use of a multi-user installation for real-time processing and the use of a high level programming language, PL/I, as an implementation language for a system which uses parallel processing. The experience accumulated is summarized in a number of conclusions

  7. GSI-contributions to HCI-92

    International Nuclear Information System (INIS)

    1992-11-01

    This preprint comprises all the papers presented at the VIth International Conference on the Physics of Highly Charged Ions (Manhattan, Kansas, September 28 - October 2, 1992) reporting on results from experiments performed at the GSI heavy ion accelerator facilities. See hints under the relevant topics. (orig./HSI)

  8. Heavy ion accelerators at GSI

    International Nuclear Information System (INIS)

    Angert, N.

    1984-01-01

    The status of the Unilac heavy ion linear accelerator at GSI, Darmstadt is given. A schematic overall plan view of the Unilac is shown and its systems are described. List of isotopes and intensities accelerated at the Unilac is presented. The experimental possibilities at GSI should be considerably extended by a heavy ion synchrotron (SIS 18) in combination with an experimental storage ring (ESR). A prototype of the rf-accelerating system of the synchrotron has been built and tested. Prototypes for the quadrupole and dipole magnets for the ring are being constructed. The SIS 18 is desigmed for a maximum magnetic rigidity of 18Tm so that neon can be accelerated to 2 GeV/W and uranium to 1 GeV/u. The design allows also the acceleration of protons up to 4.5 GeV. The ESR permits to storage fully stripped uranium ions up to an energy of approximately R50 MeV/u

  9. Girls' Science Investigations (GSI) New Haven: Evaluating the Impact

    Science.gov (United States)

    Knodell, Claire; Fleming, Bonnie

    2009-05-01

    Girls' Science Investigations (GSI) New Haven seeks to empower the girls of today to shape the science of tomorrow. Funded by the NSF and Yale University and held at Yale, this program was designed to motivate, empower, and interest middle school girls in developing the skills required to pursue a career in science during a day-long investigation of the session's featured topic in science. Yale students and female professors act as mentors and guide younger girls through an environment for understanding and exploring various disciplines of science through hands-on activities in a laboratory setting. GSI strives to close the gap between males and females one action-packed Saturday at a time. This paper evaluates the success of the program. Student participant evaluations over the past 2 years coupled with student testimony and GSI coordinator, instructors', and volunteers' interviews allowed for an analysis of GSI's ability to inspire girls to pursue careers in science. The data indicates that a majority of girls who attended the program were more inclined to continue their study of science. The positive results are detailed in the following paper which points to the hands-on activities and enthusiasm of instructors as integral to the program's success.

  10. Evaluation on safety issues of SMART

    International Nuclear Information System (INIS)

    Kim, W. S.; Seol, K. W.; Yoon, Y. K.; Lee, J. H.

    2001-01-01

    Safety issues on the SMART were evaluated in the light of the compliance with the Ministerial Ordinance of Technical Requirements applying to Nuclear Installations, which was recently revised. Evaluation concludes that regulatory requirements associated with following items have to be developed as the licensing criteria for the SMART: (1) proving the safety of design or materials different form existing reactors; (2) coping with beyond design basis accidents; (3) rulemaking on the safety of reactor safeguard vessel ; (4) ensuring integrity of steam generator tubes; and (5) classifying equipment based on their safety significance. Appropriate actions including implementation of new requirements under development should be taken for safety issues such as diversity of reactivity control and in-service inspection of steam generator tubes that are not complied with the current Technical Requirements. Safety level of the SMART design will be evaluated further by the more detailed assessment according to the Technical Requirements, and additional safety issues will be identified and resolved, if it necessary

  11. Collimation and material science studies (ColMat) at GSI.

    CERN Document Server

    Stadlmann, J; Kollmus, H; Krause, M; Mustafin, E; Petzenhauser, I; Spiller, P; Strasik, I; Tahir, N; Tomut, M; Trautmann, C

    2010-01-01

    Within the frame of the EuCARD program, the GSI Helmholtzzentrum für Schwerionenforschung in Darmstadt is performing accelerator R&D in workpackage 8: ColMat. The coordinated effort is focussed on materials aspects important for building the FAIR accelerator facility at GSI and the LHC upgrade at CERN. Accelerator components and especially protection devices have to be operated in high dose environments. The radiation hazard occurs either by the primary proton and ion beams or the secondary radiation after initial beam loss. Detailed numerical simulations have been carried out to study the damage caused to solid targets by the full impact of the LHC beam as well as the SPS beam. Tungsten, copper and graphite as possible collimator materials have been studied. Experimental an theoretical studies on radiation damage on materials used for the LHC upgrade and the FAIR accelerators are performed at the present GSI experimental facilities. Technical decisions based on these results will have an impact on the F...

  12. GSI operation software: migration from OpenVMS TO Linux

    International Nuclear Information System (INIS)

    Huhmann, R.; Froehlich, G.; Juelicher, S.; Schaa, V.R.W.

    2012-01-01

    The current operation software at GSI, controlling the linac, beam transfer lines, synchrotron and storage ring, has been developed over a period of more than two decades using OpenVMS on Alpha-Workstations. The GSI accelerator facilities will serve as an injector chain for the new FAIR accelerator complex for which a control system is currently developed. To enable reuse and integration of parts of the distributed GSI software system, in particular the linac operation software, within the FAIR control system, the corresponding software components must be migrated to Linux. Inter-operability with FAIR controls applications is achieved by adding a generic middle-ware interface accessible from Java applications. For porting applications to Linux a set of libraries and tools has been developed covering the necessary OpenVMS system functionality. Currently, core applications and services are already ported or rewritten and functionally tested but not in operational usage. This paper presents the current status of the project and concepts for putting the migrated software into operation. (authors)

  13. The evolution of gonad expenditure and gonadosomatic index (GSI) in male and female broadcast-spawning invertebrates.

    Science.gov (United States)

    Parker, Geoff A; Ramm, Steven A; Lehtonen, Jussi; Henshaw, Jonathan M

    2018-05-01

    Sedentary broadcast-spawning marine invertebrates, which release both eggs and sperm into the water for fertilization, are of special interest for sexual selection studies. They provide unique insight into the early stages of the evolutionary succession leading to the often-intense operation of both pre- and post-mating sexual selection in mobile gonochorists. Since they are sessile or only weakly mobile, adults can interact only to a limited extent with other adults and with their own fertilized offspring. They are consequently subject mainly to selection on gamete production and gamete success, and so high gonad expenditure is expected in both sexes. We review literature on gonadosomatic index (GSI; the proportion of body tissue devoted to gamete production) of gonochoristic broadcast spawners, which we use as a proxy for gonad expenditure. We show that such taxa most often have a high GSI that is approximately equal in both sexes. When GSI is asymmetric, female GSI usually exceeds male GSI, at least in echinoderms (the majority of species recorded). Intriguingly, though, higher male GSI also occurs in some species and appears more common than female-biased GSI in certain orders of gastropod molluscs. Our limited data also suggest that higher male GSI may be the prevalent pattern in sperm casters (where only males release gametes). We explore how selection might have shaped these patterns using game theoretic models for gonad expenditure that consider possible trade-offs with (i) somatic maintenance or (ii) growth, while also considering sperm competition, sperm limitation, and polyspermy. Our models of the trade-off between somatic tissue (which increases survival) and gonad (which increases reproductive success) predict that GSI should be equal for the two sexes when sperm competition is intense, as is probably common in broadcast spawners due to synchronous spawning in aggregations. Higher female GSI occurs under low sperm competition. Sperm limitation appears

  14. Advances in beam position monitoring methods at GSI synchrotrons

    Energy Technology Data Exchange (ETDEWEB)

    Singh, Rahul; Reiter, Andreas; Forck, Peter; Kowina, Piotr; Lang, Kevin; Miedzik, Piotr [GSI, Darmstadt (Germany)

    2016-07-01

    At the GSI synchrotron facilities, capacitive beam pick-up signals for position evaluation are immediately digitized within the acquisition electronics due to availability of reliable, fast and high resolution ADCs. The signal processing aspects are therefore fully dealt with in the digital domain. Novel digital techniques for asynchronous and synchronous (bunch-by-bunch) beam position estimation have been developed at GSI SIS-18 and CRYRING as part of FAIR development program. This contribution will highlight the advancements and its impact on the operational ease and high availability of the BPM systems.

  15. Status of safety issues at licensed power plants

    International Nuclear Information System (INIS)

    1991-05-01

    As part of ongoing US Nuclear Regulatory Commission (NRC) efforts to ensure the quality and accountability of safety issue information, a program has been established whereby an annual NUREG report will be published on the status of licensee implementation and NRC verification of safety issues in major NRC requirement areas. This report, the second volume of a three-volume series, addresses the status of unresolved safety issues (USIs) at licensed plants. The data contained in these NUREG reports are a product of the NRC's Safety Issues Management System (SIMS) database, which is maintained by the Project Management Staff in the Office of Nuclear Reactor Regulation and by NRC regional personnel. The purpose of this report is to provide a comprehensive description of the status of implementation and verification of the 27 safety issues designated as USIs and to make this information available to other interested parties, including the public. A corollary purpose of this NUREG report is to serve as a follow-on to NUREG-0933, ''A Prioritization of Generic Safety Issues,'' which tracks safety issues up until requirements are approved for imposition at licensed plants. 3 figs., 4 tabs

  16. The impact of green stormwater infrastructure installation on surrounding health and safety

    Science.gov (United States)

    Michelle C. Kondo; Sarah C. Low; Jason Henning; Charles C. Branas

    2015-01-01

    We investigated the health and safety effects of urban green stormwater infrastructure (GSI) installments. We conducted a difference-in-differences analysis of the effects of GSI installments on health (e.g., blood pressure, cholesterol and stress levels) and safety (e.g., felonies, nuisance and property crimes, narcotics crimes) outcomes from 2000 to 2012 in...

  17. Hydrogen Safety Issues Compared to Safety Issues with Methane and Propane

    International Nuclear Information System (INIS)

    Green, Michael A.

    2005-01-01

    The hydrogen economy is not possible if the safety standards currently applied to liquid hydrogen and hydrogen gas by many laboratories are applied to devices that use either liquid or gaseous hydrogen. Methane and propane are commonly used by ordinary people without the special training. This report asks, 'How is hydrogen different from flammable gasses that are commonly being used all over the world?' This report compares the properties of hydrogen, methane and propane and how these properties may relate to safety when they are used in both the liquid and gaseous state. Through such an analysis, sensible safety standards for the large-scale (or even small-scale) use of liquid and gaseous hydrogen systems can be developed. This paper is meant to promote discussion of issues related to hydrogen safety so that engineers designing equipment can factor sensible safety standards into their designs

  18. Hydrogen Safety Issues Compared to Safety Issues with Methane andPropane

    Energy Technology Data Exchange (ETDEWEB)

    Green, Michael A.

    2005-08-20

    The hydrogen economy is not possible if the safety standards currently applied to liquid hydrogen and hydrogen gas by many laboratories are applied to devices that use either liquid or gaseous hydrogen. Methane and propane are commonly used by ordinary people without the special training. This report asks, 'How is hydrogen different from flammable gasses that are commonly being used all over the world?' This report compares the properties of hydrogen, methane and propane and how these properties may relate to safety when they are used in both the liquid and gaseous state. Through such an analysis, sensible safety standards for the large-scale (or even small-scale) use of liquid and gaseous hydrogen systems can be developed. This paper is meant to promote discussion of issues related to hydrogen safety so that engineers designing equipment can factor sensible safety standards into their designs.

  19. The impact of green stormwater infrastructure installation on surrounding health and safety.

    Science.gov (United States)

    Kondo, Michelle C; Low, Sarah C; Henning, Jason; Branas, Charles C

    2015-03-01

    We investigated the health and safety effects of urban green stormwater infrastructure (GSI) installments. We conducted a difference-in-differences analysis of the effects of GSI installments on health (e.g., blood pressure, cholesterol and stress levels) and safety (e.g., felonies, nuisance and property crimes, narcotics crimes) outcomes from 2000 to 2012 in Philadelphia, Pennsylvania. We used mixed-effects regression models to compare differences in pre- and posttreatment measures of outcomes for treatment sites (n=52) and randomly chosen, matched control sites (n=186) within multiple geographic extents surrounding GSI sites. Regression-adjusted models showed consistent and statistically significant reductions in narcotics possession (18%-27% less) within 16th-mile, quarter-mile, half-mile (P<.001), and eighth-mile (P<.01) distances from treatment sites and at the census tract level (P<.01). Narcotics manufacture and burglaries were also significantly reduced at multiple scales. Nonsignificant reductions in homicides, assaults, thefts, public drunkenness, and narcotics sales were associated with GSI installation in at least 1 geographic extent. Health and safety considerations should be included in future assessments of GSI programs. Subsequent studies should assess mechanisms of this association.

  20. Editorial safety science special issue road safety management.

    NARCIS (Netherlands)

    Wegman, F.C.M. & Hagezieker, M.P.

    2014-01-01

    The articles presented in this Special Issue on Road Safety Management represent an illustration of the growing interest in policy-related research in the area of road safety. The complex nature of this type of research combined with the observation that scientific journals pay limited attention to

  1. Official News relating to CERN Safety Rules

    CERN Multimedia

    HSE Unit

    2015-01-01

    The CERN Safety Rules listed below have been published on the official CERN Safety Rules website (see here).   Safety Regulation SR-WS Works and services: this SR-WS (version 1) will cancel and replace the corresponding provisions of Safety Instruction IS50 “Safety Coordination on CERN Worksites”. General Safety Instruction GSI-WS-1 Safety coordination for works and services: this GSI-WS-1 (version 1) will cancel and replace the corresponding provisions of Safety Instruction IS39 “Notice of Start of Works (AOC)” and of Safety Instruction IS50 “Safety Coordination on CERN Worksites” ​Specific Safety Instruction SSI-WS-1-1 Safety coordinator for category 1 operations: this SSI-WS-1-4 (version 1) will cancel and replace the corresponding provisions of Safety Instruction IS50 “Safety Coordination on CERN Worksites”.​ ​ In order to limit the impact on the end-of-year technical st...

  2. Status of safety issues at licensed power plants

    International Nuclear Information System (INIS)

    1991-06-01

    As part of ongoing US Nuclear Regulatory Commission (NRC) efforts to ensure the quality and accountability of safety issue information, a program has been established whereby an annual NUREG report will be published on the status of licensee implementation and NRC verification of safety issues in major NRC requirement areas. This report, the third volume of a three-volume series, addresses the status of generic safety issues (GSIs) at licensed plants. Volume 1 addressed the status of Three Mile Island Action Plan requirements and was published in March 1991. Volume 2 addressed the status of implementation and verification of unresolved safety issues and was published in May 1991. The annual NUREG report will combine these three areas in a single volume to be published in late 1991. The data contained in these NUREG reports are a product of the NRC's Safety Issues Management System (SIMS) database, which is maintained by the Project Management Staff in the Office of Nuclear Reactor Regulation and by NRC regional personnel. The purpose of this report is to provide a comprehensive description of the status of implementation and verification of the 34 GSIs and sub-issues that have been resolved by the NRC and involve implementation of an action or actions by licensees. This NUREG report also serves as a follow-on to NUREG-0933, ''A Prioritization of Generic Safety Issues,'' which tracks safety issues up until a request for action by licensees is issued by NRC. 3 figs., 6 tabs

  3. The GSI control system

    International Nuclear Information System (INIS)

    Krause, U.; Schaa, V.; Steiner, R.

    1992-01-01

    The GSI accelerator facility consists of an old linac and two modern machines, a synchrotron and a storage ring. It is operated from one control room. Only three operators at a time have to keep it running with only little assistance from machine specialists in daytime. So the control tools must provide a high degree of abstraction and modeling to relieve the operators from details on the device level. The program structures to achieve this are described in this paper. A coarse overview of the control architecture is given. (author)

  4. High-heat tank safety issue resolution program plan

    International Nuclear Information System (INIS)

    Wang, O.S.

    1993-12-01

    The purpose of this program plan is to provide a guide for selecting corrective actions that will mitigate and/or remediate the high-heat waste tank safety issue for single-shell tank (SST) 241-C-106. This program plan also outlines the logic for selecting approaches and tasks to mitigate and resolve the high-heat safety issue. The identified safety issue for high-heat tank 241-C-106 involves the potential release of nuclear waste to the environment as the result of heat-induced structural damage to the tank's concrete, if forced cooling is interrupted for extended periods. Currently, forced ventilation with added water to promote thermal conductivity and evaporation cooling is used to cool the waste. At this time, the only viable solution identified to resolve this safety issue is the removal of heat generating waste in the tank. This solution is being aggressively pursued as the permanent solution to this safety issue and also to support the present waste retrieval plan. Tank 241-C-106 has been selected as the first SST for retrieval. The program plan has three parts. The first part establishes program objectives and defines safety issues, drivers, and resolution criteria and strategy. The second part evaluates the high-heat safety issue and its mitigation and remediation methods and alternatives according to resolution logic. The third part identifies major tasks and alternatives for mitigation and resolution of the safety issue. Selected tasks and best-estimate schedules are also summarized in the program plan

  5. The HITRAP project at GSI

    International Nuclear Information System (INIS)

    Poth, H.; Hasse, R.W.

    1990-10-01

    We present a proposal for the development of a facility to capture highly-charged ions, produced in the GSI heavy ion complex, and to store them in electromagnetic traps at thermal or subthermal energy. Such a facility would allow to exploit the physics opened up by the heavy ion rings SIS and ESR and by the fragment separator FRS with unprecedented possibilities as will be shown in the outlined physics program. (orig.)

  6. GSI research and development programme 1983-85

    International Nuclear Information System (INIS)

    1982-01-01

    In this report the research program of the GSI Darmstadt is described. This program concerns heavy ion reactions, atomic collisions with heavy ions, and applications of heavy ion beams in other fields of science. Furthermore the future development of accelerators and detection methods is described. (HSI) [de

  7. Hospital safety climate surveys: measurement issues.

    Science.gov (United States)

    Jackson, Jeanette; Sarac, Cakil; Flin, Rhona

    2010-12-01

    Organizational safety culture relates to behavioural norms in the workplace and is usually assessed by safety climate surveys. These can be a diagnostic indicator on the state of safety in a hospital. This review examines recent studies using staff surveys of hospital safety climate, focussing on measurement issues. Four questionnaires (hospital survey on patient safety culture, safety attitudes questionnaire, patient safety climate in healthcare organizations, hospital safety climate scale), with acceptable psychometric properties, are now applied across countries and clinical settings. Comparisons for benchmarking must be made with caution in case of questionnaire modifications. Increasing attention is being paid to the unit and hospital level wherein distinct cultures may be located, as well as to associated measurement and study design issues. Predictive validity of safety climate is tested against safety behaviours/outcomes, with some relationships reported, although effects may be specific to professional groups/units. Few studies test the role of intervening variables that could influence the effect of climate on outcomes. Hospital climate studies are becoming a key component of healthcare safety management systems. Large datasets have established more reliable instruments that allow a more focussed investigation of the role of culture in the improvement and maintenance of staff's safety perceptions within units, as well as within hospitals.

  8. Construction and characterization of a laser-driven proton beamline at GSI

    OpenAIRE

    Busold, Simon

    2014-01-01

    The thesis includes the first experiments with the new 100 TW laser beamline of the PHELIX laser facility at GSI Darmstadt to drive a TNSA (Target Normal Sheath Acceleration) proton source at GSI's Z6 experimental area. At consecutive stages a pulsed solenoid has been applied for beam transport and energy selection via chromatic focusing, as well as a radiofrequency cavity for energy compression of the bunch. This novel laser-driven proton beamline, representing a central experiment of the...

  9. Food control concept: Food safety/ingestion issues

    International Nuclear Information System (INIS)

    Armstrong, B.

    1995-01-01

    This talk outlines the issues in food safety/ingestion in the case of radiation accidents at nuclear power plants and how emergency preparedness plans can/should be tailored. The major topics are as follows: In Washington: food safety/ingestion issues exist at transition between response and regulatory worlds; agricultural concerns; customer concerns; Three Mile Island: detailed maps; development of response procedures; development of tools; legal issues

  10. Generic safety questions. evaluation of investigations, studies and expertises of other states for the knowledge base GeSi; Generische Sicherheitsfragen. Auswertung von Untersuchungen, Studien und Gutachten anderer Staaten fuer die Wissensbasis GeSi

    Energy Technology Data Exchange (ETDEWEB)

    Boenigke, Guenther; Eismar, Shanna

    2016-03-15

    For the non-profit-making expert organization Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) gGmbH, maintaining know-how and broadening its knowledge in the field of nuclear safety is of fundamental relevance. One important approach to achieving this goal is to collect and assess national and international findings and events in the field of nuclear safety e.g. in connection with generic issues - i.e. issues that are not specific to a particular plant. The GeSi/GeSi International database and its subsystems serves for reflecting the current state of the art in science and technology in the field of generic issues and also as a tool in the area of knowledge management. Within the framework of Project 3611 I 01500 sponsored by the BMUB, information on these issues was compiled systematically. The aim of the project was to examine the safety issues that are cur-rently discussed at national and international level with regard to their relevance for the conditions prevailing in Germany and to follow up in detail those issues that are of relevance for national safety practice. Similar knowledge databases also exist in other major nuclear-power-plant-operating countries such as the US, Canada, and France. At present (September 2014), there are 303 issues in the overall database, of which 23 are assessed to be of ''high'' significance for German plants. Of these, 16 issues belong to the sub-database for generic safety issues (GSI) and seven belong to the sub-database for generic research issues (GFO). The database GSI currently contains 138 issues that need to be further addressed and 101 issues that are considered as solved. 43 issues from the database GFO require further investigation, while 21 issues are considered as solved.

  11. The safety issues of medical robotics

    Energy Technology Data Exchange (ETDEWEB)

    Fei Baowei; Ng, W.S.; Chauhan, Sunita; Kwoh, Chee Keong

    2001-08-01

    In this paper, we put forward a systematic method to analyze, control and evaluate the safety issues of medical robotics. We created a safety model that consists of three axes to analyze safety factors. Software and hardware are the two material axes. The third axis is the policy that controls all phases of design, production, testing and application of the robot system. The policy was defined as hazard identification and safety insurance control (HISIC) that includes seven principles: definitions and requirements, hazard identification, safety insurance control, safety critical limits, monitoring and control, verification and validation, system log and documentation. HISIC was implemented in the development of a robot for urological applications that was known as URObot. The URObot is a universal robot with different modules adaptable for 3D ultrasound image-guided interstitial laser coagulation, radiation seed implantation, laser resection, and electrical resection of the prostate. Safety was always the key issue in the building of the robot. The HISIC strategies were adopted for safety enhancement in mechanical, electrical and software design. The initial test on URObot showed that HISIC had the potential ability to improve the safety of the system. Further safety experiments are being conducted in our laboratory.

  12. The safety issues of medical robotics

    International Nuclear Information System (INIS)

    Fei Baowei; Ng, W.S.; Chauhan, Sunita; Kwoh, Chee Keong

    2001-01-01

    In this paper, we put forward a systematic method to analyze, control and evaluate the safety issues of medical robotics. We created a safety model that consists of three axes to analyze safety factors. Software and hardware are the two material axes. The third axis is the policy that controls all phases of design, production, testing and application of the robot system. The policy was defined as hazard identification and safety insurance control (HISIC) that includes seven principles: definitions and requirements, hazard identification, safety insurance control, safety critical limits, monitoring and control, verification and validation, system log and documentation. HISIC was implemented in the development of a robot for urological applications that was known as URObot. The URObot is a universal robot with different modules adaptable for 3D ultrasound image-guided interstitial laser coagulation, radiation seed implantation, laser resection, and electrical resection of the prostate. Safety was always the key issue in the building of the robot. The HISIC strategies were adopted for safety enhancement in mechanical, electrical and software design. The initial test on URObot showed that HISIC had the potential ability to improve the safety of the system. Further safety experiments are being conducted in our laboratory

  13. Development of RF-linac and storage ring system for high-current experiments at GSI

    International Nuclear Information System (INIS)

    Hofmann, I.

    1986-08-01

    The heavy ion facility under construction at GSI is suitable for the generation of high-current beams. It consists of a new high-current injector into the Unilac and a synchrotron and storage ring. We discuss the capability of this system to produce short pulses of heavy ions with a specific energy of the order of 0.1 MJ/g. Under these conditions the system allows to perform a first generation of heavy ion driven target experiments and to test most of the critical issues of a large scale heavy ion fusion driver facility. (orig.)

  14. Status of safety issues at licensed power plants

    International Nuclear Information System (INIS)

    1991-03-01

    As part of ongoing US Nuclear Regulatory Commission (NRC) efforts to ensure the quality and accountability of safety issue information, a program has been established whereby an annual NUREG series report will be published on the status of licensee implementation and NRC verification of safety issues in major NRC requirement areas. The data contained in this report are a product of the NRC's Safety Issues Management System database, which is maintained by the Project Management Staff in the Office of Nuclear Reactor Regulation and by personnel in the NRC regions. This report has been prepared in order to provide a comprehensive description of the implementation and verification status of all the TMI Action Plan requirements at licensed reactors, and to make this information available to other interested parties, including the public. A corollary purpose of this report is for it to serve as a follow-on to NUREG-0933, ''A Prioritization of Safety Issues,'' which tracks safety issues up until requirements are approved for imposition at licensed facilities

  15. Safety issues on advanced fuel

    International Nuclear Information System (INIS)

    Gross, H.; Krebs, W.D.

    1998-01-01

    In the recent years a general discussion has started whether unsolved safety issues are related to advanced fuel. Advanced fuel is in this context a summary of features like high burnup, improved clad materials, low leakage loading pattern with high peaking factors etc. The design basis accidents RIA and Loca are of special interest for this discussion. From the Siemens point of view RIA is not a safety issue. There are sufficient margins between the enthalpy rise calculated by modern 3D methods and the fuel failures which occurred in RIA simulation tests when the effect of pulse width is taken into account. The evaluation of possible uncertainties for the established Loca criteria (17% equivalent corrosion, 1200 C clad temperature) for high burnup makes sense. But fuel with high burnup has significantly lower peaking factors than fuel with lower burnup. This gives sufficient margin counterbalancing possible uncertainties. In contrast to the above incomplete control rod insertion at higher burnup is potentially a real safety issue. Although Siemens fuel was not affected by the reported incidents they addressed the problem and checked that they have sufficient design margin for their fuel. (orig.) [de

  16. Impact of hybrid GSI analysis using ETR ensembles

    Indian Academy of Sciences (India)

    Impact of hybrid GSI analysis using ETR ensembles. V S Prasad∗ and C J .... In this study, impact of hybrid ..... of water between vapour, clouds and ice (Damrath et al. 2000). ... flooding – June 2013; Weather and Climate Extremes 4. 22–34.

  17. Unresolved safety issues summary: aqua book

    International Nuclear Information System (INIS)

    1982-06-01

    The unresolved safety issues summary is designed to provide the management of the Nuclear Regulatory Commission with a quarterly overview of the progress and plans for completion of generic tasks addressing unresolved safety issues reported to Congress pursuant to Section 210 of the Energy Reorganization Act of 1974 as amended. This summary utilizes data collected from the Office of Nuclear Reactor Regulation, Office of Nuclear Regulatory Research, and the National Laboratories and is prepared by the Office of Resource Management. The schedules in this book include a milestone at the end of each action plan which represents the initiation of the implementation process both with respect to incorporation of the technical resolution in the NRC official guidance or requirements and also the application of changes to individual operating plants. The progress and status for implementation of unresolved safety issues for which a technical resolution has been completed are reported specifically in a separate table provided in this summary

  18. 76 FR 67461 - Cosmetic Microbiological Safety Issues; Public Meeting

    Science.gov (United States)

    2011-11-01

    ...] Cosmetic Microbiological Safety Issues; Public Meeting AGENCY: Food and Drug Administration, HHS. ACTION... Administration (FDA) is announcing a public meeting entitled ``Cosmetic Microbiological Safety Issues.'' The... cosmetic microbiological safety and to suggest areas for the possible development of FDA guidance documents...

  19. Categorization of reactor safety issues from a risk perspective

    International Nuclear Information System (INIS)

    1985-03-01

    This report presents the results of an effort to identify and rank reactor safety and risk issues identified from past Probabilistic Risk Assessments (PRAs) and other safety analyses. Because of the varied scope of these analyses, the list of issues may be incomplete. Nevertheless, those studies comprised ordered analyses to whatever their respective depths; hence, they warranted scrutiny for whatever insights they could reveal with respect to issue importance. The top-ranked issues in terms of their contribution to the uncertainty in risk are described in some detail. All of these risk issues are compared to the generic safety issues for completeness and omissions

  20. Unresolved safety issues: where do we go from here

    International Nuclear Information System (INIS)

    Aycock, M.B.

    1980-01-01

    Section 210 of the Energy reorganization Act of 1974, as amended requires the NRC to develop a program for resolving Unresolved Safety Issues related to nuclear power plants. Seventeen Unresolved Safety Issues were identified by the NRC in 1978 and by early 1979 the NRC Unresolved Safety Issues Program was quickly becoming a well defined and manageable effort. Although, the Three Mile Island accident caused the momentum developed in early 1979 to be lost, efforts on ongoing generic tasks were continued by a special NRC Task Force established in June 1979. The momentum that was lost must be regained, however, if the Congressional mandate in Section 210 is to be met. With increased industry involvement and the marriage of the Unresolved Safety Issues Program with the improved and broader safety program development, audit and evaluation activities of the new NRR Division of Safety Technology, this should be possible

  1. Rock mass classification system : transition from RMR to GSI.

    Science.gov (United States)

    2013-11-01

    The AASHTO LRFD Bridge Design Specifications is expected to replace the rock mass rating : (RMR) system with the Geological Strength Index (GSI) system for classifying and estimating : engineering properties of rock masses. This transition is motivat...

  2. Key issues for passive safety

    International Nuclear Information System (INIS)

    Hayns, M.R.

    1996-01-01

    The paper represents a summary of the introductory presentation made at this Advisory Group Meeting on the Technical Feasibility and Reliability of Passive Safety Systems. It was intended as an overview of our views on what are the key issues and what are the technical problems which might dominate any future developments of passive safety systems. It is, therefore, not a ''review paper'' as such and only record the highlights. (author)

  3. Key issues for passive safety

    Energy Technology Data Exchange (ETDEWEB)

    Hayns, M R [AEA Technology, Harwell, Didcot (United Kingdom). European Institutions; Hicken, E F [Forschungszentrum Juelich GmbH (Germany)

    1996-12-01

    The paper represents a summary of the introductory presentation made at this Advisory Group Meeting on the Technical Feasibility and Reliability of Passive Safety Systems. It was intended as an overview of our views on what are the key issues and what are the technical problems which might dominate any future developments of passive safety systems. It is, therefore, not a ``review paper`` as such and only record the highlights. (author).

  4. Unresolved safety issues summary: aqua book

    International Nuclear Information System (INIS)

    1983-06-01

    The unresolved safety issues summary is designed to provide the management of the nuclear regulatory commission with a quarterly overview of the progress and plans for completion of generic tasks addressing unresolved safety issues reported to congress pursuant to section 210 of the Energy Reorganization Act of 1974 as amended. The schedules in this book include a milestone at the end of each action plan which represents the initiation of the implementation process both with respect to incorporation of the technical resolution in the NRC official guidance or requirements and also the application of changes to individual operating plants. The schedule for implementation will not normally be included in the task action plan(s) for the resolution of a USI since the nature and extent of the activities necessary to accomplish the implementation cannot normally be reasonably determined prior to the determination of a technical resolution. The progress and status for implementation of unresolved safety issues for which a technical resolution has been completed are reported specifically in a separate table provided in this summary

  5. Effect of generic issues program on improving safety

    International Nuclear Information System (INIS)

    Fard, M. R.; Kauffman, J. V.

    2010-01-01

    The U.S. Nuclear Regulatory Commission (NRC) identifies (by its assessment of plant operation) certain issues involving public health and safety, the common defense and security, or the environment that could affect multiple entities under NRC jurisdiction. The Generic Issues Program (GIP) addresses the resolution of these Generic Issues (GIs). The resolution of these issues may involve new or revised rules, new or revised guidance, or revised interpretation of rules or guidance that affect nuclear power plant licensees, nuclear material certificate holders, or holders of other regulatory approvals. U.S. NRC provides information related to the past and ongoing GIP activities to the general public by the use of three main resources, namely NUREG-0933, 'Resolution of Generic Safety Issues, ' Generic Issues Management Control System (GIMCS), and GIP public web page. GIP information resources provide information such as historical information on resolved GIs, current status of the open GIs, policy documents, program procedures, GIP annual and quarterly reports and the process to contact GIP and propose a GI This paper provides an overview of the GIP and several examples of safety improvements resulting from the resolution of GIs. In addition, the paper provides a brief discussion of a few recent GIs to illustrate how the program functions to improve safety. (authors)

  6. Practicing industrial safety - issues involved

    International Nuclear Information System (INIS)

    Gunasekaran, P.

    2016-01-01

    Industrial safety is all about measures or techniques implemented to reduce the risk of injury, loss to persons, property or the environment in any industrial facility. The issue of industrial safety evolved concurrently with industrial development as a shift from compensation to prevention as well. Today, industrial safety is widely regarded as one of the most important factors that any business, large or small, must consider in its operations, as prevention of loss is also a part of profit. Factories Act of Central government and Rules made under it by the state deals with the provisions on industrial safety legislation. There are many other acts related to safety of personnel, property and environment. Occupational health and safety is also of primary concern. The aim is to regulate health and safety conditions for all employers. It includes safety standards and health standards. These acts encourage employers and employees to reduce workplace hazards and to implement new or improve existing safety and health standards; and develop innovative ways to achieve them. Maintain a reporting and record keeping system to monitor job-related injuries and illnesses; establish training programs to increase the number and competence of occupational safety and health personnel

  7. Safety Issues with Hydrogen as a Vehicle Fuel

    Energy Technology Data Exchange (ETDEWEB)

    L. C. Cadwallader; J. S. Herring

    1999-09-01

    This report is an initial effort to identify and evaluate safety issues associated with the use of hydrogen as a vehicle fuel in automobiles. Several forms of hydrogen have been considered: gas, liquid, slush, and hydrides. The safety issues have been discussed, beginning with properties of hydrogen and the phenomenology of hydrogen combustion. Safety-related operating experiences with hydrogen vehicles have been summarized to identify concerns that must be addressed in future design activities and to support probabilistic risk assessment. Also, applicable codes, standards, and regulations pertaining to hydrogen usage and refueling have been identified and are briefly discussed. This report serves as a safety foundation for any future hydrogen safety work, such as a safety analysis or a probabilistic risk assessment.

  8. Safety Issues with Hydrogen as a Vehicle Fuel

    Energy Technology Data Exchange (ETDEWEB)

    Cadwallader, Lee Charles; Herring, James Stephen

    1999-10-01

    This report is an initial effort to identify and evaluate safety issues associated with the use of hydrogen as a vehicle fuel in automobiles. Several forms of hydrogen have been considered: gas, liquid, slush, and hydrides. The safety issues have been discussed, beginning with properties of hydrogen and the phenomenology of hydrogen combustion. Safety-related operating experiences with hydrogen vehicles have been summarized to identify concerns that must be addressed in future design activities and to support probabilistic risk assessment. Also, applicable codes, standards, and regulations pertaining to hydrogen usage and refueling have been identified and are briefly discussed. This report serves as a safety foundation for any future hydrogen safety work, such as a safety analysis or a probabilistic risk assessment.

  9. Road safety issues for bus transport management.

    Science.gov (United States)

    Cafiso, Salvatore; Di Graziano, Alessandro; Pappalardo, Giuseppina

    2013-11-01

    Because of the low percentage of crashes involving buses and the assumption that public transport improves road safety by reducing vehicular traffic, public interest in bus safety is not as great as that in the safety of other types of vehicles. It is possible that less attention is paid to the significance of crashes involving buses because the safety level of bus systems is considered to be adequate. The purpose of this study was to evaluate the knowledge and perceptions of bus managers with respect to safety issues and the potential effectiveness of various technologies in achieving higher safety standards. Bus managers were asked to give their opinions on safety issues related to drivers (training, skills, performance evaluation and behaviour), vehicles (maintenance and advanced devices) and roads (road and traffic safety issues) in response to a research survey. Kendall's algorithm was used to evaluate the level of concordance. The results showed that the majority of the proposed items were considered to have great potential for improving bus safety. The data indicated that in the experience of the participants, passenger unloading and pedestrians crossing near bus stops are the most dangerous actions with respect to vulnerable users. The final results of the investigation showed that start inhibition, automatic door opening, and the materials and internal architecture of buses were considered the items most strongly related to bus passenger safety. Brake assistance and vehicle monitoring systems were also considered to be very effective. With the exception of driver assistance systems for passenger and pedestrian safety, the perceptions of the importance of other driver assistance systems for vehicle monitoring and bus safety were not unanimous among the bus company managers who participated in this survey. The study results showed that the introduction of new technologies is perceived as an important factor in improving bus safety, but a better understanding

  10. International conference on topical issues in nuclear safety. Contributed papers

    International Nuclear Information System (INIS)

    2001-01-01

    The objective of the Conference was to foster the exchange of information on topical issues in nuclear safety, with the aim of consolidating an international consensus on the present status of these issues, priorities for future work, and needs for strengthening international cooperation, including the IAEA recommendations for future activities. This book contains concise contributed papers submitted on issues falling within the thematic scope of the Conference: risk informed decision making, influence of external factors on safety, safety of fuel cycle facilities, safety of research reactors, and safety performance indicators

  11. International conference on topical issues in nuclear safety. Contributed papers

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-07-01

    The objective of the Conference was to foster the exchange of information on topical issues in nuclear safety, with the aim of consolidating an international consensus on the present status of these issues, priorities for future work, and needs for strengthening international cooperation, including the IAEA recommendations for future activities. This book contains concise contributed papers submitted on issues falling within the thematic scope of the Conference: risk informed decision making, influence of external factors on safety, safety of fuel cycle facilities, safety of research reactors, and safety performance indicators.

  12. Visit safety

    CERN Document Server

    2012-01-01

    Experiment areas, offices, workshops: it is possible to have co-workers or friends visit these places.     You already know about the official visits service, the VIP office, and professional visits. But do you know about the safety instruction GSI-OHS1, “Visits on the CERN site”? This is a mandatory General Safety Instruction that was created to assist you in ensuring safety for all your visits, whatever their nature—especially those that are non-official. Questions? The HSE Unit will be happy to answer them. Write to safety-general@cern.ch.   The HSE Unit

  13. Nuclear Structure Physics at GSI - Challenges and Perspectives

    Energy Technology Data Exchange (ETDEWEB)

    Muenzenberg, G.

    1999-12-31

    The perspectives at GSI for the exploration of exotic regions with new high-current accelerators and recent technical developments including single-atom decay studies, ultra sensitive {gamma}-spectroscopy, new set-ups for reaction studies at relativistic energies in complete kinematics, heavy ion storage rings, and low-energy heavy-ion-electron colliders will be discussed.

  14. The PRESPEC liquid-hydrogen target for in-beam gamma spectroscopy of exotic nuclei at GSI

    International Nuclear Information System (INIS)

    Louchart, C.; Gheller, J.M.; Chesny, Ph.; Authelet, G.; Rousse, J.Y.; Obertelli, A.; Boutachkov, P.; Pietri, S.; Ameil, F.; Audirac, L.; Corsi, A.; Dombradi, Z.; Gerl, J.; Gillibert, A.; Korten, W.; Mailleret, C.; Merchan, E.; Nociforo, C.; Pietralla, N.; Ralet, D.

    2014-01-01

    We report on a new liquid hydrogen and deuterium target dedicated to in-beam γ spectroscopy experiments in inverse kinematics at relativistic incident energies at GSI/FAIR. Target thicknesses from 10 to 80 mm can be achieved for an effective diameter of 60 mm. The target-cell and entrance window are maded of 200μm thick Mylar. The design has the advantage of being free of absorbing material at forward angles and 90°, allowing the detection of photons in a wide angular range. A commissioning experiment with a 54 Cr beam at 130 MeV/nucleon has been performed at GSI, using the Rare Isotopes INvestigation at GSI (RISING) detectors. The target has been shown to behave as expected and is ready for experiments at fragmentation Radioactive-Ion Beam Facilities. -- Highlights: • We report on a new liquid hydrogen target for gamma spectroscopy experiments at FAIR. • A commissioning experiment has been performed at GSI, using the RISING detectors. • The target behaves as expected and is ready for experiments

  15. Safety and licensing issues for Indian PHWRs

    International Nuclear Information System (INIS)

    Srinivasan, G.R.; Das, M.

    1997-01-01

    India has achieved competency in design, construction, commissioning and operation of Pressurized Heavy Water Reactor based Nuclear Power Plants and has completed more than 120 reactor operating years with an extremely satisfactory safety record. In this paper, the safety management in NPCIL and operational safety aspects are discussed, licensing and regulatory approach is described and some of the main safety issues for Indian PHWRs are brought out. (author)

  16. Characterization report for the ferrocyanide safety issue

    International Nuclear Information System (INIS)

    Pulsipher, B.A.; Burger, L.L.; Liebetrau, A.M.; Scheele, R.D.

    1997-06-01

    Recently PNNL was tasked by DOE to develop and demonstrate a risk-based strategic approach to characterizing Hanford's Nuclear Waste Tanks. This strategic approach was documented in a report entitled ''A Risk-Based Focused Decision-Management Approach for Justifying Characterization of Hanford Tank Waste''. In support of the general approach, a specific strategy for addressing each of the several safety issues associated with the tanks was developed. This report documents the approach for the Ferrocyanide Safety Issue. The purpose of this report is to describe a structured logic diagram (SLD) for determining the risk associated with the ferrocyanide tank safety issue and provide the supporting information for the SLD. The SLD addresses the resolution of risks resulting from the presence of ferrocyanide layers within the Hanford tanks. The informational requirements for determining risk from any reaction stemming from ferrocyanide are outlined in the SLD. This report will describe the potential paths to a successful resolution of the ferrocyanide safety issue. Complete development of the intervention pathway is outside the scope of this current activity. General descriptions of the approach, key components of the SLD, and conclusions are provided in the body of this report. The complete SLD, descriptions of each box shown in the SLD, a discussion on how to fill data needs, and a list of contributors is provided in the appendices

  17. Strategy for resolution of the flammable gas safety issue

    International Nuclear Information System (INIS)

    Johnson, G.D.

    1997-01-01

    This document provides a strategy for resolution of the Flammable Gas Safety Issue. It defines the key elements required for the following: Closing the Flammable Gas Unreviewed Safety Question (USQ); Providing the administrative basis for resolving the safety issue; Defining the data needed to support these activities; and Providing the technical and administrative path for removing tanks from the Watch List

  18. Strategy for resolution of the flammable gas safety issue

    Energy Technology Data Exchange (ETDEWEB)

    Johnson, G.D.

    1997-05-23

    This document provides a strategy for resolution of the Flammable Gas Safety Issue. It defines the key elements required for the following: Closing the Flammable Gas Unreviewed Safety Question (USQ); Providing the administrative basis for resolving the safety issue; Defining the data needed to support these activities; and Providing the technical and administrative path for removing tanks from the Watch List.

  19. Draft pilot report - Approaches to the resolution of safety issues

    International Nuclear Information System (INIS)

    2006-01-01

    The purpose of this report is to present in a concise form how some safety matters associated with currently operating light water reactors have been addressed. The issues discussed in this report are common to member countries with currently operating LWRs (PWR, BWR, VVER) and, as such, have wide interest in the nuclear safety community. Accordingly, this report can serve as a reference for researchers, regulations and others (e.g., industry) interested in understanding the approach and status of issues. This report should also be useful for knowledge transfer by documenting what has been done or is planned regarding selected safety matters and as a source for identifying reference material containing additional detail. The issues addressed in this report should not be viewed as questioning the safety of operating reactors, which have reached very high operational safety record, but rather as areas where uncertainty in knowledge exists, where safety assessment has been based on conservative assumptions, and where regulatory decisions need, or will need to be confirmed. Thus, the development of sound technical bases through continuing research will improve the current knowledge and allow for more realistic safety assessment. The safety issues discussed in this initial version of the report are: - design basis accident spectrum; - severe accident issues; - reactor pressure vessel integrity; - hydrogen control; - containment integrity; - accident management; - station blackout; - high burnup fuel; - power up-rates; - ECCS strainer clogging; - boron dilution. For each issue, the scope of the issue is defined, its status discussed and planned work or research described, including schedule. This pilot version of the report is limited to input from nine countries (Belgium, Czech Republic, Finland, France, Germany, Japan, Korea, Sweden and the U.S.). An overview of this information for each issue by country is provided in the table. This document does not contain a

  20. High-heat tank safety issue resolution program plan. Revision 2

    International Nuclear Information System (INIS)

    Wang, O.S.

    1994-12-01

    The purpose of this program plan is to provide a guide for selecting corrective actions that will mitigate and/or remediate the high-heat waste tank safety issue for single-shell tank 241-C-106. The heat source of approximately 110,000 Btu/hr is the radioactive decay of the stored waste material (primarily 90 Sr) inadvertently transferred into the tank in the later 1960s. Currently, forced ventilation, with added water to promote thermal conductivity and evaporation cooling, is used for heat removal. The method is very effective and economical. At this time, the only viable solution identified to permanently resolve this safety issue is the removal of heat-generating waste in the tank. This solution is being aggressively pursued as the only remediation method to this safety issue, and tank 241-C-106 has been selected as the first single-shell tank for retrieval. The current cooling method and other alternatives are addressed in this program as means to mitigate this safety issue before retrieval. This program plan has three parts. The first part establishes program objectives and defines safety issue, drivers, and resolution criteria and strategy. The second part evaluates the high-heat safety issue and its mitigation and remediation methods and other alternatives according to resolution logic. The third part identifies major tasks and alternatives for mitigation and resolution of the safety issue. A table of best-estimate schedules for the key tasks is also included in this program plan

  1. A Modular VME Data Acquisition System for Counter Applications at the GSI Synchrotron

    CERN Document Server

    Liakin, D A

    2003-01-01

    Particle counters perform the control of beam loss and slowly extracted currents at the heavy ion synchrotron (SIS) at GSI. A new VME/Lynx - PC/Linux based data acquisition system has been developed to combine the operating purposes beam loss measurement, spill analysis, spill structure measurement and matrix switching functionality in one single assembly. In this paper a detailed PC-side software description is presented. To achieve best system stability, the software has been divided into time critical networking and data deploying threads and low or normal priority interface tasks. Some new abilities in the fields of data computation and presentation are reported. A hardware description is presented, in detail a programmable GSI-EVENT controller, which is based on an ordinary 8 bit RISC microprocessor and which has been integrated into the system, to synchronize the data acquisition with the sophisticated “virtual accelerator” timing at GSI. First experiences gained while the commission...

  2. Vectra GSI, Inc. low-level waste melter testing Phase 1 test report

    Energy Technology Data Exchange (ETDEWEB)

    Stegen, G.E.; Wilson, C.N.

    1996-02-21

    A multiphase program was initiated in 1994 to test commercially available melter technologies for the vitrification of the low-level waste (LLW) stream from defense wastes stored in underground tanks at the Hanford Site in southeastern Washington State. Vectra GSI, Inc. was one of seven vendors selected for Phase 1 of the melter demonstration tests using simulated LLW that were completed during fiscal year 1995. The attached report prepared by Vectra GSI, Inc. describes results of melter testing using slurry feed and dried feeds. Results of feed drying and prereaction tests using a fluid bed calciner and rotary dryer also are described.

  3. Vectra GSI, Inc. low-level waste melter testing Phase 1 test report

    International Nuclear Information System (INIS)

    Stegen, G.E.; Wilson, C.N.

    1996-01-01

    A multiphase program was initiated in 1994 to test commercially available melter technologies for the vitrification of the low-level waste (LLW) stream from defense wastes stored in underground tanks at the Hanford Site in southeastern Washington State. Vectra GSI, Inc. was one of seven vendors selected for Phase 1 of the melter demonstration tests using simulated LLW that were completed during fiscal year 1995. The attached report prepared by Vectra GSI, Inc. describes results of melter testing using slurry feed and dried feeds. Results of feed drying and prereaction tests using a fluid bed calciner and rotary dryer also are described

  4. A new standard method for the surveying and alignment of beamline facilities at GSI

    Energy Technology Data Exchange (ETDEWEB)

    Wirth, H. [Metronom, Gesellschaft fuer Industrievermessung mbH, Mainz (Germany); Moritz, G.

    1996-01-01

    The GSI institute of heavy ion research is financed by the country of Germany. Founded in 1969, the main emphasis of the institute`s work is the research of the characteristics of atomic nuclei. The Universal Linear Accelerator UNILAC was built first and in 1987 new facilities were added to the setup. The GSI accelarators allow acceleration of all atomic nuclei up to Uranium to an energy of 20 MeV/u. In 1993 Metronome started working on a new alignment concept for the GSI`s accelerators. Metronome has developed the TASA concept. TSAS stands for Techeometric Accelerator Surveying and Alignment and is based on the new generation of high-precision total stations. One feature included in the TASA Concept, has been the replacement of all mobile plates by fixed consoles. An immense advantage of new fixed consoles, welded onto every component, is that they can be positioned to locations where they can be easily measured, simply by taking measuring conditions (lines of sight, heights of stands, error-figures, configuration, etc.) into consideration. The TASA Concept can be used for all alignments of the different GSI accelerators. For all accelerators a special investigation was carried out to check if it is possible to position a new pillar system and to install new consoles on the components. The free positioning of fiducial points makes it possible to use polar measurements for all components. This is an enormous advantage and a step forward for alignment procedures at GSI. Furthermore, use of a total station as opposed to the ECDS System means that one operator less is needed. (S.Y.)

  5. 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)

  6. Assessment of basic safety issues

    International Nuclear Information System (INIS)

    Queniart, D.

    1996-01-01

    Work on the French-German common safety approach for future nuclear power plants continued in 1994 to allow for more detailed discussion of some major issues, taking into account the options provided by the industry for the EPR (European Pressurized water Reactor) project, as described in the document entitled 'Conceptual Safety Features Review File'. Seven meetings of a GPR/RSK advisory experts subgroup, six GPR/RSK plenary sessions and six meetings of the safety authorities (DFD) dealt with the following topics: design of the systems and use of probabilistic approaches, application of a 'break preclusion' approach to the main primary pipings, protection against external hazards (aircraft crashes, explosions, earthquakes), provisions with respect to accidents involving core melt and to containment design, radiological consequences of reference accidents and accidents involving core melt at low pressure. The important aspects of the joint policy are recalled in the presentation. The whole set of GPR/RSK recommendations were agreed by the French and German safety authorities during the DFD meetings of 1994 and early 1995. The utilities decided to begin the basic design phase in February, 1995. Work is now continuing to develop the common French-German approach for future nuclear power plants, in the same way as before. In 1995, this mainly covers the design of the containment and of the systems, but also new issues such as the protection against secondary side overpressurization, radiological protection of workers and radioactive wastes. (J.S.). 3 figs., 1 tab

  7. Light Water Reactor Generic Safety Issues Database (LWRGSIDB). User's manual

    International Nuclear Information System (INIS)

    1999-01-01

    The IAEA Conference on 'The Safety of Nuclear Power: Strategy for the Future' in 1991 was a milestone in nuclear safety. The objective of this conference was to review nuclear power safety issues for which achieving international consensus would be desirable, to address concerns on nuclear safety and to formulate recommendations for future actions by national and international authorities to advance nuclear safety to the highest level. Two of the important items addressed by this conference were ensuring and enhancing safety of operating plants and treatment of nuclear power plants built to earlier safety standards. Some of the publications related to these two items that have been issued subsequent to this conference are: A Common Basis for Judging the Safety of Nuclear Power Plants Built to Earlier Standards, INSAG-8 (1995), the IAEA Safety Guide 50-SG-O12, Periodic Safety Review of Operational Nuclear Power Plants (1994) and IAEA Safety Reports Series No. 12, Evaluation of the Safety of Operating Nuclear Power Plants Built to Earlier Standards: A Common Basis for Judgement (1998). Some of the findings of the 1991 conference have not yet been fully addressed. An IAEA Symposium on Reviewing the Safety of Existing Nuclear Power Plants in 1996 showed that there is an urgent need for operating organizations and national authorities to review those operating nuclear power plants which do not reach the high safety levels of the vast majority of plants and to undertake improvements with assistance from the international community if required. Safety reviews of operating nuclear power plants take on added importance in the context of the Convention on Nuclear Safety and its implementation. In order to perform safety reviews and to reassess the safety of operating nuclear power plants in a uniform manner, it is imperative to have an internationally accepted reference. Existing guidance needs to be complemented by a list of safety issues which have been encountered and

  8. Current safety issues of CANDU licensing

    International Nuclear Information System (INIS)

    Lee, Y.; Natalizio, A.

    1994-01-01

    As requested by Korea Institute of Nuclear Safety(KINS), the status of five generic licensing issues has been examined and their potential impact on a new plant that would be constructed in Canada has been evaluated. The results and conclusions of this evaluation are summarized as follows: steam explosion in calandria, hydrogen explosion in containment, use of PSA in reactor licensing, human factors, safety critical software

  9. Therapy operation at GSI

    International Nuclear Information System (INIS)

    Scheeler, U.; Wilms, D.

    2004-01-01

    GSI is the heavy ion research center in Germany operating the three accelerators UNILAC (linac), SIS (synchrotron) and ESR (storage ring). Experiments are made on the fields of nuclear and atomic physics, plasma physics, nuclear chemistry, material research and biophysics. The most important program of the biophysics group is the study of the advantage of Carbon ions for cancer irradiation. The developed raster-scanning technique allows the direct 3D irradiation of irregular shaped tumor and minimizes the dose in healthy tissue [1],[2]. This method requires the reliable request of a large variety of beam parameters (energy, intensity, beam-spot diameter) for sequential synchrotron cycles. Certain restrictions to the physics experimental program have to be considered during the treatment sessions. To deliver excellent conditions for the other experiments, these restrictions had to be kept a small as possible. (author)

  10. The cost system of GSI - heavy ion facility in Darmstadt

    International Nuclear Information System (INIS)

    1979-01-01

    The paper gives an overview about the organization and the research program of the GSI (Heavy Ion Facility in Darmstadt). The cost accounting system is discussed in detail, financing, cost center accounting and cost unit accounting are described. (A.N.)

  11. Safety issue resolution strategy plan for inactive miscellaneous underground storage tanks

    International Nuclear Information System (INIS)

    Wang, O.S.; Powers, T.B.

    1994-09-01

    The purpose of this strategy plan is to identify, confirm, and resolve safely issues associated with inactive miscellaneous underground storage tanks (MUSTs) using a risk-based priority approach. Assumptions and processes to assess potential risks and operational concerns are documented in this report. Safety issue priorities are ranked based on a number of considerations including risk ranking and cost effectiveness. This plan specifies work scope and recommends schedules for activities related to resolving safety issues, such as collecting historical data, searching for authorization documents, performing Unreviewed Safety Question (USQ) screening and evaluation, identifying safety issues, imposing operational controls and monitoring, characterizing waste contents, mitigating and resolving safety issues, and fulfilling other remediation requirements consistent with the overall Tank Waste Remediation System strategy. Recommendations for characterization and remediation are also recommended according to the order of importance and practical programmatic consideration

  12. Development and user guide for GSI

    International Nuclear Information System (INIS)

    Lee, Dong Young; Kim, Jeong Taek; Hwang, In Ku; Ham, Chang Sik; Kwon, Ki Chun.

    1997-05-01

    ADIOS(Alarm Diagnosis and Integrated Operator Support) is designed to improve the operation performance of the man-machine interface system by giving dynamic alarm priority according to plant situation, and implemented with G2 real-time expert shell. It processes alarm priority in G2 using the plant data which is received from simulator, and sends the processed alarm signals to the alarm tile through TCP/IP communication link. This report includes some experiences about the GSI(G2 Standard Interface) configuration and user programming, and describes about how to build on-line ADIOS system. (author)

  13. A prioritization of generic safety issues. Supplement 21, Revision insertion instructions

    Energy Technology Data Exchange (ETDEWEB)

    None, None

    1996-12-31

    The report presents the safety priority ranking for generic safety issues related to nuclear power plants. The purpose of these rankings is to assist in the timely and efficient allocation of NRC resources for the resolution of those safety issues that have a significant potential for reducing risk. The safety priority rankings are HIGH, MEDIUM, LOW, and DROP, and have been assigned on the basis of risk significance estimates, the ratio of risk to costs and other impacts estimated to result if resolution of the safety issues were implemented, and the consideration of uncertainties and other quantitative or qualitative factors. To the extent practical, estimates are quantitative.

  14. A prioritization of generic safety issues. Supplement 21, Revision insertion instructions

    International Nuclear Information System (INIS)

    1996-01-01

    The report presents the safety priority ranking for generic safety issues related to nuclear power plants. The purpose of these rankings is to assist in the timely and efficient allocation of NRC resources for the resolution of those safety issues that have a significant potential for reducing risk. The safety priority rankings are HIGH, MEDIUM, LOW, and DROP, and have been assigned on the basis of risk significance estimates, the ratio of risk to costs and other impacts estimated to result if resolution of the safety issues were implemented, and the consideration of uncertainties and other quantitative or qualitative factors. To the extent practical, estimates are quantitative.

  15. 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

  16. Guidelines for nuclear-power-plant safety-issue-prioritization information development

    International Nuclear Information System (INIS)

    Andrews, W.B.; Gallucci, R.H.V.; Heaberlin, S.W.; Bickford, W.E.; Konzek, G.J.; Strenge, D.L.; Smith, R.I.; Weakley, S.A.

    1983-02-01

    Pacific Northwest Laboratory has developed a methodology, with examples, to calculate - to an approximation serviceable for prioritization purposes - the risk, dose and cost impacts of implementing resolutions to reactor safety issues. This report is an applications guide to issue-specific calculations. A description of the approach, mathematical models, worksheets and step-by-step examples are provided. Analysis using this method is intended to provide comparable results for many issues at a cost of two staff-weeks per issue. Results will be used by the NRC to support decisions related to issue priorities in allocation of resources to complete safety issue resolutions

  17. Grid Computing at GSI for ALICE and FAIR - present and future

    International Nuclear Information System (INIS)

    Schwarz, Kilian; Uhlig, Florian; Karabowicz, Radoslaw; Montiel-Gonzalez, Almudena; Zynovyev, Mykhaylo; Preuss, Carsten

    2012-01-01

    The future FAIR experiments CBM and PANDA have computing requirements that fall in a category that could currently not be satisfied by one single computing centre. One needs a larger, distributed computing infrastructure to cope with the amount of data to be simulated and analysed. Since 2002, GSI operates a tier2 center for ALICE-CERN. The central component of the GSI computing facility and hence the core of the ALICE tier2 centre is a LSF/SGE batch farm, currently split into three subclusters with a total of 15000 CPU cores shared by the participating experiments, and accessible both locally and soon also completely via Grid. In terms of data storage, a 5.5 PB Lustre file system, directly accessible from all worker nodes is maintained, as well as a 300 TB xrootd-based Grid storage element. Based on this existing expertise, and utilising ALICE's middleware ‘AliEn’, the Grid infrastructure for PANDA and CBM is being built. Besides a tier0 centre at GSI, the computing Grids of the two FAIR collaborations encompass now more than 17 sites in 11 countries and are constantly expanding. The operation of the distributed FAIR computing infrastructure benefits significantly from the experience gained with the ALICE tier2 centre. A close collaboration between ALICE Offline and FAIR provides mutual advantages. The employment of a common Grid middleware as well as compatible simulation and analysis software frameworks ensure significant synergy effects.

  18. A prioritization of generic safety issues. Supplement 19, Revision insertion instructions

    International Nuclear Information System (INIS)

    1995-11-01

    The report presents the safety priority ranking for generic safety issues related to nuclear power plants. The purpose of these rankings is to assist in the timely and efficient allocation of NRC resources for the resolution of those safety issues that have a significant potential for reducing risk. The safety priority rankings are HIGH, MEDIUM, LOW, and DROP, and have been assigned on the basis of risk significance estimates, the ratio of risk to costs and other impacts estimated to result if resolution of the safety issues were implemented, and the consideration of uncertainties and other quantitative or qualitative factors. To the extent practical, estimates are quantitative. This document provides revisions and amendments to the report

  19. A prioritization of generic safety issues. Supplement 19, Revision insertion instructions

    Energy Technology Data Exchange (ETDEWEB)

    None

    1995-11-01

    The report presents the safety priority ranking for generic safety issues related to nuclear power plants. The purpose of these rankings is to assist in the timely and efficient allocation of NRC resources for the resolution of those safety issues that have a significant potential for reducing risk. The safety priority rankings are HIGH, MEDIUM, LOW, and DROP, and have been assigned on the basis of risk significance estimates, the ratio of risk to costs and other impacts estimated to result if resolution of the safety issues were implemented, and the consideration of uncertainties and other quantitative or qualitative factors. To the extent practical, estimates are quantitative. This document provides revisions and amendments to the report.

