WorldWideScience

Sample records for preliminary safety information

  1. Preliminary safety information document for the standard MHTGR. Volume 4

    Energy Technology Data Exchange (ETDEWEB)

    None

    1986-01-01

    This report contains information concerning: operational radionuclide control; occupational radiation protection, conduct of operations; initial test program; safety analysis; technical specifications; and quality assurance. (JDB)

  2. Preliminary Safety Information Document for the Standard MHTGR. Volume 1, (includes latest Amendments)

    Energy Technology Data Exchange (ETDEWEB)

    None

    1986-01-01

    With NRC concurrence, the Licensing Plan for the Standard HTGR describes an application program consistent with 10CFR50, Appendix O to support a US Nuclear Regulatory Commission (NRC) review and design certification of an advanced Standard modular High Temperature Gas-Cooled Reactor (MHTGR) design. Consistent with the NRC's Advanced Reactor Policy, the Plan also outlines a series of preapplication activities which have as an objective the early issuance of an NRC Licensability Statement on the Standard MHTGR conceptual design. This Preliminary Safety Information Document (PSID) has been prepared as one of the submittals to the NRC by the US Department of Energy in support of preapplication activities on the Standard MHTGR. Other submittals to be provided include a Probabilistic Risk Assessment, a Regulatory Technology Development Plan, and an Emergency Planning Bases Report.

  3. Liquid-metal fast-breeder reactors: Preliminary safety and environmental information document. Volume VI

    International Nuclear Information System (INIS)

    1980-01-01

    Information is presented concerning LMFBR design characteristics; uranium-plutonium/uranium recycle homogeneous core; uranium-plutonium/uranium spiked recycle heterogeneous core; uranium-plutonium/uranium spiked recycle homogeneous core; uranium-plutonium/thorium spiked recycle heterogeneous core; uranium-plutonium/thorium spiked recycle homogeneous core; thorium-plutonium/thorium spiked recycle homogeneous core; denatured uranium-233/thorium cycle homogeneous core; safety consideration for the LMFBR; and environmental considerations

  4. Fuel-cycle facilities: preliminary safety and environmental information document. Volume VII

    Energy Technology Data Exchange (ETDEWEB)

    1980-01-01

    Information is presented concerning the mining and milling of uranium and thorium; uranium hexafluoride conversion; enrichment; fuel fabrication; reprocessing; storage options; waste disposal options; transportation; heavy-water-production facilities; and international fuel service centers.

  5. Fuel-cycle facilities: preliminary safety and environmental information document. Volume VII

    International Nuclear Information System (INIS)

    1980-01-01

    Information is presented concerning the mining and milling of uranium and thorium; uranium hexafluoride conversion; enrichment; fuel fabrication; reprocessing; storage options; waste disposal options; transportation; heavy-water-production facilities; and international fuel service centers

  6. Licensing assessment of the CANDU pressurized heavy water reactor. Volume I. Preliminary safety information document

    International Nuclear Information System (INIS)

    1977-06-01

    The PHWR design contains certain features that will require significant modifications to comply with USNRC siting and safety requirements. The most significant of these features are the reactor vessel; control systems; quality assurance program requirements; seismic design of structures, systems and components; and providing an inservice inspection program capability. None of these areas appear insolvable with current state-of-the-art engineering or with upgrading of the quality assurance program for components constructed outside of the USA. In order to be licensed in the U. S., the entire reactor assembly would have to be redesigned to comply with ASME Boiler and Pressure Vessel Code, Section III, Division 1 and Division 2. A summary matrix at the end of this volume identifies compliance of the systems and structures of the PHWR plant with the USNRC General Design Criteria. The matrix further identifies the estimated incremental cost to a 600 MWe PHWR that would be required to license the plant in the U. S. Further, the matrix identifies whether or not the incremental licensing cost is size dependent and the relative percentage of the base direct cost of a Canadian sited plant

  7. Light-water reactors: preliminary safety and environmental information document. Volume I

    International Nuclear Information System (INIS)

    1980-01-01

    Information is presented concerning the reference PWR reactor system; once-through, low-enrichment uranium-235 fuel, 30 MWD per kilogram (PWR LEU(5)-OT); once-through, low-enrichment, high-burnup uranium fuel (PWR LEU(5)-Mod OT); self-generated plutonium spiked recycle (PWR LEU(5)-Pu-Spiked Recycle); denatured uranium-233/thorium cycle (PWR DU(3)-Th Recycle DU(3)); and plutonium/thorium cycle

  8. Animal Product Safety Information

    Science.gov (United States)

    ... Home Animal & Veterinary Safety & Health Product Safety Information Product Safety Information Share Tweet Linkedin Pin it More ... to report adverse experiences with veterinary drugs. Additional Product Information Questions and Answers: Evanger’s Dog and Cat ...

  9. Flu Vaccine Safety Information

    Science.gov (United States)

    ... Influenza Types Seasonal Avian Swine Variant Pandemic Other Flu Vaccine Safety Information Questions & Answers Language: English (US) ... safety of flu vaccines monitored? Egg Allergy Are flu vaccines safe? Flu vaccines have good safety record. ...

  10. Preliminary safety evaluation for CSR1000 with passive safety system

    International Nuclear Information System (INIS)

    Wu, Pan; Gou, Junli; Shan, Jianqiang; Zhang, Bo; Li, Xiang

    2014-01-01

    Highlights: • The basic information of a Chinese SCWR concept CSR1000 is introduced. • An innovative passive safety system is proposed for CSR1000. • 6 Transients and 3 accidents are analysed with system code SCTRAN. • The passive safety systems greatly mitigate the consequences of these incidents. • The inherent safety of CSR1000 is enhanced. - Abstract: This paper describes the preliminary safety analysis of the Chinese Supercritical water cooled Reactor (CSR1000), which is proposed by Nuclear Power Institute of China (NPIC). The two-pass core design applied to CSR1000 decreases the fuel cladding temperature and flattens the power distribution of the core at normal operation condition. Each fuel assembly is made up of four sub-assemblies with downward-flow water rods, which is favorable to the core cooling during abnormal conditions due to the large water inventory of the water rods. Additionally, a passive safety system is proposed for CSR1000 to increase the safety reliability at abnormal conditions. In this paper, accidents of “pump seizure”, “loss of coolant flow accidents (LOFA)”, “core depressurization”, as well as some typical transients are analysed with code SCTRAN, which is a one-dimensional safety analysis code for SCWRs. The results indicate that the maximum cladding surface temperatures (MCST), which is the most important safety criterion, of the both passes in the mentioned incidents are all below the safety criterion by a large margin. The sensitivity analyses of the delay time of RCPs trip in “loss of offsite power” and the delay time of RMT actuation in “loss of coolant flowrate” were also included in this paper. The analyses have shown that the core design of CSR1000 is feasible and the proposed passive safety system is capable of mitigating the consequences of the selected abnormalities

  11. Preliminary report of radiological safety to hydrology 1993 campaign; Informe preliminar de seguridad radiologica para la campana de hidrologia 1993

    Energy Technology Data Exchange (ETDEWEB)

    Badano, A; Suarez Antola, R; Dellepere, A; Barreiro, M [MIEM, Direccion Nacional de Tecnologia Nuclear, Montevideo (Uruguay)

    1993-07-01

    This report has been prepared based on the interaction between project managers and division radiological Protection and Nuclear Safety. In seeking to establish a basis for approval from the point of view of radiation safety practices . The idea for the audit has been provided at all times because the interest was the exchange of ideas and the use of common sense to improve the safety of radioactive substances, security of operators and public safety and environment.The above shows that in the planned radiation safety condition described in this report,the practice can be carried out according to the criteria of safety accepted .

  12. Preliminary safety analysis methodology for the SMART

    Energy Technology Data Exchange (ETDEWEB)

    Bae, Kyoo Hwan; Chung, Y. J.; Kim, H. C.; Sim, S. K.; Lee, W. J.; Chung, B. D.; Song, J. H. [Korea Atomic Energy Research Institute, Taejeon (Korea)

    2000-03-01

    This technical report was prepared for a preliminary safety analysis methodology of the 330MWt SMART (System-integrated Modular Advanced ReacTor) which has been developed by Korea Atomic Energy Research Institute (KAERI) and funded by the Ministry of Science and Technology (MOST) since July 1996. This preliminary safety analysis methodology has been used to identify an envelope for the safety of the SMART conceptual design. As the SMART design evolves, further validated final safety analysis methodology will be developed. Current licensing safety analysis methodology of the Westinghouse and KSNPP PWRs operating and under development in Korea as well as the Russian licensing safety analysis methodology for the integral reactors have been reviewed and compared to develop the preliminary SMART safety analysis methodology. SMART design characteristics and safety systems have been reviewed against licensing practices of the PWRs operating or KNGR (Korean Next Generation Reactor) under construction in Korea. Detailed safety analysis methodology has been developed for the potential SMART limiting events of main steam line break, main feedwater pipe break, loss of reactor coolant flow, CEA withdrawal, primary to secondary pipe break and the small break loss of coolant accident. SMART preliminary safety analysis methodology will be further developed and validated in parallel with the safety analysis codes as the SMART design further evolves. Validated safety analysis methodology will be submitted to MOST as a Topical Report for a review of the SMART licensing safety analysis methodology. Thus, it is recommended for the nuclear regulatory authority to establish regulatory guides and criteria for the integral reactor. 22 refs., 18 figs., 16 tabs. (Author)

  13. Safety performance of preliminary KALIMER conceptual design

    Energy Technology Data Exchange (ETDEWEB)

    Hahn Dohee; Kim Kyoungdoo; Kwon Youngmin; Chang Wonpyo; Suk Soodong [Korea atomic Energy Resarch Inst., Taejon (Korea)

    1999-07-01

    The Korea Atomic Energy Research Institute (KAERI) is developing KALIMER (Korea Advanced Liquid Metal Reactor), which is a sodium cooled, 150 MWe pool-type reactor. The safety design of KALIMER emphasizes accident prevention by using passive processes, which can be accomplished by the safety design objectives including the utilization of inherent safety features. In order to assess the effectiveness of the inherent safety features in achieving the safety design objectives, a preliminary evaluation of ATWS performance for the KALIMER design has been performed with SSC-K code, which is a modified version of SSC-L code. KAERI's modification of the code includes development of reactivity feedback models for the core and a pool model for KALIMER reactor vessel. This paper describes the models for control rod driveline expansion, gas expansion module and the thermal hydraulic model for reactor pool and the results of preliminary analyses for unprotected loss of flow and loss o heat sink. (author)

  14. Safety performance of preliminary KALIMER conceptual design

    International Nuclear Information System (INIS)

    Hahn Dohee; Kim Kyoungdoo; Kwon Youngmin; Chang Wonpyo; Suk Soodong

    1999-01-01

    The Korea Atomic Energy Research Institute (KAERI) is developing KALIMER (Korea Advanced Liquid Metal Reactor), which is a sodium cooled, 150 MWe pool-type reactor. The safety design of KALIMER emphasizes accident prevention by using passive processes, which can be accomplished by the safety design objectives including the utilization of inherent safety features. In order to assess the effectiveness of the inherent safety features in achieving the safety design objectives, a preliminary evaluation of ATWS performance for the KALIMER design has been performed with SSC-K code, which is a modified version of SSC-L code. KAERI's modification of the code includes development of reactivity feedback models for the core and a pool model for KALIMER reactor vessel. This paper describes the models for control rod driveline expansion, gas expansion module and the thermal hydraulic model for reactor pool and the results of preliminary analyses for unprotected loss of flow and loss o heat sink. (author)

  15. State Traffic Safety Information

    Data.gov (United States)

    Department of Transportation — The State Traffic Safety Information (STSI) portal is part of the larger Fatality Analysis Reporting System (FARS) Encyclopedia. STSI provides state-by-state traffic...

  16. Preliminary safety assessment of the WIPP facility

    International Nuclear Information System (INIS)

    Balestri, R.J.; Torres, B.W.; Pahwa, S.B.; Brannen, J.P.

    1979-01-01

    This paper summarizes the efforts to perform a safety assessment of the Waste Isolation Pilot Plant (WIPP) facility being proposed for southeastern New Mexico. This preliminary safety assessment is limited to a consequence assessment in terms of the dose to a maximally exposed individual as a result of introducing the radionuclides into the biosphere. The extremely low doses to the organs as a result of the liquid breach scenarios are contrasted with the background radiation

  17. Preliminary safety analysis report for the TFTR

    International Nuclear Information System (INIS)

    Lind, K.E.; Levine, J.D.; Howe, H.J.

    A Preliminary Safety Analysis Report has been prepared for the Tokamak Fusion Test Reactor. No accident scenarios have been identified which would result in exposures to on-site personnel or the general public in excess of the guidelines defined for the project by DOE

  18. Safety Information System Guide

    International Nuclear Information System (INIS)

    Bullock, M.G.

    1977-03-01

    This Guide provides guidelines for the design and evaluation of a working safety information system. For the relatively few safety professionals who have already adopted computer-based programs, this Guide may aid them in the evaluation of their present system. To those who intend to develop an information system, it will, hopefully, inspire new thinking and encourage steps towards systems safety management. For the line manager who is working where the action is, this Guide may provide insight on the importance of accident facts as a tool for moving ideas up the communication ladder where they will be heard and acted upon; where what he has to say will influence beneficial changes among those who plan and control his operations. In the design of a safety information system, it is suggested that the safety manager make friends with a computer expert or someone on the management team who has some feeling for, and understanding of, the art of information storage and retrieval as a new and better means for communication

  19. Gas-Cooled Fast Breeder Reactor Preliminary Safety Information Document, Amendment 10. GCFR residual heat removal system criteria, design, and performance

    International Nuclear Information System (INIS)

    1980-01-01

    This report presents a comprehensive set of safety design bases to support the conceptual design of the gas-cooled fast breeder reactor (GCFR) residual heat removal (RHR) systems. The report is structured to enable the Nuclear Regulatory Commission (NRC) to review and comment in the licensability of these design bases. This report also presents information concerning a specific plant design and its performance as an auxiliary part to assist the NRC in evaluating the safety design bases

  20. Preliminary safety design analysis of KALIMER

    Energy Technology Data Exchange (ETDEWEB)

    Suk, Soo Dong; Kwon, Y. M.; Kim, K. D. [Korea Atomic Energy Research Institute, Taejon (Korea)

    1999-03-01

    The national long-term R and D program updated in 1997 requires Korea Atomic Energy Research Institute(KAERI) to complete by the year 2006 the basic design of Korea Advanced Liquid Metal Reactor (KALIMER), along with supporting R and D work, with the capability of resolving the issue of spent fuel storage as well as with significantly enhanced safety. KALIMER is a 150 MWe pool-type sodium cooled prototype reactor that uses metallic fuel. The conceptual design is currently under way to establish a self consistent design meeting a set of the major safety design requirements for accident prevention. Some of current emphasis include those for inherent and passive means of negative reactivity insertion and decay heat removal, high shutdown reliability, prevention of and protection from sodium chemical reaction, and high seismic margin, among others. All of these requirements affect the reactor design significantly and involve supporting R and D programs of substance. This document first introduces a set of safety design requirements and accident evaluation criteria established for the conceptual design of KALIMER and then summarizes some of the preliminary results of engineering and design analyses performed for the safety of KALIMER. 19 refs., 19 figs., 6 tabs. (Author)

  1. Preliminary safety analysis of the Gorleben site

    International Nuclear Information System (INIS)

    Bracke, G.; Fischer-Appelt, K.

    2014-01-01

    The safety requirements governing the final disposal of heat-generating radioactive waste in Germany were implemented by the Federal Ministry of Environment, Natural Conservation and Nuclear Safety (BMU) in 2010. The Ministry considers as a fundamental objective the protection of man and the environment against the hazards of radioactive waste. Unreasonable burdens and obligation for future generations shall be avoided. The main safety principles are concentration and inclusion of radioactive and other pollutants in a containment-providing rock zone. Any release of radioactive nuclides may increase the risk for men and the environment only negligibly compared to natural radiation exposure. No intervention or maintenance work shall be necessary in the post-closure phase. Retrieval/recovery of the waste shall be possible up to 500 years after closure. The Gorleben salt dome has been discussed since the 1970's as a possible repository site for heat-generating radioactive waste in Germany. The objective of the project preliminary safety analysis of the Gorleben site (VSG) was to assess if repository concepts at the Gorleben site or other sites with a comparable geology could comply with these requirements based on currently available knowledge (Fischer-Appelt, 2013; Bracke, 2013). In addition to this it was assessed if methodological approaches can be used for a future site selection procedure and which technological and conceptual considerations can be transferred to other geological situations. The objective included the compilation and review of the available exploration data of the Gorleben site and on disposal in salt rock, the development of repository designs, and the identification of the needs for future R and D work and further site investigations. (authors)

  2. Aviation Safety Hotline Information System -

    Data.gov (United States)

    Department of Transportation — The Aviation Safety Hotline Information System (ASHIS) collects, stores, and retrieves reports submitted by pilots, mechanics, cabin crew, passengers, or the public...

  3. Preliminary safety assessment and preliminary safety report for the treated radwaste store, Winfrith

    International Nuclear Information System (INIS)

    Staples, A.T.

    1992-06-01

    It is the purpose of this assessment to define the categorisation of the Treated Radwaste Store, TRS, B55 at the Winfrith Technology Centre. Its further purpose is to cover all relevant sections required for a Preliminary Safety Report (PSR) encompassing the TRS and the integral Quality Assessment Unit (QUA). The TRS is designed for the interim storage of intermediate level radioactive wastes. All waste material stored in the TRS will be contained within 500 litre stainless steel drums acceptable to NIREX. It is proposed that the TRS will receive 500 litre stainless steel NIREX drums containing either irradiated DRAGON fuel or encapsulated sludge waste. (author)

  4. Preliminary study on improving safety culture in Malaysian nuclear industries

    International Nuclear Information System (INIS)

    Ibrahim, Sabariah Kader; Lee, Y. E.

    2012-01-01

    This paper presents preliminary study on safety culture and its implementation in Malaysian nuclear industries by realizing the importance of safety culture; identification of important safety culture attributes; safety culture assessment and the practices to incorporate the identified safety culture attributes in organization. The first section of this paper explains the terms and definitions related to safety culture. Second, for the realization of importance of safety culture in organization, the international operational experiences emphasizing the importance of safety culture are described. Third, important safety culture attributes which are frequently cited in literature are provided. Fourth, methods to assess safety culture in operating organization are described. Finally, the practices to enhance the safety culture in an organization are discussed

  5. Preliminary study on improving safety culture in Malaysian nuclear industries

    Energy Technology Data Exchange (ETDEWEB)

    Ibrahim, Sabariah Kader [KAIST, Daejeon (Korea, Republic of); Lee, Y. E. [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

    2012-10-15

    This paper presents preliminary study on safety culture and its implementation in Malaysian nuclear industries by realizing the importance of safety culture; identification of important safety culture attributes; safety culture assessment and the practices to incorporate the identified safety culture attributes in organization. The first section of this paper explains the terms and definitions related to safety culture. Second, for the realization of importance of safety culture in organization, the international operational experiences emphasizing the importance of safety culture are described. Third, important safety culture attributes which are frequently cited in literature are provided. Fourth, methods to assess safety culture in operating organization are described. Finally, the practices to enhance the safety culture in an organization are discussed.

  6. INFORMATION CULTURE AND INFORMATION SAFETY OF SCHOOLCHILDREN

    Directory of Open Access Journals (Sweden)

    E. G. Belyakova

    2017-01-01

    Full Text Available Introduction. The article is devoted to the problem of interaction between schoolchildren and possible informational risks transmitted on the Internet. Considering the lack of external filters on the way of harmful information streams, it is actually necessary to develop information culture of schoolchildren, their abilities to sensibly and critically interpret the information on the Internet, and choice of adequate behaviour models surfing the Web. The aim of the present research is to analyze the state of informational safety of schoolchildren while using the Internet; gaining an understanding of the role of external restrictions and opportunities of intrapersonal filtration of the harmful Internet content depending on children age. Methodology and research methods. The methodology of the research is based on modern methods aimed to consider the problem of personal socialization in modern information society. Thus, the Internet Initiatives Development Fund (IIDF questionnaire let the authors define the level of awareness of recipients on the problem under consideration. Results and scientific novelty. The theoretical analysis helped the authors predict the correlation of basic methods in order to guarantee personal safety of schoolchildren taking into account the process of maturity as well as the decrease of external filters that may stop harmful content. Empirical part of the research has enabled to reveal decrease in external control of staying of a child in network in the process of growing up against the background of restrictive attitudes prevalence among teachers and parents. Therefore, the research supposed to improve information culture of schoolchildren from the earliest ages encouraging them to sensibly and correctly interpret the information on the Internet. Practical significance. The practical recommendations to parents and teachers in order to improve informational personal safety of schoolchildren are proposed. The relevancy

  7. Preliminary Integrated Safety Analysis Status Report

    International Nuclear Information System (INIS)

    Gwyn, D.

    2001-01-01

    This report provides the status of the potential Monitored Geologic Repository (MGR) Integrated Safety Analysis (EA) by identifying the initial work scope scheduled for completion during the ISA development period, the schedules associated with the tasks identified, safety analysis issues encountered, and a summary of accomplishments during the reporting period. This status covers the period from October 1, 2000 through March 30, 2001

  8. Preliminary Safety Analysis Report for the Tokamak Physics Experiment

    International Nuclear Information System (INIS)

    Motloch, C.G.; Bonney, R.F.; Levine, J.D.; Masson, L.S.; Commander, J.C.

    1995-04-01

    This Preliminary Safety Analysis Report (PSAR), includes an indication of the magnitude of facility hazards, complexity of facility operations, and the stage of the facility life-cycle. It presents the results of safety analyses, safety assurance programs, identified vulnerabilities, compensatory measures, and, in general, the rationale describing why the Tokamak Physics Experiment (TPX) can be safely operated. It discusses application of the graded approach to the TPX safety analysis, including the basis for using Department of Energy (DOE) Order 5480.23 and DOE-STD-3009-94 in the development of the PSAR

  9. Radiation safety research information database

    International Nuclear Information System (INIS)

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

    2004-01-01

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

  10. Conversion Preliminary Safety Analysis Report for the NIST Research Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Diamond, D. J. [Brookhaven National Lab. (BNL), Upton, NY (United States); Baek, J. S. [Brookhaven National Lab. (BNL), Upton, NY (United States); Hanson, A. L. [Brookhaven National Lab. (BNL), Upton, NY (United States); Cheng, L-Y [Brookhaven National Lab. (BNL), Upton, NY (United States); Brown, N. [Brookhaven National Lab. (BNL), Upton, NY (United States); Cuadra, A. [Brookhaven National Lab. (BNL), Upton, NY (United States)

    2015-01-30

    The NIST Center for Neutron Research (NCNR) is a reactor-laboratory complex providing the National Institute of Standards and Technology (NIST) and the nation with a world-class facility for the performance of neutron-based research. The heart of this facility is the NIST research reactor (aka NBSR); a heavy water moderated and cooled reactor operating at 20 MW. It is fueled with high-enriched uranium (HEU) fuel elements. A Global Threat Reduction Initiative (GTRI) program is underway to convert the reactor to low-enriched uranium (LEU) fuel. This program includes the qualification of the proposed fuel, uranium and molybdenum alloy foil clad in an aluminum alloy, and the development of the fabrication techniques. This report is a preliminary version of the Safety Analysis Report (SAR) that would be submitted to the U.S. Nuclear Regulatory Commission (NRC) for approval prior to conversion. The report follows the recommended format and content from the NRC codified in NUREG-1537, “Guidelines for Preparing and Reviewing Applications for the Licensing of Non-power Reactors,” Chapter 18, “Highly Enriched to Low-Enriched Uranium Conversions.” The emphasis in any conversion SAR is to explain the differences between the LEU and HEU cores and to show the acceptability of the new design; there is no need to repeat information regarding the current reactor that will not change upon conversion. Hence, as seen in the report, the bulk of the SAR is devoted to Chapter 4, Reactor Description, and Chapter 13, Safety Analysis.

  11. Review of SFR Design Safety using Preliminary Regulatory PSA Model

    International Nuclear Information System (INIS)

    Na, Hyun Ju; Lee, Yong Suk; Shin, Andong; Suh, Nam Duk

    2013-01-01

    The major objective of this research is to develop a risk model for regulatory verification of the SFR design, and thereby, make sure that the SFR design is adequate from a risk perspective. In this paper, the development result of preliminary regulatory PSA model of SFR is discussed. In this paper, development and quantification result of preliminary regulatory PSA model of SFR is discussed. It was confirmed that the importance PDRC and ADRC dampers is significant as stated in the result of KAERI PSA model. However, the importance can be changed significantly depending on assumption of CCCG and CCF factor of PDRC and ADRC dampers. SFR (sodium-cooled fast reactor) which is Gen-IV nuclear energy system, is designed to accord with the concept of stability, sustainability and proliferation resistance. KALIMER-600, which is under development in Korea, includes passive safety systems (e. g. passive reactor shutdown, passive residual heat removal, and etc.) as well as active safety systems. Risk analysis from a regulatory perspective is needed to support the regulatory body in its safety and licensing review for SFR (KALIMER-600). Safety issues should be identified in the early design phase in order to prevent the unexpected cost increase and delay of the SFR licensing schedule that may be caused otherwise

  12. The Commodity Form of Safety Information

    Directory of Open Access Journals (Sweden)

    Rodrigo Finkelstein

    2015-10-01

    Full Text Available The production of safety information is deemed a vital resource to protect human lives at the work site. The injury rate, lost days, incapacity rate, and fatality rate, are key indicators to prop up labour risk awareness and identify job hazards. However, safety information gets highly distorted because it does not only measure risk but serves as a means of exchange. It determines the amount of money to be swapped between Workers’ Compensation Boards and their client corporations. Moreover, as a depository of exchange value, safety information tends to exert pressure over social reality rather than just being a passive reflection of it. This paper discloses the commodity form of safety information. Based on a political economy of information framework, it identifies, describes, and analyses the safety information commodity in its active role of organizing safety and labour health.

  13. Pesticide Health and Safety Information

    Science.gov (United States)

    Animal Health Safe Use Practices Pest Control Food Safety Low Risk Pesticides Integrated Pest Management directed by the product label. Pesticides may be ingested if stored improperly in food or beverage ; Environment Human Health Animal Health Safe Use Practices Food Safety Environment Air Water Soil Wildlife

  14. Response to Absorber-Focus Coil Preliminary Safety Review Panel

    International Nuclear Information System (INIS)

    Barr, Giles; Baynham, Elwyn; Black, Edgar; Bradshaw, Tom; Cummings, Mary Anne; Green, Michael A.; Ishimoto, Shigeru; Ivanyushenkov, Yury; Lau, Wing; Zisman, Michael S.

    2004-01-01

    In this document we provide responses to the various issues raised in the report of the Preliminary Safety Review Panel (see http://mice.iit.edu/mnp/MICE0069.pdf). In some cases we have made design changes in response to the Panels suggestions. In other cases, we have chosen not to do so. In a few cases, we indicate our plans, although the tasks have not yet been completed. For simplicity, the responses are organized along the same lines as those of the Panel Report

  15. Reactor operation safety information document

    Energy Technology Data Exchange (ETDEWEB)

    1990-01-01

    The report contains a reactor facility description which includes K, P, and L reactor sites, structures, operating systems, engineered safety systems, support systems, and process and effluent monitoring systems; an accident analysis section which includes cooling system anomalies, radioactive materials releases, and anticipated transients without scram; a summary of onsite doses from design basis accidents; severe accident analysis (reactor core disruption); a description of operating contractor organization and emergency planning; and a summary of reactor safety evolution. (MB)

  16. 1972 preliminary safety analysis report based on a conceptual design of a proposed repository in Kansas

    International Nuclear Information System (INIS)

    Blomeke, J.O.

    1977-08-01

    This preliminary safety analysis report is based on a proposed Federal Repository at Lyons, Kansas, for receiving, handling, and depositing radioactive solid wastes in bedded salt during the remainder of this century. The safety analysis applies to a hypothetical site in central Kansas identical to the Lyons site, except that it is free of nearby salt solution-mining operations and bore holes that cannot be plugged to Repository specifications. This PSAR contains much information that also appears in the conceptual design report. Much of the geological-hydrological information was gathered in the Lyons area. This report is organized in 16 sections: considerations leading to the proposed Repository, design requirements and criteria, a description of the Lyons site and its environs, land improvements, support facilities, utilities, different impacts of Repository operations, safety analysis, design confirmation program, operational management, requirements for eventually decommissioning the facility, design criteria for protection from severe natural events, and the proposed program of experimental investigations

  17. 1972 preliminary safety analysis report based on a conceptual design of a proposed repository in Kansas

    Energy Technology Data Exchange (ETDEWEB)

    Blomeke, J.O.

    1977-08-01

    This preliminary safety analysis report is based on a proposed Federal Repository at Lyons, Kansas, for receiving, handling, and depositing radioactive solid wastes in bedded salt during the remainder of this century. The safety analysis applies to a hypothetical site in central Kansas identical to the Lyons site, except that it is free of nearby salt solution-mining operations and bore holes that cannot be plugged to Repository specifications. This PSAR contains much information that also appears in the conceptual design report. Much of the geological-hydrological information was gathered in the Lyons area. This report is organized in 16 sections: considerations leading to the proposed Repository, design requirements and criteria, a description of the Lyons site and its environs, land improvements, support facilities, utilities, different impacts of Repository operations, safety analysis, design confirmation program, operational management, requirements for eventually decommissioning the facility, design criteria for protection from severe natural events, and the proposed program of experimental investigations. (DLC)

  18. Safety campaigns. TIS Launches New Safety Information Campaign

    CERN Multimedia

    2001-01-01

    Need to start a new installation and worried about safety aspects? Or are you newly responsible for safety matters in a CERN building? Perhaps you're simply interested in how to make the working environment safer for yourself and your colleagues. Whatever the case, a new information campaign launched by TIS this week can help. The most visible aspects of the new campaign will be posters distributed around the Laboratory treating a different subject each month. The Web site - http://safety.cern.ch/ - which provides all safety related information. But these are not the only aspects of the new campaign. Members of the TIS/GS group, whose contact details can be found on the safety web site, are available to give information and advice on a one-to-one basis at any time. The campaign's launch has been timed to coincide with European Safety Week, organized by the European Agency for Safety and Health at Work and the subject treated in the first posters is safety inspection. This particular topic only concerns thos...

  19. Preliminary safety evaluation for the plutonium stabilization and packaging system

    International Nuclear Information System (INIS)

    Shapley, J.E.

    1997-01-01

    This Preliminary Safety Evaluation (PSE) describes and analyzes the installation and operation of the Plutonium Stabilization and Packaging System (SPS) at the Plutonium Finishing Plant (PFP). The SPS is a combination of components required to expedite the safe and timely storage of Plutonium (Pu) oxide. The SPS program will receive site Pu packages, process the Pu for storage, package the Pu into metallic containers, and safely store the containers in a specially modified storage vault. The location of the SPS will be in the 2736- ZB building and the storage vaults will be in the 2736-Z building of the PFP, as shown in Figure 1-1. The SPS will produce storage canisters that are larger than those currently used for Pu storage at the PFP. Therefore, the existing storage areas within the PFP secure vaults will require modification. Other modifications will be performed on the 2736-ZB building complex to facilitate the installation and operation of the SPS

  20. 40 CFR 68.48 - Safety information.

    Science.gov (United States)

    2010-07-01

    ...) CHEMICAL ACCIDENT PREVENTION PROVISIONS Program 2 Prevention Program § 68.48 Safety information. (a) The... regulated substances, processes, and equipment: (1) Material Safety Data Sheets that meet the requirements...) Equipment specifications; and (5) Codes and standards used to design, build, and operate the process. (b...

  1. Managing knowledge and information on nuclear safety

    International Nuclear Information System (INIS)

    Hahn, L.

    2005-01-01

    Described is the management of nuclear safety knowledge through education networks, knowledge pool, sharing, archiving and distributing the knowledge information. Demonstrated is the system used at Gesellschaft fuer Anlagen-und Reaktorsicherheit

  2. Functional safety of health information technology.

    LENUS (Irish Health Repository)

    Chadwick, Liam

    2012-03-01

    In an effort to improve patient safety and reduce adverse events, there has been a rapid growth in the utilisation of health information technology (HIT). However, little work has examined the safety of the HIT systems themselves, the methods used in their development or the potential errors they may introduce into existing systems. This article introduces the conventional safety-related systems development standard IEC 61508 to the medical domain. It is proposed that the techniques used in conventional safety-related systems development should be utilised by regulation bodies, healthcare organisations and HIT developers to provide an assurance of safety for HIT systems. In adopting the IEC 61508 methodology for HIT development and integration, inherent problems in the new systems can be identified and corrected during their development. Also, IEC 61508 should be used to develop a healthcare-specific standard to allow stakeholders to provide an assurance of a system\\'s safety.

  3. International exchange of safety and licensing information

    International Nuclear Information System (INIS)

    Lafleur, J.D. Jr.; Hauber, R.D.; Chenier, D.M.

    1977-01-01

    A network of formal and informal bilateral arrangements for the exchange of nuclear safety information is being established by the US Nuclear Regulatory Commission. For developing countries such arrangements can provide ready access to the extensive, fully documented safety analyses and safety research results that USNRC has accumulated. USNRC has been receiving foreign visitors at a rate of about 500 per year, largely for discussions of safety and licensing questions related to light water reactors. Exchanges also are taking place on the safety of advanced reactors. A special interest of the USNRC is in providing for reciprocal communication, at the earliest possible time, of important problems, decisions and other actions on nuclear safety matters. For example, it is essential that a newly discovered problem in a nuclear reactor be brought immediately to the attention of other governments that are responsible for the safety of similar reactors. Definite progress has been made in the USA in defining categories of information that USNRC can receive in confidence from foreign countries, and can protect from disclosure under the US Freedom of Information Act. Certain exchanges have taken place on this basis. Experience in the establishment and operation of USNRC's bilateral exchange arrangements is summarized. A typical exchange with the regulatory authority of a country building its first power reactor is described. (author)

  4. Implementing national nuclear safety plan at the preliminary stage of nuclear power project development

    International Nuclear Information System (INIS)

    Xue Yabin; Cui Shaozhang; Pan Fengguo; Zhang Lizhen; Shi Yonggang

    2014-01-01

    This study discusses the importance of nuclear power project design and engineering methods at the preliminary stage of its development on nuclear power plant's operational safety from the professional view. Specifically, we share our understanding of national nuclear safety plan's requirement on new reactor accident probability, technology, site selection, as well as building and improving nuclear safety culture and strengthening public participation, with a focus on plan's implications on preliminary stage of nuclear power project development. Last, we introduce China Huaneng Group's work on nuclear power project preliminary development and the experience accumulated during the process. By analyzing the siting philosophy of nuclear power plant and the necessity of building nuclear safety culture at the preliminary stage of nuclear power project development, this study explicates how to fully implement the nuclear safety plan's requirements at the preliminary stage of nuclear power project development. (authors)

  5. Preliminary safety analysis of molten salt breeder reactor

    International Nuclear Information System (INIS)

    Cheng Maosong; Dai Zhimin

    2013-01-01

    Background: The molten salt reactor is one of the six advanced reactor concepts identified by the Generation IV International Forum as a candidate for cooperative development, which is characterized by remarkable advantages in inherent safety, fuel cycle, miniaturization, effective utilization of nuclear resources and proliferation resistance. ORNL finished the conceptual design of Molten Salt Breeder Reactor (MSBR) based on the design, building and operation of Molten Salt Reactor Experiment (MSRE). Purpose: We attempt to implement the preliminary safety analysis of MSBR in order to provide a reference for the design and optimization of MSBR in the future. Methods: According to the conceptual design of MSBR, a model of safety analysis using point kinetics coupled with the simplified heat transfer mechanism is presented. The model is applied to simulate the transient phenomena of MSBR initiated by an abnormal step reactivity addition and an abnormal ramp reactivity addition at full-power equilibrium condition. Results: The thermal power in the core increases rapidly at the beginning and is accompanied by a rise of the fuel and graphite temperatures after 100, 300, 500 and 600 pcm reactivity addition. The maximum outlet temperature of the fuel in the core is at 1250℃ in 500 pcm reactivity addition, but up to 1350℃ in 600 pcm reactivity addition. The maximum of the power and the temperature are delayed and lower in the ramp reactivity addition rather than in the step reactivity addition. Conclusions: Based on the results, when the reactivity inserted is less than 500 pcm in maximum at full power equilibrium condition, the structural material in Hastelloy-N is not melted and can keep integrity without external control action. And it is necessary to try to avoid inserting a reactivity at short time. (authors)

  6. International exchange of safety and licensing information

    International Nuclear Information System (INIS)

    Lafleur, J.D. Jr.; Hauber, R.D.; Chenier, D.M.

    1977-01-01

    A network of formal and informal bilateral arrangements for the exchange of nuclear safety information is being established by the U.S. Nuclear Regulatory Commission. For developing countries, such arrangements can provide ready access to the extensive, fully documented safety analyses and safety research results that NRC has accumulated. NRC has been receiving foreign visitors at a rate of about 500 per year, largely for discussions of safety and licensing questions related to light water reactors. Exchanges also are taking place on the safety of advanced reactors. A special interest of the NRC is in providing for reciprocal communicaion, at the earliest possible time, of important problems, decisions and other actions on nuclear safety matters. For example, it is essential that a newly-discovered problem in a nuclear reactor be brought immediately to the attention of other governments which are responsible for the safety of similar reactors. Definite progress has been made in the U.S. Freedom of Information Act. Certain exchanges have taken place on this basis. Experience in the establishment and operation of NRC's bilateral exchange arrangements is summarized. A typical exchange with the regulatory authority of country building its first power reactor is described

  7. Preliminary safety evaluation for a medical therapy reactor

    International Nuclear Information System (INIS)

    Jones, J.L.; Neuman, W.A.

    1989-01-01

    A conceptual design of a passively safe reactor facility for boron neutron capture therapy has been previously described. The medical therapy reactor (MTR) has a maximum power level of 10 MW(thermal) and utilizes 45 wt% uranium in UZrH, 20 wt% 235 U enriched hydride fuel matrix with 1 wt% erbium, which is a burnable poison and provides prompt negative reactivity feedback. The facility has five beam ports for patient treatment and advanced neutron beam research and is capable of 2,000 to 10,000 treatments per year, assuming single 8h/day, 5 day/week operation. The epithermal treatment flux from the beam ports is large, enabling single-session treatment of brain cancers of <10-min duration, with minimal fast neutron and gamma contaminants. The reactor core is designed with sufficient excess reactivity to yield a core lifetime equal to a facility lifetime of 30 yr. A preliminary safety evaluation was performed using the RELAP5 thermal-hydraulic code. The analysis addressed accidents in several major categories, including a pump coastdown, a loss of secondary heat sink, and a $0.5 step reactivity insertion

  8. Preliminary safety evaluation for the spent nuclear fuel project`s cold vacuum drying system

    Energy Technology Data Exchange (ETDEWEB)

    Garvin, L.J., Westinghouse Hanford

    1996-07-01

    This preliminary safety evaluation (PSE) considers only the Cold Vacuum Drying System (CVDS) facility and its mission as it relates to the integrated process strategy (WHC 1995). The purpose of the PSE is to identify those CBDS design functions that may require safety- class and safety-significant accident prevention and mitigation features.

  9. Food safety: correct information for pregnant women

    Directory of Open Access Journals (Sweden)

    Bartolomeo Griglio

    2013-04-01

    Full Text Available This study was aimed at investigating the knowledge of pregnant women on food safety with particular attention to the effectiveness of the informative material (pamphlet and poster prepared in a previous study. To this scope, a questionnaire composed by 8 questions (Likert scaled was used except for one which was a Y/N question. Themes of the questionnaire were: level of concerns on food safety, and knowledge on foodborne diseases (salomonellosis, toxoplasmosis and listeriosis, risk factors and preventive measures. Results indicate that knowledge increased in respect to that of the previous study, but in relation to informative material previously distributed.

  10. Operating performance and environmental and safety risks: A preliminary comparison of majors and independents

    International Nuclear Information System (INIS)

    Pulsipher, A.G.; Iledare, W.O.; Baumann, R.H.; Mesyanzhinov, D.

    1995-01-01

    The objective is to compare the safety and environmental records of oil and gas companies operating on the OCS in the Gulf of Mexico over the past decade. The reason for doing so is to help inform public sector policy-makers and private sector decision-makers about the potential safety and environmental risks associated with the expected increased presence of smaller independents in the domestic oil and gas industry in general and on the federal OCS in particular. The preliminary conclusion is that although independents have had a modestly high incidence of fires and explosions than the majors, the difference is not significant statistically and is largely attributable to a few ''bad actors'' rather than demonstrably poorer practice by the group as a whole

  11. Preliminary considerations on safety of computerized control rooms

    International Nuclear Information System (INIS)

    Vittet, J.

    1983-02-01

    Safety problems are analyzed in this report by the study of the interaction: ''human behavior in a rigid environment/information overload in perturbed situation''. For pedagogy the study is presented as a research of factors influencing operator performance in a control room and a dialogue between an analyst and a conceiving engineer. Danger of all control room where the strategy for data acquisition is too rigid and without spatial reference is stressed in conclusion. Orientations for an advanced control room are outlined [fr

  12. Collateral Information for Equating in Small Samples: A Preliminary Investigation

    Science.gov (United States)

    Kim, Sooyeon; Livingston, Samuel A.; Lewis, Charles

    2011-01-01

    This article describes a preliminary investigation of an empirical Bayes (EB) procedure for using collateral information to improve equating of scores on test forms taken by small numbers of examinees. Resampling studies were done on two different forms of the same test. In each study, EB and non-EB versions of two equating methods--chained linear…

  13. Problems of use of preliminary information technology in maritime passes

    Directory of Open Access Journals (Sweden)

    Elena I. Antonova

    2017-12-01

    Full Text Available The technology of preliminary informing is the priority direction of development of information technologies in the customs authorities. Russian model prior information on Maritime transport contains a number of features that distinguish it from world practice. The studied is the possibility of creating a unified information system of state regulatory bodies in the Maritime checkpoints. The article considers one of directions of automation of information interaction between Maritime stakeholders in the conduct of customs and other types of state control with the use of a single information space, based on the then-experimental solutions. Analysis of experience of implementation and operation of the software complex "Portal port" in the region of the Vladivostok customs have helped to identify problems in the application of the technology of preliminary information on Maritime transport. The proposed solutions to these problems provide an opportunity to work on improvement of this technology and to introduce mandatory preliminary notification in all sea checkpoints on the territory of the Russian Federation, will allow to optimize the performance of customs and other state Supervisory authorities at the seaport, us-blame the turnover and will contribute to the development of the far Eastern region as a whole.

  14. Preliminary Study on the Revision of Nuclear Safety Policy Statement

    International Nuclear Information System (INIS)

    Lee, Y. E.; Lee, S. H.; Chang, H. S.; Choi, K. S.; Jung, S. J.

    2011-01-01

    Nuclear safety policy in Korea is currently declared in the Nuclear Safety Charter as the highest tier document and safety principles and directions are announced in the Nuclear Safety Policy Statement. As the circumstances affecting on the nuclear safety policy change, it needs to revise the Statement. This study aims to develop the revised Nuclear Safety Policy Statement to declare that securing safety is a prerequisite to the utilization of nuclear energy, and that all workers in nuclear industry and regulatory body must adhere to the principle of priority to safety. As a result, two different types of revision are being prepared as of August. One is based on the spirit of Nuclear Safety Charter as well as the direction of future-oriented safety policies including the changes in the environment after declaration of the Statement. The other is to declare the fundamental safety objective and safety principles as the top philosophy of national nuclear safety policy by adopting the '10 Safety Principles in IAEA Safety Fundamental' instead of the current Charter. Both versions of revision are subject to further in-depth discussion. However once the revision is finalized and declared, it would be useful to accomplish effectively the organizational responsibilities and to enhance the public confidence in nuclear safety by performing the regulatory activities in a planned and systematic manner and promulgating the government's dedication to priority to safety

  15. Ares-I-X Vehicle Preliminary Range Safety Malfunction Turn Analysis

    Science.gov (United States)

    Beaty, James R.; Starr, Brett R.; Gowan, John W., Jr.

    2008-01-01

    Ares-I-X is the designation given to the flight test version of the Ares-I rocket (also known as the Crew Launch Vehicle - CLV) being developed by NASA. As part of the preliminary flight plan approval process for the test vehicle, a range safety malfunction turn analysis was performed to support the launch area risk assessment and vehicle destruct criteria development processes. Several vehicle failure scenarios were identified which could cause the vehicle trajectory to deviate from its normal flight path, and the effects of these failures were evaluated with an Ares-I-X 6 degrees-of-freedom (6-DOF) digital simulation, using the Program to Optimize Simulated Trajectories Version 2 (POST2) simulation framework. The Ares-I-X simulation analysis provides output files containing vehicle state information, which are used by other risk assessment and vehicle debris trajectory simulation tools to determine the risk to personnel and facilities in the vicinity of the launch area at Kennedy Space Center (KSC), and to develop the vehicle destruct criteria used by the flight test range safety officer. The simulation analysis approach used for this study is described, including descriptions of the failure modes which were considered and the underlying assumptions and ground rules of the study, and preliminary results are presented, determined by analysis of the trajectory deviation of the failure cases, compared with the expected vehicle trajectory.

  16. RISK-INFORMED SAFETY MARGIN CHARACTERIZATION

    International Nuclear Information System (INIS)

    Dinh, Nam; Szilard, Ronaldo

    2009-01-01

    The concept of safety margins has served as a fundamental principle in the design and operation of commercial nuclear power plants (NPPs). Defined as the minimum distance between a system's 'loading' and its 'capacity', plant design and operation is predicated on ensuring an adequate safety margin for safety-significant parameters (e.g., fuel cladding temperature, containment pressure, etc.) is provided over the spectrum of anticipated plant operating, transient and accident conditions. To meet the anticipated challenges associated with extending the operational lifetimes of the current fleet of operating NPPs, the United States Department of Energy (USDOE), the Idaho National Laboratory (INL) and the Electric Power Research Institute (EPRI) have developed a collaboration to conduct coordinated research to identify and address the technological challenges and opportunities that likely would affect the safe and economic operation of the existing NPP fleet over the postulated long-term time horizons. In this paper we describe a framework for developing and implementing a Risk-Informed Safety Margin Characterization (RISMC) approach to evaluate and manage changes in plant safety margins over long time horizons

  17. Preliminary report of radiological safety to hydrology 1993 campaign

    International Nuclear Information System (INIS)

    Badano, A.; Suarez Antola, R.; Dellepere, A.; Barreiro, M.

    1993-01-01

    This report has been prepared based on the interaction between project managers and division radiological Protection and Nuclear Safety. In seeking to establish a basis for approval from the point of view of radiation safety practices . The idea for the audit has been provided at all times because the interest was the exchange of ideas and the use of common sense to improve the safety of radioactive substances, security of operators and public safety and environment.The above shows that in the planned radiation safety condition described in this report,the practice can be carried out according to the criteria of safety accepted .

  18. Analysis and design on airport safety information management system

    Directory of Open Access Journals (Sweden)

    Yan Lin

    2017-01-01

    Full Text Available Airport safety information management system is the foundation of implementing safety operation, risk control, safety performance monitor, and safety management decision for the airport. The paper puts forward the architecture of airport safety information management system based on B/S model, focuses on safety information processing flow, designs the functional modules and proposes the supporting conditions for system operation. The system construction is helpful to perfecting the long effect mechanism driven by safety information, continually increasing airport safety management level and control proficiency.

  19. Maintenance of radiation safety information system

    Energy Technology Data Exchange (ETDEWEB)

    Choi, Ho Sun [Korea Institute of Nuclear Safety, Taejon (Korea, Republic of); Park, Moon Il; Chung, Chong Kyu; Lim, Bock Soo; Kim, Hyung Uk; Chang, Kwang Il; Nam, Kwan Hyun; Cho, Hye Ryan [AD center incubation LAB, Taejon (Korea, Republic of)

    2001-12-15

    The objectives of radiation safety information system maintenance are to maintain the requirement of users, change of job process and upgrade of the system performance stably and effectively while system maintenance. We conduct the code of conduct recommended by IAEA, management of radioisotope inventory database systematically using analysis for the state of inventory database integrated in this system. This system and database will be support the regulatory guidance, rule making and information to the MOST, KINS, other regulatory related organization and general public optimizationally.

  20. 77 FR 15453 - Pipeline Safety: Information Collection Activities

    Science.gov (United States)

    2012-03-15

    ... DEPARTMENT OF TRANSPORTATION Pipeline and Hazardous Materials Safety Administration [Docket No... information collection titled, ``Gas Pipeline Safety Program Certification and Hazardous Liquid Pipeline... collection request that PHMSA will be submitting to OMB for renewal titled, ``Gas Pipeline Safety Program...

  1. Information systems in food safety management.

    Science.gov (United States)

    McMeekin, T A; Baranyi, J; Bowman, J; Dalgaard, P; Kirk, M; Ross, T; Schmid, S; Zwietering, M H

    2006-12-01

    Information systems are concerned with data capture, storage, analysis and retrieval. In the context of food safety management they are vital to assist decision making in a short time frame, potentially allowing decisions to be made and practices to be actioned in real time. Databases with information on microorganisms pertinent to the identification of foodborne pathogens, response of microbial populations to the environment and characteristics of foods and processing conditions are the cornerstone of food safety management systems. Such databases find application in: Identifying pathogens in food at the genus or species level using applied systematics in automated ways. Identifying pathogens below the species level by molecular subtyping, an approach successfully applied in epidemiological investigations of foodborne disease and the basis for national surveillance programs. Predictive modelling software, such as the Pathogen Modeling Program and Growth Predictor (that took over the main functions of Food Micromodel) the raw data of which were combined as the genesis of an international web based searchable database (ComBase). Expert systems combining databases on microbial characteristics, food composition and processing information with the resulting "pattern match" indicating problems that may arise from changes in product formulation or processing conditions. Computer software packages to aid the practical application of HACCP and risk assessment and decision trees to bring logical sequences to establishing and modifying food safety management practices. In addition there are many other uses of information systems that benefit food safety more globally, including: Rapid dissemination of information on foodborne disease outbreaks via websites or list servers carrying commentary from many sources, including the press and interest groups, on the reasons for and consequences of foodborne disease incidents. Active surveillance networks allowing rapid dissemination

  2. Mass-media information campaigns about road safety. [previously known as: Public information about road safety.

    NARCIS (Netherlands)

    2009-01-01

    In the Netherlands, public information is often used as an instrument to improve road safety. The purpose of each public information campaign is a voluntary and lasting change in traffic behaviour. This requires road users to have sufficient knowledge about a problem and to adapt their behaviour.

  3. Preliminary report in radiological safety for 1993 hydrology campaign

    International Nuclear Information System (INIS)

    Badano, A.; Suraez, R.; Dellepere, A.; Barreiro, M.

    1993-01-01

    The purpose of this report is to provide a study about industrial effluents influence on water pollution of Montevideo coastal beaches. The methods which have been considered are nuclear tracer techniques with a special attention in the radioprotection supervision. Three points are considered as evaluation: handling of radioactive tracers and safety, radiation protection workers, environment and public safety. tabs

  4. Preliminary investigation on reliability assessment of passive safety system

    International Nuclear Information System (INIS)

    Huang Changfan; Kuang Bo

    2012-01-01

    The reliability evaluation of passive safety system plays an important part in probabilistic safety assessment (PSA) of nuclear power plant applying passive safety design, which depends quantitatively on reliabilities of passive safety system. According to the object of reliability assessment of passive safety system, relevant parameters are identified. Then passive system behavior during accident scenarios are studied. A practical example of this method is given for the case of reliability assessment of AP1000 passive heat removal system in loss of normal feedwater accident. Key and design parameters of PRHRS are identified and functional failure criteria are established. Parameter combinations acquired by Latin hyper~ cube sampling (LHS) in possible parametric ranges are input and calculations of uncertainty propagation through RELAP5/MOD3 code are carried out. Based on the calculations, sensitivity assessment on PRHRS functional criteria and reliability evaluation of the system are presented, which might provide further PSA with PRHR system reliability. (authors)

  5. Preliminary Study on the Development of Quantitative Safety Culture Index

    International Nuclear Information System (INIS)

    Lee, Young Eal; Kim, Hun Sil; Ahn, Nam Sung

    2005-01-01

    Safety culture is that assembly of characteristics and attitudes in organizations and individuals which establishes that, as an overriding priority, nuclear plant safety issues receive the attention warranted by their significance. Because it needs to be recognized as the most significant consciousness to achieve the nuclear safety performance, Korean government and nuclear power generation company have tried to develop the practical method to improve the safety culture from the long term point view. In this study, based on the site interviews to define the potential issues on organizational behavior for the safe operation and the survey on the level of safety culture of occupied workers are conducted. Survey results are quantified as a few indicators of nuclear safety by the statistical method and it can be simulated by the dynamic modeling as time goes on. Currently index and dynamic modeling are still being developed, however, results can be used to suggest the long term strategy which safety is clearly integrated into all activities in the nuclear organization

  6. The status of waste information in South Africa: preliminary findings of the waste information baseline

    CSIR Research Space (South Africa)

    Oelofse, Suzanna HH

    2012-10-01

    Full Text Available of the tonnages of waste recycled, treated, landfilled and exported. Waste information thus collected will inform amongst others, education, awareness raising, planning, reporting and public safety management. However, until SAWIS moves from voluntary reporting...

  7. Preliminary safety analysis report for the Waste Characterization Facility

    International Nuclear Information System (INIS)

    1994-10-01

    This safety analysis report outlines the safety concerns associated with the Waste Characterization Facility located in the Radioactive Waste Management Complex at the Idaho National Engineering Laboratory. The three main objectives of the report are to: define and document a safety basis for the Waste Characterization Facility activities; demonstrate how the activities will be carried out to adequately protect the workers, public, and environment; and provide a basis for review and acceptance of the identified risk that the managers, operators, and owners will assume. 142 refs., 38 figs., 39 tabs

  8. Documentation of Hanford Site independent review of the Hanford Waste Vitrification Plant Preliminary Safety Analysis Report

    International Nuclear Information System (INIS)

    Herborn, D.I.

    1991-10-01

    The requirements for Westinghouse Hanford independent review of the Preliminary Safety Analysis Report (PSAR) are contained in Section 1.0, Subsection 4.3 of WCH-CM-4-46. Specifically, this manual requires the following: (1) Formal functional reviews of the HWVP PSAR by the future operating organization (HWVP Operations), and the independent review organizations (HWVP and Environmental Safety Assurance, Environmental Assurance, and Quality Assurance); and (2) Review and approval of the HWVP PSAR by the Tank Waste Disposal (TWD) Subcouncil of the Safety and Environmental Advisory Council (SEAC), which provides independent advice to the Westinghouse Hanford President and executives on matters of safety and environmental protection. 7 refs

  9. Preliminary Safety Design Report for Remote Handled Low-Level Waste Disposal Facility

    Energy Technology Data Exchange (ETDEWEB)

    Timothy Solack; Carol Mason

    2012-03-01

    A new onsite, remote-handled low-level waste disposal facility has been identified as the highest ranked alternative for providing continued, uninterrupted remote-handled low-level waste disposal for remote-handled low-level waste from the Idaho National Laboratory and for nuclear fuel processing activities at the Naval Reactors Facility. Historically, this type of waste has been disposed of at the Radioactive Waste Management Complex. Disposal of remote-handled low-level waste in concrete disposal vaults at the Radioactive Waste Management Complex will continue until the facility is full or until it must be closed in preparation for final remediation of the Subsurface Disposal Area (approximately at the end of Fiscal Year 2017). This preliminary safety design report supports the design of a proposed onsite remote-handled low-level waste disposal facility by providing an initial nuclear facility hazard categorization, by discussing site characteristics that impact accident analysis, by providing the facility and process information necessary to support the hazard analysis, by identifying and evaluating potential hazards for processes associated with onsite handling and disposal of remote-handled low-level waste, and by discussing the need for safety features that will become part of the facility design.

  10. Preliminary safety analysis of unscrammed events for KLFR

    International Nuclear Information System (INIS)

    Kim, S.J.; Ha, G.S.

    2005-01-01

    The report presents the design features of KLFR; Safety Analysis Code; steady-state calculation results and analysis results of unscrammed events. The calculations of the steady-state and unscrammed events have been performed for the conceptual design of KLFR using SSC-K code. UTOP event results in no fuel damage and no centre-line melting. The inherent safety features are demonstrated through the analysis of ULOHS event. Although the analysis of ULOF has much uncertainties in the pump design, the analysis results show the inherent safety characteristics. 6% flow of rated flow of natural circulation is formed in the case of ULOF. In the metallic fuel rod, the cladding temperature is somewhat high due to the low heat transfer coefficient of lead. ULOHS event should be considered in design of RVACS for long-term cooling

  11. Preliminary safety analysis of the HTTR-IS nuclear hydrogen production system

    International Nuclear Information System (INIS)

    Sato, Hiroyuki; Ohashi, Hirofumi; Tazawa, Yujiro; Tachibana, Yukio; Sakaba, Nariaki

    2010-06-01

    Japan Atomic Energy Agency is planning to demonstrate hydrogen production by thermochemical water-splitting IS process utilizing heat from the high-temperature gas-cooled reactor HTTR (HTTR-IS system). The previous study identified that the HTTR modification due to the coupling of hydrogen production plant requires an additional safety review since the scenario and quantitative values of the evaluation items would be altered from the original HTTR safety review. Hence, preliminary safety analyses are conducted by using the system analysis code. Calculation results showed that evaluation items such as a coolant pressure, temperatures of heat transfer tubes at the pressure boundary, etc., did not exceed allowable values. Also, the peak fuel temperature did not exceed allowable value and therefore the reactor core was not damaged and cooled sufficiently. This report compiles calculation conditions, event scenarios and the calculation results of the preliminary safety analysis. (author)

  12. Preliminary safety analysis for key design features of KALIMER

    Energy Technology Data Exchange (ETDEWEB)

    Hahn, D. H.; Kwon, Y. M.; Chang, W. P.; Suk, S. D.; Lee, S. O.; Lee, Y. B.; Jeong, K. S

    2000-07-01

    KAERI is currently developing the conceptual design of a liquid metal reactor, KALIMER(Korea Advanced Liquid Metal Reactor) under the long-term nuclear R and D program. In this report, descriptions of the KALIMER safety design features and safety analyses results for selected ATWS accidents are presented. First, the basic approach to achieve the safety goal is introduced in chapter 1, and the safety evaluation procedure for the KALIMER design is described in chapter 2. It includes event selection, event categorization, description of design basis events, and beyond design basis events. In chapter 3, results of inherent safety evaluations for the KALIMER conceptual design are presented. The KALIMER core and plant system are designed to assure design performance during a selected set of events without either reactor control or protection system intervention. Safety analyses for the postulated anticipated transient without scram(ATWS) have been performed to investigate the KALIMER system response to the events. They are categorized as bounding events(BEs) because of their low probability of occurrence. In chapter 4, the design of the KALIMER containment dome and the results of its performance analysis are presented. The designs of the existing LMR containment and the KALIMER containment dome have been compared in this chapter. Procedure of the containment performance analysis and the analysis results are described along with the accident scenario and source terms. Finally, a simple methodology is introduced to investigate the core kinetics and hydraulic behavior during HCDA in chapter 5. Mathematical formulations have been developed in the framework of the modified bethe-tait method, and scoping analyses have been performed for the KALIMER core behavior during super-prompt critical excursions.

  13. 47 CFR 80.1135 - Transmission of maritime safety information.

    Science.gov (United States)

    2010-10-01

    ... 47 Telecommunication 5 2010-10-01 2010-10-01 false Transmission of maritime safety information. 80... RADIO SERVICES STATIONS IN THE MARITIME SERVICES Global Maritime Distress and Safety System (GMDSS) Operating Procedures for Distress and Safety Communications § 80.1135 Transmission of maritime safety...

  14. Stakeholder Safety in Information Systems Research

    Directory of Open Access Journals (Sweden)

    R.H. Barbour

    2006-11-01

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

  15. Preliminary Marine Safety Risk Assessment, Brandon Road Lock and Dam Invasive Species Control Measures

    Science.gov (United States)

    2016-12-01

    Decision makers must include control-measure monitoring and emergency “interventions” to insure safety. The Coast Guard operational commanders...system” incorporates a travelling car on a rail above the barge-loading wharf to prevent loading personnel, cargo surveyors, or others from falling...to the Gulf of Mexico . As “Loopers”, they will have already transited the CSSC electric barriers. Preliminary Marine Safety Risk Assessment, BRLD

  16. Study of fast reactor safety test facilities. Preliminary report

    International Nuclear Information System (INIS)

    Bell, G.I.; Boudreau, J.E.; McLaughlin, T.; Palmer, R.G.; Starkovich, V.; Stein, W.E.; Stevenson, M.G.; Yarnell, Y.L.

    1975-05-01

    Included are sections dealing with the following topics: (1) perspective and philosophy of fast reactor safety analysis; (2) status of accident analysis and experimental needs; (3) experiment and facility definitions; (4) existing in-pile facilities; (5) new facility options; and (6) data acquisition methods

  17. 49 CFR 211.61 - Informal safety inquiries.

    Science.gov (United States)

    2010-10-01

    ... information on selected topics relating to railroad safety. A notice of each such inquiry will be published in... 49 Transportation 4 2010-10-01 2010-10-01 false Informal safety inquiries. 211.61 Section 211.61..., DEPARTMENT OF TRANSPORTATION RULES OF PRACTICE Miscellaneous Safety-Related Proceedings and Inquiries § 211...

  18. 40 CFR 68.65 - Process safety information.

    Science.gov (United States)

    2010-07-01

    ... (CONTINUED) CHEMICAL ACCIDENT PREVENTION PROVISIONS Program 3 Prevention Program § 68.65 Process safety... 40 Protection of Environment 15 2010-07-01 2010-07-01 false Process safety information. 68.65... compilation of written process safety information before conducting any process hazard analysis required by...

  19. Mixed Waste Management Facility Preliminary Safety Analysis Report. Chapters 1 to 20

    Energy Technology Data Exchange (ETDEWEB)

    1994-09-01

    This document provides information on waste management practices, occupational safety, and a site characterization of the Lawrence Livermore National Laboratory. A facility description, safety engineering analysis, mixed waste processing techniques, and auxiliary support systems are included.

  20. Mixed Waste Management Facility Preliminary Safety Analysis Report. Chapters 1 to 20

    International Nuclear Information System (INIS)

    1994-09-01

    This document provides information on waste management practices, occupational safety, and a site characterization of the Lawrence Livermore National Laboratory. A facility description, safety engineering analysis, mixed waste processing techniques, and auxiliary support systems are included

  1. Preliminary Evaluation of an Aviation Safety Thesaurus' Utility for Enhancing Automated Processing of Incident Reports

    Science.gov (United States)

    Barrientos, Francesca; Castle, Joseph; McIntosh, Dawn; Srivastava, Ashok

    2007-01-01

    This document presents a preliminary evaluation the utility of the FAA Safety Analytics Thesaurus (SAT) utility in enhancing automated document processing applications under development at NASA Ames Research Center (ARC). Current development efforts at ARC are described, including overviews of the statistical machine learning techniques that have been investigated. An analysis of opportunities for applying thesaurus knowledge to improving algorithm performance is then presented.

  2. Environmental safety of the global information space

    Directory of Open Access Journals (Sweden)

    В’ячеслав Степанович Волошин

    2015-03-01

    Databases of full-text publications – journals, articles, monographs- are surely a means of salvation for science. There already exist a large number of such portals. Besides, advantages and disadvantages of electronic subscriptions to periodicals should certainly be considered. The former include the following most evident ones: aggregation of large data arrays, saving money on a subscription, an opportunity to work with relevant publications, thematic collections of materials, availability of records, simultaneous access of an unlimited number of users and others. Nevertheless, there are many disadvantages that make it difficult to work with full-text publications. They are the following: selective representativeness of publication numbers, complexity of keyword search, occasional presence of obsolete text formats, printed versions, possible psychological barrier, physiological incompatibility with computer equipment, fatigue caused by prolonged work on the computer. The Internet was followed by the appearance of global control networks, their aims ranging from control of a human life support to a unified control of humanity. So, the formed global information space promises the man to get access to almost any information source. Meanwhile, environmental safety of the man, his/her objective biological psyche and abilities in harmonious development are at serious risk

  3. 75 FR 53733 - Pipeline Safety: Information Collection Activities

    Science.gov (United States)

    2010-09-01

    ... DEPARTMENT OF TRANSPORTATION Pipeline and Hazardous Materials Safety Administration [Docket No. PHMSA-2010-0246] Pipeline Safety: Information Collection Activities AGENCY: Pipeline and Hazardous... liquefied natural gas, hazardous liquid, and gas transmission pipeline systems operated by a company. The...

  4. Recommendations: Procedure to develop a preliminary safety report as part of the radioactive waste repository construction licensing process

    International Nuclear Information System (INIS)

    2003-01-01

    The structure of a preliminary safety report for the title purpose should be as follows: A. Textual part: 1. General (Introduction, Basic information about the construction, Timetable); 2. Site information (Siting, Geography and demography, Meteorology and climatic situation, Hydrology, Geology and hydrogeology); 3. Repository design description (Basic function and performance requirements, Design, Auxiliary systems, Fire prevention/protection, Emergency plans); 4. Operation of the repository (Waste acceptance and inspection, Waste handling and interim storage, Waste disposal, Operating monitoring), 5. Health and environmental impact assessment (Radionuclide inventory, Radionuclide transport paths and mechanisms of release into the environment, Radionuclide release in normal and emergency situations, Radiation protection - health impact assessment and regulatory compliance, Draft operating limits and conditions, Proposed ways of assuring physical protection, Uncertainty assessment), 6. Safe repository shutdown/decommissioning concept, 7 Quality assurance assessment, 8. List of selected equipment. B. Annexes: Maps, Drawings, Diagrams, Miscellaneous; C. Documentation: Previous safety report amendments, Protocols, Miscellaneous. (P.A.)

  5. Think over nuclear safety. ''Information asymmetry'' and ''comminicative action''

    International Nuclear Information System (INIS)

    Suzuki, Atsuyuki

    2006-01-01

    Nuclear safety should be fully understood not only technically but also socially. In order to think over nuclear safety socially, four different concepts were recommended to refer, which were ''procedural rationality'', information asymmetry'', ''certainty effect'' and ''communicative action'' proposed by three economists and a philosopher respectively. Risk-based communication approach for nuclear safety could be effective within the higher frequency area than safety goal, but not good for the lower frequency area than safety goal. The latter could be highly subjective and more qualitative. For this area, ''safety communication'' would be highly maintained with taking account of existence of ''information asymmetry'' and need of ''communicative action''. (T.Tanaka)

  6. Deep repository for long-lived low- and intermediate-level waste. Preliminary safety assessment

    International Nuclear Information System (INIS)

    1999-11-01

    A preliminary safety assessment has been performed of a deep repository for long-lived low- and intermediate-level waste, SFL 3-5. The purpose of the study is to investigate the capacity of the facility to act as a barrier to the release of radionuclides and toxic pollutants, and to shed light on the importance of the location of the repository site. A safety assessment (SR 97) of a deep repository for spent fuel has been carried out at the same time. In SR 97, three hypothetical repository sites have been selected for study. These sites exhibit fairly different conditions in terms of hydrogeology, hydrochemistry and ecosystems. To make use of information and data from the SR 97 study, we have assumed that SFL 3-5 is co-sited with the deep repository for spent fuel. A conceivable alternative is to site SFL 3-5 as a completely separate repository. The focus of the SFL 3-5 study is a quantitative analysis of the environmental impact for a reference scenario, while other scenarios are discussed and analyzed in more general terms. Migration in the repository's near- and far-field has been taken into account in the reference scenario. Environmental impact on the three sites has also been calculated. The calculations are based on an updated forecast of the waste to be disposed of in SFL 3-5. The forecast includes radionuclide content, toxic metals and other substances that have a bearing on a safety assessment. The safety assessment shows how important the site is for safety. Two factors stand out as being particularly important: the water flow at the depth in the rock where the repository is built, and the ecosystem in the areas on the ground surface where releases may take place in the future. Another conclusion is that radionuclides that are highly mobile and long-lived, such as 36 Cl and 93 Mo , are important to take into consideration. Their being long-lived means that barriers and the ecosystems must be regarded with a very long time horizon

  7. Deep repository for long-lived low- and intermediate-level waste. Preliminary safety assessment

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-11-01

    A preliminary safety assessment has been performed of a deep repository for long-lived low- and intermediate-level waste, SFL 3-5. The purpose of the study is to investigate the capacity of the facility to act as a barrier to the release of radionuclides and toxic pollutants, and to shed light on the importance of the location of the repository site. A safety assessment (SR 97) of a deep repository for spent fuel has been carried out at the same time. In SR 97, three hypothetical repository sites have been selected for study. These sites exhibit fairly different conditions in terms of hydrogeology, hydrochemistry and ecosystems. To make use of information and data from the SR 97 study, we have assumed that SFL 3-5 is co-sited with the deep repository for spent fuel. A conceivable alternative is to site SFL 3-5 as a completely separate repository. The focus of the SFL 3-5 study is a quantitative analysis of the environmental impact for a reference scenario, while other scenarios are discussed and analyzed in more general terms. Migration in the repository's near- and far-field has been taken into account in the reference scenario. Environmental impact on the three sites has also been calculated. The calculations are based on an updated forecast of the waste to be disposed of in SFL 3-5. The forecast includes radionuclide content, toxic metals and other substances that have a bearing on a safety assessment. The safety assessment shows how important the site is for safety. Two factors stand out as being particularly important: the water flow at the depth in the rock where the repository is built, and the ecosystem in the areas on the ground surface where releases may take place in the future. Another conclusion is that radionuclides that are highly mobile and long-lived, such as {sup 36}Cl and {sup 93}Mo , are important to take into consideration. Their being long-lived means that barriers and the ecosystems must be regarded with a very long time horizon.

  8. Most significant preliminary results of the probabilistic safety analysis on the Juragua nuclear power plant

    International Nuclear Information System (INIS)

    Perdomo, Manuel

    1995-01-01

    Since 1990 the Group for PSA Development and Applications (GDA/APS) is working on the Level-1 PSA for the Juragua-1 NPP, as a part of an IAEA Technical Assistance Project. The main objective of this study, which is still under way, is to assess, in a preliminary way, the Reactor design safety to find its potential 'weak points' at the construction stage, using a eneric data base. At the same time, the study allows the PSA team to familiarize with the plant design and analysis techniques for the future operational PSA of the plant. This paper presents the most significant preliminary results of the study, which reveal some advantages of the safety characteristics of the plant design in comparison with the homologous VVER-440 reactors and some areas, where including slight modifications would improve the plant safety, considering the level of detail at which the study is carried out. (author). 13 refs, 1 fig, 2 tabs

  9. Safety of High Speed Magnetic Levitation Transportation Systems: Preliminary Safety Review of the Transrapid Maglev System

    Science.gov (United States)

    1990-11-01

    The safety of various magnetically levitated trains under development for possible : implementation in the United States is of direct concern to the Federal Railroad : Administration. This report, one in a series of planned reports on maglev safety, ...

  10. Preliminary safety evaluation (PSE) for Sodium Storage Facility at the Fast Flux Test Facility

    International Nuclear Information System (INIS)

    Bowman, B.R.

    1994-01-01

    This evaluation was performed for the Sodium Storage Facility (SSF) which will be constructed at the Fast Flux Test Facility (FFTF) in the area adjacent to the South and West Dump Heat Exchanger (DHX) pits. The purpose of the facility is to allow unloading the sodium from the FFTF plant tanks and piping. The significant conclusion of this Preliminary Safety Evaluation (PSE) is that the only Safety Class 2 components are the four sodium storage tanks and their foundations. The building, because of its imminent risk to the tanks under an earthquake or high winds, will be Safety Class 3/2, which means the building has a Safety Class 3 function with the Safety Class 2 loads of seismic and wind factored into the design

  11. Safety Case Development as an Information Modelling Problem

    Science.gov (United States)

    Lewis, Robert

    This paper considers the benefits from applying information modelling as the basis for creating an electronically-based safety case. It highlights the current difficulties of developing and managing large document-based safety cases for complex systems such as those found in Air Traffic Control systems. After a review of current tools and related literature on this subject, the paper proceeds to examine the many relationships between entities that can exist within a large safety case. The paper considers the benefits to both safety case writers and readers from the future development of an ideal safety case tool that is able to exploit these information models. The paper also introduces the idea that the safety case has formal relationships between entities that directly support the safety case argument using a methodology such as GSN, and informal relationships that provide links to direct and backing evidence and to supporting information.

  12. Ibogaine: complex pharmacokinetics, concerns for safety, and preliminary efficacy measures.

    Science.gov (United States)

    Mash, D C; Kovera, C A; Pablo, J; Tyndale, R F; Ervin, F D; Williams, I C; Singleton, E G; Mayor, M

    2000-09-01

    Ibogaine is an indole alkaloid found in the roots of Tabernanthe Iboga (Apocynaceae family), a rain forest shrub that is native to western Africa. Ibogaine is used by indigenous peoples in low doses to combat fatigue, hunger and thirst, and in higher doses as a sacrament in religious rituals. Members of American and European addict self-help groups have claimed that ibogaine promotes long-term drug abstinence from addictive substances, including psychostimulants and opiates. Anecdotal reports attest that a single dose of ibogaine eliminates opiate withdrawal symptoms and reduces drug craving for extended periods of time. The purported efficacy of ibogaine for the treatment of drug dependence may be due in part to an active metabolite. The majority of ibogaine biotransformation proceeds via CYP2D6, including the O-demethylation of ibogaine to 12-hydroxyibogamine (noribogaine). Blood concentration-time effect profiles of ibogaine and noribogaine obtained for individual subjects after single oral dose administrations demonstrate complex pharmacokinetic profiles. Ibogaine has shown preliminary efficacy for opiate detoxification and for short-term stabilization of drug-dependent persons as they prepare to enter substance abuse treatment. We report here that ibogaine significantly decreased craving for cocaine and heroin during inpatient detoxification. Self-reports of depressive symptoms were also significantly lower after ibogaine treatment and at 30 days after program discharge. Because ibogaine is cleared rapidly from the blood, the beneficial aftereffects of the drug on craving and depressed mood may be related to the effects of noribogaine on the central nervous system.

  13. A preliminary safety evaluation of polyhexamethylene guanidine hydrochloride.

    Science.gov (United States)

    Asiedu-Gyekye, Isaac Julius; Mahmood, Seidu Abdulai; Awortwe, Charles; Nyarko, Alexander Kwadwo

    2014-01-01

    Polyhexamethylene guanidine hydrochloride (PHMGH) is used worldwide as an antimicrobial agent with broad spectra of activity and also for treating pool water. This non-GLP preliminary study aims at investigating in a subchronic toxicity study possible effects at supra-optimal doses of this biocide. Both acute and subchronic toxicity studies were conducted. LD(50) for PHMGH was estimated to be 600 mg/kg (ie LC(50) 2 ml of 7.5% solution) when administered as a single dose by gavage via a stomach tube in accordance with the expected route of administration. The acute studies showed that the median lethal dose (LD(50)) of 600 mg/kg was accompanied by signs of neurotoxicity. Haematological and biochemical parameters of subchronic toxicity studies were non-significant. Subchronic doses of 0.006 mg/kg, 0.012 mg/kg and 0.036 mg/kg were administered. 20% of the animals at a dose of 0.006 mg/kg and 0.036 mg/kg showed mild degrees of hydropic changes in proximal tubules while 10% of animals at all the doses had their liver tissues showing local areas of mild pericentral hepatocytes degeneration. PHMGH did not produce any major organ defect with regard to the kidney, heart, and liver. The LD(50) was much higher than the recommended dosage by a factor of about 50,000. The recommended residual concentration is far less than the median lethal dose using rats as test subjects. These results could serve as a basis for investigating the full toxicological profile if it is to be used for the treatment of raw water to make it potable. © The Author(s) 2014.

  14. Discussion about risk-informed regulations on the nuclear safety

    International Nuclear Information System (INIS)

    Gu Yeyi

    2008-01-01

    The article introduces the background and status quo of regulations on the nuclear safety in China, and points out the inadequacies existing with the current regulations. The author explains the risk-informed safety management concerning its development, status quo, and achievements made, in an attempt to make out the trend of improving regulations on the nuclear safety through risk-informed methods. Combining the U.S. development program of establishing risk-informed regulations on the nuclear safety, the author narrates principles and features of the new regulations system, and provides suggestions for the promotion of risk-informed safety management and establishment of risk-informed regulations on the nuclear safety. (author)

  15. Preliminary study for unified management of CANDU safety codes and construction of database system

    International Nuclear Information System (INIS)

    Min, Byung Joo; Kim, Hyoung Tae

    2003-03-01

    It is needed to develop the Graphical User Interface(GUI) for the unified management of CANDU safety codes and to construct database system for the validation of safety codes, for which the preliminary study is done in the first stage of the present work. The input and output structures and data flow of CATHENA and PRESCON2 are investigated and the interaction of the variables between CATHENA and PRESCON2 are identified. Furthermore, PC versions of CATHENA and PRESCON2 codes are developed for the interaction of these codes and GUI(Graphic User Interface). The PC versions are assessed by comparing the calculation results with those by HP workstation or from FSAR(Final Safety Analysis Report). Preliminary study on the GUI for the safety codes in the unified management system are done. The sample of GUI programming is demonstrated preliminarily. Visual C++ is selected as the programming language for the development of GUI system. The data for Wolsong plants, reactor core, and thermal-hydraulic experiments executed in the inside and outside of the country, are collected and classified following the structure of the database system, of which two types are considered for the final web-based database system. The preliminary GUI programming for database system is demonstrated, which is updated in the future work

  16. Toward introduction of risk informed safety regulation. Nuclear Safety Commission taskforce's interim report

    International Nuclear Information System (INIS)

    2006-01-01

    Nuclear Safety Commission's taskforce on 'Introduction of Safety Regulation Utilizing Risk Information' completed the interim report on its future subjects and directions in December 2005. Although current safety regulatory activities have been based on deterministic approach, this report shows the risk informed approach is expected to be very useful for making nuclear safety regulation and assurance activities reasonable and also for appropriate allocation of regulatory resources. For introduction of risk informed regulation, it also recommends pileups of experiences with gradual introduction and trial of the risk informed approach, improvement of plant maintenance rules and regulatory requirements utilizing risk information, and establishment of framework to assure quality of risk evaluation. (T. Tanaka)

  17. Preliminary safety evaluation for 241-C-106 waste retrieval, project W-320

    International Nuclear Information System (INIS)

    Conner, J.C.

    1994-01-01

    This document presents the Preliminary Safety Evaluation for Project W-320, Tank 241-C-106 Waste Retrieval Sluicing System (WRSS). The US DOE has been mandated to develop plans for response to safety issues associated with the waste storage tanks at the Hanford Site, and to report the progress of implementing those plans to Congress. The objectives of Project W-230 are to design, fabricate, develop, test, and operate a new retrieval system capable of removing a minimum of about 75% of the high-heat waste contained in C-106. It is anticipated that sluicing operations can remove enough waste to reduce the remaining radiogenic heat load to levels low enough to resolve the high-heat safety issue as well as allow closure of the tank safety issue

  18. Preliminary Acceptance Criteria for Safety Analysis of KALIMER-600 SFR

    International Nuclear Information System (INIS)

    Kwon, Young Min; Lee, Kwi Lim; Ha, Kwi Seok; Chang, Won Pyo; Jeong, Hae Yong

    2010-01-01

    The KALIMER-600 event categorization in the function of occurrence frequency has been made by traditional engineering judgment with information from some reference plants such as CRBR, PRISM and EFR. The dividing line between DBE and BDBE is the frequency of 10 -7 per plant-year. Each event belongs to one of five categories based upon its nominal frequency per reactor-year (f) as a criterion. (1) Moderate frequency Event (MF): f ≥ 10 -1 (2) Infrequent Event (IE): 10 -1 > f ≥ 10 -2 (3) Unlikely Event (UE): 10 -2 > f ≥ 10 -4 (4) Extremely Unlikely Event (XU): 10 -4 > f ≥ 10 -7 (5) Beyond DBE (BDBE): > f ≥ 10 -4

  19. Documentation of Hanford Site independent review of the Hanford Waste Vitrification Plant Preliminary Safety Analysis Report

    International Nuclear Information System (INIS)

    Herborn, D.I.

    1993-11-01

    Westinghouse Hanford Company (WHC) is the Integrating Contractor for the Hanford Waste Vitrification Plant (HWVP) Project, and as such is responsible for preparation of the HWVP Preliminary Safety Analysis Report (PSAR). The HWVP PSAR was prepared pursuant to the requirements for safety analyses contained in US Department of Energy (DOE) Orders 4700.1, Project Management System (DOE 1987); 5480.5, Safety of Nuclear Facilities (DOE 1986a); 5481.lB, Safety Analysis and Review System (DOE 1986b) which was superseded by DOE order 5480-23, Nuclear Safety Analysis Reports, for nuclear facilities effective April 30, 1992 (DOE 1992); and 6430.lA, General Design Criteria (DOE 1989). The WHC procedures that, in large part, implement these DOE requirements are contained in WHC-CM-4-46, Nonreactor Facility Safety Analysis Manual. This manual describes the overall WHC safety analysis process in terms of requirements for safety analyses, responsibilities of the various contributing organizations, and required reviews and approvals

  20. Preliminary safety evaluation of the Gas Turbine-Modular Helium Reactor (GT-MHR)

    International Nuclear Information System (INIS)

    Dunn, T.D.; Lommers, L.J.; Tangirala, V.E.

    1994-04-01

    A qualitative comparison between the safety characteristics of the Gas Turbine-Modular Helium Reactor (GT-MHR) and those of the steam cycle shows that the two designs achieve equivalent levels of overall safety performance. This comparison is obtained by applying the scaling laws to detailed steam-cycle computations as well as the conclusions obtained from preliminary GT-MHR model simulations. The gas turbine design is predicted to be superior for some event categories, while the steam cycle design is better for others. From a safety perspective, the GT-MHR has a modest advantage for pressurized conduction cooldown events. Recent computational simulations of 102 column, 550 MW(t) GT-MHR during a depressurized conduction cooldown show that peak fuel temperatures are within the limits. The GT-MHR has a significantly lower risk due to water ingress events under operating conditions. Two additional scenarios, namely loss of load event and turbine deblading event that are specific to the GT-MHR design are discussed. Preliminary evaluation of the GT-MHR's safety characteristics indicate that the GT-MHR can be expected to satisfy or exceed its safety requirements

  1. Deep Brain Stimulation in Huntington’s Disease—Preliminary Evidence on Pathophysiology, Efficacy and Safety

    Directory of Open Access Journals (Sweden)

    Lars Wojtecki

    2016-08-01

    Full Text Available Huntington’s disease (HD is one of the most disabling degenerative movement disorders, as it not only affects the motor system but also leads to cognitive disabilities and psychiatric symptoms. Deep brain stimulation (DBS of the pallidum is a promising symptomatic treatment targeting the core motor symptom: chorea. This article gives an overview of preliminary evidence on pathophysiology, safety and efficacy of DBS in HD.

  2. Notification: Preliminary Research on EPA's Decision Making Process to Release Information Under the Freedom of Information Act

    Science.gov (United States)

    July 19, 2013. The Office of Inspector General plans to begin preliminary research on the U.S. Environmental Protection Agency’s process for deciding to release information requested under the Freedom of Information Act.

  3. The impact of health information technology on patient safety.

    Science.gov (United States)

    Alotaibi, Yasser K; Federico, Frank

    2017-12-01

    Since the original Institute of Medicine (IOM) report was published there has been an accelerated development and adoption of health information technology with varying degrees of evidence about the impact of health information technology on patient safety.  This article is intended to review the current available scientific evidence on the impact of different health information technologies on improving patient safety outcomes. We conclude that health information technology improves patient's safety by reducing medication errors, reducing adverse drug reactions, and improving compliance to practice guidelines. There should be no doubt that health information technology is an important tool for improving healthcare quality and safety. Healthcare organizations need to be selective in which technology to invest in, as literature shows that some technologies have limited evidence in improving patient safety outcomes.

  4. The impact of health information technology on patient safety

    Directory of Open Access Journals (Sweden)

    Yasser K. Alotaibi

    2017-12-01

    Full Text Available Since the original Institute of Medicine (IOM report was published there has been an accelerated development and adoption of health information technology with varying degrees of evidence about the impact of health information technology on patient safety. This article is intended to review the current available scientific evidence on the impact of different health information technologies on improving patient safety outcomes. We conclude that health information technology improves patient’s safety by reducing medication errors, reducing adverse drug reactions, and improving compliance to practice guidelines. There should be no doubt that health information technology is an important tool for improving healthcare quality and safety. Healthcare organizations need to be selective in which technology to invest in, as literature shows that some technologies have limited evidence in improving patient safety outcomes.

  5. Gas cooled fast reactor 2400 MWTh, status on the conceptual design studies and preliminary safety analysis

    International Nuclear Information System (INIS)

    Malo, J.Y.; Alpy, N.; Bentivoglio, F.

    2009-01-01

    The Gas cooled Fast Reactor (GFR) is considered by the French Commissariat a l'Energie Atomique as a promising concept, combining the benefits of fast spectrum and high temperature, using Helium as coolant. A status on the GFR preliminary viability was made at the end of 2007, ending the pre-conceptual design phase. A consistent overall systems arrangement was proposed and a preliminary safety analysis based on operating transient calculations and a simplified PSA had established a global confidence in the feasibility and safety of this baseline concept. Its potential for attractive performances had been pointed out. Compare to the more mature Sodium Fast Reactor technology, no demonstrator has ever been built and the feasibility demonstration will required a longer lead time. The next main project milestone is related to the GFR viability, scheduled in 2012. The current studies consist in revisiting the reactor reference design options as selected at the end of 2007. Most of them are being consolidated by going more in depth in the analysis. Some possible alternatives are assessed. The paper will give a status on the last studies performed on the core design and corresponding neutronics and cycle performance, the Decay Heat Removal strategy and preliminary safety analysis, systems design and balance of plant... This paper is complementary to the Icapp'09 papers 9062 dealing with the Gas cooled Fast Reactor Demonstrator ALLEGRO and 9378 related to GFR transients analysis. (author)

  6. Risk-informed analysis as a support to the preliminary design of the CEA GFR2400

    International Nuclear Information System (INIS)

    Bertrand, F.; Bassi, C.; Azria, P.; Bentivoglio, F.; Messie, A.; Balmain, M.

    2012-01-01

    The integration of safety issues in the early phase of the design of a 4. generation reactor of the concepts is expected. For this purpose, probabilistic insights are increasingly employed in the safety demonstration in combination with the deterministic approach in the frame of a so-called risk informed approach. The present paper deals with the safety assessment of the preliminary design of the GFR2400 developed by CEA and how it has been improved in order to fulfil deterministic criteria as well as to reach a risk level comparable to the generation III reactors. GFR2400 is a 2400 MWth, 3-loops, helium-cooled fast reactor developed at a pre-conceptual design stage whose secondary circuit is filled with a mixture of helium and nitrogen, the ternary circuit being filled with water vaporized in 3 steam generators according to a classical Rankine cycle. The resulting cycle efficiency is very close to 45 %. Considering the results obtained with a preliminary level 1 PSA (L1PSA) model, it emerged that an increased reliability of the DHR (Decay Heat Removal) function in high pressure conditions (not corresponding to a LOCA) was suitable to reduce the overall core damage frequency. On the other hand, some small break LOCA situations were not adequately mitigated according to the line of protection deterministic method. Both issues have been solved by design improvements. In addition, this final L1PSA model, characterized by success criteria based on transient calculations performed with the CATHARE2 code and performed in a perimeter extended to all representative internal initiating events at full operating power, permitted to propose design evolutions that did not increase significantly the CDF. In the same time, those evolutions enabled the DHR system to increase its redundancy level as required in the deterministic approach. Finally, a modified design has been reached implying a more extended covering of various accidental situations by means of a progressive DHR

  7. Food safety information and food demand

    DEFF Research Database (Denmark)

    Smed, Sinne; Jensen, Jørgen Dejgård

    2005-01-01

    Purpose – The purpose of this paper is to analyze how news about food-related health risks affects consumers’ demands for safe food products. Design/methodology/approach – By identifying structural breaks in an econometrically estimated demand model, news with permanent impact on demand...... induces a permanent increase in the demand for pasteurized eggs, while more moderate negative news influences demand temporarily and to a lesser extent. There is, however, considerable variation in the response to food safety news across socio-demographic groups of consumers. Research limitations...... is distinguished from news with temporary impact. The Danish demand for pasteurized versus shell eggs is used as an illustrative case. Findings – Negative safety news about one product variety can provide significant stimulation to the demand for safe varieties. Severe negative news about the safety of shell eggs...

  8. Improving plant state information for better operational safety

    International Nuclear Information System (INIS)

    Girard, C.; Olivier, E.; Grimaldi, X.

    1994-01-01

    Nuclear Power Plant (NPP) safety is strongly dependent on components' reliability and particularly on plant state information reliability. This information, used by the plant operators in order to produce appropriate actions, have to be of a high degree of confidence, especially in accidental conditions where safety is threatened. In this perspective, FRAMATOME, EDF and CEA have started a joint research program to prospect different solutions aiming at a better reliability for critical information needed to safety operate the plant. This paper gives the main results of this program and describes the developments that have been made in order to assess reliability of different information systems used in a Nuclear Power Plant. (Author)

  9. Conclusion of the Preliminary Safety report for the LILW Repository on Trgovska Gora

    International Nuclear Information System (INIS)

    Lokner, V.; Levanat, I.; Schaller, A.; Kucar-Dragicevic, S.; Cerskov Klika, M.; Subasic, D.

    2002-01-01

    For more than a decade, APO d.o.o. has been engaged in preparations which might lead to establishment of a radioactive waste repository on Trgovska Gora, suitable for disposal of low and intermediate level waste (LILW) from the nuclear power plant Krsko. A recent product of theses activities is the preliminary safety assessment report (PSAR) for the proposed repository. In addition to an extensive overview of the repository project status, this preliminary SAR describes how the safety assessment methodology is used to demonstrate that a LILW facility will comply with radiological protection and safety requirements after the repository closure. LILW repository is designed to isolate waste from the environment for a couple hundred years in a reasonably efficient manner. It is generally not practicable to grant full waste containment throughout that period, because it suffices to demonstrate that radionuclide release and migration will remain below acceptable levels, which is achieved through safety assessment scenarios, modeling and calculations. However, with very limited repository specific data, safety assessment can only produce a conservative estimate of the upper bounds of potential exposures the repository could inflict. This PSAR arrives at such estimates in two different ways: (a) by simple bounding calculations and (b) through more sophisticated modeling and application of dedicated computer codes, but with similar conservative assumptions. Both approaches conservatively estimate that the highest potential dose to a nearby resident cannot significantly exceed the dose constraint of 0.2 mSv per year. Only in case of inadvertent intrusion into the near-surface disposal vault, much higher doses might be inflicted immediately after the planned institutional control of 250 years expires, but that can be prevented by a longer control period. Despite the preliminary and bounding style of the calculations, the PSAR has identified most important assumptions and

  10. Mapping the nomological network of employee self-determined safety motivation: A preliminary measure in China.

    Science.gov (United States)

    Jiang, Li; Tetrick, Lois E

    2016-09-01

    The present study introduced a preliminary measure of employee safety motivation based on the definition of self-determination theory from Fleming (2012) research and validated the structure of self-determined safety motivation (SDSM) by surveying 375 employees in a Chinese high-risk organization. First, confirmatory factor analysis (CFA) was used to examine the factor structure of SDSM, and indices of five-factor model CFA met the requirements. Second, a nomological network was examined to provide evidence of the construct validity of SDSM. Beyond construct validity, the analysis also produced some interesting results concerning the relationship between leadership antecedents and safety motivation, and between safety motivation and safety behavior. Autonomous motivation was positively related to transformational leadership, negatively related to abusive supervision, and positively related to safety behavior. Controlled motivation with the exception of introjected regulation was negatively related to transformational leadership, positively related to abusive supervision, and negatively related to safety behavior. The unique role of introjected regulation and future research based on self-determination theory were discussed. Copyright © 2016 Elsevier Ltd. All rights reserved.

  11. A Value Function Approach to Information Operations MOE's: A Preliminary Study

    National Research Council Canada - National Science Library

    Doyle, Michael

    1997-01-01

    A value focused thinking approach is applied to information operations. A preliminary value hierarchy for information operations is constructed by extracting the values of senior military leadership from existing doctrine...

  12. Development of Safety Assessment Information System (SAIS)

    Energy Technology Data Exchange (ETDEWEB)

    Park, Byung Shik; Lee, Kyung Jin; Lee, Byung Chul [FNC Tech. Co. Ltd. SNU, Seoul (Korea, Republic of); Song, Tae Young; Lee, Chang Ho [KHNP, Daejeon (Korea, Republic of)

    2007-10-15

    Many reports and documents about nuclear power plant safety analysis like a Periodic Safe Review (PSR), Periodic Safety Analysis (PSA) and Severe Accident Management Guideline (SAMG) come to be drawn up from KHNP. Since these are not arranged easy to look up, the systematic arrangement of data was necessary. The solution against hereupon is to store database, and it was developed with the name, SAIS, by FNC Tech. Co. together with NETEC KHNP. In this web program it is easy to manage (registration, search and statistics) data. And the authorized user can approach this system. This was developed, and was verified under the development environment of; - Web Server : Apache 2.2.5 - Program Language : PHP 5.2 - DBMS : Oracle 10g.

  13. Development of Safety Assessment Information System (SAIS)

    International Nuclear Information System (INIS)

    Park, Byung Shik; Lee, Kyung Jin; Lee, Byung Chul; Song, Tae Young; Lee, Chang Ho

    2007-01-01

    Many reports and documents about nuclear power plant safety analysis like a Periodic Safe Review (PSR), Periodic Safety Analysis (PSA) and Severe Accident Management Guideline (SAMG) come to be drawn up from KHNP. Since these are not arranged easy to look up, the systematic arrangement of data was necessary. The solution against hereupon is to store database, and it was developed with the name, SAIS, by FNC Tech. Co. together with NETEC KHNP. In this web program it is easy to manage (registration, search and statistics) data. And the authorized user can approach this system. This was developed, and was verified under the development environment of; - Web Server : Apache 2.2.5 - Program Language : PHP 5.2 - DBMS : Oracle 10g

  14. HACCP and water safety plans in Icelandic water supply: preliminary evaluation of experience.

    Science.gov (United States)

    Gunnarsdóttir, María J; Gissurarson, Loftur R

    2008-09-01

    Icelandic waterworks first began implementing hazard analysis and critical control points (HACCP) as a preventive approach for water safety management in 1997. Since then implementation has been ongoing and currently about 68% of the Icelandic population enjoy drinking water from waterworks with a water safety plan based on HACCP. Preliminary evaluation of the success of HACCP implementation was undertaken in association with some of the waterworks that had implemented HACCP. The evaluation revealed that compliance with drinking water quality standards improved considerably following the implementation of HACCP. In response to their findings, waterworks implemented a large number of corrective actions to improve water safety. The study revealed some limitations for some, but not all, waterworks in relation to inadequate external and internal auditing and a lack of oversight by health authorities. Future studies should entail a more comprehensive study of the experience with the use of HACCP with the purpose of developing tools to promote continuing success.

  15. European passive plant program preliminary safety analyses to support system design

    International Nuclear Information System (INIS)

    Saiu, Gianfranco; Barucca, Luciana; King, K.J.

    1999-01-01

    In 1994, a group of European Utilities, together with Westinghouse and its Industrial Partner GENESI (an Italian consortium including ANSALDO and FIAT), initiated a program designated EPP (European Passive Plant) to evaluate Westinghouse Passive Nuclear Plant Technology for application in Europe. In the Phase 1 of the European Passive Plant Program which was completed in 1996, a 1000 MWe passive plant reference design (EP1000) was established which conforms to the European Utility Requirements (EUR) and is expected to meet the European Safety Authorities requirements. Phase 2 of the program was initiated in 1997 with the objective of developing the Nuclear Island design details and performing supporting analyses to start development of Safety Case Report (SCR) for submittal to European Licensing Authorities. The first part of Phase 2, 'Design Definition' phase (Phase 2A) was completed at the end of 1998, the main efforts being design definition of key systems and structures, development of the Nuclear Island layout, and performing preliminary safety analyses to support design efforts. Incorporation of the EUR has been a key design requirement for the EP1000 form the beginning of the program. Detailed design solutions to meet the EUR have been defined and the safety approach has also been developed based on the EUR guidelines. The present paper describes the EP1000 approach to safety analysis and, in particular, to the Design Extension Conditions that, according to the EUR, represent the preferred method for giving consideration to the Complex Sequences and Severe Accidents at the design stage without including them in the design bases conditions. Preliminary results of some DEC analyses and an overview of the probabilistic safety assessment (PSA) are also presented. (author)

  16. Safety evaluation report related to the preliminary design of the Standard Reference System, RESAR-414

    International Nuclear Information System (INIS)

    1978-11-01

    The safety evaluation for the Westinghouse Standard Reactor includes information on general reactor characteristics; design criteria for systems and components; reactor coolant system; engineered safety systems; instrumentation and controls; electric power systems; auxiliary systems; steam and power conversion system; radioactive waste management; radiation protection; conduct of operations; accident analyses; and quality assurance

  17. Preliminary safety assessment study for the conceptual design of a repository in tuff at Yucca Mountain

    International Nuclear Information System (INIS)

    Jackson, J.L.; Gram, H.F.; Hong, K.J.; Ng, H.S.; Pendergrass, A.M.

    1984-12-01

    Preliminary estimates of the upper bounds on postulated worst-case radiological releases resulting from possible accidents during the operating period of a prospective repository in tuff at Yucca Mountain are presented. Possible disrupting events are screened to identify the accidents of greatest potential consequence. The radiological dose commitments for the general public and repository personnel are estimated for postulated releases caused by natural phenomena, man-made events, and operational accidents. All postulated worst-case releases result in doses to the public that are lower than the 0.5-rem, whole-body dose-per-accident limit set by the Nuclear Regulatory Commission (NRC) in 10 CFR 60. Doses to repository personnel are within the NRC's 5.0-rem/yr occupational exposure limit set in 10 CFR 20 for normal operations. Doses are within this limit for all accidents except the transportation accident and fire in a drift. A preliminary risk assessment has also been performed. Based on this preliminary safety study, the proposed site boundaries and design criteria routinely used in constructing nuclear facilities appear to be adequate to protect the safety of the general public during the operating phase of the repository

  18. Development of the Advanced Nuclear Safety Information Management (ANSIM) System

    Energy Technology Data Exchange (ETDEWEB)

    Sohn, Jae Min; Ko, Young Cheol; Song, Tai Gil [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2012-05-15

    Korea has become a technically independent nuclear country and has grown into an exporter of nuclear technologies. Thus, nuclear facilities are increasing in significance at KAERI (Korea Atomic Energy Research Institute), and it is time to address the nuclear safety. The importance of nuclear safety cannot be overemphasized. Therefore, a management system is needed urgently to manage the safety of nuclear facilities and to enhance the efficiency of nuclear information. We have established ISP (Information Strategy Planning) for the Integrated Information System of nuclear facility and safety management. The purpose of this paper is to develop a management system for nuclear safety. Therefore, we developed the Advanced Nuclear Safety Information Management system (hereinafter referred to as the 'ANSIM system'). The ANSIM system has been designed and implemented to computerize nuclear safety information for standardization, integration, and sharing in real-time. Figure 1 shows the main home page of the ANSIM system. In this paper, we describe the design requirements, contents, configurations, and utilizations of the ANSIM system

  19. Food Safety and Nutrition Information for Kids and Teens

    Science.gov (United States)

    ... Vaccines, Blood & Biologics Animal & Veterinary Cosmetics Tobacco Products Food Home Food Resources for You Consumers Kids & Teens ... More sharing options Linkedin Pin it Email Print Food Safety & Nutrition Information for Kids and Teens Fun & ...

  20. A Survey of Pilots on the Dissemination of Safety Information

    National Research Council Canada - National Science Library

    Rakovan, Lori

    1999-01-01

    A survey was conducted to obtain information from the pilot population on erections of safety-related training currently being offered, its usefulness, and the process through which it might be better...

  1. Risk-informed, performance-based safety-security interface

    International Nuclear Information System (INIS)

    Mrowca, B.; Eltawila, F.

    2012-01-01

    Safety-security interface is a term that is used as part of the commercial nuclear power security framework to promote coordination of the many potentially adverse interactions between plant security and plant safety. Its object is to prevent the compromise of either. It is also used to describe the concept of building security into a plant's design similar to the long standing practices used for safety therefore reducing the complexity of the operational security while maintaining or enhancing overall security. With this in mind, the concept of safety-security interface, when fully implemented, can influence a plant's design, operation and maintenance. It brings the approach use for plant security to one that is similar to that used for safety. Also, as with safety, the application of risk-informed techniques to fully implement and integrate safety and security is important. Just as designers and operators have applied these techniques to enhance and focus safety, these same techniques can be applied to security to not only enhance and focus the security but also to aid in the implementation of effective techniques to address the safety-security interfaces. Implementing this safety-security concept early within the design process can prevent or reduce security vulnerabilities through low cost solutions that often become difficult and expensive to retrofit later in the design and/or post construction period. These security considerations address many of the same issues as safety in ensuring that the response of equipment and plant personnel are adequate. That is, both safety and security are focused on reaching safe shutdown and preventing radiological release. However, the initiation of challenges and the progression of actions in response these challenges and even the definitions of safe shutdown can be considerably different. This paper explores the techniques and limitations that are employed to fully implement a risk-informed, safety-security interface

  2. Transactions of the Twentieth Water Reactor Safety Information Meeting

    International Nuclear Information System (INIS)

    Weiss, A.J.

    1992-10-01

    This report contains summaries of papers on reactor safety research to be presented at the 20th Water Reactor Safety Information Meeting at the Bethesda Marriott Hotel in Bethesda, Maryland, October 21--23, 1992. The summaries briefly describe the programs and results of nuclear safety research sponsored by the Office of Nuclear Regulatory Research, USNRC. Summaries of invited papers concerning nuclear safety issues from US government laboratories, the electric utilities, the Electric Power Research Institute (EPRI), the nuclear industry, and from foreign governments and industry are also included

  3. Preliminary report on safety aspects on nuclear power generation in Sri Lanka

    International Nuclear Information System (INIS)

    Jayamanne, D.; Fernando, W.L.W.; Ariyadasa

    1988-01-01

    This document is intended as background information on nuclear energy to contribute to Sri Lanka's comparative study of alternative sources of energy. This study has considered the safety and environmental effects of nuclear power reactors. Basic concepts of nuclear physics are introduced and providing and appreciation of safety considerations and safety aspects of nuclear power plants and the personnel. Radioactive waste management, storage and disposal are also discussed. Natural radiation levels in Sri Lanka are provided as well as information on biological effects of radiation especially occupational exposure licensing procedures for nuclear power plants are outlined strategy for public awareness of nuclear power is proposed

  4. Preliminary Safety Analysis Report for the Transuranic Storage Area Retrieval Enclosure at the Idaho National Engineering Laboratory

    International Nuclear Information System (INIS)

    1993-03-01

    This Transuranic Storage Area Retrieval Enclosure Preliminary Safety Analysis Report was completed as required by DOE Order 5480.23. The purpose of this document is to construct a safety basis that supports the design and permits construction of the facility. The facility has been designed to the requirements of a Radioactive Solid Waste Facility presented in DOE Order 6430.1A

  5. Preliminary Performance Analysis Program Development for Safety System with Safeguard Vessel

    International Nuclear Information System (INIS)

    Kang, Han-Ok; Lee, Jun; Park, Cheon-Tae; Yoon, Ju-Hyeon; Park, Keun-Bae

    2007-01-01

    SMART is an advanced modular integral type pressurized water reactor for a seawater desalination and an electricity production. Major components of the reactor coolant system such as the pressurizer, Reactor Coolant Pump (RCP), and steam generators are located inside the reactor vessel. The SMART can fundamentally eliminate the possibility of large break loss of coolant accidents (LBLOCAs), improve the natural circulation capability, and better accommodate and thus enhance a resistance to a wide range of transients and accidents. The safety goals of the SMART are enhanced through highly reliable safety systems such as the passive residual heat removal system (PRHRS) and the safeguard vessel coupled with the passive safety injection feature. The safeguard vessel is a steel-made, leak-tight pressure vessel housing the RPV, SIT, and the associated valves and pipelines. A primary function of the safeguard vessel is to confine any radioactive release from the primary circuit within the vessel under DBAs related to loss of the integrity of the primary system. A preliminary performance analysis program for a safety system using the safeguard vessel is developed in this study. The developed program is composed of several subroutines for the reactor coolant system, passive safety injection system, safeguard vessel including the pressure suppression pool, and PRHRS. A small break loss of coolant accident at the upper part of a reactor is analyzed and the results are discussed

  6. Geoscientific long-term prognosis. Preliminary safety analysis for the site Gorleben

    International Nuclear Information System (INIS)

    Mrugalla, Sabine

    2011-07-01

    The preliminary safety analysis of the site Gorleben includes the following chapters: (1) Introduction; (2) Aim and content of the geoscientific long-term prognosis for the site Gorleben; (3) Boundary conditions at the site Gorleben: climate; geomorphology; overlying rocks and adjoining rocks; hydrogeology; salt deposit Gorleben. (4) Probable future geological developments at the site Gorleben: supraregional developments with effects on the site Gorleben; glacial period developments; developments of the geomorphology, overlying and adjoining rocks; future developments of the hydrological systems at the site Gorleben; future saliniferous specific developments of the salt deposit Gorleben. (5) Commentary on the unlikely or excludable developments of the site Gorleben.

  7. Atomic Information Technology Safety and Economy of Nuclear Power Plants

    CERN Document Server

    Woo, Taeho

    2012-01-01

    Atomic Information Technology revaluates current conceptions of the information technology aspects of the nuclear industry. Economic and safety research in the nuclear energy sector are explored, considering statistical methods which incorporate Monte-Carlo simulations for practical applications. Divided into three sections, Atomic Information Technology covers: • Atomic economics and management, • Atomic safety and reliability, and • Atomic safeguarding and security. Either as a standalone volume or as a companion to conventional nuclear safety and reliability books, Atomic Information Technology acts as a concise and thorough reference on statistical assessment technology in the nuclear industry. Students and industry professionals alike will find this a key tool in expanding and updating their understanding of this industry and the applications of information technology within it.

  8. Information safety by suppression of chaos

    Energy Technology Data Exchange (ETDEWEB)

    Loskutov, A; Churaev, A A [Physics Faculty, Moscow State University, Moscow 119899 (Russian Federation)

    2005-01-01

    A new original method of information processing and secure communications based on the coding of alphabet symbols by stabilized cycles of certain perturbed one-dimensional dynamical systems is proposed. The foundation of the proposed method is ciphering by the one-to-one correspondence between periods of such cycles and certain alphabet symbols. It is shown that for some maps perturbations which lead to the stabilization of cycles of the given period, form some domain in the parametric space. This fact is used for coding identical symbols via random selection of parameters from this domain, that ensures that the probability of decoding the transmitting information by an external observer is zero. Analytic estimations of the admissible noise level in the communication channel and the randomness degree of transmitting signals are made. Some variants of the ciphered sequences are presented.