  20. Determination of the mechanical parameters of rock mass based on a GSI system and displacement back analysis

    Science.gov (United States)

    Kang, Kwang-Song; Hu, Nai-Lian; Sin, Chung-Sik; Rim, Song-Ho; Han, Eun-Cheol; Kim, Chol-Nam

    2017-08-01

    It is very important to obtain the mechanical paramerters of rock mass for excavation design, support design, slope design and stability analysis of the underground structure. In order to estimate the mechanical parameters of rock mass exactly, a new method of combining a geological strength index (GSI) system with intelligent displacment back analysis is proposed in this paper. Firstly, average spacing of joints (d) and rock mass block rating (RBR, a new quantitative factor), surface condition rating (SCR) and joint condition factor (J c) are obtained on in situ rock masses using the scanline method, and the GSI values of rock masses are obtained from a new quantitative GSI chart. A correction method of GSI value is newly introduced by considering the influence of joint orientation and groundwater on rock mass mechanical properties, and then value ranges of rock mass mechanical parameters are chosen by the Hoek-Brown failure criterion. Secondly, on the basis of the measurement result of vault settlements and horizontal convergence displacements of an in situ tunnel, optimal parameters are estimated by combination of genetic algorithm (GA) and numerical simulation analysis using FLAC3D. This method has been applied in a lead-zinc mine. By utilizing the improved GSI quantization, correction method and displacement back analysis, the mechanical parameters of the ore body, hanging wall and footwall rock mass were determined, so that reliable foundations were provided for mining design and stability analysis.

  1. Issues of Safety and Security: New Challenging to Malaysia Tourism Industry

    OpenAIRE

    Mohd Ayob Norizawati; Masron Tarmiji

    2014-01-01

    The safety and security issues nowadays become one of the forces causing changes in tourism industry in era of millennium. The main concern of this issues more focus on crime rates, terrorism, food safety, health issues and natural disaster. This topic gained the popularity in tourism research after 9/11 tragedy and since then the academicians and practitioners started seeking the best solution in ways to mitigate these negative impacts. For Malaysia, the image as safety and secure destinatio...

  2. Comparison of Dextran Perfusion and GSI-B4 Isolectin Staining in a Mouse Model of Oxygen-induced Retinopathy.

    Science.gov (United States)

    Huang, Shaofen; Liang, Jiajian; Yam, Gary Hin-Fai; Lu, Zhihao; Pang, Chi Pui; Chen, Haoyu

    2015-06-01

    Oxygen-induced retinopathy (OIR) is a robust and widely used animal model for the study of retinal neovascularization (NV). Dextran perfusion and Griffonia simplicifolia isolectin B4 (GSI-B4) staining are two common methods for examining the occurrence and extent of OIR. This study provides a quantitative comparison of the two for OIR detection. At postnatal day 7 (PN7), fifteen C57BL/6J mice were exposed to a 75% hyperoxic condition for 5 days and then returned to room air conditions. At PN17, the mice received intravitreal injection of GSI-B4 Alexa Fluor 568 conjugate. After 10 hours, they were infused with FITC-dextran conjugate via the left ventricle. Retinal flat mounts were photographed by confocal microscopy. Areas with fluorescent signals and the total retinal areas were quantified by Image J software. Both GSI-B4 and dextran detected the peripheral neovascular area. The mean hyper fluorescence area was 0.33 ± 0.14% of whole retinal area determined by GSI-B4 staining and 0.25 ± 0.28% determined by dextran perfusion. The difference between the two measures was 0.08% (95% CI:-0.59%, 0.43%). The Pearson correlation coefficient between the two methods was 0.386,P =0.035. The mean coincidence rates were 14.3 ± 13.4% and 24.9 ± 18.5% for GSI-B4 and dextran staining, respectively. Both methods can complement each other in demonstrating and quantitatively evaluating retinal NV. A poor agreement was found between the two methods; GSI-B4 isolectin was more effective than FITC-dextran perfusion in evaluating the extent of retinal NV in a mouse model of OIR.

  3. Guidelines for nuclear-power-plant safety-issue prioritization information development

    International Nuclear Information System (INIS)

    Andrews, W.B.; Gallucci, R.H.V.; Konzek, G.J.

    1983-05-01

    This is the second in a series of reports to document the use of a methodology developed by the Pacific Northwest Laboratory to calculate, for prioritization purposes, the risk, dose and cost impacts of implementing resolutions to reactor safety issues. This report contains results of issue-specific analyses for 15 issues. Each issue was considered within the contraints of available information as of September 1982 and two staff-weeks of labor. The results will be referenced, as one consideration in setting priorities for reactor safety issues, in an NRC prioritization report to be published at a future date

  4. Guidelines for nuclear power plant safety issue prioritization information development. Supplement 2

    International Nuclear Information System (INIS)

    Andrews, W.B.; Gallucci, R.H.V.; Konzek, G.J.; Heaberlin, S.W.; Fecht, B.A.; Allen, C.H.; Allen, R.D.; Bickford, W.E.; Carbaugh, E.H.; Lewis, J.R.

    1983-12-01

    This is the third in a series of reports to document the use of a methodology developed by the Pacific Northwest Laboratory to calculate, for prioritization purposes, the risk, dose and cost impacts of implementing resolutions to reactor safety issues (NUREG/CR-2800, Andrews et al. 1983). This report contains results of issue-specific analyses for 31 issues. Each issue was considered within the constraints of available information as of summer 1983, and two staff-weeks of labor. The results are referenced, as one consideration in setting priorities for reactor safety issues, in NUREG-0933, A Prioritization of Generic Safety Issues

  5. Topical issues in nuclear, radiation and radioactive waste safety. Contributed papers

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-08-01

    The IAEA International Conference on Topical Issues in Nuclear, Radiation and Radioactive Waste Safety was held in Vienna, Austria, 30 August - 4 September 1998 with the objective to foster the exchange of information on topical issues in nuclear, radiation and radioactive waste safety, with the aim of consolidating an international consensus on: the present status of these issues; priorities for future work; and needs for strengthening international co-operation, including recommendations for the IAEA`s future activities. The document includes 43 papers presented at the Conference dealing with the following topical issues: Safety Management; Backfitting, Upgrading and Modernization of NPPs; Regulatory Strategies; Occupational Radiation Protection: Trends and Developments; Situations of Chronic Exposure to Residual Radioactive Materials: Decommissioning and Rehabilitation and Reclamation of Land; Radiation Safety in the Far Future: The Issue of Long Term Waste Disposal. A separate abstract and indexing were provided for each paper. Refs, figs, tabs

  6. Topical issues in nuclear, radiation and radioactive waste safety. Contributed papers

    International Nuclear Information System (INIS)

    1998-08-01

    The IAEA International Conference on Topical Issues in Nuclear, Radiation and Radioactive Waste Safety was held in Vienna, Austria, 30 August - 4 September 1998 with the objective to foster the exchange of information on topical issues in nuclear, radiation and radioactive waste safety, with the aim of consolidating an international consensus on: the present status of these issues; priorities for future work; and needs for strengthening international co-operation, including recommendations for the IAEA's future activities. The document includes 43 papers presented at the Conference dealing with the following topical issues: Safety Management; Backfitting, Upgrading and Modernization of NPPs; Regulatory Strategies; Occupational Radiation Protection: Trends and Developments; Situations of Chronic Exposure to Residual Radioactive Materials: Decommissioning and Rehabilitation and Reclamation of Land; Radiation Safety in the Far Future: The Issue of Long Term Waste Disposal. A separate abstract and indexing were provided for each paper

  7. ASY-EOS experiment at GSI

    Directory of Open Access Journals (Sweden)

    Kezzar K.

    2012-07-01

    Full Text Available The elliptic-flow ratio of neutrons with respect to protons in reactions of neutron rich Heavy-Ion at intermediate energies has been recently proposed as an observable sensitive to the strength of the symmetry term in the nuclear equation of state (EOS at supra-saturation densities. The recent results obtained from the existing FOPI/LAND data for 197Au+197Au collisions at 400 MeV/nucleon in comparison with the UrQMD model allowed a first estimate of the symmetry term of the EOS but suffer from a considerable statistical uncertainty. In order to obtain an improved data set for Au+Au collisions and to extend the study to other systems, a new experiment was carried out at the GSI laboratory by the ASY-EOS collaboration in May 2011.

  8. Future Facility: FAIR at GSI

    International Nuclear Information System (INIS)

    Rosner, Guenther

    2007-01-01

    The Facility for Antiproton and Ion Research, FAIR, is a new particle accelerator facility to be built at the GSI site in Germany. The research at FAIR will cover a wide range of topics in nuclear and hadron physics, high density plasma and atomic physics, and applications in condensed matter physics and biology. A 1.1 km circumference double ring of rapidly cycling 100 and 300 Tm synchrotrons, will be FAIR's central accelerator system. It will be used to produce, inter alia, high intensity secondary beams of antiprotons and short-lived radioactive nuclei. A subsequent suite of cooler and storage rings will deliver heavy ion and antiproton beams of unprecedented quality. Large experiments are presently being designed by the NUSTAR, PANDA, PAX, CBM, SPARC, FLAIR, HEDgeHOB and BIOMAT collaborations

  9. An interagency space nuclear propulsion safety policy for SEI - Issues and discussion

    Science.gov (United States)

    Marshall, A. C.; Sawyer, J. C., Jr.

    1991-01-01

    An interagency Nuclear Safety Policy Working Group (NSPWG) was chartered to recommend nuclear safety policy, requirements, and guidelines for the Space Exploration Initiative nuclear propulsion program to facilitate the implementation of mission planning and conceptual design studies. The NSPWG developed a top level policy to provide the guiding principles for the development and implementation of the nuclear propulsion safety program and the development of Safety Functional Requirements. In addition, the NSPWG reviewed safety issues for nuclear propulsion and recommended top level safety requirements and guidelines to address these issues. Safety topics include reactor start-up, inadvertent criticality, radiological release and exposure, disposal, entry, safeguards, risk/reliability, operational safety, ground testing, and other considerations. In this paper the emphasis is placed on the safety policy and the issues and considerations that are addressed by the NSPWG recommendations.

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

    Science.gov (United States)

    Barr, Jennieffer; Welch, Anthony

    2012-07-01

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

  11. Assimilation of NUCAPS Retrieved Profiles in GSI for Unique Forecasting Applications

    Science.gov (United States)

    Berndt, Emily Beth; Zavodsky, Bradley; Srikishen, Jayanthi; Blankenship, Clay

    2015-01-01

    Hyperspectral IR profiles can be assimilated in GSI as a separate observation other than radiosondes with only changes to tables in the fix directory. Assimilation of profiles does produce changes to analysis fields and evidenced by: Innovations larger than +/-2.0 K are present and represent where individual profiles impact the final temperature analysis.The updated temperature analysis is colder behind the cold front and warmer in the warm sector. The updated moisture analysis is modified more in the low levels and tends to be drier than the original model background Analysis of model output shows: Differences relative to 13-km RAP analyses are smaller when profiles are assimilated with NUCAPS errors. CAPE is under-forecasted when assimilating NUCAPS profiles, which could be problematic for severe weather forecasting Refining the assimilation technique to incorporate an error covariance matrix and creating a separate GSI module to assimilate satellite profiles may improve results.

  12. Questionnaire responses concerning safety issues in MR examination

    International Nuclear Information System (INIS)

    Yamaguchi-Sekino, Sachiko; Nakai, Toshiharu; Muranaka, Hiroyuki

    2011-01-01

    Recently, the rising numbers of medical implants and scanners with higher static magnetic field have increased safety concerns for magnetic resonance (MR) examination. To determine future safety focus, we distributed anonymous questionnaires to 3250 members of the Japanese Society for Magnetic Resonance in Medicine (JSMRM) and received 978 responses. Safety issues on the questionnaire concentrated on the handling of patients with implants (Q7-18, appendix), acoustic trauma due to scanning (Q19-21, appendix), and MR compatibility within the scanner room (Q22-25, appendix). Ninety-three percent of respondents indicated they had encountered cases with implants or medical materials of unknown MR compatibility; 21.7% reported heating problems and 15.0%, nerve stimulation problems, in patients with implants during MR examination. Although 88.7% of respondents recognized the term ''MR compatibility'', 68.2% indicated limited detailed understanding of the term. Eleven percent had had cases with suspected acoustic injury from MR scanner noise. Scanner noise levels were not clarified in any way in 37.4% cases, but 69.5% applied ear protection to patients. Labeling of ''MR compatibility'' of equipment brought into the MR scanner room was reported by 71.9%. More than 50% experienced MR compatibility issues related to equipment brought into the MR scanner room. With regard to safety issues on metallic objects which are implanted in MR workers, 88.1% indicated they would continue current operations even the implant is inside the body. Respondents identified lectures and seminars by professional societies, safety training by manufacturers, and information from the Internet and literature as the 3 main sources for up-dating safety information for MR examination. (author)

  13. Characterization strategy report for the organic safety issues

    International Nuclear Information System (INIS)

    Goheen, S.C.; Campbell, J.A.; Fryxell, G.E.

    1997-08-01

    This report describes a logical approach to resolving potential safety issues resulting from the presence of organic components in hanford tank wastes. The approach uses a structured logic diagram (SLD) to provide a pathway for quantifying organic safety issue risk. The scope of the report is limited to selected organics (i.e., solvents and complexants) that were added to the tanks and their degradation products. The greatest concern is the potential exothermic reactions that can occur between these components and oxidants, such as sodium nitrate, that are present in the waste tanks. The organic safety issue is described in a conceptual model that depicts key modes of failure-event reaction processes in tank systems and phase domains (domains are regions of the tank that have similar contents) that are depicted with the SLD. Applying this approach to quantify risk requires knowing the composition and distribution of the organic and inorganic components to determine (1) how much energy the waste would release in the various domains, (2) the toxicity of the region associated with a disruptive event, and (3) the probability of an initiating reaction. Five different characterization options are described, each providing a different level of quality in calculating the risks involved with organic safety issues. Recommendations include processing existing data through the SLD to estimate risk, developing models needed to link more complex characterization information for the purpose of estimating risk, and examining correlations between the characterization approaches for optimizing information quality while minimizing cost in estimating risk

  14. The ASY-EOS Experiment at GSI

    Directory of Open Access Journals (Sweden)

    Russotto P.

    2016-01-01

    Full Text Available The elliptic-flow ratio of neutrons with respect to protons or light complex particles in reactions of heavy ions at pre-relativistic energies has been proposed as an observable sensitive to the strength of the symmetry term of the nuclear equation of state at supra-saturation densities. In the ASY-EOS experiment at the GSI laboratory, flows of neutrons and light charged particles were measured for 197Au+197Au collisions at 400 MeV/nucleon. Flow results obtained for the Au+Au system, in comparison with predictions of the UrQMD transport model, confirm the moderately soft to linear density dependence of the symmetry energy deduced from the earlier FOPI-LAND data.

  15. Consideration of social scientific issues in a safety case. Final report

    International Nuclear Information System (INIS)

    Sailer, Michael; Kallenbach-Herbert, Beate; Brohmann, Bettina; Spieth-Achtnich, Angelika

    2010-01-01

    The research outcome presented here - a model for identifying and describing safety-relevant social scientific issues - provides a scientific basis for addressing these issues in a safety case. In order for them to be implemented in a repository process, it would be necessary to elaborate in greater detail the initial conceptual foundations that have been laid in this research project in line with the project's terms of reference. The requisite elaboration relates to binding rules for designing the repository process, particularly with regard to the stages in which the safety case is to be developed during planning, approval, construction and operation through to repository closure. Such detailed elaboration also needs to involve specifying the extent to which each social scientific issue and sub-issue is to be addressed in the different stages. Consideration would need to be given not only to the relevance of the issue for a given stage but also to the various options and methods for providing proof of safety. It would be possible to draw on experiences with handling safety management in nuclear power plants - a sphere in which over the last ten years efforts have been ongoing to develop methods for presentation by the operator and review by the authorities. Furthermore, it is likely that the social scientific issues relevant to a safety case cannot be defined once and for all in a single process, but that the need for continual revision and adaptation will arise due to both the increasing knowledge acquired during the course of the repository process and the experiences and expectations of stakeholders (similarly to experiences in the sphere of scientific-technological requirements). Appropriate conditions need to be defined for such a process. This process could be supported by implementing the option mentioned above whereby a regulatory definition of safety management for geological disposal is formulated which encompasses all safety-relevant social scientific

  16. Safety issues for superconducting fusion magnets

    International Nuclear Information System (INIS)

    Hsieh, S.Y.; Reich, M.; Powell, J.R.

    1978-01-01

    Safety issues for future superconducting fusion magnet systems are examined. It is found that safety and failure experience with existing superconducting magnets is not very applicable to predictions as to the safety and reliability of fusion magnets. Such predictions will have to depend on analysis and judgement for many years to come, rather than on accumulated experience. A number of generic potential structural, thermal-hydraulic, and electrical safety problems are identified and analyzed. Prevention of quenches and non-uniform temperature distributions, if quenches should occur, is of great importance, since such events can trigger processes which lead to magnet damage or failure. Engineered safety features will be necessary for fusion magnets. Two of these, an energy dispersion system and external coil containment, appear capable of reducing the probability of coil disruption to very low levels. However, they do not prevent loss of function accidents which are of economic concern. Elaborate detector, temperature equalization, and energy removal systems will be required to minimize the chances of loss of function accidents

  17. Verification and validation issues for digitally-based NPP safety systems

    International Nuclear Information System (INIS)

    Ets, A.R.

    1993-01-01

    The trend toward standardization, integration and reduced costs has led to increasing use of digital systems in reactor protection systems. While digital systems provide maintenance and performance advantages, their use also introduces new safety issues, in particular with regard to software. Current practice relies on verification and validation (V and V) to ensure the quality of safety software. However, effective V and V must be done in conjunction with a structured software development process and must consider the context of the safety system application. This paper present some of the issues and concerns that impact on the V and V process. These include documentation of systems requirements, common mode failures, hazards analysis and independence. These issues and concerns arose during evaluations of NPP safety systems for advanced reactor designs and digital I and C retrofits for existing nuclear plants in the United States. The pragmatic lessons from actual systems reviews can provide a basis for further refinement and development of guidelines for applying V and V to NPP safety systems. (author). 14 refs

  18. Critical safety issues in the design of fusion machines

    International Nuclear Information System (INIS)

    Kramer, W.

    1991-01-01

    In the course of developing fusion machines both general safety considerations and safety assessments for the various components and systems of actual machines increase in number and become more and more coherent. This is particularly true for the NET/ITER projects where safety analysis plays an increasing role for the design of the machine. Since in a D/T tokamak the radiological hazards will be dominant basic radiological safety objectives are discussed. Critical safety issues as identified in particular by the NET/ITER community are reviewed. Subsequently, issues of major concern are considered both for normal operation and for conceivable accidents. The following accidents are considered to be crucial: Loss of cooling in plasma facing components, loss of vacuum, tritium system failure, and magnet system failure. To mitigate accident consequences a confinement concept based on passive features and multiple barriers including detritiation and filtering has to be applied. The reactor building as final barrier needs special attention to cope with both internal and external hazards. (orig.)

  19. Recent developments at the ISOL facility of GSI Darmstadt

    CERN Document Server

    Roeckl, E; Burkard, K; Döring, J; Grawe, H; Hüller, W; Kirchner, R; Mazzocchi, C; Mukha, I; Plettner, C

    2003-01-01

    The research programme pursued at the ISOL facility of GSI Darmstadt focuses on the study of decay properties of nuclei along the N congruent with Z line between the double shell closures at sup 5 sup 6 Ni and sup 1 sup 0 sup 0 Sn. In this report, the major scientific achievements obtained in the past two years are reviewed, with particular emphasis being put on the detection techniques.

  20. Nuclear power systems: Their safety. Current issue review

    International Nuclear Information System (INIS)

    Myers, L.C.

    1994-04-01

    Human beings utilize energy in many forms and from a variety of sources. A number of countries have chosen nuclear-electric generation as a component of their energy system. At the end of 1992, there were 419 power reactors operating in 29 countries, accounting for more than 15% of the world's production of electricity. In 1992, 13 countries derived at least 25% of their electricity from nuclear units, with Lithuania leading at just over 78%, followed closely by France at 72%. In the same year, Canada produced about 16% of its electricity from nuclear units. Some 53 power reactors are under construction in 14 countries outside the former USSR. Within the ex-USSR countries, six new reactors are currently under construction. No human endeavour carries the guarantee of perfect safety and the question of whether of not nuclear-electric generation represents an 'acceptable' risk to society has long been vigorously debated. Until the events of late April 1986 in the then Soviet Union, nuclear safety had indeed been an issue for discussion, for some concern, but not for alarm. The accident at the Chernobyl reactor irrevocably changed all that. This disaster brought the matter of nuclear safety into the public mind in a dramatic fashion. Subsequent opening of the ex-Soviet nuclear power program to outside scrutiny has done little to calm people's concerns about the safety of nuclear power in that part of the world. This paper discusses the issue of safety in complex energy systems and provides brief accounts of some of the most serious reactor accidents that have occurred to date, as well as more recent, less dramatic events touching on the safety issue. (author). 7 refs

  1. Safety issues at the defense production reactors

    International Nuclear Information System (INIS)

    1987-01-01

    The United States produces plutonium and tritium for use in nuclear weapons at the defense production reactors - the N Reactor in Washington and the Savannah River reactors in South Carolina. This report reaches general conclusions about the management of those reactors and highlights a number of safety and technical issues that should be resolved. The report provides an assessment of the safety management, safety review, and safety methodology employed by the Department of Energy and the private contractors who operate the reactors for the federal government. This report examines the safety objective established by the Department of Energy for the production reactors and the process the Department of its contractors use to implement the objective; focuses on a variety of uncertainties concerning the production reactors, particularly those related to potential vulnerabilities to severe accidents; and identifies ways in which the DOE approach to management of the safety of the production reactors can be improved

  2. 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)

  3. Health, safety and environmental issues in thin film manufacturing

    NARCIS (Netherlands)

    Alsema, E.A.; Baumann, A.E.; Hill, R.; Patterson, M.H.

    1997-01-01

    An investigation is made of Health, Safety and Environmental (HSE) aspects for the manufacturing, use and decommissioning of CdTe, CIS and a-Si modules. Issues regarding energy requirements, resource availability, emissions of toxic materials, occupational health and safety and module waste

  4. Draft report on compilation of generic safety issues for light water reactor nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-07-01

    A generally accepted approach to characterizing the safety concerns in nuclear power plants is to express them as safety issues which need to be resolved. When such safety issues are applicable to a generation of plants of a particular design or to a family of plants of similar design, they are termed generic safety issues. Examples of generic safety issues are those related to reactor vessel embrittlement, control rod insertion reliability or strainer clogging. The safety issues compiled in this document are based on broad international experience. This compilation is one element in the framework of IAEA activities to assist Member States in reassessing the safety of operating nuclear power plants. Refs.

  5. Draft report on compilation of generic safety issues for light water reactor nuclear power plants

    International Nuclear Information System (INIS)

    1997-07-01

    A generally accepted approach to characterizing the safety concerns in nuclear power plants is to express them as safety issues which need to be resolved. When such safety issues are applicable to a generation of plants of a particular design or to a family of plants of similar design, they are termed generic safety issues. Examples of generic safety issues are those related to reactor vessel embrittlement, control rod insertion reliability or strainer clogging. The safety issues compiled in this document are based on broad international experience. This compilation is one element in the framework of IAEA activities to assist Member States in reassessing the safety of operating nuclear power plants. Refs

  6. Relevant safety issues in designing the HTR-10 reactor

    International Nuclear Information System (INIS)

    Sun Yuliang; Xu Yuanghui

    2001-01-01

    The HTR-10 is a 10 MWth pebble bed high temperature gas cooled reactor being constructed as a research facility at the Institute of Nuclear Energy Technology. This paper discusses design issues of the HTR-10 which are related to safety. It addresses the safety criteria used in the development and assessment of the design, the safety important systems, and the safety classification of components. It also summarises the results of safety analysis, including the approach used for the radioactive source term, as well as the approach to containment design. (author)

  7. Analysis of high burnup fuel safety issues

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Chan Bock; Kim, D. H.; Bang, J. G.; Kim, Y. M.; Yang, Y. S.; Jung, Y. H.; Jeong, Y. H.; Nam, C.; Baik, J. H.; Song, K. W.; Kim, K. S

    2000-12-01

    Safety issues in steady state and transient behavior of high burnup LWR fuel above 50 - 60 MWD/kgU were analyzed. Effects of burnup extension upon fuel performance parameters was reviewed, and validity of both the fuel safety criteria and the performance analysis models which were based upon the lower burnup fuel test results was analyzed. It was found that further tests would be necessary in such areas as fuel failure and dispersion for RIA, and high temperature cladding corrosion and mechanical deformation for LOCA. Since domestic fuels have been irradiated in PWR up to burnup higher than 55 MWD/kgU-rod. avg., it can be said that Korea is in the same situation as the other countries in the high burnup fuel safety issues. Therefore, necessary research areas to be performed in Korea were derived. Considering that post-irradiation examination(PIE) for the domestic fuel of burnup higher than 30 MWD/kgU has not been done so far at all, it is primarily necessary to perform PIE for high burnup fuel, and then simulation tests for RIA and LOCA could be performed by using high burnup fuel specimens. For the areas which can not be performed in Korea, international cooperation will be helpful to obtain the test results. With those data base, safety of high burnup domestic fuels will be confirmed, current fuel safety criteria will be re-evaluated, and finally transient high burnup fuel behavior analysis technology will be developed through the fuel performance analysis code development.

  8. Analysis of high burnup fuel safety issues

    International Nuclear Information System (INIS)

    Lee, Chan Bock; Kim, D. H.; Bang, J. G.; Kim, Y. M.; Yang, Y. S.; Jung, Y. H.; Jeong, Y. H.; Nam, C.; Baik, J. H.; Song, K. W.; Kim, K. S

    2000-12-01

    Safety issues in steady state and transient behavior of high burnup LWR fuel above 50 - 60 MWD/kgU were analyzed. Effects of burnup extension upon fuel performance parameters was reviewed, and validity of both the fuel safety criteria and the performance analysis models which were based upon the lower burnup fuel test results was analyzed. It was found that further tests would be necessary in such areas as fuel failure and dispersion for RIA, and high temperature cladding corrosion and mechanical deformation for LOCA. Since domestic fuels have been irradiated in PWR up to burnup higher than 55 MWD/kgU-rod. avg., it can be said that Korea is in the same situation as the other countries in the high burnup fuel safety issues. Therefore, necessary research areas to be performed in Korea were derived. Considering that post-irradiation examination(PIE) for the domestic fuel of burnup higher than 30 MWD/kgU has not been done so far at all, it is primarily necessary to perform PIE for high burnup fuel, and then simulation tests for RIA and LOCA could be performed by using high burnup fuel specimens. For the areas which can not be performed in Korea, international cooperation will be helpful to obtain the test results. With those data base, safety of high burnup domestic fuels will be confirmed, current fuel safety criteria will be re-evaluated, and finally transient high burnup fuel behavior analysis technology will be developed through the fuel performance analysis code development

  9. Commercial truck parking and other safety issues.

    Science.gov (United States)

    2015-10-01

    Commercial truck parking is a safety issue, since trucks are involved in approximately 10% of all fatal accidents on interstates and : parkways in Kentucky. Drivers experience schedule demands and long hours on the road, yet they cannot easily determ...

  10. Status report on resolution of Waste Tank Safety Issues at the Hanford Site. Revision 1

    International Nuclear Information System (INIS)

    Dukelow, G.T.; Hanson, G.A.

    1995-05-01

    The purpose of this report is to provide and update the status of activities supporting the resolution of waste tank safety issues and system deficiencies at the Hanford Site. This report provides: (1) background information on safety issues and system deficiencies; (2) a description of the Tank Waste Remediation System and the process for managing safety issues and system deficiencies; (3) changes in safety issue description, prioritization, and schedules; and (4) a summary of the status, plans, order of magnitude, cost, and schedule for resolving safety issues and system deficiencies

  11. Impact of 3D Var GSI-ENKF hybrid data assimilation system

    Indian Academy of Sciences (India)

    1National Centre for Medium Range Weather Forecasting, A-50, Sector-62, Noida, ... with a two-way coupling with an 80 member Ensemble Kalman Filter of .... algorithm in the GSI system using single observa- .... casts of hybrid schemes at 850, 500 and 200 hPa pressure ... NCRWF merged rainfall data using rain gauge.

  12. Safety issues with bisphosphonate therapy for osteoporosis

    DEFF Research Database (Denmark)

    Suresh, Ernest; Pazianas, Michael; Abrahamsen, Bo

    2014-01-01

    Randomized controlled trials have demonstrated the efficacy of bisphosphonates (BP) in improving BMD and reducing fracture risk. Various safety issues that were not noted in clinical trials have, however, now emerged with post-marketing surveillance and increasing clinical experience. The risk...

  13. Safety issues on advanced fuel

    Energy Technology Data Exchange (ETDEWEB)

    Gross, H.; Krebs, W.D. [Siemens AG, Bereich Energieerzeugug (KWU), Erlangen (Germany). Geschaeftsgebiet Nukleare Energieerzeugung

    1998-05-01

    In the recent years a general discussion has started whether unsolved safety issues are related to advanced fuel. Advanced fuel is in this context a summary of features like high burnup, improved clad materials, low leakage loading pattern with high peaking factors etc. The design basis accidents RIA and Loca are of special interest for this discussion. From the Siemens point of view RIA is not a safety issue. There are sufficient margins between the enthalpy rise calculated by modern 3D methods and the fuel failures which occurred in RIA simulation tests when the effect of pulse width is taken into account. The evaluation of possible uncertainties for the established Loca criteria (17% equivalent corrosion, 1200 C clad temperature) for high burnup makes sense. But fuel with high burnup has significantly lower peaking factors than fuel with lower burnup. This gives sufficient margin counterbalancing possible uncertainties. In contrast to the above incomplete control rod insertion at higher burnup is potentially a real safety issue. Although Siemens fuel was not affected by the reported incidents they addressed the problem and checked that they have sufficient design margin for their fuel. (orig.) [Deutsch] In den letzten Jahren hat eine allgemeine Diskussion begonnen, ob mit fortgeschrittenen Brennelementen (BE) ungeklaerte Sicherheitsprobleme verbunden sind. Dabei ist `Fortgeschrittene Brennelemente` ein Sammelbegriff fuer hohe Abbraende, verbesserte Huellrohrmaterialien, Low-leakage-Einsatzplanungen mit hohen Heissstellenfaktoren usw. Die Auslegungsstoerfaelle RIA und Loca sind in dieser Diskussion von besonderer Bedeutung. Aus der Sicht von Siemens ist der RIA kein Sicherheitsproblem. Zwischen den mit modernen 3D-Methoden berechneten Enthalpieerhoehungen und den in RIA-Experimenten aufgetretenen Brennstabdefekten bestehen ausreichende Abstaende, wenn der Einfluss der Pulsbreite beruecksichtigt wird. Die Untersuchung eventueller Unsicherheiten bei hohen

  14. Safety culture and organizational issues during transition from operation to decommissioning of NPPs

    International Nuclear Information System (INIS)

    Slavcheva, K.; Mori, M.; D'Amico, N.; Sollima, C.

    2005-01-01

    The paper highlights the critical safety issues in a Nuclear Power Plant (NPP) to be managed during the transition period from operation to decommissioning. Pre-shutdown is an important period of a NPP lifetime due to the changes and issues to be faced by the NPP management, which include safety culture issues, organizational issues, plant safety issues and nuclear waste issues. Preservation of staff competence and moral, management and organizational capability, preservation of knowledge and corporate memory, preservation of safety culture, surveillance and permanent control to maintain adequate level of nuclear and radiation safety, development of appropriate solutions for the new incoming issues are the key challenges to be timely faced. The uncertainty regarding the future of the site, the future of the workers and the incoming re-organization originate numerous additional issues including stress for the personnel. It is necessary to take appropriate actions to reduce the uncertainty. The regulatory regime continues with the same rules as during operation. Responsibility for safety remains with the licensee and the regulatory supervision continues and oversees the safe operation and security of the NPP, the safe management and storage of spent nuclear fuel and radioactive waste. Anticipated attention from the Operator and the Regulator to key organizational and safety culture issues during the pre-shutdown phase has shown to be an effective preventive action. The Operator has to aim to preserve staff competence and motivation, preserve corporate memory, safety culture, reinforce monitoring and control on the health risk of workers and population, preserve the technical part of the organization from external disturb and distractions, ensure transparency and develop strategies to solve forthcoming issues. The Regulator has to aim to reorient its supervision, train its personnel and adapt its tools to the new situation, keep adequate presence onsite, keep dialogue

  15. Evacuation research: A reassessment

    Energy Technology Data Exchange (ETDEWEB)

    Vogt, B.M.; Sorensen, J.H.

    1992-11-01

    During the 1985 review of several plants technical specifications the US Nuclear Regulatory Commission (NRC) staff found that the protection system designs of some plants did not provide as complete a degree of online (at power) protection system surveillance testing capability as other plants undergoing staff review and evaluation at that time. This raised questions about the online testability of protection systems and the possibility that some nuclear power plant designs may not provide for complete online testing of their protection systems. Therefore, Generic Safety Issue (GSI)-120, ``Online Testability of Protection Systems`` was initiated. Project scope was limited to the Engineered Safety Features (ESFs) instrumentation and control testing. The major issue of concern relative to the resolution of GSI-120 deals with those ESF systems/components that cannot be tested during power operation, as actuating these systems/components could result in unwanted plant transient or trip conditions. These systems/components are tested during shutdown conditions. This report provides analysis and evaluation findings based on the review of selected issues necessary for the resolution of GSI-120. It also provides recommendations to close out GSI-120 and that no new requirements be placed on licensees of commercial light water nuclear power plants.

  16. Evacuation research: A reassessment

    Energy Technology Data Exchange (ETDEWEB)

    Vogt, B.M.; Sorensen, J.H.

    1992-11-01

    During the 1985 review of several plants technical specifications the US Nuclear Regulatory Commission (NRC) staff found that the protection system designs of some plants did not provide as complete a degree of online (at power) protection system surveillance testing capability as other plants undergoing staff review and evaluation at that time. This raised questions about the online testability of protection systems and the possibility that some nuclear power plant designs may not provide for complete online testing of their protection systems. Therefore, Generic Safety Issue (GSI)-120, Online Testability of Protection Systems'' was initiated. Project scope was limited to the Engineered Safety Features (ESFs) instrumentation and control testing. The major issue of concern relative to the resolution of GSI-120 deals with those ESF systems/components that cannot be tested during power operation, as actuating these systems/components could result in unwanted plant transient or trip conditions. These systems/components are tested during shutdown conditions. This report provides analysis and evaluation findings based on the review of selected issues necessary for the resolution of GSI-120. It also provides recommendations to close out GSI-120 and that no new requirements be placed on licensees of commercial light water nuclear power plants.

  17. Safety Issues Concerning the Medical Use of Cannabis and Cannabinoids

    Directory of Open Access Journals (Sweden)

    Mark A Ware

    2005-01-01

    Full Text Available Safety issues are a major barrier to the use of cannabis and cannabinoid medications for clinical purposes. Information on the safety of herbal cannabis may be derived from studies of recreational cannabis use, but cannabis exposure and effects may differ widely between medical and recreational cannabis users. Standardized, quality-controlled cannabinoid products are available in Canada, and safety profiles of approved medications are available through the Canadian formulary. In the present article, the evidence behind major safety issues related to cannabis use is summarized, with the aim of promoting informed dialogue between physicians and patients in whom cannabinoid therapy is being considered. Caution is advised in interpreting these data, because clinical experience with cannabinoid use is in the early stages. There is a need for long-term safety monitoring of patients using cannabinoids for a wide variety of conditions, to further guide therapeutic decisions and public policy.

  18. Ranking of safety issues for WWER-440 model 230 nuclear power plants

    International Nuclear Information System (INIS)

    1992-02-01

    In response to requests from Member States operating Soviet designed WWER-440/230 nuclear power plants (NPPs) for assistance through the IAEA's nuclear safety services, a major international project was established to evaluate these first generation reactors as a complement to relevant ongoing national, bilateral and multilateral activities. The objective is to assist countries operating WWER-440/230 NPPs in performing comprehensive safety reviews aimed at identifying design and operational weaknesses. The scope of the project includes a review of the conceptual design of WWER-440/230 NPPs, safety review missions to each one of the operating reactors to review design and operational aspects and studies to resolve issues of generic safety concern. This report was prepared by a group of international experts and the IAEA staff and discussed by the Project Steering Committee, December 9-13, 1991 in Vienna. An overview of the safety issues identified is presented indicating their effect on the performance of the basic safety functions. Conceptual recommendations related to design issues are given as a technical basis for the safety modifications required

  19. Climate and climate-related issues for the safety assessment SR-Can

    International Nuclear Information System (INIS)

    Naeslund, Jens-Ove

    2006-11-01

    The purpose of this report is to document current scientific knowledge of the climate-related conditions and processes relevant to the long-term safety of a KBS-3 repository to a level required for an adequate treatment in the safety assessment SR-Can. The report also includes a concise background description of the climate system. The report includes three main chapters: A description of the climate system (Chapter 2); Identification and discussion of climate-related issues (Chapter 3); and, A description of the evolution of climate-related conditions for the safety assessment (Chapter 4). Chapter 2 includes an overview of present knowledge of the Earth climate system and the climate conditions that can be expected to occur in Sweden on a 100,000 year time perspective. Based on this, climate-related issues relevant for the long-term safety of a KBS-3 repository are identified. These are documented in Chapter 3 'Climate-related issues' to a level required for an adequate treatment in the safety assessment. Finally, in Chapter 4, 'Evolution of climate-related conditions for the safety assessment' an evolution for a 120,000 year period is presented, including discussions of identified climate-related issues of importance for repository safety. The documentation is from a scientific point of view not exhaustive, since such a treatment is neither necessary for the purposes of the safety assessment nor possible within the scope of a safety assessment. As further described in the SR-Can Main Report and in the Features Events and Processes report, the content of the present report has been audited by comparison with FEP databases compiled in other assessment projects. This report follows as far as possible the template for documentation of processes regarded as internal to the repository system. However, the term processes is not used in this report, instead the term issue has been used. Each issue includes a set of processes together resulting in the behaviour of a

  20. Climate and climate-related issues for the safety assessment SR-Can

    Energy Technology Data Exchange (ETDEWEB)

    Naeslund, Jens-Ove (comp.)

    2006-11-15

    The purpose of this report is to document current scientific knowledge of the climate-related conditions and processes relevant to the long-term safety of a KBS-3 repository to a level required for an adequate treatment in the safety assessment SR-Can. The report also includes a concise background description of the climate system. The report includes three main chapters: A description of the climate system (Chapter 2); Identification and discussion of climate-related issues (Chapter 3); and, A description of the evolution of climate-related conditions for the safety assessment (Chapter 4). Chapter 2 includes an overview of present knowledge of the Earth climate system and the climate conditions that can be expected to occur in Sweden on a 100,000 year time perspective. Based on this, climate-related issues relevant for the long-term safety of a KBS-3 repository are identified. These are documented in Chapter 3 'Climate-related issues' to a level required for an adequate treatment in the safety assessment. Finally, in Chapter 4, 'Evolution of climate-related conditions for the safety assessment' an evolution for a 120,000 year period is presented, including discussions of identified climate-related issues of importance for repository safety. The documentation is from a scientific point of view not exhaustive, since such a treatment is neither necessary for the purposes of the safety assessment nor possible within the scope of a safety assessment. As further described in the SR-Can Main Report and in the Features Events and Processes report, the content of the present report has been audited by comparison with FEP databases compiled in other assessment projects. This report follows as far as possible the template for documentation of processes regarded as internal to the repository system. However, the term processes is not used in this report, instead the term issue has been used. Each issue includes a set of processes together resulting in the

  1. The Norwegian Plan of Action for nuclear safety issues

    International Nuclear Information System (INIS)

    1997-07-01

    The Plan of Action underlies Norwegian activities in the field of international co-operation to enhance nuclear safety and prevent radioactive contamination from activities in Eastern Europe and the former Soviet Union. Geographically the highest priority has been given to support for safety measures in north-west Russia. This information brochure outlines the main content of the Plan of Action for nuclear safety issues and lists a number of associated measures and projects

  2. The Norwegian Plan of Action for nuclear safety issues

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-07-01

    The Plan of Action underlies Norwegian activities in the field of international co-operation to enhance nuclear safety and prevent radioactive contamination from activities in Eastern Europe and the former Soviet Union. Geographically the highest priority has been given to support for safety measures in north-west Russia. This information brochure outlines the main content of the Plan of Action for nuclear safety issues and lists a number of associated measures and projects.

  3. Unresolved safety issues summary. Volume 3, Number 3. Aqua book

    International Nuclear Information System (INIS)

    1981-01-01

    The 'Unresolved Safety Issues' summary is designed to provide the management of the Nuclear Regulatory Commission with a quarterly overview of the progress and plans for completion of generic tasks addressing Unresolved Safety Issues reported to Congress pursuant to section 210 of The Energy Reorganization Act of 1974 as amended. This summary utilizes data collected from the Office of Nuclear Reactor Regulation, Office of Nuclear Regulatory Research, and the National Laboratories and is prepared by the office of Management and Program Analysis. The definition of what constitutes completion of an unresolved safety issue (USI) has recently been expanded to include the implementation of the technical resolution. This is in acknowledgement of the fact that real safety benefits occur only after the implementation has taken place. The schedules in this book include a milestone at the end of each action plan which represents the initiation of the implementation process both with respect to incorporation of the technical resolution in the NRC official guidance or requirements and also the application of changes to individual operating plants. The schedule for implementation will not normally be included in the task action plan(s) for the resolution of a USI since the nature and extent of the activities necessary to accomplish the implementation cannot normally be reasonably determined prior to the determination of a technical resolution. The progress and status for implementation of unresolved safety issues for which a technical resolution has been completed are reported specifically in a separate table provided in this summary

  4. Key practical issues in strengthening safety culture. INSAG-15. A report by the International Safety Advisory Group

    International Nuclear Information System (INIS)

    2002-01-01

    This report describes the essential practical issues to be considered by organizations aiming to strengthen safety culture. It is intended for senior executives, managers and first line supervisors in operating organizations. Although safety culture cannot be directly regulated, it is important that members of regulatory bodies understand how their actions affect the development of attempts to strengthen safety culture and are sympathetic to the need to improve the less formal human related aspects of safety. The report is therefore of relevance to regulators, although not intended primarily for them. The International Nuclear Safety Advisory Group (INSAG) introduced the concept of safety culture in its INSAG-4 report in 1991. Since then, many papers have been written on safety culture, as it relates to organizations and individuals, its improvement and its underpinning prerequisites. Variations in national cultures mean that what constitutes a good approach to enhancing safety culture in one country may not be the best approach in another. However, INSAG seeks to provide pragmatic and practical advice of wide applicability in the principles and issues presented in this report. Nuclear and radiological safety are the prime concerns of this report, but the topics discussed are so general that successful application of the principles should lead to improvements in other important areas, such as industrial safety, environmental performance and, in some respects, wider business performance. This is because many of the attitudes and practices necessary to achieve good performance in nuclear safety, including visible commitment by management, openness, care and thoroughness in completing tasks, good communication and clarity in recognizing major issues and dealing with them as a priority, have wide applicability

  5. Unresolved safety issues summary. Aqua Book. Volume 6, No. 3

    International Nuclear Information System (INIS)

    Butts, J.

    1984-01-01

    The unresolved safety issues summary is designed to provide the management of the Nuclear Regulatory Commission with a quarterly overview of the progress and plans for completion of generic tasks addressing unresolved safety issues reported to Congress pursuant to Section 210 of the Energy Reorganization Act of 1974 as amended. This summary utilizes data collected from the Office of Nuclear Reactor Regulation, Office of Nuclear Regulatory Research, and the national laboratories and is prepared by the Office of Nuclear Reactor Regulation

  6. Guidelines for nuclear power plant safety issue prioritization information development. Supplement 5

    International Nuclear Information System (INIS)

    Daling, P.M.; Lavender, J.C.

    1996-07-01

    This is the sixth in a series of reports to document the development and use of a methodology developed by the Pacific Northwest Laboratory (PNL) to calculate, for prioritization purposes, the risk, dose, and cost impacts of implementing potential resolutions to reactor safety issues (see NUREG/CR-2800, Andrews, et al., 1983). This report contains the results of issue-specific analyses for 34 generic issues. Each issue was considered within the constraints of available information at the time the issues were examined and approximately 2 staff-weeks of labor. The results are referenced as one consideration in NUREG-0933, A Prioritization of Generic Safety Issues (Emrit, et al., 1983)

  7. Guidelines for nuclear power plant safety issue prioritization information development. Supplement 5

    Energy Technology Data Exchange (ETDEWEB)

    Daling, P.M.; Lavender, J.C. [Pacific Northwest National Lab., Richland, WA (United States)

    1996-07-01

    This is the sixth in a series of reports to document the development and use of a methodology developed by the Pacific Northwest Laboratory (PNL) to calculate, for prioritization purposes, the risk, dose, and cost impacts of implementing potential resolutions to reactor safety issues (see NUREG/CR-2800, Andrews, et al., 1983). This report contains the results of issue-specific analyses for 34 generic issues. Each issue was considered within the constraints of available information at the time the issues were examined and approximately 2 staff-weeks of labor. The results are referenced as one consideration in NUREG-0933, A Prioritization of Generic Safety Issues (Emrit, et al., 1983).

  8. Safety Culture and Issue in the Malaysian Manufacturing Sector

    OpenAIRE

    Ali Danish; Yusof Yusri; Adam Anbia

    2017-01-01

    . This paper highlights the Safety culture and issue in the Malaysian Manufacturing Sector and emphasis the high occupational accidents due to lack of safety culture and non-compliance of the requirements of Occupational Safety and Health Act 1994. The aim of this study is to review the occupational accidents occurrence in the Malaysia workplace since 2012-2016. Malaysia aimed to reduce the occupational accidents, the results show by DOSH increase that Occupational Noise Induced Hearing Loss ...

  9. Key issues of the common French-German safety approach for future PWRs

    International Nuclear Information System (INIS)

    Frisch, W.; Rohde, J.; Gros, G.; Queniart, D.

    1996-01-01

    The general common safety approach issued in May 1993 contains safety objectives, general principles and already some technical principles. Based on general safety approach, detailed recommendations have been developed in 1994 on key issues such as: system design and use of PSA; integrity of the primary circuit; external hazards; severe accidents and containment design; radiological consequences of reference accidents and low pressure core melt accidents. A selection of the detailed recommendations is presented in the full paper. (author)

  10. Monte Carlo simulations for the shielding of the future high-intensity accelerator facility FAIR at GSI.

    Science.gov (United States)

    Radon, T; Gutermuth, F; Fehrenbacher, G

    2005-01-01

    The Gesellschaft für Schwerionenforschung (GSI) is planning a significant expansion of its accelerator facilities. Compared to the present GSI facility, a factor of 100 in primary beam intensities and up to a factor of 10,000 in secondary radioactive beam intensities are key technical goals of the proposal. The second branch of the so-called Facility for Antiproton and Ion Research (FAIR) is the production of antiprotons and their storage in rings and traps. The facility will provide beam energies a factor of approximately 15 higher than presently available at the GSI for all ions, from protons to uranium. The shielding design of the synchrotron SIS 100/300 is shown exemplarily by using Monte Carlo calculations with the FLUKA code. The experimental area serving the investigation of compressed baryonic matter is analysed in the same way. In addition, a dose comparison is made for an experimental area operated with medium energy heavy-ion beams. Here, Monte Carlo calculations are performed by using either heavy-ion primary particles or proton beams with intensities scaled by the mass number of the corresponding heavy-ion beam.

  11. Monte Carlo simulations for the shielding of the future high-intensity accelerator facility fair at GSI

    International Nuclear Information System (INIS)

    Radon, T.; Gutermuth, F.; Fehrenbacher, G.

    2005-01-01

    The Gesellschaft fuer Schwerionenforschung (GSI) is planning a significant expansion of its accelerator facilities. Compared to the present GSI facility, a factor of 100 in primary beam intensities and up to a factor of 10,000 in secondary radioactive beam intensities are key technical goals of the proposal. The second branch of the so-called Facility for Antiproton and Ion Research (FAIR) is the production of antiprotons and their storage in rings and traps. The facility will provide beam energies a factor of ∼15 higher than presently available at the GSI for all ions, from protons to uranium. The shielding design of the synchrotron SIS 100/300 is shown exemplarily by using Monte Carlo calculations with the FLUKA code. The experimental area serving the investigation of compressed baryonic matter is analysed in the same way. In addition, a dose comparison is made for an experimental area operated with medium energy heavy-ion beams. Here, Monte Carlo calculations are performed by using either heavy-ion primary particles or proton beams with intensities scaled by the mass number of the corresponding heavy-ion beam. (authors)

  12. Environmental safety issues for semiconductors (research on scarce materials recycling)

    International Nuclear Information System (INIS)

    Izumi, Shigekazu

    2004-01-01

    In the 21st century, in the fabrication of various industrial parts, particularly, current and future electronics devices in the semiconductor industry, environmental safety issues should be carefully considered. We coined a new term, environmental safety issues for semiconductors, considering our semiconductor research and technology which include environmental and ecological factors. The main object of this analysis is to address the present situation of environmental safety problems in the semiconductor industry; some of which are: (1) the generation and use of hazardous toxic gases in the crystal growth procedure such as molecular beam epitaxy (MBE) and metalorganic chemical vapor deposition (MOCVD), (2) the generation of industrial toxic wastes in the semiconductor process and (3) scarce materials recycling from wastes in the MBE and MOCVD growth procedure

  13. Application of a methodology to determine priorities for nuclear power plant safety issues

    International Nuclear Information System (INIS)

    Daling, P.M.

    1988-01-01

    The Nuclear Regulatory Commission (NRC) Office of Nuclear Regulatory Research (RES) is sponsoring a research program to determine priorities of nuclear power plant safety issues. A methodology has been developed at the Pacific Northwest Laboratory (PNL) to provide technical assistance in the development of risk and cost estimates for implementing resolutions to the safety issues. The information development methods are intended to provide the NRC with a consistent level of information for use in ranking the issues. The NRC uses this information, along with judgmental factors, to rank the issues for further consideration by the NRC staff. The primary purpose of the priority rankings are to assist in the allocation of resources to issues that have high potential for reducing public risk as well as to remove issues from further consideration that have little safety significance

  14. Analysis of safety issues in household meat consumption in Odeda ...

    African Journals Online (AJOL)

    The study analyzed the safety problems with household meat consumption in Odeda Local Government Area, Ogun state, Nigeria. The objectives were to describe the socioeconomic characteristics of the respondents; assess the level of awareness of safety issues in households' meat consumption; and evaluate the ...

  15. Construction and characterization of a laser-driven proton beamline at GSI

    Energy Technology Data Exchange (ETDEWEB)

    Busold, Simon

    2014-05-15

    The thesis includes the first experiments with the new 100 TW laser beamline of the PHELIX laser facility at GSI Darmstadt to drive a TNSA (Target Normal Sheath Acceleration) proton source at GSI's Z6 experimental area. At consecutive stages a pulsed solenoid has been applied for beam transport and energy selection via chromatic focusing, as well as a radiofrequency cavity for energy compression of the bunch. This novel laser-driven proton beamline, representing a central experiment of the German national LIGHT collaboration (Laser Ion Generation, Handling and Transport), has been used to create collimated, intense proton bunches at 10 MeV with 2.7% energy spread from the laser-driven source. Also, the feasibility of phase focusing experiments with this setup has been shown and simulations predict peak currents of 10{sup 10} protons/ns at this energy level. Furthermore, first quantitative measurements on the spectral properties of the also present co-moving electrons from such a proton source could be performed and their influence on the protons within the solenoid observed. Finally, permanent magnetic quadrupoles as an alternative first ion collimation system have been investigated experimentally.

  16. Review on the NEI Methodology of Debris Transport Analysis in Sump Blockage Issue for APR1400

    International Nuclear Information System (INIS)

    Kim, Jong Uk; Lee, Jeong Ik; Hong, Soon Joon; Lee, Byung Chul; Bang, Young Seok

    2007-01-01

    Since USNRC (United State Nuclear Regulatory Committee) initially addressed post-accident sump performance under Unresolved Safety Issue USI A-43, sump blockage issue has gone through GSI-191, Regulation Guide 1.82, Rev. 3 (RG. 1.82 Rev.3), and generic Letter 2004-02 for PWRs (Pressurized Water Reactors). As a response of these USNRC's activities, NEI 04-07 was issued in order to evaluate the post-accident performance of a plant's recirculation sump. The baseline methodology of NEI 04-07 is composed of break selection, debris generation, latent debris, debris transport, and head loss. In analytical refinement of NEI 04-07, computational fluid dynamic (CFD) is suggested for the evaluation of debris transport in emergency core cooling (ECC) recirculation mode as guided by RG. 1.82 Rev.3. In Korea nuclear industry also keeps step with international activities of this safety issue, with Kori 1 plant as a pioneering edge. Korean nuclear industry has been also pursuing development of an advanced PWR of APR1400, which incorporates several improved safety features. One of the key features, considering sump blockage issue, is the adoption of IRWST (In-containment Refueling Water Storage Tank). This device, as the acronym implies, changes the emergency core cooling water injection pattern. This fact makes us to review the applicability of NEI 04-07's methodology. In this paper we discuss the applicability of NEI 04- 07's methodology, and more over, new methodology is proposed. And finally the preliminary debris transport is analyzed

  17. Safety issues of nuclear production of hydrogen

    International Nuclear Information System (INIS)

    Piera, Mireia; Martinez-Val, Jose M.; Jose Montes, Ma

    2006-01-01

    Hydrogen is not an uncommon issue in Nuclear Safety analysis, particularly in relation to severe accidents. On the other hand, hydrogen is a household name in the chemical industry, particularly in oil refineries, and is also a well known chemical element currently produced by steam reforming of natural gas, and other methods (such as coal gasification). In the not-too-distant future, hydrogen will have to be produced (by chemical reduction of water) using renewable and nuclear energy sources. In particular, nuclear fission seems to offer the cheapest way to provide the primary energy in the medium-term. Safety principles are fundamental guidelines in the design, construction and operation both of hydrogen facilities and nuclear power plants. When these two technologies are integrated, a complete safety analysis must consider not only the safety practices of each industry, but any interaction that could be established between them. In particular, any accident involving a sudden energy release from one of the facilities can affect the other. Release of dangerous substances (chemicals, radiotoxic effluents) can also pose safety problems. Although nuclear-produced hydrogen facilities will need specific approaches and detailed analysis on their safety features, a preliminary approach is presented in this paper. No significant roadblocks are identified that could hamper the deployment of this new industry, but some of the hydrogen production methods will involve very demanding safety standards

  18. INDRA-GSI: Collective flow from Fermi to relativistic energies

    Energy Technology Data Exchange (ETDEWEB)

    Lukasik, J.; Trautmann, W.; Begemann-Blaich, M.L.; Bittiger, R.; Gourio, D.; Le Fevre, A.; Lynen, U.; Mueller, W.F.J.; Orth, H.; Sfienti, C.; Schwarz, C.; Turzo, K. [Gesellschaft fuer Schwerionenforschung mbH, Darmstadt (Germany); Auger, G.; Bouriquet, B.; Chbihi, A.; Frankland, J.D.; Hudan, S.; Lopez, O. [GANIL, CEA et IN2P3-CNRS, 14 - Caen (France); Borderie, B.; Galichet, E.; Lavaud, F.; Plagnol, E. [Paris-11 Univ., Institut de Physique Nucleaire, IN2P3-CNRS, 91 - Orsay (France); Bellaize, N.; Bocage, F.; Bougault, R.; Durand, D.; Hurst, B.; Steckmeyer, J.C.; Tamain, B.; Vient, E. [Caen Univ., LPC (IN2P3-CNRS/ENSI), 14 - Caen (France); Charvet, J.L.; Dayras, R.; Legrain, R.; Nalpas, L.; Volant, C. [CEA Saclay, Dept. d' Astrophysique, de Physique des Particules, de Physique Nucleaire et de l' Instrumentation Associee (DAPNIA/SPhN), 91- Gif sur Yvette (France); Guinet, D.; Lautesse, P. [Institut de Physique Nucleaire, IN2P3-CNRS et Universite, 69 - Villeurbanne (France); Rosato, E.; Vigilante, M. [INFN, Univ. Federico II, Dipartimento di Scienze Fisiche e Sezione, Napoli (Italy); Saija, A. [Universita and INFN I, Dipartimento di Fisica dell' , Catania (Italy); Trzcinski, A.; Zwieglinski, B. [A. Soltan Institute for Nuclear Studies, Warsaw (Poland); Lukasik, J. [H. Niewodniczanski Institute of Nuclear Physics, Krakow (Poland); Galichet, E. [Conservatoire National des Arts et Metiers, 75 - Paris (France)

    2003-07-01

    Directed flow for the {sup 197}Au + {sup 197}Au reactions at incident energies between 40 and 150 A*MeV has been measured using the 4{pi} multi-detector INDRA at the GSI facility. In particular, the bombarding energy at which the elliptic flow switches from in-plane to out-of-plane enhancement has been determined to be around 100 A*MeV in good agreement with the result obtained by the FOPI Collaboration. The new data allows also to extend the experimental excitation function of v{sub 2} to lower energies. (authors)

  19. INDRA-GSI: Collective flow from Fermi to relativistic energies

    International Nuclear Information System (INIS)

    Lukasik, J.; Trautmann, W.; Begemann-Blaich, M.L.; Bittiger, R.; Gourio, D.; Le Fevre, A.; Lynen, U.; Mueller, W.F.J.; Orth, H.; Sfienti, C.; Schwarz, C.; Turzo, K.; Auger, G.; Bouriquet, B.; Chbihi, A.; Frankland, J.D.; Hudan, S.; Lopez, O.; Borderie, B.; Galichet, E.; Lavaud, F.; Plagnol, E.; Bellaize, N.; Bocage, F.; Bougault, R.; Durand, D.; Hurst, B.; Steckmeyer, J.C.; Tamain, B.; Vient, E.; Charvet, J.L.; Dayras, R.; Legrain, R.; Nalpas, L.; Volant, C.; Guinet, D.; Lautesse, P.; Rosato, E.; Vigilante, M.; Saija, A.; Trzcinski, A.; Zwieglinski, B.; Lukasik, J.; Galichet, E.

    2003-01-01

    Directed flow for the 197 Au + 197 Au reactions at incident energies between 40 and 150 A*MeV has been measured using the 4π multi-detector INDRA at the GSI facility. In particular, the bombarding energy at which the elliptic flow switches from in-plane to out-of-plane enhancement has been determined to be around 100 A*MeV in good agreement with the result obtained by the FOPI Collaboration. The new data allows also to extend the experimental excitation function of v 2 to lower energies. (authors)

  20. Constraining astrophysical reaction rates: using the storage rings at FAIR/GSI

    Science.gov (United States)

    Langer, Christoph; Glorius, Jan; Slavkovská, Zuzana; Litvinov, Sergey; Litvinov, Yuri A.; Reifarth, René

    2018-01-01

    Ion optical calculations for a storage ring at the present GSI facility for direct proton-induced reactions relevant for different astrophysical processes are presented. As an example case, the 59Cu(p,γ) and 59Cu(p,α) reactions are shown. The branching of these two reactions is important in X-ray burst scenarios, since it determines the breakout out of the major 56Ni waiting point.

  1. Safety issues at the defense production reactors

    International Nuclear Information System (INIS)

    1987-01-01

    The United States produces plutonium and tritium for use in nuclear weapons at the defense production reactors endash the N Reactor in Washington and the Savannah River reactors in South Carolina. This report reaches general conclusions about the management of those reactors and highlights a number of safety and technical issues that should be resolved. The report provides an assessment of the safety management, safety review, and safety methodology employed by the Department of Energy and the private contractors who operate the reactors for the federal government. The report is necessarily based on a limited review of the defense production reactors. It does not address whether any of the reactors are ''safe,'' because such an analysis would involve a determination of acceptable risk endash a matter of obvious importance, but one that was beyond the purview of the committee. It also does not address whether the safety of the production reactors is comparable to that of commercial nuclear power stations, because even this narrower question extended beyond the charge to the committee and would have involved detailed analyses that the committee could not undertake

  2. Performance of upstream interaction region detectors for the FIRST experiment at GSI

    CERN Document Server

    Abou-Haidar, Z; Alvarez, M A G; Anelli, M; Aumann, T; Battistoni, G; Bocci, A; Bohlen, T T; Boudard, A; Brunetti, A; Carpinelli, M; Cirrone, G A P; Cortes-Giraldo, M A; Cuttone, G; De Napoli, M; Durante, M; Fernandez-Garcia, J P; Finck, C; Gallardo, M I; Golosio, B; Iarocci, E; Iazzi, F; Ickert, G; Introzzi, R; Juliani, D; Krimmer, J; Kurz, N; Labalme, M; Leifels, Y; Le Fevre, A; Leray, S; Marchetto, F; Monaco, V; Morone, M C; Oliva, P; Paoloni, A; Patera, V; Piersanti, L; Pleskac, R; Quesada, J M; Randazzo, N; Romano, F; Rossi, D; Rosso, V; Rousseau, M; Sacchi, R; Sala, P; Sarti, A; Schuy, C; Sciubba, A; Sfienti, C; Simon, H; Sipala, V; Spiriti, E; Stuttge, L; Tropea, S; Younis, H

    2012-01-01

    The FIRST (Fragmentation of Ions Relevant for Space and Therapy) experiment at GSI has been designed to study carbon fragmentation, measuring (12)C double differential cross sections (- (2)I /- - E) for different beam energies between 100 and 1000 MeV/u. The experimental setup integrates newly designed detectors in the, so called, Interaction Region around the graphite target. The Interaction Region upstream detectors are a 250 mum thick scintillator and a drift chamber optimized for a precise measurement of the ions interaction time and position on the target. In this article we review the design of the upstream detectors along with the preliminary results of the data taking performed on August 2011 with 400 MeV/u fully stripped carbon ion beam at GSI. Detectors performances will be reviewed and compared to those obtained during preliminary tests, performed with 500 MeV electrons (at the BTF facility in the INFN Frascati Laboratories) and 80 MeV/u protons and carbon ions (at the INFN LNS Laboratories in Cata...