  9. Preliminary safety evaluation, based on initial site investigation data. Planning document

    International Nuclear Information System (INIS)

    Hedin, Allan

    2002-12-01

    This report is a planning document for the preliminary safety evaluations (PSE) to be carried out at the end of the initial stage of SKBs ongoing site investigations for a deep repository for spent nuclear fuel. The main purposes of the evaluations are to determine whether earlier judgements of the suitability of the candidate area for a deep repository with respect to long-term safety holds up in the light of borehole data and to provide feed-back to continued site investigations and site specific repository design. The preliminary safety evaluations will be carried out by a safety assessment group, based on a site model, being part of a site description, provided by a site modelling group and a repository layout within that model suggested by a repository engineering group. The site model contains the geometric features of the site as well as properties of the host rock. Several alternative interpretations of the site data will likely be suggested. Also the biosphere is included in the site model. A first task for the PSE will be to compare the rock properties described in the site model to previously established criteria for a suitable host rock. This report gives an example of such a comparison. In order to provide more detailed feedback, a number of thermal, hydrological, mechanical and chemical analyses of the site will also be included in the evaluation. The selection of analyses is derived from the set of geosphere and biosphere analyses preliminarily planned for the comprehensive safety assessment named SR-SITE, which will be based on a complete site investigation. The selection is dictated primarily by the expected feedback to continued site investigations and by the availability of data after the PSE. The repository engineering group will consider several safety related factors in suggesting a repository layout: Thermal calculations will be made to determine a minimum distance between canisters avoiding canister surface temperatures above 100 deg C

  10. Value of Information Analysis in Structural Safety

    DEFF Research Database (Denmark)

    Konakli, Katerina; Faber, Michael Havbro

    2014-01-01

    of structural systems. In this context, experiments may refer to inspections or techniques of structural health monitoring. The Value of Information concept provides a powerful tool for determining whether the experimental cost is justified by the expected benefit and for identifying the optimal among different...... possible experimental schemes. This concept is elaborated through principal examples for structural components and system models. Sensitivity analyses are performed to investigate how the decision problem is influenced by the level of uncertainty that characterizes the structural properties, the amount...

  11. Customer Relationship Management System in Occupational Safety & Health Companies: Research on Practice and Preliminary Design Solution

    Directory of Open Access Journals (Sweden)

    Robert Fabac

    2011-10-01

    Full Text Available One of the most prominent contemporary trends in formation of companies is the approach to development of a customer-oriented company. In this matter, various versions related to the intensity of this orientation are differentiated. Customer relationship management (CRM system is a well-known concept, and its practice is being studied and improved in connection to various sectors. Companies providing services of occupational safety and health (OHS mainly cooperate with a large number of customers and the quality of this cooperation largely affects the occupational safety and health of employees. Therefore, it is of both scientific and wider social interest to study and improve the relationship of these companies with their customers. This paper investigates the practice of applying CRM in Croatian OHS companies. It identifies the existing conditions and suggests possible improvements in the practice of CRM, based on experts’ assessments using analytic hierarchy process evaluation. Universal preliminary design was created as a framework concept for the formation of a typical customer-oriented OHS services company. Preliminary design includes a structural view, which provides more details through system diagrams, and an illustration of main cooperation processes of a company with its customer.

  12. Safety recommendation component of mobile information assistant of the tourist

    Science.gov (United States)

    Savchuk, Valeriya V.; Kunanec, Natalia E.; Pasichnyk, Volodymyr V.; Popiel, Piotr; Weryńska-Bieniasz, RóŻa; Kashaganova, Gulzhamal; Kalizhanova, Aliya

    2017-08-01

    The goal of article is to introduce and justify the need for the safety system components of Mobile Information of the tourist (MIAT). One of the objectives of the system is to determine the level of risk in a particular tourist destination on the basis of available information in the knowledge base.

  13. Keeping rail on track: preliminary findings on safety culture in Australian rail.

    Science.gov (United States)

    Blewett, Verna; Rainbird, Sophia; Dorrian, Jill; Paterson, Jessica; Cattani, Marcus

    2012-01-01

    'Safety culture' is identified in the literature as a critical element of healthy and safe workplaces. How can rail organizations ensure that consistently effective work health and safety cultures are maintained across the diversity of their operations? This paper reports on research that is currently underway in the Australian rail industry aimed at producing a Model of Best Practice in Safety Culture for the industry. Located in rail organizations dedicated to the mining industry as well as urban rail and national freight operations, the research examines the constructs of organizational culture that impact on the development and maintenance of healthy and safe workplaces. The research uses a multi-method approach incorporating quantitative (survey) and qualitative (focus groups, interviews and document analysis) methods along with a participative process to identify interventions to improve the organization and develop plans for their implementation. The research uses as its analytical framework the 10 Platinum Rules, from the findings of earlier research in the New South Wales (Australia) mining industry, Digging Deeper. Data collection is underway at the time of writing and preliminary findings are presented at this stage. The research method may be adapted for use as a form of organizational review of safety and health in organizational culture.

  14. Information about the control of nuclear safety in France

    International Nuclear Information System (INIS)

    Gerster, D.

    1994-01-01

    The permanent objective of the French Nuclear Safety Authority is the public information about technical controls performed in French nuclear installations. Three publications from the DSIN (Direction of Nuclear Installations Safety) are devoted to this effort: the MAGNUC Minitel magazine, the annual activity report and the CONTROLE magazine. Details about the content of these publications are given. A large part of the information about control of nuclear safety concerns the incidents and accidents and their importance level. A seriousness scale was created in France at the beginning of 1988 and replaced in April 1994 by the very similar International Nuclear Event Scale (INES). Explanation of this scale is given and illustrated with examples of real events and accidents. However, international comparison between incidents and accidents remains delicate because the detailed content of safety reports can change significantly from one country to another. (J.S.). 1 fig

  15. Transactions of the nineteenth water reactor safety information meeting

    International Nuclear Information System (INIS)

    Weiss, A.J.

    1991-10-01

    This report contains summaries of papers on reactor safety research to be presented at the 19th Water Reactor Safety Information Meeting at the Bethesda Marriott Hotel in Bethesda, Maryland, October 28--30, 1991. The summaries briefly describe the programs and results of nuclear safety research sponsored by the Office of Nuclear Regulatory Research, USNRC. Summaries of invited papers concerning nuclear safety issues from US government laboratories, the electric utilities, the Electric Power Research Institute (EPRI), the nuclear industry, and from the governments and industry in Europe and Japan are also included. The summaries have been compiled in one report to provide a basis for meaningful discussion and information exchange during the course of the meeting, and are given in the order of their presentation in each session. The individual summaries have been cataloged separately

  16. Preliminary Results Obtained in Integrated Safety Analysis of NASA Aviation Safety Program Technologies

    Science.gov (United States)

    2005-01-01

    This is a listing of recent unclassified RTO technical publications for January 1, 2005 through March 31, 2005 processed by the NASA Center for AeroSpace Center available on the NASA Aeronautics and Space Database. Contents include 1) Electronic Information Management; 2) Decision Support to Combined Joint Task Force and Component Commanders; 3) RTO Technical Publications : A Quarterly Listing (December 2004); 4) The Role of Humans in Intelligent and Automated Systems.

  17. Information security as part of the nuclear safety culture

    Energy Technology Data Exchange (ETDEWEB)

    Sitnica, A., E-mail: demetrkj@westinghouse.com [Westinghouse Electric Co., 1000 Westinghouse Drive, Cranberry Township, PA 16066 (United States)

    2016-09-15

    No industry, organization, individual or even the government is immune to the information security risks which are associated with nuclear power. It can no longer be ignored, delayed or treated as unimportant. Nuclear safety is paramount to our industry, and cyber security must be woven into the fabric of our safety culture in order to succeed. Achieving this in an environment which has remained relatively unchanged and conservative prior to digitalisation demands a shift in behavior and culture. (Author)

  18. Information security as part of the nuclear safety culture

    International Nuclear Information System (INIS)

    Sitnica, A.

    2016-09-01

    No industry, organization, individual or even the government is immune to the information security risks which are associated with nuclear power. It can no longer be ignored, delayed or treated as unimportant. Nuclear safety is paramount to our industry, and cyber security must be woven into the fabric of our safety culture in order to succeed. Achieving this in an environment which has remained relatively unchanged and conservative prior to digitalisation demands a shift in behavior and culture. (Author)

  19. A participatory model for improving occupational health and safety: improving informal sector working conditions in Thailand.

    Science.gov (United States)

    Manothum, Aniruth; Rukijkanpanich, Jittra; Thawesaengskulthai, Damrong; Thampitakkul, Boonwa; Chaikittiporn, Chalermchai; Arphorn, Sara

    2009-01-01

    The purpose of this study was to evaluate the implementation of an Occupational Health and Safety Management Model for informal sector workers in Thailand. The studied model was characterized by participatory approaches to preliminary assessment, observation of informal business practices, group discussion and participation, and the use of environmental measurements and samples. This model consisted of four processes: capacity building, risk analysis, problem solving, and monitoring and control. The participants consisted of four local labor groups from different regions, including wood carving, hand-weaving, artificial flower making, and batik processing workers. The results demonstrated that, as a result of applying the model, the working conditions of the informal sector workers had improved to meet necessary standards. This model encouraged the use of local networks, which led to cooperation within the groups to create appropriate technologies to solve their problems. The authors suggest that this model could effectively be applied elsewhere to improve informal sector working conditions on a broader scale.

  20. Preliminary safety evaluation of an aircraft impact on a near-surface radioactive waste repository

    Energy Technology Data Exchange (ETDEWEB)

    Lo Frano, R.; Forasassi, G.; Pugliese, G. [Department of Industrial and Civil Engineering (DICI), University of Pisa, Pisa (Italy)

    2013-07-01

    The aircraft impact accident has become very significant in the design of a nuclear facilities, particularly, after the tragic September 2001 event, that raised the public concern about the potential damaging effects that the impact of a large civilian airplane could bring in safety relevant structures. The aim of this study is therefore to preliminarily evaluate the global response and the structural effects induced by the impact of a military or commercial airplane (actually considered as a 'beyond design basis' event) into a near surface radioactive waste (RWs) disposal facility. The safety evaluation was carried out according to the International safety and design guidelines and in agreement with the stress tests requirements for the security track. To achieve the purpose, a lay out and a scheme of a possible near surface repository, like for example those of the El Cabril one, were taken into account. In order to preliminarily perform a reliable analysis of such a large-scale structure and to determine the structural effects induced by such a types of impulsive loads, a realistic, but still operable, numerical model with suitable materials characteristics was implemented by means of FEM codes. In the carried out structural analyses, the RWs repository was considered a 'robust' target, due to its thicker walls and main constitutive materials (steel and reinforced concrete). In addition to adequately represent the dynamic response of repository under crashing, relevant physical phenomena (i.e. penetration, spalling, etc.) were simulated and analysed. The preliminary assessment of the effects induced by the dynamic/impulsive loads allowed generally to verify the residual strength capability of the repository considered. The obtained preliminary results highlighted a remarkable potential to withstand the impact of military/large commercial aircraft, even in presence of ongoing concrete progressive failure (some penetration and spalling of the

  1. Patient safety goals for the proposed Federal Health Information Technology Safety Center.

    Science.gov (United States)

    Sittig, Dean F; Classen, David C; Singh, Hardeep

    2015-03-01

    The Office of the National Coordinator for Health Information Technology is expected to oversee creation of a Health Information Technology (HIT) Safety Center. While its functions are still being defined, the center is envisioned as a public-private entity focusing on promotion of HIT related patient safety. We propose that the HIT Safety Center leverages its unique position to work with key administrative and policy stakeholders, healthcare organizations (HCOs), and HIT vendors to achieve four goals: (1) facilitate creation of a nationwide 'post-marketing' surveillance system to monitor HIT related safety events; (2) develop methods and governance structures to support investigation of major HIT related safety events; (3) create the infrastructure and methods needed to carry out random assessments of HIT related safety in complex HCOs; and (4) advocate for HIT safety with government and private entities. The convening ability of a federally supported HIT Safety Center could be critically important to our transformation to a safe and effective HIT enabled healthcare system. © The Author 2014. Published by Oxford University Press on behalf of the American Medical Informatics Association. All rights reserved. For Permissions, please email: journals.permissions@oup.com.

  2. Organizing safety: conditions for successful information assurance programs.

    Science.gov (United States)

    Collmann, Jeff; Coleman, Johnathan; Sostrom, Kristen; Wright, Willie

    2004-01-01

    Organizations must continuously seek safety. When considering computerized health information systems, "safety" includes protecting the integrity, confidentiality, and availability of information assets such as patient information, key components of the technical information system, and critical personnel. "High Reliability Theory" (HRT) argues that organizations with strong leadership support, continuous training, redundant safety mechanisms, and "cultures of high reliability" can deploy and safely manage complex, risky technologies such as nuclear weapons systems or computerized health information systems. In preparation for the Health Insurance Portability and Accountability Act (HIPAA) of 1996, the Office of the Assistant Secretary of Defense (Health Affairs), the Offices of the Surgeons General of the United States Army, Navy and Air Force, and the Telemedicine and Advanced Technology Research Center (TATRC), US Army Medical Research and Materiel Command sponsored organizational, doctrinal, and technical projects that individually and collectively promote conditions for a "culture of information assurance." These efforts include sponsoring the "P3 Working Group" (P3WG), an interdisciplinary, tri-service taskforce that reviewed all relevant Department of Defense (DoD), Miliary Health System (MHS), Army, Navy and Air Force policies for compliance with the HIPAA medical privacy and data security regulations; supporting development, training, and deployment of OCTAVE(sm), a self-directed information security risk assessment process; and sponsoring development of the Risk Information Management Resource (RIMR), a Web-enabled enterprise portal about health information assurance.

  3. A Preliminary Investigation into the Information Sharing Behavior of Social Media Users after a Natural Disaster

    Science.gov (United States)

    Maruyama, Yukiko

    2016-01-01

    The paper provides the results of a preliminary investigation into the information sharing behavior of social media users after a natural disaster. The results indicate that users shared information that they thought victims would find useful. On the other hand, they reported that they usually do not or never share information considered useful to…

  4. Application of life-cycle information for advancement in safety of nuclear fuel cycle facilities. Application of safety information to advanced safety management support system

    International Nuclear Information System (INIS)

    Suzuki, Kazuhiko; Ishida, Michihiko

    2005-08-01

    Risk management is major concern to nuclear energy reprocessing plants to improve plant and process reliability and ensure their safety. This is because we are required to predict potential risks before any accident or disaster occurs. The advancement of safety design and safety systems technologies showed large amount of useful safety-related knowledge that can be of great importance to plant operation to reduce operation risks and ensure safety. This research proposes safety knowledge modeling framework on the basis of ontology technologies to systematically construct plant knowledge model, which includes plant structure, operation, and the associated behaviors. In such plant knowledge model safety related information is defined and linked to the different elements of plant knowledge model. Ontology editor is employed to define the basic concepts and their inter-relations, which are used to capture and construct plant safety knowledge. In order to provide detailed safety knowledgebase, HAZOP results are analyzed and structured so that safety-related knowledge are identified and structured within the plant knowledgebase. The target safety knowledgebase includes: failures, deviations, causes, consequences, and fault propagation as mapped to plant knowledge. The proposed ontology-based safety framework is applied on case study nuclear plant to structure failures, causes, consequences, and fault propagation, which are used to support plant operation. (author)

  5. Use of risk information to safety regulation. Fabrication facilities

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2013-08-15

    A procedure of ISA (Integrated Safety Analysis) for uranium fuel fabrication/enrichment facilities has been under the development aiming to utilize risk information for safety regulations in this project. Activities in the fiscal year 2012 are summarized in the paper. There are two major activities in the year. First one is a study on ISA procedure for external events such as earthquakes. Second one is that for chemical consequences such as UF6 and HF. Other than the activities a fundamental study on a policy of utilizing risk information was conducted. The outline and results are provided in the chapter 1 and 2 respectively. (author)

  6. Developing a disaster education program for community safety and resilience: The preliminary phase

    Science.gov (United States)

    Nifa, Faizatul Akmar Abdul; Abbas, Sharima Ruwaida; Lin, Chong Khai; Othman, Siti Norezam

    2017-10-01

    Resilience encompasses both the principles of preparedness and reaction within the dynamic systems and focuses responses on bridging the gap between pre-disaster activities and post-disaster intervention and among structural/non-structural mitigation. Central to this concept is the ability of the affected communities to recover their livelihood and inculcating necessary safety practices during the disaster and after the disaster strikes. While these ability and practices are important to improve the community safety and resilience, such factors will not be effective unless the awareness is present among the community. There have been studies conducted highlighting the role of education in providing awareness for disaster safety and resilience from a very young age. However for Malaysia, these area of research has not been fully explored and developed based on the specific situational and geographical factors of high-risk flood disaster locations. This paper explores the importance of disaster education program in Malaysia and develops into preliminary research project which primary aim is to design a flood disaster education pilot program in Kampung Karangan Primary School, Kelantan, Malaysia.

  7. Providing public information in the Slovenian Nuclear Safety Administration

    International Nuclear Information System (INIS)

    Fon Jager, Mojca

    2000-01-01

    Full text: Good safety culture is strongly related to transparent and timely information. Experience has shown that radiation and nuclear safety are under continuous surveillance by the public. The provision of open and authentic information to the public is a fundamental policy of the SNSA. The SNSA endeavors to provide substantial and reliable information to the interested institutions, mass media and to the citizens through press conferences, public statements, media discussions, and active participation in domestic and international meetings, symposia and congresses, through publications, the Internet and direct contacts with the interested public. The SNSA regularly provides information on nuclear safety to the Government, the National Assembly and the citizens of the Republic of Slovenia. The Annual Report on Nuclear and Radiation Safety is published in Poroeevalec (Reporter) - the publication of the National Assembly - in autumn, and is available in public libraries throughout Slovenia. Annual Report is available also on the Internet (http://www.sigov.si/ursjv/uvod.html) in Slovene and English. Access to data of the Central Radiation Early Warning System of Slovenia (CROSS), recording the real time (at half-hour intervals) gamma dose rate levels, is also available through Internet. The report in English is sent every year to Slovenian embassies world-wide, to certain foreign embassies in Slovenia and to other organizations participating in the activities in the nuclear and radiological field. Reports on the SNSA activities are also published in the bulletin Okolje in prostor (Environment and Spatial Planning), published by the Ministry of Environment and Spatial Planning. The SNSA regularly contributes articles on courses, seminars and symposia attended at home and abroad. The articles are intended to give basic information on training and the names of contact persons to provide additional information on certain topics to those interested. More than half of

  8. A preliminary study of current multimedia information technology

    Energy Technology Data Exchange (ETDEWEB)

    Lee, J.C.

    1997-03-01

    This paper surveys more than 70 articles published in the IEEE Multimedia journal and other journals. The survey summarizes aspects of multimedia information technology and categorizes application areas of multimedia information technology and interesting research areas related to it.

  9. Freedom of Information Requests Survey (FIRS) : Preliminary Results

    OpenAIRE

    Dowding, Martin; Murray, Frederic; Saunders, Jeremiah

    2006-01-01

    At the request of the BC Freedom of Information and Privacy Association (FIPA), Dr. Martin Dowding, Assistant Professor at the School of Library, Archival and Information Studies (SLAIS), University of British Columbia recruited and supervised Jeremiah Saunders and Frederic Murray, MLIS candidates, to design and conduct a survey in 2005-2006 that would measure the process of and satisfaction with making a freedom of information request for public information through British Columbia's Freedom...

  10. Safety Psychology Applicating on Coal Mine Safety Management Based on Information System

    Science.gov (United States)

    Hou, Baoyue; Chen, Fei

    In recent years, with the increase of intensity of coal mining, a great number of major accidents happen frequently, the reason mostly due to human factors, but human's unsafely behavior are affected by insecurity mental control. In order to reduce accidents, and to improve safety management, with the help of application security psychology, we analyse the cause of insecurity psychological factors from human perception, from personality development, from motivation incentive, from reward and punishment mechanism, and from security aspects of mental training , and put forward countermeasures to promote coal mine safety production,and to provide information for coal mining to improve the level of safety management.

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

    International Nuclear Information System (INIS)

    Weiss, A.J.

    1986-02-01

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

  12. Los Alamos National Laboratory corregated metal pipe saw facility preliminary safety analysis report. Volume I

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1990-09-19

    This Preliminary Safety Analysis Report addresses site assessment, facility design and construction, and design operation of the processing systems in the Corrugated Metal Pipe Saw Facility with respect to normal and abnormal conditions. Potential hazards are identified, credible accidents relative to the operation of the facility and the process systems are analyzed, and the consequences of postulated accidents are presented. The risk associated with normal operations, abnormal operations, and natural phenomena are analyzed. The accident analysis presented shows that the impact of the facility will be acceptable for all foreseeable normal and abnormal conditions of operation. Specifically, under normal conditions the facility will have impacts within the limits posted by applicable DOE guidelines, and in accident conditions the facility will similarly meet or exceed the requirements of all applicable standards. 16 figs., 6 tabs.

  13. Preliminary safety criteria for organic watch list tanks at the Hanford site

    International Nuclear Information System (INIS)

    Webb, A.B.; Stewart, J.L.; Turner, O.A.; Plys, M.G.; Malinovic, B.; Grigsby, J.M.; Camaioni, D.M.; Heasler, P.G.; Samuels, W.O.; Toth, J.J.

    1995-11-01

    Condensed-phase, rapid reactions of organic salts with nitrates/nitrites in Hanford High Level Radioactive Waste single-shell tanks could lead to structural failure of the tanks resulting in significant releases of radionuclides and toxic materials. This report establishes appropriate preliminary safety criteria to ensure that tank wastes will be maintained safe. These criteria show that if actual dry wastes contain less than 1.2 MJ/kg of reactants reaction energy or less 4.5 wt % of total organic carbon, then the waste will be safe and will not propagate if ignited. Waste moisture helps to retard reactions; when waste moisture exceeds 20 wt %, rapid reactions are prevented, regardless of organic carbon concentrations. Aging and degradation of waste materials has been considered to predict the types and amounts to organic compounds present in the waste. Using measurements of 3 waste phases (liquid, salt cake, and sludge) obtained from tank waste samples analyzed in the laboratory, analysis of variance (ANOVA) models were used to estimate waste states for unmeasured tanks. The preliminary safety criteria are based upon calorimetry and propagation testing of likely organic compounds which represent actual tank wastes. These included sodium salts of citrate, formate, acetate and hydroxyethylethylenediaminetricetate (HEDTA). Hot cell tests of actual tank wastes are planned for the future to confirm propagation tests performed in the laboratory. The effects of draining liquids from the tanks which would remove liquids and moisture were considered because reactive waste which is too dry may propagate. Evaporation effects which could remove moisture from the tanks were also calculated. The various ways that the waste could be heated or ignited by equipment failures or tank operations activities were considered and appropriate monitoring and controls were recommended

  14. Preliminary safety criteria for organic watch list tanks at the Hanford site

    Energy Technology Data Exchange (ETDEWEB)

    Webb, A.B.; Stewart, J.L.; Turner, O.A. [Westinghouse Hanford Co., Richland, WA (United States); Plys, M.G.; Malinovic, B. [Fauske and Associates, Inc., Burr Ridge, IL (United States); Grigsby, J.M. [G & P Consulting, Inc. (United States); Camaioni, D.M.; Heasler, P.G.; Samuels, W.O.; Toth, J.J. [Pacific Northwest Lab., Portland, OR (United States)

    1995-11-01

    Condensed-phase, rapid reactions of organic salts with nitrates/nitrites in Hanford High Level Radioactive Waste single-shell tanks could lead to structural failure of the tanks resulting in significant releases of radionuclides and toxic materials. This report establishes appropriate preliminary safety criteria to ensure that tank wastes will be maintained safe. These criteria show that if actual dry wastes contain less than 1.2 MJ/kg of reactants reaction energy or less 4.5 wt % of total organic carbon, then the waste will be safe and will not propagate if ignited. Waste moisture helps to retard reactions; when waste moisture exceeds 20 wt %, rapid reactions are prevented, regardless of organic carbon concentrations. Aging and degradation of waste materials has been considered to predict the types and amounts to organic compounds present in the waste. Using measurements of 3 waste phases (liquid, salt cake, and sludge) obtained from tank waste samples analyzed in the laboratory, analysis of variance (ANOVA) models were used to estimate waste states for unmeasured tanks. The preliminary safety criteria are based upon calorimetry and propagation testing of likely organic compounds which represent actual tank wastes. These included sodium salts of citrate, formate, acetate and hydroxyethylethylenediaminetricetate (HEDTA). Hot cell tests of actual tank wastes are planned for the future to confirm propagation tests performed in the laboratory. The effects of draining liquids from the tanks which would remove liquids and moisture were considered because reactive waste which is too dry may propagate. Evaporation effects which could remove moisture from the tanks were also calculated. The various ways that the waste could be heated or ignited by equipment failures or tank operations activities were considered and appropriate monitoring and controls were recommended.

  15. Preliminary Assessment for the Effects of the External Hazard Factors on the Safety of NPPs

    International Nuclear Information System (INIS)

    Jin, So Beom; Hyun, Seung Gyu; Kim, Sang Yun; Lee, Sung Kyu; Hur, Youl

    2010-01-01

    The Ch.etsu Offshore Earthquake(2007.7.16) in Japan caused damage to the Kashiwazaki-Kariwa(K-K) Nuclear Power Plants (NPPs) with seismic ground motion that exceeded the design level. This incident drew the interest of the safety evaluation studies for NPPs subjected to earthquakes exceeding the design basis around the world. Also, the Indian Ocean Tsunami(2004.12.26) tripped the Madras NPP by reason of flooding of the intake pump house and inundated the construction site of a fast breeder reactor site in India. In addition, from the various man-made and natural hazards such as the oil spill accident near Mallipo, Taean, Chungnam (2007.12), the forest fire near the Ulchin NPP site, the several inflows of marine organism into the intake of the Ulchin NPP, it was confirmed that the safety of NPPs may be affected by natural and human induced disasters. Intergovernmental Panel on Climate Change (IPCC) has been warned about global warming; the average temperature rose about 1.5 .deg. C during the 20th century and the damages caused by typhoons and heavy rains have also increased in Korea. Accordingly, a natural disaster prevention research team(hereafter team) ,which have been organized and operated since 2009, has assessed the impact of various hazards such as earthquakes and environmental changes due to global warming on the safety of NPP and has discussed to establish countermeasures. This paper introduces that the preliminary assessment for the effects of the external hazard factors on the safety of NPPs was conducted by the team

  16. 78 FR 10200 - Proposed Information Collection; Captive Wildlife Safety Act

    Science.gov (United States)

    2013-02-13

    ... DEPARTMENT OF THE INTERIOR Fish and Wildlife Service [FWS-HQ-LE-2013-N020; FF09L00200-FX-LE12200900000] Proposed Information Collection; Captive Wildlife Safety Act AGENCY: Fish and Wildlife Service, Interior. ACTION: Notice; request for comments. SUMMARY: We (U.S. Fish and Wildlife Service) will ask the...

  17. Thermal analysis and safety information for metal nanopowders by DSC

    Energy Technology Data Exchange (ETDEWEB)

    Tseng, J.M.; Huang, S.T. [Institute of Safety and Disaster Prevention Technology, Central Taiwan University of Science and Technology, 666, Buzih Road, Beitun District, Taichung 40601, Taiwan, ROC (China); Duh, Y.S.; Hsieh, T.Y.; Sun, Y.Y. [Department of Safety Health and Environmental Engineering, National United University, Miaoli, Taiwan, ROC (China); Lin, J.Z. [Institute of Safety and Disaster Prevention Technology, Central Taiwan University of Science and Technology, 666, Buzih Road, Beitun District, Taichung 40601, Taiwan, ROC (China); Wu, H.C. [Institute of Occupational Safety and Health, Council of Labor Affairs, Taipei, Taiwan, ROC (China); Kao, C.S., E-mail: jcsk@nuu.edu.tw [Department of Safety Health and Environmental Engineering, National United University, Miaoli, Taiwan, ROC (China)

    2013-08-20

    Highlights: • Metal nanopowders are common and frequently employed in industry. • Nano iron powder experimental results of T{sub o} were 140–150 °C. • Safety information can benefit relevant metal powders industries. - Abstract: Metal nanopowders are common and frequently employed in industry. Iron is mostly applied in high-performance magnetic materials and pollutants treatment for groundwater. Zinc is widely used in brass, bronze, die casting metal, alloys, rubber, and paints, etc. Nonetheless, some disasters induced by metal powders are due to the lack of related safety information. In this study, we applied differential scanning calorimetry (DSC) and used thermal analysis software to evaluate the related thermal safety information, such as exothermic onset temperature (T{sub o}), peak of temperature (T{sub p}), and heat of reaction (ΔH). The nano iron powder experimental results of T{sub o} were 140–150 °C, 148–158 °C, and 141–149 °C for 15 nm, 35 nm, and 65 nm, respectively. The ΔH was larger than 3900 J/g, 5000 J/g, and 3900 J/g for 15 nm, 35 nm, and 65 nm, respectively. Safety information can benefit the relevant metal powders industries for preventing accidents from occurring.

  18. Preliminary Results of Ancillary Safety Analyses Supporting TREAT LEU Conversion Activities

    Energy Technology Data Exchange (ETDEWEB)

    Brunett, A. J. [Argonne National Lab. (ANL), Argonne, IL (United States); Fei, T. [Argonne National Lab. (ANL), Argonne, IL (United States); Strons, P. S. [Argonne National Lab. (ANL), Argonne, IL (United States); Papadias, D. D. [Argonne National Lab. (ANL), Argonne, IL (United States); Hoffman, E. A. [Argonne National Lab. (ANL), Argonne, IL (United States); Kontogeorgakos, D. C. [Argonne National Lab. (ANL), Argonne, IL (United States); Connaway, H. M. [Argonne National Lab. (ANL), Argonne, IL (United States); Wright, A. E. [Argonne National Lab. (ANL), Argonne, IL (United States)

    2015-10-01

    Report (FSAR) [3]. Depending on the availability of historical data derived from HEU TREAT operation, results calculated for the LEU core are compared to measurements obtained from HEU TREAT operation. While all analyses in this report are largely considered complete and have been reviewed for technical content, it is important to note that all topics will be revisited once the LEU design approaches its final stages of maturity. For most safety significant issues, it is expected that the analyses presented here will be bounding, but additional calculations will be performed as necessary to support safety analyses and safety documentation. It should also be noted that these analyses were completed as the LEU design evolved, and therefore utilized different LEU reference designs. Preliminary shielding, neutronic, and thermal hydraulic analyses have been completed and have generally demonstrated that the various LEU core designs will satisfy existing safety limits and standards also satisfied by the existing HEU core. These analyses include the assessment of the dose rate in the hodoscope room, near a loaded fuel transfer cask, above the fuel storage area, and near the HEPA filters. The potential change in the concentration of tramp uranium and change in neutron flux reaching instrumentation has also been assessed. Safety-significant thermal hydraulic items addressed in this report include thermally-induced mechanical distortion of the grid plate, and heating in the radial reflector.

  19. Preliminary Study on Secure Intranet Geographical Information System

    International Nuclear Information System (INIS)

    Kim, Hyun Tae; Park, Jee Won; Ko Han Suk

    2005-01-01

    A Geographical Information System (GIS) is usually defined as an information system for capturing, checking, storing, retrieving, manipulating, analyzing, and displaying spatial and relevant non-spatial data. Here 'spatial' means 'geo-referenced to the earth'. It is estimated that about 80% of the data used in business and government are of spatial type. The georeferenced information on sensitive location is usually protected as the highest level of confidentiality by the most information system. This paper discusses a commercial satellite imagery based secure Intranet GIS which runs the Microsoft .NET technology

  20. Preliminary Safety Analysis of the Gorleben Site: Safety Concept and Application to Scenario Development Based on a Site-Specific Features, Events and Processes (FEP) Database - 13304

    Energy Technology Data Exchange (ETDEWEB)

    Moenig, Joerg; Beuth, Thomas; Wolf, Jens [Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) mbH, Theodor-Heuss-Str. 4, D-38122 Braunschweig (Germany); Lommerzheim, Andre [DBE TECHNOLOGY GmbH, Eschenstr. 55, D-31224 Peine (Germany); Mrugalla, Sabine [Federal Institute for Geosciences and Natural Resources (BGR), Stilleweg 2, D-30655 Hannover (Germany)

    2013-07-01

    Based upon the German safety criteria, released in 2010 by the Federal Ministry of the Environment (BMU), a safety concept and a safety assessment concept for the disposal of heat-generating high-level waste have both been developed in the framework of the preliminary safety case for the Gorleben site (Project VSG). The main objective of the disposal is to contain the radioactive waste inside a defined rock zone, which is called containment-providing rock zone. The radionuclides shall remain essentially at the emplacement site, and at the most, a small defined quantity of material shall be able to leave this rock zone. This shall be accomplished by the geological barrier and a technical barrier system, which is required to seal the inevitable penetration of the geological barrier by the construction of the mine. The safe containment has to be demonstrated for probable and less probable evolutions of the site, while evolutions with very low probability (less than 1 % over the demonstration period of 1 million years) need not to be considered. Owing to the uncertainty in predicting the real evolution of the site, plausible scenarios have been derived in a systematic manner. Therefore, a comprehensive site-specific features, events and processes (FEP) data base for the Gorleben site has been developed. The safety concept was directly taken into account, e.g. by identification of FEP with direct influence on the barriers that provide the containment. No effort was spared to identify the interactions of the FEP, their probabilities of occurrence, and their characteristics (values). The information stored in the data base provided the basis for the development of scenarios. The scenario development methodology is based on FEP related to an impairment of the functionality of a subset of barriers, called initial barriers. By taking these FEP into account in their probable characteristics the reference scenario is derived. Thus, the reference scenario describes a

  1. Measuring and improving patient safety through health information technology: The Health IT Safety Framework.

    Science.gov (United States)

    Singh, Hardeep; Sittig, Dean F

    2016-04-01

    Health information technology (health IT) has potential to improve patient safety but its implementation and use has led to unintended consequences and new safety concerns. A key challenge to improving safety in health IT-enabled healthcare systems is to develop valid, feasible strategies to measure safety concerns at the intersection of health IT and patient safety. In response to the fundamental conceptual and methodological gaps related to both defining and measuring health IT-related patient safety, we propose a new framework, the Health IT Safety (HITS) measurement framework, to provide a conceptual foundation for health IT-related patient safety measurement, monitoring, and improvement. The HITS framework follows both Continuous Quality Improvement (CQI) and sociotechnical approaches and calls for new measures and measurement activities to address safety concerns in three related domains: 1) concerns that are unique and specific to technology (e.g., to address unsafe health IT related to unavailable or malfunctioning hardware or software); 2) concerns created by the failure to use health IT appropriately or by misuse of health IT (e.g. to reduce nuisance alerts in the electronic health record (EHR)), and 3) the use of health IT to monitor risks, health care processes and outcomes and identify potential safety concerns before they can harm patients (e.g. use EHR-based algorithms to identify patients at risk for medication errors or care delays). The framework proposes to integrate both retrospective and prospective measurement of HIT safety with an organization's existing clinical risk management and safety programs. It aims to facilitate organizational learning, comprehensive 360 degree assessment of HIT safety that includes vendor involvement, refinement of measurement tools and strategies, and shared responsibility to identify problems and implement solutions. A long term framework goal is to enable rigorous measurement that helps achieve the safety

  2. Preliminary investigation of interconnected systems interactions for the safety injection system of Indian Point-3

    International Nuclear Information System (INIS)

    Alesso, H.P.; Lappa, D.A.; Smith, C.F.; Sacks, I.J.

    1983-01-01

    The rich diversity of ideas and techniques for analyzing interconnected systems interaction has presented the NRC with the problem of identifying methods appropriate for their own review and audit. This report presents the findings of a preliminary study using the Digraph Matrix Analysis method to evaluate interconnected systems interactions for the safety injection system of Indian Point-3. The analysis effort in this study was subjected to NRC constraints regarding the use of Boolean logic, the construction of simplified plant representations or maps, and the development of heuristic measures as specified by the NRC. The map and heuristic measures were found to be an unsuccessful approach. However, from the effort to model and analyze the Indian Point-3 safety injection system, including Boolean logic in the model, singleton and doubleton cut-sets were identified. It is recommended that efforts excluding Boolean logic and utilizing the NRC heuristic measures not be pursed further and that the Digraph Matrix approach (or other comparable risk assessment technique) with Boolean logic included to conduct the audit of the Indian Point-3 systems interaction study

  3. Patient-Reported Safety Information: A Renaissance of Pharmacovigilance?

    Science.gov (United States)

    Härmark, Linda; Raine, June; Leufkens, Hubert; Edwards, I Ralph; Moretti, Ugo; Sarinic, Viola Macolic; Kant, Agnes

    2016-10-01

    The role of patients as key contributors in pharmacovigilance was acknowledged in the new EU pharmacovigilance legislation. This contains several efforts to increase the involvement of the general public, including making patient adverse drug reaction (ADR) reporting systems mandatory. Three years have passed since the legislation was introduced and the key question is: does pharmacovigilance yet make optimal use of patient-reported safety information? Independent research has shown beyond doubt that patients make an important contribution to pharmacovigilance signal detection. Patient reports provide first-hand information about the suspected ADR and the circumstances under which it occurred, including medication errors, quality failures, and 'near misses'. Patient-reported safety information leads to a better understanding of the patient's experiences of the ADR. Patients are better at explaining the nature, personal significance and consequences of ADRs than healthcare professionals' reports on similar associations and they give more detailed information regarding quality of life including psychological effects and effects on everyday tasks. Current methods used in pharmacovigilance need to optimise use of the information reported from patients. To make the most of information from patients, the systems we use for collecting, coding and recording patient-reported information and the methodologies applied for signal detection and assessment need to be further developed, such as a patient-specific form, development of a severity grading and evolution of the database structure and the signal detection methods applied. It is time for a renaissance of pharmacovigilance.

  4. DART - for design basis justification and safety related information management

    International Nuclear Information System (INIS)

    Billington, A.; Blondiaux, P.; Boucau, J.; Cantineau, B.; Doumont, C.; Mared, A.

    2000-01-01

    DART is the acronym for Design Analysis Re-engineering Tool. It embodies a systematic and integrated approach to NPP safety re-assessment and configuration management, that makes use of Reverse Failure Mode and Effect Analysis in conjunction with a state-of-the-art relational database and a standardized data format, to permit long-term management of plant safety related information. The plant design is reviewed in a step-by-step logical fashion by constructing fault trees that identify the link between undesired consequences and their causes. Each failure cause identified in a fault tree is addressed by defining functional requirements, which are in turn addressed by documenting the specific manner in which the plant complies with the requirement. The database can be used to generate up-to-date plant safety related documents, including: SAR, Systems Descriptions, Technical Specifications and plant procedures. The approach is open-minded by nature and therefore is not regulatory driven, however the plant licensing basis will also be reviewed and documented within the same database such that a Regulatory Conformance Program may be integrated with the other safety documentation. This methodology can thus reconstitute the plant design bases in a comprehensive and systematic way, while allowing to uncover weaknesses in design. The original feature of the DART methodology is that it links all the safety related documents together, facilitating the evaluation of the safety impact resulting from any plant modification. Due to its capability to retrieve the basic justifications of the plant design, it is also a useful tool for training the young generation of plant personnel. The DART methodology has been developed for application to units 2, 3 and 4 at Vattenfall's Ringhals site in Sweden. It may be applied to any nuclear power plant or industrial facility where public safety is a concern. (author)

  5. DART - for design basis justification and safety related information management

    International Nuclear Information System (INIS)

    Billington, A.; Blondiaux, B.; Boucau, J.; Cantineau, B.; Mared, A.

    2001-01-01

    DART is the acronym for Design Analysis Re-Engineering Tool. It embodies a systematic and integrated approach to NPP safety re-assessment and configuration management, that makes use of Reverse Failure Mode and Effect Analysis in conjunction with a state-of-the-art relational database and a standardized data format, to permit long-term management of plant safety related information. The plant design is reviewed in a step-by-step logical fashion by constructing fault trees that identify the link between undesired consequences and their causes. Each failure cause identified in a fault tree is addressed by defining functional requirements, which are in turn addressed by documenting the specific manner in which the plant complies with the requirement. The database can then be used to generate up-to-date plant safety related documents, including: SAR, Systems Descriptions, Technical Specifications and plant procedures. The approach is open-minded by nature and therefore is not regulatory driven, however the plant licensing basis will also be reviewed and documented within the same database such that a Regulatory Conformance Program may be integrated with the other safety documentation. This methodology can thus reconstitute the plant design bases in a comprehensive and systematic way, while allowing to uncover weaknesses in design. The original feature of the DART methodology is that it links all the safety related documents together, facilitating the evaluation of the safety impact resulting from any plant modification. Due to its capability to retrieve the basic justifications of the plant design, it is also a useful tool for training the young generation of plant personnel. The DART methodology has been developed for application to units 2, 3 and 4 at Vattenfall's Ringhals site in Sweden. It may be applied to any nuclear power plant or industrial facility where public safety is a concern. (author)

  6. Development of a Safety Assessment Information System for the Management of Periodic Safety Assessment Activities

    International Nuclear Information System (INIS)

    Song, Tae Young

    2007-01-01

    At present, the 10-year Periodic Safety Review(PSR) has been performing to confirm all the aspects of safety issues for all the operating plants in compliance with domestic nuclear law of article 23, subarticle 3. For each plant, in addition, Probabilistic Safety Assessment(PSA) and Severe Accident Management Guideline(SAMG) are being implemented and revised periodically to reflect the latest safety level according to principle fulfillment of severe accident policy statement. The assessment reports, as one of outcomes from these activities, are submitted into and reviewed by domestic regulatory body. During reviewing (in-office duty) and licensing (regulatory duty) process, a large number of outcomes of which most are the formal technical reports and licensing materials, are inevitably produced. Moreover, repeated review process over the plants can make them accumulated and produce a variety of documents additionally. This circumstance motivates to develop effective tool or system for the management of these reports and related technical documents for the future use in licensing process and for subsequent plant assessments. This paper presents the development status of Safety Assessment Information System(SAIS) which manages safety-related documents of PSR, PSA and SAMG for practical use for experienced engineers in charge of these areas

  7. Development of a Safety Assessment Information System for the Management of Periodic Safety Assessment Activities

    Energy Technology Data Exchange (ETDEWEB)

    Song, Tae Young [Nuclear Engineering and Technology Institute, Daejeon (Korea, Republic of)

    2007-07-01

    At present, the 10-year Periodic Safety Review(PSR) has been performing to confirm all the aspects of safety issues for all the operating plants in compliance with domestic nuclear law of article 23, subarticle 3. For each plant, in addition, Probabilistic Safety Assessment(PSA) and Severe Accident Management Guideline(SAMG) are being implemented and revised periodically to reflect the latest safety level according to principle fulfillment of severe accident policy statement. The assessment reports, as one of outcomes from these activities, are submitted into and reviewed by domestic regulatory body. During reviewing (in-office duty) and licensing (regulatory duty) process, a large number of outcomes of which most are the formal technical reports and licensing materials, are inevitably produced. Moreover, repeated review process over the plants can make them accumulated and produce a variety of documents additionally. This circumstance motivates to develop effective tool or system for the management of these reports and related technical documents for the future use in licensing process and for subsequent plant assessments. This paper presents the development status of Safety Assessment Information System(SAIS) which manages safety-related documents of PSR, PSA and SAMG for practical use for experienced engineers in charge of these areas.

  8. Online Food Safety Information System for Nuclear or Radiological Emergencies

    International Nuclear Information System (INIS)

    Albinet, Franck; Adjigogov, Lazar; Dercon, Gerd

    2016-01-01

    Over the last year, the protocol with regards to data management and visualization requirements for food safety decision-making, developed under CRP D1.50.15 on R esponse to Nuclear Emergency Affecting Food and Agriculture , was further implemented. The development team moved away from early series of disconnected prototypes to a more advanced Information System integrating both data management and visualization components outlined in the agreed protocol

  9. Use of risk information to safety regulation. Reprocessing facilities

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2013-08-15

    A procedure of probabilistic risk assessment (PRA) for a reprocessing facility has been under the development aiming to utilize risk information for safety regulations in this project. Activities in the fiscal year 2012 are summarized in the paper. A major activity is a fundamental study on a concept of serious accidents, requirements of serious accident management, and a policy of utilizing risk information for fabrication and reprocessing facilities. Other than the activity a study on release and transport of aerial radioactive materials at a serious accident in a reprocessing facility has been conducted. The outline and results are provided in the chapter 1 and 2 respectively. (author)

  10. Quality and safety implications of emergency department information systems.

    Science.gov (United States)

    Farley, Heather L; Baumlin, Kevin M; Hamedani, Azita G; Cheung, Dickson S; Edwards, Michael R; Fuller, Drew C; Genes, Nicholas; Griffey, Richard T; Kelly, John J; McClay, James C; Nielson, Jeff; Phelan, Michael P; Shapiro, Jason S; Stone-Griffith, Suzanne; Pines, Jesse M

    2013-10-01

    The Health Information Technology for Economic and Clinical Health Act of 2009 and the Centers for Medicare & Medicaid Services "meaningful use" incentive programs, in tandem with the boundless additional requirements for detailed reporting of quality metrics, have galvanized hospital efforts to implement hospital-based electronic health records. As such, emergency department information systems (EDISs) are an important and unique component of most hospitals' electronic health records. System functionality varies greatly and affects physician decisionmaking, clinician workflow, communication, and, ultimately, the overall quality of care and patient safety. This article is a joint effort by members of the Quality Improvement and Patient Safety Section and the Informatics Section of the American College of Emergency Physicians. The aim of this effort is to examine the benefits and potential threats to quality and patient safety that could result from the choice of a particular EDIS, its implementation and optimization, and the hospital's or physician group's approach to continuous improvement of the EDIS. Specifically, we explored the following areas of potential EDIS safety concerns: communication failure, wrong order-wrong patient errors, poor data display, and alert fatigue. Case studies are presented that illustrate the potential harm that could befall patients from an inferior EDIS product or suboptimal execution of such a product in the clinical environment. The authors have developed 7 recommendations to improve patient safety with respect to the deployment of EDISs. These include ensuring that emergency providers actively participate in selection of the EDIS product, in the design of processes related to EDIS implementation and optimization, and in the monitoring of the system's ongoing success or failure. Our recommendations apply to emergency departments using any type of EDIS: custom-developed systems, best-of-breed vendor systems, or enterprise systems

  11. Health and safety information program for hazardous materials

    International Nuclear Information System (INIS)

    O'Brien, M.P.; Fallon, N.J.; Kuehner, A.V.

    1979-01-01

    The system is used as a management tool in several safety and health programs. It is used to: trace the use of hazardous materials and to determine monitoring needs; inform the occupational physician of the potential health problems associated with materials ordered by a given individual; inform the fire and rescue group of hazardous materials in a given building; provide waste disposal recommendations to the hazardous waste management group; assist the hazardous materials shipping coordinator in identifying materials which are regulated by the Department of Transportation; and guide management decisions in the area of recognizing and rectifying unsafe conditions. The information system has been expanded from a manual effort to provide a brief description of health hazards of chemicals used at the lab to a computerized health and safety information system which serves the needs of all personnel who may encounter the material in the course of their work. The system has been designed to provide information needed to control the potential problems associated with a hazardous material up to the time that it is consumed in a given operation or is sent to the waste disposal facility

  12. A preliminary geodetic data model for geographic information systems

    Science.gov (United States)

    Kelly, K. M.

    2009-12-01

    Our ability to gather and assimilate integrated data collections from multiple disciplines is important for earth system studies. Moreover, geosciences data collection has increased dramatically, with pervasive networks of observational stations on the ground, in the oceans, in the atmosphere and in space. Contemporary geodetic observations from several space and terrestrial technologies contribute to our knowledge of earth system processes and thus are a valuable source of high accuracy information for many global change studies. Assimilation of these geodetic observations and numerical models into models of weather, climate, oceans, hydrology, ice, and solid Earth processes is an important contribution geodesists can make to the earth science community. Clearly, the geodetic observations and models are fundamental to these contributions. ESRI wishes to provide leadership in the geodetic community to collaboratively build an open, freely available content specification that can be used by anyone to structure and manage geodetic data. This Geodetic Data Model will provide important context for all geographic information. The production of a task-specific geodetic data model involves several steps. The goal of the data model is to provide useful data structures and best practices for each step, making it easier for geodesists to organize their data and metadata in a way that will be useful in their data analyses and to their customers. Built on concepts from the successful Arc Marine data model, we introduce common geodetic data types and summarize the main thematic layers of the Geodetic Data Model. These provide a general framework for envisioning the core feature classes required to represent geodetic data in a geographic information system. Like Arc Marine, the framework is generic to allow users to build workflow or product specific geodetic data models tailored to the specific task(s) at hand. This approach allows integration of the data with other existing

  13. 78 FR 34703 - Pipeline Safety: Information Collection Activities, Revision to Gas Distribution Annual Report

    Science.gov (United States)

    2013-06-10

    ... DEPARTMENT OF TRANSPORTATION Pipeline and Hazardous Materials Safety Administration [Docket No. PHMSA-2013-0004] Pipeline Safety: Information Collection Activities, Revision to Gas Distribution Annual Report AGENCY: Pipeline and Hazardous Materials Safety Administration, DOT. ACTION: Notice and request...

  14. Health and safety. Preliminary comparative assessment of the satellite power system (SPS) and other energy alternatives

    International Nuclear Information System (INIS)

    Habegger, L.J.; Gasper, J.R.; Brown, C.D.

    1980-04-01

    Existing data on the health and safety risks of a satellite power system and four electrical generation systems are analyzed: a combined-cycle coal power system with a low-Btu gasifier and open-cycle gas turbine, a fission power system with fuel reprocessing, a central-station, terrestrial, solar-photovoltaic power system, and a first-generation design for a fusion power system. The systems are compared on the basis of expected deaths and person-days lost per year associated with 1000 MW of average electricity generation and the number of health and safety risks that are identified as potentially significant but unquantifiable. The appendices provide more detailed information on risks, uncertainties, additional research needed, and references for the identified impacts of each system

  15. Preliminary safety evaluation for the Forsmark area. Based on data and site descriptions after the initial site investigation stage

    International Nuclear Information System (INIS)

    Andersson, Johan

    2005-08-01

    The main objectives of this Preliminary Safety Evaluation (PSE) of the Forsmark area have been to determine, with limited efforts, whether the feasibility study's judgement of the suitability of the candidate area with respect to long-term safety holds up in the light of the actual site investigation data; to provide feedback to continued site investigations and site-specific repository design and to identify site-specific scenarios and geoscientific issues for further analyses. The PSE focuses on comparing the attained knowledge of the sites with the suitability criteria as set out by SKB. The PSE does not aim at comparing sites and does not assess compliance with safety and radiation protection criteria. The evaluation shows that, even considering remaining uncertainties, the Forsmark area meets all stated safety requirements and preferences. Consequently, from a safety point of view, there is no reason not to continue the Site Investigations of the Forsmark area. There are still uncertainties to resolve and the safety would eventually need to be verified through a full safety assessment. Nevertheless, this Preliminary Safety Evaluation demonstrates that it is likely that a safe repository for spent nuclear fuel of the KBS-3 type could be constructed at the site. The following feedback is provided to the site investigations and the associated site modelling: Reducing the uncertainty on the deformation zone geometry inside the target area would be needed to more firmly define locations of the suitable deposition volumes. There is substantial uncertainty in the Discrete Fracture Network model. Further reduction of the uncertainties, if needed, would probably only be possible from the underground, detailed investigation phase. Efforts need also be spent on improving the DFN-modelling. There are assumptions made in current models that could be challenged and there seems to be room for better use of the borehole information. It is particularly important to provide

  16. Preliminary safety evaluation for the Forsmark area. Based on data and site descriptions after the initial site investigation stage

    Energy Technology Data Exchange (ETDEWEB)

    Andersson, Johan [JA Streamflow AB, Aelvsjoe (Sweden)

    2005-08-01

    The main objectives of this Preliminary Safety Evaluation (PSE) of the Forsmark area have been to determine, with limited efforts, whether the feasibility study's judgement of the suitability of the candidate area with respect to long-term safety holds up in the light of the actual site investigation data; to provide feedback to continued site investigations and site-specific repository design and to identify site-specific scenarios and geoscientific issues for further analyses. The PSE focuses on comparing the attained knowledge of the sites with the suitability criteria as set out by SKB. The PSE does not aim at comparing sites and does not assess compliance with safety and radiation protection criteria. The evaluation shows that, even considering remaining uncertainties, the Forsmark area meets all stated safety requirements and preferences. Consequently, from a safety point of view, there is no reason not to continue the Site Investigations of the Forsmark area. There are still uncertainties to resolve and the safety would eventually need to be verified through a full safety assessment. Nevertheless, this Preliminary Safety Evaluation demonstrates that it is likely that a safe repository for spent nuclear fuel of the KBS-3 type could be constructed at the site. The following feedback is provided to the site investigations and the associated site modelling: Reducing the uncertainty on the deformation zone geometry inside the target area would be needed to more firmly define locations of the suitable deposition volumes. There is substantial uncertainty in the Discrete Fracture Network model. Further reduction of the uncertainties, if needed, would probably only be possible from the underground, detailed investigation phase. Efforts need also be spent on improving the DFN-modelling. There are assumptions made in current models that could be challenged and there seems to be room for better use of the borehole information. It is particularly important to

  17. New Reactor Siting in Finland, Hanhikivi Site in Pyhaejoki - STUK preliminary safety assessment

    International Nuclear Information System (INIS)

    Nevalainen, Janne

    2013-01-01

    STUK has performed a preliminary assessment of the Decision-in-Principle on the Fennovoima application. A variety of factors must be considered in the selection of a site, including effects of the site on the plant design and the effects of the plant on the site environment. These include external hazards, both natural and human-induced. Since this is a new site, an extensive siting process is followed, that can include an EIA. A site survey is performed to identify candidate sites, after investigating a large region and rejecting unsuitable sites. The remaining sites are then screened and compared on the basis of safety and other considerations to select one or more preferred sites. Natural hazards include geology, seismology, hydrology and meteorology. Offshore ice will be a particular hazard for this plant, since the site is on average only 1.5 m above sea level. The design basis earthquake corresponds to a return frequency of 100,000 years, with 50 % confidence. The existing sites in southern Finland used a design peak ground acceleration of 0.1 g with the ground response spectrum maximum at 10 Hz. The candidate sites in northern Finland will require a peak ground acceleration of 0.2 g with the ground response spectrum maximum at 25 Hz

  18. FEP catalogue for the VSG. Documentation. Report on the work package 7. Preliminary safety analysis Gorleben (VSG); FEP-Katalog fuer die VSG. Dokumentation. Bericht zum Arbeitspaket 7. Vorlaeufige Sicherheitsanalyse fuer den Standort Gorleben

    Energy Technology Data Exchange (ETDEWEB)

    Wolf, Jens [Gesellschaft fuer Anlagen- und Reaktorsicherheit mbH (GRS), Koeln (Germany); Behlau, Joachim [Bundesanstalt fuer Geowissenschaften und Rohstoffe, Hannover (Germany); Beuth, Thomas [Gesellschaft fuer Anlagen- und Reaktorsicherheit mbH (GRS), Koeln (Germany)] [and others

    2012-06-15

    The report is a compendium of the FEP (features, events, processes) data base that was developed in the frame of the preliminary safety analysis Gorleben (VSG). For each FEP issue the information includes the following subchapters: definition, general information and examples, status at the site, site-specific impacts, temporal restriction, conditional incidence rate, effects on subsidiary systems, adverse effects on the function of the initial barriers, justification, direct dependencies, open questions, references.

  19. The challenge of effectively communicating patient safety information.

    Science.gov (United States)

    Hugman, Bruce; Edwards, I Ralph

    2006-07-01

    Rational use of drugs and patient safety are seriously compromised by a lack of good information, education and effective communication at all stages of drug development and use. From animal trials through to dispensing, there are misconceptions and opportunities for error which current methods of drug information communication do not adequately address: they do not provide those responsible for prescribing and dispensing drugs with the data and information they need to pass on complex and often changing messages to patients and the public. The incidence of adverse reactions due to the way drugs are used; the variable impact of regulatory guidelines and warnings on prescribing behaviour; drug scares and crises suggest a great gap between the ideals of the safe use of medicines and the reality in homes, clinics and hospitals around the world. To address these challenges, the authors review the several levels at which safety information is generated and communicated, and examine how, at each stage, the content and its significance, and the method of communication can be improved.

  20. Dataset for Phase I randomized clinical trial for safety and tolerability of GET 73 in single and repeated ascending doses including preliminary pharmacokinetic parameters

    Directory of Open Access Journals (Sweden)

    Carolina L. Haass-Koffler

    2017-12-01

    Full Text Available The data in this article outline the methods used for the administration of GET 73 in the first time-in-human manuscript entitled “Phase I randomized clinical trial for the safety, tolerability and preliminary pharmacokinetics of the mGluR5 negative allosteric modulator GET 73 following single and repeated doses in healthy male volunteers” (Haass-Koffler et al., 2017 [1]. Data sets are provided in two different manners. The first series of tables provided includes procedural information about the experiments conducted. The next series of tables provided includes Pharmacokinetic (PK parameters for GET 73 and its main metabolite MET 2. This set of data is comprised by two experiments: Experiment 1 references a single ascending dose administration of GET 73 and Experiment 2 references a repeated ascending dose administration of GET 73. Keywords: Glutamate receptor subtype 5 (mGlu5, Allosteric modulator, GET 73, Safety, Tolerability

  1. Safety and feasibility of transcranial direct current stimulation in pediatric hemiparesis: randomized controlled preliminary study.

    Science.gov (United States)

    Gillick, Bernadette T; Feyma, Tim; Menk, Jeremiah; Usset, Michelle; Vaith, Amy; Wood, Teddi Jean; Worthington, Rebecca; Krach, Linda E

    2015-03-01

    Transcranial direct current stimulation (tDCS) is a form of noninvasive brain stimulation that has shown improved adult stroke outcomes. Applying tDCS in children with congenital hemiparesis has not yet been explored. The primary objective of this study was to explore the safety and feasibility of single-session tDCS through an adverse events profile and symptom assessment within a double-blind, randomized placebo-controlled preliminary study in children with congenital hemiparesis. A secondary objective was to assess the stability of hand and cognitive function. A double-blind, randomized placebo-controlled pretest/posttest/follow-up study was conducted. The study was conducted in a university pediatric research laboratory. Thirteen children, ages 7 to 18 years, with congenital hemiparesis participated. Adverse events/safety assessment and hand function were measured. Participants were randomly assigned to either an intervention group or a control group, with safety and functional assessments at pretest, at posttest on the same day, and at a 1-week follow-up session. An intervention of 10 minutes of 0.7 mA tDCS was applied to bilateral primary motor cortices. The tDCS intervention was considered safe if there was no individual decline of 25% or group decline of 2 standard deviations for motor evoked potentials (MEPs) and behavioral data and no report of adverse events. No major adverse events were found, including no seizures. Two participants did not complete the study due to lack of MEP and discomfort. For the 11 participants who completed the study, group differences in MEPs and behavioral data did not exceed 2 standard deviations in those who received the tDCS (n=5) and those in the control group (n=6). The study was completed without the need for stopping per medical monitor and biostatisticial analysis. A limitation of the study was the small sample size, with data available for 11 participants. Based on the results of this study, tDCS appears to be safe

  2. Twenty-First Water Reaction Safety Information Meeting

    International Nuclear Information System (INIS)

    Monteleone, S.

    1994-04-01

    This three-volume report contains 90 papers out of the 102 that were presented at the Twenty-First Water Reactor Safety Information Meeting held at the Bethesda Marriott Hotel, Bethesda, Maryland, during the week of October 25--27, 1993. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included papers presented by researchers from France, Germany, Japan, Russia, Switzerland, Taiwan, and United Kingdom. The titles of the papers and the names of the authors have been updated and may differ from those that appeared in the final program of the meeting. Individual papers have been cataloged separately. This document, Volume 2, presents papers on severe accident research

  3. Twenty-First Water Reactor Safety Information Meeting

    International Nuclear Information System (INIS)

    Monteleone, S.

    1994-04-01

    This three-volume report contains 90 papers out of the 102 that were presented at the Twenty-First Water Reactor Safety Information Meeting held at the Bethesda Marriott Hotel, Bethesda, Maryland, during the week of October 25-27, 1993. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included papers presented by researchers from France, Germany, Japan, Russia, Switzerland, Taiwan, and United Kingdom. The titles of the papers and the names of the authors have been updated and may differ from those that appeared in the final program of the meeting. Selected papers were indexed separately for inclusion in the Energy Science and Technology Database

  4. Preliminary safety evaluation for the Laxemar subarea. Based on data and site descriptions after the initial site investigation stage

    Energy Technology Data Exchange (ETDEWEB)

    Andersson, Johan [JA Streamflow AB, Aelvsjoe (Sweden)

    2006-03-15

    The main objectives of this Preliminary Safety Evaluation (PSE) of the Laxemar subarea have been to determine, with limited efforts, whether the feasibility study's judgement of the suitability of the candidate area with respect to long-term safety holds up in the light of the actual site investigation data; to provide feedback to continued site investigations and site-specific repository design and to identify site-specific scenarios and geoscientific issues for further analyses. The PSE focuses on comparing the attained knowledge of the sites with the suitability criteria as set out by SKB in 2000. These criteria both concern properties of the site judged to be necessary for safety and engineering (requirements) and properties judged to be beneficial (preferences). The findings are then evaluated in order to provide feedback to continued investigations and design work. The PSE does not aim at comparing sites and does not assess compliance with safety and radiation protection criteria. The latter is eventually done in coming Safety Assessments. This preliminary safety evaluation shows that, according to existing data, the Laxemar subarea meets all safety requirements. The evaluation also shows that the Laxemar subarea meets most of the safety preferences, but for some aspects of the site description further reduction of the uncertainties would enhance the safety case. Despite the stated concerns, there is no reason, from a safety point of view, not to continue the Site Investigations at the Laxemar subarea. There are uncertainties to resolve and the safety would eventually need to be verified through a proper safety assessment. Only some of the uncertainties noted in the Site Descriptive Model have safety implications and need further resolution for this reason. Furthermore, uncertainties may need resolving for other reasons, such as giving an adequate assurance of site understanding or assisting in optimising design. Notably, there are questions about the

  5. Preliminary safety evaluation for the Laxemar subarea. Based on data and site descriptions after the initial site investigation stage

    International Nuclear Information System (INIS)

    Andersson, Johan

    2006-03-01

    The main objectives of this Preliminary Safety Evaluation (PSE) of the Laxemar subarea have been to determine, with limited efforts, whether the feasibility study's judgement of the suitability of the candidate area with respect to long-term safety holds up in the light of the actual site investigation data; to provide feedback to continued site investigations and site-specific repository design and to identify site-specific scenarios and geoscientific issues for further analyses. The PSE focuses on comparing the attained knowledge of the sites with the suitability criteria as set out by SKB in 2000. These criteria both concern properties of the site judged to be necessary for safety and engineering (requirements) and properties judged to be beneficial (preferences). The findings are then evaluated in order to provide feedback to continued investigations and design work. The PSE does not aim at comparing sites and does not assess compliance with safety and radiation protection criteria. The latter is eventually done in coming Safety Assessments. This preliminary safety evaluation shows that, according to existing data, the Laxemar subarea meets all safety requirements. The evaluation also shows that the Laxemar subarea meets most of the safety preferences, but for some aspects of the site description further reduction of the uncertainties would enhance the safety case. Despite the stated concerns, there is no reason, from a safety point of view, not to continue the Site Investigations at the Laxemar subarea. There are uncertainties to resolve and the safety would eventually need to be verified through a proper safety assessment. Only some of the uncertainties noted in the Site Descriptive Model have safety implications and need further resolution for this reason. Furthermore, uncertainties may need resolving for other reasons, such as giving an adequate assurance of site understanding or assisting in optimising design. Notably, there are questions about the

  6. Patient and nurse safety: how information technology makes a difference.

    Science.gov (United States)

    Simpson, Roy L

    2005-01-01

    The Institute of Medicine's landmark report asserted medical error is seldom the fault of individuals, but the result of faulty healthcare policy/procedure systems. Numerous studies have shown that information technology can shore up weak systems. For nursing, information technology plays a key role in protecting patients by eliminating nursing mistakes and protecting nurses by reducing their negative exposure. However, managing information technology is a function of managing the people who use it. This article examines critical issues that impact patient and nurse safety, both physical and professional. It discusses the importance of eliminating the culture of blame, the requirements of process change, how to implement technology in harmony with the organization and the significance of vision.

  7. Undetected latent failures of safety-related systems. Preliminary survey of events in nuclear power plants 1980-1997

    International Nuclear Information System (INIS)

    Lydell, B.

    1998-03-01

    This report summarizes results and insights from a preliminary survey of events involving undetected, latent failures of safety-related systems. The survey was limited to events where mispositioned equipment (e.g., valves, switches) remained undetected, thus rendering standby equipment or systems unavailable for short or long time periods. Typically, these events were symptoms of underlying latent errors (e.g., design errors, procedure errors, unanalyzed safety conditions) and programmatic errors. The preliminary survey identified well over 300 events. Of these, 95 events are documented in this report. Events involving mispositioned equipment are commonplace. Most events are discovered soon after occurrence, however. But as evidenced by the survey results, some events remained undetected beyond several shift changes. The recommendations developed by the survey emphasize the importance of applying modern root cause analysis techniques to the event analysis to ensure that the causes and implications of occurred events are fully understood

  8. A Network Diffusion Model of Food Safety Scare Behavior considering Information Transparency

    Directory of Open Access Journals (Sweden)

    Tingqiang Chen

    2017-01-01

    Full Text Available This study constructs the network diffusion model of food safety scare behavior under the effect of information transparency and examines the network topology and evolution characteristics of food safety scare behavior in a numerical simulation. The main conclusions of this study are as follows. (1 Under the effect of information transparency, the network degree distribution of food safety scare behavior diffusion demonstrates the decreasing characteristics of diminishing margins. (2 Food safety scare behavior diffusion increases with the information dissemination rate and consumer concern about food safety incidents and shows the characteristics of monotone increasing. And with the increasing of the government food safety supervision information transparency and media food safety supervision information transparency, the whole is declining characteristic of diminishing marginal. In addition, the extinction of food safety scare behavior cannot be achieved gradually given a single regulation of government food safety supervision information transparency and media food safety supervision information transparency. (3 The interaction effects between improving government food safety supervision information transparency or media food safety supervision information transparency and declining consumer concerns about food safety incidents or information transmission rate can engender the suppression of food safety scare behavior diffusion.

  9. MedWatch, the FDA Safety Information and Adverse Event Reporting Program

    Science.gov (United States)

    ... Reporting Program MedWatch: The FDA Safety Information and Adverse Event Reporting Program Share Tweet Linkedin Pin it ... approved information that can help patients avoid serious adverse events. Potential Signals of Serious Risks/New Safety ...

  10. Preliminary safety analysis of high-intensity interval training (HIIT) in persons with chronic stroke.

    Science.gov (United States)

    Carl, Daniel L; Boyne, Pierce; Rockwell, Bradley; Gerson, Myron; Khoury, Jane; Kissela, Brett; Dunning, Kari

    2017-03-01

    The purpose of this study was to assess safety via electrocardiographic (ECG), blood pressure (BP), heart rate (HR), and orthopedic responses to 3 different high-intensity interval training (HIIT) protocols in persons with stroke. Eighteen participants (10 male; 61.9 + 8.3 years of age; 5.8 + 4.2 years poststroke) completed a symptom-limited graded exercise test (GXT) with ECG monitoring to screen for eligibility and determine HR peak. The 3 HIIT protocols involved repeated 30 s bursts of treadmill walking at maximum speed alternated with rest periods of 30 s (P30), 1 min (P60), or 2 min (P120). Sessions were performed in random order and included 5 min warm up, 20 min HIIT, and 5 min cool down. Variables measured included ECG activity, BP, HR, signs and symptoms of cardiovascular intolerance, and orthopedic concerns. Generalized linear mixed models and Tukey-Kramer adjustment were used to compare protocols using p HIIT session. HIIT elicited HRs in excess of 88% of measured HR peak including 6 (P30), 8 (P60), and 2 (P120) participants eliciting a HR response above their GXT HR peak . Both maximum BP and HR were significantly higher in P30 and P60 relative to P120. Preliminary data indicate that persons with chronic stroke who have been prescreened with an ECG stress test, a symptom-limited GXT, and a harness for fall protection may safely participate in HIIT, generating substantially higher HRs than what is seen in traditional moderate intensity training.

  11. Information about robustness, reliability and safety in early design phases

    DEFF Research Database (Denmark)

    Marini, Vinicius Kaster

    methods, and an industrial case to assess how the use of information about robustness, reliability and safety as practised by current methods influences concept development. Current methods cannot be used in early design phases due to their dependence on detailed design information for the identification...... alternatives. This prompts designers to reuse working principles that are inherently flawed, as they are liable to disturbances, failures and hazards. To address this issue, an approach based upon individual records of early design issues consists of comparing failures and benefits from prior working...... principles, before making a decision, and improving the more suitable alternatives through this feedback. Workshops were conducted with design practitioners to evaluate the potential of the approach and to simulate decision-making and gain feedback on a proof-of-concept basis. The evaluation has demonstrated...

  12. Database search for safety information on cosmetic ingredients.

    Science.gov (United States)

    Pauwels, Marleen; Rogiers, Vera

    2007-12-01

    Ethical considerations with respect to experimental animal use and regulatory testing are worldwide under heavy discussion and are, in certain cases, taken up in legislative measures. The most explicit example is the European cosmetic legislation, establishing a testing ban on finished cosmetic products since 11 September 2004 and enforcing that the safety of a cosmetic product is assessed by taking into consideration "the general toxicological profile of the ingredients, their chemical structure and their level of exposure" (OJ L151, 32-37, 23 June 1993; OJ L066, 26-35, 11 March 2003). Therefore the availability of referenced and reliable information on cosmetic ingredients becomes a dire necessity. Given the high-speed progress of the World Wide Web services and the concurrent drastic increase in free access to information, identification of relevant data sources and evaluation of the scientific value and quality of the retrieved data, are crucial. Based upon own practical experience, a survey is put together of freely and commercially available data sources with their individual description, field of application, benefits and drawbacks. It should be mentioned that the search strategies described are equally useful as a starting point for any quest for safety data on chemicals or chemical-related substances in general.

  13. Preliminary characterization of risks in the nuclear waste management system based on information in the literature

    International Nuclear Information System (INIS)

    Daling, P.M.; Rhoads, R.E.; Van Luick, A.E.; Fecht, B.A.; Nilson, S.A.; Sevigny, N.L.; Armstrong, G.R.; Hill, D.H.; Rowe, M.; Stern, E.

    1992-01-01

    This document presents preliminary information on the radiological and nonradiological risks in the nuclear waste management system. The objective of the study was to (1) review the literature containing information on risks in the nuclear waste management system and (2) use this information to develop preliminary estimates of the potential magnitude of these risks. Information was collected on a broad range of risk categories to assist the US Department of Energy (DOE) in communicating information about the risks in the waste management systems. The study examined all of the portions of the nuclear waste management system currently expected to be developed by the DOE. The scope of this document includes the potential repository, the integral MRS facility, and the transportation system that supports the potential repository and the MRS facility. Relevant literature was reviewed for several potential repository sites and geologic media. A wide range of ''risk categories'' are addressed in this report: (1) public and occupational risks from accidents that could release radiological materials, (2) public and occupational radiation exposure resulting from routine operations, (3) public and occupational risks from accidents involving hazards other than radioactive materials, and (4) public and occupational risks from exposure to nonradioactive hazardous materials during routine operations. The report is intended to provide a broad spectrum of risk-related information about the waste management system. This information is intended to be helpful for planning future studies

  14. Hazardous Waste/Mixed Waste Treatment Building Safety Information Document (SID)

    International Nuclear Information System (INIS)

    Fatell, L.B.; Woolsey, G.B.

    1993-01-01

    This Safety Information Document (SID) provides a description and analysis of operations for the Hazardous Waste/Mixed Waste Disposal Facility Treatment Building (the Treatment Building). The Treatment Building has been classified as a moderate hazard facility, and the level of analysis performed and the methodology used are based on that classification. Preliminary design of the Treatment Building has identified the need for two separate buildings for waste treatment processes. The term Treatment Building applies to all these facilities. The evaluation of safety for the Treatment Building is accomplished in part by the identification of hazards associated with the facility and the analysis of the facility's response to postulated events involving those hazards. The events are analyzed in terms of the facility features that minimize the causes of such events, the quantitative determination of the consequences, and the ability of the facility to cope with each event should it occur. The SID presents the methodology, assumptions, and results of the systematic evaluation of hazards associated with operation of the Treatment Building. The SID also addresses the spectrum of postulated credible events, involving those hazards, that could occur. Facility features important to safety are identified and discussed in the SID. The SID identifies hazards and reports the analysis of the spectrum of credible postulated events that can result in the following consequences: Personnel exposure to radiation; Radioactive material release to the environment; Personnel exposure to hazardous chemicals; Hazardous chemical release to the environment; Events leading to an onsite/offsite fatality; and Significant damage to government property. The SID addresses the consequences to the onsite and offsite populations resulting from postulated credible events and the safety features in place to control and mitigate the consequences

  15. Hazardous Waste/Mixed Waste Treatment Building Safety Information Document (SID)

    Energy Technology Data Exchange (ETDEWEB)

    Fatell, L.B.; Woolsey, G.B.

    1993-04-15

    This Safety Information Document (SID) provides a description and analysis of operations for the Hazardous Waste/Mixed Waste Disposal Facility Treatment Building (the Treatment Building). The Treatment Building has been classified as a moderate hazard facility, and the level of analysis performed and the methodology used are based on that classification. Preliminary design of the Treatment Building has identified the need for two separate buildings for waste treatment processes. The term Treatment Building applies to all these facilities. The evaluation of safety for the Treatment Building is accomplished in part by the identification of hazards associated with the facility and the analysis of the facility`s response to postulated events involving those hazards. The events are analyzed in terms of the facility features that minimize the causes of such events, the quantitative determination of the consequences, and the ability of the facility to cope with each event should it occur. The SID presents the methodology, assumptions, and results of the systematic evaluation of hazards associated with operation of the Treatment Building. The SID also addresses the spectrum of postulated credible events, involving those hazards, that could occur. Facility features important to safety are identified and discussed in the SID. The SID identifies hazards and reports the analysis of the spectrum of credible postulated events that can result in the following consequences: Personnel exposure to radiation; Radioactive material release to the environment; Personnel exposure to hazardous chemicals; Hazardous chemical release to the environment; Events leading to an onsite/offsite fatality; and Significant damage to government property. The SID addresses the consequences to the onsite and offsite populations resulting from postulated credible events and the safety features in place to control and mitigate the consequences.

  16. Preliminary results from the application of risk matrix method for safety assessment in industrial radiography

    International Nuclear Information System (INIS)

    Lopez G, A.; Cruz, D.; Truppa, W.; Aravena, M.; Tamayo, B.

    2015-09-01

    Although the uses of ionizing radiation in industry are subject to procedures that provide a high level of safety, experience has shown that equipment failure, human errors, or the combination of both that can trigger accidental exposures may occur. Traditionally, the radiation safety checks whether these industrial practices (industrial radiography, industrial irradiators, among others) are sufficiently safe to prevent similar accidental exposures already occurred, so that becomes dependent on the published information and not always answers questions like: What other events can occur, or what other risks are present? Taking into account the results achieved by the Foro Iberoamericano de Organismos Reguladores Radiologicos y Nucleares, its leading position in the use of techniques of risk analysis in radioactive facilities and the need to develop a proactive approach to the prevention of accidents arising from the use of ionizing radiations in the industry, it intends to apply the risk analysis technique known as Risk Matrix to a hypothetical reference entity for the region in which industrial radiography is performed. In this paper the results of the first stage of this study are shown, that is the identification of initiating events (IE) and barriers that help mitigate the consequences of such IE, so that can appreciate the applicability of this method to industrial radiography services, to reduce the risk to acceptable levels. The fundamental advantage associated with the application of this methodology is that can be applied by the professionals working in the service and identifies specific weaknesses that from the point of view of safety there, so they can be prioritized resources depending on risk reduction. (Author)

  17. Preliminary safety analysis of the Baita Bihor radioactive waste repository, Romania

    International Nuclear Information System (INIS)

    Little, Richard; Bond, Alex; Watson, Sarah; Dragolici, Felicia; Matyasi, Ludovic; Matyasi, Sandor; Naum, Mihaela; Niculae, Ortenzia; Thorne, Mike

    2007-01-01

    A project funded under the European Commission's Phare Programme 2002 has undertaken an in-depth analysis of the operational and post-closure safety of the Baita Bihor repository. The repository has accepted low- and some intermediate-level radioactive waste from industry, medical establishments and research activities since 1985 and the current estimate is that disposals might continue for around another 20 to 35 years. The analysis of the operational and post-closure safety of the Baita Bihor repository was carried out in two iterations, with the second iteration resulting in reduced uncertainties, largely as a result taking into account new information on the hydrology and hydrogeology of the area, collected as part of the project. Impacts were evaluated for the maximum potential inventory that might be available for disposal to Baita Bihor for a number of operational and postclosure scenarios and associated conceptual models. The results showed that calculated impacts were below the relevant regulatory criteria. In light of the assessment, a number of recommendations relating to repository operation, optimisation of repository engineering and waste disposals, and environmental monitoring were made. (authors)

  18. A risk informed safety classification for a Nordic NPP

    International Nuclear Information System (INIS)

    Jaenkaelae, K.

    2002-01-01

    The report describes a study to develop a safety classification proposal or classi- fication recommendations based on risks for selected equipment of a nuclear power plant. The application plant in this work is Loviisa NPP unit 1. The safety classification proposals are to be considered as an exercise in this pilot study and do not necessarily represent final proposals in a real situation. Comparisons to original safety classifications and technical specifications were made. The study concludes that it is possible to change safety classes or safety signifi- cances as considered in technical specifications and in in-service-inspections into both directions without endangering the safety or even by improving the safety. (au)

  19. AERB information booklet: personal protective equipment- safety footwear

    International Nuclear Information System (INIS)

    1992-01-01

    The main classes of safety footwear required for industrial operations in the units of Department of Atomic Energy are the following; leather safety boots and shoes, firemen's leather boots - Wellington type, electrical safety shoes, chemical safety shoes, shoes suitable for mining operations. The criteria to be adopted for selection of safety shoes for nuclear installations are given. (M.K.V.). 5 annexures, 1 appendix

  20. Risk-informed approaches to assess ecological safety of facilities with radioactive waste

    International Nuclear Information System (INIS)

    Vashchenko, V.N.; Zlochevskij, V.V.; Skalozubov, V.I.

    2011-01-01

    Ingenious risk-informed methods to assess ecological safety of facilities with radioactive waste are proposed in the paper. Probabilistic norms on lethal outcomes and reliability of safety barriers are used as safety criteria. Based on the probability measures, it is established that ecological safety conditions are met for the standard criterion of lethal outcomes

  1. Quantifying Safety Margin Using the Risk-Informed Safety Margin Characterization (RISMC)

    Energy Technology Data Exchange (ETDEWEB)

    Grabaskas, David; Bucknor, Matthew; Brunett, Acacia; Nakayama, Marvin

    2015-04-26

    The Risk-Informed Safety Margin Characterization (RISMC), developed by Idaho National Laboratory as part of the Light-Water Reactor Sustainability Project, utilizes a probabilistic safety margin comparison between a load and capacity distribution, rather than a deterministic comparison between two values, as is usually done in best-estimate plus uncertainty analyses. The goal is to determine the failure probability, or in other words, the probability of the system load equaling or exceeding the system capacity. While this method has been used in pilot studies, there has been little work conducted investigating the statistical significance of the resulting failure probability. In particular, it is difficult to determine how many simulations are necessary to properly characterize the failure probability. This work uses classical (frequentist) statistics and confidence intervals to examine the impact in statistical accuracy when the number of simulations is varied. Two methods are proposed to establish confidence intervals related to the failure probability established using a RISMC analysis. The confidence interval provides information about the statistical accuracy of the method utilized to explore the uncertainty space, and offers a quantitative method to gauge the increase in statistical accuracy due to performing additional simulations.

  2. Measuring mobile patient safety information system success: an empirical study.

    Science.gov (United States)

    Jen, Wen-Yuan; Chao, Chia-Cheng

    2008-10-01

    The Health Risk Reminders and Surveillance (HRRS) system was designed to deliver critical abnormal test results of severely ill patients from Laboratory, Radiology, and Pathology departments to physicians within 5 min using cell phone text messages. This paper explores the success of the HRRS system. This study employed an augmented version of the DeLone and McLean IS success model. Seven variables (system quality, information quality, system use, user satisfaction, mobile healthcare anxiety, impact on the individual and impact on the organization) were used to evaluate the success of the HRRS system. The interrelationships between the seven variables were hypothesized and the hypotheses were empirically tested. The results indicate that the information quality of the HRRS system is positively associated with both system use and user satisfaction. In addition, system use is positively associated with user satisfaction, which is also positively associated with mobile healthcare anxiety. Moreover, results indicate that impact on the individual is positively associated with both user satisfaction and mobile healthcare anxiety. Finally, the impact of the organization is positively associated with impact on the individual. The results of the study provide an expanded understanding of the factors that contribute to mobile patient safety information system (IS) success. Implications of the relationship between system use and physician mobile healthcare anxiety are discussed.

  3. An approach for risk informed safety culture assessment for Canadian nuclear power stations

    International Nuclear Information System (INIS)

    Nelson, W.R.

    2010-01-01

    One of the most important components of effective safety and risk management for nuclear power stations is a healthy safety culture. DNV has developed an approach for risk informed safety culture assessment that combines two complementary paradigms for safety and risk management: loss prevention - for preventing and intervening in accidents; and critical function management - for achieving safety and performance goals. Combining these two paradigms makes it possible to provide more robust systems for safety management and to support a healthy safety culture. This approach is being applied to safety culture assessment in partnership with a Canadian nuclear utility. (author)

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2013-08-15

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

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

    International Nuclear Information System (INIS)

    2013-01-01

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

  6. 77 FR 69899 - Public Conference on Geographic Information Systems (GIS) in Transportation Safety

    Science.gov (United States)

    2012-11-21

    ... NATIONAL TRANSPORTATION SAFETY BOARD Public Conference on Geographic Information Systems (GIS) in... Geographic Information Systems (GIS) in transportation safety on December 4-5, 2012. GIS is a rapidly... visualization of data. The meeting will bring researchers and practitioners in transportation safety and GIS...

  7. 10 CFR 52.157 - Contents of applications; technical information in final safety analysis report.

    Science.gov (United States)

    2010-01-01

    ...; technical information in final safety analysis report. The application must contain a final safety analysis... 10 Energy 2 2010-01-01 2010-01-01 false Contents of applications; technical information in final safety analysis report. 52.157 Section 52.157 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSES...

  8. 10 CFR 52.79 - Contents of applications; technical information in final safety analysis report.

    Science.gov (United States)

    2010-01-01

    ...; technical information in final safety analysis report. (a) The application must contain a final safety... 10 Energy 2 2010-01-01 2010-01-01 false Contents of applications; technical information in final safety analysis report. 52.79 Section 52.79 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSES...

  9. 75 FR 13807 - Pipeline Safety: Information Collection Activities

    Science.gov (United States)

    2010-03-23

    ... DEPARTMENT OF TRANSPORTATION Pipeline and Hazardous Materials Safety Administration [Docket No... of Transportation, Pipeline and Hazardous Materials Safety Administration, 1200 New Jersey Avenue, SE...: Updates to Pipeline and Liquefied Natural Gas Reporting Requirements (One Rule). The Notice of Proposed...

  10. User-oriented information access by information need recontextualisation and articulation. Application in nuclear criticality safety

    International Nuclear Information System (INIS)

    Medini, Lionel

    2001-01-01

    This research thesis addresses the design methodology of a system of access to information which is based on an access to relevant information with respect to user needs. In a first part, the author addresses the various issues related to access to information and to information understanding. The next part addresses the involved methods and tools and presents the operational approach adopted for this research regarding access to information. Different disciplines are addressed (knowledge management, ergonomics and information science) and different technologies are used (W3 and XML, DVP, ActiveX, pdf format and the Adobe suite). In the core chapter, the author reports the design of a LMCE (a multi-user book of electronic knowledge) which allows both hypermedia navigation in knowledge diagrams and a construction of a document query. This design is based on a knowledge-management modelling to define diagrams, on ergonomics modelling for user profile identification, and on information science for a specific indexing of the information system. The prototype can be visualized with a web browser such as Internet Explorer 5. The author reports a first assessment and discusses the contribution of his approach to the problematic of access to information which is to be applied to nuclear criticality safety [fr

  11. Bridging probabilistic safety assessment studies with information Management System

    International Nuclear Information System (INIS)

    Luanco, E. M.

    2010-01-01

    Probabilistic Safety Assessment (PSA) is a critical business often known in conjunction with either new build or life extension of nuclear power plant. However, it is not so often referred to the operation phase of the plant, although it could bring a lot of long term benefits to the operator. The purpose of this paper is to discuss the potential contribution of PSA with day to day operation in bridging the deficiencies and specific failures characteristics of critical Structure System and Component (SSC) with the results of PSA studies. From and Information System prospective, the use of Information Management system (IMS) -also known as EAM solution -widely used by the majority of nuclear operators- is the potential vehicle to bridge the 2 worlds of PSA and daily operation. Most EAM solution get reliability management functionalities which are not really integrated with PSA tools and data and thus cannot provide the anticipated benefits of addressing typical aging phenomena beyond the only predictive models used by the PSA studies. The paper will also discuss potential integration scenario between PSA tools and EAM solutions. (authors)

  12. Risk-informed decision making during Bohunice NPP safety upgrading

    International Nuclear Information System (INIS)

    Lipar, M.; Muzikova, E.; Kubanyi, J.

    2001-01-01

    The paper summarizes some facts of risk-informed regulation developments within UJD regulatory environment. Based on national as well as international operating experience and indications resulted from PSA, Nuclear Regulatory Authority of the Slovak Republic (UJD) since its constituting in 1993 has devoted an effort to use PSA technology to support the regulatory policy in Slovakia. The PSA is considered a complement, not a substitute, to the deterministic approach. Suchlike integrated approach is used in decision making processes and the final decision on scope and priorities is based on it. The paper outlines risk insights used in the decision making process concerning Bohunice NPP safety upgrading and focuses on the role of PSA results in Gradual Reconstruction of Bohunice VI NPP. Besides, two other examples of the PSA results application to the decision making process are provided: the assessment of proposal of modifications to the main power supply diagram (incorporation of generator switches) and the assessment of licensee request for motor generator AOT (Allowable Outage Time) extension. As an example of improving support of Bohunice V-2 risk-informed operations, concept of AOT calculations and Bohunice V-2 Risk Monitor Project are briefly described. (author)

  13. 77 FR 22387 - Pipeline Safety: Information Collection Activities, Revision to Gas Transmission and Gathering...

    Science.gov (United States)

    2012-04-13

    ... DEPARTMENT OF TRANSPORTATION Pipeline and Hazardous Materials Safety Administration [Docket No. PHMSA-2012-0024] Pipeline Safety: Information Collection Activities, Revision to Gas Transmission and Gathering Pipeline Systems Annual Report, Gas Transmission and Gathering Pipeline Systems Incident Report...

  14. 77 FR 58616 - Pipeline Safety: Information Collection Activities, Revision to Gas Transmission and Gathering...

    Science.gov (United States)

    2012-09-21

    ... DEPARTMENT OF TRANSPORTATION Pipeline and Hazardous Materials Safety Administration [Docket No. PHMSA-2012-0024] Pipeline Safety: Information Collection Activities, Revision to Gas Transmission and Gathering Pipeline Systems Annual Report, Gas Transmission and Gathering Pipeline Systems Incident Report...

  15. Preliminary survey on the information campaign on nuclear energy of the Austrian Government

    International Nuclear Information System (INIS)

    Hirsch, H.

    1977-01-01

    To provide adequate, unbiased information to the public as well as basic material for future decisions concerning nuclear energy to parliament, the Austrian Government began the Information Campaign on Nuclear Energy in October 1976 and it will continue to June 1977. In the first phase of this campaign, teams of experts consisting of promoters and critics of nuclear energy discussed the various aspects of this topic in public as well as in internal debates, finally producing exhaustive reports. In the second phase, scheduled to take place in May and June 1977, these reports will be discussed in a series of symposia by representatives of the different viewpoints of the Austrian public on nuclear energy. They will then be submitted to parliament together with a summary provided by the Government. The motivation of the campaign, the preparation and execution of the first phase, as well as the first steps in the preparation of the second pahse, are described. Preliminary analyses concern: a) the interaction between the authorities, the experts and the public; b) the interaction among the experts; c) the character of the protest movement and its activities and the public activities of the promoters of nuclear energy; d) the role of the mass media and the information flow in society; and, very cursorily; e) the international echo. Preliminary conclusions are drawn on the organisation of the process of optimal transfer of information to the public, consensus-finding in society and decision-making; a comparison with experiences in other countries is attempted

  16. Posiva's application for a decision in principle concerning a disposal facility for spent nuclear fuel. STUK's statement and preliminary safety appraisal

    International Nuclear Information System (INIS)

    Ruokola, E.

    2000-03-01

    In May 1999, Posiva Ltd submitted to the Government an application, pursuant to the Nuclear Energy Act, for a Decision in Principle on a disposal facility for spent nuclear fuel from the Finnish nuclear power plants. The Ministry of Trade and Industry requested the Radiation and Nuclear Safety Authority (STUK) to draw up a preliminary safety appraisal concerning the proposed disposal facility. In the beginning of this report, STUK's statement to the Ministry and Industry concerning the proposed disposal facility is given. In that statement, STUK concludes that the Decision in Principle is currently justified from the standpoint of safety. The statement is followed by a safety appraisal, where STUK deems, how the proposed disposal concept, site and facility comply with the safety requirements included in the Government's Decision (478/1999). STUK's preliminary safety appraisal was supported by contributions from a number of outside experts. A collective opinion by an international group of ten distinguished experts is appended to this report. (orig.)

  17. The eNanoMapper database for nanomaterial safety information

    Directory of Open Access Journals (Sweden)

    Nina Jeliazkova

    2015-07-01

    Full Text Available Background: The NanoSafety Cluster, a cluster of projects funded by the European Commision, identified the need for a computational infrastructure for toxicological data management of engineered nanomaterials (ENMs. Ontologies, open standards, and interoperable designs were envisioned to empower a harmonized approach to European research in nanotechnology. This setting provides a number of opportunities and challenges in the representation of nanomaterials data and the integration of ENM information originating from diverse systems. Within this cluster, eNanoMapper works towards supporting the collaborative safety assessment for ENMs by creating a modular and extensible infrastructure for data sharing, data analysis, and building computational toxicology models for ENMs.Results: The eNanoMapper database solution builds on the previous experience of the consortium partners in supporting diverse data through flexible data storage, open source components and web services. We have recently described the design of the eNanoMapper prototype database along with a summary of challenges in the representation of ENM data and an extensive review of existing nano-related data models, databases, and nanomaterials-related entries in chemical and toxicogenomic databases. This paper continues with a focus on the database functionality exposed through its application programming interface (API, and its use in visualisation and modelling. Considering the preferred community practice of using spreadsheet templates, we developed a configurable spreadsheet parser facilitating user friendly data preparation and data upload. We further present a web application able to retrieve the experimental data via the API and analyze it with multiple data preprocessing and machine learning algorithms.Conclusion: We demonstrate how the eNanoMapper database is used to import and publish online ENM and assay data from several data sources, how the “representational state

  18. The eNanoMapper database for nanomaterial safety information.

    Science.gov (United States)

    Jeliazkova, Nina; Chomenidis, Charalampos; Doganis, Philip; Fadeel, Bengt; Grafström, Roland; Hardy, Barry; Hastings, Janna; Hegi, Markus; Jeliazkov, Vedrin; Kochev, Nikolay; Kohonen, Pekka; Munteanu, Cristian R; Sarimveis, Haralambos; Smeets, Bart; Sopasakis, Pantelis; Tsiliki, Georgia; Vorgrimmler, David; Willighagen, Egon

    2015-01-01

    The NanoSafety Cluster, a cluster of projects funded by the European Commision, identified the need for a computational infrastructure for toxicological data management of engineered nanomaterials (ENMs). Ontologies, open standards, and interoperable designs were envisioned to empower a harmonized approach to European research in nanotechnology. This setting provides a number of opportunities and challenges in the representation of nanomaterials data and the integration of ENM information originating from diverse systems. Within this cluster, eNanoMapper works towards supporting the collaborative safety assessment for ENMs by creating a modular and extensible infrastructure for data sharing, data analysis, and building computational toxicology models for ENMs. The eNanoMapper database solution builds on the previous experience of the consortium partners in supporting diverse data through flexible data storage, open source components and web services. We have recently described the design of the eNanoMapper prototype database along with a summary of challenges in the representation of ENM data and an extensive review of existing nano-related data models, databases, and nanomaterials-related entries in chemical and toxicogenomic databases. This paper continues with a focus on the database functionality exposed through its application programming interface (API), and its use in visualisation and modelling. Considering the preferred community practice of using spreadsheet templates, we developed a configurable spreadsheet parser facilitating user friendly data preparation and data upload. We further present a web application able to retrieve the experimental data via the API and analyze it with multiple data preprocessing and machine learning algorithms. We demonstrate how the eNanoMapper database is used to import and publish online ENM and assay data from several data sources, how the "representational state transfer" (REST) API enables building user friendly

  19. Dataset for Phase I randomized clinical trial for safety and tolerability of GET 73 in single and repeated ascending doses including preliminary pharmacokinetic parameters.

    Science.gov (United States)

    Haass-Koffler, Carolina L; Goodyear, Kimberly; Long, Victoria M; Tran, Harrison H; Loche, Antonella; Cacciaglia, Roberto; Swift, Robert M; Leggio, Lorenzo

    2017-12-01

    The data in this article outline the methods used for the administration of GET 73 in the first time-in-human manuscript entitled "Phase I randomized clinical trial for the safety, tolerability and preliminary pharmacokinetics of the mGluR5 negative allosteric modulator GET 73 following single and repeated doses in healthy male volunteers" (Haass-Koffler et al., 2017) [1]. Data sets are provided in two different manners. The first series of tables provided includes procedural information about the experiments conducted. The next series of tables provided includes Pharmacokinetic (PK) parameters for GET 73 and its main metabolite MET 2. This set of data is comprised by two experiments: Experiment 1 references a single ascending dose administration of GET 73 and Experiment 2 references a repeated ascending dose administration of GET 73.

  20. Information Management of Health and Safety at the Tarkwa Mine of ...

    African Journals Online (AJOL)

    Michael

    2016-06-01

    Jun 1, 2016 ... Information Management of Health and Safety at the Tarkwa ... heap leach technology. ... the quality of information was assessed using the content of information ..... managing library users' expectations; and reference service.

  1. Preliminary study on functional performance of compound type multistage safety injection tank

    International Nuclear Information System (INIS)

    Bae, Youngmin; Kim, Young In; Kim, Keung Koo

    2015-01-01

    Highlights: • Functional performance of compound type multistage safety injection tanks is studied. • Effects of key design parameters are scrutinized. • Distinctive flow features in compound type safety injection tanks are explored. - Abstract: A parametric study is carried out to evaluate the functional performance of a compound type multistage safety injection tank that would be considered one of the components for the passive safety injection systems in nuclear power plants. The effects of key design parameters such as the initial volume fraction and charging pressure of gas, tank elevation, vertical location of a sparger, resistance coefficient, and operating condition on the injection flow rate are scrutinized along with a discussion of the relevant flow features. The obtained results indicate that the compound type multistage safety injection tank can effectively control the injection flow rate in a passive manner, by switching the driving force for the safety injection from gas pressure to gravity during the refill and reflood phases, respectively

  2. A preliminary study on the design in architecture of nuclear and radiation safety standard system

    International Nuclear Information System (INIS)

    Song Dahu; Zhang Chi; Yang Lili; Li Bin; Liu Yingwei; An Hongzhen; Gao Siyi; Liu Ting; Meng De

    2014-01-01

    The connotation and function of nuclear and radiation safety standards are analyzed, and their relationships with the relevant laws and regulations are discussed in the paper. Some suggestions and blue print of overall architecture to build nuclear and radiation safety standard system are proposed, on the basis of researching the application status quo, existing problems and needs for nuclear and radiation safety standards in China. This work is a beneficial exploration and attempt to establish China's nuclear and radiation safety standards. (authors)

  3. PROMISE: A preliminary study of a scientific information system for MIPAS satellite experiment

    International Nuclear Information System (INIS)

    Kapetanios, E.

    1993-08-01

    A scientific information system for MIPAS satellite experiment will be presented according to its main hardware and software configuration. It will be considered as a MIPAS data processing and archiving node of the ground segment of the planned satellite mission for the remote sensing of atmospheric parameters, as well as an information system supporting the researchers in their scientific environment. In this preliminary study, the methodology of a more detailed system design has also been specified. The system consists of two logical components, an operational database for the generation, storage and management of vast amounts of MIPAS data received from the satellite, and the research and development database, which must be interfaced to the operational one, providing a more abstract and user-friendly interface for the scientific community enabling experimentation and the extraction of the information needed. (orig.) [de

  4. Feasibility, safety, acceptability, and preliminary efficacy of measurement-based care depression treatment for HIV patients in Bamenda, Cameroon.

    Science.gov (United States)

    Pence, Brian W; Gaynes, Bradley N; Atashili, Julius; O'Donnell, Julie K; Kats, Dmitry; Whetten, Kathryn; Njamnshi, Alfred K; Mbu, Tabenyang; Kefie, Charles; Asanji, Shantal; Ndumbe, Peter

    2014-06-01

    Depression affects 18-30 % of HIV-infected patients in Africa and is associated with greater stigma, lower antiretroviral adherence, and faster disease progression. However, the region's health system capacity to effectively identify and treat depression is limited. Task-shifting models may help address this large mental health treatment gap. Measurement-Based Care (MBC) is a task-shifting model in which a Depression Care Manager guides a non-psychiatric (e.g., HIV) provider in prescribing and managing antidepressant treatment. We adapted MBC for depressed HIV-infected patients in Cameroon and completed a pilot study to assess feasibility, safety, acceptability, and preliminary efficacy. We enrolled 55 participants; all started amitriptyline 25-50 mg daily at baseline. By 12 weeks, most remained at 50 mg daily (range 25-125 mg). Median (interquartile range) PHQ-9 depressive severity scores declined from 13 (12-16) (baseline) to 2 (0-3) (week 12); 87 % achieved depression remission (PHQ-9 feasibility, safety, acceptability, and preliminary efficacy in this uncontrolled pilot study. Further research should assess whether MBC could improve adherence and HIV outcomes in this setting.

  5. Preliminary post-closure safety assessment of repository concepts for low level radioactive waste at the Bruce Site, Ontario

    International Nuclear Information System (INIS)

    Little, R.H.; Penfold, J.S.S.; Egan, M.J.; Leung, H.

    2005-01-01

    The preliminary post-closure safety assessment of permanent repository concepts for low-level radioactive waste (LLW) at the Ontario Power Generation (OPG) Bruce Site is described. The study considered the disposal of both short and long-lived LLW. Four geotechnically feasible repository concepts were considered (two near-surface and two deep repositories). An approach consistent with best international practice was used to provide a reasoned and comprehensive analysis of post-closure impacts of the repository concepts. The results demonstrated that the deep repository concepts in shale and in limestone, and the surface repository concept on sand should meet radiological protection criteria. For the surface repository concept on glacial till, it appears that increased engineering such as grouting of waste and voids should be considered to meet the relevant dose constraint. Should the project to develop a permanent repository for LLW proceed, it is expected that this preliminary safety assessment would need to be updated to take account of future site-specific investigations and design updates. (author)

  6. Undetected latent failures of safety-related systems. Preliminary survey of events in nuclear power plants 1980-1997

    Energy Technology Data Exchange (ETDEWEB)

    Lydell, B. [RSA Technologies, Vista, CA (United States)

    1998-03-01

    This report summarizes results and insights from a preliminary survey of events involving undetected, latent failures of safety-related systems. The survey was limited to events where mispositioned equipment (e.g., valves, switches) remained undetected, thus rendering standby equipment or systems unavailable for short or long time periods. Typically, these events were symptoms of underlying latent errors (e.g., design errors, procedure errors, unanalyzed safety conditions) and programmatic errors. The preliminary survey identified well over 300 events. Of these, 95 events are documented in this report. Events involving mispositioned equipment are commonplace. Most events are discovered soon after occurrence, however. But as evidenced by the survey results, some events remained undetected beyond several shift changes. The recommendations developed by the survey emphasize the importance of applying modern root cause analysis techniques to the event analysis to ensure that the causes and implications of occurred events are fully understood. 7 refs, 4 tabs, 3 figs. Also available at the SKI Home page: //www.ski.se.

  7. Comprehensive development plans for the low- and intermediate-level radioactive waste disposal facility in Korea and preliminary safety assessment

    Energy Technology Data Exchange (ETDEWEB)

    Jung, Kang Il; Kim, Jin Hyeong; Kwon, Mi Jin; Jeong, Mi Seon; Hong, Sung Wook; Park, Jin Beak [Korea Radioactive Waste Agency, Daejeon (Korea, Republic of)

    2016-12-15

    The disposal facility in Gyeongju is planning to dispose of 800,000 packages of low- and intermediate- level radioactive waste. This facility will be developed as a complex disposal facility that has various types of disposal facilities and accompanying management. In this study, based on the comprehensive development plan of the disposal facility, a preliminary post-closure safety assessment is performed to predict the phase development of the total capacity for the 800,000 packages to be disposed of at the site. The results for each scenario meet the performance target of the disposal facility. The assessment revealed that there is a significant impact of the inventory of intermediate-level radionuclide waste on the safety evaluation. Due to this finding, we introduce a disposal limit value for intermediate-level radioactive waste. With stepwise development of safety case, this development plan will increase the safety of disposal facilities by reducing uncertainties within the future development of the underground silo disposal facilities.

  8. Integrated care: an Information Model for Patient Safety and Vigilance Reporting Systems.

    Science.gov (United States)

    Rodrigues, Jean-Marie; Schulz, Stefan; Souvignet, Julien

    2015-01-01

    Quality management information systems for safety as a whole or for specific vigilances share the same information types but are not interoperable. An international initiative tries to develop an integrated information model for patient safety and vigilance reporting to support a global approach of heath care quality.

  9. Preliminary study to questions relating to the safety of nuclear power plants A and B at Biblis

    International Nuclear Information System (INIS)

    Fischer, B.; Hahn, L.; Rausch, L.

    1985-01-01

    With a view to developing suitable tools for the safety evaluation of reactors A and B at Biblis, the publication compiles all aspects relevant to safety, creates an evaluation frame, and evaluates the aspects relevant to safety by means of this frame of evaluation. According to the composition of the work, the overall subject is split up into the complexes information, acquisition, evaluation of operational experience, probabilistic analyses, comparison with newer PWR type reactors, fulfilling of injunctions, modifications due to disposal problems, and the disposal situation. (DG) [de

  10. A preliminary study on safety stock placement in capacitated supply chains

    NARCIS (Netherlands)

    Sitompul, Carles; Aghezzaf, El Houssaine; Chen, Huan; Dullaert, Wout

    2006-01-01

    The issue of safety stock placement is one of the challenging problems in the area of supply chain design. Safety stocks play a significant role in supply chains since they assure the service level and the smoothness of the flow of materials throughout the chain. Some special models of the problem

  11. A PRELIMINARY STUDY ON SAFETY STOCK PLACEMENT IN CAPACITATED SUPPLY CHAINS

    NARCIS (Netherlands)

    Sitompul, Carles; Aghezzaf, El Houssaine; Chen, Huan; Dullaert, Wout; Dolgui, A.; Morel, G.; Pereira, C.E.

    2006-01-01

    Abstract The issue of safety stock placement is one of the challenging problems in the area of supply chain design. Safety stocks play a significant role in supply chains since they assure the service level and the smoothness of the flow of materials throughout the chain. Some special models of the

  12. A phenomenographic investigation into Information Literacy in nursing practice - preliminary findings and methodological issues.

    Science.gov (United States)

    Forster, Marc

    2013-10-01

    Information Literacy is essential to 'evidence-based practice'; without the ability to locate evidence, evidence-based practice is rendered extremely difficult if not impossible. There is currently little evidence to show how Information Literacy is experienced by nurses or what its parameters are within evidence-based practice and therefore whether Information Literacy educational interventions are actually promoting the correct knowledge and skills. Using phenomenographic interviews the author will attempt to discover how nurses experience Information Literacy. Insights from the findings will be used to map out its parameters and to put forward a theoretical model for a course or module to develop it effectively. This article presents preliminary findings, including 7 draft categories of description of how Information Literacy is experienced in nursing. This pilot study indicates that the complete findings may be of significant potential value in the promotion and development of Information Literacy education in nursing. It is argued that such insights into how nurses actually experience the phenomenon of Information Literacy can be used to develop potentially more effective, research-based, educational interventions. Copyright © 2012 Elsevier Ltd. All rights reserved.

  13. 75 FR 73160 - Pipeline Safety: Information Collection Activities

    Science.gov (United States)

    2010-11-29

    ... DEPARTMENT OF TRANSPORTATION Pipeline and Hazardous Materials Safety Administration [Docket No...-Related Conditions on Gas, Hazardous Liquid, and Carbon Dioxide Pipelines and Liquefied Natural Gas... Pipelines and Liquefied Natural Gas Facilities.'' The Pipeline Safety Laws (49 U.S.C. 60132) require each...

  14. 76 FR 45904 - Pipeline Safety: Information Collection Activities

    Science.gov (United States)

    2011-08-01

    ... DEPARTMENT OF TRANSPORTATION Pipeline and Hazardous Materials Safety Administration [Docket No... at U.S. Department of Transportation, Pipeline and Hazardous Materials Safety Administration, 1200...: On Occasion. Title: Record Keeping for Natural Gas Pipeline Operators. OMB Control Number: 2137-0049...

  15. 49 CFR 575.301 - Vehicle Labeling of Safety Rating Information.

    Science.gov (United States)

    2010-10-01

    ... providing them with safety rating information developed by NHTSA in its New Car Assessment Program (NCAP..., as specified at 15 U.S.C. 1231-1233. (2) Safety rating label means the label with NCAP safety rating... has approved an optional NCAP test that will cover that category, the manufacturer may depict vehicles...