  3. Contrast media. Safety issues and ESUR guidelines. 2. rev. ed.

    Energy Technology Data Exchange (ETDEWEB)

    Thomsen, Henrik S. [Copenhagen University Hospital, Herlev (Denmark). Dept. of Diagnostic Radiology; Copenhagen Univ., Herlev (Denmark). Dept. of Diagnostic Sciences; Webb, Judith A.W. (eds.) [St. Bartholomew' s Hospital London Univ. (United Kingdom). Dept. of Radiology

    2009-07-01

    In 1994 the European Society of Urogenital Radiology (ESUR) set up a committee to consider the safety of contrast media used for diagnostic imaging. Subsequently the committee questioned members, reviewed the literature, proposed guidelines and discussed these proposals with participants at the annual symposia of the society. The end result of this work was the successful first edition of this book, published in 2006. This second edition not only updates the previous edition, but also contains some completely new chapters, for example on gadolinium-based contrast agents, meta-analyses in contrast media research and various regulatory issues. Comprehensive consideration is given to the many different safety issues relating to iodinated, MR, ultrasound and barium contrast media. The text includes chapters on both acute and delayed non-renal adverse reactions and on renal adverse reactions. All those questions frequently raised in radiological practice are addressed, and the well-known ESUR guidelines on contrast media are included. This book, presented in a handy, easy to use format, provides an invaluable, unique and unparalleled source of information on the safety issues relating to contrast media. (orig.)

  4. Contribution of safety issues to public perceptions of energy systems

    International Nuclear Information System (INIS)

    Otway, H.J.; Thomas, K.

    1978-01-01

    Public opposition is an important consideration for those responsible for energy planning; however, the formulation of socially viable policies requires an understanding of the reasons for this opposition. An attitude model was applied to identify the underlying determinants of public perceptions of five energy systems: nuclear, coal, oil, solar and hydro. Empirical results (heterogeneous sample of the general public, N = 224) are reported in which these energy systems were found to be perceived in terms of four basic dimensions: psychological aspects; economic benefits; socio-political implications; environmental and physical safety issues. For the total sample, safety issues made an appreciable contribution to attitudes toward all of the systems except nuclear energy, where it was not significant. A differential analysis of two sub-samples, those respondents PRO and CON nuclear energy, showed that benefits and safety issues were important determinants of PRO attitudes while CON attitudes were primarily due to psychological aspects and concerns about personal and political power. The role of technical information in the formation of public attitudes toward technological policies is discussed

  5. Contrast media. Safety issues and ESUR guidelines. 2. rev. ed.

    International Nuclear Information System (INIS)

    Thomsen, Henrik S.; Copenhagen Univ., Herlev; Webb, Judith A.W.

    2009-01-01

    In 1994 the European Society of Urogenital Radiology (ESUR) set up a committee to consider the safety of contrast media used for diagnostic imaging. Subsequently the committee questioned members, reviewed the literature, proposed guidelines and discussed these proposals with participants at the annual symposia of the society. The end result of this work was the successful first edition of this book, published in 2006. This second edition not only updates the previous edition, but also contains some completely new chapters, for example on gadolinium-based contrast agents, meta-analyses in contrast media research and various regulatory issues. Comprehensive consideration is given to the many different safety issues relating to iodinated, MR, ultrasound and barium contrast media. The text includes chapters on both acute and delayed non-renal adverse reactions and on renal adverse reactions. All those questions frequently raised in radiological practice are addressed, and the well-known ESUR guidelines on contrast media are included. This book, presented in a handy, easy to use format, provides an invaluable, unique and unparalleled source of information on the safety issues relating to contrast media. (orig.)

  6. Workshop on Regulatory Review and Safety Assessment Issues in Repository Licensing

    International Nuclear Information System (INIS)

    Wilmot, Roger D.

    2011-02-01

    The workshop described here was organised to address more general issues regarding regulatory review of SKB's safety assessment and overall review strategy. The objectives of the workshop were: - to learn from other programmes' experiences on planning and review of a license application for a nuclear waste repository, - to offer newly employed SSM staff an opportunity to learn more about selected safety assessment issues, and - to identify and document recommendations and ideas for SSM's further planning of the licensing review

  7. The contribution of safety issues to public perceptions of energy systems

    International Nuclear Information System (INIS)

    Otway, H.J.; Thomas, Kerry

    1978-01-01

    Public opposition is an important consideration for those responsible for energy planning. An attitude model was applied to identify the underlying determinants of public perceptions of five energy systems: nuclear, coal, oil, solar and hydro. Empirical results are reported in which these energy systems were found to be perceived in terms of four basic dimensions: psychological aspects; economics benefits; socio-political implications; environmental and physical safety issues. For the total sample, safety issues made an appreciable contribution to attitudes toward all of the systems except nuclear energy, where it was not significant. A differential analysis of two sub-samples, those respondents PRO and CON nuclear energy, showed that benefits and safety issues were important determinants of PRO attitudes while CON attitudes were primarily due to psychological aspects and concerns about personal and political power. The role of technical information in the formation of public attitudes toward technological policies is discussed [fr

  8. ISSUES OF FETUS DRUG SAFETY

    Directory of Open Access Journals (Sweden)

    A.V. Ostrovskaya

    2010-01-01

    Full Text Available The article is focused on the issue of fetus drug safety. Development of a child’s health depends both on hereditary information and environment factors. The reason for deviation from the process of normal prenatal development could be any xenobiotics, physical factors and some medications having a pathogenic effect during pregnancy on the embryo and fetus. Due to that, the physician’s preventive work based on the knowledge of embryogenesis processes and critical development periods. Key words: teratogenic action, medications, prenatal development, congenital malformation, newborns, children.(Pediatric Pharmacology. – 2010; 7(1:25-28

  9. Prospects of open charm production at GSI-FAIR and J-PARC

    International Nuclear Information System (INIS)

    Riedl, J.; Schaefer, A.; Stratmann, M.

    2007-01-01

    We present a detailed phenomenological study of the prospects of open charm physics at the future pp and pp facilities GSI-FAIR and J-PARC, respectively. In particular, we concentrate on the differential cross sections and the charge and longitudinal double-spin asymmetries at next-to-leading order accuracy. Theoretical uncertainties for the proposed observables are estimated by varying the charm quark mass and the renormalization and factorization scales. (orig.)

  10. Experiments with beams of exotic nuclei at GSI and FAIR

    International Nuclear Information System (INIS)

    Emling, Hans

    2006-01-01

    The facility for antiproton and ion research FAIR will provide the international science community with a technically novel and in many respects unique accelerator system for a multi-faceted physics program. Rare-isotope beams of much improved quality together with advanced experimental concepts promise detailed experimental investigations of nuclei far away from stability. A brief description of the rare-isotope beam facility at FAIR is presented, which allows to extend substantially the current successful experimental program with exotic nuclei at GSI. (author)

  11. Non-technical issues in safety assessments for nuclear disposal facilities

    International Nuclear Information System (INIS)

    Kallenbach-Herbert, Beate; Brohmann, Bettina

    2010-09-01

    The paper highlights that a comprehensive approach to safety affords the consideration of technology, organisation, personnel and social environment. In several safety relevant contexts of nuclear waste disposal these fields are closely interrelated. The approach for the consideration of socio-scientific aspects which is sketched in this paper supports the systematic treatment of safety relevant non-technical issues in the safety case or in safety assessments for a disposal project. Furthermore it may foster the dialogue among specialists from the technical, the natural- and the socio-scientific field on questions of disposal safety. In this way it may contribute to a better understanding among the affected scientific disciplines in nuclear waste disposal.

  12. Ethical and Safety Issues of Stem Cell-Based Therapy.

    Science.gov (United States)

    Volarevic, Vladislav; Markovic, Bojana Simovic; Gazdic, Marina; Volarevic, Ana; Jovicic, Nemanja; Arsenijevic, Nebojsa; Armstrong, Lyle; Djonov, Valentin; Lako, Majlinda; Stojkovic, Miodrag

    2018-01-01

    Results obtained from completed and on-going clinical studies indicate huge therapeutic potential of stem cell-based therapy in the treatment of degenerative, autoimmune and genetic disorders. However, clinical application of stem cells raises numerous ethical and safety concerns. In this review, we provide an overview of the most important ethical issues in stem cell therapy, as a contribution to the controversial debate about their clinical usage in regenerative and transplantation medicine. We describe ethical challenges regarding human embryonic stem cell (hESC) research, emphasizing that ethical dilemma involving the destruction of a human embryo is a major factor that may have limited the development of hESC-based clinical therapies. With previous derivation of induced pluripotent stem cells (iPSCs) this problem has been overcome, however current perspectives regarding clinical translation of iPSCs still remain. Unlimited differentiation potential of iPSCs which can be used in human reproductive cloning, as a risk for generation of genetically engineered human embryos and human-animal chimeras, is major ethical issue, while undesired differentiation and malignant transformation are major safety issues. Although clinical application of mesenchymal stem cells (MSCs) has shown beneficial effects in the therapy of autoimmune and chronic inflammatory diseases, the ability to promote tumor growth and metastasis and overestimated therapeutic potential of MSCs still provide concerns for the field of regenerative medicine. This review offers stem cell scientists, clinicians and patient's useful information and could be used as a starting point for more in-depth analysis of ethical and safety issues related to clinical application of stem cells.

  13. Issue on NPP-I and C important to safety-Data Communication

    International Nuclear Information System (INIS)

    Koo, I. S.; Hong, S. B.; Cho, J. W.; Choi, Y. S.; Lee, J. C.

    2010-01-01

    1. Issue on CDV and FDIS of IEC61500 - Nuclear Power Plants - Instrumentation and control important to safety -Data communication - Activities on IEC TC45, SC45A/WGA3. 2. As issue the requirements for safety data communication which is essential part of digital I and C systems, the fundamental technology for IT based nuclear I and C is established. 3. Approval and circulation of IED61500 CDV and FDIS - Issue of the international standard, IEC 61500. 4. Issue one IEC61500, three interim documents, three presentations and five technical support to industry, and participation in IEC TC45 and SC45A plenary meeting and intermediate meeting on SC45A/WGA3. 5. Based on IEC61500, an new project on wireless technologyes application to NPP will be proceeded

  14. CARE-HHH-APD Workshop on Finalizing the Roadmap for the Upgrade of the CERN and GSI Accelerator Complex

    CERN Document Server

    Zimmermann, Frank; BEAM'07; BEAM 2007; Finalizing the Roadmap for the Upgrade of the LHC and GSI Accelerator Complex

    2008-01-01

    This report contains the Proceedings of the CARE-HHH-APD Event BEAM’07, “Finalizing the Roadmap for the Upgrade of the CERN & GSI Accelerator Complex,” which was held at CERN in Geneva, Switzerland, from 1 to 5 October 2007. BEAM’07 was primarily devoted to beam dynamics limitations for the two, or three, alternative baseline scenarios of the LHC luminosity upgrade and to critical design choices for the upgrade of the LHC injector complex at CERN and for the FAIR complex at GSI. It comprised five parts: (1) a Mini-Workshop on LHC+ Beam Performance, (2) a CERN-GSI Meeting on Collective Effects, (3) the Francesco Ruggiero Memorial Symposium, (4) a Mini-Workshop on the LHC Injectors Upgrade, and (5) the BEAM’07 Summaries. Topics addressed in the first mini-workshop of BEAM’07 ranged from the luminosity performance reach of the upgraded LHC in different scenarios, over the generation and stability of the future LHC beams, the turnaround time, beam–beam effects, luminosity levelling methods, and ...

  15. Safety issues and updates under MR environments

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Soo Jung; Kim, Kyung Ah, E-mail: bellenina@daum.net

    2017-04-15

    Highlights: • Unexpected biological effects can occur within stronger magnetic fields. • MR safety for MR conditional items is not guaranteed beyond the tested conditions. • Updated knowledge about MR-related safety is important for a safe MR environment. - Abstract: Magnetic resonance (MR) imaging is a useful imaging tool with superior soft tissue contrast for diagnostic evaluation. The MR environments poses unique risks to patients and employees differently from ionizing radiation exposure originated from computed tomography and plain x-ray films. The technology associated with MR system has evolved continuously since its introduction in the late 1970s. MR systems have advanced with static magnetic fields, faster and stronger gradient magnetic fields and more powerful radiofrequency transmission coils. Higher field strengths of MR offers greater signal to noise capability and better spatial resolution, resulting in better visualization of anatomic detail, with a reduction in scan time. With the rapid evolution of technology associated with MR, we encounter new MR-related circumstances and unexpected dangerous conditions. A comprehensive update of our knowledge about MR safety is necessary to prevent MR-related accidents and to ensure safety for patients and staff associated with MR. This review presents an overview about MR-related safety issues and updates.

  16. Resolution of GSI B-56 - Emergency diesel generator reliability

    International Nuclear Information System (INIS)

    Serkiz, A.W.

    1989-01-01

    The need for an emergency diesel generator (EDG) reliability program has been established by 10 CFR Part 50, Section 50.63, Loss of All Alternating Current Power, which requires that licensees assess their station blackout coping and recovery capability. EDGs are the principal emergency ac power sources for avoiding a station blackout. Regulatory Guide 1.155, Station Blackout, identifies a need for (1) a nuclear unit EDG reliability level of at least 0.95, and (2) an EDG reliability program to monitor and maintain the required EDG reliability levels. NUMARC-8700, Guidelines and Technical Bases for NUMARC Initiatives Addressing Station Blackout at Light Water Reactors, also provides guidance on such needs. The resolution of GSI B-56, Diesel Reliability will be accomplished by issuing Regulatory Guide 1.9, Rev. 3, Selection, Design, Qualification, Testing, and Reliability of Diesel Generator Units Used as Onsite Electric Power Systems at Nuclear Plants. This revision will integrate into a single regulatory guide pertinent guidance previously addressed in R.G. 1.9, Rev. 2, R.G. 1.108, and Generic Letter 84-15. R.G. 1.9 has been expanded to define the principal elements of an EDG reliability program for monitoring and maintaining EDG reliability levels selected for SBO. In addition, alert levels and corrective actions have been defined to detect a deteriorating situation for all EDGs assigned to a particular nuclear unit, as well as an individual problem EDG

  17. Key practical issues in strengthening safety culture. INSAG-15. A report by the International Safety Advisory Group [Russian Edition

    International Nuclear Information System (INIS)

    2015-01-01

    This report describes the essential practical issues to be considered by organizations aiming to strengthen safety culture. It is intended for senior executives, managers and first line supervisors in operating organizations. Although safety culture cannot be directly regulated, it is important that members of regulatory bodies understand how their actions affect the development of attempts to strengthen safety culture and are sympathetic to the need to improve the less formal human related aspects of safety. The report is therefore of relevance to regulators, although not intended primarily for them. The International Nuclear Safety Advisory Group (INSAG) introduced the concept of safety culture in its INSAG-4 report in 1991. Since then, many papers have been written on safety culture, as it relates to organizations and individuals, its improvement and its underpinning prerequisites. Variations in national cultures mean that what constitutes a good approach to enhancing safety culture in one country may not be the best approach in another. However, INSAG seeks to provide pragmatic and practical advice of wide applicability in the principles and issues presented in this report. Nuclear and radiological safety are the prime concerns of this report, but the topics discussed are so general that successful application of the principles should lead to improvements in other important areas, such as industrial safety, environmental performance and, in some respects, wider business performance. This is because many of the attitudes and practices necessary to achieve good performance in nuclear safety, including visible commitment by management, openness, care and thoroughness in completing tasks, good communication and clarity in recognizing major issues and dealing with them as a priority, have wide applicability

  18. Workshop on Regulatory Review and Safety Assessment Issues in Repository Licensing

    Energy Technology Data Exchange (ETDEWEB)

    Wilmot, Roger D. (Galson Sciences Limited (United Kingdom))

    2011-02-15

    The workshop described here was organised to address more general issues regarding regulatory review of SKB's safety assessment and overall review strategy. The objectives of the workshop were: - to learn from other programmes' experiences on planning and review of a license application for a nuclear waste repository, - to offer newly employed SSM staff an opportunity to learn more about selected safety assessment issues, and - to identify and document recommendations and ideas for SSM's further planning of the licensing review

  19. Generic safety issues for nuclear power plants with light water reactors and measures taken for their resolution

    International Nuclear Information System (INIS)

    1998-09-01

    The IAEA Conference on 'The Safety of Nuclear Power: Strategy for the Future' in 1991 was a milestone in nuclear safety. Two of the important items addressed by this conference were ensuring and enhancing safety of operating plants and treatment of nuclear power plants built to earlier safety standards. A number of publications related to these two items issued subsequent to this conference were: A Common Basis for Judging the Safety of Nuclear Power Plants Built to Earlier Standards, INSAG-9 (1995), the IAEA Safety Guide 50-SG-O12, periodic Safety Review of Operational Nuclear Power Plants (1994) and an IAEA publication on the Safety Evaluation of Operating Nuclear Power Plants Built to Earlier Standards - A Common Basis for Judgement (1997). Some of the findings of the 1991 Conference have not yet been fully addressed. An IAEA Symposium on reviewing the Safety of Existing Nuclear Power Plants in 1996 showed that there is an urgent need for operating organizations and national authorities to review operating nuclear power plants which do not meet the high safety levels of the vast majority of plants and to undertake improvements with assistance from the international community if required. Safety reviews of operating nuclear power plants take on added importance in the context of the Convention on Nuclear safety and its implementation. The purpose of this TECDOC compilation based on broad international experience, is to assist the Member States in the reassessment of operating plants by providing a list of generic safety issues identified in nuclear power plants together with measures taken to resolve these issues. These safety issues are generic in nature with regard to light water reactors and the measures for their resolution are for use as a reference for the safety reassessment of operating plants. The TECDOC covers issues thought to be significant to Member States based on consensus process. It provides an introduction to the use of generic safety issues for

  20. U.S. Food System Working Conditions as an Issue of Food Safety.

    Science.gov (United States)

    Clayton, Megan L; Smith, Katherine C; Pollack, Keshia M; Neff, Roni A; Rutkow, Lainie

    2017-02-01

    Food workers' health and hygiene are common pathways to foodborne disease outbreaks. Improving food system jobs is important to food safety because working conditions impact workers' health, hygiene, and safe food handling. Stakeholders from key industries have advanced working conditions as an issue of public safety in the United States. Yet, for the food industry, stakeholder engagement with this topic is seemingly limited. To understand this lack of action, we interviewed key informants from organizations recognized for their agenda-setting role on food-worker issues. Findings suggest that participants recognize the work standards/food safety connection, yet perceived barriers limit adoption of a food safety frame, including more pressing priorities (e.g., occupational safety); poor fit with organizational strategies and mission; and questionable utility, including potential negative consequences. Using these findings, we consider how public health advocates may connect food working conditions to food and public safety and elevate it to the public policy agenda.

  1. 14 CFR 414.35 - Public notification of the criteria by which a safety approval was issued.

    Science.gov (United States)

    2010-01-01

    ... issued. For each grant of a safety approval, the FAA will publish in the Federal Register a notice of the... which a safety approval was issued. 414.35 Section 414.35 Aeronautics and Space COMMERCIAL SPACE TRANSPORTATION, FEDERAL AVIATION ADMINISTRATION, DEPARTMENT OF TRANSPORTATION LICENSING SAFETY APPROVALS Safety...

  2. Ethical issues in patient safety: Implications for nursing management.

    Science.gov (United States)

    Kangasniemi, Mari; Vaismoradi, Mojtaba; Jasper, Melanie; Turunen, Hannele

    2013-12-01

    The purpose of this article is to discuss the ethical issues impacting the phenomenon of patient safety and to present implications for nursing management. Previous knowledge of this perspective is fragmented. In this discussion, the main drivers are identified and formulated in 'the ethical imperative' of patient safety. Underlying values and principles are considered, with the aim of increasing their visibility for nurse managers' decision-making. The contradictory nature of individual and utilitarian safety is identified as a challenge in nurse management practice, together with the context of shared responsibility and identification of future challenges. As a conclusion, nurse managers play a strategic role in patient safety. Their role is to incorporate ethical values of patient safety into decision-making at all levels in an organization, and also to encourage clinical nurses to consider values in the provision of care to patients. Patient safety that is sensitive to ethics provides sustainable practice where the humanity and dignity of all stakeholders are respected.

  3. Nuclear reactors safety issues

    International Nuclear Information System (INIS)

    Barre, Francois; Seiler, Nathalie

    2008-01-01

    Full text of publication follows: Since the seventies, economic incentives have led the utilities to drive a permanent evolution of the light water reactor (LWR). The evolution deals with the reactor designs as well as the way to operate them in a more flexible manner. It is for instance related to the fuel technologies and management. On the one hand, the technologies are in continuous evolution, such as the fuel pellets (MOX, Gd fuel, or Cr doped fuels..) as well as advanced cladding materials (M5 TM , MDA or ZIRLO). On the other hand, the fuel management is also subject to continuous evolution in particular in terms of increasing the level of burn-up, the reactor (core) power, the enrichment, as well as the duration of reactor cycles. For instance, in a few years in France, the burn-up has raised beyond the value of 39 GWj/t, initially authorized up to 52 GWj/t for the UO 2 fuel. In the near future, utilities foreseen to reach fuel burn-up of 60 GWj/t for MOX fuel and 70 GWj/t for UO 2 fuel. Furthermore, the future reactor of fourth generation will use new fuels of advanced conception. Furthermore with the objective of improving the safety margins, methods and calculation tools used by the utilities in the elaboration of their safety demonstrations submitted to the Safety Authority, are in movement. The margin evaluation methodologies often consist of a calculation chain of best-estimate multi-field simulations (e.g. various codes being coupled to simulate in a realistic way the evolution of the thermohydraulic, neutronic and mechanic state of the reactor). The statistical methods are more and more sophisticated and the computer codes are integrating ever-complex physical models (e.g. three-dimensional at fine scale). Following this evolution, the Institute of Radioprotection and Nuclear Safety (IRSN), whose one of the roles is to examine the safety records and to rend a technical expertise, considers the necessity of reevaluating the safety issues for advanced

  4. Safety culture issues and perspectives

    International Nuclear Information System (INIS)

    Dahlgren Persson, K.

    1999-01-01

    indicators, the symptoms and significance of shortcomings and degradation in the safety management processes and safety culture and hence failed to take effective corrective actions at an early stage. Key performance issues such as critical oversight, self assessment processes and effective corrective action programmes were not fully appreciated by senior management even after performance deficiencies were identified by the regulator and other external agencies. The seeming inability of the regulator to influence this senior management level, especially at the early stages of safety performance degradation was a major contributing factor in the continuation of the performance decline to the point that regulatory intervention became a necessity. Recovery processes commonly used a new utility senior management team to kick-start the change process and corresponding regulatory resource increases focused on monitoring the recovery. A comprehensive recovery plan and an interactive relationship with the regulator were deemed essential for a successful recovery. A review of the developing safety culture was a factor considered necessary to ensure sustainability. Public involvement in the regulatory monitoring process helped restore their confidence in the regulator, utility and plant management. The group recommended IAEA continue work to develop guidance for senior corporate management and regulators in this area (author) (ml)

  5. Legislation for the countermeasures on special issues of nuclear safety regulations

    International Nuclear Information System (INIS)

    Cho, Byung Sun; Lee, Mo Sung; Chung, Gum Chun; Kim, Heon Jin; Oh, Ho Chul

    2004-02-01

    Since the present nuclear safety regulation has some legal problems that refer to special issues and contents of regulatory provisions, this report has preformed research on the legal basic theory of nuclear safety regulation to solve the problems. In addition, this report analyzed the problems of each provisions and suggested the revision drafts on the basis of analyzing problems and the undergoing theory of nuclear safety regulation

  6. Legislation for the countermeasures on special issues of nuclear safety regulations

    Energy Technology Data Exchange (ETDEWEB)

    Cho, Byung Sun; Lee, Mo Sung; Chung, Gum Chun; Kim, Heon Jin; Oh, Ho Chul [Chongju Univ., Cheongju (Korea, Republic of)

    2004-02-15

    Since the present nuclear safety regulation has some legal problems that refer to special issues and contents of regulatory provisions, this report has preformed research on the legal basic theory of nuclear safety regulation to solve the problems. In addition, this report analyzed the problems of each provisions and suggested the revision drafts on the basis of analyzing problems and the undergoing theory of nuclear safety regulation.

  7. Experience with carbon ion radiotherapy at GSI

    Energy Technology Data Exchange (ETDEWEB)

    Jaekel, O. [Division of Medical Physics in Radiation Therapy (E040), German Cancer Research Center, Deutsches Krebsforschungszentrum, Im Neuenheimer Feld 280, 69120 Heidelberg (Germany)]. E-mail: o.jaekel@dkfz.de; Schulz-Ertner, D. [Department of Radiation Oncology, University of Heidelberg, Heidelberg (Germany); Karger, C.P. [Division of Medical Physics in Radiation Therapy (E040), German Cancer Research Center, Deutsches Krebsforschungszentrum, Im Neuenheimer Feld 280, 69120 Heidelberg (Germany); Heeg, P. [Division of Medical Physics in Radiation Therapy (E040), German Cancer Research Center, Deutsches Krebsforschungszentrum, Im Neuenheimer Feld 280, 69120 Heidelberg (Germany); Debus, J. [Department of Radiation Oncology, University of Heidelberg, Heidelberg (Germany)

    2005-12-15

    At GSI, a radiotherapy facility was established using beam scanning and active energy variation. Between December 1997 and April 2004, 220 patients have been treated at this facility with carbon ions. Most patients are treated for chordoma and chondrosarcoma of the base of skull, using a dose of 60 Gye (Gray equivalent) in 20 fractions. Carbon ion therapy is also offered in a combination with conventional radiotherapy for a number of other tumors (adenoidcystic carcinoma, chordoma of the cervical spine and sacrum, atypical menningeoma). The patients treated for skull base tumors showed an overall local control rate after two years of 90%. The overall treatment toxicity was mild. This shows that carbon ion radiotherapy can safely be applied using a scanned beam and encouraged the Heidelberg university hospital to build a hospital based facility for ion therapy.

  8. Technical Issues and Proposes on the Legislation of Probabilistic Safety Assessment in Periodic Safety Review

    International Nuclear Information System (INIS)

    Hwang, Seok-Won; Jeon, Ho-Jun; Na, Jang-Hwan

    2015-01-01

    Korean Nuclear Power Plants have performed a comprehensive safety assessment reflecting design and procedure changes and using the latest technology every 10 years. In Korea, safety factors of PSR are revised to 14 by revision of IAEA Safety Guidelines in 2003. In the revised safety guidelines, safety analysis field was subdivided into deterministic safety analysis, PSA (Probabilistic safety analysis), and hazard analysis. The purpose to examine PSA as a safety factor on PSR is to make sure that PSA results and assumptions reflect the latest state of NPPs, validate the level of computer codes and analytical models, and evaluate the adequacy of PSA instructions. In addition, its purpose is to derive the plant design change, operating experience of other plants and safety enhancement items as well. In Korea, PSA is introduced as a new factor. Thus, the overall guideline development and long-term implementation strategy are needed. Today in Korea, full-power PSA model revision and low-power and shutdown (LPSD) PSA model development is being performed as a part of the post Fukushima action items for operating plants. The scope of the full-power PSA is internal/external level 1, 2 PSA. But in case of fire PSA, the scope is level 1 PSA using new method, NUREG/CR-6850. In case of LPSD PSA, level 1 PSA for all operating plants, and level 2 PSA for 2 demonstration plants are under development. The result of the LPSD PSA will be used as major input data for plant specific SAMG (Severe Accident Management Guideline). The scope of PSA currently being developed in Korea cannot fulfill 'All Mode, All Scope' requirements recommended in the IAEA Safety Guidelines. Besides the legislation of PSA, step-by-step development strategy for non-performed scopes such as level 3 PSA and new fire PSA is one of the urgent issues in Korea. This paper suggests technical issues and development strategies for each PSA technical elements.

  9. Dust Combustion Safety Issues for Fusion Applications

    Energy Technology Data Exchange (ETDEWEB)

    L. C. Cadwallader

    2003-05-01

    This report summarizes the results of a safety research task to identify the safety issues and phenomenology of metallic dust fires and explosions that are postulated for fusion experiments. There are a variety of metal dusts that are created by plasma erosion and disruptions within the plasma chamber, as well as normal industrial dusts generated in the more conventional equipment in the balance of plant. For fusion, in-vessel dusts are generally mixtures of several elements; that is, the constituent elements in alloys and the variety of elements used for in-vessel materials. For example, in-vessel dust could be composed of beryllium from a first wall coating, tungsten from a divertor plate, copper from a plasma heating antenna or diagnostic, and perhaps some iron and chromium from the steel vessel wall or titanium and vanadium from the vessel wall. Each of these elements has its own unique combustion characteristics, and mixtures of elements must be evaluated for the mixture’s combustion properties. Issues of particle size, dust temperature, and presence of other combustible materials (i.e., deuterium and tritium) also affect combustion in air. Combustion in other gases has also been investigated to determine if there are safety concerns with “inert” atmospheres, such as nitrogen. Several coolants have also been reviewed to determine if coolant breach into the plasma chamber would enhance the combustion threat; for example, in-vessel steam from a water coolant breach will react with metal dust. The results of this review are presented here.

  10. Application of the risk-based strategy to the Hanford tank waste organic-nitrate safety issue

    International Nuclear Information System (INIS)

    Hunter, V.L.; Colson, S.D.; Ferryman, T.; Gephart, R.E.; Heasler, P.; Scheele, R.D.

    1997-12-01

    This report describes the results from application of the Risk-Based Decision Management Approach for Justifying Characterization of Hanford Tank Waste to the organic-nitrate safety issue in Hanford single-shell tanks (SSTs). Existing chemical and physical models were used, taking advantage of the most current (mid-1997) sampling and analysis data. The purpose of this study is to make specific recommendations for planning characterization to help ensure the safety of each SST as it relates to the organic-nitrate safety issue. An additional objective is to demonstrate the viability of the Risk-Based Strategy for addressing Hanford tank waste safety issues

  11. Application of the risk-based strategy to the Hanford tank waste organic-nitrate safety issue

    Energy Technology Data Exchange (ETDEWEB)

    Hunter, V.L.; Colson, S.D.; Ferryman, T.; Gephart, R.E.; Heasler, P.; Scheele, R.D.

    1997-12-01

    This report describes the results from application of the Risk-Based Decision Management Approach for Justifying Characterization of Hanford Tank Waste to the organic-nitrate safety issue in Hanford single-shell tanks (SSTs). Existing chemical and physical models were used, taking advantage of the most current (mid-1997) sampling and analysis data. The purpose of this study is to make specific recommendations for planning characterization to help ensure the safety of each SST as it relates to the organic-nitrate safety issue. An additional objective is to demonstrate the viability of the Risk-Based Strategy for addressing Hanford tank waste safety issues.

  12. Ecological Issues Related to Children's Health and Safety

    Science.gov (United States)

    Aldridge, Jerry; Kohler, Maxie

    2009-01-01

    Issues concerning the health and safety of children and youth occur at multiple levels. Bronfenbrenner (1995) proposed an ecological systems approach in which multiple systems interact to enhance or diminish children's development. The same systems are at work in health promotion. The authors present and review articles that reflect the multiple…

  13. Development and application of an initial quality assurance program for dosimetry at GSI

    Energy Technology Data Exchange (ETDEWEB)

    Heeg, P; Hartmann, G; Jaekel, O; Karger, C; Kriessbach, A [DKFZ Heidelberg (Germany); Schardt, D [GSI Darmstadt (Germany)

    1997-09-01

    c set of test procedures has been developed for dosimetric quality inspections at the heavy ion therapy facility at GSI. In some cases new test principles had to be established to meet the requirements at the heavy ion beam. As a first application the acceptance test has been carried out during the technical commissioning of the facility. (orig.)

  14. Issues of Safety and Security: New Challenging to Malaysia Tourism Industry

    Directory of Open Access Journals (Sweden)

    Mohd Ayob Norizawati

    2014-01-01

    Full Text Available The safety and security issues nowadays become one of the forces causing changes in tourism industry in era of millennium. The main concern of this issues more focus on crime rates, terrorism, food safety, health issues and natural disaster. This topic gained the popularity in tourism research after 9/11 tragedy and since then the academicians and practitioners started seeking the best solution in ways to mitigate these negative impacts. For Malaysia, the image as safety and secure destination was tarnished a few years lately and new unfortunates incident in this year bring more damage to Malaysia image. Healthy issues, terrorism, Lahad Datu intrusion, repeated kidnapping and shooting in Sabah, twin airlines incident, riot and illegal demonstration and false reporting by international media brings new challenging to Malaysia. Although some incident may be had short-term impact to Malaysia tourism industry, but it’s still gave the big impact to Malaysia branding process. Many travellers and Malaysian itself still believe that Malaysia is a one of safer destination and country to visit and stayed in, but more outstanding efforts was require to make sure Malaysia tourism industry was capable to recover from this negative impact as soon as possible.

  15. Resolution of the Hanford site ferrocyanide safety issue

    International Nuclear Information System (INIS)

    Cash, R.J.; Lilga, M.A.; Babad, H.

    1997-01-01

    The Ferrocyanide Safety Issue at the Hanford Site was officially resolved in December 1996. This paper summarizes the key activities that led to final resolution of this safety hazard, a process that began in 1990 after it and other safety concerns were identified for the underground high-level waste storage tanks at the Hanford Site. At the time little was known about ferrocyanide-nitrate/nitrite reactions and their potential to cause offsite releases of radioactivity. The ferrocyanide hazard was a perceived problem, but it took six years of intense studies and analyses of tank samples to prove that the problem no longer exists. The issue revolved around the fact that ferrocyanide and nitrate mixtures can be made to explode violently if concentrated, dry, and heated to temperatures of at least 250 degrees C. The studies conducted over the last six years have shown that the combined effects of temperature, radiation, and pH during 40 or more years of storage have destroyed almost all of the ferrocyanide originally added to tanks. This was shown in laboratory experiments using simulant wastes and confirmed by actual samples taken from the ferrocyanide tanks. The tank waste sludges are now too dilute to support a sustained exothermic reaction, even if dried out and heated to high temperatures. 2 tabs., 18 refs

  16. NS [Nuclear Safety] update. Current safety and security activities and developments taking place in the Department of Nuclear Safety and Security, Issue no. 11, June 2009

    International Nuclear Information System (INIS)

    2009-06-01

    The current issue presents information about the following topics: Nuclear Safety Review for the Year 2008; Feedback from IRS Topical Studies and Events Applied to Safety Standards; Education and Training Programmes at the IAEA Department of Nuclear Safety and Security; Peer Review of Operational Safety Performance (PROSPER)

  17. Containment-emergency-sump performance. Technical findings related to Unresolved Safety Issue A-43

    International Nuclear Information System (INIS)

    1983-04-01

    This report summarizes key technical findings related to the Unresolved Safety Issue A-43, Containment Emergency Sump Performance, and provides recommendations for resolution of attendant safety issues. The key safety questions relate to: (a) effects of insulation debris on sump performance; (b) sump hydraulic performance as determined by design features, submergence, and plant induced effects, and (c) recirculation pump performance wherein air and/or particulate ingestion can occur. The technical findings presented in this report provide information relevant to the design and performance evaluation of the containment emergency sump

  18. Collegiate Aviation Research and Education Solutions to Critical Safety Issues

    Science.gov (United States)

    Bowen, Brent (Editor)

    2002-01-01

    This Conference Proceedings is a collection of 6 abstracts and 3 papers presented April 19-20, 2001 in Denver, CO. The conference focus was "Best Practices and Benchmarking in Collegiate and Industry Programs". Topics covered include: satellite-based aviation navigation; weather safety training; human-behavior and aircraft maintenance issues; disaster preparedness; the collegiate aviation emergency response checklist; aviation safety research; and regulatory status of maintenance resource management.

  19. Emerging issues in occupational safety and health.

    Science.gov (United States)

    Schulte, Paul A

    2006-01-01

    In developed countries, changes in the nature of work and the workforce may necessitate recalibrating the vision of occupational safety and health (OSH) researchers, practitioners, and policymakers to increase the focus on the most important issues. New methods of organizing the workplace, extensive labor contracting, expansion of service and knowledge sectors, increase in small business, aging and immigrant workers, and the continued existence of traditional hazards in high-risk sectors such as construction, mining, agriculture, health care, and transportation support the need to address: 1) broader consideration of the role and impact of work, 2) relationship between work and psychological dysfunction, 3) increased surveillance basis for research and intervention, 4) overcoming barriers to the conduct and use of epidemiologic research, 5) information and knowledge transfer and application, 6) economic issues in prevention, and 7) the global interconnectedness of OSH. These issues are offered to spur thinking as new national research agendas for OSH are considered for developed countries.

  20. Collegiate Aviation Research and Education Solutions to Critical Safety Issues. UNO Aviation Monograph Series. UNOAI Report.

    Science.gov (United States)

    Bowen, Brent, Ed.

    This document contains four papers concerning collegiate aviation research and education solutions to critical safety issues. "Panel Proposal Titled Collegiate Aviation Research and Education Solutions to Critical Safety Issues for the Tim Forte Collegiate Aviation Safety Symposium" (Brent Bowen) presents proposals for panels on the…

  1. Decommissioning: Regulatory activities and identification of key organizational and human factors safety issues

    International Nuclear Information System (INIS)

    Durbin, N.E.; Melber, B.D.; Lekberg, A.

    2001-12-01

    In the late 1990's the Swedish government decided to shut down Unit 1 of the Barsebaeck nuclear power plant. This report documents some of the efforts made by the Swedish Nuclear Power Inspectorate (SKI) to address human factors and organizational issues in nuclear safety during decommissioning of a nuclear facility. This report gives a brief review of the background to the decommissioning of Barsebaeck 1 and points out key safety issues that can arise during decommissioning. The main regulatory activities that were undertaken were requirements that the plant provide special safety reports on decommissioning focusing on first, the operation of both units until closure of Unit 1 and second, the operation of Unit 2 when Unit 1 was closed. In addition, SKI identified areas that might be affected by decommissioning and called these areas out for special attention. With regard to these areas of special attention, SKI required that the plant provide monthly reports on changing and emerging issues as well as self-assessments of the areas to be addressed in the special safety reports. Ten key safety issues were identified and evaluated with regard to different stages of decommissioning and with regard to the actions taken by Barsebaeck. Some key conclusions from SKI's experience in regulating a decommissioning nuclear power plant conclude the report

  2. Safety in GPR prospecting: a rarely-considered issue

    Science.gov (United States)

    Persico, Raffaele; Pajewski, Lara; Trela, Christiane; Carrick Utsi, Erica

    2016-04-01

    Safety issues (of people first of all, but also of the equipment and environment) are rarely considered in Ground-Penetrating Radar (GPR) prospecting and, more in general, in near-surface geophysical prospecting. As is right and fully understandable, the scientific community devotes greatest attention first of all to the theoretical and practical aspects of GPR technique, affecting the quality of attainable results, secondly to the efforts and costs needed to achieve them [1-2]. However, the (luckily) growing GPR market and range of applications make it worth giving serious consideration to safety issues, too. The existing manuals dealing with safety in geophysics are mainly concerned with applications requiring "deep" geophysical prospecting, for example the search for oilfields and other hydrocarbon resources [3]. Near-surface geophysics involves less dangers than deep geophysics, of course. Nevertheless, several accidents have already happened during GPR experimental campaigns. We have personally had critical experiences and collected reliable testimonies concerning occurred problems as mountain sicks, fractures of legs, stomach problems, allergic reactions, encounters with potentially-dangerous animals, and more. We have also noticed that much more attention is usually paid to safety issues during indoor experimental activities (in laboratory), rather than during outdoor fieldworks. For example, the Italian National research Council is conventioned with safety experts who hold periodical seminaries about safety aspects. Having taken part to some of them, to our experience we have never heard a "lecture" devoted to outdoor prospecting. Nowadays, any aspects associated to the use of the technologies should be considered. The increasing sensibility and sense of responsibility towards environmental matters impose GPR end-users to be careful not to damage the environment and also the cultural heritage. Near-surface prospecting should not compromise the flora and

  3. Current status of environmental, health, and safety issues of nickel metal-hydride batteries for electric vehicles

    Energy Technology Data Exchange (ETDEWEB)

    Corbus, D; Hammel, C J; Mark, J

    1993-08-01

    This report identifies important environment, health, and safety issues associated with nickel metal-hydride (Ni-MH) batteries and assesses the need for further testing and analysis. Among the issues discussed are cell and battery safety, workplace health and safety, shipping requirements, and in-vehicle safety. The manufacture and recycling of Ni-MH batteries are also examined. This report also overviews the ``FH&S`` issues associated with other nickel-based electric vehicle batteries; it examines venting characteristics, toxicity of battery materials, and the status of spent batteries as a hazardous waste.

  4. Current status of environmental, health, and safety issues of nickel metal-hydride batteries for electric vehicles

    International Nuclear Information System (INIS)

    Corbus, D.; Hammel, C.J.; Mark, J.

    1993-08-01

    This report identifies important environment, health, and safety issues associated with nickel metal-hydride (Ni-MH) batteries and assesses the need for further testing and analysis. Among the issues discussed are cell and battery safety, workplace health and safety, shipping requirements, and in-vehicle safety. The manufacture and recycling of Ni-MH batteries are also examined. This report also overviews the ''FH ampersand S'' issues associated with other nickel-based electric vehicle batteries; it examines venting characteristics, toxicity of battery materials, and the status of spent batteries as a hazardous waste

  5. Safety issues and their ranking for WWER-1000 model 320 nuclear power plants. A publication of the extrabudgetary programme on the safety of WWER and RBMK nuclear power plants

    International Nuclear Information System (INIS)

    1996-03-01

    The objective of this report is to present a consolidated list of safety deficiencies, called safety issues, ranked according to their safety significance and the corrective measures to improve overall safety. It is intended for use as a reference to facilitate the development of plant specific safety improvement programmes and to serve as a basis for reviewing their implementation. To the extent that information was made available to the IAEA, the country/plant specific status with respect to each safety issue is described. Section 2 provides an overview of the impact of the relevant issues on the main safety functions in different operational conditions and other aspects important to overall plant safety. A summary of the safety issues and their respective ranking is given in Tables 1 and 2 at the end of Section 2. Section 3 deals with individual safety issues identified in the design which are presented according to the structure below. Section 4 presents the safety issues related to operational safety according to a similar structure but without the ranking. 73 refs, 3 tabs

  6. Safety issues and their ranking for WWER-1000 model 320 nuclear power plants. A publication of the extrabudgetary programme on the safety of WWER and RBMK nuclear power plants

    International Nuclear Information System (INIS)

    1997-04-01

    The objective of this report is to present a consolidated list of safety deficiencies, called safety issues, ranked according to their safety significance and the corrective measures to improve overall safety. It is intended for use as a reference to facilitate the development of plant specific safety improvement programmes and to serve as a basis for reviewing their implementation. To the extent that information was made available to the IAEA, the country/plant specific status with respect to each safety issue is described. Section 2 provides an overview of the impact of the relevant issues on the main safety functions in different operational conditions and other aspects important to overall plant safety. A summary of the safety issues and their respective ranking is given in Tables 1 and 2 at the end of Section 2. Section 3 deals with individual safety issues identified in the design which are presented according to the structure below. Section 4 presents the safety issues related to operational safety according to a similar structure but without the ranking

  7. 75 FR 57537 - Sunshine Act; Notice of Meetings

    Science.gov (United States)

    2010-09-21

    ..., 2010 9:30 a.m. Briefing on Security Issues (Closed--Ex. 1). * * * * * * The schedule for Commission..., 2010 1 p.m. Briefing on Resolution of Generic Safety Issue (GSI)--191, Assessment of Debris... 18, 2010 1:30 p.m. NRC All Employees Meeting (Public Meeting) Marriott Bethesda North Hotel, 5701...

  8. Occupational safety and health issues associated with green building

    NARCIS (Netherlands)

    Terwoert, J.; Ustailieva, E.

    2013-01-01

    This e-fact provides information on the work-related risk factors and the occupational safety and health (OSH) issues associated the planning and construction of green buildings, their maintenance, renovation (retrofitting), demolition, on-site waste collection. Some of these OSH risks are new

  9. Ferrocyanide Safety Program: Data requirements for the ferrocyanide safety issue developed through the data quality objectives (DQO) process

    International Nuclear Information System (INIS)

    Buck, J.W.; Anderson, C.M.; Pulsipher, B.A.; Toth, J.J.; Turner, P.J.; Cash, R.J.; Dukelow, G.T.; Meacham, J.E.

    1993-12-01

    This document records the data quality objectives (DQO) process applied to the Ferrocyanide Waste Tank Safety Issue at the Hanford Site by the Pacific Northwest Laboratory and Westinghouse Hanford Company. Specifically, the major recommendations and findings from this Ferrocyanide DQO process are presented so that decision makers can determine the type, quantity, and quality of data required for addressing tank safety issues. The decision logic diagrams and error tolerance equations also are provided. Finally, the document includes the DQO sample-size formulas for determining specific tank sampling requirements

  10. The future of nuclear power after Sizewell B. 3 v.: v. 1 Economic issues; v. 2 Environmental and safety issues; v. 3 Public perception issues

    International Nuclear Information System (INIS)

    1987-01-01

    The three days of conference proceedings are published in three separate volumes. The first includes 7 papers relating to economic issues - those presented at the Sizewell-B public inquiry and the changes in the economic situation since the inquiry ended. The electricity demand, how this demand is to be met by nuclear and other fuel sources and how energy conservation might be an economic alternative to simply building more generating capacity are all issues discussed. The possible privatisation of the industry is also touched on. Volume two has 8 papers concerned with environmental and safety issues. These include the influence of the Sizewell-B decision on nuclear licensing and reactor safety, the technical and safety aspects of pressurized water reactors (PWR), the roles of British Nuclear Fuels and the United Kingdom Atomic Energy Authority, and radiation protection and effluent discharge control. The six papers in volume 3 look at public perception issues - not only towards nuclear power but towards the public inquiry process. The local authority view, the Friends of the Earth case against the PWR, and technical expertise in the decision process are also topics covered. All the papers are indexed separately. (UK)

  11. Safety issues and their ranking for 'small series' WWER-1000 nuclear power plants. A publication of the extrabudgetary programme on the safety of WWER and RBMK nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-09-01

    This report presents the safety issues in 'small series' WWER-1000 nuclear power plants (NPPs). Safety issues are deviations from current recognized safety practices in design and operation judged to be safety significant by their impact on the plants' defence in depth. This report is intended to serve as reference for the development of plant specific safety improvement programmes and for the evaluation of measures proposed and/or implemented. The identification of safety issues is based on safety studies conducted by the operators of 'small series' WWER-1000 units and by organizations dealing with these reactors, on findings of IAEA safety missions to 'small series' WWER-1000 plants in South Ukraine, at Novovoronezh and Kalinin, and on information obtained from specialists from various countries during an IAEA consultants meeting, 8-12 September 1997 in Vienna, within the framework of the Extra budgetary Programme on the Safety of WWER and RBMK NPPs. Safety issues are first presented according to their impact on the main safety functions and are then described individually. The safety issues are characterized by issue title and specified by issue clarification. Safety issues connected with plant design are followed by the ranking of the issue and ranking justification. Altogether 85 safety issues have been identified, 12 of which are in Category III (defence in depth is insufficient, immediate corrective action is necessary), 38 in Category 11 (defence in depth is degraded, action is needed to resolve the issue) and 22 in Category I (departure from international practices, to be addressed as part of actions to resolve higher priority issues). In the case of operational safety issues (13 safety issues) no ranking is provided as the available material was considered insufficient. For each safety issue, comments and recommendations are made by the IAEA; the status of corresponding measures to improve safety implemented or planned at each site are presented in the

  12. Safety issues and their ranking for 'small series' WWER-1000 nuclear power plants. A publication of the extrabudgetary programme on the safety of WWER and RBMK nuclear power plants

    International Nuclear Information System (INIS)

    2000-09-01

    This report presents the safety issues in 'small series' WWER-1000 nuclear power plants (NPPs). Safety issues are deviations from current recognized safety practices in design and operation judged to be safety significant by their impact on the plants' defence in depth. This report is intended to serve as reference for the development of plant specific safety improvement programmes and for the evaluation of measures proposed and/or implemented. The identification of safety issues is based on safety studies conducted by the operators of 'small series' WWER-1000 units and by organizations dealing with these reactors, on findings of IAEA safety missions to 'small series' WWER-1000 plants in South Ukraine, at Novovoronezh and Kalinin, and on information obtained from specialists from various countries during an IAEA consultants meeting, 8-12 September 1997 in Vienna, within the framework of the Extra budgetary Programme on the Safety of WWER and RBMK NPPs. Safety issues are first presented according to their impact on the main safety functions and are then described individually. The safety issues are characterized by issue title and specified by issue clarification. Safety issues connected with plant design are followed by the ranking of the issue and ranking justification. Altogether 85 safety issues have been identified, 12 of which are in Category III (defence in depth is insufficient, immediate corrective action is necessary), 38 in Category 11 (defence in depth is degraded, action is needed to resolve the issue) and 22 in Category I (departure from international practices, to be addressed as part of actions to resolve higher priority issues). In the case of operational safety issues (13 safety issues) no ranking is provided as the available material was considered insufficient. For each safety issue, comments and recommendations are made by the IAEA; the status of corresponding measures to improve safety implemented or planned at each site are presented in the

  13. ISSUES AND RECENT TRENDS IN VEHICLE SAFETY COMMUNICATION SYSTEMS

    Directory of Open Access Journals (Sweden)

    Sadayuki TSUGAWA

    2005-01-01

    Full Text Available This paper surveys the research on the applications of inter-vehicle communications, the issues of the deployment and technology, and the current status of inter-vehicle communications projects in Europe, the United States and Japan. The inter-vehicle communications, defined here as communications between on-board ITS computers, improve road traffic safety and efficiency by expanding the horizon of the drivers and on-board sensors. One of the earliest studies on inter-vehicle communications began in Japan in the early 1980s. The inter-vehicle communications play an essential role in automated platooning and cooperative driving systems developed since the 1990's by enabling vehicles to obtain data that would be difficult or impossible to measure with on-board sensors. During these years, interest in applications for inter-vehicle communications increased in the EU, the US and Japan, resulting in many national vehicle safety communications projects such as CarTALK2000 in the EU and VSCC in the US. The technological issues include protocol and communications media. Experiments employ various kinds of protocols and typically use infrared, microwave or millimeter wave media. The situation is ready for standardization. The deployment strategy is another issue. To be feasible, deployment should begin with multiple rather than single services that would work even at a low penetration rate of the communication equipment. In addition, non-technological, legal and institutional issues remained unsolved. Although inter-vehicle communications involve many issues, such applications should be promoted because they will lead to safer and more efficient automobile traffic.

  14. NS [Nuclear Safety] update. Current safety and security activities and developments taking place in the Department of Nuclear Safety and Security, Issue no. 12, September 2009

    International Nuclear Information System (INIS)

    2009-09-01

    The current issue presents information about the following topics: Nuclear Security Report 2009; G8 Nuclear Safety and Security Group (NSSG); Uranium Production Site Appraisal Team (UPSAT); New Entrant Nuclear Power Programmes Safety Guide on the Establishment of the Safety Infrastructure (DS424)

  15. An alternative window upon the GSI sharp lepton problem

    International Nuclear Information System (INIS)

    Griffin, J.J.

    1997-10-01

    Two major heavy ion studies of the GSI ''(e + e - )-Puzzle'' have ended in stalemate: APEX reports no evidence, but its data show a peak near 800 keV. EPOS/II cannot reproduce its own results,and leans towards random fluctuations as the explanation of sharp pair lines. (But one EPOS/II report shows evidence for a peak at an EPOS/I line energy, 610 keV, and under selection conditions the same as EPOSII's.) It is clear that these latest heavy ion studies, designed to settle once and for all the question of sharp pairs, have failed to fulfill that goal. Attention must now turn towards the sharp electron lines reported by Sakai et al. and others in collisions of few MeV beta decay positrons on U and Th atoms. In the Q 0 Scenario of the Sharp Lepton Problem these arise from the same source as the GSI pairs. Verification of Sakai's 100 mb cross section for such sharp electrons in collisions of few MeV electrons (or positrons) upon U or Th atoms would confirm this new experimental window upon the Sharp Lepton Problem. These relatively simple experiments, which are both inexpensive and reproducible (as their heavy ion counterparts are not), promise a less ponderous pace for the study of these questions. On the other hand, they require a challenging combination of proficiencies to measure a nuclear sized cross section in an atomic physics environment. The authors review briefly the diverse history (and especially the most recent developments) of the Sharp Lepton Problem, and outline how the Quadronium Scenario provides it with a unifying conceptual framework. That discussion points clearly towards the experimental study of sharp leptons and sharp pairs from few MeV (lepton+ATOM) and (photon+ATOM) processes as the appropriate next step towards either verifying the earlier results or precluding them

  16. A Green Soundscape Index (GSI): The potential of assessing the perceived balance between natural sound and traffic noise.

    Science.gov (United States)

    Kogan, Pablo; Arenas, Jorge P; Bermejo, Fernando; Hinalaf, María; Turra, Bruno

    2018-06-13

    Urban soundscapes are dynamic and complex multivariable environmental systems. Soundscapes can be organized into three main entities containing the multiple variables: Experienced Environment (EE), Acoustic Environment (AE), and Extra-Acoustic Environment (XE). This work applies a multidimensional and synchronic data-collecting methodology at eight urban environments in the city of Córdoba, Argentina. The EE was assessed by means of surveys, the AE by acoustic measurements and audio recordings, and the XE by photos, video, and complementary sources. In total, 39 measurement locations were considered, where data corresponding to 61 AE and 203 EE were collected. Multivariate analysis and GIS techniques were used for data processing. The types of sound sources perceived, and their extents make up part of the collected variables that belong to the EE, i.e. traffic, people, natural sounds, and others. Sources explaining most of the variance were traffic noise and natural sounds. Thus, a Green Soundscape Index (GSI) is defined here as the ratio of the perceived extents of natural sounds to traffic noise. Collected data were divided into three ranges according to GSI value: 1) perceptual predominance of traffic noise, 2) balanced perception, and 3) perceptual predominance of natural sounds. For each group, three additional variables from the EE and three from the AE were applied, which reported significant differences, especially between ranges 1 and 2 with 3. These results confirm the key role of perceiving natural sounds in a town environment and also support the proposal of a GSI as a valuable indicator to classify urban soundscapes. In addition, the collected GSI-related data significantly helps to assess the overall soundscape. It is noted that this proposed simple perceptual index not only allows one to assess and classify urban soundscapes but also contributes greatly toward a technique for separating environmental sound sources. Copyright © 2018 Elsevier B

  17. Specific issues, exact locations: case study of a community mapping project to improve safety in a disadvantaged community.

    Science.gov (United States)

    Qummouh, Rana; Rose, Vanessa; Hall, Pat

    2012-12-01

    Safety is a health issue and a significant concern in disadvantaged communities. This paper describes an example of community-initiated action to address perceptions of fear and safety in a suburb in south-west Sydney which led to the development of a local, community-driven research project. As a first step in developing community capacity to take action on issues of safety, a joint resident-agency group implemented a community safety mapping project to identify the extent of safety issues in the community and their exact geographical location. Two aerial maps of the suburb, measuring one metre by two metres, were placed on display at different locations for four months. Residents used coloured stickers to identify specific issues and exact locations where crime and safety were a concern. Residents identified 294 specific safety issues in the suburb, 41.9% (n=123) associated with public infrastructure, such as poor lighting and pathways, and 31.9% (n=94) associated with drug-related issues such as drug activity and discarded syringes. Good health promotion practice reflects community need. In a very practical sense, this project responded to community calls for action by mapping resident knowledge on specific safety issues and exact locations and presenting these maps to local decision makers for further action.

  18. Safety issues and their ranking for WWER-440 model 213 nuclear power plants. A publication of the extrabudgetary programme on the safety of WWER and RBMK nuclear power plants

    International Nuclear Information System (INIS)

    1996-04-01

    The objective of this report is to present a consolidated list of generic safety concerns, called safety issues, ranked according to their safety significance and the corrective measures to improve safety. It is intended for use as a reference to facilitate the development of plant specific safety improvement programmes and to serve as a basis for reviewing their implementation. Section 2 provides and overview of the impact of all relevant issues on the main safety functions and other aspects important to overall plant safety. Section 3 presents safety issues identified in design according to the structure described below. Section 4 presents the safety issues in the area of operation, according to the same structure except that no ranking is given. At the end of Section 2, Tables 1 and 2 present a summary of all safety issues in a tabular form. 138 refs, tabs

  19. Hydrogen peroxide safety issues

    International Nuclear Information System (INIS)

    Conner, W.V.

    1993-01-01

    A literature survey was conducted to review the safety issues involved in handling hydrogen peroxide solutions. Most of the information found in the literature is not directly applicable to conditions at the Rocky Flats Plant, but one report describes experimental work conducted previously at Rocky Flats to determine decomposition reaction-rate constants for hydrogen peroxide solutions. Data from this report were used to calculate decomposition half-life times for hydrogen peroxide in solutions containing several decomposition catalysts. The information developed from this survey indicates that hydrogen peroxide will undergo both homogeneous and heterogeneous decomposition. The rate of decomposition is affected by temperature and the presence of catalytic agents. Decomposition of hydrogen peroxide is catalyzed by alkalies, strong acids, platinum group and transition metals, and dissolved salts of transition metals. Depending upon conditions, the consequence of a hydrogen peroxide decomposition can range from slow evolution of oxygen gas to a vapor, phase detonation of hydrogen peroxide vapors

  20. IAEA activities on communication of nuclear safety issues

    International Nuclear Information System (INIS)

    Wieland, P.

    2001-01-01

    The regulatory authorities in several countries have taken the initiative to overcome the renowned difficulties of communicating nuclear safety issues. They communicate with segments of the public specially in case of nuclear/radiological accidents, waste disposal, transport of radioactive material or food irradiation. This reflects the full recognition of the importance of the topic. However it is also recognized that there is hitherto a need of international assistance in order to develop a regulatory communication strategy that could be harmonized and at the same time customized to the different needs. Communications on nuclear, radiation, transport and radioactive waste safety are needed to: disseminate information on safety to the public in both routine and emergency situations ; be attentive to public concerns, and address them; maintain social trust and confidence by keeping society informed on the established safety standards and how they are enforced; facilitate the decision-making process on nuclear matters by promptly presenting factual information in a clear manner; integrate and maintain an information network at both the national and international levels; improve co-operation with other countries and international organizations; encourage the dissemination of factual information on nuclear issues in schools. A major factor in addressing all of these questions is understanding the audience(s). A two way communication process is needed to establish what particular audiences want to know and in what form they prefer to receive information. This will differ depending on the audience and circumstances. For example, the information on a routine day-to-day basis will be different from what might be needed at the time of an accident. Communication with the news media is a matter of particular importance, as they are both an audience in themselves and a channel for communicating with wider audiences. (author)

  1. Planning exercise for the resolution of high level waste tank safety issues

    International Nuclear Information System (INIS)

    Bunting, J.; Saveland, J.

    1992-01-01

    Several conditions have been found to exist within high level radioactive waste storage tanks at the Hanford site which could lead to uncontrolled exothermic reactions and/or to the release of tank contents into the environment. These conditions have led to the establishment of four priority 1 safety issues for the Hanford tanks. Resolution of these safety issues will require the coordinated efforts of professionals in chemical, nuclear, operations, safety, and other technical areas. A coordinated and integrated approach is necessary in order to achieve resolution in the shortest possible time, while ensuring that the steps taken do not complicate the later jobs of vitrification and ultimate disposal. This paper describes the purpose, process, and results of an effort to develop a suggested approach. (author)

  2. Resolution of Generic Safety Issue 29: Bolting degradation or failure in nuclear power plants

    International Nuclear Information System (INIS)

    Johnson, R.E.