  16. 75 FR 36615 - Pipeline Safety: Information Collection Gas Distribution Annual Report Form

    Science.gov (United States)

    2010-06-28

    ... DEPARTMENT OF TRANSPORTATION Pipeline and Hazardous Materials Safety Administration 49 CFR Part 192 [Docket No. PHMSA-RSPA-2004-19854] Pipeline Safety: Information Collection Gas Distribution Annual Report Form AGENCY: Pipeline and Hazardous Materials Safety Administration (PHMSA), DOT. ACTION: Request...

  17. Evaluating and Predicting Patient Safety for Medical Devices With Integral Information Technology

    Science.gov (United States)

    2005-01-01

    323 Evaluating and Predicting Patient Safety for Medical Devices with Integral Information Technology Jiajie Zhang, Vimla L. Patel, Todd R...errors are due to inappropriate designs for user interactions, rather than mechanical failures. Evaluating and predicting patient safety in medical ...the users on the identified trouble spots in the devices. We developed two methods for evaluating and predicting patient safety in medical devices

  18. 29 CFR 1960.12 - Dissemination of occupational safety and health program information.

    Science.gov (United States)

    2010-07-01

    ... 29 Labor 9 2010-07-01 2010-07-01 false Dissemination of occupational safety and health program... OCCUPATIONAL SAFETY AND HEALTH PROGRAMS AND RELATED MATTERS Administration § 1960.12 Dissemination of occupational safety and health program information. (a) Copies of the Act, Executive Order 12196, program...

  19. Criteria for safety-related nuclear plant operator actions: a preliminary assessment of available data

    International Nuclear Information System (INIS)

    Haas, P.M.; Bott, T.F.

    1980-01-01

    In the US, an effort has been underway for a number of years to develop a design standard to define when required manual operator action can be accepted as part of a nuclear plant design basis. Insufficient data are available to provide quantitative guidelines for the standard. To provide the necessary data base to support such standards and the necessary quantitative assessment of operator reliability, the US Nuclear Regulatory Commission is sponsoring a study at Oak National Laboratory to develop the data base. A preliminary assessment completed in April, 1979 concluded that sufficient data from US operating experience did not exist to provide an adequate data base. A program of research using full-scope nuclear plant simulators and results that are correlated to field data was suggested. That program was recently initiated. The approach, results and conclusions of the preliminary assessment are reviewed and the planned research program of simulator studies is summarised. (author)

  20. Preliminary Assessment of Operational Hazards and Safety Requirements for Airborne Trajectory Management (ABTM) Roadmap Applications

    Science.gov (United States)

    Cotton, William B.; Hilb, Robert; Koczo, Stefan, Jr.; Wing, David J.

    2016-01-01

    A set of five developmental steps building from the NASA TASAR (Traffic Aware Strategic Aircrew Requests) concept are described, each providing incrementally more efficiency and capacity benefits to airspace system users and service providers, culminating in a Full Airborne Trajectory Management capability. For each of these steps, the incremental Operational Hazards and Safety Requirements are identified for later use in future formal safety assessments intended to lead to certification and operational approval of the equipment and the associated procedures. Two established safety assessment methodologies that are compliant with the FAA's Safety Management System were used leading to Failure Effects Classifications (FEC) for each of the steps. The most likely FEC for the first three steps, Basic TASAR, Digital TASAR, and 4D TASAR, is "No effect". For step four, Strategic Airborne Trajectory Management, the likely FEC is "Minor". For Full Airborne Trajectory Management (Step 5), the most likely FEC is "Major".

  1. Preliminary safety concept for disposal of the very low level radioactive waste in Romania.

    Science.gov (United States)

    Niculae, O; Andrei, V; Ionita, G; Duliu, O G

    2009-05-01

    In Romania, there are certain nuclear installations in operation or under decommissioning, all of them representing an important source of very low level waste (VLLW). This paper presents an overview on the approach of the VLLW management in Romania, focused on those resulted from the nuclear power plants decommissioning. At the same time, the basic elements of safety concept, together with some safety evaluations concerning VLLW repository are presented and discussed too.

  2. Safety

    International Nuclear Information System (INIS)

    Jones, P.M.S.

    1987-01-01

    Aspects of fission reactors are considered - control, heat removal and containment. Brief descriptions of the reactor accidents at the SL-1 reactor (1961), Windscale (1957), Browns Ferry (1975), Three Mile Island (1979) and Chernobyl (1986) are given. The idea of inherently safe reactor designs is discussed. Safety assessment is considered under the headings of preliminary hazard analysis, failure mode analysis, event trees, fault trees, common mode failure and probabalistic risk assessments. These latter can result in a series of risk distributions linked to specific groups of fault sequences and specific consequences. A frequency-consequence diagram is shown. Fatal accident incidence rates in different countries including the United Kingdom for various industries are quoted. The incidence of fatal cancers from occupational exposure to chemicals is tabulated. Human factors and the acceptability of risk are considered. (U.K.)

  3. Additional information for impact response of the restart safety rods

    International Nuclear Information System (INIS)

    Yau, W.W.F.

    1991-01-01

    WSRC-RP-91-677 studied the structural response of the safety rods under the conditions of brake failure and accidental release. It was concluded that the maximum impact loading to the safety rod is 6020 pounds based on conservative considerations that energy dissipation attributable to fluid resistance and reactor superstructure flexibility. The staffers of the Defense Nuclear Facility Safety Board reviewed the results and inquired about the extent of conservatism. By request of the RESTART team, I reassessed the impact force due to these conservative assumptions. This memorandum reports these assessments

  4. Occupational health and safety in the Moroccan construction sites: preliminary diagnosis

    Science.gov (United States)

    Tarik, Bakeli; Adil, Hafidi Alaoui

    2018-05-01

    Managing occupational health and safety on Moroccan construction sector represents the first step for projects' success. In fact, by avoiding accidents, all the related direct and indirect costs and delays can be prevented. That leads to an important question always asked by any project manager: what are the factors responsible for accidents? How can they be avoided? Through this research, the aim is to go through these questions, to contribute in occupational health and safety principles understanding, to identify construction accidentology and risk management opportunities and to approach the case of Moroccan construction sites by an accurate diagnosis. The approach is to make researchers, managers, stakeholders and deciders aware about the criticality of construction sites health and safety situation. And, to do the first step for a scientific research project in relation with health and safety in the Moroccan construction sector. For this, the paper will study the related state of art namely about construction sites accidents causation, and will focus on Reason's `Swiss cheese' model and its utilization for Moroccan construction sites health and safety diagnosis. The research will end with an estimation of an accidents fatality rate in the Moroccan construction sector and a benchmarking with the international rates. Finally, conclusions will be presented about the necessity of Occupational Health and Safety Management System (OHSMS) implementation, which shall cover all risk levels, and insure, at the same time, that the necessary defenses against accidents are on place.

  5. Preliminary Findings from an Analysis of Building Energy Information System Technologies

    Energy Technology Data Exchange (ETDEWEB)

    Granderson, Jessica; Piette, Mary Ann; Ghatikar, Girish; Price, Philip

    2009-06-01

    Energy information systems comprise software, data acquisition hardware, and communication systems that are intended to provide energy information to building energy and facilities managers, financial managers, and utilities. This technology has been commercially available for over a decade, however recent advances in Internet and other information technology, and analytical features have expanded the number of product options that are available. For example, features such as green house gas tracking, configurable energy analyses and enhanced interoperability are becoming increasingly common. Energy information systems are used in a variety of commercial buildings operations and environments, and can be characterized in a number of ways. Basic elements of these systems include web-based energy monitoring, web-based energy management linked to controls, demand response, and enterprise energy management applications. However the sheer number and variety of available systems complicate the selection of products to match the needs of a given user. In response, a framework was developed to define the capabilities of different types of energy information systems, and was applied to characterize approximately 30 technologies. Measurement is a critical component in managing energy consumption and energy information must be shared at all organizational levels to maintain persistent, efficient operations. Energy information systems are important to understand because they offer the analytical support to process measured data into information, and they provide the informational link between the primary actors who impact building energy efficiency - operators, facilities and energy managers, owners and corporate decision makers. In this paper, preliminary findings are presented, with a focus on overall trends and the general state of the technology. Key conclusions include the need to further pursue standardization and usability, x-y plotting as an under-supported feature, and

  6. 77 FR 51848 - Pipeline Safety: Information Collection Activities

    Science.gov (United States)

    2012-08-27

    ... DEPARTMENT OF TRANSPORTATION Pipeline and Hazardous Materials Safety Administration [Docket No... Program for Gas Distribution Pipelines. DATES: Interested persons are invited to submit comments on or.... These regulations require operators of hazardous liquid pipelines and gas pipelines to develop and...

  7. 76 FR 65778 - Pipeline Safety: Information Collection Activities

    Science.gov (United States)

    2011-10-24

    ... DEPARTMENT OF TRANSPORTATION Pipeline and Hazardous Materials Safety Administration [Docket No...: 12,120. Frequency of Collection: On occasion. 2. Title: Recordkeeping for Natural Gas Pipeline... investigating incidents. Affected Public: Operators of natural gas pipeline systems. Annual Reporting and...

  8. 77 FR 74275 - Pipeline Safety: Information Collection Activities

    Science.gov (United States)

    2012-12-13

    ... DEPARTMENT OF TRANSPORTATION Pipeline and Hazardous Materials Safety Administration [Docket No.... These regulations require operators of hazardous liquid pipelines and gas pipelines to develop and... control room. Affected Public: Operators of both natural gas and hazardous liquid pipeline systems. Annual...

  9. 77 FR 27279 - Pipeline Safety: Information Collection Activities

    Science.gov (United States)

    2012-05-09

    ... DEPARTMENT OF TRANSPORTATION Pipeline and Hazardous Materials Safety Administration [Docket No... collections relate to the pipeline integrity management requirements for gas transmission pipeline operators... Management in High Consequence Areas Gas Transmission Pipeline Operators. OMB Control Number: 2137-0610...

  10. 77 FR 46155 - Pipeline Safety: Information Collection Activities

    Science.gov (United States)

    2012-08-02

    ... DEPARTMENT OF TRANSPORTATION Pipeline and Hazardous Materials Safety Administration [Docket No... collections relate to the pipeline integrity management requirements for gas transmission pipeline operators... Management in High Consequence Areas Gas Transmission Pipeline Operators. OMB Control Number: 2137-0610...

  11. Criticality Safety Information Resource Center Web portal: www.csirc.net

    International Nuclear Information System (INIS)

    Harmon, C.D. II; Jones, T.

    2000-01-01

    The Nuclear Criticality Safety Group (ESH-6) at Los Alamos National Laboratory (LANL) is in the process of collecting and archiving historical and technical information related to nuclear criticality safety from LANL and other facilities. In an ongoing effort, this information is being made available via the Criticality Safety Information Resource Center (CSIRC) web site, which is hosted and maintained by ESH-6 staff. Recently, the CSIRC Web site was recreated as a Web portal that provides the criticality safety community with much more than just archived data

  12. Patterns of patient safety culture: a complexity and arts-informed project of knowledge translation.

    Science.gov (United States)

    Mitchell, Gail J; Tregunno, Deborah; Gray, Julia; Ginsberg, Liane

    2011-01-01

    The purpose of this paper is to describe patterns of patient safety culture that emerged from an innovative collaboration among health services researchers and fine arts colleagues. The group engaged in an arts-informed knowledge translation project to produce a dramatic expression of patient safety culture research for inclusion in a symposium. Scholars have called for a deeper understanding of the complex interrelationships among structure, process and outcomes relating to patient safety. Four patterns of patient safety culture--blinding familiarity, unyielding determination, illusion of control and dismissive urgency--are described with respect to how they informed creation of an arts-informed project for knowledge translation.

  13. Preliminary design of safety and interlock system for indian test facility of diagnostic neutral beam

    International Nuclear Information System (INIS)

    Tyagi, Himanshu; Soni, Jignesh; Yadav, Ratnakar; Bandyopadhyay, Mainak; Rotti, Chandramouli; Gahlaut, Agrajit; Joshi, Jaydeep; Parmar, Deepak; Bansal, Gourab; Pandya, Kaushal; Chakraborty, Arun

    2016-01-01

    Highlights: • Indian Test Facility being built to characterize DNB for ITER delivery. • Interlock system required to safeguard the investment incurred in building the facility and protecting ITER deliverable components. • Interlock levels upto 3IL-3 identified. • Safety instrumented system for occupational safety being designed. Safety I&C functions of SIL-2 identified. • The systems are based on ITER PIS and PSS design guidelines. - Abstract: Indian Test Facility (INTF) is being built in Institute For Plasma Research to characterize Diagnostic Neutral Beam in co-operation with ITER Organization. INTF is a complex system which consists of several plant systems like beam source, gas feed, vacuum, cryogenics, high voltage power supplies, high power RF generators, mechanical systems and diagnostics systems. Out of these, several INTF components are ITER deliverable, that is, beam source, beam line components and power supplies. To ensure successful operation of INTF involving integrated operation of all the constituent plant systems a matured Data Acquisition and Control System (DACS) is required. The INTF DACS is based on CODAC platform following on PCDH (Plant Control Design Handbook) guidelines. The experimental phases involve application of HV power supplies (100 KV) and High RF power (∼800 KW) which will produce energetic beam of maximum power 6MW within the facility for longer durations. Hence the entire facility will be exposed tohigh heat fluxes and RF radiations. To ensure investment protection and to provide occupational safety for working personnel a matured Safety and Interlock system is required for INTF. The Safety and Interlock systems are high-reliability I&C systems devoted completely to the specific functions. These systems will be separate from the conventional DACS of INTF which will handle the conventional control and acquisition functions. Both, the Safety and Interlock systems are based on IEC 61511 and IEC 61508 standards as

  14. Preliminary design of safety and interlock system for indian test facility of diagnostic neutral beam

    Energy Technology Data Exchange (ETDEWEB)

    Tyagi, Himanshu, E-mail: htyagi@iter-india.org [ITER-India, Institute For Plasma Research, Bhat, Gandhinagar, Gujarat (India); Soni, Jignesh [Institute For Plasma Research, Bhat, Gandhinagar, Gujarat (India); Yadav, Ratnakar; Bandyopadhyay, Mainak; Rotti, Chandramouli [ITER-India, Institute For Plasma Research, Bhat, Gandhinagar, Gujarat (India); Gahlaut, Agrajit [Institute For Plasma Research, Bhat, Gandhinagar, Gujarat (India); Joshi, Jaydeep; Parmar, Deepak [ITER-India, Institute For Plasma Research, Bhat, Gandhinagar, Gujarat (India); Bansal, Gourab; Pandya, Kaushal; Chakraborty, Arun [Institute For Plasma Research, Bhat, Gandhinagar, Gujarat (India)

    2016-11-15

    Highlights: • Indian Test Facility being built to characterize DNB for ITER delivery. • Interlock system required to safeguard the investment incurred in building the facility and protecting ITER deliverable components. • Interlock levels upto 3IL-3 identified. • Safety instrumented system for occupational safety being designed. Safety I&C functions of SIL-2 identified. • The systems are based on ITER PIS and PSS design guidelines. - Abstract: Indian Test Facility (INTF) is being built in Institute For Plasma Research to characterize Diagnostic Neutral Beam in co-operation with ITER Organization. INTF is a complex system which consists of several plant systems like beam source, gas feed, vacuum, cryogenics, high voltage power supplies, high power RF generators, mechanical systems and diagnostics systems. Out of these, several INTF components are ITER deliverable, that is, beam source, beam line components and power supplies. To ensure successful operation of INTF involving integrated operation of all the constituent plant systems a matured Data Acquisition and Control System (DACS) is required. The INTF DACS is based on CODAC platform following on PCDH (Plant Control Design Handbook) guidelines. The experimental phases involve application of HV power supplies (100 KV) and High RF power (∼800 KW) which will produce energetic beam of maximum power 6MW within the facility for longer durations. Hence the entire facility will be exposed tohigh heat fluxes and RF radiations. To ensure investment protection and to provide occupational safety for working personnel a matured Safety and Interlock system is required for INTF. The Safety and Interlock systems are high-reliability I&C systems devoted completely to the specific functions. These systems will be separate from the conventional DACS of INTF which will handle the conventional control and acquisition functions. Both, the Safety and Interlock systems are based on IEC 61511 and IEC 61508 standards as

  15. Preliminary safety analysis for key design features of KALIMER with breakeven core

    Energy Technology Data Exchange (ETDEWEB)

    Hahn, Do Hee; Kwon, Y. M.; Chang, W. P.; Suk, S. D.; Lee, Y. B.; Jeong, K. S

    2001-06-01

    KAERI is currently developing the conceptual design of a Liquid Metal Reactor, KALIMER (Korea Advanced Liquid MEtal Reactor) under the Long-term Nuclear R and D Program. KALIMER addresses key issues regarding future nuclear power plants such as plant safety, economics, proliferation, and waste. In this report, descriptions of safety design features and safety analyses results for selected ATWS accidents for the breakeven core KALIMER are presented. First, the basic approach to achieve the safety goal is introduced in Chapter 1, and the safety evaluation procedure for the KALIMER design is described in Chapter 2. It includes event selection, event categorization, description of design basis events, and beyond design basis events.In Chapter 3, results of inherent safety evaluations for the KALIMER conceptual design are presented. The KALIMER core and plant system are designed to assure benign performance during a selected set of events without either reactor control or protection system intervention. Safety analyses for the postulated anticipated transient without scram (ATWS) have been performed to investigate the KALIMER system response to the events. In Chapter 4, the design of the KALIMER containment dome and the results of its performance analyses are presented. The design of the existing containment and the KALIMER containment dome are compared in this chapter. Procedure of the containment performance analysis and the analysis results are described along with the accident scenario and source terms. Finally, a simple methodology is introduced to investigate the core energetics behavior during HCDA in Chapter 5. Sensitivity analyses have been performed for the KALIMER core behavior during super-prompt critical excursions, using mathematical formulations developed in the framework of the Modified Bethe-Tait method. Work energy potential was then calculated based on the isentropic fuel expansion model.

  16. Development of Behavioral Indicators of Competences for Safety Culture of Nuclear Power Plants: A Preliminary Study

    International Nuclear Information System (INIS)

    Moon, Kwangsu; Kim, Sa Kil; Oh, Yeon Ju; Shin, Youmin; Lee, Yong-Hee; Jang, Tong Il

    2015-01-01

    The term of safety competency in nuclear field was presented in the OECD/NEA workshop held in 1999. A model of the safety culture competencies in nuclear power plants was developed by KAERI (Korea Atomic Energy Research Institute). In general, a competency (competence) is defined as 'cluster of employee's attribute, knowledge, skill, ability or other characteristic that contributes to successful job performance'. We also defined safety culture competency as 'cluster of various internal characteristics (e.g., knowledge, skill, ability, motive, attitude and etc.) of employee that contribute to perform job safely and shape a healthy and strong safety culture.' By this definition, the safety culture competency is the broader construct including job competency. An employee having high level of safety culture competency shows extra discretionary effort to improve safety of peer, team and organization in addition to the individual's successful and safe job accomplishment. The behavioral indicators for each of the competencies are focal points of conversations on progress and are monitored continuously by self-assessment and managers or supervisors' intervention. Deficiencies in any of these indicators can point to coaching, training or other learning opportunities that employees may be required in order to improve. The purpose of this study was to derive a model of safety competencies for improving safety culture of NPPs and develop a set of behavioral indicators of each competency. In addition, the method of measuring behavioral indicators was suggested. For the application of developed safety culture competences and behavioral indicators, the most suitable measuring method for behavioral indicators must be developed. In the case of behavioral observations, behavioral dimensions (frequency, persistence and latency), observation possibility, occurrence basis of behavior (daily job performance, situational dependent) are considered to

  17. Development of Behavioral Indicators of Competences for Safety Culture of Nuclear Power Plants: A Preliminary Study

    Energy Technology Data Exchange (ETDEWEB)

    Moon, Kwangsu; Kim, Sa Kil; Oh, Yeon Ju; Shin, Youmin; Lee, Yong-Hee; Jang, Tong Il [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2015-10-15

    The term of safety competency in nuclear field was presented in the OECD/NEA workshop held in 1999. A model of the safety culture competencies in nuclear power plants was developed by KAERI (Korea Atomic Energy Research Institute). In general, a competency (competence) is defined as 'cluster of employee's attribute, knowledge, skill, ability or other characteristic that contributes to successful job performance'. We also defined safety culture competency as 'cluster of various internal characteristics (e.g., knowledge, skill, ability, motive, attitude and etc.) of employee that contribute to perform job safely and shape a healthy and strong safety culture.' By this definition, the safety culture competency is the broader construct including job competency. An employee having high level of safety culture competency shows extra discretionary effort to improve safety of peer, team and organization in addition to the individual's successful and safe job accomplishment. The behavioral indicators for each of the competencies are focal points of conversations on progress and are monitored continuously by self-assessment and managers or supervisors' intervention. Deficiencies in any of these indicators can point to coaching, training or other learning opportunities that employees may be required in order to improve. The purpose of this study was to derive a model of safety competencies for improving safety culture of NPPs and develop a set of behavioral indicators of each competency. In addition, the method of measuring behavioral indicators was suggested. For the application of developed safety culture competences and behavioral indicators, the most suitable measuring method for behavioral indicators must be developed. In the case of behavioral observations, behavioral dimensions (frequency, persistence and latency), observation possibility, occurrence basis of behavior (daily job performance, situational dependent) are considered to

  18. Preliminary assessment of a combined passive safety system for typical 3-loop PWR CPR1000

    Energy Technology Data Exchange (ETDEWEB)

    Yang, Zijiang; Shan, Jianqiang, E-mail: jqshan@mail.xjtu.edu.cn; Gou, Junli

    2017-03-15

    Highlights: • A combined passive safety system was placed on a typical 3-loop PWR CPR1000. • Three accident analyses show the three different accident mitigation methods of the passive safety system. • The three mitigation methods were proved to be useful. - Abstract: As the development of the nuclear industry, passive technology turns out to be a remarkable characteristic of advanced nuclear power plants. Since the 20th century, much effort has been given to the passive technology, and a number of evolutionary passive systems have developed. Thoughts have been given to upgrade the existing reactors with passive systems to meet stricter safety demands. In this paper, the CPR1000 plant, which is one kind of mature pressurized water reactor plants in China, is improved with some passive systems to enhance safety. The passive systems selected are as follows: (1) the reactor makeup tank (RMT); (2) the advanced accumulator (A-ACC); (3) the in-containment refueling water storage tank (IRWST); (4) the passive emergency feed water system (PEFS), which is installed on the secondary side of SGs; (5) the passive depressurization system (PDS). Although these passive components is based on the passive technology of some advanced reactors, their structural and trip designs are adjusted specifically so that it could be able to mitigate accidents of the CPR1000. Utilizing the RELAP5/MOD3.3 code, accident analyses (small break loss of coolant accident, large break loss of coolant accident, main feed water line break accident) of this improved CPR1000 plant were presented to demonstrate three different accident mitigation methods of the safety system and to test whether the passive safety system preformed its function well. In the SBLOCA, all components of the passive safety system were put into work sequentially, which prevented the core uncover. The LBLOCA analysis illustrates the contribution of the A-ACCs whose small-flow-rate injection can control the maximum cladding

  19. THE FORMATION OF THE CONTOUR OF THE DOCUMENTED AND REAL FLIGHT SAFETY IN THE SYSTEM OF THE INFORMATION PROVISION OF SAFETY OF FLIGHTS

    Directory of Open Access Journals (Sweden)

    B. I. Bachkalo

    2015-01-01

    Full Text Available The article discusses the principles and mechanisms of formation of the contour of the real safety of flights and contour of the documented safety, allowing us to obtain information to control fligh safety. The proposed approach can be used in the algorithms of active on-board flight safety management system for the implementation of information support to the crew in flight and automatic control of flight safety.

  20. Preliminary safety evaluation for the Simpevarp subarea. Based on data and site descriptions after the initial site investigation stage

    International Nuclear Information System (INIS)

    2005-04-01

    The main objectives of this Preliminary safety evaluation (PSE) of the Simpevarp subarea are: to determine, whether the feasibility study's judgement of the suitability of the candidate area with respect to long-term safety holds up in the light of the site investigation data; to provide feedback to continued site investigations and site-specific repository design and to identify site specific scenarios and geoscientific issues for further analyses. The PSE focuses on comparing the attained knowledge of the sites with the suitability criteria as set out by SKB in the report SKB-TR--00-12. These criteria both concern properties of the site judged to be necessary for safety and engineering (requirements) and properties judged to be beneficial (preferences). The findings are then evaluated in order to provide feedback to continued investigations and design work. The PSE does not aim at comparing sites and does not assess compliance with safety and radiation protection criteria. The evaluation shows that even considering remaining uncertainties, the Simpevarp subarea meets all safety requirements and most of the safety preferences. Consequently, from a safety point of view, there is no reason not to continue the Site Investigations of the Simpevarp subarea. There are still uncertainties to resolve and the safety would eventually need to be verified through a full safety assessment. Still, this Preliminary Safety Evaluation demonstrates that it is likely that a safe repository for spent nuclear fuel of the KBS-3 type could be constructed at the site. The following feedback is provided to the site investigations and the associated site modelling: Reducing the uncertainty on the deformation zone geometry within the Simpevarp subarea would allow for a more specified layout, although the sensitivity analysis shows that the space needed is rather robust with respect to uncertainties in the zones. There is substantial uncertainty in the discrete fracture network (DFN) model

  1. Patient handover in orthopaedics, improving safety using Information Technology.

    Science.gov (United States)

    Pearkes, Tim

    2015-01-01

    Good inpatient handover ensures patient safety and continuity of care. An adjunct to this is the patient list which is routinely managed by junior doctors. These lists are routinely created and managed within Microsoft Excel or Word. Following the merger of two orthopaedic departments into a single service in a new hospital, it was felt that a number of safety issues within the handover process needed to be addressed. This quality improvement project addressed these issues through the creation and implementation of a new patient database which spanned the department, allowing trouble free, safe, and comprehensive handover. Feedback demonstrated an improved user experience, greater reliability, continuity within the lists and a subsequent improvement in patient safety.

  2. The Criticality Safety Information Resource Center (CSIRC) at Los Alamos National Laboratory

    International Nuclear Information System (INIS)

    Henderson, B.D.; Meade, R.A.; Pruvost, N.L.

    1999-01-01

    The Criticality Safety Information Resource Center (CSIRC) at Los Alamos National Laboratory (LANL) is a program jointly funded by the U.S. Department of Energy (DOE) and the U.S. Nuclear Regulatory Commission (NRC) in conjunction with the Defense Nuclear Facilities Safety Board (DNFSB) Recommendation 97-2. The goal of CSIRC is to preserve primary criticality safety documentation from U.S. critical experimental sites and to make this information available for the benefit of the technical community. Progress in archiving criticality safety primary documents at the LANL archives as well as efforts to make this information available to researchers are discussed. The CSIRC project has a natural linkage to the International Criticality Safety Benchmark Evaluation Project (ICSBEP). This paper raises the possibility that the CSIRC project will evolve in a fashion similar to the ICSBEP. Exploring the implications of linking the CSIRC to the international criticality safety community is the motivation for this paper

  3. Criteria for safety related nuclear plant operator actions: a preliminary assessment of available data

    International Nuclear Information System (INIS)

    Haas, P.M.; Bott, T.F.

    1982-01-01

    The need for a quantitative data base on the reliability of nuclear power plant operators has long been recognised by human factors and reliability analysts, and the great need for further assessment of operator performance under accident conditions has been dramatically emphasised by the incident at Three Mile Island-2. In the US, an effort has been under way for a number of years to develop a design standard to define when required manual operator action can be accepted as part of a nuclear plant design basis. To provide the necessary data base to support such standards and the necessary quantitative assessment of operator reliability, the US Nuclear Regulatory Commission is sponsoring a study at Oak Ridge National Laboratory to develop the data base. A preliminary assessment, completed in April 1979, concluded that sufficient data from US operating experience did not exist to provide an adequate data base. A programme of research using full-scope nuclear plant simulators and results that are correlated to field data was suggested. That programme was recently initiated. This paper reviews the approach, results and conclusions of the preliminary assessment and summarises the planned research programme of simulator studies. (author)

  4. Preliminary standard review guide for Environmental Restoration/Decontamination and Decommissioning safety analyses

    International Nuclear Information System (INIS)

    Ellingson, D.R.

    1993-06-01

    The review guide is based on the shared experiences, approaches, and philosophies of the Environmental Restoration/Decontamination and Decommissioning (ER/D ampersand D) subgroup members. It is presented in the form of a review guide to maximize the benefit to both the safety analyses practitioner and reviewer. The guide focuses on those challenges that tend to be unique to ER/D ampersand D cleanup activities. Some of these experiences, approaches, and philosophies may find application or be beneficial to a broader spectrum of activities such as terminal cleanout or even new operations. Challenges unique to ER/D ampersand D activities include (1) consent agreements requiring activity startup on designated dates; (2) the increased uncertainty of specific hazards; and (3) the highly variable activities covered under the broad category of ER/D ampersand D. These unique challenges are in addition to the challenges encountered in all activities; e.g., new and changing requirements and multiple interpretations. The experiences in approaches, methods, and solutions to the challenges are documented from the practitioner and reviewer's perspective, thereby providing the viewpoints on why a direction was taken and the concerns expressed. Site cleanup consent agreements with predetermined dates for restoration activity startup add the dimension of imposed punitive actions for failure to meet the date. Approval of the safety analysis is a prerequisite to startup. Actions that increase expediency are (1) assuring activity safety; (2) documenting that assurance; and (3) acquiring the necessary approvals. These actions increase the timeliness of startup and decrease the potential for punitive action. Improvement in expediency has been achieved by using safety analysis techniques to provide input to the line management decision process rather than as a review of line management decisions. Expediency is also improved by sharing the safety input and resultant decisions with

  5. Establishing management information system to solve the information management problem of nuclear safety related personnel's qualification management

    International Nuclear Information System (INIS)

    Sun Haipeng; Liu Zhijun; Li Tianshu

    2013-01-01

    With the rapid progress of nuclear energy and nuclear technology utilization, nuclear safety related personnel play an increasingly important role in ensuring nuclear safety. NNSA personnel qualification management information system conducts a multi-faceted, effective, real-time monitoring and information collection for nuclear safety staff practice unit management, knowledge management, license application, appraisal management or supervision, training management or supervision and certified staff management, and also is a milestone for NNSA to build the state department with 'five-feature' (learning-oriented, service-oriented, economical, innovative, clean-type). (authors)

  6. KKP 1. Report to inform the Reactor Safety Commission

    International Nuclear Information System (INIS)

    1987-01-01

    This report goes into details of the operation during its reporting period, giving the total activity in the primary events. Radiation exposure, activities, dose rates of persons, collective doses from activity and radioactive emission to water and waste air are given. Account is given of all modifications or extensions made on safety-related parts of the plant, on controls and regulation. (DG) [de

  7. 78 FR 55775 - Pipeline Safety: Information Collection Activities

    Science.gov (United States)

    2013-09-11

    ... important tool for identifying safety trends in the hazardous liquid pipeline industry. In a Federal... reference of American Petroleum Institute (API) API 1130 (the industry standard on leak detection) which... requests that volume exiting a system during a controlled event not be reported. PHMSA Response: PHMSA does...

  8. The Geographic Climate Information System Project (GEOCLIMA): Overview and preliminary results

    Science.gov (United States)

    Feidas, H.; Zanis, P.; Melas, D.; Vaitis, M.; Anadranistakis, E.; Symeonidis, P.; Pantelopoulos, S.

    2012-04-01

    The project GEOCLIMA aims at developing an integrated Geographic Information System (GIS) allowing the user to manage, analyze and visualize the information which is directly or indirectly related to climate and its future projections in Greece. The main components of the project are: a) collection and homogenization of climate and environmental related information, b) estimation of future climate change based on existing regional climate model (RCM) simulations as well as a supplementary high resolution (10 km x 10 km) simulation over the period 1961-2100 using RegCM3, c) compilation of an integrated uniform geographic database, and d) mapping of climate data, creation of digital thematic maps, and development of the integrated web GIS application. This paper provides an overview of the ongoing research efforts and preliminary results of the project. First, the trends in the annual and seasonal time series of precipitation and air temperature observations for all available stations in Greece are assessed. Then the set-up of the high resolution RCM simulation (10 km x 10 km) is discussed with respect to the selected convective scheme. Finally, the relationship of climatic variables with geophysical features over Greece such as altitude, location, distance from the sea, slope, aspect, distance from climatic barriers, land cover etc) is investigated, to support climate mapping. The research has been co-financed by the European Union (European Regional Development Fund) and Greek national funds through the Operational Program "Competitiveness and Entrepreneurship" of the National Strategic Reference Framework (NSRF) - Research Funding Program COOPERATION 2009.

  9. Preliminary systems-interaction results from the Digraph Matrix Analysis of the Watts Bar Nuclear Power Plant safety-injection systems

    International Nuclear Information System (INIS)

    Sacks, I.J.; Ashmore, B.C.; Champney, J.M.; Alesso, H.P.

    1983-06-01

    This report provides preliminary results generated by a Digraph Matrix Analysis (DMA) for a Systems Interaction analysis performed on the Safety Injection System of the Tennessee Valley Authority Watts Bar Nuclear Power Plant. An overview of DMA is provided along with a brief description of the computer codes used in DMA

  10. 78 FR 71036 - Pipeline Safety: Random Drug Testing Rate; Contractor Management Information System Reporting...

    Science.gov (United States)

    2013-11-27

    ... PHMSA-2013-0248] Pipeline Safety: Random Drug Testing Rate; Contractor Management Information System Reporting; and Obtaining Drug and Alcohol Management Information System Sign-In Information AGENCY: Pipeline... Management Information System (MIS) Data; and New Method for Operators to Obtain User Name and Password for...

  11. Feasibility and Safety of a Powered Exoskeleton for Assisted Walking for Persons With Multiple Sclerosis: A Single-Group Preliminary Study.

    Science.gov (United States)

    Kozlowski, Allan J; Fabian, Michelle; Lad, Dipan; Delgado, Andrew D

    2017-07-01

    To examine the feasibility, safety, and secondary benefit potential of exoskeleton-assisted walking with one device for persons with multiple sclerosis (MS). Single-group longitudinal preliminary study with 8-week baseline, 8-week intervention, and 4-week follow-up. Outpatient MS clinic, tertiary care hospital. Participants (N=13; age range, 38-62y) were mostly women with Expanded Disability Status Scale scores ranging from 5.5 to 7.0. Exoskeleton-assisted walk training. Primary outcomes were accessibility (enrollment/screen pass), tolerability (completion/dropout), learnability (time to event for standing, walking, and sitting with little or no assistance), acceptability (satisfaction on the device subscale of the Quebec User Evaluation of Satisfaction with Assistive Technology version 2), and safety (event rates standardized to person-time exposure in the powered exoskeleton). Secondary outcomes were walking without the device (timed 25-foot walk test and 6-minute walk test distance), spasticity (Modified Ashworth Scale), and health-related quality of life (Patient-Reported Outcomes Measurement and Information System pain interference and Quality of Life in Neurological Conditions fatigue, sleep disturbance, depression, and positive affect and well-being). The device was accessible to 11 and tolerated by 5 participants. Learnability was moderate, with 5 to 15 sessions required to walk with minimal assistance. Safety was good; the highest adverse event rate was for skin issues at 151 per 1000 hours' exposure. Acceptability ranged from not very satisfied to very satisfied. Participants who walked routinely improved qualitatively on sitting, standing, or walking posture. Two participants improved and 2 worsened on ≥1 quality of life domain. The pattern of spasticity scores may indicate potential benefit. The device appeared feasible and safe for about a third of our sample, for whom routine exoskeleton-assisted walking may offer secondary benefits. Copyright

  12. Preliminary safety examination on thorium molten-salt nuclear energy synergetics

    International Nuclear Information System (INIS)

    Furukawa, Kazuo

    1991-01-01

    The new global fission industry for the next century should keep a strong public acceptance, which means to ensure an enough rational safety feature not only in the engineering issue but also in all issues of integral fuel-cycle system. In this sense, the safety characteristics of the Thorium Molten-Salt Nuclear Energy Synergetic System (THORIMS-NES) is widely examined relating with the several aspects of environmental (including resources, radio-waste, etc.) social (including anti-nuclear proliferation and terrorism, etc), basic technological, engineering, institutional, and economical aspects. From this examination it seems that this system is verified as one of the most promising measures of North-South problem, greenhouse effect, etc in the world. (author). 11 refs., 3 figs., 5 tabs

  13. Human Factors engineering criteria and design for the Hanford Waste Vitrification Plant preliminary safety analysis report

    International Nuclear Information System (INIS)

    Wise, J.A.; Schur, A.; Stitzel, J.C.L.

    1993-09-01

    This report provides a rationale and systematic methodology for bringing Human Factors into the safety design and operations of the Hanford Waste Vitrification Plant (HWVP). Human Factors focuses on how people perform work with tools and machine systems in designed settings. When the design of machine systems and settings take into account the capabilities and limitations of the individuals who use them, human performance can be enhanced while protecting against susceptibility to human error. The inclusion of Human Factors in the safety design of the HWVP is an essential ingredient to safe operation of the facility. The HWVP is a new construction, nonreactor nuclear facility designed to process radioactive wastes held in underground storage tanks into glass logs for permanent disposal. Its design and mission offer new opposites for implementing Human Factors while requiring some means for ensuring that the Human Factors assessments are sound, comprehensive, and appropriately directed

  14. A preliminary CATHENA thermalhydraulic model of the Canadian SCWR for safety analysis

    Energy Technology Data Exchange (ETDEWEB)

    Wang, D.F.; Wang, S., E-mail: wangd@aecl.ca [Atomic Energy of Canada Limited, Chalk River, Ontario (Canada)

    2014-06-15

    The supercritical water-cooled reactor (SCWR) is one of six reactor concepts under development in the Generation-IV International Forum (GIF). As a member of GIF, Canada is developing a pressure-tube type SCWR, which has the potential to fulfill all major GIF goals on enhanced safety, sustainability, economics, and proliferation resistance. The system thermalhydraulics code CATHENA will be used in the safety analyses for the Canadian SCWR. Based on the current conceptual design of the Canadian SCWR, a CATHENA idealization has been developed. This model includes all 336 fuel channels with a detailed model of heat transfer in the reactor core. Also modeled are the main pumps, inlet plenum, outlet plenum, turbines, and heavy water moderator. In this paper, the CATHENA idealization of the Canadian SCWR conceptual design is described. Simulation results for steady-state normal operations are also presented for the current Canadian SCWR conceptual design. (author)

  15. Health and safety: Preliminary comparative assessment of the Satellite Power System (SPS) and other energy alternatives

    Science.gov (United States)

    Habegger, L. J.; Gasper, J. R.; Brown, C.

    1980-01-01

    Data readily available from the literature were used to make an initial comparison of the health and safety risks of a fission power system with fuel reprocessing; a combined-cycle coal power system with a low-Btu gasifier and open-cycle gas turbine; a central-station, terrestrial, solar photovoltaic power system; the satellite power system; and a first-generation fusion system. The assessment approach consists of the identification of health and safety issues in each phase of the energy cycle from raw material extraction through electrical generation, waste disposal, and system deactivation; quantitative or qualitative evaluation of impact severity; and the rating of each issue with regard to known or potential impact level and level of uncertainty.

  16. A preliminary safety analysis for the prototype Gen IV Sodium-Cooled Fast Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Kwi Lim; Ha, Kwi Seok; Jeong, Jae Ho; Choi, Chi Woong; Jeong, Tae Kyeong; Ahn, Sang June; Lee, Seung Won; Chang, Won Pyo; Kang, Seok Hun; Yoo, Jae Woon [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2016-10-15

    Korea Atomic Energy Research Institute has been developing a pool-type sodium-cooled fast reactor of the Prototype Gen-IV Sodium-cooled Fast Reactor (PGSFR). To assess the effectiveness of the inherent safety features of the PGSFR, the system transients during design basis accidents and design extended conditions are analyzed with MARS-LMR and the subchannel blockage events are analyzed with MATRA-LMR-FB. In addition, the in-vessel source term is calculated based on the super-safe, small, and simple reactor methodology. The results show that the PGSFR meets safety acceptance criteria with a sufficient margin during the events and keeps accidents from deteriorating into more severe accidents.

  17. Compatibility of Safety Properties and Possibilistic Information Flow Security in MAKS

    OpenAIRE

    Bauereiss , Thomas; Hutter , Dieter

    2014-01-01

    Part 6: Information Flow Control; International audience; Motivated by typical security requirements of workflow management systems, we consider the integrated verification of both safety properties (e.g. separation of duty) and information flow security predicates of the MAKS framework (e.g. modeling confidentiality requirements). Due to the refinement paradox, enforcement of safety properties might violate possibilistic information flow properties of a system. We present an approach where s...

  18. Safety Requirements and Modern Technical Requirements in Human Information Systems in Amman Hotels

    OpenAIRE

    Farouq Ahmad Alazzam; Sattam Rakan Allahawiah; Mohammad Nayef Alsarayreh; Kafa Hmoud Abdallah al Nawaiseh

    2015-01-01

    This study aimed to demonstrate the availability of Safety requirements and modern technical requirements in human information systems in Amman hotels. an the most important results of this study is the availability of security and safety requirements in human information systems In Amman hotels and The adequacy of the information that it provided .and show that all departments are not connected by appropriate and effective communication networks in adequate form . Also sophisticated operatin...

  19. White paper: Preliminary assessment of LNG vehicle technology, economics, and safety issues (Revision 1). Topical report, April-August 1991

    International Nuclear Information System (INIS)

    Powars, C.; Lucher, D.; Moyer, C.; Browning, L.

    1992-01-01

    The objective of the study is to evaluate the potential of LNG as a vehicle fuel, to determine market niches, and to identify needed technology improvements. The white paper is being issued when the work is approximately 30 percent complete to preview the study direction, draw preliminary conclusions, and make initial recommendations. Interim findings relative to LNG vehicle technology, economics, and safety are presented. It is important to decide if heavier hydrocarbons should be allowed in LNG vehicle fuel. Development of suitable refueling couplings and vehicle fuel supply pressure systems are recommended. Initial economics analyses considered transit buses and pickup and delivery trucks fueled via onsite liquefiers and imported LNG. Net user costs were more than (but in some cases close to) those for diesel fuel and gasoline. Lowering the cost of small-scale liquefiers would significantly improve the economics of LNG vehicles. New emissions regulations may introduce considerations beyond simple cost comparisons. LNG vehicle safety and available accident data are reviewed. Consistent codes for LNG vehicles and refueling facilities are needed

  20. Preliminary safety analysis of the PWR with accident-tolerant fuels during severe accident conditions

    International Nuclear Information System (INIS)

    Wu, Xiaoli; Li, Wei; Wang, Yang; Zhang, Yapei; Tian, Wenxi; Su, Guanghui; Qiu, Suizheng; Liu, Tong; Deng, Yongjun; Huang, Heng

    2015-01-01

    Highlights: • Analysis of severe accident scenarios for a PWR fueled with ATF system is performed. • A large-break LOCA without ECCS is analyzed for the PWR fueled with ATF system. • Extended SBO cases are discussed for the PWR fueled with ATF system. • The accident-tolerance of ATF system for application in PWR is illustrated. - Abstract: Experience gained in decades of nuclear safety research and previous nuclear accidents direct to the investigation of passive safety system design and accident-tolerant fuel (ATF) system which is now becoming a hot research point in the nuclear energy field. The ATF system is aimed at upgrading safety characteristics of the nuclear fuel and cladding in a reactor core where active cooling has been lost, and is preferable or comparable to the current UO 2 –Zr system when the reactor is in normal operation. By virtue of advanced materials with improved properties, the ATF system will obviously slow down the progression of accidents, allowing wider margin of time for the mitigation measures to work. Specifically, the simulation and analysis of a large break loss of coolant accident (LBLOCA) without ECCS and extended station blackout (SBO) severe accident are performed for a pressurized water reactor (PWR) loaded with ATF candidates, to reflect the accident-tolerance of ATF

  1. Safety of Information System on Emergence of Semantic Instability

    Directory of Open Access Journals (Sweden)

    Viacheslav Ernstovich Wolfengagen

    2013-02-01

    Full Text Available We study the question of the effect of semantic instability and a possible violation of the safe mode of the information system. A similar effect occurs in the construction of specialized information systems, such as the blogosphere and other dynamic online communities. In a more general formulation, we consider the problem of finding the individual on “information path” left by him that currently comes to the fore in information technology.

  2. Environment, safety, and health information technology systems integration.

    Energy Technology Data Exchange (ETDEWEB)

    Hendrickson, David A.; Bayer, Gregory W.

    2006-02-01

    The ES&H Information Systems department, motivated by the numerous isolated information technology systems under its control, undertook a significant integration effort. This effort was planned and executed over the course of several years and parts of it still continue today. The effect was to help move the ES&H Information Systems department toward integration with the corporate Information Solutions and Services center.

  3. Preliminary thermal-hydraulic and safety analysis of China DFLL-TBM system

    Energy Technology Data Exchange (ETDEWEB)

    Li, Wei [School of Nuclear Science and Technology, Xi’an Jiaotong University, No. 28, Xianning West Road, Xi’an, Shanxi 710049 (China); Tian, Wenxi, E-mail: wxtian@mail.xjtu.edu.cn [School of Nuclear Science and Technology, Xi’an Jiaotong University, No. 28, Xianning West Road, Xi’an, Shanxi 710049 (China); Qiu, Suizheng; Su, Guanghui; Jiao, Hong [School of Nuclear Science and Technology, Xi’an Jiaotong University, No. 28, Xianning West Road, Xi’an, Shanxi 710049 (China); Bai, Yunqing; Chen, Hongli [Institute of Nuclear Energy Safety Technology, Chinese Academy of Sciences, Hefei, Anhui 230031 (China); Wu, Yican, E-mail: yican.Wu@Fds.Org.Cn [Institute of Nuclear Energy Safety Technology, Chinese Academy of Sciences, Hefei, Anhui 230031 (China)

    2013-06-15

    Highlights: • Thermal-hydraulic and safety analysis on DFLL-TBM system is performed. • The TBM FW maximum temperature is 541 °C under steady state condition. • The TBM FW maximum temperature does not exceed the melt point of CLAM steel 1500 °C. • Neither the VV pressurization nor vault pressure build-up goes beyond 0.2 MPa. -- Abstract: China has proposed the dual-functional lithium-lead (DFLL) tritium breeding blanket concept for testing in ITER as a test blanket module (TBM), to demonstrate the technologies of tritium self-sufficiency, high-grade heat extraction and efficient electricity production which are needed for DEMO and fusion power plant. Safety assessment of the TBM and its auxiliary system should be conducted to deal with ITER safety issues directly caused by the TBM system failure during the design process. In this work, three potential initial events (PIEs) – in-vessel loss of helium (He) coolant and ex-vessel loss of He coolant and loss of flow without scram (LOFWS) – were analyzed for the TBM system with a modified version of the RELAP5/MOD3 code containing liquid lithium-lead eutectic (LiPb). The code also comprised an empirical expression for MHD pressure drop relevant to three-dimensional (3D) effect, the Lubarsky–Kaufman convective heat transfer correlation for LiPb flow and the Gnielinski convective heat transfer correlation for He flow. Since both LiPb and He serve as TBM coolants, the LiPb and He ancillary cooling systems were modeled to investigate the thermal-hydraulic characteristic of the TBM system and its influence on ITER safety under those accident conditions. The TBM components and the coolants flow within the TBM were simulated with one-dimensional heat structures and their associated hydrodynamic components. ITER enclosures including vacuum vessel (VV), port cell and TCWS vault were also covered in the model for accident analyses. Through this best estimate approach, the calculation indicated that the current

  4. Impediments for the application of risk-informed decision making in nuclear safety

    International Nuclear Information System (INIS)

    Hahn, L.

    2001-01-01

    A broad application of risk-informed decision making in the regulation of safety of nuclear power plants is hindered by the lack of quantitative risk and safety standards as well as of precise instruments to demonstrate an appropriate safety. An additional severe problem is associated with the difficulty to harmonize deterministic design requirements and probabilistic safety assessment. The problem is strengthened by the vulnerability of PSA for subjective influences and the potential of misuse. Beside this scepticism the nuclear community is encouraged to intensify the efforts to improve the quality standards for probabilistic safety assessments and their quality assurance. A prerequisite for reliable risk-informed decision making processes is also a well-defined and transparent relationship between deterministic and probabilistic safety approaches. (author)

  5. Research and development of technologies for safe and environmentally optimal recovery and disposal of explosive wastes. Task 2, Preliminary impact assessment for environment, health and safety (EIA)

    Energy Technology Data Exchange (ETDEWEB)

    Duijm, N.J.; Markert, F. [Risoe (Denmark); Larsen, S.G. [DEMEX A/S (Denmark)

    1998-09-01

    As described in the project proposal `Research and Development of Technologies for Safe and Environmentally optimal recovery and Disposal of Explosive Wastes`, dated 31. May 1996, the objective of Task 2, Preliminary Impact Assessment for Environment, Health and Safety, is to: Analyse the environmental impact of noise and emissions to air, water and soil; Assess the risk of hazards to workers` health and safety and to the public. Task 2, Preliminary Impact Assessment for Environment, Health and Safety (EIA), has been performed from August 1997 to September 1998. First, a methodology has been established, based on Multi-Criteria Decision Analysis (MCDA), to select the `best` technology on the basis of clearly defined objectives, including minimal impacts on environment, health and safety. This included a review of different types of explosive waste with a focus on the environment implications, identifying the issues relevant to defining the criteria or objectives with respect to environment and safety in the framework of explosive waste, as well as the preliminary definition of objectives for the final impact assessment. Second, the previously identified recovery and disposal technologies (Task 1) have been qualitatively assessed on the basis of the relevant objectives. This qualitative assessment includes also economic considerations and an attempt to rank the technologies in an MCDA framework. (au)

  6. Preliminary safety assessment of C-8 xylitol monoester and xylitol phosphate esters.

    Science.gov (United States)

    Silveira, J E P S; Pereda, M C V; Nogueira, C; Dieamant, G; Cesar, C K M; Assanome, K M; Silva, M S; Torello, C O; Queiroz, M L S; Eberlin, S

    2016-02-01

    Most of the cosmetic compounds with preservative properties available in the market pose some risks concerning safety, such as the possibility of causing sensitization. Due to the fact that there are few options, the proper development of new molecules with this purpose is needed. Xylitol is a natural sugar, and the antimicrobial properties of xylitol-derived compounds have already been described in the literature. C-8 xylitol monoester and xylitol phosphate esters may be useful for the development of skincare products. As an initial screen for safety of chemicals, the combination of in silico methods and in vitro testing can aid in prioritizing resources in toxicological investigations while reducing the ethical and monetary costs that are related to animal and human testing. This study was designed to evaluate the safety of C-8 xylitol monoester and xylitol phosphate esters regarding carcinogenicity, mutagenicity, skin and eye irritation/corrosion and sensitization through alternative methods. For the initial safety assessment, quantitative structure-activity relationship methodology was used. The prediction of the parameters carcinogenicity/mutagenicity, skin and eye irritation/corrosion and sensitization was generated from the chemical structure. The analysis also comprised physical-chemical properties, Cramer rules, threshold of toxicological concern and Michael reaction. In silico results of candidate molecules were compared to 19 compounds with preservative properties that are available in the market. Additionally, in vitro tests (Ames test for mutagenicity, cytotoxicity and phototoxicity tests and hen's egg test--chorioallantoic membrane for irritation) were performed to complement the evaluation. In silico evaluation of both molecules presented no structural alerts related to eye and skin irritation, corrosion and sensitization, but some alerts for micronucleus and carcinogenicity were detected. However, by comparison, C-8 xylitol monoester, xylitol

  7. Swine plasma immunoglobulins for prevention and treatment of post-weaning diarrhoea: Safety and Preliminary results

    DEFF Research Database (Denmark)

    Hedegaard, Chris Juul; Strube, Mikael Lenz; Bendix Hansen, Marie

    . coli F4+ induced PWD, we observed that piglets given IgG as a feed supplement cleared the E coli infection significantly faster than control weaner piglets not receiving an immunoglobulin feed supplement. Furthermore, deep sequencing of the ileal microbiota showed a significantly lowered colonization...... their adhesion to porcine epithelial cells in vitro. As the immunoglobulin fraction is intended for oral use as a feed supplement, we also tested the safety of feeding 4 grams of natural immunoglobulins to 4-5 week old weaner piglets for 14 days and observed no adverse effects. In an experimental model of E...

  8. Deep Borehole Disposal Safety Analysis.

    Energy Technology Data Exchange (ETDEWEB)

    Freeze, Geoffrey A. [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States); Stein, Emily [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States); Price, Laura L. [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States); MacKinnon, Robert J. [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States); Tillman, Jack Bruce [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States)

    2016-10-01

    This report presents a preliminary safety analysis for the deep borehole disposal (DBD) concept, using a safety case framework. A safety case is an integrated collection of qualitative and quantitative arguments, evidence, and analyses that substantiate the safety, and the level of confidence in the safety, of a geologic repository. This safety case framework for DBD follows the outline of the elements of a safety case, and identifies the types of information that will be required to satisfy these elements. At this very preliminary phase of development, the DBD safety case focuses on the generic feasibility of the DBD concept. It is based on potential system designs, waste forms, engineering, and geologic conditions; however, no specific site or regulatory framework exists. It will progress to a site-specific safety case as the DBD concept advances into a site-specific phase, progressing through consent-based site selection and site investigation and characterization.

  9. Analysis of safety information for nuclear power plants and development of source term estimation program

    International Nuclear Information System (INIS)

    Kim, Tae Woon; Choi, Seong Soo; Park, Jin Hee

    1999-12-01

    Current CARE(Computerized Advisory System for Radiological Emergency) in KINS(Korea Institute of Nuclear Safety) has no STES(Source Term Estimation System) which links between SIDS(Safety Information Display System) and FADAS(Following Accident Dose Assessment System). So in this study, STES is under development. STES system is the system that estimates the source term based on the safety information provided by SIDS. Estimated source term is given to FADAS as an input for estimation of environmental effect of radiation. Through this first year project STES for the Kori 3,4 and Younggwang 1,2 has been developed. Since there is no CARE for Wolsong(PHWR) plants yet, CARE for Wolsong is under construction. The safety parameters are selected and the safety information display screens and the alarm logic for plant status change are developed for Wolsong Unit 2 based on the design documents for CANDU plants

  10. The Research on Safety Management Information System of Railway Passenger Based on Risk Management Theory

    Science.gov (United States)

    Zhu, Wenmin; Jia, Yuanhua

    2018-01-01

    Based on the risk management theory and the PDCA cycle model, requirements of the railway passenger transport safety production is analyzed, and the establishment of the security risk assessment team is proposed to manage risk by FTA with Delphi from both qualitative and quantitative aspects. The safety production committee is also established to accomplish performance appraisal, which is for further ensuring the correctness of risk management results, optimizing the safety management business processes and improving risk management capabilities. The basic framework and risk information database of risk management information system of railway passenger transport safety are designed by Ajax, Web Services and SQL technologies. The system realizes functions about risk management, performance appraisal and data management, and provides an efficient and convenient information management platform for railway passenger safety manager.

  11. Usage of information safety requirements in improving tube bending process

    Science.gov (United States)

    Livshitz, I. I.; Kunakov, E.; Lontsikh, P. A.

    2018-05-01

    This article is devoted to an improvement of the technological process's analysis with the information security requirements implementation. The aim of this research is the competition increase analysis in aircraft industry enterprises due to the information technology implementation by the example of the tube bending technological process. The article analyzes tube bending kinds and current technique. In addition, a potential risks analysis in a tube bending technological process is carried out in terms of information security.

  12. Preliminary safety analysis report for the Auxiliary Hot Cell Facility, Sandia National Laboratories, Albuquerque, New Mexico

    International Nuclear Information System (INIS)

    OSCAR, DEBBY S.; WALKER, SHARON ANN; HUNTER, REGINA LEE; WALKER, CHERYL A.

    1999-01-01

    The Auxiliary Hot Cell Facility (AHCF) at Sandia National Laboratories, New Mexico (SNL/NM) will be a Hazard Category 3 nuclear facility used to characterize, treat, and repackage radioactive and mixed material and waste for reuse, recycling, or ultimate disposal. A significant upgrade to a previous facility, the Temporary Hot Cell, will be implemented to perform this mission. The following major features will be added: a permanent shield wall; eight floor silos; new roof portals in the hot-cell roof; an upgraded ventilation system; and upgraded hot-cell jib crane; and video cameras to record operations and facilitate remote-handled operations. No safety-class systems, structures, and components will be present in the AHCF. There will be five safety-significant SSCs: hot cell structure, permanent shield wall, shield plugs, ventilation system, and HEPA filters. The type and quantity of radionuclides that could be located in the AHCF are defined primarily by SNL/NM's legacy materials, which include radioactive, transuranic, and mixed waste. The risk to the public or the environment presented by the AHCF is minor due to the inventory limitations of the Hazard Category 3 classification. Potential doses at the exclusion boundary are well below the evaluation guidelines of 25 rem. Potential for worker exposure is limited by the passive design features incorporated in the AHCF and by SNL's radiation protection program. There is no potential for exposure of the public to chemical hazards above the Emergency Response Protection Guidelines Level 2

  13. Preliminary safety analysis report for the Auxiliary Hot Cell Facility, Sandia National Laboratories, Albuquerque, New Mexico

    Energy Technology Data Exchange (ETDEWEB)

    OSCAR,DEBBY S.; WALKER,SHARON ANN; HUNTER,REGINA LEE; WALKER,CHERYL A.

    1999-12-01

    The Auxiliary Hot Cell Facility (AHCF) at Sandia National Laboratories, New Mexico (SNL/NM) will be a Hazard Category 3 nuclear facility used to characterize, treat, and repackage radioactive and mixed material and waste for reuse, recycling, or ultimate disposal. A significant upgrade to a previous facility, the Temporary Hot Cell, will be implemented to perform this mission. The following major features will be added: a permanent shield wall; eight floor silos; new roof portals in the hot-cell roof; an upgraded ventilation system; and upgraded hot-cell jib crane; and video cameras to record operations and facilitate remote-handled operations. No safety-class systems, structures, and components will be present in the AHCF. There will be five safety-significant SSCs: hot cell structure, permanent shield wall, shield plugs, ventilation system, and HEPA filters. The type and quantity of radionuclides that could be located in the AHCF are defined primarily by SNL/NM's legacy materials, which include radioactive, transuranic, and mixed waste. The risk to the public or the environment presented by the AHCF is minor due to the inventory limitations of the Hazard Category 3 classification. Potential doses at the exclusion boundary are well below the evaluation guidelines of 25 rem. Potential for worker exposure is limited by the passive design features incorporated in the AHCF and by SNL's radiation protection program. There is no potential for exposure of the public to chemical hazards above the Emergency Response Protection Guidelines Level 2.

  14. 78 FR 50079 - Information Collection Activities: Safety and Environmental Management Systems (SEMS); Proposed...

    Science.gov (United States)

    2013-08-16

    ... DEPARTMENT OF THE INTERIOR Bureau of Safety and Environmental Enforcement [Docket ID BSEE-2013-0005; OMB Control Number 1014-0017: 134E1700D2 EEEE500000 ET1SF0000.DAQ000] Information Collection Activities: Safety and Environmental Management Systems (SEMS); Proposed Collection; Comment Request...

  15. A framework of risk-informed seismic safety evaluation of nuclear power plants in Japan

    International Nuclear Information System (INIS)

    Kondo, S.; Sakagami, M.; Hirano, M.; Shiba, M.

    2001-01-01

    A framework of risk-informed seismic design and safety evaluation of nuclear power plants is under consideration in Japan so as to utilize the progress in the seismic probabilistic safety assessment methodology. Issues resolved to introduce this framework are discussed after the concept, evaluation process and characteristics of the framework are described. (author)

  16. 75 FR 42818 - Agency Information Collection; Activity Under OMB Review; Collection of Safety Culture Data for...

    Science.gov (United States)

    2010-07-22

    ... Collection; Activity Under OMB Review; Collection of Safety Culture Data for Program Evaluation AGENCY... . SUPPLEMENTARY INFORMATION: Title: Collection of Safety Culture Data for Program Evaluation. Type of Request... data on the nation's transportation system is an important component of BTS' responsibility to the...

  17. 77 FR 28602 - Agency Information Collection Activities; Proposed Collection; Comment Request; Early Food Safety...

    Science.gov (United States)

    2012-05-15

    ... appropriate, and other forms of information technology. Early Food Safety Evaluation of New Non-Pesticidal... Evaluation of New Non-Pesticidal Proteins Produced by New Plant Varieties Intended for Food Use AGENCY: Food... for early food safety evaluation of new non-pesticidal proteins produced by new plant varieties...

  18. 8 CFR 214.12 - Preliminary enrollment of schools in the Student and Exchange Visitor Information System (SEVIS).

    Science.gov (United States)

    2010-01-01

    ... of schools in the Student and Exchange Visitor Information System (SEVIS). (a) Private elementary and private secondary schools, public high schools, post-secondary schools, language schools, and vocational... 8 Aliens and Nationality 1 2010-01-01 2010-01-01 false Preliminary enrollment of schools in the...

  19. Detect to Avoid: Supporting Aviation Safety with Bird Movement Information

    NARCIS (Netherlands)

    Metz, I.C.; Muhlhausen, Thorsten; Ellerbroek, J.; Hoekstra, J.M.; Kügler, D.

    2017-01-01

    The presented research evaluates the concept of providing an airport’s Air Traffic Control with a bird strike advisory system. Such a system informs the controller about current and predicted bird movements in the arrival and departure corridors. Based on this information, the controller can decide

  20. 75 FR 76831 - Publicly Available Consumer Product Safety Information Database

    Science.gov (United States)

    2010-12-09

    ... information as evidenced by their verification that they have done so. We also note that reports of harm... ``Others'' file reports of harm with us using our online incident reporting form by self-reporting as... requirements for verification of information it intends to make public. Response--Congress provided a clear...

  1. Sharing Information to Promote a Culture of Safety

    Science.gov (United States)

    Goodrum, Sarah; Woodward, William; Thompson, Andrew J.

    2017-01-01

    Much of the research on school shootings emphasizes the need for peers, not school officials, to share information about students of concern. This qualitative case study examined the information school officials had prior to a school shooting, which left two students dead. The data came from school officials' deposition testimony and school…

  2. The safety management of the informative communication technologies

    International Nuclear Information System (INIS)

    Kotora, D.

    2009-01-01

    In the first part, the contribute deals with the basic principals of the central monitoring of safety by means of the product Cisco SIMS (now netForensic SIM One), which enable to monitor the multi / platform surroundings, the collection of the data of central data base and to provide the analytical tools and the progress at the incidents detection. The second part pays attention to the integration of SAP A3 into the central monitoring of safety, what enables the automatic correlation of notice SAP with the other monitoring equipment's (farewell's, IPS etc.) and thereby the possibility to uncover the sophisticated attacks and data leakage. Within the integrated works, the mechanisms enabling the automatic control of activity concord on the system SAP with the required organization rules and consecutive alert for following events were formed: I. Environment segregation violation - the violation of the principles for department of the development, testing and production surroundings e.g. the change of authorized profiles on the production system in spite of the transport from the testing surrounding; II. Operation violation - unauthorized access to the operations, object etc.; III. The violation of the principles by the important users; IV. The access of the common users on the important operations

  3. Scrambler therapy efficacy and safety for neuropathic pain correlated with chemotherapy-induced peripheral neuropathy in adolescents: A preliminary study.

    Science.gov (United States)

    Tomasello, Caterina; Pinto, Rita Maria; Mennini, Chiara; Conicella, Elena; Stoppa, Francesca; Raucci, Umberto

    2018-04-06

    Chemotherapy-induced peripheral neuropathy (CIPN) is a common side effect of chemotherapy, in need of effective treatment. Preliminary data support the efficacy of scrambler therapy (ST), a noninvasive cutaneous electrostimulation device, in adults with CIPN. We test the efficacy, safety, and durability of ST for neuropathic pain in adolescents with CIPN. We studied nine pediatric patients with cancer and CIPN who received ST for pain control. Each patient received 45-min daily sessions for 10 consecutive days as a first step, but some of them required additional treatment. Pain significantly improved comparing Numeric Rate Scale after 10 days of ST (9.22 ± 0.83 vs. 2.33 ± 2.34; P < 0.001) and at the end of the optimized cycle (EOC) (9.22 ± 0.83 vs. 0.11 ± 0.33, P < 0.001). The improvement in quality of life was significantly reached on pain interference with general activity (8.67 ± 1.66 vs. 3.33 ± 2.12, P < 0.0001), mood (8.33 ± 3.32 vs. 2.78 ± 2.82, P < 0.0005), walking ability (10.00 vs. 2.78 ± 1.22, P < 0.0001), sleep (7.56 ± 2.24 vs. 2.67 ± 1.41, P < 0.001), and relations with people (7.89 ± 2.03 vs. 2.11 ± 2.03, P < 0.0002; Lansky score 26.7 ± 13.2 vs. 10 days of ST 57.8 ± 13.9, P < 0.001; 26.7 ± 13.2 vs. EOC 71.1 ± 16.2, P < 0.001). Based on these preliminary data, ST could be a good choice for adolescents with CIPN for whom pain control is difficult. ST caused total relief or dramatic reduction in CIPN pain and an improvement in quality of life, durable in follow-up. It caused no detected side effects, and can be retrained successfully. Further larger studies should be performed to confirm our promising preliminary data in pediatric patients with cancer. © 2018 Wiley Periodicals, Inc.

  4. Preliminary analysis of the safety and environmental impact of the Tritium Systems Test Assembly

    International Nuclear Information System (INIS)

    Carlson, R.V.; Jalbert, R.A.

    1980-01-01

    The Tritium Systems Test Assembly (TSTA) is a facility dedicated to the development of technologies associated with the D-T fuel cycle of future fusion reactors while demonstrating that TSTA can be operated safely with no significant losses to the environment. During the initial design stage of TSTA, a safety analysis was performed which investigated the effects of major subsystem component failure, the meteorology and seismicity of the site and their possible effect on the facility, and accident scenarios which result in tritium releases. Major releases of tritium to the environment are considered highly improbable since they require a compound failure of primary and secondary containment, along with either a breach of the building or a failure of the Emergency Tritium Cleanup system. Accidental releases caused by natural phenomena (earthquake, tornado, etc.) are considered highly improbable

  5. Methods of Certification tests PLC-Networks in Compliance Safety Information

    Directory of Open Access Journals (Sweden)

    A. A. Balaev

    2011-12-01

    Full Text Available The aim of this research was description of the methodology of the audit plc-network to meet the requirements of information security. The technique is based on the provisions of the guidance documents and model FSTEC Russia test object methods of information on safety information.

  6. Safety and feasibility of inpatient exercise training in pediatric heart failure: a preliminary report.

    Science.gov (United States)

    McBride, Michael G; Binder, Tracy Jo; Paridon, Stephen M

    2007-01-01

    To determine the safety and feasibility of an inpatient exercise training program for a group of pediatric heart transplantation candidates on multiple inotropic support. Children with end-stage heart disease often require heart transplantation. Currently, no data exist on the safety and feasibility of an inpatient exercise training program in pediatric patients awaiting heart transplantation while on inotropic support. Twenty ambulatory patients (11 male; age, 13.6 +/- 3.2 years) were admitted, listed, and subsequently enrolled into an exercise training program while awaiting heart transplantation. Patient diagnoses consisted of dilated cardiomyopathy (n = 15), restrictive cardiomyopathy (n = 1), and failing single-ventricle physiology (n = 4). Inotropic support consisted of a combination of dobutamine, dopamine, or milrinone. Exercise sessions were scheduled three times a week lasting from 30 to 60 minutes and consisted of aerobic and musculoskeletal conditioning. Over 6.2 +/- 4.2 months, 1,251 of a possible 1,508 exercise training sessions were conducted, with a total of 615 hours (26.3 +/- 2.7 min/session) dedicated to low-intensity aerobic exercise. Reasons for noncompliance included a change in medical status, staffing, or patient cooperation. Two adverse episodes (seizures) occurred, neither of which resulted in termination from the program. No adverse episodes of hypotension or significant complex arrhythmias occurred. No complication of medication administration or loss of intravenous access occurred. Data from this study indicate that pediatric patients on inotropic support as a result of systemic ventricular or biventricular heart failure can safely participate in exercise training programs with relatively moderate to high compliance.

  7. Intelligent Information Processing for Enhanced Safety in the NAS, Phase I

    Data.gov (United States)

    National Aeronautics and Space Administration — We propose a system that focuses on how improved information flow between agents acting in a flight deck environment can improve safety performance. Agents are...

  8. State Traffic Safety Information - 2010-2015 FARS Accident File data

    Data.gov (United States)

    Department of Transportation — The State Traffic Safety Information (STSI) portal is part of the larger Fatality Analysis Reporting System (FARS) Encyclopedia. STSI provides state-by-state traffic...

  9. Intelligent Information Processing for Enhanced Safety in the NAS, Phase II

    Data.gov (United States)

    National Aeronautics and Space Administration — Our Phase I work focused on how improved information flow between actors in a flight deck environment can improve safety performance. An operational prototype was...

  10. Quantitative Information Flow as Safety and Liveness Hyperproperties

    Directory of Open Access Journals (Sweden)

    Hirotoshi Yasuoka

    2012-07-01

    Full Text Available We employ Clarkson and Schneider's "hyperproperties" to classify various verification problems of quantitative information flow. The results of this paper unify and extend the previous results on the hardness of checking and inferring quantitative information flow. In particular, we identify a subclass of liveness hyperproperties, which we call "k-observable hyperproperties", that can be checked relative to a reachability oracle via self composition.

  11. The UK health and safety executive's policies on information relating to nuclear safety regulation

    International Nuclear Information System (INIS)

    Williams, L.

    1994-01-01

    How a message is transmitted can be as important as what is said. To be effective a message has to be timely, targeted and clear. People do not always remember what was said, by how and when it was said. This paper discusses some of the tools which the Nuclear Safety Division (NSD), the UK's nuclear regulator, has used and emphasizes the need to recognize the importance of a recipient interest in attempting to transmit a message. (author). 4 refs

  12. An Adaptive Information Quantity-Based Broadcast Protocol for Safety Services in VANET

    Directory of Open Access Journals (Sweden)

    Wenjie Wang

    2016-01-01

    Full Text Available Vehicle-to-vehicle communication plays a significantly important role in implementing safe and efficient road traffic. When disseminating safety messages in the network, the information quantity on safety packets changes over time and space. However, most of existing protocols view each packet the same to disseminate, preventing vehicles from collecting more recent and precise safety information. Hence, an information quantity-based broadcast protocol is proposed in this paper to ensure the efficiency of safety messages dissemination. In particular, we propose the concept of emergency-degree to evaluate packets’ information quantity. Then we present EDCast, an emergency-degree-based broadcast protocol. EDCast differentiates each packet’s priority for accessing the channel based on its emergency-degree so as to provide vehicles with more safety information timely and accurately. In addition, an adaptive scheme is presented to ensure fast dissemination of messages in different network condition. We compare the performance of EDCast with those of three other representative protocols in a typical highway scenario. Simulation results indicate that EDCast achieves higher broadcast efficiency and less redundancy with less delivery delay. What we found demonstrates that it is feasible and necessary for incorporating information quantity of messages in designing an efficient safety message broadcast protocol.

  13. Safety and Immunogenicity of an Anti-Zika Virus DNA Vaccine - Preliminary Report.

    Science.gov (United States)

    Tebas, Pablo; Roberts, Christine C; Muthumani, Kar; Reuschel, Emma L; Kudchodkar, Sagar B; Zaidi, Faraz I; White, Scott; Khan, Amir S; Racine, Trina; Choi, Hyeree; Boyer, Jean; Park, Young K; Trottier, Sylvie; Remigio, Celine; Krieger, Diane; Spruill, Susan E; Bagarazzi, Mark; Kobinger, Gary P; Weiner, David B; Maslow, Joel N

    2017-10-04

    Background Although Zika virus (ZIKV) infection is typically self-limiting, other associated complications such as congenital birth defects and the Guillain-Barré syndrome are well described. There are no approved vaccines against ZIKV infection. Methods In this phase 1, open-label clinical trial, we evaluated the safety and immunogenicity of a synthetic, consensus DNA vaccine (GLS-5700) encoding the ZIKV premembrane and envelope proteins in two groups of 20 participants each. The participants received either 1 mg or 2 mg of vaccine intradermally, with each injection followed by electroporation (the use of a pulsed electric field to introduce the DNA sequence into cells) at baseline, 4 weeks, and 12 weeks. Results The median age of the participants was 38 years, and 60% were women; 78% were white, and 22% black; in addition, 30% were Hispanic. At the interim analysis at 14 weeks (i.e., after the third dose of vaccine), no serious adverse events were reported. Local reactions at the vaccination site (e.g., injection-site pain, redness, swelling, and itching) occurred in approximately 50% of the participants. After the third dose of vaccine, binding antibodies (as measured on enzyme-linked immunosorbent assay) were detected in all the participants, with geometric mean titers of 1642 and 2871 in recipients of 1 mg and 2 mg of vaccine, respectively. Neutralizing antibodies developed in 62% of the samples on Vero-cell assay. On neuronal-cell assay, there was 90% inhibition of ZIKV infection in 70% of the serum samples and 50% inhibition in 95% of the samples. The intraperitoneal injection of postvaccination serum protected 103 of 112 IFNAR knockout mice (bred with deletion of genes encoding interferon-α and interferon-β receptors) (92%) that were challenged with a lethal dose of ZIKV-PR209 strain; none of the mice receiving baseline serum survived the challenge. Survival was independent of the neutralization titer. Conclusions In this phase 1, open-label clinical

  14. Posiva's application for a decision in principle concerning a disposal facility for spent nuclear fuel. STUK's statement and preliminary safety appraisal

    Energy Technology Data Exchange (ETDEWEB)

    Ruokola, E. [ed.

    2000-03-01

    In May 1999, Posiva Ltd submitted to the Government an application, pursuant to the Nuclear Energy Act, for a Decision in Principle on a disposal facility for spent nuclear fuel from the Finnish nuclear power plants. The Ministry of Trade and Industry requested the Radiation and Nuclear Safety Authority (STUK) to draw up a preliminary safety appraisal concerning the proposed disposal facility. In the beginning of this report, STUK's statement to the Ministry and Industry concerning the proposed disposal facility is given. In that statement, STUK concludes that the Decision in Principle is currently justified from the standpoint of safety. The statement is followed by a safety appraisal, where STUK deems, how the proposed disposal concept, site and facility comply with the safety requirements included in the Government's Decision (478/1999). STUK's preliminary safety appraisal was supported by contributions from a number of outside experts. A collective opinion by an international group of ten distinguished experts is appended to this report. (orig.)

  15. Treatment of Passive Component Reliability in Risk-Informed Safety Margin Characterization FY 2010 Report

    Energy Technology Data Exchange (ETDEWEB)

    Robert W Youngblood

    2010-09-01

    The Risk-Informed Safety Margin Characterization (RISMC) pathway is a set of activities defined under the U.S. Department of Energy (DOE) Light Water Reactor Sustainability Program. The overarching objective of RISMC is to support plant life-extension decision-making by providing a state-of-knowledge characterization of safety margins in key systems, structures, and components (SSCs). A technical challenge at the core of this effort is to establish the conceptual and technical feasibility of analyzing safety margin in a risk-informed way, which, unlike conventionally defined deterministic margin analysis, is founded on probabilistic characterizations of SSC performance.

  16. Clinical pharmacokinetics, safety, and preliminary efficacy evaluation of icotinib in patients with advanced non-small cell lung cancer.

    Science.gov (United States)

    Liu, Dongyang; Zhang, Li; Wu, Yiwen; Jiang, Ji; Tan, Fenlai; Wang, Yingxiang; Liu, Yong; Hu, Pei

    2015-09-01

    To receive pharmacokinetics, safety, and anti-tumor activity of icotinib, a novel epidermal growth factor receptor (EGFR)-tyrosine kinase inhibitor (TKI), in patients with advanced non-small-cell lung cancer (NSCLC). Patients (n=40) with advanced NSCLC were enrolled to receive escalating doses of icotinib, which was administrated on Day 1 followed by 28-day continuous dosing starting from Day 4. Four dosing regimens, 100mg b.i.d., 150 mg b.i.d., 125 mg t.i.d., and 200mg b.i.d. were studied. Pharmacokinetics (PK), safety, and efficacy of icotinib were evaluated. Icotinib was well tolerated in Chinese patients with refractory NSCLC. No toxicity with >3 grades were reported in more than 2 patients under any dose levels. One complete response (3%) and 9 partial responses (23%) were received. Total disease control rate could reach at 73% and median progress-free survival (range) was 154 (17-462) days. PK exposure of icotinib increased with increase of dose in NSCLC patients. Food was suggested to increase PK exposure by ∼30%. Mean t1/2β was within 5.31-8.07 h. No major metabolite (>10% plasma exposure of icotinib) was found in NSCLC patients. Icotinib with up to 400 mg/day exhibited good tolerance and preliminary antitumor activity in Chinese NSCLC patients. Pharmacokinetics of icotinib and 5 major metabolites were fully investigated in NSCLC patients. Optimized biologic dose (OBD) was finally recommended to be 125 mg t.i.d. for the later clinical study. Copyright © 2015 Elsevier Ireland Ltd. All rights reserved.

  17. ADME studies and preliminary safety pharmacology of LDT5, a lead compound for the treatment of benign prostatic hyperplasia

    Directory of Open Access Journals (Sweden)

    F. Noël

    Full Text Available This study aimed to estimate the absorption, distribution, metabolism and excretion (ADME properties and safety of LDT5, a lead compound for oral treatment of benign prostatic hyperplasia that has previously been characterized as a multi-target antagonist of α1A-, α1D-adrenoceptors and 5-HT1A receptors. The preclinical characterization of this compound comprised the evaluation of its in vitro properties, including plasma, microsomal and hepatocytes stability, cytochrome P450 metabolism and inhibition, plasma protein binding, and permeability using MDCK-MDR1 cells. De-risking and preliminary safety pharmacology assays were performed through screening of 44 off-target receptors and in vivo tests in mice (rota-rod and single dose toxicity. LDT5 is stable in rat and human plasma, human liver microsomes and hepatocytes, but unstable in rat liver microsomes and hepatocytes (half-life of 11 min. LDT5 is highly permeable across the MDCK-MDR1 monolayer (Papp ∼32×10-6 cm/s, indicating good intestinal absorption and putative brain penetration. LDT5 is not extensively protein-bound and is a substrate of human CYP2D6 and CYP2C19 but not of CYP3A4 (half-life >60 min, and did not significantly influence the activities of any of the human cytochrome P450 isoforms screened. LDT5 was considered safe albeit new studies are necessary to rule out putative central adverse effects through D2, 5-HT1A and 5-HT2B receptors, after chronic use. This work highlights the drug-likeness properties of LDT5 and supports its further preclinical development.

  18. Opportunities for Using Building Information Modeling to Improve Worker Safety Performance

    Directory of Open Access Journals (Sweden)

    Kasim Alomari

    2017-02-01

    Full Text Available Building information modelling (BIM enables the creation of a digital representation of a designed facility combined with additional information about the project attributes, performance criteria, and construction process. Users of BIM tools point to the ability to visualize the final design along with the construction process as a beneficial feature of using BIM. Knowing the construction process in relationship to a facility’s design benefits both safety professionals when planning worker safety measures for a project and designers when creating a project’s design. Success in using BIM to enhance safety partly depends on the familiarity of project personnel with BIM tools and the extent to which the tools can be used to identify and eliminate safety hazards. In a separate, ongoing study, the authors investigated the connection between BIM and safety to document the opportunities, barriers, and impacts. Utilizing an on-line survey of project engineers who work for construction firms together with a comprehensive literature review, the study found those who use BIM feel that it aids in communication of project information and project delivery, both of which have been found to have positive impacts on construction site safety. Further, utilizing the survey results, the authors apply the binary logistic regression econometric framework to better understand the factors that lead to safety professionals believing that BIM increases safety in the work place. In addition, according to the survey results, a large percentage of the engineers who use BIM feel that ultimately it helps to eliminate safety hazards and improve worker safety. The study findings suggest that improvements in safety performance across the construction industry may be due in part to increased use of BIM in the construction industry.

  19. Exchange of information between nuclear safety authorities: Policy of the French regulator

    International Nuclear Information System (INIS)

    Asty, Michel

    2000-01-01

    Full text: The decree setting up the Nuclear Safety Authority in 1973 entrusted it with international assignments whose objectives are still valid: - develop exchanges of information with foreign counterparts on regulatory systems and practices, on problems encountered in the nuclear safety field and on provisions made, with a view to enhancing its approach, and - becoming better acquainted with the actual operating practice of these Safety Authorities from which lessons could be learned for its own working procedures; - improving its position in the technical discussions with the French operators, since its arguments would be strengthened by practical knowledge of conditions abroad; - make known and explain the French approach and practices in the nuclear safety field and provide information on measures taken to deal with the problems encountered. This approach has several objectives: - promote the circulation of information on French positions on certain issues, such as very low level waste, for instance; - assist some countries wishing to create or modify their Nuclear Safety Authority, such as countries of the former USSR, the Central and Eastern European countries, and emerging countries on other continents; - help, when requested, foreign Safety Authorities required to issue permits for nuclear equipment of French origin; - provide the countries concerned with all relevant information on French nuclear installations located near their frontiers. Examples are given on the way the French Nuclear Safety Authority implements these objectives. (author)

  20. Preliminary safety equipment list for Tank 241-C-106 Manipulator Retrieval System, Project W-340

    International Nuclear Information System (INIS)

    Guthrie, R.L.

    1994-01-01

    This document identifies the anticipated safety classification of the estimated major subsystems, based on the projected major functions, that will be used as guidance for the development of the conceptual design of the Manipulator Retrieval System for Tank 241-C-106. This document is intended to be updated as the design of the Manipulator Retrieval System evolves through the conceptual and definitive design phases. The Manipulator Retrieval System is to be capable of removing the hardened sludge heel at the bottom of single shell Tank 241-C-106 and to perform an overall clean out of the tank that leaves a maximum of 360 ft 3 (TPA milestone M-45-00). The thickness of the heel prior to initiation of waste retrieval with the Manipulator Retrieval System is estimated to be 1- to 2-ft. The Manipulator Retrieval System is currently in the pre-conceptual phase with no definitive systems or subsystems. The anticipated retrieval functions for the Manipulator Retrieval System is based on Table 6-2 of WHC-SD-W340-ES-001, Rev. 1. Projected equipment to accomplish these functions were based on the following systems and equipment: Rotary Mode Core Sampling Equipment (WHC-SD-WM-SEL-032); Light Duty Utility Arm System Equipment (WHC-SD-WM-SEL-034); Single Shell Tanks Equipment (WHC-SD-WM-SEL-020)

  1. [Transjugular intrahepatic portosystemic shunting with covered stents in children: a preliminary study of safety and patency].

    Science.gov (United States)

    Zurera, L J; Espejo, J J; Canis, M; Bueno, A; Vicente, J; Gilbert, J J

    2014-01-01

    To retrospectively analyze the safety and efficacy of transjugular intrahepatic portosystemic shunting (TIPS) using covered stents in children. We present 6 children (mean age, 10.6 years; mean weight, 33.5kg) who underwent TIPS with 8mm diameter Viatorr(®) covered stents for acute (n=4) or recurrent (n=2) upper digestive bleeding that could not be controlled by endoscopic measures. Five of the children had cirrhosis and the other had portal vein thrombosis with cavernous transformation. We analyzed the relapse of upper digestive bleeding, the complications that appeared, and the patency of the TIPS shunt on sequential Doppler ultrasonography or until transplantation. A single stent was implanted in a single session in each child; none of the children died. The mean transhepatic gradient decreased from 16mmHg (range: 12-21mmHg) before the procedure to 9mmHg (range: 1-15mmHg) after TIPS. One patient developed mild encephalopathy, and the girl who had portal vein thrombosis with cavernous transformation developed an acute occlusion of the TIPS that resolved after the implantation of a coaxial stent. Three children received transplants (7, 9, and 10 months after the procedure, respectively), and the patency of the TIPS was confirmed at transplantation. In the three remaining children, patency was confirmed with Doppler ultrasonography 1, 3, and 5 months after implantation. None of the children had new episodes of upper digestive bleeding during follow-up after implantation (mean: 8.1 months). Our results indicate that TIPS with 8mm diameter Viatorr(®) covered stents can be safe and efficacious for the treatment of upper digestive bleeding due to gastroesophageal varices in cirrhotic children; our findings need to be corroborated in larger series. Copyright © 2011 SERAM. Published by Elsevier Espana. All rights reserved.

  2. Report on probabilistic safety assessment (PSA) quality assurance in utilization of risk information

    International Nuclear Information System (INIS)

    2006-12-01

    Recently in Japan, introduction of nuclear safety regulations using risk information such as probabilistic safety assessment (PSA) has been considered and utilization of risk information in the rational and practical measures on safety assurance has made a progress to start with the operation or inspection area. The report compiled results of investigation and studies of PSA quality assurance in risk-informed activities in the USA. Relevant regulatory guide and standard review plan as well as issues and recommendations were reviewed for technical adequacy and advancement of probabilistic risk assessment technology in risk-informed decision making. Useful and important information to be referred as issues in PSA quality assurance was identified. (T. Tanaka)

  3. Use of information technologies to contribute for optimizing the safety radiation management in Cuba

    International Nuclear Information System (INIS)

    Valdes Ramos, M.; Prendes Alonso, M.; Hernandez Saiz, A.; Manzano de Armas, J.

    2013-01-01

    This paper presents the results achieved in Cuba, with the development of a group of information management tools to implement radiation safety systemic and proactive approaches to safety and ICT supported. These tools were designed for different organisms with responsibility for the security at the country level, to the regulatory authority, for user entities, for individual monitoring services and other radiation protection services. It describes the philosophy of information management model used, the characteristics of the developed tools and their integration, the work performed for the homogenization of information available and the ability to capture and deliver data at different levels in decision making. The tools developed are based on the use of variables and indicators of importance to the safety and the systemic approach adopted allows to facilitate the optimization process for supervision of safety practices as well as contribute to the management of knowledge in radiation safety, through a synergistic combination of process data, information, information management systems, and the creative and innovative radiation safety experts

  4. Transport safety research abstracts. No. 2. Information on research recently concluded and in progress

    International Nuclear Information System (INIS)

    1994-09-01

    Transport Safety Research Abstracts (TSRA) was first published by the IAEA in 1991 as a means of disseminating information on research in radioactive material transport. This second edition utilizes International Nuclear Information System (INIS) protocol for data processing and report preparation for a research-in-progress database established by the IAEA's Division of Scientific and Technical Information. INIS subject categories and descriptors are included in the information about each project

  5. Transport safety research abstracts. No. 2. Information on research recently concluded and in progress

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1994-09-01

    Transport Safety Research Abstracts (TSRA) was first published by the IAEA in 1991 as a means of disseminating information on research in radioactive material transport. This second edition utilizes International Nuclear Information System (INIS) protocol for data processing and report preparation for a research-in-progress database established by the IAEA`s Division of Scientific and Technical Information. INIS subject categories and descriptors are included in the information about each project.

  6. Safety

    International Nuclear Information System (INIS)

    1998-01-01

    A brief account of activities carried out by the Nuclear power plants Jaslovske Bohunice in 1997 is presented. These activities are reported under the headings: (1) Nuclear safety; (2) Industrial and health safety; (3) Radiation safety; and Fire protection

  7. Information Management system of the safety regulatory requirements and guidance for the Korea next generation reactors

    Energy Technology Data Exchange (ETDEWEB)

    Yun, Y. C. [LG-EDS Systems, Seoul (Korea, Republic of); Lee, J. H.; Lee, H. C.; Lee, J. S. [Korea Institute of Nuclear Safety, Taejon (Korea, Republic of)

    2000-05-01

    In order to achieve the safety of the Korea Next Generation Reactors (KNGR), the Korea Institute of Nuclear Safety has carried out the Safety and Regulatory Requirements and Guidance (SRRG) development program from 1992 such as establishment of the SRRG hierarchy, development of technical requirements and guidance, and consideration of new licensing system. The SRRG hierarchy for the KNGR was consisted of five tiers; Safety Objectives, Safety Principles, General Safety Criteria, Specific Safety Requirements and Safety Regulatory Guides. The developed SRRG have been compared the criteria in 10CFR and Reg. Guide in the U.S.A and the IAEA documents for assuring internationally acceptable level of the SRRG. To improve the efficiency and accuracy of SRRG development, the construction of database system was required in the course of development. Therefore, the Information Management System of SRRG for the KNGR has been developed which enables developers to quickly and accurately seek and systematically manage whole contexts of the SRRG, reference requirements, and current atomic energy regulation rules. Moreover, through homepage whose URL is 'http://kngr.kins.re.kr', the concerned persons and public can acquire the information related with SRRG and KNGR project, and post his/her thought to the opinion forum in the homepage.

  8. Information Management system of the safety regulatory requirements and guidance for the Korea next generation reactors

    International Nuclear Information System (INIS)

    Yun, Y. C.; Lee, J. H.; Lee, H. C.; Lee, J. S.

    2000-01-01

    In order to achieve the safety of the Korea Next Generation Reactors (KNGR), the Korea Institute of Nuclear Safety has carried out the Safety and Regulatory Requirements and Guidance (SRRG) development program from 1992 such as establishment of the SRRG hierarchy, development of technical requirements and guidance, and consideration of new licensing system. The SRRG hierarchy for the KNGR was consisted of five tiers; Safety Objectives, Safety Principles, General Safety Criteria, Specific Safety Requirements and Safety Regulatory Guides. The developed SRRG have been compared the criteria in 10CFR and Reg. Guide in the U.S.A and the IAEA documents for assuring internationally acceptable level of the SRRG. To improve the efficiency and accuracy of SRRG development, the construction of database system was required in the course of development. Therefore, the Information Management System of SRRG for the KNGR has been developed which enables developers to quickly and accurately seek and systematically manage whole contexts of the SRRG, reference requirements, and current atomic energy regulation rules. Moreover, through homepage whose URL is 'http://kngr.kins.re.kr', the concerned persons and public can acquire the information related with SRRG and KNGR project, and post his/her thought to the opinion forum in the homepage

  9. A risk-informed perspective on deterministic safety analysis of nuclear power plants

    International Nuclear Information System (INIS)

    Wan, P.T.

    2009-01-01

    In this work, the deterministic safety analysis (DSA) approach to nuclear safety is examined from a risk-informed perspective. One objective of safety analysis of a nuclear power plant is to demonstrate via analysis that the risks to the public from events or accidents that are within the design basis of the power plant are within acceptable levels with a high degree of assurance. This nuclear safety analysis objective can be translated into two requirements on the risk estimates of design basis events or accidents: the nominal risk estimate to the public must be shown to be within acceptable levels, and the uncertainty in the risk estimates must be shown to be small on an absolute or relative basis. The DSA approach combined with the defense-in-depth (DID) principle is a simplified safety analysis approach that attempts to achieve the above safety analysis objective in the face of potentially large uncertainties in the risk estimates of a nuclear power plant by treating the various uncertainty contributors using a stylized conservative binary (yes-no) approach, and applying multiple overlapping physical barriers and defense levels to protect against the release of radioactivity from the reactor. It is shown that by focusing on the consequence aspect of risk, the previous two nuclear safety analysis requirements on risk can be satisfied with the DSA-DID approach to nuclear safety. It is also shown the use of multiple overlapping physical barriers and defense levels in the traditional DSA-DID approach to nuclear safety is risk-informed in the sense that it provides a consistently high level of confidence in the validity of the safety analysis results for various design basis events or accidents with a wide range of frequency of occurrence. It is hoped that by providing a linkage between the consequence analysis approach in DSA with a risk-informed perspective, greater understanding of the limitation and capability of the DSA approach is obtained. (author)

  10. Factors shaping effective utilization of health information technology in urban safety-net clinics.

    Science.gov (United States)

    George, Sheba; Garth, Belinda; Fish, Allison; Baker, Richard

    2013-09-01

    Urban safety-net clinics are considered prime targets for the adoption of health information technology innovations; however, little is known about their utilization in such safety-net settings. Current scholarship provides limited guidance on the implementation of health information technology into safety-net settings as it typically assumes that adopting institutions have sufficient basic resources. This study addresses this gap by exploring the unique challenges urban resource-poor safety-net clinics must consider when adopting and utilizing health information technology. In-depth interviews (N = 15) were used with key stakeholders (clinic chief executive officers, medical directors, nursing directors, chief financial officers, and information technology directors) from staff at four clinics to explore (a) nonhealth information technology-related clinic needs, (b) how health information technology may provide solutions, and (c) perceptions of and experiences with health information technology. Participants identified several challenges, some of which appear amenable to health information technology solutions. Also identified were requirements for effective utilization of health information technology including physical infrastructural improvements, funding for equipment/training, creation of user groups to share health information technology knowledge/experiences, and specially tailored electronic billing guidelines. We found that despite the potential benefit that can be derived from health information technologies, the unplanned and uninformed introduction of these tools into these settings might actually create more problems than are solved. From these data, we were able to identify a set of factors that should be considered when integrating health information technology into the existing workflows of low-resourced urban safety-net clinics in order to maximize their utilization and enhance the quality of health care in such settings.

  11. Natural language retrieval in nuclear safety information system

    International Nuclear Information System (INIS)

    Komata, Masaoki; Oosawa, Yasuo; Ujita, Hiroshi

    1983-01-01

    A natural language retrieval program NATLANG is developed to assist in the retrieval of information from event-and-cause descriptions in Licensee Event Reports (LER). The characteristics of NATLANG are (1) the use of base forms of words to retrieve related forms altered by the addition of prefixes or suffixes or changes in inflection, (2) direct access and short time retrieval with an alphabet pointer, (3) effective determination of the items and entries for a Hitachi event classification in a two step retrieval scheme, and (4) Japanese character output with the PL-1 language. NATLANG output reduces the effort needed to re-classify licensee events in the Hitachi event classification. (author)

  12. CMIS: Crime Map Information System for Safety Environment

    Science.gov (United States)

    Kasim, Shahreen; Hafit, Hanayanti; Yee, Ng Peng; Hashim, Rathiah; Ruslai, Husni; Jahidin, Kamaruzzaman; Syafwan Arshad, Mohammad

    2016-11-01

    Crime Map is an online web based geographical information system that assists the public and users to visualize crime activities geographically. It acts as a platform for the public communities to share crime activities they encountered. Crime and violence plague the communities we are living in. As part of the community, crime prevention is everyone's responsibility. The purpose of Crime Map is to provide insights of the crimes occurring around Malaysia and raise the public's awareness on crime activities in their neighbourhood. For that, Crime Map visualizes crime activities on a geographical heat maps, generated based on geospatial data. Crime Map analyse data obtained from crime reports to generate useful information on crime trends. At the end of the development, users should be able to make use of the system to access to details of crime reported, crime analysis and report crimes activities. The development of Crime Map also enable the public to obtain insights about crime activities in their area. Thus, enabling the public to work together with the law enforcer to prevent and fight crime.

  13. Creation and preliminary validation of the screening for self-medication safety post-stroke scale (S-5).

    Science.gov (United States)

    Kaizer, Franceen; Kim, Angela; Van, My Tram; Korner-Bitensky, Nicol

    2010-03-01

    Patients with stroke should be screened for safety prior to starting a self-medication regime. An extensive literature review revealed no standardized self-medication tool tailored to the multi-faceted needs of the stroke population. The aim of this study was to create and validate a condition-specific tool to be used in screening for self-medication safety in individuals with stroke. Items were generated using expert consultation and review of the existing tools. The draft tool was pilot-tested on expert stroke clinicians to receive feedback on content, clarity, optimal cueing and domain omissions. The final version was piloted on patients with stroke using a structured interviewer-administered interview. The tool was progressively refined and validated according to feedback from the 11 expert reviewers. The subsequent version was piloted on patients with stroke. The final version includes 16 questions designed to elicit information on 5 domains: cognition, communication, motor, visual-perception and, judgement/executive function/self-efficacy. The Screening for Safe Self-medication post-Stroke Scale (S-5) has been created and validated for use by health professionals to screen self-medication safety readiness of patients after stroke. Its use should also help to guide clinicians' recommendations and interventions aimed at enhancing self-medication post-stroke.

  14. Improving Aviation Safety with information Visualization: A Flight Simulation Study

    Science.gov (United States)

    Aragon, Cecilia R.; Hearst, Marti

    2005-01-01

    Many aircraft accidents each year are caused by encounters with invisible airflow hazards. Recent advances in aviation sensor technology offer the potential for aircraft-based sensors that can gather large amounts of airflow velocity data in real-time. With this influx of data comes the need to study how best to present it to the pilot - a cognitively overloaded user focused on a primary task other than that of information visualization. In this paper, we present the results of a usability study of an airflow hazard visualization system that significantly reduced the crash rate among experienced helicopter pilots flying a high fidelity, aerodynamically realistic fixed-base rotorcraft flight simulator into hazardous conditions. We focus on one particular aviation application, but the results may be relevant to user interfaces in other operationally stressful environments.

  15. Using Active Learning to Identify Health Information Technology Related Patient Safety Events.

    Science.gov (United States)

    Fong, Allan; Howe, Jessica L; Adams, Katharine T; Ratwani, Raj M

    2017-01-18

    The widespread adoption of health information technology (HIT) has led to new patient safety hazards that are often difficult to identify. Patient safety event reports, which are self-reported descriptions of safety hazards, provide one view of potential HIT-related safety events. However, identifying HIT-related reports can be challenging as they are often categorized under other more predominate clinical categories. This challenge of identifying HIT-related reports is exacerbated by the increasing number and complexity of reports which pose challenges to human annotators that must manually review reports. In this paper, we apply active learning techniques to support classification of patient safety event reports as HIT-related. We evaluated different strategies and demonstrated a 30% increase in average precision of a confirmatory sampling strategy over a baseline no active learning approach after 10 learning iterations.

  16. Licensing assessment of the Candu Pressurized Heavy Water Reactor. Preliminary safety information document. Volume II

    International Nuclear Information System (INIS)

    1977-06-01

    ERDA has requested United Engineers and Constructors (UE and C) to evaluate the design of the Canadian natural uranium fueled, heavy water moderated (CANDU) nuclear reactor power plant to assess its conformance with the licensing criteria and guidelines of the U.S. Nuclear Regulatory Commission (USNRC) for light water reactors. This assessment was used to identify cost significant items of nonconformance and to provide a basis for developing a detailed cost estimate for a 1140 MWe, 3-loop Pressurized Heavy Water Reactor (PHWR) located at the Middletown, USA Site

  17. Transactions of the Twenty-First Water Reactor Safety Information Meeting

    International Nuclear Information System (INIS)

    Monteleone, S.

    1993-10-01

    This report contains summaries of papers on reactor safety research to be presented at the 21st Water Reactor Safety Information Meeting at the Bethesda Marriott Hotel, Bethesda, Maryland, October 25--27, 1993. The summaries briefly describe the programs and results of nuclear safety research sponsored by the Office of Nuclear Regulatory Research, US NRC. Summaries of invited papers concerning nuclear safety issues from US government laboratories, the electric utilities, the Electric Power Research Institute (EPRI), the nuclear industry, and from foreign governments and industry are also included. The summaries have been compiled in one report to provide a basis for meaningful discussion and information exchange during the course of the meeting and are given in the order of their presentation in each session

  18. Transactions of the twenty-fifth water reactor safety information meeting

    Energy Technology Data Exchange (ETDEWEB)

    Monteleone, S. [comp.

    1997-09-01

    This report contains summaries of papers on reactor safety research to be presented at the 25th Water Reactor Safety Information Meeting at the Bethesda Marriott Hotel in Bethesda, Maryland, October 20--22, 1997. The summaries briefly describe the programs and results of nuclear safety research sponsored by the Office of Nuclear Regulatory Research, US NRC. Summaries of invited papers concerning nuclear safety issues from US government laboratories, the electric utilities, the nuclear industry, and from foreign governments and industry are also included. The summaries have been compiled in one report to provide a basis for meaningful discussion of information exchanged during the course of the meeting, and are given in order of their presentation in each session.

  19. Transactions of the twenty-fifth water reactor safety information meeting

    International Nuclear Information System (INIS)

    Monteleone, S.

    1997-09-01

    This report contains summaries of papers on reactor safety research to be presented at the 25th Water Reactor Safety Information Meeting at the Bethesda Marriott Hotel in Bethesda, Maryland, October 20--22, 1997. The summaries briefly describe the programs and results of nuclear safety research sponsored by the Office of Nuclear Regulatory Research, US NRC. Summaries of invited papers concerning nuclear safety issues from US government laboratories, the electric utilities, the nuclear industry, and from foreign governments and industry are also included. The summaries have been compiled in one report to provide a basis for meaningful discussion of information exchanged during the course of the meeting, and are given in order of their presentation in each session

  20. Why consumers behave as they do with respect to food safety and risk information

    DEFF Research Database (Denmark)

    Verbeke, Wim; Frewer, Lynn J.; Scholderer, Joachim

    2007-01-01

    rankings. The aim of this contribution is to provide a better understanding to food risk analysts of why consumers behave as they do with respect to food safety and risk information. This paper presents some cases of seemingly irrational and inconsistent consumer behaviour with respect to food safety...... and risk information and provides explanations for these behaviours based on the nature of the risk and individual psychological processes. Potential solutions for rebuilding consumer confidence in food safety and bridging between lay and expert opinions towards food risks are reviewed. These include......In recent years, it seems that consumers are generally uncertain about the safety and quality of their food and their risk perception differs substantially from that of experts. Hormone and veterinary drug residues in meat persist to occupy a high position in European consumers' food concern...

  1. Transactions of the twenty-second water reactor safety information meeting

    International Nuclear Information System (INIS)

    1994-10-01

    This report contains summaries of papers on reactor safety research to be presented at the 22nd Water Reactor Safety Information Meeting at the Bethesda Marriott Hotel, Bethesda, Maryland, October 24--26, 1994. The summaries briefly describe the programs and results of nuclear safety research sponsored by the Office of Nuclear Regulatory Research, US NRC. Summaries of invited papers concerning nuclear safety issues from US government laboratories, the electric utilities, the nuclear industry, and from foreign governments and industry are also included. The summaries have been compiled in one report to provide a basis for meaningful discussion and information exchange during the course of the meeting and are given in the order of their presentation in each session. Individual papers have been cataloged separately

  2. Transactions of the Twenty-First Water Reactor Safety Information Meeting

    Energy Technology Data Exchange (ETDEWEB)

    Monteleone, S. [comp.

    1993-10-01

    This report contains summaries of papers on reactor safety research to be presented at the 21st Water Reactor Safety Information Meeting at the Bethesda Marriott Hotel, Bethesda, Maryland, October 25--27, 1993. The summaries briefly describe the programs and results of nuclear safety research sponsored by the Office of Nuclear Regulatory Research, US NRC. Summaries of invited papers concerning nuclear safety issues from US government laboratories, the electric utilities, the Electric Power Research Institute (EPRI), the nuclear industry, and from foreign governments and industry are also included. The summaries have been compiled in one report to provide a basis for meaningful discussion and information exchange during the course of the meeting and are given in the order of their presentation in each session.

  3. Participatory approach to improving safety, health and working conditions in informal economy workplaces in Cambodia.

    Science.gov (United States)

    Kawakami, Tsuyoshi; Tong, Leng; Kannitha, Yi; Sophorn, Tun

    2011-01-01

    The present study aimed to improve safety and health in informal economy workplaces such as home workplaces, small construction sites, and rural farms in Cambodia by using "participatory" approach. The government, workers' and employers' organizations and NGOs jointly assisted informal economy workers in improving safety and health by using participatory training methodologies. The steps taken were: (1) to collect existing good practices in safety and health in Cambodia; (2) to develop new participatory training programmes for home workers and small construction sites referring to ILO's WISE training programme, and (3) to train government officers, workers, employers and NGOs as safety and health trainers. The participatory training programmes developed consisted of action-checklists associated with illustrations, good example photo sheets, and texts explaining practical, low-cost improvement measures. The established safety and health trainers reached many informal economy workers through their human networks, and trained them by using the developed participatory training programmes. More than 3,000 informal economy workers were trained and they implemented improvements by using low-cost methods. Participatory training methodologies and active cooperation between the government, workers, employers and NGOs made it possible to provide practical training for those involved in the informal economy workplaces.

  4. Trade associations and labor organizations as intermediaries for disseminating workplace safety and health information.

    Science.gov (United States)

    Okun, Andrea H; Watkins, Janice P; Schulte, Paul A

    2017-09-01

    There has not been a systematic study of the nature and extent to which business and professional trade associations and labor organizations obtain and communicate workplace safety and health information to their members. These organizations can serve as important intermediaries and play a central role in transferring this information to their members. A sample of 2294 business and professional trade associations and labor organizations in eight industrial sectors identified by the National Occupational Research Agenda was surveyed via telephone. A small percent of these organizations (40.9% of labor organizations, 15.6% of business associations, and 9.6% of professional associations) were shown to distribute workplace safety and health information to their members. Large differences were also observed between industrial sectors with construction having the highest total percent of organizations disseminating workplace safety and health information. There appears to be significant potential to utilize trade and labor organizations as intermediaries for transferring workplace safety and health information to their members. Government agencies have a unique opportunity to partner with these organizations and to utilize their existing communication channels to address high risk workplace safety and health concerns. Published 2017. This article is a U.S. Government work and is in the public domain in the USA.

  5. Proceedings of the US Nuclear Regulatory Commission twentieth water reactor safety information meeting

    International Nuclear Information System (INIS)

    Weiss, A.J.

    1993-03-01

    This three-volume report contains papers presented at the Twentieth Water Reactor Safety Information Meeting held at the Bethesda Marriott Hotel, Bethesda, Maryland, during the week of October 21--23, 1992. The papers describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included 10 different papers presented by researchersfrom CEC, China, Finland, France, Germany, Japan, Spain and Taiwan

  6. Report of the 52. meeting of the Superior Council of the Nuclear Safety and Information (project)

    International Nuclear Information System (INIS)

    2000-01-01

    Since june 2000, the CSSIN (Superior Council on Nuclear Safety and Information) decided to present the meeting of its sessions, on the Internet site of the Nuclear Safety Authority. This document is the meeting project concerning the session of the 27 june 2000. The following subjects have been treated: the Blayais accident and its consequences; the Euratom Directive transposition on the workers and people protection; methodology and organization of the CSSIN concerning the civil nuclear installations and the radiation protection; actualization of the CSSIN heading in the Internet site of the Nuclear Safety Authority. (A.L.B.)

  7. 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

  8. Design Information from the PSA for Digital Safety-Critical Systems

    International Nuclear Information System (INIS)

    Kang, Hyun Gook; Jang, Seung Cheol

    2005-01-01

    Many safety-critical applications such as nuclear field application usually adopt a similar design strategy for digital safety-critical systems. Their differences from the normal design for the non-safety-critical applications could be summarized as: multiple-redundancy, highly reliable components, strengthened monitoring mechanism, verified software, and automated test procedure. These items are focusing on maintaining the capability to perform the given safety function when it is requested. For the past several decades, probabilistic safety assessment (PSA) techniques are used in the nuclear industry to assess the relative effects of contributing events on plant risk and system reliability. They provide a unifying means of assessing physical faults, recovery processes, contributing effects, human actions, and other events that have a high degree of uncertainty. The applications of PSA provide not only the analysis results of already installed system but also the useful information for the system under design. The information could be derived from the PSA experience of the various safety-critical systems. Thanks to the design flexibility, the digital system is one of the most suitable candidates for risk-informed design (RID). In this article, we will describe the feedbacks for system design and try to develop a procedure for RID. Even though the procedure is not sophisticated enough now, it could be the start point of the further investigation for developing more complete and practical methodology

  9. Measuring Health Information Dissemination and Identifying Target Interest Communities on Twitter: Methods Development and Case Study of the @SafetyMD Network.