    1990-06-01

    This report describes the US Nuclear Regulatory Commission's (NRC's) Generic Safety Issue 29, ''Bolting Degradation or Failure in Nuclear Power Plants,'' including the bases for establishing the issue and its historical highlights. The report also describes the activities of the Atomic Industrial Forum (AIF) relevant to this issue, including its cooperation with the Materials Properties Council (MPC) to organize a task group to help resolve the issue. The Electric Power Research Institute, supported by the AIF/MPC task group, prepared and issued a two-volume document that provides, in part, the technical basis for resolving Generic Safety Issue 29. This report presents the NRC's review and evaluation of the two-volume document and NRC's conclusion that this document, in conjunction with other information from both industry and NRC, provides the bases for resolving this issue

  3. Test of a non-invasive bunch shape monitor at the GSI high current LINAC

    Energy Technology Data Exchange (ETDEWEB)

    Zwicker, Benjamin; Forck, Peter; Kester, Oliver [GSI Helmholtzzentrum fuer Schwerionenforschung, Darmstadt (Germany); Institut fuer Angewandte Physik, Goethe Universitaet Frankfurt (Germany); Dorn, Christoph; Kowina, Piotr [GSI Helmholtzzentrum fuer Schwerionenforschung, Darmstadt (Germany)

    2014-07-01

    At the heavy ion LINAC at GSI, a novel scheme of non-invasive Bunch Shape Monitor has been tested with several ion beams at 11.4 MeV/u. Caused by the beam impact on the residual gas, secondary electrons are liberated. These electrons are accelerated by an electrostatic field, transported through a sophisticated electrostatic energy analyzer and an rf-deflector, acting as a time-to-space converter. Finally a MCP detects the electron distribution. For the applied beam settings this Bunch Shape Monitor is able to obtain longitudinal profiles down to 400 ps with a resolution of 50 ps, corresponding to 2 degree of the 36 MHz acceleration frequency. During a long shutdown period for the GSI accelerators in 2013, the monitor underwent a general technical retrofit: Influence of the beam has been significantly reduced, due enhanced electrodes, new apertures have been installed to decrease electron scattering, sophisticated stepping motors will allow better image properties, a MCP shielding plate will prevent high background. Together with these improvements the achievements of the monitor are discussed.

  4. Study on operational safety issues in the Japanese disposal concept

    International Nuclear Information System (INIS)

    Suzuki, Satoru; Kitagawa, Yoshito; Hyodo, Hideaki; Kubota, Shigeru; Iijima, Masayoshi; Tamura, Akio; Ishiguro, Katsuhiko; Fujihara, Hiroshi

    2014-01-01

    In Japan, vitrified high-level radioactive waste (HLW) and certain types of low-level radioactive waste that results from the reprocessing of spent fuel and classified as TRU waste will be disposed of in deep geological formations. NUMO aims to ensure the safety of local residents and workers during the operational phase and after repository closure and will therefore establish a safety case for the geological disposal programme at the end of each stage of the stepwise siting process. Although the Japanese programme is still in the stage before initiation of the siting process, updating the generic (non-site-specific) safety case is required for building confidence among stakeholders. This study focuses on operational safety issues for the Japanese HLW disposal concept. (authors)

  5. A framework for elaborating a geological disposal safety case: Main issues to be addressed

    International Nuclear Information System (INIS)

    Besnus, F.; Gay, D.

    2002-01-01

    International guidance on safety standards for the geological disposal of radioactive waste is being elaborated by IAEA. A comparison of experiences acquired in developing deep repository projects shows that many important issues related to the progressive building of confidence in the safety demonstration of such facilities are commonly addressed by the various organisations involved in radioactive waste management. However, there is still some discrepancies in defining the steps that form the staged elaboration of a safety case. This paper intends to propose a framework for defining the safety case in describing the main issues to be addressed and highlighting questions of consistency between former steps. (author)

  6. NS [Nuclear Safety] update. Current safety and security activities and developments taking place in the Department of Nuclear Safety and Security, Issue no. 6, March 2008

    International Nuclear Information System (INIS)

    2008-03-01

    The current issue presents information about the following activities: 1) International Conference on Illicit Nuclear Trafficking which took place in November 2007 in Edinburgh. The principal aim of the conference was to examine the threat and context of illicit nuclear trafficking of radioactive material, specifically, what is being done to combat such trafficking and where more needs to be done. The conference was also to consider how the obligations and commitments of the legally binding and non-binding international instruments could be and are being implemented by various States. 2) INSAG Message on Nuclear Safety Infrastructure in which the INSAG Chairman Richard Meserve addressed nuclear safety in the current context and various issues that warrant special attention. 3) approved for publication the Safety Requirements publication on Safety of Nuclear Fuel Cycle Facilities. 4) The Asian Nuclear Safety Network (ANSN)

  7. NS [Nuclear Safety] update. Current safety and security activities and developments taking place in the Department of Nuclear Safety and Security, Issue no. 10, March 2009

    International Nuclear Information System (INIS)

    2009-03-01

    The current issue contains information about the following meetings: Application of the Code of Conduct on the Safety of Research Reactors (the 'Code'). Environmental Modelling for Radiation Safety (EMRAS II); Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management (the Joint Convention). The document also gives an overview on International Nuclear Security Advisory Service (INSServ)

  8. Contrast media. Safety issues and ESUR guidelines

    Energy Technology Data Exchange (ETDEWEB)

    Thomsen, H.S. (ed.) [Copenhagen Univ. Hospital, Herlev (Denmark). Dept. of Diagnostic Radiology 54E2

    2006-07-01

    In 1994 the European Society of Urogenital Radiology (ESUR) set up a committee to consider the safety of the contrast media used in radiology departments. Since then, the committee has questioned members, reviewed the literature, proposed guidelines, and discussed these proposals with participants at the annual symposia on urogenital radiology. This book represents the end result of this hard work. It contains all of the agreed guidelines, updated when necessary, and thereby comprehensively covers the many different safety issues relating to the diverse contrast media: barium contrast media, iodinated contrast media, MR contrast media (both gadolinium-based extracellular and organ-specific) and ultrasound contrast media. The prevention and treatment of both acute and delayed non-renal adverse reactions as well as the renal adverse reactions are covered in detail. The inclusion of all the ESUR guidelines within one book will offer an invaluable, unique and unparalleled resource. (orig.)

  9. Contrast media. Safety issues and ESUR guidelines

    International Nuclear Information System (INIS)

    Thomsen, H.S.

    2006-01-01

    In 1994 the European Society of Urogenital Radiology (ESUR) set up a committee to consider the safety of the contrast media used in radiology departments. Since then, the committee has questioned members, reviewed the literature, proposed guidelines, and discussed these proposals with participants at the annual symposia on urogenital radiology. This book represents the end result of this hard work. It contains all of the agreed guidelines, updated when necessary, and thereby comprehensively covers the many different safety issues relating to the diverse contrast media: barium contrast media, iodinated contrast media, MR contrast media (both gadolinium-based extracellular and organ-specific) and ultrasound contrast media. The prevention and treatment of both acute and delayed non-renal adverse reactions as well as the renal adverse reactions are covered in detail. The inclusion of all the ESUR guidelines within one book will offer an invaluable, unique and unparalleled resource. (orig.)

  10. Addressing the fundamental issues in reliability evaluation of passive safety of AP1000 for a comparison with active safety of PWR

    International Nuclear Information System (INIS)

    Hashim Muhammad; Yoshikawa, Hidekazu; Yang Ming

    2013-01-01

    Passive safety systems adopted in advanced Pressurized Water Reactor (PWR), such as AP1000 and EPR, should attain higher reliability than the existing active safety systems of the conventional PWR. The objective of this study is to discuss the fundamental issues relating to the reliability evaluation of AP1000 passive safety systems for a comparison with the active safety systems of conventional PWR, based on several aspects. First, comparisons between conventional PWR and AP1000 are made from the both aspects of safety design and cost reduction. The main differences between these PWR plants exist in the configurations of safety systems: AP1000 employs the passive safety system while reducing the number of active systems. Second, the safety of AP1000 is discussed from the aspect of severe accident prevention in the event of large break loss of coolant accidents (LOCA). Third, detailed fundamental issues on reliability evaluation of AP1000 passive safety systems are discussed qualitatively by using single loop models of safety systems of both PWRs plants. Lastly, methodology to conduct quantitative estimation of dynamic reliability for AP1000 passive safety systems in LOCA condition is discussed, in order to evaluate the reliability of AP1000 in future by a success-path-based reliability analysis method (i.e., GO-FLOW). (author)

  11. Safety issues relating to the design of fusion power facilities

    International Nuclear Information System (INIS)

    Stasko, R.R.; Wong, K.Y.; Russell, S.B.

    1986-06-01

    In order to make fusion power a viable future source of energy, it will be necessary to ensure that the cost of power for fusion electric generation is competitive with advanced fission concepts. In addition, fusion power will have to live up to its original promise of being a more radiologically benign technology than fission, and be able to demonstrate excellent operational safety performance. These two requirements are interrelated, since the selection of an appropriate safety philosophy early in the design phase could greatly reduce or eliminate the capital costs of elaborate safety related and protective sytems. This paper will briefly overview a few of the key safety issues presently recognized as critical to the ultimate achievement of licensable, environmentally safe and socially acceptable fusion power facilities. 12 refs

  12. Conceptualizing a Genomics Software Institute (GSI).

    Science.gov (United States)

    Gilbert, Jack A; Catlett, Charlie; Desai, Narayan; Knight, Rob; White, Owen; Robbins, Robert; Sankaran, Rajesh; Sansone, Susanna-Assunta; Field, Dawn; Meyer, Folker

    2012-03-19

    Microbial ecology has been enhanced greatly by the ongoing 'omics revolution, bringing half the world's biomass and most of its biodiversity into analytical view for the first time; indeed, it feels almost like the invention of the microscope and the discovery of the new world at the same time. With major microbial ecology research efforts accumulating prodigious quantities of sequence, protein, and metabolite data, we are now poised to address environmental microbial research at macro scales, and to begin to characterize and understand the dimensions of microbial biodiversity on the planet. What is currently impeding progress is the need for a framework within which the research community can develop, exchange and discuss predictive ecosystem models that describe the biodiversity and functional interactions. Such a framework must encompass data and metadata transparency and interoperation; data and results validation, curation, and search; application programming interfaces for modeling and analysis tools; and human and technical processes and services necessary to ensure broad adoption. Here we discuss the need for focused community interaction to augment and deepen established community efforts, beginning with the Genomic Standards Consortium (GSC), to create a science-driven strategic plan for a Genomic Software Institute (GSI).

  13. The FIRST experiment at GSI

    International Nuclear Information System (INIS)

    Pleskac, R.; Abou-Haidar, Z.; Agodi, C.; Alvarez, M.A.G.; Aumann, T.; Battistoni, G.; Bocci, A.; Böhlen, T.T.; Boudard, A.; Brunetti, A.; Carpinelli, M.; Cirrone, G.A.P.; Cortes-Giraldo, M.A.; Cuttone, G.; De Napoli, M.; Durante, M.; Fernández-García, J.P.; Finck, C.; Golosio, B.; Gallardo, M.I.

    2012-01-01

    The FIRST (Fragmentation of Ions Relevant for Space and Therapy) experiment at the SIS accelerator of GSI laboratory in Darmstadt has been designed for the measurement of ion fragmentation cross-sections at different angles and energies between 100 and 1000 MeV/nucleon. Nuclear fragmentation processes are relevant in several fields of basic research and applied physics and are of particular interest for tumor therapy and for space radiation protection applications. The start of the scientific program of the FIRST experiment was on summer 2011 and was focused on the measurement of 400 MeV/nucleon 12 C beam fragmentation on thin (8 mm) graphite target. The detector is partly based on an already existing setup made of a dipole magnet (ALADiN), a time projection chamber (TP-MUSIC IV), a neutron detector (LAND) and a time of flight scintillator system (TOFWALL). This pre-existing setup has been integrated with newly designed detectors in the Interaction Region, around the carbon target placed in a sample changer. The new detectors are a scintillator Start Counter, a Beam Monitor drift chamber, a silicon Vertex Detector and a Proton Tagger scintillator system optimized for the detection of light fragments emitted at large angles. In this paper we review the experimental setup, then we present the simulation software, the data acquisition system and finally the trigger strategy of the experiment.

  14. The FIRST experiment at GSI

    Energy Technology Data Exchange (ETDEWEB)

    Pleskac, R. [GSI Helmholtzzentrum fuer Schwerionenforschung, Darmstadt (Germany); Abou-Haidar, Z. [CNA, Sevilla (Spain); Agodi, C. [Istituto Nazionale di Fisica Nucleare - Laboratori Nazionali del Sud (Italy); Alvarez, M.A.G. [CNA, Sevilla (Spain); Aumann, T. [GSI Helmholtzzentrum fuer Schwerionenforschung, Darmstadt (Germany); Battistoni, G. [Istituto Nazionale di Fisica Nucleare - Sezione di Milano (Italy); Bocci, A. [CNA, Sevilla (Spain); Boehlen, T.T. [European Organization for Nuclear Research CERN, Geneva (Switzerland); Medical Radiation Physics, Karolinska Institutet and Stockholm University, Stockholm (Sweden); Boudard, A. [CEA-Saclay, IRFU/SPhN, Gif sur Yvette Cedex (France); Brunetti, A.; Carpinelli, M. [Istituto Nazionale di Fisica Nucleare - Sezione di Cagliari (Italy); Universita' di Sassari (Italy); Cirrone, G.A.P. [Istituto Nazionale di Fisica Nucleare - Laboratori Nazionali del Sud (Italy); Cortes-Giraldo, M.A. [Departamento de Fisica Atomica, Molecular y Nuclear, University of Sevilla, 41080-Sevilla (Spain); Cuttone, G. [Istituto Nazionale di Fisica Nucleare - Laboratori Nazionali del Sud (Italy); De Napoli, M. [Istituto Nazionale di Fisica Nucleare - Sezione di Catania (Italy); Durante, M. [GSI Helmholtzzentrum fuer Schwerionenforschung, Darmstadt (Germany); Fernandez-Garcia, J.P. [Departamento de Fisica Atomica, Molecular y Nuclear, University of Sevilla, 41080-Sevilla (Spain); Finck, C. [Institut Pluridisciplinaire Hubert Curien, Strasbourg (France); Golosio, B. [Istituto Nazionale di Fisica Nucleare - Sezione di Cagliari (Italy); Universita' di Sassari (Italy); Gallardo, M.I. [Departamento de Fisica Atomica, Molecular y Nuclear, University of Sevilla, 41080-Sevilla (Spain); and others

    2012-06-21

    The FIRST (Fragmentation of Ions Relevant for Space and Therapy) experiment at the SIS accelerator of GSI laboratory in Darmstadt has been designed for the measurement of ion fragmentation cross-sections at different angles and energies between 100 and 1000 MeV/nucleon. Nuclear fragmentation processes are relevant in several fields of basic research and applied physics and are of particular interest for tumor therapy and for space radiation protection applications. The start of the scientific program of the FIRST experiment was on summer 2011 and was focused on the measurement of 400 MeV/nucleon {sup 12}C beam fragmentation on thin (8 mm) graphite target. The detector is partly based on an already existing setup made of a dipole magnet (ALADiN), a time projection chamber (TP-MUSIC IV), a neutron detector (LAND) and a time of flight scintillator system (TOFWALL). This pre-existing setup has been integrated with newly designed detectors in the Interaction Region, around the carbon target placed in a sample changer. The new detectors are a scintillator Start Counter, a Beam Monitor drift chamber, a silicon Vertex Detector and a Proton Tagger scintillator system optimized for the detection of light fragments emitted at large angles. In this paper we review the experimental setup, then we present the simulation software, the data acquisition system and finally the trigger strategy of the experiment.

  15. The FIRST experiment at GSI

    Science.gov (United States)

    Pleskac, R.; Abou-Haidar, Z.; Agodi, C.; Alvarez, M. A. G.; Aumann, T.; Battistoni, G.; Bocci, A.; Böhlen, T. T.; Boudard, A.; Brunetti, A.; Carpinelli, M.; Cirrone, G. A. P.; Cortes-Giraldo, M. A.; Cuttone, G.; De Napoli, M.; Durante, M.; Fernández-García, J. P.; Finck, C.; Golosio, B.; Gallardo, M. I.; Iarocci, E.; Iazzi, F.; Ickert, G.; Introzzi, R.; Juliani, D.; Krimmer, J.; Kurz, N.; Labalme, M.; Leifels, Y.; Le Fevre, A.; Leray, S.; Marchetto, F.; Monaco, V.; Morone, M. C.; Oliva, P.; Paoloni, A.; Piersanti, L.; Quesada, J. M.; Raciti, G.; Randazzo, N.; Romano, F.; Rossi, D.; Rousseau, M.; Sacchi, R.; Sala, P.; Sarti, A.; Scheidenberger, C.; Schuy, C.; Sciubba, A.; Sfienti, C.; Simon, H.; Sipala, V.; Spiriti, E.; Stuttge, L.; Tropea, S.; Younis, H.; Patera, V.

    2012-06-01

    The FIRST (Fragmentation of Ions Relevant for Space and Therapy) experiment at the SIS accelerator of GSI laboratory in Darmstadt has been designed for the measurement of ion fragmentation cross-sections at different angles and energies between 100 and 1000 MeV/nucleon. Nuclear fragmentation processes are relevant in several fields of basic research and applied physics and are of particular interest for tumor therapy and for space radiation protection applications. The start of the scientific program of the FIRST experiment was on summer 2011 and was focused on the measurement of 400 MeV/nucleon 12C beam fragmentation on thin (8 mm) graphite target. The detector is partly based on an already existing setup made of a dipole magnet (ALADiN), a time projection chamber (TP-MUSIC IV), a neutron detector (LAND) and a time of flight scintillator system (TOFWALL). This pre-existing setup has been integrated with newly designed detectors in the Interaction Region, around the carbon target placed in a sample changer. The new detectors are a scintillator Start Counter, a Beam Monitor drift chamber, a silicon Vertex Detector and a Proton Tagger scintillator system optimized for the detection of light fragments emitted at large angles. In this paper we review the experimental setup, then we present the simulation software, the data acquisition system and finally the trigger strategy of the experiment.

  16. Japan's regulatory and safety issues regarding nuclear materials transport

    International Nuclear Information System (INIS)

    Saito, T.; Yamanaka, T.

    2004-01-01

    This paper focuses on the regulatory and safety issues on nuclear materials transport which the Government of Japan (GOJ) faces and needs to well handle. Background information about the status of nuclear power plants (NPP) and nuclear fuel cycle (NFC) facilities in Japan will promote a better understanding of what this paper addresses

  17. Campus Safety and Student Privacy Issues in Higher Education

    Science.gov (United States)

    Burnett, Kristen Slater

    2010-01-01

    The purpose of this study is to delve into, and further understand, the perceptions of higher education administrators when they experience having to simultaneously balance the issues of campus safety and student privacy. The research surveyed approximately 900 (with 147 returns) administrators who self-identified as having a role in incidents of…

  18. Assessment of policy issues in nuclear safety regulation according to circumstantial changes

    Energy Technology Data Exchange (ETDEWEB)

    Chang, Soon Heung; Lee, Byong Ho; Baek, Won Pil; Lee, Kwang Gu; Huh, Gyun Young; Hahn, Young Tae [Korea Advanced Institute of Science and Technology, Taejon (Korea, Republic of)

    2000-03-15

    The objective of the work is to assess various issues in nuclear safety regulation in consideration of circumstantial changes. Emphasis is given to the safety of operating NPPs. It is concluded that the Periodic Safety Review (PSR) should be implemented in Korea as soon as possible, in harmonization with the regulation for life extension of NPPs. The IAEA guidelines, including 10 year intervals and 11 safety factors, should be used as the basic guidelines. The approach to improve regulatory effectiveness is also reviewed and a transition to 'knowledge-based regulation' is suggested.

  19. Assessment of policy issues in nuclear safety regulation according to circumstantial changes

    Energy Technology Data Exchange (ETDEWEB)

    Chang, Soon Heung; Chang, Soon Heung; Lee, Byong Ho; Baek, Won Pil; Roh, Chang Hyun; Lee, Kwang Gu; Kim, Hong Chae; Lee, Yong Ho [Korea Advanced Institute of Science and Technology, Taejon (Korea, Republic of)

    1999-03-15

    The objective of the work is to assess various issues in nuclear safety regulation in consideration of circumstantial changes. Emphasis is given to the safety of operating NPPs. It is concluded that the Periodic Safety Review (PSR) should be implemented in Korea as soon as possible, in harmonization with the regulation for life extension of NPPs. The IAEA guidelines, including 10 year intervals and 11 safety factors, should be used as the basic guidelines. Efforts are also required to cope with other circumstantial changes such as the establishment of International Nuclear Regulators Association (INRA)

  20. Safety issues related to the intermediate heat storage for the EU DEMO

    Energy Technology Data Exchange (ETDEWEB)

    Carpignano, Andrea [NEMO group, Dipartimento Energia, Politecnico di Torino, C.so Duca degli Abruzzi 24, 10129 Torino (Italy); Pinna, Tonio [ENEA, 00044 Frascati (Italy); Savoldi, Laura; Sobrero, Giulia; Uggenti, Anna Chiara [NEMO group, Dipartimento Energia, Politecnico di Torino, C.so Duca degli Abruzzi 24, 10129 Torino (Italy); Zanino, Roberto, E-mail: roberto.zanino@polito.it [NEMO group, Dipartimento Energia, Politecnico di Torino, C.so Duca degli Abruzzi 24, 10129 Torino (Italy)

    2016-11-01

    Highlights: • IHS affects only the PHTS and the BoP (Balance of Plant). • PIEs list does not change but IHS influences PIEs evolution. • Additional issues to be addressed in PIEs study due to the implementation of HIS. • No safety/operational major obstacles were found for IHS concept. - Abstract: The functional deviations able to compromise system safety in the EU DEMO Primary Heat Transfer System (PHTS) with intermediate heat storage (IHS) based on molten salts are identified and compared to the deviations identified with PHTS without IHS. The resulting safety issues for the Balance of Plant (BoP) have been taken into account. Functional Failure Mode and Effects Analysis (FFMEA) is used to highlight the Postulated Initiating Events (PIE) of incident/accident sequences and to provide some safety insights during the preliminary design. The architecture of the system with IHS does not introduce new PIE with respect to the case without IHS, but it modifies some of them. In particular the two Postulated Initiating Events that are affected by the presence of IHS are the LOCA in the tubes of the HX between primary and intermediate circuit and the loss of heat sink for the first wall or the breeding zone. In fact the IHS introduces some advantages concerning the stability of the secondary circuit, but some weaknesses are associated to the physical-chemical nature of molten salts, especially oxidizing power, corrosive nature and risk of solidification. These issues can be managed in the design by the introduction of new safety functions.

  1. The Sump Screen Clogging Issue in Belgium from the Standpoint of the Authorized Inspection Organisation (AIO) (AVN)

    International Nuclear Information System (INIS)

    Tombuyses, B.; Gelder, P. de; Vandewalle, A.

    2004-01-01

    All Belgian NPPs are PWRs. These PWRs have different containment designs and different sump designs. The four most recent units took RG 1.82 rev. 0 into account for the recirculation sump design. Several improvements were made in the framework of the first Periodic Safety Review to the oldest units such as enlargement of the sumps strainer in 1985, taking into account the requirements of RG 1.82 rev. 0. The problem of recirculation sump screen clogging due to the accumulation of insulation debris after an accident was also identified as a safety issue in the first Periodic Safety Review for Doel 3 and Tihange 2 and the second Periodic Safety Review for Doel 1 and 2 and Tihange 1, that started in the nineties. One of the purposes of the Periodic Safety Review being the justification of the safety level of the power plants with regard to the most recent safety rules and practices, the licensee was asked to review the characteristics of the sump strainers according to the revision 1 of the RG 1.82 (which referred to Nureg 0897 rev. 1). Later on, the Barsebaeck incident and the events leading to the NRC IN 93-34 showed that the conclusions of Nureg 0897 could underestimate the potential for loss of NPSH of the ECCS- and CSS-pumps. The issue was further examined and the AIO asked the licensee to continue efforts to recollect information. After issuance of the results from the parametric evaluation for pressurised water reactor recirculation sump performance (GSI-191) performed by LANL under NRC contract, the AIO asked the Belgian licensee in August 2002 to increase its efforts to investigate and to solve this issue. The requirements to the Licensee and the corresponding action plan as approved by the AIO are presented. Some significant lessons learned from the implementation of this action plan are discussed. (authors)

  2. Eminent radiological safety issues confronting the State of Hawaii

    International Nuclear Information System (INIS)

    Hashimoto, H.H.

    1984-01-01

    The State of Hawaii currently has over one hundred radioactive material use licenses. Nuclear Regulatory Commission licenses are primarily held by hospitals, industrial radiographers, and academic institutions. Complementing this, the State Department of Health regulates x-ray machines, radium, and has an emergency response role for accidents involving radioactive materials. The existing radiation protection program was created by piecemeal legislation. As a result, regulatory surveillance and actual control vary widely among the agencies. The State Legislature, in 1980, decided that action must be taken to set a clear state policy towards the use and disposal of nuclear materials. It was therefore recommended that the State of Hawaii Radiation Safety Advisory Committee be convened to assist the state in the evaluation of the issues. This report contains issue papers on radiation related topics addressed by the Radiation Safety Advisory Committe. Topics discussed include transportation, environmental monitoring, emergency response, and waste disposal. A survey of various radioactive sources identified medical applications as a category requiring stricter control. Selected chapters of the Hawaii Revised Statutes are also examined

  3. Food safety measurement issues. Way forward

    International Nuclear Information System (INIS)

    Venkatesh Iyengar

    2013-01-01

    Ensuring food safety (FS) is a persistent concern frequently faced by many countries. Safeguarding the quality of food that is fit for human consumption is the primary responsibility of the governmental regulatory agencies. For most part, agro-industries and food processors assume voluntary leadership for producing safe food. However, in the event of FS breach, the regulatory responsibility kicks into identify and rectify the situation. Notwithstanding whether it is the regulator or the industry that institutes the remedial action (e.g. improved hygiene and refined agricultural and manufacturing practices), the role of laboratory measurements is central in safeguarding the integrity of a functioning FS system. There are many analytical tools available to implement this task, such as validated analytical methods, natural matrix reference materials, field tested monitoring systems (proactive assessment) and effective surveillance systems (constant vigilance to prevent repeat safety violations). Way forward: existing FS tools are insufficient and should be strengthened with innovative approaches. Examples are: assembling swift intervention logistics to face FS breaches; rapid response systems including communication; robust metrology based measurement systems located at strategic locations in the country; and inter-disciplinary human resource to match the need for capacity development. These issues are discussed. (author)

  4. Identification of unresolved safety issues relating to nuclear power plants. Report to Congress

    International Nuclear Information System (INIS)

    1979-01-01

    The report describes the review undertaken over the last year that resulted in identifying 17 issues as Unresolved Safety Issues. In addition, the report provides specific discussions of why certain issues were not included. The report also provides a brief background discussion describing Section 210 of the Energy Reorganization Act and the NRC program for the resolution of generic issues described in NUREG-0410

  5. Materials-related issues in the safety and licensing of nuclear fusion facilities

    Science.gov (United States)

    Taylor, N.; Merrill, B.; Cadwallader, L.; Di Pace, L.; El-Guebaly, L.; Humrickhouse, P.; Panayotov, D.; Pinna, T.; Porfiri, M.-T.; Reyes, S.; Shimada, M.; Willms, S.

    2017-09-01

    Fusion power holds the promise of electricity production with a high degree of safety and low environmental impact. Favourable characteristics of fusion as an energy source provide the potential for this very good safety and environmental performance. But to fully realize the potential, attention must be paid in the design of a demonstration fusion power plant (DEMO) or a commercial power plant to minimize the radiological hazards. These hazards arise principally from the inventory of tritium and from materials that become activated by neutrons from the plasma. The confinement of these radioactive substances, and prevention of radiation exposure, are the primary goals of the safety approach for fusion, in order to minimize the potential for harm to personnel, the public, and the environment. The safety functions that are implemented in the design to achieve these goals are dependent on the performance of a range of materials. Degradation of the properties of materials can lead to challenges to key safety functions such as confinement. In this paper the principal types of material that have some role in safety are recalled. These either represent a potential source of hazard or contribute to the amelioration of hazards; in each case the related issues are reviewed. The resolution of these issues lead, in some instances, to requirements on materials specifications or to limits on their performance.

  6. The EXL experiment at FAIR and plans with the ESR at GSI

    International Nuclear Information System (INIS)

    Kalantar-Nayestanaki, N.

    2011-01-01

    In this contribution, the physics program of the EXL experiment at FAIR-NuSTAR along with its experimental setup will be briefly outlined. This experiment aims to study the structure and the dynamics of radioactive nuclei which collide with light ions in inverse kinematics. On the way to the final measurements, several measurements have been proposed at the existing ESR at GSI with the purpose of understanding the detection systems for EXL and obtaining the first physics results in this type of experiments in a storage ring.

  7. Safety performance indicators. Topical issues paper no. 5

    International Nuclear Information System (INIS)

    Dahlgren, K.; Lederman, L.; Szikszai, T.; Palomo, J.

    2001-01-01

    performance, they are just one of a larger set of tools including probabilistic safety assessment (PSA), regulatory inspection, quality assurance, external reviews and self-assessment needed to assess operational safety performance. The integration of information compiled from such evaluation tools yields the best results. Two areas of increasingly common interest are 'risk based' indicators, and 'safety culture' indicators. The key to managing the nuclear business today is to establish a high quality safety management system as well as developing a strong safety culture within the entire organization. 'The safety management system comprises those arrangements made by the organization for the management of safety in order to promote a strong safety culture and achieve good safety performance'. This definition, presented in INSAG-13, illustrates the close connection between 'safety management systems' and 'safety culture' and that they are in fact inseparable. To manage safety effectively you need a systematic approach and at the same time be aware of the effects of the approach on individual and collective human behaviour. This issue covers the following: development of safety performance indicators, indicator selection and use, recommended indicators, indicators collected from nuclear power plant initiatives, management of safety and safety culture, need and feasibility of an international system, plant management needs, regulatory use of safety performance indicators, public communication, and recommendations for priorities in future work

  8. Review of EU-APR Design for Selected Safety Issues of WERNA RHWG 2013

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Yong Soo; Kim, Ji Hwan [KHNP CRI, Daejeon (Korea, Republic of)

    2016-10-15

    Western European Nuclear Regulators' Association (WENRA) was established in 1999 to develop a harmonized approach to nuclear safety and radiation protection and their regulation. In 2013, the Reactor Harmonization Working Group (RHWG) of WENRA sets out the common positions on the seven selected key safety issues. This paper is to introduce the regulatory positions of WENRA RHWG 2013 and to review the compliance of the EU-APR with them. In this paper, we reviewed the compliance of the EUAPR regarding seven safety issues for new NPPs presented by WERNA RHWG in 2013. The EU-APR design fully complies with all WERNA RHWG safety issues since the following measures have been incorporated in it: - Successive five levels of DiD maintaining independence between different levels of DiD - Diverse design against multiple failure events such as ATWS, SBO, Loss of Ultimate Heat Sink, and Loss of Spent Fuel Pool Cooling - SAs dedicated mitigation systems to ensure the containment integrity during the SAs. - Practically eliminates accident sequences with a large or early release of radiological materials by diverse designs for multiple failure events, SAs dedicated mitigation system, and double containment design - Standard site parameters not lead to core melt accidents due to natural or man-made external hazards.

  9. Implementation of Safety and Security Issues in the Transport of Radioactive Material in Argentina

    International Nuclear Information System (INIS)

    López Vietri, J.; Elechosa, C.; Gerez Miranda, C.; Menossi, S.; Rodríguez Roldán, M.S.; Fernández, A.

    2016-01-01

    This paper is intended to describe implementation of safety and security issues in the transport of radioactive material by the Nuclear Regulatory Authority (in Spanish Autoridad Regulatoria Nuclear, ARN), which is the Competent Authority of Argentina in Safety, Security and Safeguards of radioactive and nuclear material. There are depicted main regulatory activities dealing with the mentioned issues, and relevant milestones of national regulatory standards and guidance applied, that are based on requirements and guides from IAEA. Interfaces between Safety and Security sections are most of the times complementary but sometimes conflictive, therefore the resolution of such conflicts and goals achieved during their implementation are also commented; as well as future joint planned activities between both sections of ARN as a way to provide safety and security without compromising one or the other. (author)

  10. GSI papers presented at the 3. European particle accelerator conference

    International Nuclear Information System (INIS)

    1992-04-01

    This report contains the articles presented by the GSI at the named conference. These concern an ion source for heavy ion synchrotron injection, a power amplifier, the new heavy ion injector of the UNILAC, the heavy ion synchrotron SIS, beam intensity measurements at the SIS, heavy ion storage rings, the performance and impedances and instability studies at the ESR, longitudinal space-charge effects in cooled bunched beams, the ERS electron cooling device, experiments with synthetic colored noise at the ESR, ion beams for heavy ion fusion research, a reactor driver concept for indirect drive, plasma lenses for heavy-ion beam focusing, synchrotrons for cancer therapy, and future accelerator projects in collaboration with industry. (orig.)

  11. Tune measurement at GSI SIS-18. Methods and applications

    Energy Technology Data Exchange (ETDEWEB)

    Singh, Rahul

    2014-05-15

    Two parallel tune measurement systems are installed at GSI SIS-18 based on different principles. The first is called the Tune, Orbit and POSition measurement system TOPOS. Its working principle involves direct digitization of BPM signals at 125 MSa/s, which is used for online bunch-by-bunch position calculation in FPGAs. In the course of this work, position calculation algorithms were developed and studied for real time implementation in the TOPOS FPGAs. The regression fit algorithm is found to be more efficient and robust in comparison to previously used weighted mean algorithm with the baseline restoration procedure. The second system is the Baseband Tune measurement system referred to as BBQ system. The operational principle of this system was conceived at the CERN Beam Instrumentation group and is based on direct diode detection. In the framework of this work, this system was optimized and brought into operation at GSI SIS-18. Front-end data from both systems are used to calculate the tune spectrum every 250-5000 beam revolutions or turns within SIS-18 based on the resolution requirement and the mode of operation. Advanced non-parametric spectrum estimation method like amplitude Capon estimator is compared to the conventional DFT based methods in terms of resolving power and computational requirements for the calculated spectrum. Further the TOPOS and BBQ systems are compared and characterized in terms of sensitivity, reliability and operational usage. The results from both systems are found to be consistent with each other and have their favoured regimes of operation. The effects on tune spectra obtained from both systems were studied with different types of excitations with excitation power levels up to 6 mW/Hz. These systems in association with other beam diagnostic devices at SIS-18 were used to conduct extensive experiments to understand the effect of high intensity beams on the tune spectrum. These careful measurements recorded all the relevant beam

  12. RBMK safety issues

    International Nuclear Information System (INIS)

    Weber, J.P.; Reichenbach, D.; Tscherkashow, J.M.

    1995-01-01

    On the basis of information and documents from the RBMK operation countries, the Western consortium mainly examined the two most modern plants, Ignalin-2 and Smolensk-3. The identification of numerous shortcomings, some of which had already been recongized by the participating Eastern organizations, resulted in some 300 specific recommendations to reactor designers, operators and licensing authorities. These recommendations are to be acted upon at once; only a small number did not meet with the approval of the Eastern partners. The safety review provided the Western consotrium with a profound insight into the design and safety of third-generation RBMK reactors; the Eastern partners were able to accumulate experience in working with Western safety philosophy. (orig.) [de

  13. Generic safety issues for nuclear power plants with pressurized heavy water reactors and measures for their resolution

    International Nuclear Information System (INIS)

    2007-06-01

    The IAEA Conference on The Safety of Nuclear Power: Strategy for the Future in 1991 was a milestone in nuclear safety. The objective of this conference was to review nuclear power safety issues for which achieving international consensus would be desirable, to address concerns on nuclear safety and to formulate recommendations for future actions by national and international authorities to advance nuclear safety to the highest level. Two of the important items addressed by this conference were ensuring and enhancing safety of operating plants and treatment of nuclear power plants built to earlier safety standards. Publications related to these two items, that have been issued subsequent to this conference, include: A Common Basis for Judging the Safety of Nuclear Power Plants Built to Earlier Standards, INSAG-8 (1995), the IAEA Safety Guide 50-SG-O12, Periodic Safety Review of Operational Nuclear Power Plants (1994) and an IAEA publication on the Safety Evaluation of Operating Nuclear Power Plants Built to Earlier Standards - A Common Basis for Judgement (1997). Some of the findings of the 1991 conference have not yet been fully addressed. An IAEA Symposium on Reviewing the Safety of Existing Nuclear Power Plants in 1996 showed that there is an urgent need for operating organizations and national authorities to review operating nuclear power plants which do not meet the high safety levels of the vast majority of plants and to undertake improvements, with assistance from the international community if required. Safety reviews of operating nuclear power plants take on added importance in the context of the Convention on Nuclear Safety and its implementation. To perform safety reviews and to reassess the safety of operating nuclear power plants in a uniform manner, it is imperative to have an internationally accepted reference. Existing guidance needs to be complemented by a list of safety issues which have been encountered and resolved in other plants and which can

  14. Modeling issues associated with production reactor safety assessment

    International Nuclear Information System (INIS)

    Stack, D.W.; Thomas, W.R.

    1990-01-01

    This paper describes several Probabilistic Safety Assessment (PSA) modeling issues that are related to the unique design and operation of the production reactors. The identification of initiating events and determination of a set of success criteria for the production reactors is of concern because of their unique design. The modeling of accident recovery must take into account the unique operation of these reactors. Finally, a more thorough search and evaluation of common-cause events is required to account for combinations of unique design features and operation that might otherwise not be included in the PSA. It is expected that most of these modeling issues also would be encountered when modeling some of the other more unique reactor and nonreactor facilities that are part of the DOE nuclear materials production complex. 9 refs., 2 figs

  15. Key issues on safety design basis selection and safety assessment

    International Nuclear Information System (INIS)

    An, S.; Togo, Y.

    1976-01-01

    In current fast reactor design in Japan, four design accident conditions and four design seismic conditions are adopted as the design base classifications. These are classified by the considerations on both likelihood of occurrence and the severeness of the consequences. There are several major problem areas in safety design consideration such as core accident problems which include fuel sodium interaction, fuel failure propagation and residual decay heat removal, and decay heat removal systems problems which is more or less the problem of selection of appropriate system and of assurance of high reliability of the system. In view of licensing, two kinds of accidents are postulated in evaluating the adequacy of a reactor site. The one is the ''major accident'' which is the accident to give most severe radiation hazard to the public from technical point of view. The other is the ''hypothetical accident'', induced public accident of which is severer than that of major accident. While the concept of the former is rather unique to Japanese licensing, the latter is almost equivalent to design base hypothetical accident of the US practice. In this paper, design bases selections, key safety issues and some of the licensing considerations in Japan are described

  16. Occupational health and safety issues among nurses in the Philippines.

    Science.gov (United States)

    de Castro, A B; Cabrera, Suzanne L; Gee, Gilbert C; Fujishiro, Kaori; Tagalog, Eularito A

    2009-04-01

    Nursing is a hazardous occupation in the United States, but little is known about workplace health and safety issues facing the nursing work force in the Philippines. In this article, work-related problems among a sample of nurses in the Philippines are described. Cross-sectional data were collected through a self-administered survey during the Philippine Nurses Association 2007 convention. Measures included four categories: work-related demographics, occupational injury/illness, reporting behavior, and safety concerns. Approximately 40% of nurses had experienced at least one injury or illness in the past year, and 80% had experienced back pain. Most who had an injury did not report it. The top ranking concerns were stress and overwork. Filipino nurses encounter considerable health and safety concerns that are similar to those encountered by nurses in other countries. Future research should examine the work organization factors that contribute to these concerns and strengthen policies to promote health and safety.

  17. Occupational Health and Safety Issues Among Nurses in the Philippines

    Science.gov (United States)

    de Castro, A. B.; Cabrera, Suzanne L.; Gee, Gilbert C.; Fujishiro, Kaori; Tagalog, Eularito A.

    2009-01-01

    Nursing is a hazardous occupation in the United States, but little is known about workplace health and safety issues facing the nursing work force in the Philippines. In this article, work-related problems among a sample of nurses in the Philippines are described. Cross-sectional data were collected through a self-administered survey during the Philippine Nurses Association 2007 convention. Measures included four categories: work-related demographics, occupational injury/illness, reporting behavior, and safety concerns. Approximately 40% of nurses had experienced at least one injury or illness in the past year, and 80% had experienced back pain. Most who had an injury did not report it. The top ranking concerns were stress and overwork. Filipino nurses encounter considerable health and safety concerns that are similar to those encountered by nurses in other countries. Future research should examine the work organization factors that contribute to these concerns and strengthen policies to promote health and safety. PMID:19438081

  18. The E052 - GSI Experiment, Deceleration of highly charged ions by crystal channeling. (Technical notes)

    International Nuclear Information System (INIS)

    Kirsch, R.

    2003-01-01

    The report on the E052 - GSI Experiment, devoted to 'Deceleration of highly charged ions by crystal channeling' present the technical notes and the status of this experiment in 2003. The report contains 13 sections and two annexes. The sections deal with the following issues: 1. File system of the 'PC monitor' for E052 - GSI Experiment in 2003; 2. Parameters of the 'PC monitor' file system; 3. Operation of the two PCs; 3.1. Layout of goniometer remote control; 3.2. 'PC motors' side by the beam hall; 3.3. RS232 connection cabling; 3.4. RS232 configuration on the COM1 ports of the two PCs; 4. Motor connection; 4.1. SubD-25 acquisition PC monitor arm on 'COM1'; 4.2. Motors step by step feeding side SubD-25 on 'COM1'; 4.3. Distribution of digital step by step control signals; 4.5. Upper an lower goniometer connection; 4.6. Rotation and inclination outer goniometer connection; 4.7. Ultra vacuum inner rotation and inclination connection; 5. Motor characteristics; 5.1. Upstream and downstream; 5.2. Rotation; 5.3 Inclination; 5.4. Feedings; 6. Goniometer in-beam positioning; 6.1. Height fine motor positioning; 6.2. Side manual positioning; 7. Goniometer movements; 8. Crystals and electron detection; 8.1. General layout; 8.2. 1 μm Si(100) crystal; 8.3. 33 μm Si(100) crystal; 8.4. Crystal mounting; 8.5. Electron detection; 9. Reference laser positioning of angular movements; 10. Beam track and collimators upstream the target; 11. User manual - Monitoring programme; 11.Start scanning program (GSIscan.exe); 11.2. SCANNING the crystal (Scan Control window); 11.3. MOVING THE GONIOMETER MANUALY (goniometer control window); 11.4. USING THE COUNTERS (counter display window); 11.5. MULTISCALER PLOT DISPLAY; 11.6. SELECT ACTIVE PLOT; 11.7. CURSORS; 11.8. STATISTICS; 11.9. Y SCALE change; 11.10. PLOT view and hide counter; 11.11. SAVE multiscaler spectra; 11.12. PRINT plot; 12. Simplified acquisition electronic setup; 13. The 'PC motors' software; 13.1. The code structure; 13

  19. Research of beryllium safety issues

    International Nuclear Information System (INIS)

    Longhurst, G.R.; Anderl, R.A.; Dolan, T.J.; Hankins, M.R.; Pawelko, R.J.

    1993-01-01

    Beryllium has been identified as a leading contender for the plasma-facing material in ITER. Its use has some obvious advantages, but there are also a number of safety concerns associated with it. The Idaho National Engineering Laboratory (INEL) has undertaken a number of studies to help resolve some of these issues. One issue is the response of beryllium to neutron irradiation. We have tested samples irradiated in the Advanced Test Reactor (ATR) and are currently preparing to make measurements of the change in mechanical properties of beryllium samples irradiated at elevated temperatures in the Fast Flux Test Facility (FFTF) and the Experimental Breeder Reactor II (EBR-II) at the INEL. Mechanical tests will be conducted at the irradiation temperatures of 375-550 C. Other experiments address permeation and retention of implanted tritium in plasma-sprayed beryllium. In one test the porosity of the material allowed 0.12% of implanted ions and 0.17% of atoms from background gas pressure to pass through the foil with essentially no delay. For comparison, similar tests on fully dense hot-rolled, vacuum melted or sintered powder foils of high purity beryllium showed only 0.001% of implanting ions to pass through the foil, and then only after a delay of several hours. None of the molecular gas appeared to permeate these latter targets. An implication is that plasma-sprayed beryllium may substantially enhance recycling of tritium to the plasma provided it is affixed to a relatively impermeable substrate. (orig.)

  20. Team of experts concludes review of safety issues at Temelin

    International Nuclear Information System (INIS)

    2001-01-01

    Full text: At the request of the Czech Government, the International Atomic Energy Agency (IAEA) assembled a team of national experts from Bulgaria, France, Germany, Spain, and the United Kingdom, with an observer from Austria, to review safety issues at the Temelin power plant that were identified in 1996 as relevant to reactors of the generic Temelin design (WWER-1000/320 type). Following a detailed on-site review from 18 to 23 November 2001, the experts concluded that most identified issues had been addressed and resolved. Work is continuing on the few remaining issues. These issues, however, are not judged by them to be significant and would not from the experts' standpoint preclude the safe operation of the Temelin nuclear power plant. The final report of the team of experts will be available to the Czech Government in one month's time. (author)

  1. Program plan for evaluation of the Ferrocyanide Waste Tank safety issue at the Hanford Site

    International Nuclear Information System (INIS)

    Borsheim, G.L.; Meacham, J.E.; Cash, R.J.; Dukelow, G.T.

    1994-03-01

    This document describes the background, priorities, strategy and logic, and task descriptions for the Ferrocyanide Waste Tank Safety Program. The Ferrocyanide Safety Program was established in 1990 to provide resolution of a major safety issue identified for 24 high-level radioactive waste tanks at the Hanford Site

  2. Confined Site Construction: A qualitative investigation of critical issues affecting management of Health and Safety

    OpenAIRE

    Spillane, John P.; Oyedele, Lukumon O.; Von Meding, Jason; Konanahalli, Ashwini; Jaiyeoba, Babatunde E.; Tijani, Iyabo K.

    2011-01-01

    The construction industry is inherently risky, with a significant number of accidents and disasters occurring, particularly on confined construction sites. This research investigates and identifies the various issues affecting successful management of health and safety in confined construction sites. The rationale is that identifying the issues would assist the management of health and safety particularly in inner city centres which are mostly confined sites. Using empiricism epistemology, th...

  3. Resolution of thermal-hydraulic safety and licensing issues for the system 80+trademark design

    International Nuclear Information System (INIS)

    Carpentino, S.E.; Ritterbusch, S.E.; Schneider, R.E.

    1995-01-01

    The System 80+ trademark Standard Design is an evolutionary Advanced Light Water Reactor (ALWR) with a generating capacity of 3931 MWt (1350 MWe). The Final Design Approval (FDA) for this design was issued by the Nuclear Regulatory Commission (NRC) in July 1994. The design certification by the NRC is anticipated by the end of 1995 or early 1996. NRC review of the System 80+ design has involved several new safety issues never before addressed in a regulatory atmosphere. In addition, conformance with the Electric Power Research Institute (EPRI) ALWR Utility Requirements Document (URD) required that the System 80+ plant address nuclear industry concerns with regard to design, construction, operation and maintenance of nuclear power plants. A large number of these issues/concerns deals with previously unresolved generic thermal-hydraulic safety issues and severe accident prevention and mitigation. This paper discusses the thermal-hydraulic analyses and evaluations performed for the System 80+ design to resolve safety and licensing issues relevant to both the Nuclear Stream Supply System (NSSS) and containment designs. For the NSSS design, the Safety Depressurization System mitigation capability and resolution of the boron dilution concern are described. Examples of containment design issues dealing with containment shell strength, robustness of the reactor cavity walls and hydrogen mixing under severe accident conditions are also provided. Finally, the overall approach used in the application of NRC's new (NUREG-1465) radiological source term for System 80+ evaluation is described. The robustness of the System 80+ containment design to withstand severe accident consequences was demonstrated through detailed thermal-hydraulic analyses and evaluations. This advanced design to shown to meet NRC severe accident policy goals and ALWR URD requirements without any special design features and unnecessary costs

  4. Upgrade of the GSI-Unilac as a FAIR high current injector

    Energy Technology Data Exchange (ETDEWEB)

    Haehnel, Hendrik [Institut fuer Angewandte Physik, Goethe Universitaet Frankfurt (Germany)

    2016-07-01

    The existing UNIversal Linear Accelerator (UNILAC) at GSI will serve as ion and dedicated uranium ion injector for the Facility for Antiproton and Ion Research (FAIR). For nominal FAIR operation, 15 emA of Uranium 28+ at low emittances have to be injected by multiturn-injection into FAIR. To meet these requirements and to ensure reliable operation, the UNILAC will undergo a significant upgrade process. Upgrade measures concerning key accelerator components are described and a main focus is put on a replacement of the 54m Alvarez-section by a compact IH-DTL. This will open new options for future injection schemes into SIS100.

  5. NASA SPoRT Modeling and Data Assimilation Research and Transition Activities Using WRF, LIS and GSI

    Science.gov (United States)

    Case, Jonathan L.; Blankenship, Clay B.; Zavodsky, Bradley T.; Srikishen, Jayanthi; Berndt, Emily B.

    2014-01-01

    weather research and forecasting ===== The NASA Short-term Prediction Research and Transition (SPoRT) program has numerous modeling and data assimilation (DA) activities in which the WRF model is a key component. SPoRT generates realtime, research satellite products from the MODIS and VIIRS instruments, making the data available to NOAA/NWS partners running the WRF/EMS, including: (1) 2-km northwestern-hemispheric SST composite, (2) daily, MODIS green vegetation fraction (GVF) over CONUS, and (3) NASA Land Information System (LIS) runs of the Noah LSM over the southeastern CONUS. Each of these datasets have been utilized by specific SPoRT partners in local EMS model runs, with select offices evaluating the impacts using a set of automated scripts developed by SPoRT that manage data acquisition and run the NCAR Model Evaluation Tools verification package. SPoRT is engaged in DA research with the Gridpoint Statistical Interpolation (GSI) and Ensemble Kalman Filter in LIS for soil moisture DA. Ongoing DA projects using GSI include comparing the impacts of assimilating Atmospheric Infrared Sounder (AIRS) radiances versus retrieved profiles, and an analysis of extra-tropical cyclones with intense non-convective winds. As part of its Early Adopter activities for the NASA Soil Moisture Active Passive (SMAP) mission, SPoRT is conducting bias correction and soil moisture DA within LIS to improve simulations using the NASA Unified-WRF (NU-WRF) for both the European Space Agency's Soil Moisture Ocean Salinity and upcoming SMAP mission data. SPoRT has also incorporated real-time global GVF data into LIS and WRF from the VIIRS product being developed by NOAA/NESDIS. This poster will highlight the research and transition activities SPoRT conducts using WRF, NU-WRF, EMS, LIS, and GSI.

  6. Regulatory analysis for resolution of USI [Unresolved Safety Issue] A-47

    International Nuclear Information System (INIS)

    Szukiewicz, A.J.

    1989-07-01

    This report presents a summary of the regulatory analysis conducted by the US Nuclear Regulatory Commission staff to evaluate the value/impact of alternatives for the resolution of Unresolved Safety Issue A-47, ''Safety Implications of Control Systems.'' The NRC staff's resolution presented herein is based on these analyses and on the technical findings and conclusions presented in NUREG-1217, the companion document to this report. The staff has concluded that certain actions should be taken to improve safety in light-water reactor plants. The staff recommended that certain plants improve their control systems to preclude reactor vessel/steam generator overfill events and to prevent steam generator dryout, modify their technical specifications to verify operability of such systems, and modify selected emergency procedures to ensure safe shutdown of the plant following a small-break loss-of-coolant accident. This report was issued as a draft for public comment on May 27, 1988. As a result of the public comments received, this report was revised. The NRC staff's responses to and resolution of the public comments are included as Appendix C to the final report, NUREG-1217

  7. The GSI plans for an international accelerator facility for beams of ions and antiprotons

    International Nuclear Information System (INIS)

    Suemmerer, K.

    2003-01-01

    GSI proposes to build a next-generation facility for research with relativistic beams of ions and antiprotons. This facility allows a broad range of topics in nuclear and astrophysics, plasma and atomic physics to be addressed. The topic most interesting in the context of this conference is physics with high-intensity beams of exotic nuclei. In addition, a short overview of the opportunities in the other fields of nuclear physics is given

  8. Editorial: emerging issues in sociotechnical systems thinking and workplace safety.

    Science.gov (United States)

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

    2015-01-01

    The burden of on-the-job accidents and fatalities and the harm of associated human suffering continue to present an important challenge for safety researchers and practitioners. While significant improvements have been achieved in recent decades, the workplace accident rate remains unacceptably high. This has spurred interest in the development of novel research approaches, with particular interest in the systemic influences of social/organisational and technological factors. In response, the Hopkinton Conference on Sociotechnical Systems and Safety was organised to assess the current state of knowledge in the area and to identify research priorities. Over the course of several months prior to the conference, leading international experts drafted collaborative, state-of-the-art reviews covering various aspects of sociotechnical systems and safety. These papers, presented in this special issue, cover topics ranging from the identification of key concepts and definitions to sociotechnical characteristics of safe and unsafe organisations. This paper provides an overview of the conference and introduces key themes and topics. Sociotechnical approaches to workplace safety are intended to draw practitioners' attention to the critical influence that systemic social/organisational and technological factors exert on safety-relevant outcomes. This paper introduces major themes addressed in the Hopkinton Conference within the context of current workplace safety research and practice challenges.

  9. Recent progress in multichamber deposition of high-quality amorphous silicon solar cells on planar and compound curved substrates at GSI

    Energy Technology Data Exchange (ETDEWEB)

    Schropp, R.E.I.; Roedern, B. von; Klose, P.; Hollingsworth, R.E.; Xi, J.; Cueto, J. del; Chatham, H.; Bhat, P.K. (Glasstech Solar, Inc. (GSI), Wheat Ridge, CO (USA))

    1989-10-15

    We present recent advances obtained at GSI in scaling-up multichamber fabrication of solar cells. We have successfully adopted the multichamber approach in the development of large-area compound curved semitransparent modules. For this application, a new semitransparent electrode was developed, together with an innovative three-dimensional laser patterning technique. A fully automated 1.5 MW annual production line with a ''glass-in-panel-out'' approach has been completed for the Government of India, and another 3 MW plant is presently under construction. GSI's research effort using its multichamber R and D system has achieved single-junction conversion efficiencies of 11.3% at low intrinsic layer deposition rates and of 9.7% at a rate of 18 A s{sup -1}. (orig.).

  10. Issues regarding Risk Effect Analysis of Digitalized Safety Systems and Main Risk Contributors

    International Nuclear Information System (INIS)

    Kang, Hyun Gook; Jang, Seung-Cheol

    2008-01-01

    Risk factors of safety-critical digital systems affect overall plant risk. In order to assess this risk effect, a risk model of a digitalized safety system is required. This article aims to provide an overview of the issues when developing a risk model and demonstrate their effect on plant risk quantitatively. Research activities in Korea for addressing these various issues, such as the software failure probability and the fault coverage of self monitoring mechanism are also described. The main risk contributors related to the digitalized safety system were determined in a quantitative manner. Reactor protection system and engineered safety feature component control system designed as part of the Korean Nuclear I and C System project are used as example systems. Fault-tree models were developed to assess the failure probability of a system function which is designed to generate an automated signal for actuating both of the reactor trip and the complicated accident-mitigation actions. The developed fault trees were combined with a plant risk model to evaluate the effect of a digitalized system's failure on the plant risk. (authors)

  11. GSI Quantitative Parameters: Preoperative Diagnosis of Metastasis Lymph Nodes in Lung Cancer

    Directory of Open Access Journals (Sweden)

    Fengfeng YANG

    2016-11-01

    Full Text Available Background and objective Mediastinal involvement in lung cancer is an important prognostic factor affecting survival, and accurate staging of the mediastinum lymph node correctly identifies patients who can benefit the most from surgery. The aim of this study is to investigate the value of dual-energy spectral computed tomography (DEsCT imaging in differentiating metastatic from non-metastatic lymph nodes in lung cancer. Methods Forty-eight patients with non-small cell lung cancer (NSCLC underwent arterial (AP and portal venous (PP phase contrast-enhanced DEsCT imaging followed by surgical treatment. gemstone spectral imaging (GSI data images were reconstructed and transmitted to an offline workstation. GSI quantitative parameters, including lymph-node size, CT value, IC, water concentration, and spectral curve. Differences were tested for statistical significance using the two-sample t test. ROC analysis was performed to assess diagnostic performance. Results The mean short-axis diameter of metastatic LNs, slope of the spectral Hounsfield unit curve (λHU, normalized iodine concentration measured during, and both AP and PP were significantly higher in metastatic lymph node than that in benign lymph nodes. The best parameter for detecting metastatic lymph nodes was AP λHU when a threshold λHU of 2.75 was used; sensitivity, specificity, and accuracy were 88.2%, 88.4%, and 87.0%, respectively. Conclusion Quantitative assessment with gemstone spectral imaging quantitative parameters showed higher accuracy than the qualitative assessment of conventional CT imaging features for the preoperative diagnosis of metastatic lymph nodes in patients with lung cancer.

  12. An Evaluation Methodology Development and Application Process for Severe Accident Safety Issue Resolution

    Directory of Open Access Journals (Sweden)

    Robert P. Martin

    2012-01-01

    Full Text Available A general evaluation methodology development and application process (EMDAP paradigm is described for the resolution of severe accident safety issues. For the broader objective of complete and comprehensive design validation, severe accident safety issues are resolved by demonstrating comprehensive severe-accident-related engineering through applicable testing programs, process studies demonstrating certain deterministic elements, probabilistic risk assessment, and severe accident management guidelines. The basic framework described in this paper extends the top-down, bottom-up strategy described in the U.S Nuclear Regulatory Commission Regulatory Guide 1.203 to severe accident evaluations addressing U.S. NRC expectation for plant design certification applications.

  13. High level issues in reliability quantification of safety-critical software

    International Nuclear Information System (INIS)

    Kim, Man Cheol

    2012-01-01

    For the purpose of developing a consensus method for the reliability assessment of safety-critical digital instrumentation and control systems in nuclear power plants, several high level issues in reliability assessment of the safety-critical software based on Bayesian belief network modeling and statistical testing are discussed. Related to the Bayesian belief network modeling, the relation between the assessment approach and the sources of evidence, the relation between qualitative evidence and quantitative evidence, how to consider qualitative evidence, and the cause-consequence relation are discussed. Related to the statistical testing, the need of the consideration of context-specific software failure probabilities and the inability to perform a huge number of tests in the real world are discussed. The discussions in this paper are expected to provide a common basis for future discussions on the reliability assessment of safety-critical software. (author)

  14. Review of criticality safety and shielding analysis issues for transportation packages

    International Nuclear Information System (INIS)

    Parks, C.V.; Broadhead, B.L.

    1995-01-01

    The staff of the Nuclear Engineering Applications Section (NEAS) at Oak Ridge National Laboratory (ORNL) have been involved for over 25 years with the development and application of computational tools for use in analyzing the criticality safety and shielding features of transportation packages carrying radioactive material (RAM). The majority of the computational tools developed by ORNL/NEAS have been included within the SCALE modular code system (SCALE 1995). This code system has been used throughout the world for the evaluation of nuclear facility and package designs. With this development and application experience as a basis, this paper highlights a number of criticality safety and shielding analysis issues that confront the designer and reviewer of a new RAM package. Changes in the types and quantities of material that need to be shipped will keep these issues before the technical community and provide challenges to future package design and certification

  15. The SIS-ESR project of GSI

    International Nuclear Information System (INIS)

    Kienle, P.

    1985-05-01

    During the last years GSI developed plans for future accelerators and experimental facilities with the intention to extend heavy ion research in a wide scope to higher energies and into new fields of research using novel techniques for acceleration, accumulation, storage and phase space density increase of heavy ion beams up to 238 U. The prime goals of this development plan using as a first step a synchrotron acceleration ring connected with an accumulator-, storage-, cooling- and experimental ring are the following: 1. Provide completely stripped heavy ion beams up to U 92+ with the highest phase space densities using various cooling techniques in a storage ring. 2. Provide radioactive heavy ion beams by accumulation, storage and cooling of fragmentation or fission products from beams of the synchrotron. 3. Provide facilities for internal target experiments using simultaneously cooled circulating beams. 4. Provide two merging beams in the storage ring with well defineable collision energies up to the Coulomb barrier of the heaviest ions like U 92+ in order to study atomic collision processes in high Coulomb fields with both nuclei highly ionized. 5. Provide a beam of heavy ions up to U 92+ with best phase space density for further acceleration and collisions in superconducting collider rings at very high c.m. energies (>20 GeV/u) and as high as possible luminosities. (orig.)

  16. Safety issues of tooth whitening using peroxide-based materials.

    Science.gov (United States)

    Li, Y; Greenwall, L

    2013-07-01

    In-office tooth whitening using hydrogen peroxide (H₂O₂) has been practised in dentistry without significant safety concerns for more than a century. While few disputes exist regarding the efficacy of peroxide-based at-home whitening since its first introduction in 1989, its safety has been the cause of controversy and concern. This article reviews and discusses safety issues of tooth whitening using peroxide-based materials, including biological properties and toxicology of H₂O₂, use of chlorine dioxide, safety studies on tooth whitening, and clinical considerations of its use. Data accumulated during the last two decades demonstrate that, when used properly, peroxide-based tooth whitening is safe and effective. The most commonly seen side effects are tooth sensitivity and gingival irritation, which are usually mild to moderate and transient. So far there is no evidence of significant health risks associated with tooth whitening; however, potential adverse effects can occur with inappropriate application, abuse, or the use of inappropriate whitening products. With the knowledge on peroxide-based whitening materials and the recognition of potential adverse effects associated with the procedure, dental professionals are able to formulate an effective and safe tooth whitening regimen for individual patients to achieve maximal benefits while minimising potential risks.