    Science.gov (United States)

    Kandadai, Venk; Yang, Haodong; Jiang, Ling; Yang, Christopher C; Fleisher, Linda; Winston, Flaura Koplin

    2016-05-05

    Little is known about the ability of individual stakeholder groups to achieve health information dissemination goals through Twitter. This study aimed to develop and apply methods for the systematic evaluation and optimization of health information dissemination by stakeholders through Twitter. Tweet content from 1790 followers of @SafetyMD (July-November 2012) was examined. User emphasis, a new indicator of Twitter information dissemination, was defined and applied to retweets across two levels of retweeters originating from @SafetyMD. User interest clusters were identified based on principal component analysis (PCA) and hierarchical cluster analysis (HCA) of a random sample of 170 followers. User emphasis of keywords remained across levels but decreased by 9.5 percentage points. PCA and HCA identified 12 statistically unique clusters of followers within the @SafetyMD Twitter network. This study is one of the first to develop methods for use by stakeholders to evaluate and optimize their use of Twitter to disseminate health information. Our new methods provide preliminary evidence that individual stakeholders can evaluate the effectiveness of health information dissemination and create content-specific clusters for more specific targeted messaging.

  10. Preliminary Analysis of a Steam Line Break Accident with the MARS-KS code for the SMART Design with Passive Safety Systems

    Energy Technology Data Exchange (ETDEWEB)

    Kang, Doohyuk; Ko, Yungjoo; Suh, Jaeseung [Hannam Univ., Daejeon (Korea, Republic of); Bae, Hwang; Ryu, Sunguk; Yi, Sungjae; Park, Hyunsik [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2014-05-15

    SMART has been developed by KAERI, and SMART-Standard Design Approval (SDA) was recently granted in 2012. A SMART design with Passive Safety System (PSS) features (called SMART-PSS) is being developed and added to the standard design of SMART by KAERI to improve its safety system. Active safety systems such as safety injection pumps will be replaced by a passive safety system, which is actuated only by the gravity force caused by the height difference. All tanks for the passive safety systems are higher than the injection nozzle, which is located around the reactor coolant pumps (RCPs). In this study, a preliminary analysis of the main steam line break accident (MSLB) was performed using the MARS-KS code to understand the general behavior of the SMART-PSS design and to prepare its validation test with the SMART-ITL (FESTA) facility. An anticipated accident for the main steam line break (MSLB) was performed using the MARS-KS code to understand the thermal-hydraulic behaviors of the SMART-PSS design. The preliminary analysis provides good insight into the passive safety system design features of the SMART-PSS and the thermal-hydraulic characteristics of the SMART design. The analysis results of the MSLB showed that the core water collapsed level inside the core support barrel was maintained high over the active core top level during the transient period. Therefore, the SMART-PSS design has satisfied the requirements to maintain the plant at a safe shutdown condition during 72 hours without AC power or operator action after an anticipated accident.

  11. High committee for nuclear safety transparency and information. March 17, 2009 meeting

    International Nuclear Information System (INIS)

    2009-03-01

    The high committee for the nuclear safety transparency and information (HCTISN) is an information, consultation and debate authority devoted to the assessment of the risks linked with nuclear activities and to the analysis of their impact on public health, on the environment and on nuclear safety. Each year, the HCTISN organizes several ordinary meetings in order to analyze some specific topics of the moment. This meeting was organized around 9 main topics: 1 - presentation by the French nuclear safety authority (ASN) of a dismantling strategy for nuclear facilities, in particular taking into account a final state for the site and the information of populations; 2 - status of the next campaign of iodine tablets distribution; 3 - the management of ancient uranium mines and in particular the long-term environmental and health impact of mine tailings; 4 - the implementation of the high committee's recommendations; 5 - work progress of the working group on information transparency; 6 - Areva's invitation of the working group on information transparency to assist to the organisation of a Mox fuel convoy between Cherbourg and Japan; 7 - progress of the working group on the elaboration of a 'communication scale' comparable to the INES scale; 8 - presentation of the meetings organized by the ANCLI (French national association of local information commissions) about the implementation of the Aarhus convention; 9 - presentation by the IRSN (Institute of radiation protection and nuclear safety) of its communication approach towards the public. (J.S.)

  12. Standardized System of Nuclear Safety Information for the Promotion of Transparency and Openness

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Gihyung; Kim, Sanghyun; Lee, Gyehwi; Yoon, Yeonhwa; Song, Song Hyerim; Jeong, Jina [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of); Byun, Jaehyung; Seo, Jonghwan [Dong-A Univ., Busan (Korea, Republic of)

    2013-05-15

    There has been an increasing emphasis on the need for increased disclosure of information through the home page of the Korea Institute of Nuclear Safety (KINS), responsible for nuclear safety regulations, and the Nuclear Safety Information Center (NSIC) to enhance public understanding of nuclear safety. However, due to the dazzled structure of the existing KINS and NSIC home pages, improvements in accessibility and convenience are necessary. At the same time, content standardization is required to increase operational efficiency and provide coherent information. In this study, the Delphi method was used to select the major contents to make available on the home page as well as the main user base definition for the home page layout development. Also, internal and external expert groups were created to conduct AHP (Analytic Hierarchy Process) analysis and develop the comparative analysis items for the U. S. Nuclear Regulatory Commission(NRC)/KINS/NSIC home pages. Afterwards, problems and points of improvements for the home page system, design, and profile were derived using heuristic analysis. The implications arising from the Delphi analysis results were applied to the home page layout. In the nuclear safety information standardized system construction process, the comparative analysis conducted using the AHP and heuristic analyses of the NRC home page resulted in deriving improvements for the Guidance, Organization, and Trustworthy items of the KINS/NSIC home page. Furthermore, through the Delphi analysis, a clear purpose and core values were set for the KINS web site, and the needs of the main user base were identified. By developing the home page layout, user interest and utility were raised to improve the organization method and layout. Through this study, KINS was able to construct a nuclear safety information standardized system and increase transparency and openness by providing feature enhancements in information provision as well as user accessibility and

  13. Standardized System of Nuclear Safety Information for the Promotion of Transparency and Openness

    International Nuclear Information System (INIS)

    Lee, Gihyung; Kim, Sanghyun; Lee, Gyehwi; Yoon, Yeonhwa; Song, Song Hyerim; Jeong, Jina; Byun, Jaehyung; Seo, Jonghwan

    2013-01-01

    There has been an increasing emphasis on the need for increased disclosure of information through the home page of the Korea Institute of Nuclear Safety (KINS), responsible for nuclear safety regulations, and the Nuclear Safety Information Center (NSIC) to enhance public understanding of nuclear safety. However, due to the dazzled structure of the existing KINS and NSIC home pages, improvements in accessibility and convenience are necessary. At the same time, content standardization is required to increase operational efficiency and provide coherent information. In this study, the Delphi method was used to select the major contents to make available on the home page as well as the main user base definition for the home page layout development. Also, internal and external expert groups were created to conduct AHP (Analytic Hierarchy Process) analysis and develop the comparative analysis items for the U. S. Nuclear Regulatory Commission(NRC)/KINS/NSIC home pages. Afterwards, problems and points of improvements for the home page system, design, and profile were derived using heuristic analysis. The implications arising from the Delphi analysis results were applied to the home page layout. In the nuclear safety information standardized system construction process, the comparative analysis conducted using the AHP and heuristic analyses of the NRC home page resulted in deriving improvements for the Guidance, Organization, and Trustworthy items of the KINS/NSIC home page. Furthermore, through the Delphi analysis, a clear purpose and core values were set for the KINS web site, and the needs of the main user base were identified. By developing the home page layout, user interest and utility were raised to improve the organization method and layout. Through this study, KINS was able to construct a nuclear safety information standardized system and increase transparency and openness by providing feature enhancements in information provision as well as user accessibility and

  14. Riding on air: critical safety information for you and your tires

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2002-07-01

    This booklet is issued for public distribution by Transport Canada. It provides a few simple tips concerning automobile tire safety which, if followed, is expected to result in increased personal and vehicle safety, improved fuel economy, prolonged tire life, energy savings and reduced environmental pollution. The information provided include tips about tire pressure, tire inspection for damage and wear, rotation of tires for more even wear, replacing worn tires, the advantages of using snow tires in winter and an explanation of the meaning of the information found on the tire sidewall.

  15. Classification of antecedents towards safety use of health information technology: A systematic review.

    Science.gov (United States)

    Salahuddin, Lizawati; Ismail, Zuraini

    2015-11-01

    This paper provides a systematic review of safety use of health information technology (IT). The first objective is to identify the antecedents towards safety use of health IT by conducting systematic literature review (SLR). The second objective is to classify the identified antecedents based on the work system in Systems Engineering Initiative for Patient Safety (SEIPS) model and an extension of DeLone and McLean (D&M) information system (IS) success model. A systematic literature review (SLR) was conducted from peer-reviewed scholarly publications between January 2000 and July 2014. SLR was carried out and reported based on the preferred reporting items for systematic reviews and meta-analyses (PRISMA) statement. The related articles were identified by searching the articles published in Science Direct, Medline, EMBASE, and CINAHL databases. Data extracted from the resultant studies included are to be analysed based on the work system in Systems Engineering Initiative for Patient Safety (SEIPS) model, and also from the extended DeLone and McLean (D&M) information system (IS) success model. 55 articles delineated to be antecedents that influenced the safety use of health IT were included for review. Antecedents were identified and then classified into five key categories. The categories are (1) person, (2) technology, (3) tasks, (4) organization, and (5) environment. Specifically, person is attributed by competence while technology is associated to system quality, information quality, and service quality. Tasks are attributed by task-related stressor. Organisation is related to training, organisation resources, and teamwork. Lastly, environment is attributed by physical layout, and noise. This review provides evidence that the antecedents for safety use of health IT originated from both social and technical aspects. However, inappropriate health IT usage potentially increases the incidence of errors and produces new safety risks. The review cautions future

  16. Information dissemination and use: critical components in occupational safety and health.

    Science.gov (United States)

    Schulte, P A; Okun, A; Stephenson, C M; Colligan, M; Ahlers, H; Gjessing, C; Loos, G; Niemeier, R W; Sweeney, M H

    2003-11-01

    Information dissemination is a mandated, but understudied, requirement of occupational and environmental health laws and voluntary initiatives. Research is needed on the factors that enhance and limit the development, transfer, and use of occupational safety and health information (OSH). Contemporary changes in the workforce, workplaces, and the nature of work will require new emphasis on the dissemination of information to foster prevention. Legislative and regulatory requirements and voluntary initiatives for dissemination of OSH information were identified and assessed. Literature on information dissemination was reviewed to identify important issues and useful approaches. More than 20 sections of laws and regulations were identified that mandated dissemination of occupational and environmental safety and health information. A four-stage approach for tracking dissemination and considering the flow of information was delineated. Special areas of dissemination were identified: the information needs of the changing workforce, new and young workers; small businesses; and workers with difficulty in understanding or reading English. We offer a framework for dissemination of OSH information and underscore the need to focus on the extent to which decision-makers and others receive and use such information. More solid data are also needed on current investments in disseminating, diffusing and applying OSH information and on the utility of that information. Am. J. Ind. Med. 44:515-531, 2003. Published 2003 Wiley-Liss, Inc.

  17. High committee for nuclear safety transparency and information. July 1, 2009 meeting

    International Nuclear Information System (INIS)

    2009-07-01

    The high committee for the nuclear safety transparency and information (HCTISN) is an information, consultation and debate authority devoted to the assessment of the risks linked with nuclear activities and to the analysis of their impact on public health, on the environment and on nuclear safety. Each year, the HCTISN organizes several ordinary meetings in order to analyze some specific topics of the moment. This meeting was organized around 5 main points: 1 - radioactive waste management: status and steps of the June 28, 2006 law, ANDRA's projects of deep geologic disposal for long living/high-medium activity wastes and of low depth disposal for long living/low activity wastes, French nuclear safety authority (ASN) opinion about the sites choice, implementation of article 10 of the June 28, 2006 law relative to public information; 2 - progress of the working groups' works on transparency and secrecy, on the development of a communication scale, and on the creation of an Internet portal for the radio-ecological follow-up of nuclear sites; 3 - comments of the ASN's report on the nuclear safety and radiation protection in France in 2008; 4 - procedure of management of the radio-physicists shortage in order to warrant the patients' safety and information; 5 - miscellaneous points: project of European directive on nuclear safety, organisation of a visit day onboard of a ship for nuclear materials transportation, comments about the by-law from May 5, 2009, relative to the exemption to informing consumers about the addition of radionuclides to consumption and construction products. (J.S.)

  18. Information report on nuclear safety and radiation protection of the ECRIN INB - Issue 2014

    International Nuclear Information System (INIS)

    2015-06-01

    Published in compliance with the French code of the environment, this report first presents the Malvesi establishment, the ECRIN basic nuclear installation (INB), the COMURHEX II project, and the policy for a sustainable development and continuous progress of this establishment. It describes the various measures regarding nuclear safety and radiation protection: nuclear safety, safety guarantee for personnel and installations, management of emergency situations, preservation of staff health and protection, inspections, actions undertaken regarding nuclear safety and radiation protection. It reports nuclear events which occurred, describes the management of effluents and the control of the environment (environmental policy, management of effluents from the Malvesi establishment, management of effluents from the ECRIN INB, reduction of consumptions). It addresses the waste management (industrial and radioactive wastes) and the management of other impacts of the ECRIN INB. It gives an overview of actions undertaken regarding information and transparency. Recommendations of the CHSCT are reported

  19. Information report on nuclear safety and radiation protection of the ECRIN INB - Issue 2012

    International Nuclear Information System (INIS)

    2013-06-01

    Published in compliance with the French code of the environment, this report first presents the Malvesi establishment, the ECRIN basic nuclear installation (INB), the COMURHEX II project, and the policy for a sustainable development and continuous progress of this establishment. It describes the various measures regarding nuclear safety and radiation protection: nuclear safety, safety guarantee for personnel and installations, management of emergency situations, preservation of staff health and protection, inspections, actions undertaken regarding nuclear safety and radiation protection. It reports nuclear events which occurred, describes the management of effluents and the control of the environment (environmental policy, management of effluents from the Malvesi establishment, management of effluents from the ECRIN INB, reduction of consumptions). It addresses the waste management (industrial and radioactive wastes) and the management of other impacts of the ECRIN INB. It gives an overview of actions undertaken regarding information and transparency. Recommendations of the CHSCT are reported

  20. Quality Indicators in Laboratory Medicine: from theory to practice. Preliminary data from the IFCC Working Group Project "Laboratory Errors and Patient Safety".

    Science.gov (United States)

    Sciacovelli, Laura; O'Kane, Maurice; Skaik, Younis Abdelwahab; Caciagli, Patrizio; Pellegrini, Cristina; Da Rin, Giorgio; Ivanov, Agnes; Ghys, Timothy; Plebani, Mario

    2011-05-01

    The adoption of Quality Indicators (QIs) has prompted the development of tools to measure and evaluate the quality and effectiveness of laboratory testing, first in the hospital setting and subsequently in ambulatory and other care settings. While Laboratory Medicine has an important role in the delivery of high-quality care, no consensus exists as yet on the use of QIs focussing on all steps of the laboratory total testing process (TTP), and further research in this area is required. In order to reduce errors in laboratory testing, the IFCC Working Group on "Laboratory Errors and Patient Safety" (WG-LEPS) developed a series of Quality Indicators, specifically designed for clinical laboratories. In the first phase of the project, specific QIs for key processes of the TTP were identified, including all the pre-, intra- and post-analytic steps. The overall aim of the project is to create a common reporting system for clinical laboratories based on standardized data collection, and to define state-of-the-art and Quality Specifications (QSs) for each QI independent of: a) the size of organization and type of activities; b) the complexity of processes undertaken; and c) different degree of knowledge and ability of the staff. The aim of the present paper is to report the results collected from participating laboratories from February 2008 to December 2009 and to identify preliminary QSs. The results demonstrate that a Model of Quality Indicators managed as an External Quality Assurance Program can serve as a tool to monitor and control the pre-, intra- and post-analytical activities. It might also allow clinical laboratories to identify risks that lead to errors resulting in patient harm: identification and design of practices that eliminate medical errors; the sharing of information and education of clinical and laboratory teams on practices that reduce or prevent errors; the monitoring and evaluation of improvement activities.

  1. Insights from an international stakeholder consultation to identify informational needs related to seafood safety

    Energy Technology Data Exchange (ETDEWEB)

    Tediosi, Alice, E-mail: alice.tediosi@aeiforia.eu [Aeiforia Srl, 29027 Gariga di Podenzano (PC) (Italy); Fait, Gabriella [Aeiforia Srl, 29027 Gariga di Podenzano (PC) (Italy); Jacobs, Silke [Department of Public Health, Ghent University, 9000 Ghent (Belgium); Department of Agricultural Economics, Ghent University, 9000 Ghent (Belgium); Verbeke, Wim [Department of Agricultural Economics, Ghent University, 9000 Ghent (Belgium); Álvarez-Muñoz, Diana [Catalan Institute for Water Research (ICRA), Parc Científic i Tecnològic de la Universitat de Girona, 17003 Girona (Spain); Diogene, Jorge [IRTA, 43540 Sant Carles de la Ràpita (Spain); Reuver, Marieke [AquaTT, Dublin 2 (Ireland); Marques, António [Division of Aquaculture and Upgrading (DivAV), Portuguese Institute for the Sea and Atmosphere (IPMA), 1449-006 Lisbon (Portugal); Capri, Ettore [Università Cattolica del Sacro Cuore, 29122 Piacenza (Italy)

    2015-11-15

    Food safety assessment and communication have a strong importance in reducing human health risks related to food consumption. The research carried out within the ECsafeSEAFOOD project aims to assess seafood safety issues, mainly related to non-regulated priority environmental contaminants, and to evaluate their impact on public health. In order to make the research results accessible and exploitable, and to respond to actual stakeholders' demands, a consultation with international stakeholders was performed by means of a survey. The focus was on policy and decision makers, food producers and processors, and agencies (i.e. EU and National or Regional agencies related to Food Safety or Public Health) and consumer organisations. The survey considered questions related to: seafood safety assessment and mitigation strategies, availability of data, such as the level of information on different contaminants, and communication among different stakeholder groups. Furthermore, stakeholders were asked to give their opinion on how they believe consumers perceive risks associated with environmental contaminants. The survey was distributed to 531 key stakeholders and 91 responses were received from stakeholders from 30 EU and non-EU countries. The main results show that communication between different groups of stakeholders needs to be improved and that there is a deficit of information and data in the field of seafood safety. This pertains mainly to the transfer of contaminants between the environment and seafood, and to the diversity of environmental contaminants such as plastic additives, algal toxins and hormones. On-line tools were perceived to be the most useful communication channel. - Highlights: • We consulted stakeholders to identify their needs about seafood safety. • An on-line survey was prepared and sent to gather stakeholders' opinions. • Communication among stakeholders needs to be improved. • There is a deficit of information and data in the

  2. Insights from an international stakeholder consultation to identify informational needs related to seafood safety

    International Nuclear Information System (INIS)

    Tediosi, Alice; Fait, Gabriella; Jacobs, Silke; Verbeke, Wim; Álvarez-Muñoz, Diana; Diogene, Jorge; Reuver, Marieke; Marques, António; Capri, Ettore

    2015-01-01

    Food safety assessment and communication have a strong importance in reducing human health risks related to food consumption. The research carried out within the ECsafeSEAFOOD project aims to assess seafood safety issues, mainly related to non-regulated priority environmental contaminants, and to evaluate their impact on public health. In order to make the research results accessible and exploitable, and to respond to actual stakeholders' demands, a consultation with international stakeholders was performed by means of a survey. The focus was on policy and decision makers, food producers and processors, and agencies (i.e. EU and National or Regional agencies related to Food Safety or Public Health) and consumer organisations. The survey considered questions related to: seafood safety assessment and mitigation strategies, availability of data, such as the level of information on different contaminants, and communication among different stakeholder groups. Furthermore, stakeholders were asked to give their opinion on how they believe consumers perceive risks associated with environmental contaminants. The survey was distributed to 531 key stakeholders and 91 responses were received from stakeholders from 30 EU and non-EU countries. The main results show that communication between different groups of stakeholders needs to be improved and that there is a deficit of information and data in the field of seafood safety. This pertains mainly to the transfer of contaminants between the environment and seafood, and to the diversity of environmental contaminants such as plastic additives, algal toxins and hormones. On-line tools were perceived to be the most useful communication channel. - Highlights: • We consulted stakeholders to identify their needs about seafood safety. • An on-line survey was prepared and sent to gather stakeholders' opinions. • Communication among stakeholders needs to be improved. • There is a deficit of information and data in the field of

  3. Information System Hazard Analysis: A Method for Identifying Technology-induced Latent Errors for Safety.

    Science.gov (United States)

    Weber, Jens H; Mason-Blakley, Fieran; Price, Morgan

    2015-01-01

    Many health information and communication technologies (ICT) are safety-critical; moreover, reports of technology-induced adverse events related to them are plentiful in the literature. Despite repeated criticism and calls to action, recent data collected by the Institute of Medicine (IOM) and other organization do not indicate significant improvements with respect to the safety of health ICT systems. A large part of the industry still operates on a reactive "break & patch" model; the application of pro-active, systematic hazard analysis methods for engineering ICT that produce "safe by design" products is sparse. This paper applies one such method: Information System Hazard Analysis (ISHA). ISHA adapts and combines hazard analysis techniques from other safety-critical domains and customizes them for ICT. We provide an overview of the steps involved in ISHA and describe.

  4. Smooth handling: the lack of safety-related consumer information in car advertisements.

    Science.gov (United States)

    Wilson, Nick; Maher, Anthony; Thomson, George; Keall, Michael

    2007-10-01

    To examine the content and trends of safety-related consumer information in magazine vehicle advertisements, as a case study within the worldwide marketing of vehicles. Content analysis of popular current affairs magazines in New Zealand for the 5-year period 2001-2005 was undertaken (n = 514 advertisements), supplemented with vehicle data from official websites. Safety information in advertisements for light passenger vehicles was relatively uncommon with only 27% mentioning one or more of nine key safety features examined (average: 1.7 out of nine features in this 27%). Also included were potentially hazardous features of: speed imagery (in 29% of advertisements), power references (14%), and acceleration data (4%). The speed and power aspects became relatively more common over the 5-year period (p advertisements and vehicle marketing - as already occurs with many other consumer products.

  5. 14 CFR 193.5 - How may I submit safety or security information and have it protected from disclosure?

    Science.gov (United States)

    2010-01-01

    ... SUBMITTED INFORMATION § 193.5 How may I submit safety or security information and have it protected from... 14 Aeronautics and Space 3 2010-01-01 2010-01-01 false How may I submit safety or security information and have it protected from disclosure? 193.5 Section 193.5 Aeronautics and Space FEDERAL AVIATION...

  6. Health Information Technology in Healthcare Quality and Patient Safety: Literature Review.

    Science.gov (United States)

    Feldman, Sue S; Buchalter, Scott; Hayes, Leslie W

    2018-06-04

    The area of healthcare quality and patient safety is starting to use health information technology to prevent reportable events, identify them before they become issues, and act on events that are thought to be unavoidable. As healthcare organizations begin to explore the use of health information technology in this realm, it is often unclear where fiscal and human efforts should be focused. The purpose of this study was to provide a foundation for understanding where to focus health information technology fiscal and human resources as well as expectations for the use of health information technology in healthcare quality and patient safety. A literature review was conducted to identify peer-reviewed publications reporting on the actual use of health information technology in healthcare quality and patient safety. Inductive thematic analysis with open coding was used to categorize a total of 41 studies. Three pre-set categories were used: prevention, identification, and action. Three additional categories were formed through coding: challenges, outcomes, and location. This study identifies five main categories across seven study settings. A majority of the studies used health IT for identification and prevention of healthcare quality and patient safety issues. In this realm, alerts, clinical decision support, and customized health IT solutions were most often implemented. Implementation, interface design, and culture were most often noted as challenges. This study provides valuable information as organizations determine where they stand to get the most "bang for their buck" relative to health IT for quality and patient safety. Knowing what implementations are being effectivity used by other organizations helps with fiscal and human resource planning as well as managing expectations relative to cost, scope, and outcomes. The findings from this scan of the literature suggest that having organizational champion leaders that can shepherd implementation, impact culture

  7. SAFETY

    CERN Multimedia

    Niels Dupont

    2013-01-01

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

  8. Tornadoes: Nature's Most Violent Storms. A Preparedness Guide Including Safety Information for Schools.

    Science.gov (United States)

    American National Red Cross, Washington, DC.

    This preparedness guide explains and describes tornadoes, and includes safety information for schools. A tornado is defined as a violently rotating column of air extending from a thunderstorm to the ground. The guide explains the cause of tornadoes, provides diagrams of how they form, describes variations of tornadoes, and classifies tornadoes by…

  9. Food Safety in the Domestic Environment: The Effect of Consumer Risk Information on Human Disease Risks

    NARCIS (Netherlands)

    Nauta, M.J.; Fischer, A.R.H.; Asselt, van E.D.; Jong, de A.E.I.; Frewer, L.J.; Jonge, de R.

    2008-01-01

    The improvement of food safety in the domestic environment requires a transdisciplinary approach, involving interaction between both the social and natural sciences. This approach is applied in a study on risks associated with Campylobacter on broiler meat. First, some web-based information

  10. Technical background information for the environmental and safety report, Volume 4: White Oak Lake and Dam

    International Nuclear Information System (INIS)

    Oakes, T.W.; Kelly, B.A.; Ohnesorge, W.F.; Eldridge, J.S.; Bird, J.C.; Shank, K.E.; Tsakeres, F.S.

    1982-03-01

    This report has been prepared to provide background information on White Oak Lake for the Oak Ridge National Laboratory Environmental and Safety Report. The paper presents the history of White Oak Dam and Lake and describes the hydrological conditions of the White Oak Creek watershed. Past and present sediment and water data are included; pathway analyses are described in detail

  11. High Committee for transparency and information on nuclear safety: Annual activity report (January 2010 - December 2010)

    International Nuclear Information System (INIS)

    2010-01-01

    After a description of the operation of the French 'High Committee for transparency and information on nuclear safety' (HCTISN), of its missions, its organisation and its means, the progress report presents the High Committee activity for 2010 with summaries of its report on the transparency of nuclear material and waste management, its meetings, its work groups, its visits and participations to other events

  12. Improving Hospital Quality and Patient Safety an Examination of Organizational Culture and Information Systems

    Science.gov (United States)

    Gardner, John Wallace

    2012-01-01

    This dissertation examines the effects of safety culture, including operational climate and practices, as well as the adoption and use of information systems for delivering high quality healthcare and improved patient experience. Chapter 2 studies the influence of both general and outcome-specific hospital climate and quality practices on process…

  13. Evolution of human factors research and studies of health information technologies: the role of patient safety

    NARCIS (Netherlands)

    Beuscart-Zéphir, M. C.; Borycki, E.; Carayon, P.; Jaspers, M. W. M.; Pelayo, S.

    2013-01-01

    The objective of this survey paper is to present and explain the impact of recent regulations and patient safety initiatives (EU, US and Canada) on Human Factors (HF)/Usability studies and research focusing on Health Information Technology (HIT). The authors have selected the most prominent of these

  14. The electronic security partnership of safety/security and information systems departments.

    Science.gov (United States)

    Yow, J Art

    2012-01-01

    The ever-changing world of security electronics is reviewed in this article. The author focuses on its usage in a hospital setting and the need for safety/security and information systems departments to work together to protect and get full value from IP systems.

  15. Increase plant safety and reduce cost by implementing risk-informed in-service inspection programs

    International Nuclear Information System (INIS)

    Billington, A.; Monette, P.

    2001-01-01

    The idea behind the program is that it is possible to 'inspect less, but inspect better'. In other words, the risk-informed In-Service Inspection (ISI) process is used to improve the effectiveness of examination of piping components, i.e. concentrate inspection resources and enhance inspection strategies on high safety significant locations, and reduce inspection requirements on others. The Westinghouse Owners Group (WOG) risk-informed ISI process has already been applied for full scope (Millstone 3, Surry 1) and limited scope (Beznau, Ringhals 4, Asco, Turkey Point 3). By examining the high safety significant piping segments for the different fluid piping systems, the total piping core damage frequency is reduced. In addition, more than 80% of the risk associated with potential pressure boundary failures is addressed with the WOG risk-informed ISI process, while typically less that 50% of this same risk is addressed by the current inspection programs. The risk-informed ISI processes are used to improve the effectiveness of inspecting safety-significant piping components, to reduce inspection requirements on other piping components, to evaluate improvements to plant availability and enhanced safety measures, including reduction of personnel radiation exposure, and to reduce overall Operation and Maintenance (O and M) costs while maintaining regulatory compliance. A description of the process as well as benefits from past projects is presented, since the methodology is applicable for WWER plant design. (author)

  16. Technical background information for the environmental and safety report, Volume 4: White Oak Lake and Dam

    Energy Technology Data Exchange (ETDEWEB)

    Oakes, T.W.; Kelly, B.A.; Ohnesorge, W.F.; Eldridge, J.S.; Bird, J.C.; Shank, K.E.; Tsakeres, F.S.

    1982-03-01

    This report has been prepared to provide background information on White Oak Lake for the Oak Ridge National Laboratory Environmental and Safety Report. The paper presents the history of White Oak Dam and Lake and describes the hydrological conditions of the White Oak Creek watershed. Past and present sediment and water data are included; pathway analyses are described in detail.

  17. Information report on nuclear safety and radiation protection of the Tricastin AREVA site, 2010 edition

    International Nuclear Information System (INIS)

    2010-01-01

    This report presents the Tricastin site, the different arrangements concerning nuclear safety and radiation protection on this site, and recent nuclear events. It describes how site releases are managed and how the environment is controlled and monitored, how wastes are managed, and how other impacts are controlled. It finally presents the different actions regarding transparency and information

  18. Negotiating the 'trading zone'. Creating a shared information infrastructure in the Dutch public safety sector

    NARCIS (Netherlands)

    Boersma, F.K.; Wagenaar, F.P.; Wolbers, J.J.

    2012-01-01

    Our main concern in this article is whether nation-wide information technology (IT) infrastructures or systems in emergency response and disaster management are the solution to the communication problems the safety sector suffers from. It has been argued that implementing nation-wide IT systems will

  19. 75 FR 35286 - Agency Information Collection Activities; Proposed Collection; Comment Request; Safety Standard...

    Science.gov (United States)

    2010-06-21

    ... the retail package. There are seven known firms supplying walkers to the United States market. Four of... instructional literature requirements in the Safety Standard for Infant walkers. DATES: Submit written or... for marking and instructional literature. We estimate the burden of this collection of information as...

  20. 75 FR 30783 - Agency Information Collection Activities; Proposed Collection; Comment Request; Safety Standard...

    Science.gov (United States)

    2010-06-02

    ... product and the retail package. There are three known firms supplying bath seats to the United States... marking and instructional literature requirements in the Safety Standard for Infant Bath Seats. DATES... for marking and instructional literature. We estimate the burden of this collection of information as...

  1. Increase plant safety and reduce cost by implementing risk-informed In-Service Inspection programs

    International Nuclear Information System (INIS)

    Billington, A.; Monette, P.; Doumont, C.

    2000-01-01

    The idea behind the program is that it is possible to 'inspect less, but inspect better'. In other words, the risk-informed In-Service Inspection (ISI) process is used to improve the effectiveness of examination of piping components, i.e. concentrate inspection resources and enhance inspection strategies on high safety significant locations, and reduce inspection requirements on others. The Westinghouse Owners Group (WOG) risk-informed ISI process has already been applied for full scope (Millstone 3, Surry 1) and limited scope (Beznau, Ringhals 4, Asco, Turkey Point 3). By examining the high safety significant piping segments for the different fluid piping systems, the total piping core damage frequency is reduced. In addition, more than 80% of the risk associated with potential pressure boundary failures is addressed with the WOG risk-informed ISI process, while typically less than 50% of this same risk is addressed by the current inspection programs. The risk-informed ISI processes are used: to improve the effectiveness of inspecting safety-significant piping components; to reduce inspection requirements on other piping components; to evaluate improvements to plant availability and enhanced safety measures, including reduction of personnel radiation exposure; and to reduce overall Operation and Maintenance (O and M) costs while maintaining regulatory compliance. A description of the process as well as benefits of past projects is presented, since the methodology is applicable for VVER plant design. (author)

  2. Quantitative and Qualitative Analysis of Nutrition and Food Safety Information in School Science Textbooks of India

    Science.gov (United States)

    Subba Rao, G. M.; Vijayapushapm, T.; Venkaiah, K.; Pavarala, V.

    2012-01-01

    Objective: To assess quantity and quality of nutrition and food safety information in science textbooks prescribed by the Central Board of Secondary Education (CBSE), India for grades I through X. Design: Content analysis. Methods: A coding scheme was developed for quantitative and qualitative analyses. Two investigators independently coded the…

  3. Perceptions of Psychological and Physical Safety Environments of Information Technology Employees: A Phenomenological Study

    Science.gov (United States)

    Payne, Sheila C.

    2012-01-01

    A qualitative phenomenological study was conducted to gain a deeper understanding of psychological and safety environments of an oil and gas multinational enterprise. Twenty information technology professionals were interviewed to explore their feelings, perceptions, beliefs, and values of the phenomenon. The interviews elicited data about facets…

  4. 75 FR 64348 - BOEMRE Information Collection Activity: 1010-0182, Increased Safety Measures for Energy...

    Science.gov (United States)

    2010-10-19

    ... No. BOEM-2010-0052] BOEMRE Information Collection Activity: 1010-0182, Increased Safety Measures for... the likelihood of blowouts, loss of well control, fires, spillages, physical obstruction to other... subsequent oil spill in the Gulf of Mexico. These events highlight the importance of ensuring safe operations...

  5. The Radiation Safety Information Computational Center (RSICC): A Resource for Nuclear Science Applications

    Energy Technology Data Exchange (ETDEWEB)

    Kirk, Bernadette Lugue [ORNL

    2009-01-01

    The Radiation Safety Information Computational Center (RSICC) has been in existence since 1963. RSICC collects, organizes, evaluates and disseminates technical information (software and nuclear data) involving the transport of neutral and charged particle radiation, and shielding and protection from the radiation associated with: nuclear weapons and materials, fission and fusion reactors, outer space, accelerators, medical facilities, and nuclear waste management. RSICC serves over 12,000 scientists and engineers from about 100 countries.

  6. Information requirements of the National Aeronautics and Space Administration's safety, environmental health, and occupational medicine programs

    Science.gov (United States)

    Whyte, A. A.

    1978-01-01

    A survey of the internal and external reporting and recordkeeping procedures of these programs was conducted and the major problems associated with them are outlined. The impact of probable future requirements on existing information systems is evaluated. This report also presents the benefits of combining the safety and health information systems into one computerized system and recommendations for the development and scope of that system.

  7. Feedback from incident reporting: information and action to improve patient safety.

    Science.gov (United States)

    Benn, J; Koutantji, M; Wallace, L; Spurgeon, P; Rejman, M; Healey, A; Vincent, C

    2009-02-01

    Effective feedback from incident reporting systems in healthcare is essential if organisations are to learn from failures in the delivery of care. Despite the wide-scale development and implementation of incident reporting in healthcare, studies in the UK suggest that information concerning system vulnerabilities could be better applied to improve operational safety within organisations. In this article, the findings and implications of research to identify forms of effective feedback from incident reporting are discussed, to promote best practices in this area. The research comprised a mixed methods review to investigate mechanisms of effective feedback for healthcare, drawing upon experience within established reporting programmes in high-risk industry and transport domains. Systematic searches of published literature were undertaken, and 23 case studies describing incident reporting programmes with feedback were identified for analysis from the international healthcare literature. Semistructured interviews were undertaken with 19 subject matter experts across a range of domains, including: civil aviation, maritime, energy, rail, offshore production and healthcare. In analysis, qualitative information from several sources was synthesised into practical requirements for developing effective feedback in healthcare. Both action and information feedback mechanisms were identified, serving safety awareness, improvement and motivational functions. The provision of actionable feedback that visibly improved systems was highlighted as important in promoting future reporting. Fifteen requirements for the design of effective feedback systems were identified, concerning: the role of leadership, the credibility and content of information, effective dissemination channels, the capacity for rapid action and the need for feedback at all levels of the organisation, among others. Above all, the safety-feedback cycle must be closed by ensuring that reporting, analysis and

  8. A qualitative exploration of patients' attitudes towards the 'Participate Inform Notice Know' (PINK) patient safety video.

    Science.gov (United States)

    Pinto, Anna; Vincent, Charles; Darzi, Ara; Davis, Rachel

    2013-02-01

    To explore patients' attitudes towards the PINK video, a patient education video aimed at encouraging hospital patients' involvement in safety-relevant behaviours. Qualitative semi-structured interviews. Detailed field notes were taken during the interviews which were analysed using content analysis. One National Health System (NHS) teaching hospital based in London, UK. Thirty-six in-patients aged between 20 and 79 years, 18 of them males. The PINK video is a short animated educational video aimed at encouraging patients to be involved in the safety of their care during hospitalization. Patients' perceptions of how informative, relevant and acceptable the video is; attitudes towards participating in the recommended safety-related behaviours and; potential negative side effects of watching the video. Overall the video was received favourably among the interviewees. Commonly cited benefits included raising awareness and facilitating patients to be involved in their care during their hospital stay. More variability was found in participants' views with regard to the video's role as a patient safety enhancement tool. A number of suggestions for improvement of the video were provided relating to tailoring its content and design to meet the needs of individual patients and their circumstances. Educational videos such as PINK have significant potential to empower patients in the safety and quality of their care. However, efforts to implement patient safety educational videos in practice need to consider different patient groups' needs and characteristics instead of trying to adopt 'a one size fits all' approach.

  9. Implantation of a safety management system information under the ISO 27001: risk analysis information

    Directory of Open Access Journals (Sweden)

    José Gregorio Arévalo Ascanio

    2015-11-01

    Full Text Available In this article the structure of the business of the city of Ocaña is explored with the aim of expanding the information and knowledge of the main variables of the productive activity of the municipality, its entrepreneurial spirit, technological development and productive structure. For this, a descriptive research was performed to identify economic activity in its various forms and promote the implementation of administrative practices consistent with national and international references.The results allowed to establish business weaknesses, including information, which once identified are used to design spaces training, acquisition of abilities and employers management practices in consistent with the challenges of competitiveness and stay on the market.As of the results was collected information regarding technological component companies of the productive fabric of the city, for which the application of tools for the analysis of information systems is proposed using the ISO 27001: 2005, using most appropriate technologies to study organizations that protect their most important asset information: information.

  10. EUMENES, a computer software for managing the radiation safety program information at an institutional level

    International Nuclear Information System (INIS)

    Hernandez Saiz, Alejandro; Cornejo Diaz, Nestor; Valdes Ramos, Maryzury; Martinez Gonzalez, Alina; Gonzalez Rodriguez, Niurka; Vergara Gil, Alex

    2008-01-01

    The correct application of national and international regulations in the field of Radiological Safety requires the implementation of Radiation Safety Programs appropriate to the developed practice. These Programs demand the preparation and keeping of an important number of records and data, the compliance with working schedules, systematic quality controls, audits, delivery of information to the Regulatory Authority, the execution of radiological assessments, etc. Therefore, it is unquestionable the necessity and importance of having a computer tool to support the management of the information related to the Radiation Safety Program in any institution. The present work describes a computer program that allows the efficient management of these data. Its design was based on the IAEA International Basic Safety Standards recommendations and on the requirements of the Cuban national standards, with the objective of being flexible enough to be applied in most of the institutions using ionizing radiations. The most important records of Radiation Safety Programs were incorporated and reports can be generated by the users. An additional tools-module allows the user to access to a radionuclide data library, and to carry out different calculations of interest in radiological protection. The program has been developed in Borland Delphi and manages Microsoft Access databases. It is a user friendly code that aims to support the optimization of Radiation Safety Programs. The program contributes to save resources and time, as the generated information is electronically kept and transmitted. The code has different security access levels according to the user responsibility at the institution and also provides for the analysis of the introduced data, in a quick and efficient way, as well as to notice deadlines, the exceeding of reference levels and situations that require attention. (author)

  11. Safety

    International Nuclear Information System (INIS)

    2001-01-01

    This annual report of the Senior Inspector for the Nuclear Safety, analyses the nuclear safety at EDF for the year 1999 and proposes twelve subjects of consideration to progress. Five technical documents are also provided and discussed concerning the nuclear power plants maintenance and safety (thermal fatigue, vibration fatigue, assisted control and instrumentation of the N4 bearing, 1300 MW reactors containment and time of life of power plants). (A.L.B.)

  12. Use of site specific data from Aespoe - preliminary results from the on-going safety analysis SR 97

    International Nuclear Information System (INIS)

    Stroem, A.; Selroos, J.O.; Andersson, Johan

    1998-01-01

    This paper discusses an on-going safety assessment study of SKB as well as the use of field data from Aespoe for obtaining input parameters for flow and radionuclide transport modelling in the geosphere. In the on-going Safety Assessment study SR 97, three individual sites in Sweden are used for exemplifying site specific conditions on overall repository performance. Thus, models capable of reproducing site specific characteristics are utilised. This is primarily obtained by implementing the geologic structural models in suitable conceptual models for groundwater flow on both regional and local scales. The models for flow incorporate observed and/or inferred water conducting features as well as other site-specific characteristics necessary for realistic descriptions of flow at the sites. The flow modelling thus aims at realism; the results obtained for present day conditions should not in any serious aspect conflict with observations at the site. Agreement between observed and modelled entities provides confidence in that a sound understanding of the site is obtained. Aespoe is one of the three sites providing site-specific conditions in SR 97. Transport is subsequently modelled using a stream tube approach where the 'travel times', for non-sorbing species, and discharge locations of a set of one-dimensional stream tubes are obtained from particle tracking in the flow model. The resulting distribution of 'travel times' in a single model realisation reflects the spatial variability and spatial extent of the repository, whereas the ensemble travel time distribution (over several realisations) for a given canister location reflects the uncertainty in travel time. The actual transport paths used in the transport modelling are thus dependent on site specific information such as e.g. existence of water conductive features. Other input parameters to the transport model are based on more generic and/or conservative arguments. However, the goal in a safety assessment

  13. Immunogenicity and Safety of the New Inactivated Quadrivalent Influenza Vaccine Vaxigrip Tetra: Preliminary Results in Children ≥6 Months and Older Adults

    Directory of Open Access Journals (Sweden)

    Emanuele Montomoli

    2018-03-01

    Full Text Available Since the mid-1980s, two lineages of influenza B viruses have been distinguished. These can co-circulate, limiting the protection provided by inactivated trivalent influenza vaccines (TIVs. This has prompted efforts to formulate quadrivalent influenza vaccines (QIVs, to enhance protection against circulating influenza B viruses. This review describes the results obtained from seven phase III clinical trials evaluating the immunogenicity, safety, and lot-to-lot consistency of a new quadrivalent split-virion influenza vaccine (Vaxigrip Tetra® formulated by adding a second B strain to the already licensed TIV. Since Vaxigrip Tetra was developed by means of a manufacturing process strictly related to that used for TIV, the data on the safety profile of TIV are considered supportive of that of Vaxigrip Tetra. The safety and immunogenicity of Vaxigrip Tetra were similar to those of the corresponding licensed TIV. Moreover, the new vaccine elicits a superior immune response towards the additional strain, without affecting immunogenicity towards the other three strains. Vaxigrip Tetra is well tolerated, has aroused no safety concerns, and is recommended for the active immunization of individuals aged ≥6 months. In addition, preliminary data confirm its immunogenicity and safety even in children aged 6–35 months and its immunogenicity in older subjects (aged 66–80 years.

  14. NASA Informal Education: Final Report. A Descriptive Analysis of NASA's Informal Education Portfolio: Preliminary Case Studies

    Science.gov (United States)

    Rulf Fountain, Alyssa; Levy, Abigail Jurist

    2010-01-01

    This report was requested by the National Aeronautics and Space Administration's (NASA), Office of Education in July 2009 to evaluate the Informal Education Program. The goals of the evaluation were twofold: (1) to gain insight into its investment in informal education; and (2) to clarify existing distinctions between its informal education…

  15. Risk-informed decision making a keystone in advanced safety assessment

    International Nuclear Information System (INIS)

    Reinhart, M.

    2007-01-01

    Probabilistic Safety Assessment (PSA) has provided extremely valuable complementary insight, perspective, comprehension, and balance to deterministic nuclear reactor safety assessment. This integrated approach of risk-informed management and decision making has been called Risk-Informed Decision Making (RIDM). RIDM provides enhanced safety, reliability, operational flexibility, reduced radiological exposure, and improved fiscal economy. Applications of RIDM continuously increase. Current applications are in the areas of design, construction, licensing, operations, and security. Operational phase safety applications include the following: technical specifications improvement, risk-monitors and configuration control, maintenance planning, outage planning and management, in-service inspection, inservice testing, graded quality assurance, reactor oversight and inspection, inspection finding significance determination, operational events assessment, and rulemaking. Interestingly there is a significant spectrum of approaches, methods, programs, controls, data bases, and standards. The quest of many is to assimilate the full compliment of PSA and RIDM information and to achieve a balanced international harmony. The goal is to focus the best of the best, so to speak, for the benefit of all. Accordingly, this presentation will address the principles, benefits, and applications of RIDM. It will also address some of the challenges and areas to improve. Finally it will highlight efforts by the IAEA and others to capture the international thinking, experience, successes, challenges, and lessons in RIDM. (authors)

  16. The importance of online communication in the information upon safety and security at work

    Directory of Open Access Journals (Sweden)

    Chiţu Ioana Bianca

    2017-07-01

    Full Text Available This study aims at presenting the employees’ opinions on the use of online environment as a medium for communicating the information related to labour safety and security. The study is based on a quantitative marketing research achieved by interviewing 95 participants, within a conference on labour safety and security. The idea of conducting this research was based on the increasing number of internet users in our country, as well as on the fact that the young generations are ever more dependent on the communication in the online environment, to the detriment of the communication by classical promotional media.

  17. Integrating risk management and safety culture in a framework for risk informed decision making

    International Nuclear Information System (INIS)

    Nelson, W.R.

    2009-01-01

    Operators and regulators of nuclear power plants agree on the importance of maintaining safety and controlling accident risks. Effective safety and risk management requires treatment of both technical and organizational components. Probabilistic Risk Assessment (PRA) provides tools for technical risk management. However, organizational factors are not treated in PRA, but are addressed using different approaches. To bring both components together, a framework of Risk Informed Decision Making (RIDM) is needed. The objective tree structure of the International Atomic Energy Agency (IAEA) is a promising approach to combine both elements. Effective collaboration involving regulatory and industry groups is needed to accomplish the integration. (author)

  18. 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)

  19. 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

  20. 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).

  1. Training in Information Management for Army Brigade and Battalion Staff: Methods and Preliminary Findings

    National Research Council Canada - National Science Library

    Freeman, Jared

    1997-01-01

    Training, training Support software, and measurement instruments were developed to help Army brigade and below staff manage information and overcome information overload in a digital messaging environment...

  2. Geoscientific long-term prognosis. Preliminary safety analysis for the site Gorleben; Geowissenschaftliche Langzeitprognose. Bericht zum Arbeitspaket 2. Vorlaeufige Sicherheitsanalyse fuer den Standort Gorleben

    Energy Technology Data Exchange (ETDEWEB)

    Mrugalla, Sabine [Bundesanstalt fuer Geowissenschaften und Rohstoffe, Hannover (Germany)

    2011-07-15

    The preliminary safety analysis of the site Gorleben includes the following chapters: (1) Introduction; (2) Aim and content of the geoscientific long-term prognosis for the site Gorleben; (3) Boundary conditions at the site Gorleben: climate; geomorphology; overlying rocks and adjoining rocks; hydrogeology; salt deposit Gorleben. (4) Probable future geological developments at the site Gorleben: supraregional developments with effects on the site Gorleben; glacial period developments; developments of the geomorphology, overlying and adjoining rocks; future developments of the hydrological systems at the site Gorleben; future saliniferous specific developments of the salt deposit Gorleben. (5) Commentary on the unlikely or excludable developments of the site Gorleben.

  3. A qualitative exploration of the perceptions and information needs of public health inspectors responsible for food safety

    Directory of Open Access Journals (Sweden)

    Sargeant Jan M

    2010-06-01

    Full Text Available Abstract Background In Ontario, local public health inspectors play an important frontline role in protecting the public from foodborne illness. This study was an in-depth exploration of public health inspectors' perceptions of the key food safety issues in public health, and their opinions and needs with regards to food safety information resources. Methods Four focus group discussions were conducted with public health inspectors from the Central West region of Ontario, Canada during June and July, 2008. A questioning route was used to standardize qualitative data collection. Audio recordings of sessions were transcribed verbatim and data-driven content analysis was performed. Results A total of 23 public health inspectors participated in four focus group discussions. Five themes emerged as key food safety issues: time-temperature abuse, inadequate handwashing, cross-contamination, the lack of food safety knowledge by food handlers and food premise operators, and the lack of food safety information and knowledge about specialty foods (i.e., foods from different cultures. In general, participants reported confidence with their current knowledge of food safety issues and foodborne pathogens. Participants highlighted the need for a central source for food safety information, access to up-to-date food safety information, resources in different languages, and additional food safety information on specialty foods. Conclusions The information gathered from these focus groups can provide a basis for the development of resources that will meet the specific needs of public health inspectors involved in protecting and promoting food safety.

  4. Preliminary construction of a service provider--informed domestic violence research agenda.

    Science.gov (United States)

    Murray, Christine E; Welch, Metoka L

    2010-12-01

    This article presents the results of a statewide survey of domestic violence (DV) service providers that focused on the needs, background characteristics, and opinions of service providers related to research. The survey included an examination of service providers' motivation for working in the field, research background and training, and perceptions of research as well as the topics they believe are important for researchers to study, the resources they consult to learn about DV, and their suggestions to help researchers learn more about the nature of their work. The results are integrated into a preliminary agenda for future DV research that accounts for the needs and insight of service providers.

  5. Risk-Informed Safety Margin Characterization (RISMC): Integrated Treatment of Aleatory and Epistemic Uncertainty in Safety Analysis

    International Nuclear Information System (INIS)

    Youngblood, R.W.

    2010-01-01

    The concept of 'margin' has a long history in nuclear licensing and in the codification of good engineering practices. However, some traditional applications of 'margin' have been carried out for surrogate scenarios (such as design basis scenarios), without regard to the actual frequencies of those scenarios, and have been carried out with in a systematically conservative fashion. This means that the effectiveness of the application of the margin concept is determined in part by the original choice of surrogates, and is limited in any case by the degree of conservatism imposed on the evaluation. In the RISMC project, which is part of the Department of Energy's 'Light Water Reactor Sustainability Program' (LWRSP), we are developing a risk-informed characterization of safety margin. Beginning with the traditional discussion of 'margin' in terms of a 'load' (a physical challenge to system or component function) and a 'capacity' (the capability of that system or component to accommodate the challenge), we are developing the capability to characterize probabilistic load and capacity spectra, reflecting both aleatory and epistemic uncertainty in system response. For example, the probabilistic load spectrum will reflect the frequency of challenges of a particular severity. Such a characterization is required if decision-making is to be informed optimally. However, in order to enable the quantification of probabilistic load spectra, existing analysis capability needs to be extended. Accordingly, the INL is working on a next-generation safety analysis capability whose design will allow for much more efficient parameter uncertainty analysis, and will enable a much better integration of reliability-related and phenomenology-related aspects of margin.

  6. Analysis of safety impacts from external flooding using the risk-informed safety margin characterization (RISMC) Toolkit

    International Nuclear Information System (INIS)

    Smith, Curtis L.; Mandelli, Diego; Prescott, Steve

    2015-01-01

    The existing fleet of U.S. nuclear power plants is in the process of extending its lifetime and increasing the power generated from these plants via power uprates. In order to evaluate the impact of these factors on the safety of the plant, the Risk-Informed Safety Margin Characterization (RISMC) project aims to provide insight to decision makers through a series of simulations of the plant dynamics for different initial conditions (e.g., probabilistic analysis and uncertainty quantification). This paper demonstrates how Idaho National Laboratory (INL) researchers use the RISMC Toolkit to investigate complex nuclear plant phenomena using RAVEN and RELAP-7. The analysis focused on a highly relevant topic currently facing some nuclear power plants – specifically flooding issues. This research and development looked at challenges to a hypothetical pressurized water reactor, including: (1) a potential loss of off-site power followed by the possible loss of all diesel generators (i.e., a station black-out event), (2) earthquake induced station-blackout, and (3) a potential earthquake induced tsunami flood. The analysis is performed by using a set of codes: a thermal-hydraulic code (RELAP-7), a flooding simulation tool (NEUTRINO) and a stochastic analysis tool (RAVEN) – these are currently under development at INL. Using RAVEN, we were able to perform multiple RELAP-7 simulation runs by changing specific parts of the model in order to reflect specific aspects of different scenarios, including both the failure and recovery of critical components. The simulation employed traditional statistical tools (such as Monte-Carlo sampling) and more advanced machine-learning based algorithms to perform uncertainty quantification in order to understand changes in system performance and limitations as a consequence of power uprate. Qualitative and quantitative results obtained gave a detailed picture of the issues associated with potential accident scenarios. These types of

  7. A comparative review of patient safety initiatives for national health information technology

    DEFF Research Database (Denmark)

    Magrabi, Farah; Aarts, Jos; Nøhr, Christian

    2013-01-01

    OBJECTIVE: To collect and critically review patient safety initiatives for health information technology (HIT). METHOD: Publicly promulgated set of advisories, recommendations, guidelines, or standards potentially addressing safe system design, build, implementation or use were identified...... by searching the websites of regional and national agencies and programmes in a non-exhaustive set of exemplar countries including England, Denmark, the Netherlands, the USA, Canada and Australia. Initiatives were categorised by type and software systems covered. RESULTS: We found 27 patient safety initiatives...... were aimed at certification in the USA, Canada and Australia. Safety is addressed alongside interoperability in the Australian certification programme but it is not explicitly addressed in the US and Canadian programmes, though conformance with specific functionality, interoperability, security...