  17. Safety Culture and Issue in the Malaysian Manufacturing Sector

    Directory of Open Access Journals (Sweden)

    Ali Danish

    2017-01-01

    Full Text Available . This paper highlights the Safety culture and issue in the Malaysian Manufacturing Sector and emphasis the high occupational accidents due to lack of safety culture and non-compliance of the requirements of Occupational Safety and Health Act 1994. The aim of this study is to review the occupational accidents occurrence in the Malaysia workplace since 2012-2016. Malaysia aimed to reduce the occupational accidents, the results show by DOSH increase that Occupational Noise Induced Hearing Loss 83.7%, occupational musculoskeletal diseases, 4.4% and occupational lung diseases 2.3%. But the as per the record from DOSH that in last 5-Years, the increment in the fatal accidents by Average 26%, Permanent Disability by Average 71% and Non-Permanent Disability by 64 % are investigated only in Manufacturing Industries. The government must show their high interest on such a vulnerable employees to accomplish the above aim. This step will be helpful for planning to reduce the accidents in workplaces and it will also detect the prevention for the future accidents.

  18. Contrast media. Safety issues and ESUR guidelines. 3. ed.

    International Nuclear Information System (INIS)

    Thomsen, Henrik S.; Webb, Judith A.W.

    2014-01-01

    Fully updates the previous edition and includes new chapters on various complex topics. Represents a unique and unparalleled source of information on the many safety issues relating to different contrast media. Includes chapters on acute and delayed non-renal adverse reactions and on renal adverse reactions. Presented in a handy, easy-to-use format. In 1994 the European Society of Urogenital Radiology (ESUR) set up a committee to consider the safety of contrast media used for diagnostic imaging. Subsequently the committee questioned ESUR members, reviewed the literature, proposed guidelines, and discussed these proposals with participants at the annual symposia of the society. The end result of this work was the successful first edition of this book, published in 2006, which was followed by an equally successful second edition in 2009. This third edition not only fully updates the previous edition, but also includes new chapters on complex topics such as use of contrast media in children and practical aspects of off-label contrast media use. The authorship includes members, past members, and non-members of the Contrast Media Safety Committee.

  19. Special Issue. 5th Meeting on Technology and Safety

    International Nuclear Information System (INIS)

    Kusakabe, Masashi; Kumagaya, Tadafusa; Minohara, Shinichi

    2010-01-01

    The documents in this Special Issue are the representative reports of achievements presented in the National Institute of Radiological Sciences (NIRS) 5th Meeting on Technology and Safety held on March 17, 2010. Personnel and investigators of NIRS and related companies gave their achievements by 19 oral and 31 poster presentations in fields of [IAR] irradiation (2 topics), accelerator/radiometry (9 topics), [EA] experimental animals (25 topics), [SM] safety management of facilities (5 topics), computer network system (4 topics), experimental instrument (1 topic), molecular imaging (2 topics) and others (2 topics). The Issue contains, as well as introductory and ending remarks, following 12 topics: [IAR] Working report of patient positioning system for radiotherapy with use of X-ray flat panel detector; Status of maintenance and management of facilities and equipments in Research center for Radiation Emergency Medicine; [EA] Past, present and future of mouse breeding in NIRS; Breeding of marmoset in NIRS/How can we have a bouncing marmoset baby?; Establishment of a genotyping method of transformed genes in transgenic mouse/genome walking method; Genetic monitoring system of mice by micro-satellite marker and its application in NIRS; Verification of sorting precision of FACSAria (Becton Dickinson and Co.), a highly sensitive, rapid sorting apparatus of cells/for precise sorting; Proposal of a task-solution workflow to determine the animal features for molecular imaging studies; [SM] Toward the introduction of Occupational Safety and Health Management System in NIRS; Use of unsealed radioisotopes less than the lower limit outside the legal control area; Arrangement of managing and supporting system for clinical studies; and Rearrangement of working system of personnel affairs. (T.T.)

  20. An approach to maintenance optimization where safety issues are important

    International Nuclear Information System (INIS)

    Vatn, Jorn; Aven, Terje

    2010-01-01

    The starting point for this paper is a traditional approach to maintenance optimization where an object function is used for optimizing maintenance intervals. The object function reflects maintenance cost, cost of loss of production/services, as well as safety costs, and is based on a classical cost-benefit analysis approach where a value of prevented fatality (VPF) is used to weight the importance of safety. However, the rationale for such an approach could be questioned. What is the meaning of such a VPF figure, and is it sufficient to reflect the importance of safety by calculating the expected fatality loss VPF and potential loss of lives (PLL) as being done in the cost-benefit analyses? Should the VPF be the same number for all type of accidents, or should it be increased in case of multiple fatality accidents to reflect gross accident aversion? In this paper, these issues are discussed. We conclude that we have to see beyond the expected values in situations with high safety impacts. A framework is presented which opens up for a broader decision basis, covering considerations on the potential for gross accidents, the type of uncertainties and lack of knowledge of important risk influencing factors. Decisions with a high safety impact are moved from the maintenance department to the 'Safety Board' for a broader discussion. In this way, we avoid that the object function is used in a mechanical way to optimize the maintenance and important safety-related decisions are made implicit and outside the normal arena for safety decisions, e.g. outside the traditional 'Safety Board'. A case study from the Norwegian railways is used to illustrate the discussions.

  1. An approach to maintenance optimization where safety issues are important

    Energy Technology Data Exchange (ETDEWEB)

    Vatn, Jorn, E-mail: jorn.vatn@ntnu.n [NTNU, Production and Quality Engineering, 7491 Trondheim (Norway); Aven, Terje [University of Stavanger (Norway)

    2010-01-15

    The starting point for this paper is a traditional approach to maintenance optimization where an object function is used for optimizing maintenance intervals. The object function reflects maintenance cost, cost of loss of production/services, as well as safety costs, and is based on a classical cost-benefit analysis approach where a value of prevented fatality (VPF) is used to weight the importance of safety. However, the rationale for such an approach could be questioned. What is the meaning of such a VPF figure, and is it sufficient to reflect the importance of safety by calculating the expected fatality loss VPF and potential loss of lives (PLL) as being done in the cost-benefit analyses? Should the VPF be the same number for all type of accidents, or should it be increased in case of multiple fatality accidents to reflect gross accident aversion? In this paper, these issues are discussed. We conclude that we have to see beyond the expected values in situations with high safety impacts. A framework is presented which opens up for a broader decision basis, covering considerations on the potential for gross accidents, the type of uncertainties and lack of knowledge of important risk influencing factors. Decisions with a high safety impact are moved from the maintenance department to the 'Safety Board' for a broader discussion. In this way, we avoid that the object function is used in a mechanical way to optimize the maintenance and important safety-related decisions are made implicit and outside the normal arena for safety decisions, e.g. outside the traditional 'Safety Board'. A case study from the Norwegian railways is used to illustrate the discussions.

  2. Highly charged ions at rest: The HITRAP project at GSI

    International Nuclear Information System (INIS)

    Herfurth, F.; Beier, T.; Dahl, L.; Eliseev, S.; Heinz, S.; Kester, O.; Kluge, H.-J.; Kozhuharov, C.; Maero, G.; Quint, W.

    2005-01-01

    A decelerator will be installed at GSI in order to provide and study bare heavy nuclei or heavy nuclei with only few electrons at very low energies or even at rest. Highly-charged ions will be produced by stripping at relativistic energies. After electron cooling and deceleration in the Experimental Storage Ring the ions are ejected out of the storage ring at 4 MeV/u and further decelerated in a combination of an IH and RFQ structure. Finally, they are injected into a Penning trap where the ions are cooled to 4 K. From here, the ions can be transferred in a quasi dc or in a pulsed mode to different experimental setups. This article describes the technical concepts of this project as well as planned key experiments

  3. International conference on topical issues in nuclear installation safety: Continuous improvement of nuclear safety in a changing world. Book of contributed papers

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2004-07-01

    Papers presented at this conference where devoted to the following NPP safety related topical issues: Changing environments - coping with diversity and globalisation; Operating experience - managing changes effectively; Regulatory management systems - adapting to changes in the environment; Long term operations - maintaining safety margins while extending plant lifetime.

  4. Safety and Regulatory Issues of the Thorium Fuel Cycle

    Energy Technology Data Exchange (ETDEWEB)

    Ade, Brian [ORNL; Worrall, Andrew [ORNL; Powers, Jeffrey [ORNL; Bowman, Steve [ORNL; Flanagan, George [ORNL; Gehin, Jess [ORNL

    2014-02-01

    Thorium has been widely considered an alternative to uranium fuel because of its relatively large natural abundance and its ability to breed fissile fuel (233U) from natural thorium (232Th). Possible scenarios for using thorium in the nuclear fuel cycle include use in different nuclear reactor types (light water, high temperature gas cooled, fast spectrum sodium, molten salt, etc.), advanced accelerator-driven systems, or even fission-fusion hybrid systems. The most likely near-term application of thorium in the United States is in currently operating light water reactors (LWRs). This use is primarily based on concepts that mix thorium with uranium (UO2 + ThO2), add fertile thorium (ThO2) fuel pins to LWR fuel assemblies, or use mixed plutonium and thorium (PuO2 + ThO2) fuel assemblies. The addition of thorium to currently operating LWRs would result in a number of different phenomenological impacts on the nuclear fuel. Thorium and its irradiation products have nuclear characteristics that are different from those of uranium. In addition, ThO2, alone or mixed with UO2 fuel, leads to different chemical and physical properties of the fuel. These aspects are key to reactor safety-related issues. The primary objectives of this report are to summarize historical, current, and proposed uses of thorium in nuclear reactors; provide some important properties of thorium fuel; perform qualitative and quantitative evaluations of both in-reactor and out-of-reactor safety issues and requirements specific to a thorium-based fuel cycle for current LWR reactor designs; and identify key knowledge gaps and technical issues that need to be addressed for the licensing of thorium LWR fuel in the United States.

  5. Assessment of policy issues in nuclear safety regulation according to circumstantial changes

    Energy Technology Data Exchange (ETDEWEB)

    Chang, Soon Heung; Lee, Byong Ho; Baek, Woon Pil; Lee, Seong Wook; Choi, Seong Soo; Roh, Chang Hyun; Lee, Kwang Gu [Korea Advanced Institute of Scienc and Technology, Taejon (Korea, Republic of)

    1998-03-15

    The objective of the work is to assess various issues in nuclear safety regulation in consideration of circumstantial changes. Emphasis is given to the safety of operating NPPs. The derivation of an effective regulation system considering 'Rhodic Safety Review (PSR)', 'operating License Renewal (LR)', 'backfitting' and 'maintenance rule' is the main objective of the first two years. It is found that those approaches should be introduced in Korea as soon as possible, with cross lingkage to maximize the effectiveness of regulation. In particular, the approaches for PSR are discussed with consultation of IAEA document and foreign practices.

  6. Resolution of thermal-hydraulic safety and licensing issues for the system 80+{sup {trademark}} design

    Energy Technology Data Exchange (ETDEWEB)

    Carpentino, S.E.; Ritterbusch, S.E.; Schneider, R.E. [ABB-Combustion Engineering, Windsor, CT (United States)] [and others

    1995-09-01

    The System 80+{sup {trademark}} Standard Design is an evolutionary Advanced Light Water Reactor (ALWR) with a generating capacity of 3931 MWt (1350 MWe). The Final Design Approval (FDA) for this design was issued by the Nuclear Regulatory Commission (NRC) in July 1994. The design certification by the NRC is anticipated by the end of 1995 or early 1996. NRC review of the System 80+ design has involved several new safety issues never before addressed in a regulatory atmosphere. In addition, conformance with the Electric Power Research Institute (EPRI) ALWR Utility Requirements Document (URD) required that the System 80+ plant address nuclear industry concerns with regard to design, construction, operation and maintenance of nuclear power plants. A large number of these issues/concerns deals with previously unresolved generic thermal-hydraulic safety issues and severe accident prevention and mitigation. This paper discusses the thermal-hydraulic analyses and evaluations performed for the System 80+ design to resolve safety and licensing issues relevant to both the Nuclear Stream Supply System (NSSS) and containment designs. For the NSSS design, the Safety Depressurization System mitigation capability and resolution of the boron dilution concern are described. Examples of containment design issues dealing with containment shell strength, robustness of the reactor cavity walls and hydrogen mixing under severe accident conditions are also provided. Finally, the overall approach used in the application of NRC`s new (NUREG-1465) radiological source term for System 80+ evaluation is described. The robustness of the System 80+ containment design to withstand severe accident consequences was demonstrated through detailed thermal-hydraulic analyses and evaluations. This advanced design to shown to meet NRC severe accident policy goals and ALWR URD requirements without any special design features and unnecessary costs.

  7. The critical issue of nuclear power plant safety in developing countries

    International Nuclear Information System (INIS)

    Rosen, M.

    1977-01-01

    A little more than a decade from now, large commercial nuclear power facilities will be in operation in almost 40 countries, of which approximately one-half are presently considered industrially less developed. Ambitious nuclear programmes coupled with minimal and frequently under-staffed regulatory and utility organizations are only one aspect of the difficulties related to the safety of nuclear plants that face these developing countries. Inherent problems of meeting current safety standards and requirements for the significantly non-standard nuclear power plant exports can be compounded by financial considerations that may lead to purchases of reactors of various types, from more than one supplier country and with different safety standards and requirements. An examination of these issues points to the necessity and opportunity for effective action which could include provision for adequate funding for safety considerations in the purchase contract, and for sufficient regulatory assistance and training from the developed countries. The article will introduce the topic, discuss specific examples, and offer some suggestions. (author)

  8. Evaluation of systems interactions in nuclear power plants: Technical findings related to Unresolved Safety Issue A-17

    International Nuclear Information System (INIS)

    Thatcher, D.

    1989-05-01

    This report presents a summary of the activities related to Unresolved Safety Issue (USI)A-17, ''Systems Interactions in Nuclear Power Plants,'' and also includes the NRC staff's conclusions based on those activities. The staff's technical findings provide the framework for the final resolution of this unresolved safety issue. The final resolution will be published later as NUREG-1229. 52 refs., 4 tabs

  9. Resolving the Ferrocyanide Safety Issue at the Hanford Site

    International Nuclear Information System (INIS)

    Meacham, J.E.; Cash, R.J.; Babad, H.

    1994-02-01

    Considerable data have been obtained on the chemical and physical properties of ferrocyanide waste stored in Hanford Site single-shell tanks (SSTs). Theoretical analyses and ferrocyanide waste simulant studies have led to the development of fuel, moisture, and temperature criteria that define continued safe storage. Developing the criteria provides the technical basis for closing the Ferrocyanide Unreviewed Safety Question (USQ). Using the safety criteria, the ferrocyanide tanks have been ranked into one of three safety categories: Safe, Conditionally Safe, and Unsafe. All the ferrocyanide tanks are currently ranked in either the Safe or Conditionally Safe categories. Analyses of core samples taken from three ferrocyanide tanks have shown cyanide concentrations about a factor of ten lower than predicted by the original flowsheets. Hydrolytic and radiolytic destruction (aging) of the ferrocyanide matrix has occurred during the 35 plus years the waste has been stored at the Hanford Site. Because of waste aging, it is possible that all of the ferrocyanide tanks may now contain less than the 8 wt % sodium nickel ferrocyanide specified in the fuel criterion for the Safe category. Ferrocyanide tanks that remain in the Conditionally Safe category may require monitoring and surveillance to verify that the waste remains in an unreactive state. Further characterization of the tanks by core sampling and analyses should lead to resolution of the Ferrocyanide Safety Issue by September 1997

  10. Japan's regulatory and safety issues regarding nuclear materials transport

    Energy Technology Data Exchange (ETDEWEB)

    Saito, T. [Nuclear and Industrial Safety Agency, Ministry of Economy, Trade and Industry, Government of Japan, Tokyo (Japan); Yamanaka, T. [Japan Nuclear Energy Safety Organization, Government of Japan, Tokyo (Japan)

    2004-07-01

    This paper focuses on the regulatory and safety issues on nuclear materials transport which the Government of Japan (GOJ) faces and needs to well handle. Background information about the status of nuclear power plants (NPP) and nuclear fuel cycle (NFC) facilities in Japan will promote a better understanding of what this paper addresses.

  11. Current issues and perspectives in food safety and risk assessment.

    Science.gov (United States)

    Eisenbrand, G

    2015-12-01

    In this review, current issues and opportunities in food safety assessment are discussed. Food safety is considered an essential element inherent in global food security. Hazard characterization is pivotal within the continuum of risk assessment, but it may be conceived only within a very limited frame as a true alternative to risk assessment. Elucidation of the mode of action underlying a given hazard is vital to create a plausible basis for human toxicology evaluation. Risk assessment, to convey meaningful risk communication, must be based on appropriate and reliable consideration of both exposure and mode of action. New perspectives, provided by monitoring human exogenous and endogenous exposure biomarkers, are considered of great promise to support classical risk extrapolation from animal toxicology. © The Author(s) 2015.

  12. Patient safety issues in office-based surgery and anaesthesia in Switzerland: a qualitative study.

    Science.gov (United States)

    McLennan, Stuart; Schwappach, David; Harder, Yves; Staender, Sven; Elger, Bernice

    2017-08-01

    To identify the spectrum of patient safety issues in office-based surgery and anaesthesia in Switzerland. Purposive sample of 23 experts in surgery and anaesthesia and quality and regulation in Switzerland. Data were collected via individual qualitative interviews using a researcher-developed semi-structured interview guide between March 2016 and September 2016. Interviews were transcribed and analysed using conventional content analysis. Issues were categorised under the headings "structure", "process", and "outcome". Experts identified two key overarching patient safety and regulatory issues in relation to office-based surgery and anaesthesia in Switzerland. First, experts repeatedly raised the current lack of data and transparency of the setting. It is unknown how many surgeons are operating in offices, how many and what types of operations are being done, and what the outcomes are. Secondly, experts also noted the limited oversight and regulation of the setting. While some standards exists, most experts felt that more minimal safety standards are needed regarding the requirements that must be met to do office-based surgery and what can and cannot be done in the office-based setting are needed, but they advocated a self-regulatory approach. There is a lack of empirical data regarding the quantity and quality office-based surgery and anaesthesia in Switzerland. Further research is needed to address these research gaps and inform health policy in relation to patient safety in office-based surgery and anaesthesia in Switzerland. Copyright © 2017. Published by Elsevier GmbH.

  13. Workshop on radioisotope safety issues in medical and academic institutions

    International Nuclear Information System (INIS)

    1995-03-01

    The purpose of this workshop was to present current trends and recent initiatives of AECB staff members on issues relating to the regulation of radiation safety at hospitals and universities, and to invite the views of licencees on these matters. This report provides a record of presentations and discussions at this workshop. Presentation overheads are included as well as the results of workshop evaluations and a list of participants

  14. Workshop on radioisotope safety issues in medical and academic institutions

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-03-01

    The purpose of this workshop was to present current trends and recent initiatives of AECB staff members on issues relating to the regulation of radiation safety at hospitals and universities, and to invite the views of licencees on these matters. This report provides a record of presentations and discussions at this workshop. Presentation overheads are included as well as the results of workshop evaluations and a list of participants.

  15. Measurement and interpretation of laser accelerated protons at GSI

    International Nuclear Information System (INIS)

    Al-Omari, Husam

    2014-01-01

    generated by the Matlab program, while the TraceWin code is employed to study the tracking through magnetic elements. - Chapter 6 describes the PHELIX laser parameters at GSI with chirp pulse amplification technique (CPA), and Gafchromic Radiochromic film (RCF) as a spatial energy resolver film detector. The results of experiments with laser proton acceleration, which were performed in two experimental areas at GSI (Z6 area and PHELIX Laser Hall (PLH)), are presented in section 6.3. - Chapter 7 includes the main results of this work, conclusions and gives a perspective for future experimental activities.

  16. Measurement and interpretation of laser accelerated protons at GSI

    Energy Technology Data Exchange (ETDEWEB)

    Al-Omari, Husam

    2014-04-28

    generated by the Matlab program, while the TraceWin code is employed to study the tracking through magnetic elements. - Chapter 6 describes the PHELIX laser parameters at GSI with chirp pulse amplification technique (CPA), and Gafchromic Radiochromic film (RCF) as a spatial energy resolver film detector. The results of experiments with laser proton acceleration, which were performed in two experimental areas at GSI (Z6 area and PHELIX Laser Hall (PLH)), are presented in section 6.3. - Chapter 7 includes the main results of this work, conclusions and gives a perspective for future experimental activities.

  17. Environmental, health, and safety issues of sodium-sulfur batteries for electric and hybrid vehicles. Volume 1, Cell and battery safety

    Energy Technology Data Exchange (ETDEWEB)

    Ohi, J M

    1992-09-01

    This report is the first of four volumes that identify and assess the environmental, health, and safety issues involved in using sodium-sulfur (Na/S) battery technology as the energy source in electric and hybrid vehicles that may affect the commercialization of Na/S batteries. This and the other reports on recycling, shipping, and vehicle safety are intended to help the Electric and Hybrid Propulsion Division of the Office of Transportation Technologies in the US Department of Energy (DOE/EHP) determine the direction of its research, development, and demonstration (RD&D) program for Na/S battery technology. The reports review the status of Na/S battery RD&D and identify potential hazards and risks that may require additional research or that may affect the design and use of Na/S batteries. This volume covers cell design and engineering as the basis of safety for Na/S batteries and describes and assesses the potential chemical, electrical, and thermal hazards and risks of Na/S cells and batteries as well as the RD&D performed, under way, or to address these hazards and risks. The report is based on a review of the literature and on discussions with experts at DOE, national laboratories and agencies, universities, and private industry. Subsequent volumes will address environmental, health, and safety issues involved in shipping cells and batteries, using batteries to propel electric vehicles, and recycling and disposing of spent batteries. The remainder of this volume is divided into two major sections on safety at the cell and battery levels. The section on Na/S cells describes major component and potential failure modes, design, life testing and failure testing, thermal cycling, and the safety status of Na/S cells. The section on batteries describes battery design, testing, and safety status. Additional EH&S information on Na/S batteries is provided in the appendices.

  18. Rate-dependent performance of ion chambers for particle-ID at the GSI fragment separator

    Energy Technology Data Exchange (ETDEWEB)

    Hucka, Jan-Paul; Allred, Timothy; Enders, Joachim [Institut fuer Kernphysik, TU Darmstadt (Germany); Gernhaeuser, Roman; Maurus, Steffen [Physik Department, TU Muenchen (Germany); Nociforo, Chiara; Pietri, Stephane; Prochazka, Andrej [GSI Helmholtzzentrum fuer Schwerionenforschung (Germany)

    2015-07-01

    At the GSI Fragment Separator (FRS), multi-sampling ion chambers (MUSIC) employing a Frisch grid are used for charge identification of secondary ion beams. At the FAIR Super-FRS, higher rates are expected, and an event-by-event determination of the charge of secondary ions will be needed at rates of several 100000 events per second. The comparison of results from test measurements for the MUSIC performance with that of a recently constructed tilted-electrode gas ion chamber (TEGIC), which was designed similar to the one discussed, is presented.

  19. {sup 96}Ru(p,{gamma}){sup 97}Rh measurement at the GSI storage ring

    Energy Technology Data Exchange (ETDEWEB)

    Zhong, Q; Aumann, T; Boretzky, K; Bosch, F; Braeuning, H; Brandau, C; Ershova, O; Geissel, H; Heil, M; Kelic, A; Kozhuharov, C; Langer, C; Bleis, T Le; Litvinov, Y A [GSI Helmholtzzentrum fuer Schwerionenforschung GmbH, Darmstadt, 64291 (Germany); Bishop, S; Dillmann, I [Technische Universitaet Muenchen, 85748 Garching (Germany); Blaum, K [Max-Planck-Institut fuer Kernphysik, 69117 Heidelberg (Germany); Davinson, T [University of Edinburgh, Edinburgh (United Kingdom); Gyuerky, G [Institute of Nuclear Research of the Hungarian Academy of Sciences (Hungary); Kaeppeler, F, E-mail: r.reifarth@gsi.d [Forschungszentrum Karlsruhe, Institut fuer Kernphysik, Karlsruhe (Germany)

    2010-01-01

    A pioneering experiment was recently performed at the Experimental Storage Ring (ESR) at GSI. Fully stripped ions of {sup 96}Ru were injected into the storage ring and slowed down to a few MeV per nucleon. The {sup 97}Rh ions from the {sup 96}Ru(p,{gamma}) reaction at a newly developed hydrogen jet target were detected with Double Sided Silicon Strip Detectors (DSSSD) mounted inside a pocket. The experiment and the status of the analysis at a beam energy of 11 MeV per nucleon will be presented.

  20. Safety issues of dry fuel storage at RSWF

    International Nuclear Information System (INIS)

    Clarksean, R.L.; Zahn, T.P.

    1995-01-01

    Safety issues associated with the dry storage of EBR-II spent fuel are presented and discussed. The containers for the fuel have been designed to prevent a leak of fission gases to the environment. The storage system has four barriers for the fission gases. These barriers are the fuel cladding, an inner container, an outer container, and the liner at the RSWF. Analysis has shown that the probability of a leak to the environment is much less than 10 -6 per year, indicating that such an event is not considered credible. A drop accident, excessive thermal loads, criticality, and possible failure modes of the containers are also addressed

  1. Resolution of the ferrocyanide safety issue for the Hanford site high-level waste tanks

    International Nuclear Information System (INIS)

    Cash, R.J.

    1996-01-01

    This paper describes the approach used to resolve the ferrocyanide safety issue, a process that began in 1990 after heightened concern was expressed by various government agencies about the safety of Hanford site high-level waste tanks. At the time, little was known about ferrocyanide-nitrate/nitrite reactions and the potential for offsite releases of radioactivity from the Hanford Site. Recent studies have shown that the combined effects of temperature, radiation, and pH during more than 38 years of storage have destroyed most of the ferrocyanide originally added to tanks. This has been proven in the laboratory using flowsheet-derived waste simulants and confirmed by waste samples obtained from the ferrocyanide tanks. The resulting tank waste sludges are too dilute to support a sustained exothermic reaction, even if dried out and heated to temperatures of at least 250 C. The US Department of Energy (DOE) has been requested to close the ferrocyanide safety issue

  2. Ethical issues in engineering design processes ; regulative frameworks for safety and sustainability

    NARCIS (Netherlands)

    Gorp, A. van

    2007-01-01

    The ways designers deal with ethical issues that arise in their consideration of safety and sustainability in engineering design processes are described. In the case studies, upon which this article is based, a difference can be seen between normal and radical design. Designers refer to regulative

  3. Guidelines for nuclear power plant safety issue prioritization information development. Supplement 3

    International Nuclear Information System (INIS)

    Andrews, W.B.; Bickford, W.E.; Counts, C.A.; Gallucci, R.H.V.; Heaberlin, S.W.; Powers, T.B.; Weakley, S.A.

    1985-09-01

    This supplemental report is the fourth in a series that document and use methods developed to calculate, for prioritization purposes, the risk, dose and cost impacts of implementing resolutions to reactor safety issues. The initial report in this series was published by Andrews et al. in 1983 as NUREG/CR-2800. This supplement consists of two parts describing separate research efforts: (1) an alternative human factors methodology approach, and (2) a prioritization of the NRC's Human Factors Program Plan. The alternative human factors methodology approach may be used in specific future cases in which the methods identified in the initial report (NUREG/CR-2800) may not adequately assess the proper impact for resolution of new safety issues. The alternative methodology included in this supplement is entitled ''Methodology for Estimating the Public Risk Reduction Affected by Human Factors Improvement.'' The prioritization section of this report is entitled ''Prioritization of the US Nuclear Regulatory Commission Human Factors Program Plan.''

  4. Identification of new unresolved safety issues relating to nuclear power plants - special report to Congress. Congressional report

    International Nuclear Information System (INIS)

    1981-03-01

    As a result of NRC staff review and extended collegial consultations and investigations within the NRC, the Commission has designated four new Unresolved Safety Issues (USIs). This report describes the process used to evaluate the large number of concerns and recommendations which resulted from the major investigations of the Three Mile Island-2 accident as well as other events and investigations of the past year, and the report identifies the four new USIs selected as follows: (1) Shutdown decay heat removal requirements (Task A-45); (2) Seismic qualification of equipment in operating plants (Task A-46); (3) Safety implications of control systems (Task A-47); and (4) Hydrogen control measures and effects of hydrogen burns on safety equipment (Task A-48). Appendix A of the report presents an expanded discussion of each new USI including issue definition, a preliminary discussion of the action plan and a basis for continued plant operations and licensing. Appendix B of the report provides a brief discussion of each of the candidate safety issues not designated as an USI

  5. Food safety issues in China: a case study of the dairy sector.

    Science.gov (United States)

    Dong, Xiaoxia; Li, Zhemin

    2016-01-15

    Over the past 10 years, food safety incidents have occurred frequently in China. Food safety issues in the dairy sector have increasingly gained the attention of the Chinese government and the public. The objective of this research is to explore consumption changes of dairy products of different income groups after these dairy safety incidents. The research indicates that consumers' response to dairy safety risk is very intense. Dairy consumption has experienced a declining trend in recent years, and the impact of dairy safety incidents has lasted for at least 5 years. Until 2012, dairy consumption had not yet fully recovered from this influence. Using the random effects model, this study examined the relationship between food safety incident and consumption. Overall, the results show that consumers in the low-income group are more sensitive to safety risk than those in the high-income group. It can be seen from this paper that the decrease of urban residents' dairy consumption was mainly driven by changes in fresh milk consumption, while the decline of milk powder consumption, which was affected by the melamine incident, was relatively moderate, and milk powder consumption for the high-income group even increased. © 2015 Society of Chemical Industry.

  6. A digest of the Nuclear Safety Division report on the Fukushima Dai-ichi accident seminar (4). Issues identified by the accident

    International Nuclear Information System (INIS)

    Moriyama, Kumiaki; Abe, Kiyoharu

    2013-01-01

    AESJ Nuclear Safety Division published 'Report on the Fukushima Dai-ichi Accident Seminar - what was wrong and what should been down in future-' which would be published as five special articles of the AESJ journal. The Fukushima Dai-ichi accident identified issues of several activities directly related with nuclear safety in the areas of safety design, severe accident management and safety regulations. PRA, operational experiences and safety research could not always contribute safety assurance of nuclear power plant so much. This article (4) summarized technical issues based on related facts of the accident as much as possible and discussed' what was wrong and what should be down in future'. Important issues were identified from defense-in-depth philosophy and lessons learned on safety design were obtained from accident progression analysis. Activities against external events and continuous improvements of safety standards based on latest knowledge were most indispensable. Strong cooperation among experts in different areas was also needed. (T. Tanaka)

  7. Experiments on the interaction of heavy ions with dense plasma at GSI-Darmstadt

    International Nuclear Information System (INIS)

    Stoeckl, C.; Boine-Frankenheim, O.; Geissel, M.; Roth, M.; Wetzler, H.; Seelig, W.; Iwase, O.; Spiller, P.; Bock, R.; Suess, W.; Hoffmann, D.H.H.

    1998-01-01

    One of the main objectives of the experimental plasma physics activities at the Gesellschaft fuer Schwerionenforschung (GSI) are the interaction processes of heavy ions with dense ionized matter. Gas-discharge plasma targets were used for energy loss and charge state measurements in a regime of electron density and temperature up to 10 19 cm -3 and 20 eV, respectively. An improved model of the charge exchange processes in fully ionized hydrogen plasma, taking into account multiple excited electronic configurations which subsequently ionize, has removed the discrepancies of previous theoretical descriptions. The energy loss of the ion beam in partially ionized plasmas such as argon was found to agree very well with our simple theoretical model based on the modified Bethe-Bloch theory. A new setup with a 100 J/5 GW Nd-glass laser now provides access to density ranges up to 10 21 cm -3 and temperatures of up to 100 eV. First results of interaction experiments with laser-produced plasma are presented. To fully exploit the experimental possibilities of the new laser-plasma setup both improved charge state detection systems and better plasma diagnostics are indispensable. Present developments and future possibilities in these fields are presented. This paper summarizes the following contributions: Interaction of heavy-ion beams with laser plasma by C. Stoeckl et al. Energy loss of heavy ions in a laser-produced plasma by M. Roth et al. Charge state measurements of heavy ions passing a laser produced plasma with high time resolution by W. Suess et al. Plasma diagnostics for laser-produced plasma by O. Iwase et al. Future possibilities of plasma diagnostics at GSI by M. Geissel et al. (orig.)

  8. Compiler issues associated with safety-related software

    International Nuclear Information System (INIS)

    Feinauer, L.R.

    1991-01-01

    A critical issue in the quality assurance of safety-related software is the ability of the software to produce identical results, independent of the host machine, operating system, or compiler version under which the software is installed. A study is performed using the VIPRE-0l, FREY-01, and RETRAN-02 safety-related codes. Results from an IBM 3083 computer are compared with results from a CYBER 860 computer. All three of the computer programs examined are written in FORTRAN; the VIPRE code uses the FORTRAN 66 compiler, whereas the FREY and RETRAN codes use the FORTRAN 77 compiler. Various compiler options are studied to determine their effect on the output between machines. Since the Control Data Corporation and IBM machines inherently represent numerical data differently, methods of producing equivalent accuracy of data representation were an important focus of the study. This paper identifies particular problems in the automatic double-precision option (AUTODBL) of the IBM FORTRAN 1.4.x series of compilers. The IBM FORTRAN version 2 compilers provide much more stable, reliable compilation for engineering software. Careful selection of compilers and compiler options can help guarantee identical results between different machines. To ensure reproducibility of results, the same compiler and compiler options should be used to install the program as were used in the development and testing of the program

  9. Safety issues to be taken into account in designing future nuclear fusion facilities

    Energy Technology Data Exchange (ETDEWEB)

    Perrault, Didier, E-mail: didier.perrault@irsn.fr

    2016-11-01

    Highlights: • Assess if decay heat removal is a safety function. • Re-study accidents considered for ITER and identify those specific to DEMO. • Limit tritium inventory and optimize main gaseous tritium release routes. • Take into account constraints related to requirements of waste disposal routes. - Abstract: For several years now, the French “Institut de Radioprotection et de Sûreté Nucléaire” has been carrying out expertise of ITER fusion facility safety files at the request of the French “Autorité de Sûreté Nucléaire”. As part of the lengthy process which should lead to mastering nuclear fusion, different fusion facility projects are currently under study throughout the world to be ready to continue building on the work which will take place in the ITER facility. On the basis of the experience acquired during the ITER safety expertise, the IRSN has carried out a preliminary study of the safety issues which seem necessary to take into account right from the earliest design phase of these DEMO facilities. The issues studied have included the decay heat removal, exposure to ionizing radiation, potential accidents, and effluent releases and waste. The study shows that it will be important to give priority to the following actions, given that their results would have a major influence on the design: assess if decay heat removal is a safety function, re-study the accidents considered in the context of the ITER project and identify those specific to DEMO, and optimize each of the main routes for gaseous tritium releases.

  10. Effects of the Smartphone Application "Safe Patients" on Knowledge of Patient Safety Issues Among Surgical Patients.

    Science.gov (United States)

    Cho, Sumi; Lee, Eunjoo

    2017-12-01

    Recently, the patient's role in preventing adverse events has been emphasized. Patients who are more knowledgeable about safety issues are more likely to engage in safety initiatives. Therefore, nurses need to develop techniques and tools that increase patients' knowledge in preventing adverse events. For this reason, an educational smartphone application for patient safety called "Safe Patients" was developed through an iterative process involving a literature review, expert consultations, and pilot testing of the application. To determine the effect of "Safe Patients," it was implemented for patients in surgical units in a tertiary hospital in South Korea. The change in patients' knowledge about patient safety was measured using seven true/false questions developed in this study. A one-group pretest and posttest design was used, and a total of 123 of 190 possible participants were tested. The percentage of correct answers significantly increased from 64.5% to 75.8% (P effectively improve patients' knowledge of safety issues. This will ultimately empower patients to engage in safe practices and prevent adverse events related to surgery.

  11. Environmental, health, and safety issues of sodium-sulfur batteries for electric and hybrid vehicles. Volume 4, In-vehicle safety

    Energy Technology Data Exchange (ETDEWEB)

    Mark, J.

    1992-11-01

    This report is the last of four volumes that identify and assess the environmental, health, and safety issues that may affect the commercial-scale use of sodium-sulfur (Na/S) battery technology as the energy source in electric and hybrid vehicles. The reports are intended to help the Electric and Hybrid Propulsion Division of the Office of Transportation Technologies in the US Department of Energy (DOE/EHP) determine the direction of its research, development, and demonstration (RD&D) program for Na/S battery technology. The reports review the status of Na/S battery RD&D and identify potential hazards and risks that may require additional research or that may affect the design and use of Na/S batteries. This volume covers the in-vehicle safety issues of electric vehicles powered by Na/S batteries. The report is based on a review of the literature and on discussions with experts at DOE, national laboratories and agencies, and private industry. It has three major goals: (1) to identify the unique hazards associated with electric vehicle (EV) use; (2) to describe the existing standards, regulations, and guidelines that are or could be applicable to these hazards; and (3) to discuss the adequacy of the existing requirements in addressing the safety concerns of EVs.

  12. Progress and Updates of Regulatory Challenges and Safety Issues in Korea during Three Years after Fukushima Accident

    International Nuclear Information System (INIS)

    Lee, Young Eal; Kim, Kyun Tae

    2014-01-01

    Before the public fear on radiation risk caused by neighboring country's severe accident disappeared, a series of nuclear safety issues last 3 years made a few reactors shut down and the public trust much lower than before. Because of these scandals such as cover-ups, forged certificated items, corruption of manager of licensee and so on, many efforts made during three year after Fukushima accident on improving the nuclear safety were invalidated and even regulators as well as operators have been sharply criticized for its responsibility and transparency. This paper shares information on the progress and uprates achieved in Korea so far in connection with the safety issues caused during last 3 years and actions taken by the regulatory body. Before the public fear on radiation risk caused by neighboring country's severe accident disappeared, a series of nuclear safety issues last 3 years made a few reactors shut down and the public trust much lower than before. Because of these scandals such as cover-ups, forged certificated items, corruption of manager of licensee and so on, many efforts made during three year after Fukushima accident on improving the nuclear safety were invalidated and even regulators as well as operators have been sharply criticized for its responsibility and transparency

  13. Progress and Updates of Regulatory Challenges and Safety Issues in Korea during Three Years after Fukushima Accident

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Young Eal; Kim, Kyun Tae [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

    2014-10-15

    Before the public fear on radiation risk caused by neighboring country's severe accident disappeared, a series of nuclear safety issues last 3 years made a few reactors shut down and the public trust much lower than before. Because of these scandals such as cover-ups, forged certificated items, corruption of manager of licensee and so on, many efforts made during three year after Fukushima accident on improving the nuclear safety were invalidated and even regulators as well as operators have been sharply criticized for its responsibility and transparency. This paper shares information on the progress and uprates achieved in Korea so far in connection with the safety issues caused during last 3 years and actions taken by the regulatory body. Before the public fear on radiation risk caused by neighboring country's severe accident disappeared, a series of nuclear safety issues last 3 years made a few reactors shut down and the public trust much lower than before. Because of these scandals such as cover-ups, forged certificated items, corruption of manager of licensee and so on, many efforts made during three year after Fukushima accident on improving the nuclear safety were invalidated and even regulators as well as operators have been sharply criticized for its responsibility and transparency.

  14. The symmetry energy at suprasaturation density and the ASY-EOS experiment at GSI

    Directory of Open Access Journals (Sweden)

    De Filippo E.

    2017-01-01

    Full Text Available The ASY-EOS experiment at GSI laboratory measured the direct and elliptic flow of neutrons and light charged particles in the reaction 197Au+197 Au at 400 A MeV incident energy. The ratio of elliptic flow of neutrons with respect to that of the light charged particles was used as main experimental observable to probe the density dependence of the symmetry energy term of the nuclear equation of state. Results, obtained by comparison of the experimental data with the UrQMD model predictions, strongly support a moderately soft to linear density dependence of the symmetry energy at suprasaturation densities below 2ρ0.

  15. Emergency diesel generator reliability program

    International Nuclear Information System (INIS)

    Serkiz, A.W.

    1989-01-01

    The need for an emergency diesel generator (EDG) reliability program has been established by 10 CFR Part 50, Section 50.63, Loss of All Alternating Current Power, which requires that utilities assess their station blackout duration and recovery capability. EDGs are the principal emergency ac power sources for coping with a station blackout. Regulatory Guide 1.155, Station Blackout, identifies a need for (1) an EDG reliability equal to or greater than 0.95, and (2) an EDG reliability program to monitor and maintain the required levels. The resolution of Generic Safety Issue (GSI) B-56 embodies the identification of a suitable EDG reliability program structure, revision of pertinent regulatory guides and Tech Specs, and development of an Inspection Module. Resolution of B-56 is coupled to the resolution of Unresolved Safety Issue (USI) A-44, Station Blackout, which resulted in the station blackout rule, 10 CFR 50.63 and Regulatory Guide 1.155, Station Blackout. This paper discusses the principal elements of an EDG reliability program developed for resolving GSI B-56 and related matters

  16. Lessons Learned and Regulatory Countermeasures of Nuclear Safety Issues Last Year

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Y. E. [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

    2013-05-15

    Competitiveness of nuclear as the electric resource in terms of the least cost and the carbon abatement has been debated. Some institutions insist that the radioactive wastes management cost, nuclear accident cost and cheap shale gas would make the nuclear energy less competitive, while others still address the ability of nuclear energy as economical and low-carbon electric resource. This situation reminds that ensuring nuclear safety is the most important prerequisite to use of nuclear energy. Therefore, this paper will compare the different views on future nuclear competitiveness discussed right after the Fukushima accident and summarize the lessons learned and regulatory countermeasures from nuclear safety issues last year. Korea has improved the effectiveness of safety regulation up to now and still has been making efforts on further enhancing nuclear safety. The outcomes of these efforts have resulted in a high level of safety in Korean NPPs and contributing largely to the global nuclear safety through sharing and exchanging the information and knowledge of our nuclear experiences. However, now we are faced with the new challenges such as decreasing the public. Additionally, public criticism of the regulatory activities demands more clear regulatory guides and transparent process. Recently, new president announced the 'Priority to Safety and Public Trust' as the precondition to utilize the nuclear energy. We will continue to make much more efforts for the improvement of the quality of regulatory activities and effectiveness of regulatory decision making process than we have done so far. Competence through effective capacity building would be a helpful pathway to build up the public trust and ensure the acceptable level of nuclear safety. We are set to prepare the action items to be taken in the near future for improving the technical competency and transparency as the essential components of the national safety and will make efforts to implement them

  17. Maintenance as a safety issue.

    Science.gov (United States)

    White, Jim

    2008-11-01

    Because safety is related to electrical power systems maintenance, it seems reasonable to assume there could be legal issues if maintenance is not performed. OSHA has not yet taken the stand that not performing maintenance as required by the manufacturer, NFPA 70B, or ANSI/NETA MTS-07 constitutes a willful violation. OSHA defines a willful citation as one where: "the employer knowingly commits with plain indifference to the law. The employer either knows that what he or she is doing constitutes a violation, or is aware that a hazardous condition existed and made no reasonable effort to eliminate it". However, NFPA 70E 2009 requires this maintenance, and OSHA has stated on its Web site that NFPA 70E is "a guide for meeting the requirements of the OSHA electrical regulations". In addition, federal courts have found that NFPA 70E is "standard industry practice." Once a company receives and accepts a willful citation, especially if received as the result of an accident investigation, its worker's compensation protection no longer shields it. One definition given by a trial attorney for a willful citation was that it is equal to negligent behavior. Be smart: Maintain that equipment and save yourself major problems, including unscheduled shutdowns and possible litigation.

  18. Databases on safety issues for WWER and RBMK reactors. Users' manual. A publication of the extrabudgetary programme on the safety of WWER and RBMK nuclear power plants

    International Nuclear Information System (INIS)

    1996-04-01

    At the beginning of the IAEA Extrabudgetary Programme on the safety of WWER reactors a great number of findings and recommendations (safety items) were collected as a result of design review and safety review missions of the WWER-440/230 type reactors. On the basis of these findings a technical database containing more than 1300 records was established to support the consolidation of the information obtained and to help in identification of safety issues. After the scope of the WWER extrabudgetary programme was extended similar data sets were prepared for the WWER-440/213, WWER-1000 and RBMK nuclear power plants. This publication describes the structure of the databases on safety issues of WWER and RBMK NPPs, the information sources used in the databases and interrogation capabilities for users to obtain the necessary information. 14 refs, 9 figs, 5 tabs

  19. Conclusions and Recommendations of the IAEA International Conference on Topical Issues in Nuclear Safety: Ensuring Safety for Sustainable Nuclear Development

    International Nuclear Information System (INIS)

    El-Shanawany, Mamdouh

    2011-01-01

    programmes. National safety authorities could take the initiative of organizing international workshops on how OEF has been used and implemented. Moreover, lessons learned from new construction should be provided and shared between all countries embarking and considering new build. 5. It is vital in today's environment that the synergies between safety and security are maximized, and that culture be developed that integrates safety and security requirements. Safety and security have the same purpose: protecting people, society, environment and both could be based on similar principles even if there are some differences in implementation such as openness and transparency. There are important advantages from integrating the regulation of safety and security as much as possible. 6. The quality of the supply chain is an emerging issue. Harmonization of safety requirements, design codes and quality standards within the supply chain is acknowledged as requiring further collaboration among Member States, international organizations and supplier companies. Multinational Design Evaluation Programme (MDEP) is an important first step towards this goal. 7. Transparency, collaboration, information sharing and openness is responsibility of all Member States to assure not only safety but to foster confidence and trust among all stakeholders. 8. Despite NPPs high level of safety, emergency preparedness and response is an important issue in the context of developing nuclear energy. Through international cooperation, emergency and response plans need to be developed and well coordinated within all relevant entities. 9. In the context of developing nuclear energy the generation gap in education and training as well as the necessity to build technical capacity to properly address safety issues has been acknowledged by the Conference. Therefore, adequate education and training programmes should be developed and implemented.

  20. Main Conclusions and Recommendations of International Conference on Topical Issues in Nuclear Installation Safety: Ensuring Safety for Sustainable Nuclear Development

    International Nuclear Information System (INIS)

    El-Shanawany, Mamdouh

    2011-01-01

    programmes. National safety authorities could take the initiative of organizing international workshops on how OEF has been used and implemented. Moreover, lessons learned from new construction should be provided and shared between all countries embarking and considering new build. 5. It is vital in today's environment that the synergies between safety and security are maximized, and that culture be developed that integrates safety and security requirements. Safety and security have the same purpose: protecting people, society, environment and both could be based on similar principles even if there are some differences in implementation such as openness and transparency. There are important advantages from integrating the regulation of safety and security as much as possible. 6. The quality of the supply chain is an emerging issue. Harmonization of safety requirements, design codes and quality standards within the supply chain is acknowledged as requiring further collaboration among Member States, international organizations and supplier companies. Multinational Design Evaluation Programme (MDEP) is an important first step towards this goal. 7. Transparency, collaboration, information sharing and openness is responsibility of all Member States to assure not only safety but to foster confidence and trust among all stakeholders. 8. Despite NPPs high level of safety, emergency preparedness and response is an important issue in the context of developing nuclear energy. Through international cooperation, emergency and response plans need to be developed and well coordinated within all relevant entities. 9. In the context of developing nuclear energy the generation gap in education and training as well as the necessity to build technical capacity to properly address safety issues has been acknowledged by the Conference. Therefore, adequate education and training programmes should be developed and implemented.

  1. The R and D issues necessary to achieve the safety design of commercialized liquid-metal cooled fast reactors

    International Nuclear Information System (INIS)

    Shoji, Kotake; Koji, Dozaki; Shigenobu, Kubo; Yoshio, Shimakawa; Hajime, Niwa; Masakazu, Ichimiya

    2002-01-01

    Within the framework of the feasibility study on commercialized fast reactor cycle systems (hereafter described as F/S), the safety design principle is investigated and several kinds of design studies are now in progress. Among the designs for liquid-metal cooled fast reactor (LMR), the advanced loop type sodium cooled fast reactor (FR) is one of the promising candidate as future commercialized LMR. In this paper, the safety related research and development (R and D) issues necessary to achieve the safety design are described along the defence-in-depth principle, taking account of not only the system characteristics of the advanced loop concepts but also design studies and R and D experiences so far. Safety issues related to the hypothetical core disruptive accidents (CDA) are emphasized both from the prevention and mitigation. A re-criticality free core concept with a special fuel assembly is pursued by performing both analytical and experimental efforts, in order to realize the rational design and to establish easy-to-understand safety logic. Sodium related issues are also given to ensure plant availability and to enhance the acceptability to the public. (authors)

  2. Strategy for resolution of the Flammable Gas Safety Issue

    International Nuclear Information System (INIS)

    Johnson, G.D.

    1995-01-01

    The purpose of this document is to provide the general strategy for resolution of the flammable gas safety issue; it is not a detailed description of program activities. budgets and schedules. Details of the program activities have been issued (Johnson and Sherwood, 1994) and the information pertaining to budgets is provided in the FY 1995-1997 Multi-Year Work Plan for Tank Waste Remediation System (TWRS) (Program Element 1.1.1.2.02.). The key element in this strategy is to provide an understanding of the behavior of each of the Flammable Gas Watch List tanks. While a review of historical information does provide some insight, it is necessary to gather current information about the gases, behavior and nature of the waste,. and about the control systems that maintain and monitor the waste. Analysis of this information will enable TWRS to determine the best approach to place any tank in a safe condition, if it is found to be in an unsafe state

  3. HTGR Dust Safety Issues and Needs for Research and Development

    Energy Technology Data Exchange (ETDEWEB)

    Paul W. Humrickhouse

    2011-06-01

    This report presents a summary of high temperature gas-cooled reactor dust safety issues. It draws upon a literature review and the proceedings of the Very High Temperature Reactor Dust Assessment Meeting held in Rockville, MD in March 2011 to identify and prioritize the phenomena and issues that characterize the effect of carbonaceous dust on high temperature reactor safety. It reflects the work and input of approximately 40 participants from the U.S. Department of Energy and its National Labs, the U.S. Nuclear Regulatory Commission, industry, academia, and international nuclear research organizations on the topics of dust generation and characterization, transport, fission product interactions, and chemical reactions. The meeting was organized by the Idaho National Laboratory under the auspices of the Next Generation Nuclear Plant Project, with support from the U.S. Nuclear Regulatory Commission. Information gleaned from the report and related meetings will be used to enhance the fuel, graphite, and methods technical program plans that guide research and development under the Next Generation Nuclear Plant Project. Based on meeting discussions and presentations, major research and development needs include: generating adsorption isotherms for fission products that display an affinity for dust, investigating the formation and properties of carbonaceous crust on the inside of high temperature reactor coolant pipes, and confirming the predominant source of dust as abrasion between fuel spheres and the fuel handling system.

  4. Safety culture and organisational issues specific to the transitional phase from operation to decommissioning of the Ignalina Nuclear Power Plant

    International Nuclear Information System (INIS)

    Medeliene, D.

    2005-01-01

    The PHARE project Support to State Nuclear Power Safety Inspectorate for safety culture and organisational issues specific to the pre-shutdown phase of Ignalina Nuclear Power Plant was aimed at providing assistance to VATESI in their task to oversee that the Ignalina Nuclear Power Plant's management and staff are able to provide an acceptable level of reactor safety taking into account possible safety culture related problems that may occur due to the decision of an early closure of both units. Safety culture is used as a concept to characterise the attitudes, behaviour and perceptions of people that are important in ensuring the safety of nuclear power facility. Since the Chernobyl accident, the International Atomic Energy Agency (IAEA) has been active in creating guidance for ensuring that an adequate safety culture can be created and maintained. The transition from operation to decommissioning introduces uncertainty for both the organisation and individuals. This creates new challenges that need to be dealt with. Although safety culture and organisational issues have to be addressed during the entire life cycle of a nuclear power plant, owing to these special challenges, it should be especially highlighted during the transitional period from operation to decommissioning. Nuclear safety experts from Sweden, Finland, Italy, the UK and Germany, as well as Lithuanian specialists, participated in the project, and it proved to be a most effective way to share experience. The aim of this brochure is to provide information about: the importance of safety culture issues during the transitional phase from operation to decommissioning of Ignalina Nuclear Power Plant; the purpose, activities and results of this PHARE project; recommendations that are provided by western experts concerning the management of safety culture issues specific to the pre-decommissioning phase of Ignalina Nuclear Power Plant. (author)

  5. Current Status of Health and Safety Issues of Sodium/Metal Chloride (Zebra) Batteries

    International Nuclear Information System (INIS)

    David Trickett

    1998-01-01

    This report addresses environmental, health, and safety (EH ampersand S) issues associated with sodium/ metal chloride batteries, in general, although most references to specific cell or battery types refer to units developed or being developed under the Zebra trademark. The report focuses on issues pertinent to sodium/metal chloride batteries and their constituent components; however, the fact that some ''issues'' arise from interaction between electric vehicle (EV) and battery design com- pels occasional discussion amid the context of EV vehicle design and operation. This approach has been chosen to provide a reasonably comprehensive account of the topic from a cell technology perspective and an applications perspective

  6. Current Status of Health and Safety Issues of Sodium/Metal Chloride (Zebra) Batteries

    Energy Technology Data Exchange (ETDEWEB)

    Trickett, D.

    1998-12-15

    This report addresses environmental, health, and safety (EH&S) issues associated with sodium/ metal chloride batteries, in general, although most references to specific cell or battery types refer to units developed or being developed under the Zebra trademark. The report focuses on issues pertinent to sodium/metal chloride batteries and their constituent components; however, the fact that some ''issues'' arise from interaction between electric vehicle (EV) and battery design compels occasional discussion amid the context of EV vehicle design and operation. This approach has been chosen to provide a reasonably comprehensive account of the topic from a cell technology perspective and an applications perspective.

  7. Environmental, health, and safety issues of sodium-sulfur batteries for electric and hybrid vehicles

    Energy Technology Data Exchange (ETDEWEB)

    Ohi, J.M.

    1992-09-01

    This report is the first of four volumes that identify and assess the environmental, health, and safety issues involved in using sodium-sulfur (Na/S) battery technology as the energy source in electric and hybrid vehicles that may affect the commercialization of Na/S batteries. This and the other reports on recycling, shipping, and vehicle safety are intended to help the Electric and Hybrid Propulsion Division of the Office of Transportation Technologies in the US Department of Energy (DOE/EHP) determine the direction of its research, development, and demonstration (RD D) program for Na/S battery technology. The reports review the status of Na/S battery RD D and identify potential hazards and risks that may require additional research or that may affect the design and use of Na/S batteries. This volume covers cell design and engineering as the basis of safety for Na/S batteries and describes and assesses the potential chemical, electrical, and thermal hazards and risks of Na/S cells and batteries as well as the RD D performed, under way, or to address these hazards and risks. The report is based on a review of the literature and on discussions with experts at DOE, national laboratories and agencies, universities, and private industry. Subsequent volumes will address environmental, health, and safety issues involved in shipping cells and batteries, using batteries to propel electric vehicles, and recycling and disposing of spent batteries. The remainder of this volume is divided into two major sections on safety at the cell and battery levels. The section on Na/S cells describes major component and potential failure modes, design, life testing and failure testing, thermal cycling, and the safety status of Na/S cells. The section on batteries describes battery design, testing, and safety status. Additional EH S information on Na/S batteries is provided in the appendices.

  8. LMFBR safety. 5. Review of current issues and bibliography of literature (1975--1976)

    International Nuclear Information System (INIS)

    Buchanan, J.R.; Keilholtz, G.W.

    1977-01-01

    The current status of liquid-metal fast breeder reactor (LMFBR) development and one of the principal safety issues, a hypothetical core-disruptive accident (HCDA), are discussed. Bibliographic information on worldwide LMFBRs relative to the development and safety of the breeder reactor is presented for the period 1975 through 1976. The bibliography consists of approximately 1618 abstracts covering early research and development and operating experiences leading up to the present design practices that are necessary for the licensing of breeder reactors. Keyword, author, and permuted-title indexes are included for completeness

  9. LMFBR safety. 5. Review of current issues and bibliography of literature (1975--1976)

    Energy Technology Data Exchange (ETDEWEB)

    Buchanan, J.R.; Keilholtz, G.W.

    1977-06-08

    The current status of liquid-metal fast breeder reactor (LMFBR) development and one of the principal safety issues, a hypothetical core-disruptive accident (HCDA), are discussed. Bibliographic information on worldwide LMFBRs relative to the development and safety of the breeder reactor is presented for the period 1975 through 1976. The bibliography consists of approximately 1618 abstracts covering early research and development and operating experiences leading up to the present design practices that are necessary for the licensing of breeder reactors. Keyword, author, and permuted-title indexes are included for completeness.

  10. Overview of safety and environmental issues for inertial fusion energy

    International Nuclear Information System (INIS)

    Piet, S.J.; Brereton, S.J.; Tanaka, S.

    1996-01-01

    This paper summarizes safety and environmental issues of Inertial Fusion Energy (IFE): inventories, effluents, maintenance, accident safety, waste management, and recycling. The fusion confinement approach among inertial and magnetic options affects how the fusion reaction is maintained and which materials surround the reaction chamber. The target fill technology has a major impact on the target factory tritium inventory. IFE fusion reaction chambers usually employ some means to protect the first structural wall from fusion pulses. This protective fluid or granular bed also moderates and absorbs most neutrons before they reach the first structural wall. Although the protective fluid activates, most candidate fluids have low activation hazard. Hands-on maintenance seems practical for the driver, target factory, and secondary coolant systems; remote maintenance is likely required for the reaction chamber, primary coolant, and vacuum exhaust cleanup systems. The driver and fuel target facility are well separated from the main reaction chamber

  11. Health safety issues of synthetic food colorants.

    Science.gov (United States)

    Amchova, Petra; Kotolova, Hana; Ruda-Kucerova, Jana

    2015-12-01

    Increasing attention has been recently paid to the toxicity of additives used in food. The European Parliament and the Council published the REGULATION (EC) No. 1333/2008 on food additives establishing that the toxicity of food additives evaluated before 20th January 2009 must be re-evaluated by European Food Safety Authority (EFSA). The aim of this review is to survey current knowledge specifically on the toxicity issues of synthetic food colorants using official reports published by the EFSA and other available studies published since the respective report. Synthetic colorants described are Tartrazine, Quinoline Yellow, Sunset Yellow, Azorubine, Ponceau 4R, Erythrosine, Allura Red, Patent Blue, Indigo Carmine, Brilliant Blue FCF, Green S, Brilliant Black and Brown HT. Moreover, a summary of evidence on possible detrimental effects of colorant mixes on children's behaviour is provided and future research directions are outlined. Copyright © 2015 Elsevier Inc. All rights reserved.

  12. Advanced CFD simulation for the assessment of nuclear safety issues at EDF. Some examples

    International Nuclear Information System (INIS)

    Vare, Christophe

    2014-01-01

    EDF R and D has computer power that puts it amongst the top industrial research centers in the world. Its supercomputers and in-house codes as well as its experts represent important capabilities to support EDF activities (safety analyses, support to the design of new reactors, analysis of accidental situations non reproducible by experiments, better understanding of physics or complex system response, effects of uncertainties and identification of prominent parameters, qualification and optimization of processes and materials...). Advanced numerical simulation is a powerful tool allowing EDF to increase its competitiveness, improve its performance and the safety of its plants. On this issue, EDF made the choice to develop its own in-house codes, instead of using commercial software, in order to be able to capitalize its expertise and methodologies. This choice allowed as well easier technological transfer to the concerned business units or engineering divisions, fast adaptation of our simulation tools to emerging needs and the development of specific physics or functionalities not addressed by the commercial offer. During the last ten years, EDF has decided to open its in-house codes, through the Open Source way. This is the case for Code – Aster (structure analysis), Code – Saturne (computational fluid dynamics, CFD), TELEMAC (flow calculations in aquatic environment), SALOME (generic platform for Pre and Post-Processing) and SYRTHES (heat transfer in complex geometries), among others. The 3 open source software: Code – Aster, Code – Saturne and TELEMAC, are certified by the French Nuclear Regulatory Authority for many «Important to Safety» studies. Advanced simulation, which treats complex, multi-field and multi-physics problems, is of great importance for the assessment of nuclear safety issues. This paper will present 2 examples of advanced simulation using Code – Saturne for safety issues of nuclear power plants in the fields of R and D and

  13. Chemical Hazards and Safety Issues in Fusion Safety Design

    International Nuclear Information System (INIS)

    Cadwallader, L.C.

    2003-01-01

    Radiological inventory releases have dominated accident consequences for fusion; these consequences are important to analyze and are generally the most severe result of a fusion facility accident event. However, the advent of, or plan for, large-scale usage of some toxic materials poses the additional hazard of chemical exposure from an accident event. Examples of toxic chemicals are beryllium for magnetic fusion and fluorine for laser fusion. Therefore, chemical exposure consequences must also be addressed in fusion safety assessment. This paper provides guidance for fusion safety analysis. US Department of Energy (DOE) chemical safety assessment practices for workers and the public are reviewed. The US Environmental Protection Agency (EPA) has published some guidance on public exposure to releases of mixtures of chemicals, this guidance has been used to create an initial guideline for treating mixed radiological and toxicological releases in fusion; for example, tritiated hazardous dust from a tokamak vacuum vessel. There is no convenient means to judge the hazard severity of exposure to mixed materials. The chemical fate of mixed material constituents must be reviewed to determine if there is a separate or combined radiological and toxicological carcinogenesis, or if other health threats exist with radiological carcinogenesis. Recommendations are made for fusion facility chemical safety evaluation and safety guidance for protecting the public from chemical releases, since such levels are not specifically identified in the DOE fusion safety standard

  14. The challenges for global harmonisation of food safety norms and regulations: issues for India.

    Science.gov (United States)

    Prakash, Jamuna

    2014-08-01

    Safe and adequate food is a human right, safety being a prime quality attribute without which food is unfit for consumption. Food safety regulations are framed to exercise control over all types of food produced, processed and sold so that the customer is assured that the food consumed will not cause any harm. From the Indian perspective, global harmonisation of food regulations is needed to improve food and nutrition security, the food trade and delivery of safe ready-to-eat (RTE) foods at all places and at all times. The Millennium Development Goals (MDGs) put forward to transform developing societies incorporate many food safety issues. The success of the MDGs, including that of poverty reduction, will in part depend on an effective reduction of food-borne diseases, particularly among the vulnerable group, which includes women and children. Food- and water-borne illnesses can be a serious health hazard, being responsible for high incidences of morbidity and mortality across all age groups of people. Global harmonisation of food regulations would assist in facilitating food trade within and outside India through better compliance, ensuring the safety of RTE catered foods, as well as addressing issues related to the environment. At the same time, regulations need to be optimum, as overregulation may have undue negative effects on the food trade. © 2013 Society of Chemical Industry.

  15. Atomic physics with highly-charged heavy ions at the GSI future facility: The scientific program of the SPARC collaboration

    International Nuclear Information System (INIS)

    Stoehlker, Th.; Beier, T.; Beyer, H.F.; Bosch, F.; Braeuning-Demian, A.; Gumberidze, A.; Hagmann, S.; Kozhuharov, C.; Kuehl, Th.; Liesen, D.; Mann, R.; Mokler, P.H.; Quint, W.; Schuch, R.; Warczak, A.

    2005-01-01

    In the current report a short overview about the envisioned program of the atomic physics research collaboration SPARC (Stored Particle Atomic Research Collaboration, at the new international accelerator Facility for Antiproton and Ion Research (FAIR) at GSI is given. In addition, a condensed description of the planned experimental areas devoted to atomic physics research at the new facility is presented

  16. Outline of experimental schemes for measurements of thermophysical and transport properties in warm dense matter at GSI and FAIR

    International Nuclear Information System (INIS)

    Tauschwitz, Anna; Jacoby, Joachim; Maruhn, Joachim; Basko, Mikhail; Efremov, Vladimir; Iosilevskiy, Igor; Neumayer, Paul; Novikov, Vladimir; Tauschwitz, Andreas; Rosmej, Frank

    2010-01-01

    Different experimental schemes for investigation of warm dense matter produced with intense energetic ion beams are presented. The described target configurations allow direct measurements of thermophysical and transport properties of warm dense matter without hydrodynamic recalculations. The presented experiments will be realized at the current GSI synchrotron SIS-18 and the future FAIR facility in the framework of the WDM-collaboration.

  17. A working procedure for identifying emerging food safety issues at an early stage: Implications for European and international risk management practices

    NARCIS (Netherlands)

    Marvin, H.J.P.; Kleter, G.A.; Frewer, L.J.; Cope, S.F.; Wentholt, M.T.A.; Rowe, G.

    2009-01-01

    There is a need for early identification of emerging food safety issues in order to prevent them from developing into health risks. In this paper, various existing methods and procedures which can be used for early identification of safety issues are reviewed, including the monitoring of the

  18. Beam Diagnostics Challenges in the FAIR Project at GSI

    International Nuclear Information System (INIS)

    Peters, Andreas; Forck, Peter

    2006-01-01

    The planned FAIR (Facility for Antiproton and Ion Research) project consists of two heavy ion synchrotrons and four large storage rings, the existing GSI facility together with a new high-current proton linac will be used as the injector chain. The fast cycling, superconducting synchrotrons are build for high current operation with the aim of secondary ion and antiproton production. A large variety of low current secondary beams as well as the antiprotons are stored and cooled in the four storage rings. A complex operation scheme with multiple use of transport lines is foreseen. This demands an exceptional high dynamic range for the beam instrumentation. Due to the enormous beam power, non-destructive methods are mandatory for high currents as well as for the low current secondary beams due to the low repetition rate. Precise measurements of all beam parameters and automatic steering or feedback capabilities are required due to the necessary exploitation of the full ring acceptances. Moreover, online beam-corrections with short response times are mandatory for the fast ramping super-conducting magnets. An overview of the challenges and projected innovative solutions for various diagnostic installations will be given

  19. Development of a GSI-Based, 2D-VAR Data Assimilation System for Operational Wave Guidance at the National Weather Service

    Science.gov (United States)

    Flampouris, S.; Alves, H.; Pondeca, M.

    2016-02-01

    The US National Centers for Environmental Prediction (NCEP) provides wave guidance to the National Weather Service (NWS) via a suite of operational wave models, which include three global-scale systems. An approach is being developed to include data assimilation into the global wave models using a 2D version of NCEP's grid-point statistical interpolation (2D-GSI), as described in Derber & Rosatti (1989), and Pondeca et al (2011). As a first step to the global implementation of a wave DA system, a prototype is being developed that will consist of adding wave heights as an analysis variable to the operational Real-Time Mesoscale Analysis (RTMA), which provides hourly analyses of several near sea-surface meteorological parameters, and supports a variety of applications within the NWS. The core of the RTMA is a 2D version of the GSI, which is a variational data assimilation system, and the first guess for the wave-height analysis is provided by NCEP's global wave models. For the new application, the RTMA will be modified to reflect background error covariances consistent with wave-height fields for regional and nearshore applications. In addition, quality control modules for in situ and altimeter significant wave height have been developed and integrated into the system. The strengths and the performance of the 2D-GSI are illustrated with both in situ and satellite measurements of significant wave height in the NW Atlantic and the Gulf of Mexico. The validation of follows the typical cross-validation procedure of RTMA products, based on 10% of the observations, for a period of 15 days. The error statistics (mean, root-mean-square) of the wave-height analysis shows significant improvement, relative to the first guess.

  20. Factor Analysis and Framework Development for Incorporating Public Trust on Nuclear Safety issues

    Energy Technology Data Exchange (ETDEWEB)

    Cho, Seongkyung; Lee, Gyebong [The Myongji Univ., Seoul (Korea, Republic of); Lee, Gihyung; Lee, Gyehwi; Jeong, Jina [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

    2014-05-15

    The Korea Institute of Nuclear Safety (KINS), a regulatory expert organization in charge of nuclear safety in Korea, realized that a more fundamental and systematic analysis of activities is needed to actively meet the greater variety of concerns people have and increase the reliability of the results of regulation. Nuclear safety, a highly specialized field, has previously been discussed primarily from the viewpoint of the engineers who deal with the technology, but now 'public trust in nuclear safety' has to be viewed from the standpoint of the general public and from the socio-cultural perspective. Specific measures must be taken to examine which factors affect public trust and how we can secure and reproduce those factors to gain it. Also, an efficient system for incorporating public trust in nuclear safety must be established. In this study, various case studies were examined to identify the factors that affect public trust in nuclear safety. First, nuclear safety laws and information disclosure systems of major countries were examined by investigating data and conducting in-depth interviews. To explore a public framework concerning nuclear safety, big data of social media were analyzed. Also, Q methodology was used to analyze the risk schemata of the opinion leaders living in areas near nuclear power plants. Several surveys were conducted to analyze the amount of trust the public had in nuclear safety as well as their awareness of nuclear safety issues. Based on these analyses, factors affecting public trust in nuclear safety were extracted, and measures to build systems incorporating public trust in nuclear safety were proposed. This study addresses the public trust in nuclear safety on condition that the safety is ensured technically and mechanically.

  1. Factor Analysis and Framework Development for Incorporating Public Trust on Nuclear Safety issues

    International Nuclear Information System (INIS)

    Cho, Seongkyung; Lee, Gyebong; Lee, Gihyung; Lee, Gyehwi; Jeong, Jina

    2014-01-01

    The Korea Institute of Nuclear Safety (KINS), a regulatory expert organization in charge of nuclear safety in Korea, realized that a more fundamental and systematic analysis of activities is needed to actively meet the greater variety of concerns people have and increase the reliability of the results of regulation. Nuclear safety, a highly specialized field, has previously been discussed primarily from the viewpoint of the engineers who deal with the technology, but now 'public trust in nuclear safety' has to be viewed from the standpoint of the general public and from the socio-cultural perspective. Specific measures must be taken to examine which factors affect public trust and how we can secure and reproduce those factors to gain it. Also, an efficient system for incorporating public trust in nuclear safety must be established. In this study, various case studies were examined to identify the factors that affect public trust in nuclear safety. First, nuclear safety laws and information disclosure systems of major countries were examined by investigating data and conducting in-depth interviews. To explore a public framework concerning nuclear safety, big data of social media were analyzed. Also, Q methodology was used to analyze the risk schemata of the opinion leaders living in areas near nuclear power plants. Several surveys were conducted to analyze the amount of trust the public had in nuclear safety as well as their awareness of nuclear safety issues. Based on these analyses, factors affecting public trust in nuclear safety were extracted, and measures to build systems incorporating public trust in nuclear safety were proposed. This study addresses the public trust in nuclear safety on condition that the safety is ensured technically and mechanically

  2. The progress and issues of national nuclear and radiation safety supervision and MIS

    International Nuclear Information System (INIS)

    Zhou Kefei; Sun Guochen; Jiang Guang; Li Jingxi; Zhang Lin

    2009-01-01

    The article briefly describes the pre-planning construction of 'National Nuclear and Radiation Safety Supervision and Management Information System', Including the overall frame of the system and the main issues found in the work which affect and confine the progress of the program. Some recommendations are put forward. (authors)

  3. State Legislative Developments on Campus Sexual Violence: Issues in the Context of Safety

    Science.gov (United States)

    Morse, Andrew; Sponsler, Brian A.; Fulton, Mary

    2015-01-01

    NASPA--Student Affairs Administrators in Higher Education and Education Commission of the States (ECS) have partnered to address legislative developments and offer considerations for leaders in higher education and policy on two top-level safety issues facing the higher education community: campus sexual violence and guns on campus. The first in a…

  4. Challenges and opportunities for atomic physics at FAIR: The new GSI accelerator project

    Energy Technology Data Exchange (ETDEWEB)

    Hagmann, S. [Institut f. Kernphysik, University of Frankfurt (Germany) and GSI, Max Planckstr.1, Darmstadt (Germany)]. E-mail: s.hagmann@gsi.de; Beyer, H.F. [GSI, Max Planckstr.1, Darmstadt (Germany); Bosch, F. [GSI, Max Planckstr.1, Darmstadt (Germany); Braeuning-Demian, A. [GSI, Max Planckstr.1, Darmstadt (Germany); Kluge, H.-J. [GSI, Max Planckstr.1, Darmstadt (Germany); Kozhuharov, Ch. [GSI, Max Planckstr.1, Darmstadt (Germany); Kuehl, Th. [GSI, Max Planckstr.1, Darmstadt (Germany); Liesen, D. [GSI, Max Planckstr.1, Darmstadt (Germany); Stoehlker, Th. [GSI, Max Planckstr.1, Darmstadt (Germany); Ullrich, J. [Max Planck Inst. f. Kernphysik, Heidelberg (Germany); Moshammer, R. [Max Planck Inst. f. Kernphysik, Heidelberg (Germany); Mann, R. [GSI, Max Planckstr.1, Darmstadt (Germany); Mokler, P. [GSI, Max Planckstr.1, Darmstadt (Germany); Quint, W. [GSI, Max Planckstr.1, Darmstadt (Germany); Schuch, R. [Department of Physics, University of Stockholm (Sweden); Warczak, A. [Department of Physics, University of Cracow (Poland)

    2005-12-15

    We present a short overview of the current status of the new accelerator project FAIR at GSI with the new double synchrotron rings and the multi-storage rings. The key features of the new facility, which provides intense relativistic beams of stable and unstable nuclei, are introduced and their relation to the anticipated experimental programs in nuclear structure physics and antiproton physics is shown. The main emphasis in this overview is given to the atomic physics program with unique opportunities which will be provided e.g. by bare U{sup 92+} ions with kinetic energies continuously variable between relativistic energies corresponding to {gamma} up to {approx_equal}35 down to kinetic energies of such ions in traps corresponding to fractions of a Kelvin.

  5. Current status of environmental, health, and safety issues of lithium ion electric vehicle batteries

    Energy Technology Data Exchange (ETDEWEB)

    Vimmerstedt, L.J.; Ring, S.; Hammel, C.J.

    1995-09-01

    The lithium ion system considered in this report uses lithium intercalation compounds as both positive and negative electrodes and has an organic liquid electrolyte. Oxides of nickel, cobalt, and manganese are used in the positive electrode, and carbon is used in the negative electrode. This report presents health and safety issues, environmental issues, and shipping requirements for lithium ion electric vehicle (EV) batteries. A lithium-based electrochemical system can, in theory, achieve higher energy density than systems using other elements. The lithium ion system is less reactive and more reliable than present lithium metal systems and has possible performance advantages over some lithium solid polymer electrolyte batteries. However, the possibility of electrolyte spills could be a disadvantage of a liquid electrolyte system compared to a solid electrolyte. The lithium ion system is a developing technology, so there is some uncertainty regarding which materials will be used in an EV-sized battery. This report reviews the materials presented in the open literature within the context of health and safety issues, considering intrinsic material hazards, mitigation of material hazards, and safety testing. Some possible lithium ion battery materials are toxic, carcinogenic, or could undergo chemical reactions that produce hazardous heat or gases. Toxic materials include lithium compounds, nickel compounds, arsenic compounds, and dimethoxyethane. Carcinogenic materials include nickel compounds, arsenic compounds, and (possibly) cobalt compounds, copper, and polypropylene. Lithiated negative electrode materials could be reactive. However, because information about the exact compounds that will be used in future batteries is proprietary, ongoing research will determine which specific hazards will apply.

  6. CANDU reactors, their regulation in Canada, and the identification of relevant NRC safety issues

    International Nuclear Information System (INIS)

    Charak, I.; Kier, P.H.

    1995-04-01

    Atomic Energy of Canada, Limited (AECL) and its subsidiary in the US, are considering submitting the CANDU 3 design for standard design certification under 10 CFR Part 52. CANDU reactors are pressurized heavy water power reactors. They have some substantially different safety responses and safety systems than the LWRs that the commercial power reactor licensing regulations of the US Nuclear Regulatory Commission (NRC) have been developed to deal with. In this report, the authors discuss the basic design characteristics of CANDU reactors, specifically of the CANDU 3 where possible, and some safety-related consequences of these characteristics. The authors also discuss the Canadian regulatory provisions, and the CANDU safety systems that have evolved to satisfy the Canadian regulatory requirements as of December 1992. Finally, the authors identify NRC regulations, mainly in 10 CFR Parts 50 and 100, with issues for CANDU 3 reactor designs. In all, eleven such regulatory issues are identified. They are: (1) the ATWS rule (section 50.62); (2) station blackout (section 50.63); (3) conformance with Standard Review Plan (SRP); (4) appropriateness of the source term (section 50.34(f) and section 100.11); (5) applicability of reactor coolant pressure boundary (RCPB) requirements (section 50.55a, etc); (6) ECCS acceptance criteria (section 50.46)(b); (7) combustible gas control (section 50.44, etc); (8) power coefficient of reactivity (GDC 11); (9) seismic design (Part 100); (10) environmental impacts of the fuel cycle (section 51.51); and (11) (standards section 50.55a)

  7. Environmental, health and safety issues related to commercializing CuInSe{sub 2}-based photovoltaics

    Energy Technology Data Exchange (ETDEWEB)

    Eberspacher, C. [UNISUN, Newbury Park, CA (United States); Fthenakis, V.M.; Moskowtiz, P.D. [Brookhaven National Lab., Upton, NY (United States)

    1996-07-01

    Photovoltaics technology is rapidly evolving towards a new generation of low-cost thin film technologies. One of the most promising materials in this new generation is copper indium selenide (CuInSe{sub 2} or CIS). As with any new material, successful commercialization of CIS photovoltaic (PV) technology will require attention to environmental, health and safety issues, including consideration of the sources, usage, and end-of-product-life disposal and/or recycling of the constituent materials. This work focuses on three specific environmental, health and safety (EH and S) issues related to CIS PV: (1) economics are analyzed to determine their impact on materials use and re-use; (2) Federal and California State environmental disposal and waste handling regulations are analyzed to evaluate their impact on PV module manufacturing and end-of-life module handling; and (3) the logistics and economics of product recycling and waste disposal by industries with comparable EH and S issues are examined to quantify the corresponding options available for handling, disposing of and/or recycling manufacturing by-products and end-of-life modules.

  8. A Prototype Regional GSI-based EnKF-Variational Hybrid Data Assimilation System for the Rapid Refresh Forecasting System: Dual-Resolution Implementation and Testing Results

    Science.gov (United States)

    Pan, Yujie; Xue, Ming; Zhu, Kefeng; Wang, Mingjun

    2018-05-01

    A dual-resolution (DR) version of a regional ensemble Kalman filter (EnKF)-3D ensemble variational (3DEnVar) coupled hybrid data assimilation system is implemented as a prototype for the operational Rapid Refresh forecasting system. The DR 3DEnVar system combines a high-resolution (HR) deterministic background forecast with lower-resolution (LR) EnKF ensemble perturbations used for flow-dependent background error covariance to produce a HR analysis. The computational cost is substantially reduced by running the ensemble forecasts and EnKF analyses at LR. The DR 3DEnVar system is tested with 3-h cycles over a 9-day period using a 40/˜13-km grid spacing combination. The HR forecasts from the DR hybrid analyses are compared with forecasts launched from HR Gridpoint Statistical Interpolation (GSI) 3D variational (3DVar) analyses, and single LR hybrid analyses interpolated to the HR grid. With the DR 3DEnVar system, a 90% weight for the ensemble covariance yields the lowest forecast errors and the DR hybrid system clearly outperforms the HR GSI 3DVar. Humidity and wind forecasts are also better than those launched from interpolated LR hybrid analyses, but the temperature forecasts are slightly worse. The humidity forecasts are improved most. For precipitation forecasts, the DR 3DEnVar always outperforms HR GSI 3DVar. It also outperforms the LR 3DEnVar, except for the initial forecast period and lower thresholds.

  9. Breakout Session A: Safety Issues. Report from breakout session and discussion on safety issues

    International Nuclear Information System (INIS)

    Petit, Marc

    2013-01-01

    The first issue discussed during the breakout session on safety aspects of accident-tolerant fuels was the objective that must be assigned to the development of such concepts. The first goal should be to avoid, or at least limit, the release of radioactive materials into the environment in case of an accident. This implies that severe accidents (core melt) situations must be avoided. To reach this goal, the core geometry must remain coolable, even for accident scenarios worse than what current fuel designs are able to sustain. There was a consensus that the station blackout (SBO) is a good reference transient to evaluate the potential benefits from new, more robust, fuel designs. With respect to the present situation, the merits of new designs can be analysed with respect to three figures: - the 'grace period', i.e. the additional amount of time before the onset of core melt, during which more recovery actions can be made; - the amount of combustible gases produced; - the amount of radioactive materials released. It is important to note that those three values are not independent from one another. They may be understood as three different ways to measure the improvements arising from accident tolerant fuels. The notion of 'grace period' was discussed and it was suggested that it should be compared to the amount of time needed to switch from normal operation to accident management type of procedures. The participants agreed that the 'grace period' should be counted in hours (or even days but the realism of this last goal was questioned). In other words, there was a consensus that a 'grace period' of some minutes is pointless and definitely not worth the effort of developing and characterising the behaviour of new concepts. Although the purpose of accident-tolerant fuel development is to improve the core robustness in design basis accidents (DBA) and situations somewhat beyond like SBO, it was recognised that new concepts must

  10. Application of coupled codes for safety analysis and licensing issues

    International Nuclear Information System (INIS)

    Langenbuch, S.; Velkov, K.

    2006-01-01

    An overview is given on the development and the advantages of coupled codes which integrate 3D neutron kinetics into thermal-hydraulic system codes. The work performed within GRS by coupling the thermal-hydraulic system code ATHLET and the 3D neutronics code QUABOX/CUBBOX is described as an example. The application of the coupled codes as best-estimate simulation tools for safety analysis is discussed. Some examples from German licensing practices are given which demonstrate how the improved analytical methods of coupled codes have contributed to solve licensing issues related to optimized and more economical use of fuel. (authors)

  11. Worker health and safety and climate change in the Americas: issues and research needs

    Directory of Open Access Journals (Sweden)

    Max Kiefer

    Full Text Available SYNOPSIS This report summarizes and discusses current knowledge on the impact that climate change can have on occupational safety and health (OSH, with a particular focus on the Americas. Worker safety and health issues are presented on topics related to specific stressors (e.g., temperature extremes, climate associated impacts (e.g., ice melt in the Arctic, and a health condition associated with climate change (chronic kidney disease of non-traditional etiology. The article discusses research needs, including hazards, surveillance, and risk assessment activities to better characterize and understand how OSH may be associated with climate change events. Also discussed are the actions that OSH professionals can take to ensure worker health and safety in the face of climate change.

  12. Radiation effects on reactor pressure vessel supports

    International Nuclear Information System (INIS)

    Johnson, R.E.

    1996-05-01

    The purpose of this report is to present the findings from the work done in accordance with the Task Action Plan developed to resolve the Nuclear Regulatory Commission (NRC) Generic Safety Issue No. 15, (GSI-15). GSI-15 was established to evaluate the potential for low-temperature, low-flux-level neutron irradiation to embrittle reactor pressure vessel (RPV) supports to the point of compromising plant safety. An evaluation of surveillance samples from the High Flux Isotope Reactor (HFIR) at the Oak Ridge National Laboratory (ORNL) had suggested that some materials used for RPV supports in pressurized-water reactors could exhibit higher than expected embrittlement rates. However, further tests designed to evaluate the applicability of the HFIR data to reactor RPV supports under operating conditions led to the conclusion that RPV supports could be evaluated using traditional method. It was found that the unique HFIR radiation environment allowed the gamma radiation to contribute significantly to the embrittlement. The shielding provided by the thick steel RPV shell ensures that degradation of RPV supports from gamma irradiation is improbable or minimal. The findings reported herein were used, in part, as the basis for technical resolution of the issue

  13. Biology experiments at UNILAC. Reports from the biology user meeting, GSI, 3 October 1985

    International Nuclear Information System (INIS)

    1985-10-01

    On 3 Oct 1985, an internal Biology User Meeting of the groups working at GSI was arranged for the purpose of exchanging information and having discussions. It was found that the experimental data obtained so far are quite complex, and that the attempts at a theoretical treatment are still in a very early stage. To keep the discussion going, this report therefore presents the contributions of the various groups as far as these have been available. Most of the information was not in finished reports but in the form of diagrams and tables with explanations, sometimes even in the form of handwritten notes or sketches. Separate records are available for 13 contributions. (orig./MG) [de

  14. Nuclear power and related safety issues

    International Nuclear Information System (INIS)

    Valdezco, Eulinia M.

    2009-01-01

    There are a cluster of trends that reinforce the importance of nuclear power on the world scene. Energy is the essential underpinning for economic and societal progress and, as the developing world advances, the demand for energy is growing significantly. At the same time, the carbon-intensive sources of energy on which the world has traditionally relied - in particular, coal, oil, and natural gas - pose grave threats because the growing concentrations of carbon dioxide in the atmosphere will bring about climate and ocean acidification. At the same time, rising and volatile fossil fuel prices, coupled with concerns about the security of supplies of oil and gas, enhance interest in sources of energy that do not pose the same costs and risks. As an important part of the world's response to these threats, many countries are embarking on either new or expanded nuclear power programs, more commonly referred to as a nuclear renaissance. The construction of nuclear power plants is under consideration in over thirty countries that do not currently use nuclear power. For new entrants that may have experience in constructing and operating large-scale industrial and infrastructure projects, they may not be fully familiar with the unique requirements of nuclear power and may not be fully recognize the major commitments and understandings that they must assume. Additionally, an understanding of the full range of obligations may have diminished in those countries with only one or a few reactors and where nuclear construction has not been undertaken for a long time. It is therefore in the interest of all to ensure that every country with a nuclear power program has the resources, expertise, authority and capacity to assure safety in a complete and effective manner and is committed to doing so. This presentation will outline some of the more important national infrastructure considerations including nuclear safety issues for launching a nuclear power program. An update on the

  15. Radiological protection, safety and security issues in the industrial and medical applications of radiation sources

    International Nuclear Information System (INIS)

    Vaz, Pedro

    2015-01-01

    The use of radiation sources, namely radioactive sealed or unsealed sources and particle accelerators and beams is ubiquitous in the industrial and medical applications of ionizing radiation. Besides radiological protection of the workers, members of the public and patients in routine situations, the use of radiation sources involves several aspects associated to the mitigation of radiological or nuclear accidents and associated emergency situations. On the other hand, during the last decade security issues became burning issues due to the potential malevolent uses of radioactive sources for the perpetration of terrorist acts using RDD (Radiological Dispersal Devices), RED (Radiation Exposure Devices) or IND (Improvised Nuclear Devices). A stringent set of international legally and non-legally binding instruments, regulations, conventions and treaties regulate nowadays the use of radioactive sources. In this paper, a review of the radiological protection issues associated to the use of radiation sources in the industrial and medical applications of ionizing radiation is performed. The associated radiation safety issues and the prevention and mitigation of incidents and accidents are discussed. A comprehensive discussion of the security issues associated to the global use of radiation sources for the aforementioned applications and the inherent radiation detection requirements will be presented. Scientific, technical, legal, ethical, socio-economic issues are put forward and discussed. - Highlights: • The hazards associated to the use of radioactive sources must be taken into account. • Security issues are of paramount importance in the use of radioactive sources. • Radiation sources can be used to perpetrate terrorist acts (RDDs, INDs, REDs). • DSRS and orphan sources trigger radiological protection, safety and security concerns. • Regulatory control, from cradle to grave, of radioactive sources is mandatory.

  16. Report of the review of WWER-1000 safety issues resolution at Temelin nuclear power plant, Temelin, Czech Republic 11 to 15 March 1996

    International Nuclear Information System (INIS)

    Almeida, C.; Hoehn, J.; Seiberling, R.; Chambon, J.L.; Fil, N.S.; Munoz, A.; Roennberg, G.; Wenk, W.

    1996-01-01

    At the request of the Government of the Czech Republic, the IAEA conducted, in the period of 11-15 March 1996, a mission to review the resolution of WWER-1000 safety issues at Temelin NPP. These safety issues have been identified for WWER-1000 model 320 reactors and ranked according to their importance to safety in the frameworks of the IAEA Extrabudgetary Programme on Safety of WWER and RBMK Nuclear Power Plants. The Temelin NPP is a WWER-1000 and was originally designed according to standards of the former Soviet Union. After a series of reviews in the 1980s, a decision was taken by the Temelin NPP management to upgrade the design of Temelin, including the supply of fuel and instrumentation and control by a western company. The objective of the mission was to review the response of Temelin to the safety issues identified by the IAEA. The mission assessed the current Temelin design, including proposed modifications and plans for operation at Temelin, in the light of the IAEA recommendations for each relevant issue. The present report contains the mission's general conclusions and recommendations and an overview of the review performed in each topical area. The attachment contains a brief summary of the discussions on each individual safety issue and associated conclusions and recommendations. 3 refs

  17. Technical findings and regulatory analysis for Generic Safety Issue II.E.4.3, ''Containment Integrity Check''

    International Nuclear Information System (INIS)

    Serkiz, A.W.

    1988-04-01

    This report contains the technical findings and regulatory analysis for Generic Safety Issue II.E.4.3, ''Containment Integrity Check.'' An evaluation of the containment isolation history from 1965 to 1983 reveals that (except for a small number of events) containment integrity has been maintained and that the majority of reported events have been events related to exceeding Technical Specification limits (or 0.6 of the allowable leakage level). In addition, more recent risk analyses have shown that allowable leakage rates even if increased by a factor of 10 would not significantly increase risk. Potential methods of continuous monitoring are identified and evaluated. Therefore, these technical findings and risk evaluations support closure of Generic Safety Issue II.E.4.3

  18. The optimized advanced demonstrator for the SC CW heavy ion linac at GSI

    Energy Technology Data Exchange (ETDEWEB)

    Schwarz, Malte; Basten, Markus; Busch, Marco; Dziuba, Florian; Podlech, Holger; Ratzinger, Ulrich; Tiede, Rudolf [Institut fuer Angewandte Physik, Goethe-Universitaet Frankfurt am Main (Germany); Gettmann, Viktor; Heilmann, Manuel [GSI Helmholtzzentrum, Darmstadt (Germany); Barth, Winfried; Mickat, Sascha [GSI Helmholtzzentrum, Darmstadt (Germany); HIM, Helmholtzinstitut, Mainz (Germany); Miski-Oglu, Maksym [HIM, Helmholtzinstitut, Mainz (Germany); Aulenbacher, Kurt [KPH, Johannes Gutenberg Universitaet, Mainz (Germany)

    2016-07-01

    For future experiments with heavy ions at the coulomb barrier within the SHE research project a multi-stage R and D program of GSI, HIM and IAP is currently under progress. It aims at developing a superconducting (sc) continuous wave (cw) LINAC with multiple CH-cavities as key components. As intermediate step towards the whole LINAC, the Optimized Advanced Demonstrator is proposed. Consisting of short CH-cavities and cryostats, it could provide several advantages regarding velocity acceptance, higher tolerance with respect to frequency and field deviation, easier mounting, handling and maintenance as well as a more robust longitudinal beam dynamic. The beam dynamics concept is based on EQUUS (Equidistant Multigap Structure) constant-beta cavities. The corresponding simulations for the proposed next extension stage - the Optimized Advanced Demonstrator - will be presented.

  19. Safety issues for LMFBR: important features drawn from the assessments of Superphenix

    International Nuclear Information System (INIS)

    Natta, M.

    2002-01-01

    Superphenix, which is built on the site of Creys-Malville, is still the biggest LMFBR plant that has been in operation. It is a pool type reactor, as Phenix and the RNR 1 500 and EFR projects. After the analysis of the preliminary safety (1974-1975), the construction was authorised by decree of the Prime Minister in 1977, the authorization for fuel loading and star-up to 3% was given by the minister of industry in July 1985 and full power was achieved in December 1986. The plant was operated until the end of December 1996, producing the equivalent of 320 EFPD, corresponding to half of the maximum barn-up of the first core. The plant was definitively stopped on the 20. of April 1998 by a decision of the French government. During this period of 25 years of licensing, construction and operation of Superphenix, others discussions and preliminary licensing procedures were started for new projects, mainly the RNR 1500 French project and the EFR European project. The operation of Superphenix was also marked by several incidents, which led to additional licensing procedures and important modifications. This period was also marked by an important work of research and development in the safety field, mostly related to the issues concerning hypothetical core disruptive accidents (HCDA) and sodium fires; further, this period was marked by the Three Mile Island accident in 1979 and the Chernobyl accident in 1986. The purpose of this paper is to present some items which were discussed during this period of 25 years and which should be of interest for future LMFBRs. In this presentation, we shall discuss the key issues concerning the safety criteria and options taken with respect to severe accidents, i.e. core melt accidents, giving details on some specific which are less known since they were assessed only lately for Superphenix, sometimes in connection with the on-going safety researches. (author)

  20. Key regulatory and safety issues emerging NEA activities. Lessons Learned from Fukushima Dai-ichi NPS Accident - Key Regulatory and Safety Issues

    International Nuclear Information System (INIS)

    Nakoski, John

    2013-01-01

    A presentation was provided on the key safety and regulatory issues and an update of activities undertaken by the NEA and its members in response to the accident at the Fukushima Daiichi nuclear power stations (NPS) on 11 March 2011. An overview of the accident sequence and the consequences was provided that identified the safety functions that were lost (electrical power, core cooling, and primary containment) that lead to units 1, 2, and 3 being in severe accident conditions with large off-site releases. Key areas identified for which activities of the NEA and member countries are in progress include accident management; defence-in-depth; crisis communication; initiating events; operating experience; deterministic and probabilistic assessments; regulatory infrastructure; radiological protection and public health; and decontamination and recovery. For each of these areas, a brief description of the on-going and planned NEA activities was provided within the three standing technical committees of the NEA with safety and regulatory mandates (the Committee on Nuclear Regulatory Activities - CNRA, the Committee on the Safety of Nuclear Installations - CSNI, and the Committee on Radiation Protection and Public Health - CRPPH). On-going activities of CNRA include a review of enhancement being made to the regulatory aspects for the oversight of on-site accident management strategies and processes in light of the lessons learned from the accident; providing guidance to regulators on crisis communication; and supporting the peer review of the safety assessments of risk-significant research reactor facilities in light of the accident. Within the scope of the CSNI mandate, activities are being undertaken to better understand accident progression; characteristics of new fuel designs; and a benchmarking study of fast-running software for estimating source term under severe accident conditions to support protective measure recommendations. CSNI also has ongoing work in human

  1. RBMK nuclear power plants: Generic safety issues. A publication of the extrabudgetary programme on the safety of WWER and RBMK nuclear power plants

    International Nuclear Information System (INIS)

    1996-05-01

    This report has been prepared on the basis of above mentioned report and it is intended to provide information on RBMK NPPs generic safety issues. As all other insights, recommendations and conclusions resulting from the IAEA Programme, this report is intended to assist national decision makers, who have sole responsibility for the regulation and safe operation of their nuclear power plants. It also serves to focus national and international projects on priority of the RBMK safety improvements. 23 refs, 10 figs, 3 tabs

  2. Level of knowledge among the population of radiation safety basic issues

    Directory of Open Access Journals (Sweden)

    S. A. Zelencova

    2015-01-01

    Full Text Available The goal of research was to determine the level of knowledge among the population on issues like sources of ionising radiation, methods of ionising radiation measurement, measures of self-protection in case of threating or actual radioactive pollution in the district, and to study self-estimation by the population of their knowledge of radiation safety issues. Research was carried out using the method of questioning of population groups in three regions close to the places of previous peaceful nuclear explosions (Arkhangelsk, Murmansk and Tyumen regions, and in five Far East regions of the Russian Federation (Kamchatka, Khabarovsk, Primorsky, Magadan and South-Sakhalin regions after radiation accident in Japan at "Fukushima-1" NPP. This research included processing of 243 questionnaires from the regions close to places of previous peaceful nuclear explosions and 216 questionnaires from the Far East regions.The analysis of obtained questioning results enabled to make the following conclusions: the level of knowledge among the population about the basic concepts of radiation safety appeared to be generally low among respondents of all eight territories. Considerable number of respondents in seven groups correctly mentioned the x-ray device as a source of ionising radiation (from 71 to 88 % of answers. In Murmansk region – only 52 % of the answers. Respondents of the same seven groups often correctly answered the question on how to detect ionising radiation (only with devices – from 68 to 98 % in different groups. The smallest number of correct answers to this question (42 % is also noted among respondents from the Murmansk region.Level of knowledge on self-protection measures at threating or actual radioactive pollution of the places of residence appeared a little higher among the Far East region population, who had actual concerns regarding the threat of radioactive pollution at the present time. However, in all eight investigated groups

  3. Road safety in a globalised and more sustainable world: current issues and future challenges.

    Science.gov (United States)

    Daniels, Stijn; Risser, Ralf

    2014-01-01

    Although many countries have had considerable success in reducing traffic injuries over recent decades, there are still some fundamental problems in this area. At the same time, there is increasing focus on road safety research and policy development in the context of globalisation, sustainability, liveability and health. This special section presents a selection of papers that were presented at the annual ICTCT workshop held on the 8th and 9th of November 2012 in Hasselt, Belgium, and accepted for publication in Accident Analysis and Prevention following the journal's reviewing procedure. The aim of the ICTCT workshop was to analyse road safety facts, data and visions for the future in the wider context of current issues and future challenges in road safety. Copyright © 2013 Elsevier Ltd. All rights reserved.

  4. Characterization strategy for the flammable gas safety issue

    International Nuclear Information System (INIS)

    Stewart, C.W.; Brewster, M.E.; Roberts, J.S.

    1997-06-01

    The characterization strategy for resolving the flammable gas safety issue for Hanford waste tanks is based on a structured logic diagram (SLD) that displays the outcomes necessary to reach the desired goal of making flammable gas risk acceptable. The diagram provides a structured path that can identify all information inputs, data as well as models, needed to achieve the goal. Tracing the path from need to outcome provides an immediate and clear justification and defense of a specific need. The diagram itself is a open-quote picture of a risk calculation close-quote and forms the basis for a quantitative model of risk. The SLID, with the risk calculation, identifies options for characterization, mitigation, and controls that have the maximum effect in reducing risk. It provides quantitative input to risk-based decision making so that options are chosen for maximum impact at least cost

  5. Effect of Containment Spray Additives on the Chemical Effect after a Loss of Coolant Accident in Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Seung Chan; Park, Jong Woon; Lee, Guen Sung [KOREA HYDRO and NUCLEAR POWER Co., Daejeon (Korea, Republic of)

    2007-10-15

    As a part of USNRC GSI-191, evaluation of Kori Unit 1 ECCS recirculation sump performance has been carried out in 2006. The work is derived from the result of first PSR(Periodic Safety Review) of Kori Unit1. In this work, we have considered the replacement of spray additive in containment building to solve issues of GSI-191 and GL2004-02. We estimated the chemical effect of changing NaOH into TSP(Trisodium Phosphate) based on SRP(Standard Review Plan) 6.5.2. Rev.02. WCAP-16530 methodology is used to compare chemical effects of spray additive(or buffering agents). In the other side, chemical thermodynamic simulation can be utilized. Herein, the results using WCAP-16530 methodology and chemical simulation are presented.

  6. Construction and building of a compact RFQ spiral structure for the stopping of highly charged heavy ion beams for the HITRAP project of the GSI; Konstruktion und Aufbau einer kompakten RFQ-Spiral-Struktur zum Abbremsen hochgeladener Schwerionenstrahlen fuer das HITRAP-Projekt der GSI

    Energy Technology Data Exchange (ETDEWEB)

    Hofmann, B.

    2007-07-01

    For experiments of the atomic-physics group of the GSI in Darmstadt an ion stopper is built, which will make low-energetic, extremely highly charged ions available. The plannings for the so-called HITRAP (highly charged ion's trap) began at the beginning of the ninetieth. With this facility highly-charged heavy ions shall be stopped in two stages to very low, thermal velocities, and be available for highly precise mass spectroscopy, measurements of the g factor of the bound electron of hydrogen-like ions, and other atomic-physics experiments. This decelerator facility shall first be built in the reinjection channel behind the ESR with the possibility, to apply all components later in teh extension of the GSI in the framework of the FAIR project in the facility for low-energetic antiprotons and ions to be newly built. the present thesis treats the development and the building of an integrated RFQ debuncher stopping accelerator, which represents a part of the HITRAP stopping structures. By this the ion beam is stopped from the IH stopping accelerator with an energy of 500 keV/u to 5 keV/u. By the integrated spiral buncher the beam can be fitted in energy and energy deviation to the subsequent cooler trap. In this thesis the foundations of the particle dynamics in a RFQ accelerator for the stopping of particle beams were worked out and realized, the particle-dynamics calculations necessary for the lay-out of such a structure performed with RFQSim, suitable RF structures with the simulation program Microwave Studio developed and studied, as well as the thermal load of the structures studied with the finite-element code ALGOR. A further, central topic of this thesis is the building and the tuning of the RFQ structure in order to reach a homogeneous as possible field distribution along the electrodes. Measurements of the fields in the RFQ were performed with a disturbing condenser, at the debuncher with a disturbing body. After successfully performed vacuum tests at

  7. Environmental, health, and safety issues of fuel cells in transportation. Volume 1: Phosphoric acid fuel-cell buses

    Energy Technology Data Exchange (ETDEWEB)

    Ring, S

    1994-12-01

    The U.S. Department of Energy (DOE) chartered the Phosphoric Acid Fuel-Cell (PAFC) Bus Program to demonstrate the feasibility of fuel cells in heavy-duty transportation systems. As part of this program, PAFC- powered buses are being built to meet transit industry design and performance standards. Test-bed bus-1 (TBB-1) was designed in 1993 and integrated in March 1994. TBB-2 and TBB-3 are under construction and should be integrated in early 1995. In 1987 Phase I of the program began with the development and testing of two conceptual system designs- liquid- and air-cooled systems. The liquid-cooled PAFC system was chosen to continue, through a competitive award, into Phase H, beginning in 1991. Three hybrid buses, which combine fuel-cell and battery technologies, were designed during Phase III. After completing Phase II, DOE plans a comprehensive performance testing program (Phase HI) to verify that the buses meet stringent transit industry requirements. The Phase III study will evaluate the PAFC bus and compare it to a conventional diesel bus. This NREL study assesses the environmental, health, and safety (EH&S) issues that may affect the commercialization of the PAFC bus. Because safety is a critical factor for consumer acceptance of new transportation-based technologies the study focuses on these issues. The study examines health and safety together because they are integrally related. In addition, this report briefly discusses two environmental issues that are of concern to the Environmental Protection Agency (EPA). The first issue involves a surge battery used by the PAFC bus that contains hazardous constituents. The second issue concerns the regulated air emissions produced during operation of the PAFC bus.

  8. Public involvement in environmental, safety and health issues at the DOE Nuclear Weapons Complex

    International Nuclear Information System (INIS)

    Taylor, Laura L.; Morgan, Robert P.

    1992-01-01

    The state of public involvement in environmental, safety, and health issues at the DOE Nuclear Weapons Complex is assessed through identification of existing opportunities for public involvement and through interviews with representatives of ten local citizen groups active in these issues at weapons facilities in their communities. A framework for analyzing existing means of public involvement is developed. On the whole, opportunities for public involvement are inadequate. Provisions for public involvement are lacking in several key stages of the decision-making process. Consequently, adversarial means of public involvement have generally been more effective than cooperative means in motivating change in the Weapons Complex. Citizen advisory boards, both on the local and national level, may provide a means of improving public involvement in Weapons Complex issues. (author)

  9. Studies on fission with ALADIN. Precise and simultaneous measurement of fission yields, total kinetic energy and total prompt neutron multiplicity at GSI

    International Nuclear Information System (INIS)

    Martin, Julie-Fiona; Taieb, Julien; Chatillon, Audrey; Belier, Gilbert; Boutoux, Guillaume; Ebran, Adeline; Gorbinet, Thomas; Grente, Lucie; Laurent, Benoit; Pellereau, Eric; Alvarez-Pol, Hector; Ayyad, Yassid; Benlliure, Jose; Cortina Gil, Dolores; Caamano, Manuel; Fernandez Dominguez, Beatriz; Paradela, Carlos; Ramos, Diego; Rodriguez-Sanchez, Jose-Luis; Vargas, Jossitt; Audouin, Laurent; Tassan-Got, Laurent; Aumann, Thomas; Casarejos, Enrique; Farget, Fanny; Rodriguez-Tajes, Carme; Heinz, Andreas; Jurado, Beatriz; Kelic-Heil, Aleksandra; Kurz, Nikolaus; Nociforo, Chiara; Pietri, Stephane; Rossi, Dominic; Schmidt, Karl-Heinz; Simon, Haik; Voss, Bernd; Weick, Helmut

    2015-01-01

    A novel technique for fission studies, based on the inverse kinematics approach, is presented. Following pioneering work in the nineties, the SOFIA Collaboration has designed and built an experimental set-up dedicated to the simultaneous measurement of isotopic yields, total kinetic energies and total prompt neutron multiplicities, by fully identifying both fission fragments in coincidence, for the very first time. This experiment, performed at GSI, permits to study the fission of a wide variety of fissioning systems, ranging from mercury to neptunium, possibly far from the valley of stability. A first experiment, performed in 2012, has provided a large array of unprecedented data regarding the nuclear fission process. An excerpt of the results is presented. With this solid starter, further improvements of the experimental set-up are considered, which are consistent with the expected developments at the GSI facility, in order to measure more fission observables in coincidence. The completeness reached in the SOFIA data, permits to scrutinize the correlations between the interesting features of fission, offering a very detailed insight in this still unraveled mechanism. (orig.)

  10. Studies on fission with ALADIN. Precise and simultaneous measurement of fission yields, total kinetic energy and total prompt neutron multiplicity at GSI

    Energy Technology Data Exchange (ETDEWEB)

    Martin, Julie-Fiona; Taieb, Julien; Chatillon, Audrey; Belier, Gilbert; Boutoux, Guillaume; Ebran, Adeline; Gorbinet, Thomas; Grente, Lucie; Laurent, Benoit; Pellereau, Eric [CEA DAM Bruyeres-le-Chatel, Arpajon (France); Alvarez-Pol, Hector; Ayyad, Yassid; Benlliure, Jose; Cortina Gil, Dolores; Caamano, Manuel; Fernandez Dominguez, Beatriz; Paradela, Carlos; Ramos, Diego; Rodriguez-Sanchez, Jose-Luis; Vargas, Jossitt [Universidad de Santiago de Compostela, Santiago de Compostela (Spain); Audouin, Laurent; Tassan-Got, Laurent [CNRS/IN2P3, IPNO, Orsay (France); Aumann, Thomas [Technische Universitaet Darmstadt, Darmstadt (Germany); Casarejos, Enrique [Universidad de Vigo, Vigo (Spain); Farget, Fanny; Rodriguez-Tajes, Carme [CNRS/IN2P3, GANIL, Caen (France); Heinz, Andreas [Chalmers University of Technology, Gothenburg (Sweden); Jurado, Beatriz [CNRS/IN2P3, CENBG, Gradignan (France); Kelic-Heil, Aleksandra; Kurz, Nikolaus; Nociforo, Chiara; Pietri, Stephane; Rossi, Dominic; Schmidt, Karl-Heinz; Simon, Haik; Voss, Bernd; Weick, Helmut [GSI Helmholtzzentrum fuer Schwerionenforschung GmbH, Darmstadt (Germany)

    2015-12-15

    A novel technique for fission studies, based on the inverse kinematics approach, is presented. Following pioneering work in the nineties, the SOFIA Collaboration has designed and built an experimental set-up dedicated to the simultaneous measurement of isotopic yields, total kinetic energies and total prompt neutron multiplicities, by fully identifying both fission fragments in coincidence, for the very first time. This experiment, performed at GSI, permits to study the fission of a wide variety of fissioning systems, ranging from mercury to neptunium, possibly far from the valley of stability. A first experiment, performed in 2012, has provided a large array of unprecedented data regarding the nuclear fission process. An excerpt of the results is presented. With this solid starter, further improvements of the experimental set-up are considered, which are consistent with the expected developments at the GSI facility, in order to measure more fission observables in coincidence. The completeness reached in the SOFIA data, permits to scrutinize the correlations between the interesting features of fission, offering a very detailed insight in this still unraveled mechanism. (orig.)

  11. Key considerations and safety issues for the stretch power uprate at Chinshan Nuclear Power Station

    Energy Technology Data Exchange (ETDEWEB)

    Huang, P., E-mail: u808966@taipower.com.tw [Taiwan Power Company, Taipei, Taiwan (China)

    2014-07-01

    The Taiwan Power Company (TPC) has elected in recent years to implement the power uprate program as a key measure to improve the performance for TPC's nuclear power plants. The Measurement Uncertainty Recapture (MUR) power uprate for the TPC's three operating plants (reported in 16th PBNC) had been successfully implemented by July 2009. For the stretch power uprate (SPU) followed, the magnitude of uprate (~3%) is determined based on the available margins for original plant design, constant pressure approach (BWR) is adopted to simplify the evaluation, and major plant modifications are not considered. As the first application, the SPU safety analysis report (SAR) for the Chinshan plant was submitted to the ROCAEC in December 2010. A review task force was organized by the ROCAEC to perform a very thorough review. As the licensing bases are fully re-examined during the review process, many important issues have been identified and addressed. The key issues resolved include: conformance of SAR to ROCAEC's review guidance; re-examination of post-Fukushima comprehensive safety assessment; qualification of containment protective coatings; GL 96-06 (Assurance of Equipment Operability and Containment Integrity During DBA Conditions); credit for Containment Accident Pressure; issue for Annulus Pressurization Loads Evaluation. These issues required very extensive efforts to resolve. With the cooperative efforts by TPC and contractor (Institute of Nuclear Energy Research), however, all the issues were fully clarified and SAR was approved by ROCAEC on November 15, 2012. The first step SPU (2% OLTP) was successfully implemented in November 2012 at both units. (author)

  12. Tune measurements with high intensity ion beams at GSI SIS-18

    Energy Technology Data Exchange (ETDEWEB)

    Singh, Rahul [GSI, Darmstadt (Germany); TEMF, TU Darmstadt (Germany); Forck, Peter; Kowina, Piotr; Kaufmann, Wolfgang [GSI, Darmstadt (Germany); Weiland, Thomas [TEMF, TU Darmstadt (Germany)

    2012-07-01

    A precise tune measurement during a full accelerating cycle is required to achieve stable high current operation. A new system has been commissioned at GSI for position, orbit and tune measurements. It consists of three distinct parts; an exciter which provides power to excite coherent betatron oscillations in the bunched beam; Fast ADCs to digitize the BPM signals at 125 MSa/s; the post processing electronics uses digitized BPM signals to acquire one position value per bunch. Subsequently the baseband tune is determined by Fourier transformation of the position data. Experiments were conducted to understand the effects of high beam intensity on tune at injection plateau (11.4 MeV/u) and during acceleration ramp (11.4-600 MeV/u). These experiments were performed with U{sup 73+} and Ar{sup 18+} ion beam at highest achievable intensities of 2.10{sup 9} and 2.5.10{sup 10} respectively. Tune shift with increased intensity was observed. The working principle of the tune measurement system and observed high intensity effects on tune will be reported in this contribution.

  13. IAEA databases on safety issues and plant status for Central and Eastern European NPPs

    International Nuclear Information System (INIS)

    Czibolya, L.

    1995-01-01

    The main principles of the database development for safety issues of WWER and RBMK reactors are described. The IAEA contribution to the G-24 Project Data Bank and an analysis of gaps and overlaps in assistance projects is given. As an example the database on WWER-440/VV-230 type reactors is shown. (HP)

  14. Feasibility Study of Using Gemstone Spectral Imaging (GSI) and Adaptive Statistical Iterative Reconstruction (ASIR) for Reducing Radiation and Iodine Contrast Dose in Abdominal CT Patients with High BMI Values.

    Science.gov (United States)

    Zhu, Zheng; Zhao, Xin-ming; Zhao, Yan-feng; Wang, Xiao-yi; Zhou, Chun-wu

    2015-01-01

    To prospectively investigate the effect of using Gemstone Spectral Imaging (GSI) and adaptive statistical iterative reconstruction (ASIR) for reducing radiation and iodine contrast dose in abdominal CT patients with high BMI values. 26 patients (weight > 65kg and BMI ≥ 22) underwent abdominal CT using GSI mode with 300mgI/kg contrast material as study group (group A). Another 21 patients (weight ≤ 65kg and BMI ≥ 22) were scanned with a conventional 120 kVp tube voltage for noise index (NI) of 11 with 450mgI/kg contrast material as control group (group B). GSI images were reconstructed at 60keV with 50%ASIR and the conventional 120kVp images were reconstructed with FBP reconstruction. The CT values, standard deviation (SD), signal-noise-ratio (SNR), contrast-noise-ratio (CNR) of 26 landmarks were quantitatively measured and image quality qualitatively assessed using statistical analysis. As for the quantitative analysis, the difference of CNR between groups A and B was all significant except for the mesenteric vein. The SNR in group A was higher than B except the mesenteric artery and splenic artery. As for the qualitative analysis, all images had diagnostic quality and the agreement for image quality assessment between the reviewers was substantial (kappa = 0.684). CT dose index (CTDI) values for non-enhanced, arterial phase and portal phase in group A were decreased by 49.04%, 40.51% and 40.54% compared with group B (P = 0.000), respectively. The total dose and the injection rate for the contrast material were reduced by 14.40% and 14.95% in A compared with B. The use of GSI and ASIR provides similar enhancement in vessels and image quality with reduced radiation dose and contrast dose, compared with the use of conventional scan protocol.

  15. Feasibility Study of Using Gemstone Spectral Imaging (GSI and Adaptive Statistical Iterative Reconstruction (ASIR for Reducing Radiation and Iodine Contrast Dose in Abdominal CT Patients with High BMI Values.

    Directory of Open Access Journals (Sweden)

    Zheng Zhu

    Full Text Available To prospectively investigate the effect of using Gemstone Spectral Imaging (GSI and adaptive statistical iterative reconstruction (ASIR for reducing radiation and iodine contrast dose in abdominal CT patients with high BMI values.26 patients (weight > 65kg and BMI ≥ 22 underwent abdominal CT using GSI mode with 300mgI/kg contrast material as study group (group A. Another 21 patients (weight ≤ 65kg and BMI ≥ 22 were scanned with a conventional 120 kVp tube voltage for noise index (NI of 11 with 450mgI/kg contrast material as control group (group B. GSI images were reconstructed at 60keV with 50%ASIR and the conventional 120kVp images were reconstructed with FBP reconstruction. The CT values, standard deviation (SD, signal-noise-ratio (SNR, contrast-noise-ratio (CNR of 26 landmarks were quantitatively measured and image quality qualitatively assessed using statistical analysis.As for the quantitative analysis, the difference of CNR between groups A and B was all significant except for the mesenteric vein. The SNR in group A was higher than B except the mesenteric artery and splenic artery. As for the qualitative analysis, all images had diagnostic quality and the agreement for image quality assessment between the reviewers was substantial (kappa = 0.684. CT dose index (CTDI values for non-enhanced, arterial phase and portal phase in group A were decreased by 49.04%, 40.51% and 40.54% compared with group B (P = 0.000, respectively. The total dose and the injection rate for the contrast material were reduced by 14.40% and 14.95% in A compared with B.The use of GSI and ASIR provides similar enhancement in vessels and image quality with reduced radiation dose and contrast dose, compared with the use of conventional scan protocol.

  16. PETRO-SAFE '94 conference papers: Book 2. Volume 5: Emergency response ampersand spill control; Volume 6: Remediation; Volume 7: Health ampersand safety issues

    International Nuclear Information System (INIS)

    Anon.

    1994-01-01

    The Fifth Annual Environmental, Safety and Health Conference and Exhibition for the oil, gas and petrochemical industries was held January 25--27, 1994 in Houston, Texas. The objective of this conference was to provide a multidisciplinary forum dealing with state-of-the-art environmental and safety issues. This volume focuses on the following: emergency response and spill control; remediation; and health and safety issues. Individual papers have been processed separately for inclusion in the appropriate data bases

  17. NRC program for the resolution of generic issues related to nuclear power plants. (Includes plans for the resolution of ''unresolved safety issues'' pursuant to Section 210 of the Energy Reorganization Act of 1974, as amended)

    International Nuclear Information System (INIS)

    1977-12-01

    This report provides a description of the Nuclear Regulatory Commission's Program for the Resolution of Generic Issues Related to Nuclear Power Plants. The NRC program is of considerably broader scope than the ''Unresolved Safety Issues Plan'' required by Section 210. The NRC program does include plans for the resolution of ''Unresolved Safety Issues''; however, in addition, it includes generic tasks for the resolution of environmental issues, for the development of improvements in the reactor licensing process and for consideration of less conservative design criteria or operating limitations in areas where over conservatisms may be unnecessarily restrictive or costly

  18. Data requirements for the Ferrocyanide Safety Issue developed through the data quality objectives process

    International Nuclear Information System (INIS)

    Meacham, J.E.; Cash, R.J.; Dukelow, G.T.; Babad, H.; Buck, J.W.; Anderson, C.M.; Pulsipher, B.A.; Toth, J.J.; Turner, P.J.

    1994-08-01

    This document records the data quality objectives (DQO) process applied to the Ferrocyanide Safety Issue at the Hanford Site. Specifically, the major recommendations and findings from this Ferrocyanide DQO process are presented. The decision logic diagrams and decision error tolerances also are provided. The document includes the DQO sample-size formulas for determining specific tank sampling requirements, and many of the justifications for decision thresholds and decision error tolerances are briefly described. More detailed descriptions are presented in other Ferrocyanide Safety Program companion documents referenced in this report. This is a living document, and the assumptions contained within will be refined as more data from sampling and characterization become available

  19. A report by the Health and Safety Executive to the Secretary of State for Energy on a review of the generic safety issues of pressurised water reactors

    International Nuclear Information System (INIS)

    1979-01-01

    The Nuclear Installations Inspectorate (NII) has completed a detailed technical study of certain generic safety aspects of the Pressurized Water Reactor (PWR). Although a particular design has been used as a reference, the conclusions reached are not intended to relate to any specific plant. The NII consider that there is no fundamental reason for regarding safety as an obstacle to the selection of a PWR for commercial electricity generation in Britain. Although there are some safety aspects about which present information and investigations are insufficient to allow final conclusions to be reached, and some areas where more work would lead to greater confidence, the NII are satisfied that these issues are not such as to prejudice an immediate decision in principle about the suitability of the PWR for commercial use in Britain. Further progress would appropriately form part of the more detailed review of any specific design of reactor put forward for licensing. Headings of the report include: organization of the review; the PWR; reactor safety issues; basis of judgement; the generic topics (potential plant faults and their analysis, loss of coolant, integrity of primary coolant circuit, fuel elements, reactor protection system, containment, radiological risk in normal operation, radioactive wastes); alternative PWR concepts; risk evaluation; light water reactor safety R and D; conclusions. (author)

  20. Safety culture

    International Nuclear Information System (INIS)

    Keen, L.J.

    2003-01-01

    Safety culture has become a topic of increasing interest for industry and regulators as issues are raised on safety problems around the world. The keys to safety culture are organizational effectiveness, effective communications, organizational learning, and a culture that encourages the identification and resolution of safety issues. The necessity of a strong safety culture places an onus on all of us to continually question whether the safety measures already in place are sufficient, and are being applied. (author)

  1. EDF ageing management program of nuclear components: a safety and economical issue

    International Nuclear Information System (INIS)

    Faidy, C.

    2005-01-01

    Ageing management of Nuclear Power Plants is an essential issue for utilities, in term of safety and availability and corresponding economical consequences. Practically all nuclear countries have developed a systematic program to deal with ageing of components on their plants. This paper presents the ageing management program developed by EDF and that are compared with different other approaches in other countries (IAEA guidelines and GALL report). The paper presents a general overview of the programs, the major results, recommendations and conclusions. (author)

  2. Safety criteria for the future LMFBR's in France and main safety issues for the rapide 1500 project

    International Nuclear Information System (INIS)

    Justin, F.; Natta, M.; Orzoni, G.

    1985-04-01

    The main safety criteria for future LMFBR in France and the related issues for the RAPIDE 1500 project are presented and discussed. The evolutions with respect to SUPERPHENIX options and requirements are emphasized, in particular for the concerns of the prevention of core melt accidents, fuel damage limits and related required performances of the protection system, since one main option is not to consider whole core melt accidents in the containment design. One shall also point out the advantages of some mitigating features which were nevertheless added in the containment design, although without any explicit consideration for core melt accidents

  3. Resolution of Unresolved Safety Issue A-48, ''Hydrogen control measures and effects of hydrogen burns on safety equipment''

    International Nuclear Information System (INIS)

    Ferrell, C.M.; Soffer, L.

    1989-09-01

    Unresolved Safety Issue (USI) A-48 arose as a result of the large amount of hydrogen generated and burned within containment during the Three Mile Island accident. This issue covers hydrogen control measures for recoverable degraded-core accidents for all boiling-water reactors (BWRs) and those pressurized-water reactors (PWRs) with ice-condenser containments. The Commission and the nuclear industry have sponsored extensive research in this area, which has led to significant revision of the Commission's hydrogen control regulations, given in Title 10, Code of Federal Regulations, Part 50 (10 CFR 50), Section 50.44. BWRs having Mark I and II containments are presently required to operate with inerted containment atmospheres that effectively prevent hydrogen combustion. BWRs with Mark III containments and PWRs with ice-condenser containments are now required to be equipped with hydrogen control systems to protect containment integrity and safety systems inside containment. Industry has chosen to use hydrogen igniter systems to burn hydrogen produced in a controlled fashion to prevent damage. An independent review by a Committee of the National Research Council concluded that, for most accident scenarios, current regulatory requirements make it highly unlikely that hydrogen detonation would be the cause of containment failure. On the basis of the extensive research effort conducted and current regulatory requirements, including their implementation, the staff concludes that no new regulatory guidance on hydrogen control for recoverable degraded-core accidents for these types of plants is necessary and that USI A-48 is resolved

  4. Current safety issues in the development of geological disposal of radioactive waste in France

    International Nuclear Information System (INIS)

    Raimbault, P.

    2002-01-01

    Deep geological disposal of high level and medium level long-lived waste in France is one of the three research paths defined by the law of 30th December 1991 on radioactive waste management. Research should be undertaken on: separation and transmutation of long-lived radionuclides in these waste; reversible or non reversible disposal in deep geological layers supported by investigations in underground laboratories; processes for conditioning and long term surface storage of these waste. In 2006, a global evaluation report on this research should be established by the Government and sent to the French Parliament. On this basis the Parliament should promulgate a law providing new objectives for the research and possibly presenting a framework for a deep disposal process. The French Nuclear Safety Authority has the responsibility to license the underground laboratories foreseen in the second research path and the nuclear facilities involved in the first and third research paths and make sure that existing high level and medium level long-lived waste currently produced are properly managed. It will give its advice on the safety aspects associated to the envisaged future management options. Its main concern is that results obtained in 2006 will be conclusive enough to take decisions for future orientations. Concerning the deep disposal option, under the responsibility of ANDRA (Agence Nationale pour la gestion des Dechets RAdioactifs), the construction of an underground laboratory has been authorized on the Bure site, in eastern France, and the shafts are under construction. The main issue is the level of investigations that may be performed in the host rock in order to support the feasibility study of a disposal concept on this site. Other issues are the elaboration of new safety standards to set a framework for a safety assessment of a disposal concept, the specifications for acceptance of waste packages in a future deep disposal, and relation of safety matters with

  5. A beamline for x-ray laser spectroscopy at the experimental storage ring at GSI

    International Nuclear Information System (INIS)

    Winters, D F A; Bagnoud, V; Ecker, B; Eisenbarth, U; Götte, S; Kuehl, Th; Stöhlker, Th; Zielbauer, B; Neumayer, P; Spielmann, C

    2013-01-01

    By combining an x-ray laser (XRL) with a heavy-ion storage ring, precision laser spectroscopy of the fine-structure splitting in heavy Li-like ions will be possible. An initial study has been performed to determine the feasibility of a first experiment at the experimental storage ring at GSI in Darmstadt, which also has great potential for the experiments planned for FAIR. We plan to perform a unique, direct and precise measurement of a fine-structure transition in a heavy Li-like ion. Such a measurement will test state-of-the-art atomic structure calculations in strong fields. This endeavour will require that the existing infrastructure is complemented by a dedicated beamline for the XRL. In this paper, we will discuss the details of this project and outline a proof-of-principle experiment. (paper)

  6. Recent Test Results of the Fast-Pulsed 4 T COS$\\Theta$ Dipole GSI 001

    CERN Document Server

    Moritz, G; Escallier, John; Ganetis, George; Jain, Animesh K; Marone, Andrew; Muratore, Joseph F; Thomas, Richard A; Wanderer, Peter; Auchmann, Bernard; de Maria, Riccardo; Wilson, Martin N; Russenschuck, Stephan

    2005-01-01

    For the FAIR-project at GSI a model dipole was built at BNL with the nominal field of 4 T and a nominal ramp rate of 1 T/s. The magnet design was similar to the RHIC dipole with some changes for loss reduction and better cooling. The magnet was already successfully tested in a vertical cryostat with good training behaviour. Cryogenic losses were measured and first results of field harmonics were published. However, for a better understanding of the cooling process quench currents at several ramp rates were investigated. Detailed measurements of the field harmonics at different ramp rates and at several cycles were performed. To separate the effects of the coil and the iron yoke the magnet was disassembled and tested as collared coil only. Recent test results will be presented.

  7. Atomic collision studies at moderate projectile velocities using highly charged, decelerated heavy ions from the GSI-UNILAC

    International Nuclear Information System (INIS)

    Mokler, P.H.; Hoffmann, D.H.H.; Schoenfeldt, W.A.; Maor, D.

    1984-01-01

    Beams of highly ionized, very heavy atoms at moderate velocities have been produced at the UNILAC using the acceleration-stripping-deceleration method. The available ion species range from Kr 33+ to U 66+ in the energy region between 2 and 5 MeV/u. A survey on first experiments at GSI using these moderate velocity, few electron, heavy ion beams is given. The effectiveness of the method is demonstrated for Xesup(q+)-Xe collision experiments with 41 <= q <= 45. Results on vacancy transfer between inner quasimolecular levels for close collisions, and on distant collision electron capture are reported. (orig.)

  8. IAEA Issues Report on Mission to Review Japan's Nuclear Power Plant Safety Assessment Process

    International Nuclear Information System (INIS)

    2012-01-01

    Full text: A team of international nuclear safety experts has delivered its report on a mission it conducted from 21-31 January 2012 to review Japan's process for assessing nuclear safety at the nation's nuclear power plants. International Atomic Energy Agency (IAEA) officials delivered the IAEA Mission Report to Japanese officials yesterday and made it publicly available today. Following the 11 March 2011 accident at TEPCO's Fukushima Daiichi Nuclear Power Station, Japan's Nuclear and Industrial Safety Agency (NISA) announced the development of a revised safety assessment process for the nation's nuclear power reactors. At the request of the Government of Japan, the IAEA organized a team of five IAEA and three international nuclear safety experts and visited Japan to review NISA's approach to the Comprehensive Assessments for the Safety of Existing Power Reactor Facilities and how NISA examines the results submitted by nuclear operators. A Preliminary Summary Report was issued on 31 January. 'The mission report provides additional information regarding the team's recommendations and overall finding that NISA's instructions to power plants and its review process for the Comprehensive Safety Assessments are generally consistent with IAEA Safety Standards', said team leader James Lyons, Director of the IAEA's Nuclear Installation Safety Division. National safety assessments and their peer review by the IAEA are a key component of the IAEA Action Plan on Nuclear Safety, which was approved by the Agency's Member States following last year's nuclear accident at Fukushima Daiichi Nuclear Power Station. The IAEA safety review mission held meetings in Tokyo with officials from NISA, the Japanese Nuclear Energy Safety Organization (JNES), and the Kansai Electric Power Company (KEPCO), and the team visited the Ohi Nuclear Power Station to see an example of how Japan's Comprehensive Safety Assessment is being implemented by nuclear operators. In its report delivered today

  9. A summary of the low upper shelf toughness safety margin issue

    International Nuclear Information System (INIS)

    Merkle, J.G.

    1991-01-01

    The low upper shelf toughness issue has a long history, beginning with the choice of materials for the submerged arc welding process, but also potentially involving the use of A302-B plate. Criteria for vessels containing low upper shelf materials have usually been expressed in terms of the Charpy upper shelf impact energy. Although these criteria have had several different bases, the range of limiting values for wall thicknesses approaching 229 mm (9 in.) has remained between 54 to 68J (40 to 50 ft lbs). Allowable values for vessels with thinner walls and/or only circumferential low upper shelf welds might conceivably be less. A decision on criteria to be incorporated into the ASME Code is now being made. Choices to be made concern the method for estimating the decrease in upper shelf impact energy, flaw geometry for circumferential welds, statistical significance of toughness values, the choice between J D and J M , reference pressure, safety factors and the inclusion of tearing stability calculations by means of R curve extrapolation. NRC research programs have contributed significantly to the resolution of the low upper shelf issue. These programs embrace all aspects of the issue, including material characterization, large scale testing, analysis and criteria development. 52 refs., 5 figs

  10. How to bring issues of health and safety closer to young workers during their work training

    Directory of Open Access Journals (Sweden)

    Helena Mesarič

    2016-06-01

    Full Text Available The data collected by the European Community indicates that the young, economically active population, aged from 18 to 24 years, is more likely to suffer from occupational injuries and occupational diseases in comparison with the rest of the working population, due to the lack of experience and knowledge about health and safety in the workplace, and insufficient training for safe and healthy work practices. Employers must establish an adequate system to ensure workplace health and safety, with an emphasis on providing safety training for pupils and students undergoing apprenticeship and the newly-employed young people. The Ministry of Labour, Family, Social Affairs and Equal Opportunities runs a series of projects aiming to promote health and safety culture among young people in Slovenia. The goal of the national programme for introducing occupational health and safety into the education process is offering a variety of tools and devices for educators and teachers, which can be employed to introduce the issues of occupational health and safety to young people in an exciting and engaging manner.

  11. Common issues found in operating safety peer review of nuclear power plants

    International Nuclear Information System (INIS)

    Wu Meijing; Zhang Fengping

    2004-01-01

    The 3rd stage of the safety culture promotion in a Nuclear Power Plant (NPP) is characterized by establishing learning organization and continuous self-improvement. Peer Review was used as an effective tool by a lot of NPPs to improve the overall management and performance. This Paper provided the WANO Peer Review Methodology, the common issues found, the recommendation or suggestions to correct the area for improvement. It may be beneficial to other NPP which planning to have Peer Review or Self Evaluation. (authors)

  12. Influence of external factors on safety. Topical issues paper no. 2

    International Nuclear Information System (INIS)

    Packer, C.; Talbot, K.

    2001-01-01

    In recent years a number of worldwide trends have emerged which affect the operating environment of nuclear power plants (NPPs), both externally in the sense of their political and economic business climate, and internally in the sense of their budgets, staffing levels and business practices. It is very clear that the 'span', or breadth, of issues being faced by the owners, operators and regulators of NPPs today, and the speed at which these issues are changing, is much greater than ever before. Included for consideration are: plants under construction or plants for which previously halted construction was resumed; plants operating in a deregulated electricity market; plants being refurbished and restarted; plants undergoing life extension programmes; plants facing closure for political reasons; plants being laid up or decommissioned; plants experiencing changes in ownership or operating control even by non-nuclear organizations; plants which need substantial design and material condition upgrades; plants facing a significant decline in revenue or funding; plants learning new management techniques; plants engaged in new regimes of safety regulation; plants with serious shortages of human experience and talent; plants facing ageing issues (institutional, personnel and equipment). What is particularly new is that many of these activities are now often going on simultaneously within a single utility. This means that the management attention span may be substantially stretched. In the USA, in particular, many of these issues have been present for several years. They began before economic deregulation of the electricity industry and their frequency and significance have generally increased in recent years as a result of deregulation. It is of paramount importance that co-operation and learning be promoted extensively as the industry faces these multiple overlapping and potentially distracting challenges. The basic principles of safety management that have been

  13. Summary of tank information relating salt well pumping to flammable gas safety issues

    International Nuclear Information System (INIS)

    Caley, S.M.; Mahoney, L.A.; Gauglitz, P.A.

    1996-09-01

    The Hanford Site has 149 single-shell tanks (SSTs) containing radioactive wastes that are complex mixes of radioactive and chemical products. Active use of these SSTs was phased out completely by November 1980, and the first step toward final disposal of the waste in the SSTs is interim stabilization, which involves removing essentially all of the drainable liquid from the tank. Stabilization can be achieved administratively, by jet pumping to remove drainable interstitial liquid, or by supernatant pumping. To date, 116 tanks have been declared interim stabilized; 44 SSTs have had drainable liquid removed by salt well jet pumping. Of the 149 SSTs, 19 are on the Flammable Gas Watch List (FGWL) because the waste in these tanks is known or suspected, in all but one case, to generate and retain mixtures of flammable gases, including; hydrogen, nitrous oxide, and ammonia. Salt well pumping to remove the drainable interstitial liquid from these SSTs is expected to cause the release of much of the retained gas, posing a number of safety concerns. The scope of this work is to collect and summarize information, primarily tank data and observations, that relate salt well pumping to flammable gas safety issues. While the waste within FGWL SSTs is suspected offering flammable gases, the effect of salt well pumping on the waste behavior is not well understood. This study is being conducted for the Westinghouse Hanford Company as part of the Flammable Gas Project at the Pacific Northwest National Laboratory (PNNL). Understanding the historical tank behavior during and following salt well pumping will help to resolve the associated safety issues

  14. Package leaflets of the most consumed medicines in Portugal: safety and regulatory compliance issues. A descriptive study

    Directory of Open Access Journals (Sweden)

    Carla Pires

    Full Text Available CONTEXT AND OBJECTIVES: Package leaflets are necessary for safe use of medicines. The aims of the present study were: 1 to assess the compliance between the content of the package leaflets and the specifications of the pharmaceutical regulations; and 2 to identify potential safety issues for patients. DESIGN AND SETTING: Qualitative descriptive study, involving all the package leaflets of branded medicines from the three most consumed therapeutic groups in Portugal, analyzed in the Department of Pharmacoepidemiology, School of Pharmacy, University of Lisbon. METHODS: A checklist validated through an expert consensus process was used to gather the data. The content of each package leaflet in the sample was classified as compliant or non-compliant with compulsory regulatory issues (i.e. stated dosage and descriptions of adverse reactions and optional regulatory issues (i.e. adverse reaction frequency, symptoms and procedures in cases of overdose. RESULTS: A total of 651 package leaflets were identified. Overall, the package leaflets were found to be compliant with the compulsory regulatory issues. However, the optional regulatory issues were only addressed in around half of the sample of package leaflets, which made it possible to identify some situations of potentially compromised drug safety. CONCLUSION: Ideally, the methodologies for package leaflet approval should be reviewed and optimized as a way of ensuring the inclusion of the minimum essential information for safe use of medicines.

  15. The ASY-EOS experiment at GSI: investigating symmetry energy at supra-saturation densities

    Directory of Open Access Journals (Sweden)

    Russotto P.

    2014-03-01

    Full Text Available The elliptic-flow ratio of neutrons with respect to protons or light complex particles in reactions of heavy-ions at pre-relativistic energies has been proposed as an observable sensitive to the strength of the symmetry term of the nuclear equation of state at supra-saturation densities. The results obtained from the existing FOPI/LAND data for 197Au+197Au collisions at 400 MeV/nucleon in comparison with the UrQMD model simulations favoured a moderately soft symmetry term, but suffer from a considerable statistical uncertainty. These results have been confirmed by an independent analysis based on the Tübingen QMD simulations. In order to obtain an improved data set for Au+Au collisions and to extend the study to other systems, a new experiment was carried out at the GSI laboratory by the ASY-EOS collaboration. The present status of the data analysis is reported

  16. The issue of safety in the transports of radioactive materials

    International Nuclear Information System (INIS)

    Pallier, Lucien

    1961-01-01

    This report addresses and discusses the various hazards associated with transports of radioactive materials, their prevention, intervention measures, and precautions to be taken by rescuers, notably how these issues are addressed in regulations. For each of these issues, this report proposes guidelines, good practices, or procedures to handle the situation. The author first addresses hazards related to a transport of radioactive products: multiplicity of hazards, different hazards due to radioactivity, hazards due to transport modes, scale of dangerous doses. The second part addresses precautionary measures: for road transports, for air transports, for maritime transports, control procedures. The third part addresses the intervention in case of accident: case of a road accident with an unhurt or not vehicle crew, role of the first official rescuers, other kinds of accidents. The fourth part briefly addresses the case of transport of fissile materials. The fifth part discusses the implications of safety measures. Appendices indicate standards, and give guidelines for the construction of a storage building for radioactive products, for the control and storage of parcels containing radioactive products, and for the establishment of instructions for the first aid personnel

  17. Present and Future Experiments with Stored Exotic Nuclei at GSI

    International Nuclear Information System (INIS)

    Geissel, H.

    2009-01-01

    Recent results and perspectives of experiments with stored exotic nuclei at GSI-FAIR will presented. An overview on the planned NUSTAR experiments will also presented. Relativistic exotic nuclei produced via projectile fragmentation and fission were separated in flight by the fragment separator FRS and injected into the storage-cooler ring ESR for accurate mass- and lifetime measurements. Direct mass measurements of electron-cooled exotic nuclei were performed using time-resolved Schottky spectrometry. Fragments with half-lives shorter than the time required for electron cooling have been investigated by time-of-flight measurements with the ESR being operated in the isochronous mode. This novel experimental technique gives access to all nuclei with half-lives down to the microsecond range and has been successfully applied. Lifetimes of stored bare and few-electron ions have been measured with the goal to study the beta-decay under ionization conditions prevailing in stellar plasma. For the first time the direct observation of bound-state beta decay has been achieved with 2 07T l fragments. The future project FAIR includes a new large-acceptance in-flight separator (Super-FRS) in combination with a new storage ring system (CR, NESR) which will be ideal tools to study exotic nuclei far from stability.(author)

  18. Using network screening methods to determine locations with specific safety issues: A design consistency case study.

    Science.gov (United States)

    Butsick, Andrew J; Wood, Jonathan S; Jovanis, Paul P

    2017-09-01

    The Highway Safety Manual provides multiple methods that can be used to identify sites with promise (SWiPs) for safety improvement. However, most of these methods cannot be used to identify sites with specific problems. Furthermore, given that infrastructure funding is often specified for use related to specific problems/programs, a method for identifying SWiPs related to those programs would be very useful. This research establishes a method for Identifying SWiPs with specific issues. This is accomplished using two safety performance functions (SPFs). This method is applied to identifying SWiPs with geometric design consistency issues. Mixed effects negative binomial regression was used to develop two SPFs using 5 years of crash data and over 8754km of two-lane rural roadway. The first SPF contained typical roadway elements while the second contained additional geometric design consistency parameters. After empirical Bayes adjustments, sites with promise (SWiPs) were identified. The disparity between SWiPs identified by the two SPFs was evident; 40 unique sites were identified by each model out of the top 220 segments. By comparing sites across the two models, candidate road segments can be identified where a lack design consistency may be contributing to an increase in expected crashes. Practitioners can use this method to more effectively identify roadway segments suffering from reduced safety performance due to geometric design inconsistency, with detailed engineering studies of identified sites required to confirm the initial assessment. Copyright © 2017 Elsevier Ltd. All rights reserved.

  19. Safety of fuel cycle facilities. Topical issues paper no. 3

    International Nuclear Information System (INIS)

    Ranguelova, V.; Niehaus, F.; Delattre, D.

    2001-01-01

    that the relative hazards vary from facility to facility depending upon the processes employed. However, all installations should be designed and operated so as to keep all sources of radiation exposure under strict technical and administrative control. The design management should ensure that the structures, systems and components important to safety have the appropriate characteristics, specifications and material composition to perform the required safety functions. Emphasis should be placed on the use of proven engineered safety features in the implementation of the defence in depth concept in the facility design and operation. The development of nuclear safety standards is one of the tasks given by the Statute of the IAEA. Over a number of years, the IAEA has developed a comprehensive set of publications which address, in a structured manner, the safety of nuclear installations. The Safety Fundamentals publication entitled 'The Safety of Nuclear Installations' presents an international consensus on the basic concepts underlying the principles for the regulation, design and operation of nuclear installations, including fuel cycle facilities. Detailed requirements and guides for activities relating to siting, design, construction, operation, decommissioning and regulation of nuclear installations are addressed by lower hierarchy safety standards, which cover nuclear power plants (NPPs) and research reactors. Although some of the IAEA NPP standards can be adapted and applied to fuel cycle facilities and some standards on criticality safety are published by the International Organization for Standardization (ISO), in general there is a lack of international safety standards to cover the safety of such facilities. With a view to establishing a plan for the development of safety standards for fuel cycle facilities, the IAEA began to compile information on the status of national regulations and safety issues concerning such facilities. It also held a Technical Committee

  20. EDF view on next generation reactor safety and operability issues

    International Nuclear Information System (INIS)

    Serviere, G.

    2002-01-01

    In the foreseeable future, EDF will have to compete in an economically de-regulated market. Nuclear currently accounts for more than 80% of the electricity generated by the company, and generation costs are quite competitive compared to that of other competing energies. It is so likely that nuclear units will remain the backbone of EDF generating fleet in the years to come. However, to remain a viable option for electricity generation in the longer term, nuclear will have to maintain both its cost-effectiveness and a very high safety level. This could seem quite straightforward considering the current situation where safety records are at an all time high and Operating and Maintenance costs are under tight control. In fact, it could be a real challenge. Competing fossil technologies progress and there is a concurrent trend to try and improve the performance of future nuclear units. However, in most cases, proposed designs depart from the well-known Light Water Reactor (LWR) technology. They are either new concepts or designs already tested in the past and modified to address some of their perceived drawbacks. Contrary to the prevailing situation where short-term alternatives like the EPR, the ABWR or the AP600 largely build upon experience gathered on operating units, most designs contemplated for implementation beyond 2020 or 2030 cannot be considered proven. Considering the above mentioned uncertainties, EDF have confirmed their preference for proven designs with higher outputs, such as the EPR. However, it would appear unreasonable to consider that new designs are doomed to fail: they could well turn out to be adequate for specific niches in a de-regulated market and provide reasonable alternatives for the utility. Nevertheless, for such an alternative to be considered, additional evidence is needed that utility preferences are reflected in the design, and that all potential technical issues have been identified, adequately addressed and resolved. Currently, EDF

  1. Regulatory analysis for the resolution of Unresolved Safety Issue A-44, Station Blackout. Draft report

    International Nuclear Information System (INIS)

    Rubin, A.M.

    1986-01-01

    ''Station Blackout'' is the complete loss of alternating current (ac) electric power to the essential and nonessential buses in a nuclear power plant; it results when both offsite power and the onsite emergency ac power systems are unavailable. Because many safety systems required for reactor core decay heat removal and containment heat removal depend on ac power, the consequences of a station blackout could be severe. Because of the concern about the frequency of loss of offsite power, the number of failures of emergency diesel generators, and the potentially severe consequences of a loss of all ac power, ''Station Blackout'' was designated as Unresolved Safety Issue (USI) A-44. This report presents the regulatory analysis for USI A-44. It includes: (1) a summary of the issue, (2) the proposed technical resolution, (3) alternative resolutions considered by the Nuclear Regulatory Commission (NRC) staff, (4) an assessment of the benefits and costs of the recommended resolution, (5) the decision rationale, and (6) the relationship between USI A-44 and other NRC programs and requirements

  2. Engineering approach to relative quantitative assessment of safety culture and related social issues in NPP operation

    International Nuclear Information System (INIS)

    Sivokon, V.; Gladyshev, M.; Malkin, S.

    2005-01-01

    The report is devoted to presentation of engineering approach and software tool developed for Safety Culture (SC) assessment as well as to the results of their implementation at Smolensk NPP. The engineering approach is logic evolution of the IAEA ASSET method broadly used at European NPPs in 90-s. It was implemented at Russian and other plants including Olkiluoto NPP in Finland. The approach allows relative quantitative assessing and trending the aspects of SC by the analysis of evens features and causes, calculation and trending corresponding indicators. At the same time plant's operational performances and related social issues, including efficiency of plant operation and personnel reliability, can be monitored. With the help of developed tool the joint team combined from personnel of Smolensk NPP and RRC 'Kurchatov Institute' ('KI') issued the SC self-assessment report, which identifies: families of recurrent events, main safety and operational problems ; their trends and importance to SC and plant efficiency; recommendations to enhance SC and operational performance

  3. Application of Beam Diagnostics for Intense Heavy Ion Beams at the GSI UNILAC

    CERN Document Server

    Barth, W; Glatz, J; Groening, L; Richter, S; Yaramishev, S

    2003-01-01

    With the new High Current Injector (HSI) of the GSI UNILAC the beam pulse intensity had been increased by approximately two orders of magnitudes. The HSI was mounted and commissioned in 1999; since this time the UNILAC serves as an injector for the synchrotron SIS, especially for high uranium intensities. Considering the high beam power of up to 1250 kW and the short stopping range for the UNILAC beam energies (≤12 MeV/u), accelerator components could be destroyed, even during a single beam pulse. All diagnostic elements had to be replaced preferably by non-destructive devices. The beam current is mainly measured by beam transformers instead of Faraday cups, beam positions are measured with segmented capacitive pick-ups and secondary beam monitors instead of profile harps. The 24 installed pick-ups are also used to measure intensities, widths and phase of the bunches, as well beam energies by evaluating pick-ups at different positions. The residual gas ionization monitors allow on-line measurements ...

  4. Radiation Protection, Safety and Security Issues in Ghana

    International Nuclear Information System (INIS)

    Boadu, M. B.; Emi-Reynolds, G.; Amoako, J. K.; Hasford, F.; Akrobortu, E.

    2015-01-01

    The Radiation Protection Board was established in 1993 by PNDC Law 308 as the National Competent Authority for the regulation of radiation sources and radioactive materials in Ghana. The mandate and responsibilities of RPB are prescribed in the legislative instrument, LI 1559 issued in 1993. The operational functions of the Board are carried out by the Radiation Protection Institute, which was established to provide technical support for the enforcement of the legislative instrument. The regulatory activities include among others: – Issuance permits for the import/export of any radiation producing device and radioactive materials into/out of the country. It therefore certifies the radioactivity levels in food and the environmental samples. – Authorization and Inspection of practices using radiation sources and radioactive materials in Ghana. – Undertakes safety assessment services and enforcement actions on practices using radiation sources and radioactive materials in line with regulations. – Provides guidance and technical support in fulfilling regulatory requirement to users of radiation producing devices and radioactive materials nationwide by monitoring of monthly radiation absorbed doses for personnel working at radiation facilities. – Provides support to the management of practices in respect of nuclear and radioactive waste programme. – Calibrates radiation emitting equipment and nuclear instrumentation to ensure the safety of patients, workers and the general public. – Establish guidelines for the mounting (non-ionizing) communication masts. – Environmental monitoring (non-ionizing) programmes for communication masts. With the establishment of the national competent authority, facilities using radioactive sources and radiation emitting devices have been brought under regulatory control. Effective regulatory control of radiation emitting devices are achieved through established legal framework, independent Regulatory Authority supported by

  5. Characterization strategy report for the criticality safety issue

    International Nuclear Information System (INIS)

    Doherty, A.L.; Doctor, P.G.; Felmy, A.R.; Prichard, A.W.; Serne, R.J.

    1997-06-01

    High-level radioactive waste from nuclear fuels processing is stored in underground waste storage tanks located in the tank farms on the Hanford Site. Waste in tank storage contains low concentrations of fissile isotopes, primarily U-235 and Pu-239. The composition and the distribution of the waste components within the storage environment is highly complex and not subject to easy investigation. An important safety concern is the preclusion of a self-sustaining neutron chain reaction, also known as a nuclear criticality. A thorough technical evaluation of processes, phenomena, and conditions is required to make sure that subcriticality will be ensured for both current and future tank operations. Subcriticality limits must be based on considerations of tank processes and take into account all chemical and geometrical phenomena that are occurring in the tanks. The important chemical and physical phenomena are those capable of influencing the mixing of fissile material and neutron absorbers such that the degree of subcriticality could be adversely impacted. This report describes a logical approach to resolving the criticality safety issues in the Hanford waste tanks. The approach uses a structured logic diagram (SLD) to identify the characterization needed to quantify risk. The scope of this section of the report is limited to those branches of logic needed to quantify the risk associated with a criticality event occurring. The process is linked to a conceptual model that depicts key modes of failure which are linked to the SLD. Data that are needed include adequate knowledge of the chemical and geometric form of the materials of interest. This information is used to determine how much energy the waste would release in the various domains of the tank, the toxicity of the region associated with a criticality event, and the probability of the initiating criticality event

  6. NS [Nuclear Safety] update. Current safety and security activities and developments taking place in the Department of Nuclear Safety and Security. Issue no. 4, June 2007

    International Nuclear Information System (INIS)

    2007-04-01

    This newsletter contains information on the Centre for Advanced Safety Assessment Tools (CASAT), the new strategy for the recovery of radioactive sources, the Technical Support Organization Conference and a message form the Director of the Division of Nuclear Installation Safety. To improve the efficiency of safety assessment methods, ensure transparency in their validation and application and establish an excellent knowledge base and training programmes, the IAEA's Centre for Advanced Safety Assessment Tools (CASAT) has therefore been formed. The Centre addresses the need for continuous technical support mechanisms for safety assessment methods. It provides support to Member States to enhance their safety assessment capabilities for present and future generations of nuclear systems, with a special focus on countries with a developing nuclear technology and nuclear safety infrastructure. It serves as a consolidated repository of relevant safety analysis knowledge, provides for focused training including advanced analytical simulations, and supports collaboration on safety assessment projects among Member States. The resources provided through CASAT include codes, models, databases, verification and validation information, analytical procedures and guides. The main purpose of the recently established Radioactive Source Technical Coordination Group (RSTCG) is to facilitate the technical coordination of activities of the IAEA related to the control and management of radioactive sources through the development of common approaches in technical matters and to advise the management of the relevant Divisions. It is the task of the RSTCG to provide the programme managers of the participating divisions/sections with a common opinion/advice on technical issues related to the control and management of radioactive sources. The RSTCG members obtain, inter alia from programme managers, information on all relevant project proposals, and share relevant materials in due time to

  7. Production of a pion in association with a high-Q2 dilepton pair in antiproton-proton annihilation at GSI-FAIR

    International Nuclear Information System (INIS)

    Lansberg, J. P.; Pire, B.; Szymanowski, L.

    2007-01-01

    We evaluate the cross section for pp→l + l - π 0 in the forward direction and for a large lepton pair invariant mass. In this kinematical region, the leading-twist amplitude factorizes into a short-distance matrix element, long-distance antiproton-distribution amplitudes, and proton to pion transition distribution amplitudes (TDAs). Using a modeling inspired from the chiral limit for these TDAs, we obtain a first estimate of this cross section, which demonstrates that this process can be measured at GSI-FAIR

  8. Safety-critical human factors issues derived from analysis of the TEPCO Fukushima Daiichi accident investigation reports

    International Nuclear Information System (INIS)

    Sakuda, Hiroshi; Takeuchi, Michiru

    2013-01-01

    The Fukushima Daiichi nuclear power plant accident on March 11, 2011 had a large impact both in and outside Japan, and is not yet concluded. After Tokyo Electric Power Co.'s (TEPCO's) Fukushima accident, electric power suppliers have taken measures to respond in the event that the same state of emergency occurs - deploying mobile generators, temporary pumps and hoses, and training employees in the use of this equipment. However, it is not only the “hard” problems including the design of equipment, but the “soft” problems such as organization and safety culture that have been highlighted as key contributors in this accident. Although a number of organizations have undertaken factor analysis of the accident and proposed issues to be reviewed and measures to be taken, a systematic overview about electric power suppliers' organization and safety culture has not yet been undertaken. This study is based on three major reports: the report by the national Diet of Japan Fukushima Nuclear Accident Independent Investigation Commission (the Diet report), the report by the Investigation Committee on the Accident at Fukushima Nuclear Power Stations of Tokyo Electric Power Company (Government report), and the report by the non-government committee supported by the Rebuild Japan Initiative Foundation (Non-government report). From these reports, the sections relevant to electric power suppliers' organization and safety culture were extracted. These sections were arranged to correspond with the prerequisites for the ideal organization, and 30 issues to be reviewed by electric power suppliers were extracted using brainstorming methods. It is expected that the identified issues will become a reference for every organization concerned to work on preventive measures hereafter. (author)

  9. Addressing safety issues through a joint industry programme; Traiter des problemes de securite a travers un programme industriel commun

    Energy Technology Data Exchange (ETDEWEB)

    Pool, G.; Williams, T.P. [BG Technology (United Kingdom); Jones, A.M. [Health and Safety Executive (United Kingdom)

    2000-07-01

    In an increasingly fragmented gas market, the focus for national gas safety may not rest with one major utility or gas supplier but may be spread across many companies. There will also be many new organisations in a liberalized gas industry with varying views on the needs and benefits of safety related technology development but all agree there is a need to ensure that the good safety record of gas as a domestic fuel is maintained. The number of carbon monoxide (CO) incidents is not decreasing significantly despite an increased awareness of the problem. As a consequence, a two-year joint industry programme addressing issues related to carbon monoxide has been established, co-ordinated by BG Technology and supported by gas organisations, government agencies, manufacturers and suppliers across Europe and the World. The 2-year 2 pound million programme has been constructed as twelve separate projects addressing issues such as the reporting and analysis of domestic incidents, improved service or installation practice, CO alarm reliability and information dissemination. The paper gives results and achievements of the programme, through new techniques, standards, procedures or equipment and demonstrates how the gas industry can work together to meet common safety objectives. (authors)

  10. ITER safety

    International Nuclear Information System (INIS)

    Raeder, J.; Piet, S.; Buende, R.

    1991-01-01

    As part of the series of publications by the IAEA that summarize the results of the Conceptual Design Activities for the ITER project, this document describes the ITER safety analyses. It contains an assessment of normal operation effluents, accident scenarios, plasma chamber safety, tritium system safety, magnet system safety, external loss of coolant and coolant flow problems, and a waste management assessment, while it describes the implementation of the safety approach for ITER. The document ends with a list of major conclusions, a set of topical remarks on technical safety issues, and recommendations for the Engineering Design Activities, safety considerations for siting ITER, and recommendations with regard to the safety issues for the R and D for ITER. Refs, figs and tabs

  11. Examination of issues related to the development and implementation of real-time operational safety monitoring tools in the nuclear power industry

    International Nuclear Information System (INIS)

    Puglia, William J.; Atefi, Bahman

    1995-01-01

    In recent years, risk and reliability techniques have been increasingly used to optimize deterministic requirements and to improve the operational safety of nuclear power stations. This paper discusses the historical development and current status of implementation of real-time operational safety monitoring tools in the nuclear power industry worldwide. A safety monitor is defined as a PC-based risk management tool, based on a plant specific PSA, which can be used to manage plant safety during the day-to-day operation of a nuclear power plant by planning maintenance activities and providing advisory information to plant operational staff in order to avoid high risk plant configurations. As this technique has only been applied in a few plants worldwide, the technology is still evolving and there are several technical and implementation-related issues which still need to be resolved. This paper attempts to summarize all such issues and describe how they have been addressed in several different applications of this technology around the world

  12. Investigations on KONUS beam dynamics using the pre-stripper drift tube linac at GSI

    Science.gov (United States)

    Xiao, C.; Du, X. N.; Groening, L.

    2018-04-01

    Interdigital H-mode (IH) drift tube linacs (DTLs) based on KONUS beam dynamics are very sensitive to the rf-phases and voltages at the gaps between tubes. In order to design these DTLs, a deep understanding of the underlying longitudinal beam dynamics is mandatory. The report presents tracking simulations along an IH-DTL using the PARTRAN and BEAMPATH codes together with MATHCAD and CST. Simulation results illustrate that the beam dynamics design of the pre-stripper IH-DTL at GSI is sensitive to slight deviations of rf-phase and gap voltages with impact to the mean beam energy at the DTL exit. Applying the existing geometrical design, rf-voltages, and rf-phases of the DTL were re-adjusted. In simulations this re-optimized design can provide for more than 90% of transmission of an intense 15 emA beam keeping the reduction of beam brilliance below 25%.

  13. The ASY-EOS experiment at GSI: Constraining the symmetry energy at supra-saturation densities

    Directory of Open Access Journals (Sweden)

    Russotto P.

    2015-01-01

    Full Text Available The elliptic-flow ratio of neutrons with respect to protons or light complex particles in reactions of heavy ions at pre-relativistic energies has been proposed as an observable sensitive to the strength of the symmetry term of the nuclear equation of state at supra-saturation densities. In the ASY-EOS experiment at the GSI laboratory, flows of neutrons and light charged particles were measured for 197Au+197Au, 96Zr+96Zr and 96Ru+96Ru collisions at 400 MeV/nucleon with the Large Area Neutron Detector LAND as part of a setup with several additional detection systems used for the event characterization. Flow results obtained for the Au+Au system, in comparison with predictions of the UrQMD transport model, confirm the moderately soft to linear density dependence of the symmetry energy deduced from the earlier FOPI-LAND data.

  14. Managing nuclear safety at Point Lepreau

    Energy Technology Data Exchange (ETDEWEB)

    Paciga, J [New Brunswick Power, Point Lepreau NGS, PQ (Canada)

    1997-12-01

    Managing nuclear safety at Point Lepreau nuclear power plant is described, including technical issues (station aging, definition of the safe operating envelope, design configuration management, code validation, safety analysis and engineering standards); regulatory issues (action items, probabilistic safety assessment, event investigation, periodic safety review, prioritization of regulatory issues, cost benefit assessment); human performance issues (goals and measures, expectations and accountability, supervisory training, safety culture, configuration management, quality of operations and maintenance).

  15. Managing nuclear safety at Point Lepreau

    International Nuclear Information System (INIS)

    Paciga, J.

    1997-01-01

    Managing nuclear safety at Point Lepreau nuclear power plant is described, including technical issues (station aging, definition of the safe operating envelope, design configuration management, code validation, safety analysis and engineering standards); regulatory issues (action items, probabilistic safety assessment, event investigation, periodic safety review, prioritization of regulatory issues, cost benefit assessment); human performance issues (goals and measures, expectations and accountability, supervisory training, safety culture, configuration management, quality of operations and maintenance)

  16. Technical resolution of Generic Safety Issue A-29

    International Nuclear Information System (INIS)

    1989-09-01

    This report summarizes key technical findings related to Generic Safety Issue A-29, ''Nuclear Power Plant Design for Reduction of Vulnerability to Industrial Sabotage.'' The findings in this report deal with (1) a historical review of reported sabotage-related events at nuclear facilities, (2) NRC physical security requirements, (3) industry measures to prevent/mitigate sabotage, (4) design and procedural approaches that could be used to deter sabotage, (5) current NRC and industry initiatives aimed at personnel screening and selection, and (6) design considerations applicable to Advanced Light Water Reactors (ALWRs). The results reveal that insider sabotage at operating nuclear plants has not been a significant problem in the United States to date and that there are no singular design modifications or procedures that by themselves would completely eliminate or mitigate the threat of insider sabotage. Rather, it will take a combination of systematic and focused improvements in the three areas of reliable personnel, effective design features, and plant procedures developed to provide a strategy to deal with prevention of insider sabotage and to be able to mitigate adverse actions. 24 refs., 2 figs., 5 tabs

  17. A review of occupational safety and health issues relevant to the Environmental Restoration Program: Selected case histories and associated issues

    International Nuclear Information System (INIS)

    Lesperance, A.M.; Siegel, M.R.; McKinney, M.C.

    1994-08-01

    Since the 1940s, US Department of Energy (DOE) sites have been used for nuclear materials processing and production, warhead testing, and weapons research and development. These activities have resulted in extensive environmental contamination. DOE has established a goal to cleanup and restore the groundwater, soils, sediments, and surface water at its facilities across the nation. To achieve this goal, many workers will be needed to conduct the cleanup. These workers will need training and will be required to follow occupational safety and health (OSH) regulations and guidelines. Compliance with the OSH regulations and guidelines will have an anomous influence on the schedule, money, and technology needed for environmental restoration. Therefore, one area that must be considered in the early stages of long-term planning is the impact of OSH issues on the environmental restoration process. The DOE Office of Environmental Restoration and Waste Management has requested that the Pacific Northwest Laboratory (PNL) investigate the impact of these issues on the environmental restoration process

  18. Issues affecting advanced passive light-water reactor safety analysis

    International Nuclear Information System (INIS)

    Beelman, R.J.; Fletcher, C.D.; Modro, S.M.

    1992-01-01

    Next generation commercial reactor designs emphasize enhanced safety through improved safety system reliability and performance by means of system simplification and reliance on immutable natural forces for system operation. Simulating the performance of these safety systems will be central to analytical safety evaluation of advanced passive reactor designs. Yet the characteristically small driving forces of these safety systems pose challenging computational problems to current thermal-hydraulic systems analysis codes. Additionally, the safety systems generally interact closely with one another, requiring accurate, integrated simulation of the nuclear steam supply system, engineered safeguards and containment. Furthermore, numerical safety analysis of these advanced passive reactor designs wig necessitate simulation of long-duration, slowly-developing transients compared with current reactor designs. The composite effects of small computational inaccuracies on induced system interactions and perturbations over long periods may well lead to predicted results which are significantly different than would otherwise be expected or might actually occur. Comparisons between the engineered safety features of competing US advanced light water reactor designs and analogous present day reactor designs are examined relative to the adequacy of existing thermal-hydraulic safety codes in predicting the mechanisms of passive safety. Areas where existing codes might require modification, extension or assessment relative to passive safety designs are identified. Conclusions concerning the applicability of these codes to advanced passive light water reactor safety analysis are presented

  19. Nuclear Structure of the Heaviest Elements – Investigated at SHIP-GSI

    Directory of Open Access Journals (Sweden)

    Heßberger Fritz Peter

    2014-03-01

    Full Text Available The quest for the heaviest nuclei that can exist is a basic topic in natural science as their stability is characterized by a delicate interplay of short range nuclear forces acting between the nucleons (protons and neutrons and long-range Coulomb forces acting solely between charged particles, i.e. the protons. As the stability of a nucleus is strongly correlated to its structure, understanding the nuclear structure of heaviest nuclei is presently a main challenge of experimental and theoretical investigations concerning the field of Superheavy Elements. At the velocity filter SHIP at GSI Darmstadt an extensive program on nuclear structure investigations has been started about a decade ago. The project covered both as well systematic investigations of single particle levels in odd-mass isotopes populated by α-decay as investigation of two- or fourquasi-particle states forming K isomers and was supplemented by direct mass measurements at SHIPTRAP and investigation of spontaneous fission properties. Recent experimental studies allowed to extend the systematics of low lying levels in N = 151 and N = 153 up to 255Rf and 259Sg, investigation of possible relations between nuclear structure and fission properties of odd-mass nuclei and investigation of shell strengths at N = 152 and towards N = 162.

  20. Issues for resolving adverse effects on the safety culture of human work underload and workload transitions in complex human-machine systems

    International Nuclear Information System (INIS)

    Ryan, T.G.

    1996-01-01

    A workshop was conducted whose specific purpose was to build on earlier work of the US National Research Council, US federal government agencies, and the larger human factors community to: (1) clarify human factors issues pertaining to degraded safety performance in advanced human-machine systems(e.g., nuclear production, transportation, aerospace) due to human work underload and workload transition, and (2) develop strategies for resolving these issues. The workshop affirmed that: (1) work underload and workload transition are issues that will have to be addressed by designers of advanced human-machine systems, especially those relying on automation, if cost, performance, safety, and operator acceptability are to be optimized, (2) human machine allocation models, standards and guidelines which go beyond simple capability approaches will be needed to preclude or seriously diminish the work underload and workload transition problems, and (3) the 16 workload definition, measurement, situational awareness, and trust issues identified during the workshop, need resolution if these models, standards, and guidelines are to be achieved

  1. Radiological protection, safety and security issues in the industrial and medical applications of radiation sources

    Science.gov (United States)

    Vaz, Pedro

    2015-11-01

    The use of radiation sources, namely radioactive sealed or unsealed sources and particle accelerators and beams is ubiquitous in the industrial and medical applications of ionizing radiation. Besides radiological protection of the workers, members of the public and patients in routine situations, the use of radiation sources involves several aspects associated to the mitigation of radiological or nuclear accidents and associated emergency situations. On the other hand, during the last decade security issues became burning issues due to the potential malevolent uses of radioactive sources for the perpetration of terrorist acts using RDD (Radiological Dispersal Devices), RED (Radiation Exposure Devices) or IND (Improvised Nuclear Devices). A stringent set of international legally and non-legally binding instruments, regulations, conventions and treaties regulate nowadays the use of radioactive sources. In this paper, a review of the radiological protection issues associated to the use of radiation sources in the industrial and medical applications of ionizing radiation is performed. The associated radiation safety issues and the prevention and mitigation of incidents and accidents are discussed. A comprehensive discussion of the security issues associated to the global use of radiation sources for the aforementioned applications and the inherent radiation detection requirements will be presented. Scientific, technical, legal, ethical, socio-economic issues are put forward and discussed.

  2. LMFBR safety. 3. Review of current issues and bibliography of literature (1972--1974)

    International Nuclear Information System (INIS)

    Buchanan, J.R.; Keilholtz, G.W.

    1977-01-01

    The report discusses the current status of liquid-metal fast breeder reactor (LMFBR) development and one of the principal safety issues, a hypothetical core-disruptive accident (HCDA). Bibliographic information on worldwide LMFBRs relative to the development of the breeder reactor as a safe source of nuclear power is presented for the period 1972 through 1974. The bibliography consists of approximately 1380 abstracts covering research and development and operating experiences leading up to the present design practices that are necessary for the licensing of breeder reactors. Key-word, author, and permuted-title indexes are included

  3. LMFBR safety. 3. Review of current issues and bibliography of literature (1972--1974)

    Energy Technology Data Exchange (ETDEWEB)

    Buchanan, J.R.; Keilholtz, G.W.

    1977-02-24

    The report discusses the current status of liquid-metal fast breeder reactor (LMFBR) development and one of the principal safety issues, a hypothetical core-disruptive accident (HCDA). Bibliographic information on worldwide LMFBRs relative to the development of the breeder reactor as a safe source of nuclear power is presented for the period 1972 through 1974. The bibliography consists of approximately 1380 abstracts covering research and development and operating experiences leading up to the present design practices that are necessary for the licensing of breeder reactors. Key-word, author, and permuted-title indexes are included.

  4. LMFBR safety. 1. Review of current issues and bibliography of literature, 1960--1969

    Energy Technology Data Exchange (ETDEWEB)

    Buchanan, J.R.; Keilholtz, G.W.

    1976-08-16

    This report discusses the current status of liquid-metal fast breeder (LMFBR) development and one of the principal safety issues, a hypothetical core-disruptive accident (HCDA). Bibliographic information on worldwide LMFBRs relative to the development of the breeder reactor as a safe source of nuclear power is presented for the period 1960 through 1969. The bibliography consists of 1560 abstracts covering early research and development and operating experiences leading up to the present design practices that are necessary for the licensing of breeder reactors. Key-word, author, and permuted-title indexes are included for completeness.

  5. LMFBR safety. 1. Review of current issues and bibliography of literature, 1960--1969

    International Nuclear Information System (INIS)

    Buchanan, J.R.; Keilholtz, G.W.

    1976-01-01

    This report discusses the current status of liquid-metal fast breeder (LMFBR) development and one of the principal safety issues, a hypothetical core-disruptive accident (HCDA). Bibliographic information on worldwide LMFBRs relative to the development of the breeder reactor as a safe source of nuclear power is presented for the period 1960 through 1969. The bibliography consists of 1560 abstracts covering early research and development and operating experiences leading up to the present design practices that are necessary for the licensing of breeder reactors. Key-word, author, and permuted-title indexes are included for completeness

  6. Type B liquid package technical issues -- Experience with LR-56 safety analysis

    International Nuclear Information System (INIS)

    Smith, A.C.; Alstine, M.N. van; Gromada, R.J.; Hensel, S.J.; Gupta, N.K.

    1997-01-01

    In the course of the development of nuclear industry in France, shipment of Type B quantities (i.e., quantities having significant radiological consequences) of radioactive liquids between different, sites became necessary. Based on the experience acquired at the Commissariat a l'Energie Atomique (CEA) nuclear centers, a series of tanker trailers has been developed to meet this need. Similarly, as part of the ongoing program to process wastes to stable end forms, a need exists to move radioactive liquids at several DOE sites. The LR-56, developed by CEA to transport liquids of medium to high activity, was selected for these US applications, based on its design features and successful operating experience in France. No comparable Type B liquid packages are certified in the US Packages employed in transport of Type B quantities of liquids are either only suitable for small volumes, or are used within site boundaries with extensive administrative controls employed to insure that an adequate level of safety is maintained. The requirement is to provide safety equivalent to the level established by federal regulations in 10 CFR 71. Type B radioactive materials packages (RAM packages) are typically simple, rugged containers which are designed and fabricated in accordance with the ASME Boiler and Pressure Vessel Code to provide containment under the normal conditions of transport (NCT) and hypothetical accident conditions (HAC) established by the regulations. Packages designed for liquid contents must address a number of technical issues which are not common to packages for solid contents. This paper reviews the technical issues associated with Type B liquid packages from the perspective of the experience gained from the evaluation of the LR-56 for use at DOE sites

  7. Data-flow coupling and data-acquisition triggers for the PreSPEC-AGATA campaign at GSI

    Energy Technology Data Exchange (ETDEWEB)

    Ralet, D., E-mail: D.Ralet@gsi.de [Institut für Kernphysik, Technische Universität Darmstadt, Darmstadt (Germany); GSI, Helmholtzzentrum für Schwerionenforschung GmbH, Darmstadt (Germany); Pietri, S. [GSI, Helmholtzzentrum für Schwerionenforschung GmbH, Darmstadt (Germany); Aubert, Y. [Institut de Physique Nucléaire, Orsay (France); Bellato, M.; Bortolato, D. [Istituto Nazionale di Fisica Nucleare sezione di Padova, Padova (Italy); Brambilla, S.; Camera, F. [Istituto Nazionale di Fisica Nucleare sezione di Milano, Milano (Italy); Dosme, N. [CSNSM, Université Paris-Sud, Orsay (France); Gadea, A. [Instituto di Fisica Corpuscular, Valencia (Spain); Gerl, J. [GSI, Helmholtzzentrum für Schwerionenforschung GmbH, Darmstadt (Germany); Golubev, P. [Department of Physics, Lund University, Lund (Sweden); Grave, X. [CSNSM, Université Paris-Sud, Orsay (France); Johansson, H.T. [Chalmers University of Technology, Göteborg (Sweden); Karkour, N.; Korichi, A. [CSNSM, Université Paris-Sud, Orsay (France); Kurz, N. [GSI, Helmholtzzentrum für Schwerionenforschung GmbH, Darmstadt (Germany); Lafay, X.; Legay, E.; Linget, D. [CSNSM, Université Paris-Sud, Orsay (France); Pietralla, N. [Institut für Kernphysik, Technische Universität Darmstadt, Darmstadt (Germany); GSI, Helmholtzzentrum für Schwerionenforschung GmbH, Darmstadt (Germany); and others

    2015-06-21

    The PreSPEC setup for high-resolution γ-ray spectroscopy using radioactive ion beams was employed for experimental campaigns in 2012 and 2014. The setup consisted of the state of the art Advanced GAmma Tracking Array (AGATA) and the High Energy γ deteCTOR (HECTOR+) positioned around a secondary target at the final focal plane of the GSI FRagment Separator (FRS) to perform in-beam γ-ray spectroscopy of exotic nuclei. The Lund York Cologne CAlorimeter (LYCCA) was used to identify the reaction products. In this paper we report on the trigger scheme used during the campaigns. The data-flow coupling between the Multi-Branch System (MBS) based Data AcQuisition (DAQ) used for FRS-LYCCA and the “Nouvelle Acquisition temps Réel Version 1.2 Avec Linux” (NARVAL) based acquisition system used for AGATA are also described.

  8. U.S. NRC's generic issues program

    International Nuclear Information System (INIS)

    Kauffman, J.V.; Foster, J.W.

    2008-01-01

    The United States Nuclear Regulatory Commission (NRC) has a Generic Issues Program (GIP) to address Generic Issues (GI). A GI is defined as 'a regulatory matter involving the design, construction, operation, or decommissioning of several, or a class of, NRC licensees or certificate holders that is not sufficiently addressed by existing rules, guidance, or programs'. This rather legalistic definition has several practical corollaries: First, a GI must involve safety. Second, the issue must involve at least two plants, or it would be a plant-specific issue rather than a GI. Third, the potential safety question must not be covered by existing regulations and guidance (compliance). Thus, the effect of a GI is to potentially change the body of regulations and associated guidance (e.g., regulatory guides). The GIP was started in 1976, thus it is a relatively mature program. Approximately 850 issues have been processed by the program to date. More importantly, even after 30 years, new GIs continue to be proposed. The entire set of Generic Issues (GIs) is updated annually in NUREG-0933, 'A Prioritization of Generic Safety Issues'. GIs normally involve complex questions of safety and regulation. Efficient and effective means of addressing these issues are very important for regulatory effectiveness. If an issue proves to pose a genuine, significant safety question, then swift, effective, enforceable, and cost-effective action needs to be taken. Conversely, if an issue is of little safety significance, the issue should be dismissed in an expeditious manner, avoiding unnecessary expenditure of resources and regulatory burden or uncertainty. This paper provides a summary of the 5-stage program, from identification through the regulatory assessment stage. The paper also includes a discussion of the program's seven criteria, sources of proposed GIs, recent improvements, publicly available information, historical performance, and status of current GIs. (authors)

  9. Safety issues in urban transit facilities for hydrogen-fueled buses

    International Nuclear Information System (INIS)

    Hay, R.H.; Ducharme, P.

    2004-01-01

    'Full text:' The Canadian Transportation Fuel Cell Alliance (CTFCA), created by the Canadian Government as part of its 2000 Climate Change Action Plan, has commissioned MARCON-DDM's Hydrogen Intervention Team (HIT) to provide a roadmap for urban transit systems that wish to move to hydrogen fuel cell-powered bus fleets. HIT is currently in the process of gathering information from hydrogen technology providers, bus manufacturers, fuelling system providers and urban transit systems in Canada, the US and Europe. In September, HIT will be in a position to provide a hands-on perspective of the introduction of fuel-cell buses in the Canadian environment. Part of the process of adding hydrogen-fueled busses to urban transit systems involves phasing in the new technology to minimize the economic cost. This involves substituting hydrogen buses into the normal bus procurement life cycle and maximizing the use of existing facilities for garaging, maintenance and fueling. Using a schematic outline of an urban transit system, this presentation will outline the safety issues specific to hydrogen in such systems, particularly for garaging, maintenance and fueling components. It will then outline how safety of these component is addressed in current and proposed codes, standards and recommended practices. Based on these requirements the impact of the introduction of hydrogen-fueled buses on each component of the transit system will be addressed in terms of the adaptations of current facilities and practices or the requirements for new facilities and practices. (author)

  10. Hydrogen related safety issues in the context of containments of Indian PHWRs

    International Nuclear Information System (INIS)

    Markendeya, S.G.; Ghosh, A.K.; Kushwaha, H.S.; Venkat Raj, V.

    2002-01-01

    Full text: Assessment of risk due to hydrogen released during postulated hypothetical accident scenarios in the nuclear power plants (NPPs) has been an important area of R and D studies world over. The issues, such as appropriate methodologies for estimation of hydrogen source term and for hydrogen dispersion calculations, technology development for hydrogen mitigation in containment of NPPs and assessment of damage due to deflagration/detonation of hydrogen (if it occurs) are being addressed as a part of some of the multidisciplinary study programs currently underway in BARC. While a significant overall progress has been achieved in general as a result of these programs, requirements of further fine-tuning of these studies have also emerged. The present paper takes a brief look at the current state-of the-art technology available to address these issues. The progress of R and D studies underway at BARC has also been critically reviewed in the paper to bring out necessary planning of further studies so as to enhance the safety of Indian NPPs

  11. PENGARUH KOMPENSASI DAN LINGKUNGAN KERJA TERHADAP KINERJA KARYAWAN DIVISI QIP PT. GSI CIANJUR

    Directory of Open Access Journals (Sweden)

    Suharyanto Suharyanto

    2014-12-01

    Full Text Available The role of human resource management is continously improved to enhance the performance of employees. PT GSI, as one of Indonesian company producing shoe products to meet demand from all around the world, needs employees with high performance. On the other side, the employees need reasonable compensation and safe work environments. This research is conducted to investigate the relationships and the effects of the compensation and work environment variables on the job performance. Using causal descriptive research method, samples of 77 units are randomly taken from 328 labors at the Quality Inspection Production Divison. The questionaire comprising eighteen questions is applied to explore the employee minds and perceptions on the relationships and effects of the compensation and work environment variables toward the job performance variable. The result of this research shows that compensation (X1 and work environment (X2 variables simultanously effect to the job performance variable (Y. The linier regression equation constructed is represented by Y = 4,375 - 0,181X1 + 0,382X2.

  12. Consequence evaluation of radiation embrittlement of Trojan reactor pressure vessel supports

    International Nuclear Information System (INIS)

    Lu, S.C.

    1990-01-01

    The consequences evaluation of radiation embrittlement of reactor pressure vessel (RPV) supports of nuclear power plants offers a more direct and less controversial approach to the safety concerns addressed by Generic Safety Issue 15(GSI-15) identified by the U.S. Nuclear Regulatory Commission (NRC) because this approach depends on more conventional methodologies widely accepted by the engineering community. The success of this evaluation may permit a satisfactory resolution to GSI-15 by demonstrating that even under the most unfavorable circumstances, i.e., complete failure of all RPV supports, there is no undue risk to public safety. This evaluation is divided into two phases. Phase 1 is a pilot study on a selected nuclear power plant. Phase 2 is a parametric study undertaken in an attempt to generalize the conclusion of the pilot study to other nuclear power plants. The Trojan nuclear power plant was selected for the pilot study because its RPV supports are located in the high radiation zone and are subject to high tensile stresses. The pilot study comprises a structural evaluation and an effect evaluation and assumes that all four RPV supports have completely lost their load carrying capability. The current paper addresses Phase 1 results and conclusions

  13. A Seismic Analysis for Reflective Metal Insulation

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Kyuhyung; Kim, Taesoon [KHNP CRI, Daejeon (Korea, Republic of)

    2016-10-15

    U.S. NRC (Nuclear Regulatory Commission) GSI- 191 (Generic Safety Issue-191) is concerned about the head-loss of emergency core cooling pumps caused by calcium silicate insulation debris accumulated on a sump screen when a loss of coolant accident (LOCA). In order to cope with the concern, many nuclear plants in U. S. have been replacing calcium silicate insulation in containment building with reflective metal insulation (RMI). In Korea, RMI has been used for only reactor vessels recently constructed, but the RMI was imported. Therefore, we have been developing the domestic design of RMI to supply to nuclear power plants under operation and construction in relation to the GSI-191. This paper covers that the structural integrity of the RMI assembly was evaluated under SSE (safety shutdown earthquake) load. An analysis model was built for the seismic test system of a reflective metal insulation assembly and pre-stress, modal, and spectrum analysis for the model were performed using a commercial structural analysis code, ANSYS. According to the results of the analyses, the buckles fastening the RMIs showed the structural integrity under the required response spectrum containing the safety shutdown earthquake loads applied to main components in containment building. Consequently, since the RMI isn't disassembled under the SSE load, the RMI is judged not to affect safety related components.

  14. A Seismic Analysis for Reflective Metal Insulation

    International Nuclear Information System (INIS)

    Kim, Kyuhyung; Kim, Taesoon

    2016-01-01

    U.S. NRC (Nuclear Regulatory Commission) GSI- 191 (Generic Safety Issue-191) is concerned about the head-loss of emergency core cooling pumps caused by calcium silicate insulation debris accumulated on a sump screen when a loss of coolant accident (LOCA). In order to cope with the concern, many nuclear plants in U. S. have been replacing calcium silicate insulation in containment building with reflective metal insulation (RMI). In Korea, RMI has been used for only reactor vessels recently constructed, but the RMI was imported. Therefore, we have been developing the domestic design of RMI to supply to nuclear power plants under operation and construction in relation to the GSI-191. This paper covers that the structural integrity of the RMI assembly was evaluated under SSE (safety shutdown earthquake) load. An analysis model was built for the seismic test system of a reflective metal insulation assembly and pre-stress, modal, and spectrum analysis for the model were performed using a commercial structural analysis code, ANSYS. According to the results of the analyses, the buckles fastening the RMIs showed the structural integrity under the required response spectrum containing the safety shutdown earthquake loads applied to main components in containment building. Consequently, since the RMI isn't disassembled under the SSE load, the RMI is judged not to affect safety related components

  15. NS [Nuclear Safety] update. Current safety and security activities and developments taking place in the Department of Nuclear Safety and Security, Issue no. 15, February 2011

    International Nuclear Information System (INIS)

    2011-02-01

    The current issue presents information about the following topics: Supporting radiation protection in medicine. Wano's pre-startup support. One stop for incident and emergency communications. Emergency preparedness in IAEA Member States. Sophisticated On-Site Nuclide Identification (RanidSONNI). Over land, sea and air: safe and secure transport of radioactive material. INES at 20: Success from simplicity. IAEA and Ibero-American Forum - strengthening ties. Highlights of the 54th IAEA General Conference, 20-24 September 2010. Highlights of the International conference on Challenges faced by TSOs. Department of Nuclear Safety programme highlights

  16. The role of aging in resolving the ferrocyanide safety issue

    International Nuclear Information System (INIS)

    Babad, H.; Meacham, J.E.; Simpson, B.C.; Cash, R.J.

    1993-08-01

    A chemical process called aging, in which stored ferrocyanide waste could be dissolved and dispersed among waste tanks, or destroyed by radiolysis and hydrolysis, has been proposed at the Hanford Site. This paper summarizes the results of applied research, characterization, and modeling activities on Hanford Site ferrocyanide waste material that support the existence of a chemical aging mechanism. Test results from waste simulants and actual waste tank materials are presented and compared with theoretical estimates. Chemical and energetic behavior of the materials are the key indicators of destruction or dispersion. Screening experiments on vendor-prepared sodium nickel ferrocyanide and the initial results from core sampling support the concept that aging of ferrocyanide is taking place in the waste tanks at the Hanford Site. This report defines the concept of waste aging and explains the role that aging could play in resolving the Hanford Site ferrocyanide safety issue

  17. Patient safety: Safety culture and patient safety ethics

    DEFF Research Database (Denmark)

    Madsen, Marlene Dyrløv

    2006-01-01

    ,demonstrating significant, consistent and sometimes large differences in terms of safety culture factors across the units participating in the survey. Paper 5 is the results of a study of the relation between safety culture, occupational health andpatient safety using a safety culture questionnaire survey......Patient safety - the prevention of medical error and adverse events - and the initiative of developing safety cultures to assure patients from harm have become one of the central concerns in quality improvement in healthcare both nationally andinternationally. This subject raises numerous...... challenging issues of systemic, organisational, cultural and ethical relevance, which this dissertation seeks to address through the application of different disciplinary approaches. The main focus of researchis safety culture; through empirical and theoretical studies to comprehend the phenomenon, address...

  18. The use of human factors methods to identify and mitigate safety issues in radiation therapy

    International Nuclear Information System (INIS)

    Chan, Alvita J.; Islam, Mohammad K.; Rosewall, Tara; Jaffray, David A.; Easty, Anthony C.; Cafazzo, Joseph A.

    2010-01-01

    Background and purpose: New radiation therapy technologies can enhance the quality of treatment and reduce error. However, the treatment process has become more complex, and radiation dose is not always delivered as intended. Using human factors methods, a radiotherapy treatment delivery process was evaluated, and a redesign was undertaken to determine the effect on system safety. Material and methods: An ethnographic field study and workflow analysis was conducted to identify human factors issues of the treatment delivery process. To address specific issues, components of the user interface were redesigned through a user-centered approach. Sixteen radiation therapy students were then used to experimentally evaluate the redesigned system through a usability test to determine the effectiveness in mitigating use errors. Results: According to findings from the usability test, the redesigned system successfully reduced the error rates of two common errors (p < .04 and p < .01). It also improved the mean task completion time by 5.5% (p < .02) and achieved a higher level of user satisfaction. Conclusions: These findings demonstrated the importance and benefits of applying human factors methods in the design of radiation therapy systems. Many other opportunities still exist to improve patient safety in this area using human factors methods.

  19. Safety issues associated with the use of nanoparticles in human body.

    Science.gov (United States)

    Sufian, Mian Muhammad; Khattak, Jabar Zaman Khan; Yousaf, Shahzad; Rana, Muhammad Suleman

    2017-09-01

    Nanotechnology has transformed the world by the introduction of a distinctive class of materials and products in a wide array of fields. It has contributed to the production of innovative materials and devices. Having unique advantages and domestic along with industrial applications, however, has raised the issue of safety for consumers, producers and environment. Having a comparative smaller dimension and other exclusive properties, nanoparticles have the ability to harm human body by interacting through various mechanisms. Here, we endeavoured to review and discuss the characteristics of nanoparticles relevant to their toxicity, conceivable exposure routes of nanoparticles to human body like skin contact, inhalation, and ingestion, and the basic approaches which can aid to control human exposures to toxic nanoparticles have been discussed. Copyright © 2017 Elsevier B.V. All rights reserved.

  20. LMFBR safety. 2. Review of current issues and bibliography of literature, 1970--1972

    International Nuclear Information System (INIS)

    Buchanan, J.R.; Keilholtz, G.W.

    1976-01-01

    This report discusses the current status of liquid-metal fast breeder reactor (LMFBR) development and one of the principal safety issues, a hypothetical core-disruptive accident (HCDA). Bibliographic information on worldwide LMFBRs relative to the development of the breeder reactor as a safe source of nuclear power is presented for the period 1970 through 1972. The bibliography consists of approximately 1620 abstracts covering early research and development and operating experiences leading up to the present design practices that are necessary for the licensing of breeder reactors. Key-word, author, and permuted-title indexes are included for completeness

  1. LMFBR safety. 4. Review of current issues and bibliography of literature (1974--1975)

    Energy Technology Data Exchange (ETDEWEB)

    Buchanan, J.R.; Keilholtz, G.W.

    1977-03-21

    This report discusses the current status of liquid-metal fast breeder reactor (LMFBR) development and one of the principal safety issues, a hypothetical core-disruptive accident (HCDA). Bibliographic information on worldwide LMFBRs relative to the development of the breeder reactor as a safe source of nuclear power is presented for the period 1974 through 1975. The bibliography consists of approximately 1554 abstracts covering early research and development and operating experiences leading up to the present design practices that are necessary for the licensing of breeder reactors. Key-word, author, and permuted-title indexes are included for completeness.

  2. LMFBR safety. 4. Review of current issues and bibliography of literature (1974--1975)

    International Nuclear Information System (INIS)

    Buchanan, J.R.; Keilholtz, G.W.

    1977-01-01

    This report discusses the current status of liquid-metal fast breeder reactor (LMFBR) development and one of the principal safety issues, a hypothetical core-disruptive accident (HCDA). Bibliographic information on worldwide LMFBRs relative to the development of the breeder reactor as a safe source of nuclear power is presented for the period 1974 through 1975. The bibliography consists of approximately 1554 abstracts covering early research and development and operating experiences leading up to the present design practices that are necessary for the licensing of breeder reactors. Key-word, author, and permuted-title indexes are included for completeness

  3. LMFBR safety. 2. Review of current issues and bibliography of literature, 1970--1972

    Energy Technology Data Exchange (ETDEWEB)

    Buchanan, J.R.; Keilholtz, G.W.

    1976-11-22

    This report discusses the current status of liquid-metal fast breeder reactor (LMFBR) development and one of the principal safety issues, a hypothetical core-disruptive accident (HCDA). Bibliographic information on worldwide LMFBRs relative to the development of the breeder reactor as a safe source of nuclear power is presented for the period 1970 through 1972. The bibliography consists of approximately 1620 abstracts covering early research and development and operating experiences leading up to the present design practices that are necessary for the licensing of breeder reactors. Key-word, author, and permuted-title indexes are included for completeness.

  4. A pulsed supersonic gas jet target for precision spectroscopy at the HITRAP facility at GSI

    Science.gov (United States)

    Tiedemann, D.; Stiebing, K. E.; Winters, D. F. A.; Quint, W.; Varentsov, V.; Warczak, A.; Malarz, A.; Stöhlker, Th.

    2014-11-01

    A pulsed supersonic gas jet target for experiments at the HITRAP facility at the GSI Helmholtzzentrum für Schwerionenforschung in Darmstadt has been designed and built as a multi-purpose installation for key experiments on fundamental atomic physics in strong fields. This setup is currently installed at the Institut für Kernphysik of Goethe-University, Frankfurt am Main (IKF), in order to explore its operation prior to its installation at the HITRAP facility. Design and performance of the target are described. The measured target densities of 5.9×1012 atoms/cm3 for helium and 8.1×1012 atoms/cm³ for argon at the stagnation pressure of 30 bar match the required values. The target-beam diameter of 0.9 mm and the pulsed operation mode (jet built-up-time ≤15 ms) are well suited for the use at HITRAP.

  5. Thermal reactor safety

    International Nuclear Information System (INIS)

    1980-06-01

    Information is presented concerning new trends in licensing; seismic considerations and system structural behavior; TMI-2 risk assessment and thermal hydraulics; statistical assessment of potential accidents and verification of computational methods; issues with respect to improved safety; human factors in nuclear power plant operation; diagnostics and activities in support of recovery; LOCA transient analysis; unresolved safety issues and other safety considerations; and fission product transport

  6. Thermal reactor safety

    Energy Technology Data Exchange (ETDEWEB)

    1980-06-01

    Information is presented concerning new trends in licensing; seismic considerations and system structural behavior; TMI-2 risk assessment and thermal hydraulics; statistical assessment of potential accidents and verification of computational methods; issues with respect to improved safety; human factors in nuclear power plant operation; diagnostics and activities in support of recovery; LOCA transient analysis; unresolved safety issues and other safety considerations; and fission product transport.

  7. Implementing new technologies for public safety communication: competing frequency demands and standardization issues

    Science.gov (United States)

    Stevens, Kathryn J.

    1997-01-01

    Attempting to incorporate new technology into an existing environment is often very difficult. The problems are lengthy to resolve, wrought with confusion and seldom turn out like anyone expected. This document represents an overview of one such attempt. It outlines the general areas of concern which could be affected by a transition, and potential problems that may be encountered as a result of the effort. Over the past several decades, many local, state and federal agencies are pressing for more efficient use of frequency spectrums. The urgency of this issue has grown due to the demands of several groups wanting access to these channels for commercial use. Pager systems, cellular telephones, radio systems for private businesses all demand more space. Public safety agencies are starting to fear their needs will diminish in importance as the available channel spectrums are consumed by commercial ventures. How to share these channels, purchase appropriate equipment to meet your needs, and stay within a reasonable budget are not easy tasks. Public safety agencies who rely on communication networks in the performance of their jobs also know why encryption is important. Protecting the rights of citizens as police exchange information over the air, maintaining the integrity of an investigation and officer safety are all concerns police must address each time they use a radio.

  8. Conceptual design and performance study for the first implementation of AGATA at the in-flight RIB facility of GSI

    Science.gov (United States)

    Domingo-Pardo, C.; Bazzacco, D.; Doornenbal, P.; Farnea, E.; Gadea, A.; Gerl, J.; Wollersheim, H. J.; Agata Collaboration

    2012-12-01

    The main objective of the Advanced GAmma Tracking Array (AGATA) is the investigation of the structure of exotic nuclei at the new generation of RIB facilities. As part of the preparatory phase for FAIR-NUSTAR, AGATA is going to be installed at the FRS fragmentation facility of the GSI centre for an experimental campaign to be performed in 2012 and 2013. Owing to its γ-ray tracking capabilities and the envisaged enhancement in resolving power, a series of in-flight γ-ray spectroscopy experiments are being planned. The present work describes the conceptual design of this first implementation of AGATA at GSI-FRS, and provides information about the expected performance figures. According to the characteristics of each particular experiment, it is foreseen that the target-array distance is adjusted in order to achieve the optimum compromise between detection efficiency and energy resolution, or to cover an specific angular range of the emitted electromagnetic radiation. Thus, a comprehensive Monte Carlo study of the detection sensitivity in terms of photopeak efficiency, resolution and peak-to-total ratio, as a function of the target-array distance is presented. Several configurations have been investigated, and MC-calculations indicate that a remarkable enhancement in resolving power can be achieved when double-cluster AGATA detectors are developed and implemented. Several experimental effects are also investigated. This concerns the impact of passive materials between the target and the array, the angular distribution of the detection efficiency and the influence of target thickness effects and transition lifetimes in the attainable detection sensitivity. A short overview on half-life measurements via lineshape effects utilizing AGATA is also presented.

  9. Formal Safety versus Real Safety: Quantitative and Qualitative Approaches to Safety Culture – Evidence from Estonia

    Directory of Open Access Journals (Sweden)

    Järvis Marina

    2016-10-01

    Full Text Available This paper examines differences between formal safety and real safety in Estonian small and medium-sized enterprises. The results reveal key issues in safety culture assessment. Statistical analysis of safety culture questionnaires showed many organisations with an outstanding safety culture and positive safety attitudes. However, qualitative data indicated some important safety weaknesses and aspects that should be included in the process of evaluation of safety culture in organisations.

  10. Radiographers' professional knowledge regarding parameters and safety issues in plain radiography: a questionnaire survey.

    Science.gov (United States)

    Farajollahi, A R; Fouladi, D F; Ghojazadeh, M; Movafaghi, A

    2014-08-01

    To review the knowledge of radiographers and examine the possible sociodemographic and situational contributors to this knowledge. A questionnaire survey was devised and distributed to a cohort of 120 radiographers. Each questionnaire contained two sections. In the first section, background data, including sex, age, highest academic level, grade point average (GPA), length of time from graduation, work experience as a radiographer and the status of previous refresher course(s), were collected. The second section contained 17 multiple-choice questions concerning radiographic imaging parameters and safety issues. The response rate was 63.8%. In univariate analytic model, higher academic degree (p workplace (p = 0.04) and taking previous refresher course(s) (p = 0.01) were significantly associated with higher knowledge score. In multivariate analytic model, however, higher academic degree (B = 1.62; p = 0.01), higher GPA (B = 0.50; p = 0.01) and taking previous refresher course(s) (B = -1.26; p = 0.03) were independently associated with higher level of knowledge. Age, sex, length of time from graduation and work experience were not associated with the respondents' knowledge score. Academic background is a robust indicator of a radiographer's professional knowledge. Refresher courses and regular knowledge assessments are highly recommended. This is the first study in the literature that examines professional knowledge of radiographers in terms of technical and safety issues in plain radiography. Academic degree, GPA and refresher courses are independent predictors of this knowledge. Regular radiographer professional knowledge checks may be recommended.

  11. Nordic nuclear safety research program 1994-1997. Project coordination incl. SAM-4 general information issues. Report 1996. Plans for 1997

    International Nuclear Information System (INIS)

    1997-04-01

    NKS (Nordic Nuclear Safety Research) is a cooperative body in nuclear safety, radiation protection and emergency preparedness. Its purpose is to carry out cost-effective Nordic projects, thus producing research results, exercises, information, recommendations, manuals etc., to be used by decision makers and other concerned staff members at authorities and within the nuclear industry. This is the annual report for 1996, the third year of the fifth four-year NKS program (1994-1997). The report also contains plans for the rest of the program period, including budget proposals. The following major fields of research have been identified: reactor safety; radioactive waste; radioecology; emergency preparedness; and information issues. A total of nine projects are now under way within that framework. One project (RAK-1) is dedicated to reactor safety strategies: how to avoid serious accidents. A parallel project (RAK-2) deals with minimizing releases in case of an accident. When can an overheated reactor core still be water-cooled? What might be the consequences of the cooling? All Nordic countries have long-lived low and medium level radioactive waste that requires final disposal. One project (AFA-1) addresses that issue. Environmental impact of radioactive releases is studied in two radioecology projects. The project on marine radioecology, including sediment research (EKO-1), encompasses sampling, analysis and modeling. These are also key issues in the project on long ecological half-lives in semi-natural systems (EKO-2). The transfer of radioactive cesium and strontium in the chains soil - vegetation - sheep and mushroom - roe deer is studied, along with freshwater systems. Long-term doses to main is the ultimate output from the obtained models. Another aspect of environmental impact is emergency preparedness. A recently started project, EKO-5, addresses the issue of early planning for cleanup operations following a fallout. 'Early' in this context means within the

  12. 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)

  13. Current issues in developing safety culture while establishing wind energy power plants in India

    Energy Technology Data Exchange (ETDEWEB)

    Gowda, M.C.M.; Repaka, B.; Gowda, P. [MSRIT Research Centre, Bangalore (India); Chandrashekar, R. [SaIT, Bangalore (India)

    2012-07-01

    Safety is important to every one working in the various organizations. They want to be safe when coming to work, at the time of work and going back to home. The ultimate aim of every worker is to work for the needs/money and or satisfaction where these would get prioritized according to the individuals. People don't want accidents to happen. People don't want to get themselves injured nor their colleagues. People would like and love to work in a company which cares for them and keeps them safe. Having said this then what makes them meet with or see an accident in the wind farm? Yes it is the unsafe act and unsafe condition which causes an accident in the wind farm. The present study put forward the factors /issues that influence people behaviors as part of weakening the safety culture to perform an unsafe act or to ignore and work in an unsafe condition. (Author)

  14. WNA's worldwide overview on front-end nuclear fuel cycle growth and health, safety and environmental issues.

    Science.gov (United States)

    Saint-Pierre, Sylvain; Kidd, Steve

    2011-01-01

    This paper presents the WNA's worldwide nuclear industry overview on the anticipated growth of the front-end nuclear fuel cycle from uranium mining to conversion and enrichment, and on the related key health, safety, and environmental (HSE) issues and challenges. It also puts an emphasis on uranium mining in new producing countries with insufficiently developed regulatory regimes that pose greater HSE concerns. It introduces the new WNA policy on uranium mining: Sustaining Global Best Practices in Uranium Mining and Processing-Principles for Managing Radiation, Health and Safety and the Environment, which is an outgrowth of an International Atomic Energy Agency (IAEA) cooperation project that closely involved industry and governmental experts in uranium mining from around the world. Copyright © 2010 Health Physics Society

  15. Current and emerging occupational safety and health (OSH) issues in the healthcare sector, including home and community care

    NARCIS (Netherlands)

    Jong, T. de; Bos, E.; Pawlowska-Cyprysiak, K.; Hildt-Ciupinska, K.; Malinska, M.; Nicolescu, G.; Trifu, A.

    2014-01-01

    This report gives an overview of the current and emerging OSH issues for health- and social care workers and how these affect their safety and health at work and influence the quality of care they provide. It combines a literature review and the responses received to a questionnaire sent to OSH

  16. Data quality objective to support resolution of the organic complexant safety issue

    International Nuclear Information System (INIS)

    Turner, D.A.; Babad, H.; Buckley, L.L.; Meacham, J.E.

    1995-01-01

    This document records the data quality objectives (DQO) process applied to the organic complexant safety issue at the Hanford Site. Two important outputs of this particular DQO application were the following: (1) decision rules for categorizing organic tanks; and (2) analytical requirements that feed into the tank-specific characterization plans. The decision rules developed in this DQO allow the organic tanks to be categorized as safe, conditionally safe, or unsafe based on fuel and moisture concentrations. Then analytical requirements from this DQO process fall into two groups, primary and secondary. The primary data requirements are always applied, while the secondary requirements are only necessary on those half segment samples that violate the fuel and moisture decision rules or that propagate during adiabatic calorimetry testing

  17. 20 CFR 725.463 - Issues to be resolved at hearing; new issues.

    Science.gov (United States)

    2010-04-01

    ... 20 Employees' Benefits 3 2010-04-01 2010-04-01 false Issues to be resolved at hearing; new issues... OF THE FEDERAL MINE SAFETY AND HEALTH ACT, AS AMENDED Hearings § 725.463 Issues to be resolved at hearing; new issues. (a) Except as otherwise provided in this section, the hearing shall be confined to...

  18. Safety studies on Korean fusion DEMO plant using integrated safety assessment methodology

    International Nuclear Information System (INIS)

    Oh, Kyemin; Kang, Myoung-suk; Heo, Gyunyoung; Kim, Hyoung-chan

    2014-01-01

    Highlights: •The purpose of this paper is to suggest methodology that can investigate safety issues and provides a case study for Korean fusion DEMO plant. •The concepts of integrated safety assessment methodology (ISAM) that can be applied in addressing regulatory requirements and recognizing safety issues for K-DEMO were emphasized. •Phenomena identification and ranking table (PIRT) was proposed. It can recognize vulnerabilities of systems and identify the gaps in technical areas requiring additional researches. •This work is expected to contribute on the conceptual design of safety features for K-DEMO to design engineers and the guidance for regulatory requirements to licensers. -- Abstract: The purpose of this paper is to suggest methodology that can investigate safety issues and provides a case study for Korean fusion DEMO plant (K-DEMO) as a part of R and D program through the National Fusion Research Institute of Korea. Even though nuclear regulation and licensing framework is well setup due to the operating and design experience of Pressurized Water Reactors (PWRs) since 1970s, the regulatory authority of South Korea has concerns on the challenge of facing new nuclear facilities including K-DEMO due to the differences in systems, materials, and inherent safety feature from conventional PWRs. Even though the follow-up of the ITER license process facilitates to deal with significant safety issues of fusion facilities, a licensee as well as a licenser should identify the gaps between ITER and DEMO in terms of safety issues. First we reviewed the methods of conducting safety analysis for unprecedented nuclear facilities such as Generation IV reactors, particularly very high temperature reactor (VHTR), which is called as integrated safety assessment methodology (ISAM). Second, the analysis for the conceptual design of K-DEMO on the basis of ISAM was conducted. The ISAM consists of five analytical tools to develop the safety requirements from licensee

  19. Safety studies on Korean fusion DEMO plant using integrated safety assessment methodology

    Energy Technology Data Exchange (ETDEWEB)

    Oh, Kyemin; Kang, Myoung-suk [Kyung Hee University, Youngin-si, Gyeonggi-do 446-701 (Korea, Republic of); Heo, Gyunyoung, E-mail: gheo@khu.ac.kr [Kyung Hee University, Youngin-si, Gyeonggi-do 446-701 (Korea, Republic of); Kim, Hyoung-chan [National Fusion Research Institute, Daejeon-si 305-333 (Korea, Republic of)

    2014-10-15

    Highlights: •The purpose of this paper is to suggest methodology that can investigate safety issues and provides a case study for Korean fusion DEMO plant. •The concepts of integrated safety assessment methodology (ISAM) that can be applied in addressing regulatory requirements and recognizing safety issues for K-DEMO were emphasized. •Phenomena identification and ranking table (PIRT) was proposed. It can recognize vulnerabilities of systems and identify the gaps in technical areas requiring additional researches. •This work is expected to contribute on the conceptual design of safety features for K-DEMO to design engineers and the guidance for regulatory requirements to licensers. -- Abstract: The purpose of this paper is to suggest methodology that can investigate safety issues and provides a case study for Korean fusion DEMO plant (K-DEMO) as a part of R and D program through the National Fusion Research Institute of Korea. Even though nuclear regulation and licensing framework is well setup due to the operating and design experience of Pressurized Water Reactors (PWRs) since 1970s, the regulatory authority of South Korea has concerns on the challenge of facing new nuclear facilities including K-DEMO due to the differences in systems, materials, and inherent safety feature from conventional PWRs. Even though the follow-up of the ITER license process facilitates to deal with significant safety issues of fusion facilities, a licensee as well as a licenser should identify the gaps between ITER and DEMO in terms of safety issues. First we reviewed the methods of conducting safety analysis for unprecedented nuclear facilities such as Generation IV reactors, particularly very high temperature reactor (VHTR), which is called as integrated safety assessment methodology (ISAM). Second, the analysis for the conceptual design of K-DEMO on the basis of ISAM was conducted. The ISAM consists of five analytical tools to develop the safety requirements from licensee

  20. Nuclear power plant safety related pump issues

    Energy Technology Data Exchange (ETDEWEB)

    Colaccino, J.

    1996-12-01

    This paper summarizes of a number of pump issues raised since the Third NRC/ASME Symposium on Valve and Pump Testing in 1994. General issues discussed include revision of NRC Inspection Procedure 73756, issuance of NRC Information Notice 95-08 on ultrasonic flow meter uncertainties, relief requests for tests that are determined by the licensee to be impractical, and items in the ASME OM-1995 Code, Subsection ISTB, for pumps. The paper also discusses current pump vibration issues encountered in relief requests and plant inspections - which include smooth running pumps, absolute vibration limits, and vertical centrifugal pump vibration measurement requirements. Two pump scope issues involving boiling water reactor waterlog and reactor core isolation cooling pumps are also discussed. Where appropriate, NRC guidance is discussed.

  1. Nuclear power plant safety related pump issues

    International Nuclear Information System (INIS)

    Colaccino, J.

    1996-01-01

    This paper summarizes of a number of pump issues raised since the Third NRC/ASME Symposium on Valve and Pump Testing in 1994. General issues discussed include revision of NRC Inspection Procedure 73756, issuance of NRC Information Notice 95-08 on ultrasonic flow meter uncertainties, relief requests for tests that are determined by the licensee to be impractical, and items in the ASME OM-1995 Code, Subsection ISTB, for pumps. The paper also discusses current pump vibration issues encountered in relief requests and plant inspections - which include smooth running pumps, absolute vibration limits, and vertical centrifugal pump vibration measurement requirements. Two pump scope issues involving boiling water reactor waterlog and reactor core isolation cooling pumps are also discussed. Where appropriate, NRC guidance is discussed

  2. 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)

  3. Current status of environmental, health, and safety issues of lithium polymer electric vehicle batteries

    Energy Technology Data Exchange (ETDEWEB)

    Corbus, D; Hammel, C J

    1995-02-01

    Lithium solid polymer electrolyte (SPE) batteries are being investigated by researchers worldwide as a possible energy source for future electric vehicles (EVs). One of the main reasons for interest in lithium SPE battery systems is the potential safety features they offer as compared to lithium battery systems using inorganic and organic liquid electrolytes. However, the development of lithium SPE batteries is still in its infancy, and the technology is not envisioned to be ready for commercialization for several years. Because the research and development (R&D) of lithium SPE battery technology is of a highly competitive nature, with many companies both in the United States and abroad pursuing R&D efforts, much of the information concerning specific developments of lithium SPE battery technology is proprietary. This report is based on information available only through the open literature (i.e., information available through library searches). Furthermore, whereas R&D activities for lithium SPE cells have focused on a number of different chemistries, for both electrodes and electrolytes, this report examines the general environmental, health, and safety (EH&S) issues common to many lithium SPE chemistries. However, EH&S issues for specific lithium SPE cell chemistries are discussed when sufficient information exists. Although lithium batteries that do not have a SPE are also being considered for EV applications, this report focuses only on those lithium battery technologies that utilize the SPE technology. The lithium SPE battery technologies considered in this report may contain metallic lithium or nonmetallic lithium compounds (e.g., lithium intercalated carbons) in the negative electrode.

  4. Improving safety on rural local and tribal roads safety toolkit.

    Science.gov (United States)

    2014-08-01

    Rural roadway safety is an important issue for communities throughout the country and presents a challenge for state, local, and Tribal agencies. The Improving Safety on Rural Local and Tribal Roads Safety Toolkit was created to help rural local ...

  5. Issues relating to safety standards on the geological disposal of radioactive waste. Proceedings of a specialists meeting

    International Nuclear Information System (INIS)

    2002-06-01

    Within the International Atomic Energy Agency focus is currently being placed on establishing safety standards for the geological disposal of radioactive waste. This is a challenging task and a Specialists Meeting was held from 18 to 22 June 2001 with the intention of providing a mechanism for promoting discussion on some of the associated scientific and technical issues and as a means of developing the consensus needed for establishing the standards. The meeting used, as its basis, a number of position papers developed in recent years with the help of a subgroup of the Waste Safety Standards Committee (WASSC), the subgroup on Principles and Criteria for Radioactive Waste Disposal, together with selected relevant regional and national papers. The report contains the summaries of the sessions of the Specialists Meeting together with the conclusions drawn relevant to the establishment of standards. The sessions of the Meeting addressed the following topics: Common framework for radioactive waste disposal; Making the safety case - demonstrating compliance; Safety indicators; Reference critical groups and biospheres; Human intrusion; Reversibility and retrievability; Monitoring and institutional control. The publication contains 26 individual presentations delivered by participants. Each of these presentations was indexed separately

  6. Development of safety-related regulatory requirements for nuclear power in developing countries. Key issue paper no. 4

    International Nuclear Information System (INIS)

    Han, K.I.

    2000-01-01

    In implementing a national nuclear power program, balanced regulatory requirements are necessary to ensure nuclear safety and cost competitive nuclear power, and to help gain public acceptance. However, this is difficult due to the technology-intensive nature of the nuclear regulatory requirements, the need to reflect evolving technology and the need for cooperation among multidisciplinary technical groups. This paper suggests approaches to development of balanced nuclear regulatory requirements in developing countries related to nuclear power plant safety, radiation protection and radioactive waste management along with key technical regulatory issues. It does not deal with economic or market regulation of electric utilities using nuclear power. It suggests that national regulatory requirements be developed using IAEA safety recommendations as guidelines and safety requirements of the supplier country as a main reference after careful planning, manpower buildup and thorough study of international and supplier country's regulations. Regulation making is not recommended before experienced manpower has been accumulated. With an option that the supplier country's regulations may be used in the interim, the lack of complete national regulatory requirements should not deter introduction of nuclear power in developing countries. (author)

  7. Ethical and Safety Issues in Doing Sex Work Research: Reflections From a Field-Based Ethnographic Study in Kolkata, India.

    Science.gov (United States)

    Sinha, Sunny

    2017-05-01

    While much has been said about the risks and safety issues experienced by female sex workers in India, there is a considerable dearth of information about the difficulties and problems that sex work researchers, especially female researchers, experience when navigating the highly political, ideological, and stigmatized environment of the Indian sex industry. As noted by scholars, there are several methodological and ethical issues involved with sex work research, such as privacy and confidentiality of the participants, representativeness of the sample, and informed consent. Yet, there has been reluctance among scholars to comment on their research process, especially with regard to how they deal with the protocols for research ethics when conducting social and behavioral epidemiological studies among female sex workers in India and elsewhere. Drawing on my 7 months of field-based ethnographic research with "flying" or non-brothel-based female sex workers in Kolkata, India, I provide in this article a reflexive account of the problems encountered in implementing the research process, particularly the ethical and safety issues involved in gaining access and acceptance into the sex industry and establishing contact and rapport with the participants. In doing so, it is my hope that future researchers can develop the knowledge necessary for the design of ethical and non-exploitative research projects with sex workers.

  8. Fragmentation of a 500 MeV/nucleon 86Kr beam, investigated at the GSI projectile fragment separator

    International Nuclear Information System (INIS)

    Weber, M.; Donzaud, C.; Geissel, H.; Grewe, A.; Lewitowicz, M.; Magel, A.; Mueller, A.C.; Nickel, F.; Pfuetzner, M.; Piechaczek, A.; Pravikoff, M.; Roeckl, E.; Rykaczewski, K.; Saint-Laurent, M.G.; Schall, I.; Stephan, C.; Tassan-Got, L.; Voss, B.

    1993-10-01

    Production cross-sections and longitudinal momentum distributions have been investigated for reactions between a 500 MeV/nucleon 86 Kr beam and beryllium, copper and tantalum targets. Fragments in a wide A/Z range were studied at the projectile-fragment separator FRS at GSI. The experimental production cross-sections have been used for testing the predictions obtained from a semi-empirical parameterization, a statistical abrasion model and an intranuclear-cascade model. The present study allows to extrapolate the production cross-sections towards very neutron-rich isotopes such as the doubly magic nucleus 78 Ni. For fragments close to the projectile the measured longitudinal momentum distributions agrees qualitatively with a semi-empirical parameterization, which is based on the two-step picture of the fragmentation process. The momentum widths of lighter fragments, however, show deviations from this simple picture. (orig.)

  9. GSI Helmholz Centre for Heavy Ion Research - ALFA: Next generation concurrent framework for ALICE and FAIR experiments

    CERN Multimedia

    CERN. Geneva

    2015-01-01

    FAIR is a new, unique international accelerator facility for the research with antiprotons and ions. It is being built at the GSI Darmstadt in Hesse, Germany. The commonalities between the ALICE and FAIR experiments and their computing requirements led to the development of a common software framework in an experiment independent way; ALFA (ALICE-FAIR framework). ALFA is designed for high quality parallel data processing and reconstruction on heterogeneous computing systems. It provides a data transport layer and the capability to coordinate multiple data processing components. ALFA is a flexible, elastic system which balances reliability and ease of development with performance by using a message based multi-processing in addition to multi-threading. The framework allows for usage of heterogeneous computing architectures by offloading (portions of code are accelerated on the device) or natively (where the full program is executed on the device ).

  10. ASTRID SFR prototype steam generator design evolution related to safety and cost issues - 15236

    International Nuclear Information System (INIS)

    Woaye Hune, A.; Gerber, A.; Pirus, J.P.; Soucille, L.; Rodriguez, G.; Beauchamp, F.

    2015-01-01

    One option of the ASTRID prototype power conversion systems (PCS) is the steam cycle based on the Rankine cycle, which has been implemented in the past in France in the Phenix and Superphenix Sodium Fast Reactors, and is also being implemented in other SFRs in construction in the world (Russia, India, China). This paper is placed in the context of the Rankine cycle ameliorations and in particular on the Steam Generator (SG), developed by AREVA, from the safety point of view without significant penalty on cost. Therefore significant progresses are expected to reduce sodium/water reaction accident scenario impact as much by prevention as by mitigation. ASTRID project performed a thorough comparison of SG designs with regard to these safety requirements but also including increased sodium/water segregation (inlet and outlet of sodium implemented at the bottom of the SG), material issues and cost considerations. The design is based today on a monolithic SG with alloy 800 helical tubes but equipped with geometric specificities necessary for allowing the use of a single component per secondary loop. (authors)

  11. Mobility and safety issues in drivers with dementia.

    Science.gov (United States)

    Carr, David B; O'Neill, Desmond

    2015-10-01

    Although automobiles remain the mobility method of choice for older adults, late-life cognitive impairment and progressive dementia will eventually impair the ability to meet transport needs of many. There is, however, no commonly utilized method of assessing dementia severity in relation to driving, no consensus on the specific types of assessments that should be applied to older drivers with cognitive impairment, and no gold standard for determining driving fitness or approaching loss of mobility and subsequent counseling. Yet, clinicians are often called upon by patients, their families, health professionals, and driver licensing authorities to assess their patients' fitness-to-drive and to make recommendations about driving privileges. We summarize the literature on dementia and driving, discuss evidenced-based assessments of fitness-to-drive, and outline the important ethical and legal concerns. We address the role of physician assessment, referral to neuropsychology, functional screens, dementia severity tools, driving evaluation clinics, and driver licensing authority referrals that may assist clinicians with an evaluation. Finally, we discuss mobility counseling (e.g. exploration of transportation alternatives) since health professionals need to address this important issue for older adults who lose the ability to drive. The application of a comprehensive, interdisciplinary approach to the older driver with cognitive impairment will have the best opportunity to enhance our patients' social connectedness and quality of life, while meeting their psychological and medical needs and maintaining personal and public safety.

  12. Workplace health and safety issues among community nurses: a study regarding the impact on providing care to rural consumers.

    Science.gov (United States)

    Terry, Daniel; Lê, Quynh; Nguyen, Uyen; Hoang, Ha

    2015-08-12

    The objective of the study was to investigate the types of workplace health and safety issues rural community nurses encounter and the impact these issues have on providing care to rural consumers. The study undertook a narrative inquiry underpinned by a phenomenological approach. Community nursing staff who worked exclusively in rural areas and employed in a permanent capacity were contacted among 13 of the 16 consenting healthcare services. All community nurses who expressed a desire to participate were interviewed. Data were collected using semistructured interviews with 15 community nurses in rural and remote communities. Thematic analysis was used to analyse interview data. The role, function and structures of community nursing services varied greatly from site to site and were developed and centred on meeting the needs of individual communities. In addition, a number of workplace health and safety challenges were identified and were centred on the geographical, physical and organisational environment that community nurses work across. The workplace health and safety challenges within these environments included driving large distances between client's homes and their office which lead to working in isolation for long periods and without adequate communication. In addition, other issues included encountering, managing and developing strategies to deal with poor client and carer behaviour; working within and negotiating working environments such as the poor condition of patient homes and clients smoking; navigating animals in the workplace; vertical and horizontal violence; and issues around workload, burnout and work-related stress. Many nurses achieved good outcomes to meet the needs of rural community health consumers. Managers were vital to ensure that service objectives were met. Despite the positive outcomes, many processes were considered unsafe by community nurses. It was identified that greater training and capacity building are required to meet the

  13. NS [Nuclear Safety] update. Current safety and security activities and developments taking place in the Department of Nuclear Safety and Security, Issue no. 7, July 2008

    International Nuclear Information System (INIS)

    2008-09-01

    The current issue presents information about the following activities: 1) International Conference on Radioecology and Environmental Radioactivity 15-20 June 2008, Bergen organized by the Norwegian Radiation Protection Authority (NRPA) and the French Institute for Radiation Protection and Nuclear Safety (IRSN) in cooperation with IAEA, WHO, OECD/NEA, the International Union of Radioecology (IUR), the International Commission on Radiological Protection (ICRP) and the Journal of environmental Radioactivity (JER). This conference has evolved from the merging of the series of conferences by ECORAD and of the International Conferences on Radioactivity in the Environment. The primary objective of the conference was to review all scientific themes related to the study of environmental radioactivity and to identify new societal needs and requirements for regulatory bodies and industry. All sources of radiation, from industrial discharges in planned exposure situations through to sources in existing and emergency exposure situations, were included in the scope of the conference. 2) The Ibero American Forum of Nuclear and Radiation Safety and Security Regulatory Agencies (the FORO); 3) Kashiwazaki-Kariwa Nuclear Power Plant in the earthquake on 16 July 2007 - plant's response and effects and lessons learned

  14. Power plants and safety 1982

    International Nuclear Information System (INIS)

    1982-01-01

    The papers of this volume deal with the whole range of safety issues from planning and construction to the operation of power plants, and discuss also issues like availability and safety of power plants, protective clothes and their incommodating effect, alternatives for rendering hot-water generators safe and the safety philosophy in steam turbine engineering. (HAG) [de

  15. Reactor safety issues resolved by the 2D/3D Program

    International Nuclear Information System (INIS)

    Damerell, P.S.; Simons, J.W.

    1993-07-01

    The 2D/3D Program studied multidimensional thermal-hydraulics in a PWR core and primary system during the end-of-blowdown and post-blowdown phases of a large-break LOCA (LBLOCA), and during selected small-break LOCA (SBLOCA) transients. The program included tests at the Cylindrical Core Test Facility (CCTF), the Slab Core Test Facility (SCTF), and the Upper Plenum Test Facility (UPTF), and computer analyses using TRAC. Tests at CCTF investigated core thermal-hydraulics and overall system behavior while tests at SCTF concentrated on multidimensional core thermal-hydraulics. The UPTF tests investigated two-phase flow behavior in the downcomer, upper plenum, tie plate region, and primary loops. TRAC analyses evaluated thermal-hydraulic behavior throughout the primary system in tests as well as in PWRs. This report summarizes the test and analysis results in each of the main areas where improved information was obtained in the 2D/3D Program. The discussion is organized in terms of the reactor safety issues investigated

  16. Construction and building of a compact RFQ spiral structure for the stopping of highly charged heavy ion beams for the HITRAP project of the GSI

    International Nuclear Information System (INIS)

    Hofmann, B.

    2007-01-01

    For experiments of the atomic-physics group of the GSI in Darmstadt an ion stopper is built, which will make low-energetic, extremely highly charged ions available. The plannings for the so-called HITRAP (highly charged ion's trap) began at the beginning of the ninetieth. With this facility highly-charged heavy ions shall be stopped in two stages to very low, thermal velocities, and be available for highly precise mass spectroscopy, measurements of the g factor of the bound electron of hydrogen-like ions, and other atomic-physics experiments. This decelerator facility shall first be built in the reinjection channel behind the ESR with the possibility, to apply all components later in teh extension of the GSI in the framework of the FAIR project in the facility for low-energetic antiprotons and ions to be newly built. the present thesis treats the development and the building of an integrated RFQ debuncher stopping accelerator, which represents a part of the HITRAP stopping structures. By this the ion beam is stopped from the IH stopping accelerator with an energy of 500 keV/u to 5 keV/u. By the integrated spiral buncher the beam can be fitted in energy and energy deviation to the subsequent cooler trap. In this thesis the foundations of the particle dynamics in a RFQ accelerator for the stopping of particle beams were worked out and realized, the particle-dynamics calculations necessary for the lay-out of such a structure performed with RFQSim, suitable RF structures with the simulation program Microwave Studio developed and studied, as well as the thermal load of the structures studied with the finite-element code ALGOR. A further, central topic of this thesis is the building and the tuning of the RFQ structure in order to reach a homogeneous as possible field distribution along the electrodes. Measurements of the fields in the RFQ were performed with a disturbing condenser, at the debuncher with a disturbing body. After successfully performed vacuum tests at the

  17. 78 FR 29392 - Embedded Digital Devices in Safety-Related Systems, Systems Important to Safety, and Items Relied...

    Science.gov (United States)

    2013-05-20

    ... NUCLEAR REGULATORY COMMISSION [NRC-2013-0098] Embedded Digital Devices in Safety-Related Systems, Systems Important to Safety, and Items Relied on for Safety AGENCY: Nuclear Regulatory Commission. ACTION... (NRC) is issuing for public comment Draft Regulatory Issue Summary (RIS) 2013-XX, ``Embedded Digital...

  18. Safety measures to address the year 2000 issue at medical facilities which use radiation generators and radioactive materials

    International Nuclear Information System (INIS)

    1999-03-01

    In resolution GC(42)/RES/11 on 'Measures to Address the Year 2000 (Y2K) Issue', adopted on 25 September 1998, the General Conference of the International Atomic Energy Agency (IAEA) - inter alia - urged Member States 'to share information with the Secretariat regarding diagnostic and corrective actions being planned or implemented by operating and regulatory organizations at their ... medical facilities which use radioactive materials to make those facilities Year 2000 ready', encouraged the Secretariat 'within existing resources to act as a clearing-house and central point of contact for Member States to exchange information regarding diagnostic and remediation actions being taken at ... medical facilities which use radioactive materials to make these facilities Year 2000 ready', urged the Secretariat 'to handle the information provided by Member States carefully' and requested the Director General to report to it at its next (1999) regular session on the implementation of that resolution. The IAEA Secretariat convened a group of consultants who met in Vienna from 14 to 18 December 1998 and produced this report. The consultants decided that the report should cover not just 'medical facilities which use radioactive materials' but also medical facilities which, while perhaps not using radioactive materials, use ionizing radiation produced by radiation generators such as accelerators. The reports issued together are: Achieving Year 2000 Readiness: Basic Processes; Safety Measures to Address the Year 2000 Issue at Medical Facilities Which Use Radiation Generators and Radioactive Materials; and Safety Measures to Address the Year 2000 Issue at Radioactive Waste Management Facilities. This report addresses means of dealing with the Y2K problem at medical facilities which use radiation generators and radioactive materials

  19. Current status of environmental, health, and safety issues of electrochemical capacitors for advanced vehicle applications

    Energy Technology Data Exchange (ETDEWEB)

    Vimmerstedt, L J; Hammel, C J

    1997-04-01

    Electrochemical capacitors are a candidate for traction power assists in hybrid electric vehicles (HEVs). Other advanced automotive applications, while not the primary focus of current development efforts, are also possible. These include load leveling high-energy batteries, power conditioning electronics, electrically hated catalysts, electric power steering, and engine starter power. Higher power and longer cycle life are expected for electrochemical capacitors than for batteries. Evaluation of environmental, health, and safety (EH and S) issues of electrochemical capacitors is an essential part of the development and commercialization of electrochemical capacitors for advanced vehicles. This report provides an initial EH and S assessment. This report presents electrochemical capacitor electrochemistry, materials selection, intrinsic material hazards, mitigation of those hazards, environmental requirements, pollution control options, and shipping requirements. Most of the information available for this assessment pertains to commercial devices intended for application outside the advanced vehicle market and to experiment or prototype devices. Electrochemical capacitors for power assists in HEVs are not produced commercially now. Therefore, materials for advanced vehicle electrochemical capacitors may change, and so would the corresponding EH and S issues. Although changes are possible, this report describes issues for likely electrochemical capacitor designs.

  20. NS [Nuclear Safety] update. Current safety and security activities and developments taking place in the Department of Nuclear Safety and Security, Issue no. 9, December 2008

    International Nuclear Information System (INIS)

    2008-12-01

    The current issue presents information about the following activities: 1) IRRS Lessons Learned Workshop held on 3-5 November 2008, Seville. The main purpose of the workshop was to provide information to interested Member States regarding the IRRS, to discuss their experiences and lessons learned from the regulatory review conducted at the CSN and to explore further improvements in the planning and implementation of the IRRS, including the establishment of a network of experts from regulatory authorities. 2) Highlights of the 52 General Conference. 3) The 2008 IAEA General Conference welcomed the endorsement of the new International Nuclear and Radiological Event Scale (INES) User's Manual. 4) Safety and Security Infrastructure for Countries Embarking on Nuclear Power Programmes

  1. Evaluation of water-hammer experience in nuclear power plants. Technical findings relevant to Unresolved Safety Issue A-1

    International Nuclear Information System (INIS)

    Serkiz, A.W.

    1983-05-01

    This report summarizes key technical findings relevant to the Unresolved Safety Issue A-1, Water Hammer. These findings were derived from studies of reported water hammer occurrences and underlying causes and provide key insights into means to minimize or eliminate further water hammer occurrences. It should also be noted that this report does not represent a substitute for current rules and regulations

  2. Evaluation of water hammer occurrence in nuclear power plants: technical findings relevant to unresolved safety issue A-1

    International Nuclear Information System (INIS)

    1984-03-01

    This report, which includes responses to public comments, summarizes key technical findings relevant to the Unresolved Safety Issue A-1, Water Hammer. These findings were derived from studies of reported water hammer occurrences and underlying causes and provide key insights into means to minimize or eliminate further water hammer occurrences. This report does not represent a substitute for current rules and regulations

  3. Experimental Study and Computational Simulations of Key Pebble Bed Thermo-mechanics Issues for Design and Safety

    Energy Technology Data Exchange (ETDEWEB)

    Tokuhiro, Akira; Potirniche, Gabriel; Cogliati, Joshua; Ougouag, Abderrafi

    2014-07-08

    An experimental and computational study, consisting of modeling and simulation (M&S), of key thermal-mechanical issues affecting the design and safety of pebble-bed (PB) reactors was conducted. The objective was to broaden understanding and experimentally validate thermal-mechanic phenomena of nuclear grade graphite, specifically, spheres in frictional contact as anticipated in the bed under reactor relevant pressures and temperatures. The contact generates graphite dust particulates that can subsequently be transported into the flowing gaseous coolent. Under postulated depressurization transients and with the potential for leaked fission products to be adsorbed onto graphite 'dust', there is the potential for fission products to escape from the primary volume. This is a design safety concern. Furthermore, earlier safety assessment identified the distinct possibility for the dispersed dust to combust in contact with air if sufficient conditions are met. Both of these phenomena were noted as important to design review and containing uncertainty to warrant study. The team designed and conducted two separate effects tests to study and benchmark the potential dust-generation rate, as well as study the conditions under which a dust explosion may occure in a standardized, instrumented explosion chamber.

  4. Unresolved Safety Issue A-46 - seismic qualification of equipment in operating plants

    International Nuclear Information System (INIS)

    Anderson, N.

    1985-01-01

    Seismic Qualification of Equipment in Operating Plants was designated as an Unresolved Safety Issue (USI) in December, 1980. The USI A-46 program was developed in early 1981 to investigate the adequacy of mechanical and electrical equipment in operating plants to withstand a safe shutdown earthquake. The approach taken was to develop viable, cost effective alternatives to current seismic qualification licensing requirements which could be applied to operating nuclear power plants. The tasks investigated include: (1) identification of seismic sensitive systems and equipment; (2) assessment of adequacy of existing seismic qualification methods; (3) development and assessment of in-situ test procedures to assist in qualification of equipment; (4) seismic qualification of equipment using seismic experience data; and (5) development of methods to generate generic floor response spectra. Progress to date and plans for completion of resolution are reported

  5. Human reliability analysis for probabilistic safety assessments - review of methods and issues

    International Nuclear Information System (INIS)

    Srinivas, G.; Guptan, Rajee; Malhotra, P.K.; Ghadge, S.G.; Chandra, Umesh

    2011-01-01

    It is well known that the two major events in World Nuclear Power Plant Operating history, namely the Three Mile Island and Chernobyl, were Human failure events. Subsequent to these two events, several significant changes have been incorporated in Plant Design, Control Room Design and Operator Training to reduce the possibility of Human errors during plant transients. Still, human error contribution to Risk in Nuclear Power Plant operations has been a topic of continued attention for research, development and analysis. Probabilistic Safety Assessments attempt to capture all potential human errors with a scientifically computed failure probability, through Human Reliability Analysis. Several methods are followed by different countries to quantify the Human error probability. This paper reviews the various popular methods being followed, critically examines them with reference to their criticisms and brings out issues for future research. (author)

  6. Evolution of approaches to viral safety issues for biological products.

    Science.gov (United States)

    Lubiniecki, Anthony S

    2011-01-01

    CONFERENCE PROCEEDING Proceedings of the PDA/FDA Adventitious Viruses in Biologics: Detection and Mitigation Strategies Workshop in Bethesda, MD, USA; December 1-3, 2010 Guest Editors: Arifa Khan (Bethesda, MD), Patricia Hughes (Bethesda, MD) and Michael Wiebe (San Francisco, CA) Approaches to viral safety issues for biological products have evolved during the past 50+ years. The first cell culture products (viral vaccines) relied largely on the use of in vitro and in vivo virus screening assays that were based upon infectivity of adventitious viral agents. The use of Cohn fractionation and pasteurization by manufacturers of plasma derivatives introduced the concepts that purification and treatment with physical and chemical agents could greatly reduce the risk of viral contamination of human albumin and immunoglobulin products. But the limitations of such approaches became clear for thermolabile products that were removed early in fractionation such as antihemophilic factors, which transmitted hepatitis viruses and HIV-1 to some product recipients. These successes and limitations were taken into account by the early developers of recombinant DNA (rDNA)-derived cell culture products and by regulatory agencies, leading to the utilization of cloning technology to reduce/eliminate contamination due to human viruses and purification technologies to physically remove and inactivate adventitious and endogenous viruses, along with cell banking and cell bank characterization for adventitious and endogenous viruses, viral screening of biological raw materials, and testing of cell culture harvests, to ensure virus safety. Later development and incorporation of nanofiltration technology in the manufacturing process provided additional assurance of viral clearance for safety of biotechnology products. These measures have proven very effective at preventing iatrogenic infection of recipients of biotechnology products; however, viral contamination of production cell cultures has

  7. Environmental and safety issues of the fusion fuel cycle

    International Nuclear Information System (INIS)

    Crocker, J.G.

    1980-01-01

    This paper discusses the environmental and safety concerns inherent in the development of fusion energy, and the current Department of Energy programs seeking to: (1) develop safe and reliable techniques for tritium control; (2) reduce the quantity of activation products produced; and (3) provide designs to limit the potential for accidents that could result in release of radioactive materials. Because of the inherent safety features of fusion and the early start that has been made in safety problem recognition and solution, fusion should be among the lower risk technologies for generation of commercial power

  8. The Additional Value of an E-Mail to Inform Healthcare Professionals of a Drug Safety Issue: A Randomized Controlled Trial in the Netherlands.

    Science.gov (United States)

    Piening, Sigrid; de Graeff, Pieter A; Straus, Sabine M J M; Haaijer-Ruskamp, Flora M; Mol, Peter G M

    2013-09-01

    The usefulness and the impact of Direct Healthcare Professional Communications (DHPCs, or 'Dear Doctor letters') in changing the clinical behaviour of physicians have been debated. Changes in the current risk communication methods should preferably be based on the preferences of the healthcare professionals, to optimize the uptake of the message. The aim of this study was to assess whether safety issues are communicated more effectively with an additional e-mail sent by the Dutch Medicines Evaluation Board (MEB) than with the DHPC only. A randomized controlled trial was conducted amongst ophthalmologists and hospital pharmacists in the Netherlands, who were the target group of a DHPC that was issued for pegaptanib, a drug that is administered intra-ocularly in patients with macular degeneration. The intervention group (N = 110) received the pegaptanib DHPC, as well as the MEB e-mail. The control group (N = 105) received the traditional paper-based DHPC only. Two weeks later, the study population received an invitation to fill out an online questionnaire. Questions were asked about the respondents' knowledge and attitude regarding the pegaptanib issue, and any action they had consequently taken. Additional questions were asked about their satisfaction with the DHPC and the e-mail, and their preferred source of such information. Forty respondents (18.6%) completed the questionnaire. Eighty-one percent of the respondents in the intervention group (N = 21) and 47% of the control group (N = 19) correctly indicated that a serious increase in intra-ocular pressure could be caused by pegaptanib injections (Fishers' exact test, p = 0.046). Nine respondents in the intervention group versus none of the control group respondents indicated that they had taken action in response to the pegaptanib safety issue (Fishers' exact test, p = 0.01). The majority of both the intervention group and the control group confirmed that they would like to receive an MEB e-mail with safety

  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. Occupational Health and Safety Issues among Vegetable Farmers in Trinidad and the Implications for Extension.

    Science.gov (United States)

    Baksh, K S; Ganpat, W; Narine, L K

    2015-07-01

    Trinidad has an aged farming population. For a host of reasons, young persons are not entering the agricultural sector; therefore, these aged farmers will continue to be the backbone of the industry. Hence, there is much need for improving the health and safety of the workers within this sector. This first-time study assessed the prevalence of occupational health and safety disorders and discomforts among Trinidad's vegetable farmers in an attempt to understand the extent of the problem within the general farm population. The implications for extension are highlighted, and several recommendations are provided. Small-scale commercial-oriented vegetable farmers (n = 100) from ten of the most populated agricultural areas across Trinidad were surveyed. Results indicated that there was an overall moderate prevalence of occupational injuries among vegetable farmers. Most prevalent were musculoskeletal disorders of the lower back and upper body extremities, watery/burning eyes, skin rashes/itching, headaches, fatigue, dehydration, stress, and injuries attributed to slips and falls. Based on the evidence that a problem exists with health and safety, the extension service can now prepare and deliver programs to educate farmers on the actions necessary to improve their personal health and safety and that of their workers. This type of study has not been done before among farmers in Trinidad. It brings a very important and timely issue to the fore because of the aged farming population. Additionally, since the farmer profile and farming systems are similar in the wider Caribbean, policy makers can take note of the findings and recommendations and embrace actions.

  11. 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

  12. Regulatory aspects of oncology drug safety evaluation: Past practice, current issues, and the challenge of new drugs

    International Nuclear Information System (INIS)

    Rosenfeldt, Hans; Kropp, Timothy; Benson, Kimberly; Ricci, M. Stacey; McGuinn, W. David; Verbois, S. Leigh

    2010-01-01

    The drug development of new anti-cancer agents is streamlined in response to the urgency of bringing effective drugs to market for patients with limited life expectancy. FDA's regulation of oncology drugs has evolved from the practices set forth in Arnold Lehman's seminal work published in the 1950s through the current drafting of a new International Conference on Harmonization of Technical Requirements for Registration of Pharmaceuticals for Human Use (ICH) safety guidance for anti-cancer drug nonclinical evaluations. The ICH combines the efforts of the regulatory authorities of Europe, Japan, and the United States and the pharmaceutical industry from these three regions to streamline the scientific and technical aspects of drug development. The recent development of new oncology drug classes with novel mechanisms of action has improved survival rates for some cancers but also brings new challenges for safety evaluation. Here we present the legacy of Lehman and colleagues in the context of past and present oncology drug development practices and focus on some of the current issues at the center of an evolving harmonization process that will generate a new safety guidance for oncology drugs, ICH S9. The purpose of this new guidance will be to facilitate oncology drug development on a global scale by standardizing regional safety requirements.

  13. Survey of college students' MP3 listening: Habits, safety issues, attitudes, and education.

    Science.gov (United States)

    Hoover, Alicia; Krishnamurti, Sridhar

    2010-06-01

    To survey listening habits and attitudes of typical college students who use MP3 players and to investigate possible safety issues related to MP3 player listening. College students who were frequent MP3 player users (N = 428) filled out a 30-item online survey. Specific areas probed by the present survey included frequency and duration of MP3 player use, MP3 player volume levels used, types of earphones used, typical environments in which MP3 player was worn, specific activities related to safety while listening to MP3 players, and attitudes toward MP3 player use. The majority of listeners wore MP3 players for less than 2 hr daily at safe volume levels. About one third of respondents reported being distracted while wearing an MP3 player, and more than one third of listeners experienced soreness in their ears after a listening session. About one third of respondents reported occasionally using their MP3 players at maximum volume levels. Listeners indicated willingness to (a) reduce volume levels, (b) decrease listening duration, and (c) buy specialized earphones to conserve their hearing. The study found concerns regarding the occasional use of MP3 players at full volume and reduced environmental awareness among some college student users.

  14. Defining safety culture and the nexus between safety goals and safety culture. 4. Enhancing Safety Culture Through the Establishment of Safety Goals

    International Nuclear Information System (INIS)

    Tateiwa, Kenji; Miyata, Koichi; Yahagi, Kimitoshi

    2001-01-01

    efficient management. To seek compatibility between safety culture and efficient management, and to build an agreeable common perception among the utility, regulatory body, and the public on rationalizing the safety level to the extent acceptable, two issues must be considered: (a) establishing safety goals and (b) quantifying the safety culture. As for the first issue, currently no generic safety goal for the nuclear industry is available in Japan. This causes difficulty in deciding whether or not a specific action that takes place in a plant leading to a certain amount of risk increment is acceptable. Therefore, it is important for us to have a safety goal established. By establishing the safety goal, we could utilize it for the following usage: 1. to enable prompt response in case a safety level has entered an unacceptable level; 2. to sustain and enhance the safety culture centered by risk information (sustaining safety culture and achieving rational management simultaneously); 3. to use public relations for plant activities, where condemnation for overlooking safety culture might arrive for a minor risk increasing activity. As for the second issue, we must devise a method to quantify the level of safety culture. This could be done based on the safety culture indicators listed in the appendix of IAEA INSAG-4 (Ref. 1). By quantifying the level of safety culture, a comprehensive safety level of a plant can be evaluated by integrating with the safety level based on PSA. For example, when considering on-line maintenance for specific equipment, it is important not only to assess the safety level in terms of PSA but also to assess the level of safety culture in order to have a comprehensive view of the safety level and to compare it with the safety goal. By both establishing safety goals and quantifying the level of safety culture in a nuclear power plant, the ability to assess the comprehensive safety level of a plant and acknowledge the quantitative margin from the safety

  15. Regulatory analysis for resolution of Unresolved Safety Issue A-46, seismic qualification of equipment in operating plants

    International Nuclear Information System (INIS)

    Chang, T.Y.; Anderson, N.R.

    1987-02-01

    The margin of safety provided in existing nuclear power plant equipment to resist seismically induced loads and perform required safety functions may vary considerably, because of significant changes in design criteria and methods for the seismic qualification of equipment over the years. Therefore, the seismic qualification of equipment in operating plants must be reassessed to determine whether requalification is necessary. The objective of technical studies performed under Task Action Plan A-46 was to establish an explicit set of guidelines and acceptance criteria to judge the adequacy of equipment under seismic loading at all operating plants, in lieu of requiring these plants to meet the criteria that are applied to new plants. This report presents the regulatory analysis for Unresolved Safety Issue (USI) A-46. It includes: Statement of the Problem; the Objective of USI A-46; a Summary of A-46 Tasks; a Proposed Implementation Procedure; a Value-Impact Analysis; Application of the Backfit Rule; 10 CFR 50.109; Implementation; and Operating Plants To Be Reviewed to USI A-46 Requirements

  16. Environmental, health, and safety by design

    International Nuclear Information System (INIS)

    Soklow, R.G.

    1999-01-01

    Solar Turbines Incorporated created a self-directed work team, the Safety and Environmental Awareness (SEA) Team that initiated a company wide effort to raise employee awareness to promote integrating responsible environmental, health, and safety practices into product design, manufacturing, and services. Environmental, health, and safety issues influence how all businesses operate around the world. Companies choose to operate in an environmentally responsible manner because it not only benefits employees and the communities where they live, it also benefits the business when superior performance results in a competitive advantage. Solar surveyed gas turbines users to identify their top environmental and safety concerns and issues. The authors asked about various environmental and safety aspects of their equipment. Results from the survey has helped engineering and design focus efforts so that future products and product improvements assist customers in meeting their regulatory obligations and social responsibilities. Air pollution has historically been one of the most important environmental issues facing customers, because pollutant emissions greatly influence equipment choices and operation flexibility. There are other environmental, health and safety issues: sustainable fire suppression choices, start systems, hazardous materials use and ability to recycle materials, package accessibility, noise and product take back issues

  17. Nuclear safety regulations

    International Nuclear Information System (INIS)

    1998-01-01

    The Departmental Rules and The Safety Guides were issued by the NNSA in 1998. The NNSA performed the activities of propagation and implementation of nuclear safety regulations at QTNPP in order to improve the nuclear safety culture of operating organization and construct and contract organizations

  18. A brief overview of Ignalina NPP safety issues

    International Nuclear Information System (INIS)

    Almenas, K.; Ushpuras, E.

    1998-01-01

    A description of the safety of Ignalina NPP in a very popular form is presented. Answers to the most frequently recurring questions concerning the Ignalina NPP are provided based on recently completed international studies. Questions are like these: can a similar accident to the one that occurred in Chernobyl take place at Ignalina NPP, does the Ignalina NPP have a containment, what are the probabilities and potential consequences of accidents, etc. The brochure contains a short description of Ignalina NPP safety improvement programs

  19. Dukovany nuclear power plant safety

    International Nuclear Information System (INIS)

    1999-01-01

    Presentation covers recommended safety issues for the Dukovany NPP which have been solved with satisfactory conclusions. Safety issues concerned include: radiation safety; nuclear safety; security; emergency preparedness; health protection at work; fire protection; environmental protection; chemical safety; technical safety. Quality assurance programs at all stages on NPP life time is described. Report includes description of NPP staff training provision, training simulator, emergency operating procedures, emergency preparedness, Year 2000 problem, inspections and life time management. Description of Dukovany Plant Safety Analysis Projects including integrity of the equipment, modernisation, equipment innovation and safety upgrading program show that this approach corresponds to the actual practice applied in EU countries, and fulfilment of current IAEA requirements for safety enhancement of the WWER 440/213 units in the course of MORAWA Equipment Upgrading program

  20. A Global Perspective on Vaccine Safety and Public Health: The Global Advisory Committee on Vaccine Safety

    Science.gov (United States)

    Folb, Peter I.; Bernatowska, Ewa; Chen, Robert; Clemens, John; Dodoo, Alex N. O.; Ellenberg, Susan S.; Farrington, C. Patrick; John, T. Jacob; Lambert, Paul-Henri; MacDonald, Noni E.; Miller, Elizabeth; Salisbury, David; Schmitt, Heinz-J.; Siegrist, Claire-Anne; Wimalaratne, Omala

    2004-01-01

    Established in 1999, the Global Advisory Committee on Vaccine Safety advises the World Health Organization (WHO) on vaccine-related safety issues and enables WHO to respond promptly, efficiently, and with scientific rigor to issues of vaccine safety with potential global importance. The committee also assesses the implications of vaccine safety for practice worldwide and for WHO policies. We describe the principles on which the committee was established, its modus operandi, and the scope of the work undertaken, both present and future. We highlight its recent recommendations on major issues, including the purported link between the measles–mumps–rubella vaccine and autism and the safety of the mumps, influenza, yellow fever, BCG, and smallpox vaccines as well as that of thiomersal-containing vaccines. PMID:15514229