  8. Information System Passive Safety at DaimlerChrysler: from vision to reality

    Energy Technology Data Exchange (ETDEWEB)

    Ruoff, H. [DaimlerChrysler AG, Sindelfingen (Germany)

    2001-07-01

    Today, short development times and an extensive model range are key factors when it comes to remaining a leading force in the highly competitive automobile market. Information technology plays a crucial role as an 'enabler' in keeping this competitive edge. It is only possible to make full use of existing potential by using 'state-of-the-art' information technology. In particular, this involves making knowledge that is distributed in various systems and 'heads' available quickly and transparently anytime and anywhere. The improved re-use of acquired expertise, efficient information searches, and standardized and seamless applications lead to a high level of performance. This often involves the transformation of a company culture from 'information hider' to 'information provider'. The vision of converting a gradually created, complex range of systems into a seamless sequence of distributed working processes with numerous participants is becoming reality in the Passive Safety area in Automobile/Vehicle Development at DaimlerChrysler. The INFOS Passive Safety information system provides all the data and information, which is required for, or results from, the entire crash test process. (orig.)

  9. Memorandum on the use of information technology to improve medication safety.

    Science.gov (United States)

    Ammenwerth, E; Aly, A-F; Bürkle, T; Christ, P; Dormann, H; Friesdorf, W; Haas, C; Haefeli, W E; Jeske, M; Kaltschmidt, J; Menges, K; Möller, H; Neubert, A; Rascher, W; Reichert, H; Schuler, J; Schreier, G; Schulz, S; Seidling, H M; Stühlinger, W; Criegee-Rieck, M

    2014-01-01

    Information technology in health care has a clear potential to improve the quality and efficiency of health care, especially in the area of medication processes. On the other hand, existing studies show possible adverse effects on patient safety when IT for medication-related processes is developed, introduced or used inappropriately. To summarize definitions and observations on IT usage in pharmacotherapy and to derive recommendations and future research priorities for decision makers and domain experts. This memorandum was developed in a consensus-based iterative process that included workshops and e-mail discussions among 21 experts coordinated by the Drug Information Systems Working Group of the German Society for Medical Informatics, Biometry and Epidemiology (GMDS). The recommendations address, among other things, a stepwise and comprehensive strategy for IT usage in medication processes, the integration of contextual information for alert generation, the involvement of patients, the semantic integration of information resources, usability and adaptability of IT solutions, and the need for their continuous evaluation. Information technology can help to improve medication safety. However, challenges remain regarding access to information, quality of information, and measurable benefits.

  10. Survivorship Care Plan Information Needs: Perspectives of Safety-Net Breast Cancer Patients.

    Science.gov (United States)

    Burke, Nancy J; Napoles, Tessa M; Banks, Priscilla J; Orenstein, Fern S; Luce, Judith A; Joseph, Galen

    2016-01-01

    Despite the Institute of Medicine's (IOM) 2005 recommendation, few care organizations have instituted standard survivorship care plans (SCPs). Low health literacy and low English proficiency are important factors to consider in SCP development. Our study aimed to identify information needs and survivorship care plan preferences of low literacy, multi-lingual patients to support the transition from oncology to primary care and ongoing learning in survivorship. We conducted focus groups in five languages with African American, Latina, Russian, Filipina, White, and Chinese medically underserved breast cancer patients. Topics explored included the transition to primary care, access to information, knowledge of treatment history, and perspectives on SCPs. Analysis of focus group data identified three themes: 1) the need for information and education on the transition between "active treatment" and "survivorship"; 2) information needed (and often not obtained) from providers; and 3) perspectives on SCP content and delivery. Our data point to the need to develop a process as well as written information for medically underserved breast cancer patients. An SCP document will not replace direct communication with providers about treatment, symptom management and transition, a communication that is missing in participating safety-net patients' experiences of cancer care. Women turned to peer support and community-based organizations in the absence of information from providers. "Clear and effective" communication of survivorship care for safety-net patients requires dedicated staff trained to address wide-ranging information needs and uncertainties.

  11. Readability and Understanding of Informed Consent Among Participants With Low Incomes: A Preliminary Report.

    Science.gov (United States)

    Ittenbach, Richard F; Senft, Elizabeth C; Huang, Guixia; Corsmo, Jeremy J; Sieber, Joan E

    2015-12-01

    With passage and implementation of the Affordable Health Care Act, more vulnerable segments of the U.S. population will now have access to regular health care and increased opportunities to participate in biomedical research. Yet, access to new groups brings with it new responsibilities for investigators, most importantly, reducing burdens for participants. Data collected through this small pilot study suggest several preliminary but potentially important findings when working with adults from low-income populations: First, while all participants read some parts of the consent forms (55%), only a minority reported reading the entire form (45%); second, 73% of participants reported understanding the study very well whereas only 27% reported understanding the study "a little"; third, there was a slight reported advantage of the simplified form over the regular form; however, this difference varied by section. Relatedly, other research has shown a high incidence of persons reading none of the consent form, but signing a statement that they have read and understood the study. Why does this occur? What are we teaching people when we request that they sign a consent form they have chosen not to read? What are the ethical and regulatory implications? Embedded ethics studies such as this one, although pilot and preliminary in nature, offer a number of advantages, such as stimulating additional scientific inquiry as well as challenging established institutional practices. © The Author(s) 2015.

  12. High committee for nuclear safety transparency and information. October 8, 2009 meeting

    International Nuclear Information System (INIS)

    2009-10-01

    The high committee for the nuclear safety transparency and information (HCTISN) is an information, consultation and debate authority devoted to the assessment of the risks linked with nuclear activities and to the analysis of their impact on public health, on the environment and on nuclear safety. Each year, the HCTISN organizes several ordinary meetings in order to analyze some specific topics of the moment. This meeting was organized around 3 main points: 1 - the progress of the different working groups work: elaboration of a communication scale, comparable to the INES scale, for the evaluation of environmental radioactivity, the realisation of a web site for the HCTISN, the question of transparency and secrecy around the maritime transportation of radioactive materials after the visit by the High Committee of two ships from the British INS company; 2 - the management of radioactive wastes with the concept of storage reversibility: political, technical and decisional aspects, position of the National Evaluation Committee for the researches and studies relative to radioactive materials and wastes management (CNE), position of the ANCLI (French national association of local information commissions), debate; 3 - the shortage of radio-physicists in France and the information of populations and patients (declaration of incidents). Some miscellaneous points are reported as well: the first draft of the first annual report of the HCTISN, development of a societal approach for the research programs of the French institute of radiation protection and nuclear safety (IRSN), validation of a collaboration proposal with the ANCLI. (J.S.)

  13. RESI-1 and RESI-2: pPrototypes of an information system on reactor safety

    International Nuclear Information System (INIS)

    Schultheiss, G.F.; Eglin, W.; Katz, F.W.; Krings, T.; Pee, A.; Schlechtendahl, E.G.

    1975-04-01

    To demonstrate by practical experience the feasibility of the information system elaborated in the 'Study of an Information System on Reactor Safety RESI' (KFK 1900), the prototype systems RESI-1 and RESI-2 were developed and tested in operation. The two systems have been considerably reduced both in extent and contents as compared to the information system described in the study. The RESI-1 prototype system is a paper version established for verification of all the individual functions before passing over to the computer-aided interactive version RESI-2. RESI-2 is based on the GOLEM system of Siemens. Both protoype systems have proved that the essential features: 1) documentation, 2) formulation of and answering to safety questions, which are relevant with respect to particular licensing cases, 3) formulation of safety questions related to individual reactor types can be managed satisfactorily. All the functions of information retrieval have been tested carefully over several months. Particularities of project development and of the methods elaborated are described in detail and presented in this report. (orig.) [de

  14. Leader humility and team creativity: The role of team information sharing, psychological safety, and power distance.

    Science.gov (United States)

    Hu, Jia; Erdogan, Berrin; Jiang, Kaifeng; Bauer, Talya N; Liu, Songbo

    2018-03-01

    In this study, we identify leader humility, characterized by being open to admitting one's limitations, shortcomings, and mistakes, and showing appreciation and giving credit to followers, as a critical leader characteristic relevant for team creativity. Integrating the literatures on creativity and leadership, we explore the relationship between leader humility and team creativity, treating team psychological safety and team information sharing as mediators. Further, we hypothesize and examine team power distance as a moderator of the relationship. We tested our hypotheses using data gathered from 72 work teams and 354 individual members from 11 information and technology firms in China using a multiple-source, time-lagged research design. We found that the positive relationship between leader humility and team information sharing was significant and positive only within teams with a low power distance value. In addition, leader humility was negatively related to team psychological safety in teams with a high power distance value, whereas the relationship was positive yet nonsignificant in teams with low power distance. Furthermore, team information sharing and psychological safety were both significantly related to team creativity. We discuss theoretical and practical implications for leadership and work teams. (PsycINFO Database Record (c) 2018 APA, all rights reserved).

  15. Risk-informed regulation: handling uncertainty for a rational management of safety

    International Nuclear Information System (INIS)

    Zio, Enrico

    2008-01-01

    A risk-informed regulatory approach implies that risk insights be used as supplement of deterministic information for safety decision-making purposes. In this view, the use of risk assessment techniques is expected to lead to improved safety and a more rational allocation of the limited resources available. On the other hand, it is recognized that uncertainties affect both the deterministic safety analyses and the risk assessments. In order for the risk-informed decision making process to be effective, the adequate representation and treatment of such uncertainties is mandatory. In this paper, the risk-informed regulatory framework is considered under the focus of the uncertainty issue. Traditionally, probability theory has provided the language and mathematics for the representation and treatment of uncertainty. More recently, other mathematical structures have been introduced. In particular, the Dempster-Shafer theory of evidence is here illustrated as a generalized framework encompassing probability theory and possibility theory. The special case of probability theory is only addressed as term of comparison, given that it is a well known subject. On the other hand, the special case of possibility theory is amply illustrated. An example of the combination of probability and possibility for treating the uncertainty in the parameters of an event tree is illustrated

  16. Information report on the nuclear safety and radiation protection of the Aube storage Centre - 2012

    International Nuclear Information System (INIS)

    2013-07-01

    This report first present the site of the Aube Storage Centre (CSA), its storage areas, its buildings and equipment, describes the water treatment process, proposes some exploitation data for 2012 (deliveries, storage, compacting), and indicates highlights and works performed in 2012. The next part reviews measures related to nuclear safety: recall of safety principles and objectives, technical arrangements to meet safety objectives, inspections by the ASN, quality audits. The third part reviews measures related to safety and radiation protection: principles for radiation protection, staff dosimetry practices and results, personnel safety, works performed in 2012. The fourth part addresses incidents and accidents (none occurred in 2012) and other minor events classified according to the INES scale. The fifth part addresses the control of the environment and the releases by the centre: measurement locations, measurement results (in the atmosphere, in rivers, in underground waters, radiological control, control of ecosystems, assessment of the radiological impact), physical-chemical control of a local river, actions undertaken for the protection of the environment, highlights for 2012. The next chapter addresses the management of the various wastes produced by the Centre (radioactive wastes, conventional wastes) and the last part reports actions regarding information and transparency. Recommendations of the CHSCT are reported

  17. Risk-informed approach for safety, safeguards, and security (3S) by design

    International Nuclear Information System (INIS)

    Suzuki, Mitsutoshi; Burr, Tom; Howell, John

    2011-01-01

    Over several decades the nuclear energy society worldwide has developed safety assessment methodology based on probabilistic risk analysis for incorporating its benefit into design and accident prevention for nuclear reactors. Although safeguards and security communities have different histories and technical aspects compared to safety, risk assessment as a supplement to their current requirements could be developed to promote synergism between Safety, Safeguards, and Security (3S) and to install effective countermeasures in the design of complex nuclear fuel cycle facilities. Since the 3S initiative was raised by G8 countries at Hokkaido Toyako-Summit in 2008, one approach to developing synergism in a 3S By Design (3SBD) process has been the application of risk-oriented assessment methodology. In the existing regulations of safeguards and security, a risk notion has already been considered for inherent threat and hazard recognition. To integrate existing metrics into a risk-oriented approach, several mathematical methods have already been surveyed, with attention to the scarcity of intentional acts in the case of safeguards and the sparseness of actual event data. A two-dimensional probability distribution composed of measurement error and incidence probabilities has been proposed to formalize inherent difficulties in the International Atomic Energy Agency (IAEA) safeguards criteria. In particular, the incidence probability that is difficult to estimate has been explained using a Markov model and game theory. In this work, a feasibility study of 3SBD is performed for an aqueous reprocessing process, and synergetic countermeasures are presented for preliminary demonstration of 3SBD. Although differences and conflicts between individual 'S' communities exist, the integrated approach would be valuable for optimization and balance between the 3S design features as well as for effective and efficient implementation under existing regulation frameworks. In addition

  18. 75 FR 11988 - Notice of Request for Approval To Collect New Information: Collection of Safety Culture Data

    Science.gov (United States)

    2010-03-12

    ..., information about changes to the safety culture of the affected workplaces will be used as one of several data...: RITA-2008-0002] Notice of Request for Approval To Collect New Information: Collection of Safety Culture.... mail to Federal offices in Washington, DC, we recommend that persons consider an alternative method...

  19. Data Analysis Approaches for the Risk-Informed Safety Margins Characterization Toolkit

    International Nuclear Information System (INIS)

    Mandelli, Diego; Alfonsi, Andrea; Maljovec, Daniel P.; Parisi, Carlo; Cogliati, Joshua J.; Talbot, Paul W.; Smith, Curtis L.; Rabiti, Cristian; Picoco, Claudia

    2016-01-01

    In the past decades, several numerical simulation codes have been employed to simulate accident dynamics (e.g., RELAP5-3D, RELAP-7, MELCOR, MAAP). In order to evaluate the impact of uncertainties into accident dynamics, several stochastic methodologies have been coupled with these codes. These stochastic methods range from classical Monte-Carlo and Latin Hypercube sampling to stochastic polynomial methods. Similar approaches have been introduced into the risk and safety community where stochastic methods (such as RAVEN, ADAPT, MCDET, ADS) have been coupled with safety analysis codes in order to evaluate the safety impact of timing and sequencing of events. These approaches are usually called Dynamic PRA or simulation-based PRA methods. These uncertainties and safety methods usually generate a large number of simulation runs (database storage may be on the order of gigabytes or higher). The scope of this paper is to present a broad overview of methods and algorithms that can be used to analyze and extract information from large data sets containing time dependent data. In this context, ''extracting information'' means constructing input-output correlations, finding commonalities, and identifying outliers. Some of the algorithms presented here have been developed or are under development within the RAVEN statistical framework.

  20. Attitudes of the Japanese public and doctors towards use of archived information and samples without informed consent: Preliminary findings based on focus group interviews

    Directory of Open Access Journals (Sweden)

    Fukuhara Shunichi

    2002-01-01

    Full Text Available Abstract Background The purpose of this study is to explore laypersons' attitudes toward the use of archived (existing materials such as medical records and biological samples and to compare them with the attitudes of physicians who are involved in medical research. Methods Three focus group interviews were conducted, in which seven Japanese male members of the general public, seven female members of the general public and seven physicians participated. Results It was revealed that the lay public expressed diverse attitudes towards the use of archived information and samples without informed consent. Protecting a subject's privacy, maintaining confidentiality, and communicating the outcomes of studies to research subjects were regarded as essential preconditions if researchers were to have access to archived information and samples used for research without the specific informed consent of the subjects who provided the material. Although participating physicians thought that some kind of prior permission from subjects was desirable, they pointed out the difficulties involved in obtaining individual informed consent in each case. Conclusions The present preliminary study indicates that the lay public and medical professionals may have different attitudes towards the use of archived information and samples without specific informed consent. This hypothesis, however, is derived from our focus groups interviews, and requires validation through research using a larger sample.

  1. A Preliminary Procedure for Teaching Children with Autism to Mand for Social Information.

    Science.gov (United States)

    Shillingsburg, M Alice; Frampton, Sarah E; Wymer, Sarah C; Bartlett, Brittany

    2018-03-01

    We used procedures established within the mands for information literature to teach two children with autism to mand for social information. Establishing operation trials were alternated with abolishing operation trials to verify the function of the responses as mands. Use of the acquired information was evaluated by examining responding to questions about their social partner. Both participants acquired mands for social information and showed generalization to novel social partners.

  2. Public information and education on radiation safety and protection in Indonesia

    Energy Technology Data Exchange (ETDEWEB)

    Djaloeis, Azhar [National Atomic Energy Agency, Jalan KH Abdul Rohim, Mampang Prapatan, Jakarta (Indonesia)

    1999-09-01

    This paper presents a brief overview of public information and education concerning nuclear science and technology in general and radiation safety and protection in particular in Indonesia from the perspective of promoting the development and utilization of nuclear science and technology in the country. The role of nuclear science and technology in Indonesia is first introduced, followed by an overview of the nuclear activities in the country. Basic considerations, major objectives of the public information and education program on radiation safety and protection as well as basic and operational strategies to achieve those objectives are then presented. Major programs including highlights of the past and present activities as well as prospect on future course of actions are discussed. (author)

  3. Information and Communication Technologies for the Safety and Security of Fish and Fishery Products

    Directory of Open Access Journals (Sweden)

    Liliana Mihaela MOGA

    2017-06-01

    Full Text Available The food industry is becoming more customer-oriented and needs faster response times to deal with food scandals and incidents. Good traceability systems help to minimize the production and distribution of unsafe or poor quality products, thereby minimizing the potential for bad publicity, liability, and recalls. The current food labelling systems cannot guarantee that the food is authentic, good quality and safe. Therefore, traceability is applied as a tool to assist in the assurance of food safety and quality as well as to achieve consumer confidence. This paper presents comprehensive information about traceability systems and the evolution concerning the actors involved and the information about safety and quality in the food supply chain administrated within the systems. Some inventive factors, which influence the traceability systems adoption, are underlined.

  4. Public information and education on radiation safety and protection in Indonesia

    International Nuclear Information System (INIS)

    Djaloeis, Azhar

    1999-01-01

    This paper presents a brief overview of public information and education concerning nuclear science and technology in general and radiation safety and protection in particular in Indonesia from the perspective of promoting the development and utilization of nuclear science and technology in the country. The role of nuclear science and technology in Indonesia is first introduced, followed by an overview of the nuclear activities in the country. Basic considerations, major objectives of the public information and education program on radiation safety and protection as well as basic and operational strategies to achieve those objectives are then presented. Major programs including highlights of the past and present activities as well as prospect on future course of actions are discussed. (author)

  5. A Preliminary Comparison of Student and Professional Motivations for Choosing Information Systems

    Science.gov (United States)

    Brooks, Nita; Korzaan, Melinda; Ceccucci, Wendy

    2014-01-01

    Demand for qualified information systems professionals continues to rise. Additionally, over the past decade, enrollment in information systems-related educational programs has declined. In order to understand why and to better understand how to position information systems undergraduate programs to recruit and retain students, this study provides…

  6. Ensuring Adequate Health and Safety Information for Decision Makers during Large-Scale Chemical Releases

    Science.gov (United States)

    Petropoulos, Z.; Clavin, C.; Zuckerman, B.

    2015-12-01

    The 2014 4-Methylcyclohexanemethanol (MCHM) spill in the Elk River of West Virginia highlighted existing gaps in emergency planning for, and response to, large-scale chemical releases in the United States. The Emergency Planning and Community Right-to-Know Act requires that facilities with hazardous substances provide Material Safety Data Sheets (MSDSs), which contain health and safety information on the hazardous substances. The MSDS produced by Eastman Chemical Company, the manufacturer of MCHM, listed "no data available" for various human toxicity subcategories, such as reproductive toxicity and carcinogenicity. As a result of incomplete toxicity data, the public and media received conflicting messages on the safety of the contaminated water from government officials, industry, and the public health community. Two days after the governor lifted the ban on water use, the health department partially retracted the ban by warning pregnant women to continue avoiding the contaminated water, which the Centers for Disease Control and Prevention deemed safe three weeks later. The response in West Virginia represents a failure in risk communication and calls to question if government officials have sufficient information to support evidence-based decisions during future incidents. Research capabilities, like the National Science Foundation RAPID funding, can provide a solution to some of the data gaps, such as information on environmental fate in the case of the MCHM spill. In order to inform policy discussions on this issue, a methodology for assessing the outcomes of RAPID and similar National Institutes of Health grants in the context of emergency response is employed to examine the efficacy of research-based capabilities in enhancing public health decision making capacity. The results of this assessment highlight potential roles rapid scientific research can fill in ensuring adequate health and safety data is readily available for decision makers during large

  7. Analysis of doses reported to the Health and Safety Executive's Central Index of Dose Information

    International Nuclear Information System (INIS)

    1993-01-01

    This publication analyses the occupational exposure summary information reported to the UK Health and Safety Executive for the years 1986-91. In particular, it considers evidence pointing to the relative success of employers in restricting occupational exposure to ionising radiation over this period. Exposure in the nuclear industry, industrial radiography, non-coal miners underground, medicine, dentistry and the transport sector is discussed. (UK)

  8. Risk informed approach and its application in Daya Bay NPP operation safety management

    International Nuclear Information System (INIS)

    He Yu; Zhang Jinlong; Bao Yukun

    2004-01-01

    The paper presents a systematic risk assessment approach based on probabilistic theory, and discusses its significance and application process in safety management. Risk informed approach that uses deterministic engineering principles and probabilistic methods is the appropriate approach to decision making at nuclear power plants. The paper also studies an actual case taken place at Daya Bay Nuclear Power Station using PSA approach to equipment maintenance. (authors)

  9. The use of information technology to enhance patient safety and nursing efficiency.

    Science.gov (United States)

    Lee, Tso-Ying; Sun, Gi-Tseng; Kou, Li-Tseng; Yeh, Mei-Ling

    2017-10-23

    Issues in patient safety and nursing efficiency have long been of concern. Advancing the role of nursing informatics is seen as the best way to address this. The aim of this study was to determine if the use, outcomes and satisfaction with a nursing information system (NIS) improved patient safety and the quality of nursing care in a hospital in Taiwan. This study adopts a quasi-experimental design. Nurses and patients were surveyed by questionnaire and data retrieval before and after the implementation of NIS in terms of blood drawing, nursing process, drug administration, bar code scanning, shift handover, and information and communication integration. Physiologic values were easier to read and interpret; it took less time to complete electronic records (3.7 vs. 9.1 min); the number of errors in drug administration was reduced (0.08% vs. 0.39%); bar codes reduced the number of errors in blood drawing (0 vs. 10) and transportation of specimens (0 vs. 0.42%); satisfaction with electronic shift handover increased significantly; there was a reduction in nursing turnover (14.9% vs. 16%); patient satisfaction increased significantly (3.46 vs. 3.34). Introduction of NIS improved patient safety and nursing efficiency and increased nurse and patient satisfaction. Medical organizations must continually improve the nursing information system if they are to provide patients with high quality service in a competitive environment.

  10. NASA Aviation Safety Program Weather Accident Prevention/weather Information Communications (WINCOMM)

    Science.gov (United States)

    Feinberg, Arthur; Tauss, James; Chomos, Gerald (Technical Monitor)

    2002-01-01

    Weather is a contributing factor in approximately 25-30 percent of general aviation accidents. The lack of timely, accurate and usable weather information to the general aviation pilot in the cockpit to enhance pilot situational awareness and improve pilot judgment remains a major impediment to improving aviation safety. NASA Glenn Research Center commissioned this 120 day weather datalink market survey to assess the technologies, infrastructure, products, and services of commercial avionics systems being marketed to the general aviation community to address these longstanding safety concerns. A market survey of companies providing or proposing to provide graphical weather information to the general aviation cockpit was conducted. Fifteen commercial companies were surveyed. These systems are characterized and evaluated in this report by availability, end-user pricing/cost, system constraints/limits and technical specifications. An analysis of market survey results and an evaluation of product offerings were made. In addition, recommendations to NASA for additional research and technology development investment have been made as a result of this survey to accelerate deployment of cockpit weather information systems for enhancing aviation safety.

  11. Advice on drug safety in pregnancy: are there differences between commonly used sources of information?

    Science.gov (United States)

    Frost Widnes, Sofia K; Schjøtt, Jan

    2008-01-01

    Safety regarding use in pregnancy is not established for many drugs. Inconsistencies between sources providing drug information can give rise to confusion with possible therapeutic consequences. Therefore, it is important to measure clinically important differences between drug information sources. The objective of this study was to compare two easily accessible Norwegian sources providing advice on drug safety in pregnancy - the product monographs in the Felleskatalog (FK), published by the pharmaceutical companies, and the five regional Drug Information Centres (DICs) in Norway - in addition to assessing the frequency of questions regarding drug safety in pregnancy made to the DICs according to the Anatomical Therapeutic Chemical (ATC) classification system. Advice on drug use in pregnancy provided by the DICs in 2003 and 2005 were compared with advice in the product monographs for the respective drugs in the FK. Comparison of advice was based on categorization to one of four categories: can be used, benefit-risk assessment, should not be used, or no available information. A total of 443 drug advice were categorized. Seven out of ten of drugs frequently enquired about, according to the ATC system, were drugs acting on the nervous system (group N). For 208 (47%) of the drugs, advice differed between the DICs and FK. Advice from the FK was significantly (p drugs that were newly introduced and those that had been on the market for a longer time, advice regarding use of drugs in the first trimester and advice regarding use of drugs in the second or third trimester, or between advice provided during 2003 and during 2005. The results of this study show considerable differences between two Norwegian sources providing advice on the use of drugs in pregnancy. Based on the knowledge that healthcare providers choose sources of information in a random manner, our results may be of clinical importance. We believe that the problem with heterogeneous drug information on this

  12. The Decision of Information Safety Problems at Processing of the Biometric Personal Data

    Directory of Open Access Journals (Sweden)

    Y. G. Gorshkov

    2010-03-01

    Full Text Available The requirements imposed on transfer by the personal biometric information in systems and communication networks according to Federal Law № 152 “Personal data” are defined. Lacks of used decisions protection of such biometric data, as the test speech information, including parameters of a speech path, and also acoustic signals of tones and noise of heart of the person on an example of telemedicine systems construction with the using of a network telephone channels general using and wireless networks Wi-Fi are considered. Directions of works are formulated on safety of the personal biometric data transferred in telecommunication systems.

  13. Assessment of shaft safety and management system of controlling engineering information

    Energy Technology Data Exchange (ETDEWEB)

    Liu Rui-xin; Xu Yan-chun [Yanzhou Mining Group Ltd., Zoucheng (China)

    2008-02-15

    Evaluating shaft safety and establishing a system for controlling engineering information is very important because more than 90 shafts in thick alluvial areas suddenly have shaft wall fracturing or breaking problems and there are more than a few hundred shafts of similar geologic conditions. Taking shaft control in the Yangzhou Coal Mining Group as an example, an assessment and management system and related software were established. This system includes basic information of the mine, measurement results and analysis, and functions of empirical and theoretical forecasting and finite element analysis, which are confirmed to be very effective for guiding shaft well control engineering in practice. 8 refs., 3 figs., 2 tabs.

  14. What defines 'enough' information? How policy workers make judgements and decisions during information seeking: preliminary results from an exploratory study

    Directory of Open Access Journals (Sweden)

    J.M. Berryman

    2006-01-01

    Full Text Available Introduction. Reports findings from research in progress investigating judgment and decision making during information seeking in the workplace, in particular, the assessment of enough information. Characteristics of this judgment and the role of context in shaping it are framed against theories of human judgment and decision making. Method. Thirty-three semi-structured interviews were conducted with public sector policy workers in Australia. Two interviews were carried out, the first with individual participants and the second, a joint interview with two participants. Interviews were taped and transcribed and inductive data analysis carried out. Findings. Findings discussed in this paper focus on contextual factors that frame policy workers' judgment and decision making while information seeking, factors including ill-structured problems, shifting goals, time stress and action-feedback loops. Also revealed was the importance of developing a framework, against which the judgment of enough information can be made, and the fluid and iterative nature of these judgments. Conclusion. The contextual factors reported show similarities with those identified by naturalistic decision making researchers, suggesting this new field of decision theory has much to offer researchers into information seeking in context.

  15. Preliminary experiments using subjective logic for the polyrepresentation of information needs

    DEFF Research Database (Denmark)

    Lioma, Christina; Larsen, Birger; Ingwersen, Peter

    2012-01-01

    According to the principle of polyrepresentation, retrieval accuracy may improve through the combination of multiple and diverse information object representations about e.g. the context of the user, the information sought, or the retrieval system [9, 10]. Recently, the principle of polyrep......) independence or (b) dependence between the information objects that are combined. We focus on the polyrepresentation of different types of context relating to user information needs (i.e. work task, user background knowledge, ideal answer) and show that the subjective logic model can predict their optimal...

  16. Decree No 87-137 of 2 March 1987 concerning the High Council for nuclear safety and information

    International Nuclear Information System (INIS)

    1987-01-01

    This Decree amends the Decree of 13th March 1973 setting up a High Council for Nuclear Safety. Its purpose is to widen the terms of reference of the High Council for Nuclear Safety. In addition to its responsibilities as regards the safety of nuclear installations, it is now competent in the field of information. The Council is now charged with informing the media as well as the public not only on questions of safety proper but also on incidents and accidents occurring in nuclear installations. (NEA) [fr

  17. Internet access and online cancer information seeking among Latino immigrants from safety net clinics.

    Science.gov (United States)

    Selsky, Claire; Luta, George; Noone, Anne-Michelle; Huerta, Elmer E; Mandelblatt, Jeanne S

    2013-01-01

    Internet use is widespread, but little is known about Internet use for cancer information among Latinos, especially those who rely on safety net clinics. The authors investigated access to and intended use of the Internet for cancer information among low income, immigrant Latinos predominately from Central and South America. A cross-sectional study of 1,273 Latinos 21 years and older attending safety net clinics or health fairs was conducted from June 2007 to November 2008. The authors used logistic regression models to evaluate associations of age, acculturation, psychosocial factors and other covariates with Internet access and intended use of the Internet for cancer information among those with access. Of the sample, 44% reported Internet access. Higher information self-efficacy and greater trust in the Internet were independently associated with Internet access (p = .05 and p Internet use for cancer information, considering covariates. In addition, those with high (vs. low) perceived risk of cancer (OR = 1.76; 95% CI [1.14, 2.73]; p = .01) and higher levels of trust in online health information (OR = 1.47 per one-point increase; 95% [CI 1.19, 1.82]; p = .0004) were more likely to intend to seek cancer information online. These findings that Internet access is fairly high in the immigrant Latino population and that the Internet is a trusted source of cancer information suggest that the Internet may be a channel for cancer control interventions.

  18. The Origin of Value Through Information Networks : A Preliminary Framework from an Evolutionary Holonic Perspective

    NARCIS (Netherlands)

    Madureira, A.; Bakena, N.; Bouwman, H.

    2010-01-01

    The worldwide extraordinary level of interest in digital information networks deployment among nations is due to the strong perception that they bring economic, social and environmental value. Our literature review on studies aiming at clarifying the value of information networks, led us to conclude

  19. Data Analysis Approaches for the Risk-Informed Safety Margins Characterization Toolkit

    Energy Technology Data Exchange (ETDEWEB)

    Mandelli, Diego [Idaho National Lab. (INL), Idaho Falls, ID (United States); Alfonsi, Andrea [Idaho National Lab. (INL), Idaho Falls, ID (United States); Maljovec, Daniel P. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Parisi, Carlo [Idaho National Lab. (INL), Idaho Falls, ID (United States); Cogliati, Joshua J. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Talbot, Paul W. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Smith, Curtis L. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Rabiti, Cristian [Idaho National Lab. (INL), Idaho Falls, ID (United States); Picoco, Claudia [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2016-09-01

    In the past decades, several numerical simulation codes have been employed to simulate accident dynamics (e.g., RELAP5-3D, RELAP-7, MELCOR, MAAP). In order to evaluate the impact of uncertainties into accident dynamics, several stochastic methodologies have been coupled with these codes. These stochastic methods range from classical Monte-Carlo and Latin Hypercube sampling to stochastic polynomial methods. Similar approaches have been introduced into the risk and safety community where stochastic methods (such as RAVEN, ADAPT, MCDET, ADS) have been coupled with safety analysis codes in order to evaluate the safety impact of timing and sequencing of events. These approaches are usually called Dynamic PRA or simulation-based PRA methods. These uncertainties and safety methods usually generate a large number of simulation runs (database storage may be on the order of gigabytes or higher). The scope of this paper is to present a broad overview of methods and algorithms that can be used to analyze and extract information from large data sets containing time dependent data. In this context, “extracting information” means constructing input-output correlations, finding commonalities, and identifying outliers. Some of the algorithms presented here have been developed or are under development within the RAVEN statistical framework.

  20. Drug safety in pregnancy: utopia or achievable prospect? Risk information, risk research and advocacy in Teratology Information Services.

    Science.gov (United States)

    Schaefer, Christof

    2011-03-01

    Even though from preclinical testing to drug risk labeling, the situation with drugs in pregnancy has improved substantially since the thalidomide scandal, there is still an increasing need to provide healthcare professionals and patients with updated individualized risk information for clinical decision making. For the majority of drugs, clinical experience is still insufficient with respect to their safety in pregnancy. There is often uncertainty in how to interpret the available scientific data. Based on 20 years of experience with Teratology Information Services (TIS) cooperating in the European Network of Teratology Information Services (ENTIS) methods of risk interpretation, follow-up of exposed pregnancies through the consultation process and their evaluation is discussed. Vitamin K antagonists, isotretinoin and angiotensin (AT) II-receptor-antagonists are presented as examples of misinterpretation of drug risks and subjects of research based on observational clinical data recorded in TIS. As many TIS are poorly funded, advocacy is necessary by establishing contacts with decision makers in health politics and administration, informing them of the high return in terms of health outcomes and cost savings provided by TIS as reference institutions in clinical teratology. © 2011 The Author. Congenital Anomalies © 2011 Japanese Teratology Society.

  1. Father involvement in Mexican-origin families: Preliminary development of a culturally informed measure.

    Science.gov (United States)

    Roubinov, Danielle S; Luecken, Linda J; Gonzales, Nancy A; Crnic, Keith A

    2016-04-01

    An increasing body of research has documented the significant influence of father involvement on children's development and overall well-being. However, extant research has predominately focused on middle-class Caucasian samples with little examination of fathering in ethnic minority and low-income families, particularly during the infancy period. The present study evaluated measures of early father involvement (paternal engagement, accessibility, and responsibility) that were adapted to capture important cultural values relevant to the paternal role in Mexican-origin families. A sample of 180 Mexican-origin mothers (M age = 28.3) and 83 Mexican-origin fathers (M age = 31.5) were interviewed during the perinatal period. Descriptive analyses indicated that Mexican-origin fathers are involved in meaningful levels of direct interaction with their infant. A 2-factor model of paternal responsibility was supported by factor analyses, consisting of a behavioral responsibility factor aligned with previous literature and culturally derived positive machismo factor. Qualities of the romantic relationship, cultural orientation, and maternal employment status were related to indices of father involvement. These preliminary results contribute to understanding of the transition to fatherhood among low-income Mexican-origin men and bring attention to the demographic, social, and cultural contexts in which varying levels of father involvement may emerge. (c) 2016 APA, all rights reserved).

  2. Father involvement in Mexican origin families: Preliminary development of culturally-informed measure

    Science.gov (United States)

    Roubinov, Danielle S.; Luecken, Linda J.; Gonzales, Nancy A.; Crnic, Keith A.

    2015-01-01

    Objectives An increasing body of research has documented the significant influence of father involvement on children’s development and overall well-being. However, extant research has predominately focused on middle-class Caucasian samples with little examination of fathering in ethnic minority and low-income families, particularly during the infancy period. The present study evaluated measures of early father involvement (paternal engagement, accessibility, and responsibility) that were adapted to capture important cultural values relevant to the paternal role in Mexican origin families. Methods A sample of 180 Mexican origin mothers (M age = 28.3) and 83 Mexican origin fathers (M age = 31.5) were interviewed during the perinatal period. Results Descriptive analyses indicated that Mexican origin fathers are involved in meaningful levels of direct interaction with their infant. A two-factor model of paternal responsibility was supported by factor analyses, consisting of a behavioral responsibility factor aligned with previous literature and culturally-derived positive machismo factor. Qualities of the romantic relationship, cultural orientation, and maternal employment status were related to indices of father involvement. Conclusions These preliminary results contribute to understanding of the transition to fatherhood among low-income Mexican origin men and bring attention to the demographic, social, and cultural contexts in which varying levels of father involvement may emerge. PMID:26237543

  3. Trends in Health Information Technology Safety: From Technology-Induced Errors to Current Approaches for Ensuring Technology Safety

    Science.gov (United States)

    2013-01-01

    Objectives Health information technology (HIT) research findings suggested that new healthcare technologies could reduce some types of medical errors while at the same time introducing classes of medical errors (i.e., technology-induced errors). Technology-induced errors have their origins in HIT, and/or HIT contribute to their occurrence. The objective of this paper is to review current trends in the published literature on HIT safety. Methods A review and synthesis of the medical and life sciences literature focusing on the area of technology-induced error was conducted. Results There were four main trends in the literature on technology-induced error. The following areas were addressed in the literature: definitions of technology-induced errors; models, frameworks and evidence for understanding how technology-induced errors occur; a discussion of monitoring; and methods for preventing and learning about technology-induced errors. Conclusions The literature focusing on technology-induced errors continues to grow. Research has focused on the defining what an error is, models and frameworks used to understand these new types of errors, monitoring of such errors and methods that can be used to prevent these errors. More research will be needed to better understand and mitigate these types of errors. PMID:23882411

  4. High committee for nuclear safety transparency and information. December 18, 2008 meeting

    International Nuclear Information System (INIS)

    2008-12-01

    The high committee for the nuclear safety transparency and information (HCTISN) is an information, consultation and debate authority devoted to the assessment of the risks linked with nuclear activities and to the analysis of their impact on public health, on the environment and on nuclear safety. Each year, the HCTISN organizes several ordinary meetings in order to analyze some specific topics of the moment. This meeting was organized around 6 main topics: 1 - a presentation of nuclear medicine by Prof. Devaux, of its domains of application and the respect of radiation protection rules; 2 - the launching of a working group on the transparency/secrecy problem with nuclear activities; 3 - the elaboration of an environmental radioactivity index by the nuclear safety authority (ASN); 4 - the order addressed to the Cruas nuclear facility for the lack of standardized marking and maintenance of pipes used for the transport of explosive fluids; 5 - the consequences of the blocking of 2 fuel assemblies (out of 157) in the Tricastin reactor core; 6 - the flood at the Tricastin site, its origin and consequences. (J.S.)

  5. Nurses' perspectives on the intersection of safety and informed decision making in maternity care.

    Science.gov (United States)

    Jacobson, Carrie H; Zlatnik, Marya G; Kennedy, Holly Powell; Lyndon, Audrey

    2013-01-01

    To explore maternity nurses' perceptions of women's informed decision making during labor and birth to better understand how interdisciplinary communication challenges might affect patient safety. Constructivist grounded theory. Four hospitals in the western United States. Forty-six (46) nurses and physicians practicing in maternity units. Data collection strategies included individual interviews and participant observation. Data were analyzed using the constant comparative method, dimensional analysis, and situational analysis (Charmaz, 2006; Clarke, 2005; Schatzman, 1991). The nurses' central action of holding off harm encompassed three communication strategies: persuading agreement, managing information, and coaching of mothers and physicians. These strategies were executed in a complex, hierarchical context characterized by varied practice patterns and relationships. Nurses' priorities and patient safety goals were sometimes misaligned with those of physicians, resulting in potentially unsafe communication. The communication strategies nurses employed resulted in intended and unintended consequences with safety implications for mothers and providers and had the potential to trap women in the middle of interprofessional conflicts and differences of opinion. © 2013 AWHONN, the Association of Women's Health, Obstetric and Neonatal Nurses.

  6. Do Dutch workers seek and find information on occupational safety and health?

    Science.gov (United States)

    Rhebergen, Martijn D F; Lenderink, Annet F; van Dijk, Frank J H; Hulshof, Carel T J

    2012-03-01

    Currently, little is known about workers' occupational safety and health (OSH) information-seeking behavior. We assessed whether Dutch workers have (OSH) questions, what motivates them to seek information or advice to solve these questions, and whether workers actually find the information they are looking for. A random sample of 888 workers from a large business panel were sent an online questionnaire. In total, 535 workers, likely parallel to the Dutch working population, returned the questionnaire (response rate 60%). In the last year, 380 of the 535 respondents (71%) had at least one OSH question. In total, 159 of the 380 respondents (42%) with an OSH question actively searched for information or advice. In a logistic regression analysis, three factors were identified to influence workers' information seeking: cognitions about personal benefits or costs of solving the question (OR = 2.8, 95% CI: 1.8-4.5), emotions that accompany the question (OR = 1.8, 95% CI: 1.1-3.0), and encouragement by the social environment (OR = 1.8, 95% CI: 1.0-3.0). In total, 50% of the respondents seeking information indicated they could not find (all) the information they sought. The barrier most often mentioned (47%) was the poor applicability of the information. Although most workers have OSH questions, only 40% seek information or advice to answer their questions. Moreover, many OSH questions remain unanswered by common information facilities. This study provides input on how to develop campaigns and new facilities that may induce workers to seek information and that offer more applicable information. Copyright © 2011 Wiley Periodicals, Inc.

  7. High committee for nuclear safety transparency and information. November 20, 2009 meeting of the High Committee

    International Nuclear Information System (INIS)

    2009-11-01

    The high committee for the nuclear safety transparency and information (HCTISN) is an information, consultation and debate authority devoted to the assessment of the risks linked with nuclear activities and to the analysis of their impact on public health, on the environment and on nuclear safety. Each year, the HCTISN organizes several ordinary meetings in order to analyze some specific topics of the moment, and, depending on the events, some extraordinary meetings. This document is the proceedings of an extraordinary meeting about the information and transparency in relation with the management of nuclear materials and wastes at all stages of the fuel cycle. The reason of this meeting is a request from the French Minister of ecology, energy, sustainable development and sea (MEEDDM) after the broadcast of a TV documentary entitled 'wastes: the nuclear industry nightmare' and the publication of a press article affirming that 'our nuclear wastes are hidden in Siberia'. The Minister expressed his wish to have the question of the international trade of nuclear materials examined by the HCTISN. The document is organized as follows: a first part presents the hearings of the general direction of energy and climate (DGEC), of the nuclear safety authority (ASN), of EdF, of Areva, of the CEA, of the senior official for the defense and security of the MEEDDM, of Rosatom company and of Greenpeace organisation. A second part examines the incident which took place in October 2009 at the plutonium technology workshop (ATPu) of Cadarache, where about 22 to 39 kg of plutonium powder were discovered in the gloveboxes of this facility, decommissioned in 2005 and undergoing dismantlement today. This part presents the hearings of the CEA, of AREVA, of the Institute of radiation protection and nuclear safety (IRSN), of the ASN, of the hygiene, safety and labour conditions committee (CHSCT) of Areva and CEA, and of the local information commission (CLI) of Cadarache, in relation with

  8. Knowledge management: Role of the the Radiation Safety Information Computational Center (RSICC)

    Science.gov (United States)

    Valentine, Timothy

    2017-09-01

    The Radiation Safety Information Computational Center (RSICC) at Oak Ridge National Laboratory (ORNL) is an information analysis center that collects, archives, evaluates, synthesizes and distributes information, data and codes that are used in various nuclear technology applications. RSICC retains more than 2,000 software packages that have been provided by code developers from various federal and international agencies. RSICC's customers (scientists, engineers, and students from around the world) obtain access to such computing codes (source and/or executable versions) and processed nuclear data files to promote on-going research, to ensure nuclear and radiological safety, and to advance nuclear technology. The role of such information analysis centers is critical for supporting and sustaining nuclear education and training programs both domestically and internationally, as the majority of RSICC's customers are students attending U.S. universities. Additionally, RSICC operates a secure CLOUD computing system to provide access to sensitive export-controlled modeling and simulation (M&S) tools that support both domestic and international activities. This presentation will provide a general review of RSICC's activities, services, and systems that support knowledge management and education and training in the nuclear field.

  9. The Role of the Radiation Safety Information Computational Center (RSICC) in Knowledge Management

    International Nuclear Information System (INIS)

    Valentine, T.

    2016-01-01

    Full text: The Radiation Safety Information Computational Center (RSICC) is an information analysis center that collects, archives, evaluates, synthesizes and distributes information, data and codes that are used in various nuclear technology applications. RSICC retains more than 2,000 packages that have been provided by contributors from various agencies. RSICC’s customers obtain access to such computing codes (source and/or executable versions) and processed nuclear data files to promote on-going research, to help ensure nuclear and radiological safety, and to advance nuclear technology. The role of such information analysis centers is critical for supporting and sustaining nuclear education and training programmes both domestically and internationally, as the majority of RSICC’s customers are students attending U.S. universities. RSICC also supports and promotes workshops and seminars in nuclear science and technology to further the use and/or development of computational tools and data. Additionally, RSICC operates a secure CLOUD computing system to provide access to sensitive export-controlled modeling and simulation (M&S) tools that support both domestic and international activities. This presentation will provide a general review of RSICC’s activities, services, and systems that support knowledge management and education and training in the nuclear field. (author

  10. a Tool for Crowdsourced Building Information Modeling Through Low-Cost Range Camera: Preliminary Demonstration and Potential

    Science.gov (United States)

    Capocchiano, F.; Ravanelli, R.; Crespi, M.

    2017-11-01

    Within the construction sector, Building Information Models (BIMs) are more and more used thanks to the several benefits that they offer in the design of new buildings and the management of the existing ones. Frequently, however, BIMs are not available for already built constructions, but, at the same time, the range camera technology provides nowadays a cheap, intuitive and effective tool for automatically collecting the 3D geometry of indoor environments. It is thus essential to find new strategies, able to perform the first step of the scan to BIM process, by extracting the geometrical information contained in the 3D models that are so easily collected through the range cameras. In this work, a new algorithm to extract planimetries from the 3D models of rooms acquired by means of a range camera is therefore presented. The algorithm was tested on two rooms, characterized by different shapes and dimensions, whose 3D models were captured with the Occipital Structure SensorTM. The preliminary results are promising: the developed algorithm is able to model effectively the 2D shape of the investigated rooms, with an accuracy level comprised in the range of 5 - 10 cm. It can be potentially used by non-expert users in the first step of the BIM generation, when the building geometry is reconstructed, for collecting crowdsourced indoor information in the frame of BIMs Volunteered Geographic Information (VGI) generation.

  11. A Preliminary Study on the Measures to Assess the Organizational Safety: The Cultural Impact on Human Error Potential

    International Nuclear Information System (INIS)

    Lee, Yong Hee; Lee, Yong Hee

    2011-01-01

    The Fukushima I nuclear accident following the Tohoku earthquake and tsunami on 11 March 2011 occurred after twelve years had passed since the JCO accident which was caused as a result of an error made by JCO employees. These accidents, along with the Chernobyl accident, associated with characteristic problems of various organizations caused severe social and economic disruptions and have had significant environmental and health impact. The cultural problems with human errors occur for various reasons, and different actions are needed to prevent different errors. Unfortunately, much of the research on organization and human error has shown widely various or different results which call for different approaches. In other words, we have to find more practical solutions from various researches for nuclear safety and lead a systematic approach to organizational deficiency causing human error. This paper reviews Hofstede's criteria, IAEA safety culture, safety areas of periodic safety review (PSR), teamwork and performance, and an evaluation of HANARO safety culture to verify the measures used to assess the organizational safety

  12. A Preliminary Study on the Measures to Assess the Organizational Safety: The Cultural Impact on Human Error Potential

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Yong Hee; Lee, Yong Hee [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2011-10-15

    The Fukushima I nuclear accident following the Tohoku earthquake and tsunami on 11 March 2011 occurred after twelve years had passed since the JCO accident which was caused as a result of an error made by JCO employees. These accidents, along with the Chernobyl accident, associated with characteristic problems of various organizations caused severe social and economic disruptions and have had significant environmental and health impact. The cultural problems with human errors occur for various reasons, and different actions are needed to prevent different errors. Unfortunately, much of the research on organization and human error has shown widely various or different results which call for different approaches. In other words, we have to find more practical solutions from various researches for nuclear safety and lead a systematic approach to organizational deficiency causing human error. This paper reviews Hofstede's criteria, IAEA safety culture, safety areas of periodic safety review (PSR), teamwork and performance, and an evaluation of HANARO safety culture to verify the measures used to assess the organizational safety

  13. Obtaining Valid Safety Data for Software Safety Measurement and Process Improvement

    Science.gov (United States)

    Basili, Victor r.; Zelkowitz, Marvin V.; Layman, Lucas; Dangle, Kathleen; Diep, Madeline

    2010-01-01

    We report on a preliminary case study to examine software safety risk in the early design phase of the NASA Constellation spaceflight program. Our goal is to provide NASA quality assurance managers with information regarding the ongoing state of software safety across the program. We examined 154 hazard reports created during the preliminary design phase of three major flight hardware systems within the Constellation program. Our purpose was two-fold: 1) to quantify the relative importance of software with respect to system safety; and 2) to identify potential risks due to incorrect application of the safety process, deficiencies in the safety process, or the lack of a defined process. One early outcome of this work was to show that there are structural deficiencies in collecting valid safety data that make software safety different from hardware safety. In our conclusions we present some of these deficiencies.

  14. Partial nephrectomy online: a preliminary evaluation of the quality of health information on the Internet.

    Science.gov (United States)

    Fast, Angela M; Deibert, Christopher M; Boyer, Celia; Hruby, Gregory W; McKiernan, James M

    2012-12-01

    What's known on the subject? and What does the study add? Patients are highly likely to access the Internet for health information, and studies have reported that inaccurate or low-quality information may alter patients' expectations and negatively impact informed decision-making. In a unique collaboration with the Health On the Internet (HON) Foundation, we evaluated the top 20 search results for the urology search term 'partial nephrectomy,' and identified the highest and lowest scoring criteria to increase awareness of areas of concern and improvement. To further evaluate the quality of information available on the Internet with regard to the management of localized renal cancer, we evaluated websites providing information on 'partial nephrectomy' in conjunction with the Health On the Internet (HON) Foundation. Many patients now utilize the Internet as a resource to provide further information on disease, treatments and outcomes, and health information on the Internet is largely unregulated. Inaccurate information may contribute to unrealistic expectations and dissatisfied patients. A google.com search identified the top 30 websites for the search term 'partial nephrectomy'. The HON Foundation evaluated each website according to the eight principles for Health on the Internet code of conduct (HONcode) certification and reported the overall frequency of certification, as well as individual website compliance with each of the principles. Overall, seven (23.3%) of 30 websites met the requirements of HONcode certification and an additional two (6.7%) websites were under review to maintain their certification based on updating their resources. The remaining 21 (70%) websites did not meet the standards for certification. The lowest performing criteria included proper citation of medical information and a clear distinction of advertising from editorial content. The low rate of HONcode compliance for these websites illustrates the poor quality of information that

  15. Views on chemical safety information and influences on chemical disposal behaviour in the UK

    International Nuclear Information System (INIS)

    Hinks, J.; Bush, J.; Andras, P.; Garratt, J.; Pigott, G.; Kennedy, A.; Pless-Mulloli, T.

    2009-01-01

    This study examined how groups representing four tiers in the chemical supply chain (manufacturers, vendors, workers and consumers) understood safety information, and the factors that influenced disposal behaviour. Data from seven, semi-structured, focus groups was analysed both qualitatively (textual analysis) and quantitatively (network analysis). Such combined analytical methods enabled us to achieve both detailed insights into perceptions and behaviour and an objective understanding of the prevailing opinions that occurred within and between the focus group discussions. We found issues around awareness, trust, access and disposal behaviours differed between groups within the supply chain. Participants from the lower tiers perceived chemical safety information to be largely inaccessible. Labels were the main source of information on chemical risks for the middle and bottom tiers of the supply chain. Almost all of the participants were aware of the St Andrew's Cross and skull and crossbones symbols but few were familiar with the Volatile Organic Compound logo or the fish and tree symbol. Both the network and thematic analysis demonstrated that whilst frequent references to health risks associated with chemicals were made environmental risks were usually only articulated after prompting. It is clear that the issues surrounding public understanding of chemical safety labels are highly complex and this is compounded by inconsistencies in the cognitive profiles of chemical users. Substantially different cognitive profiles are likely to contribute towards communication difficulties between different tiers of the supply chain. Further research is needed to examine the most effective ways of communicating chemical hazards information to the public. The findings demonstrate a need to improve and simplify disposal guidance to members of the public, to raise public awareness of the graphic symbols in the CHIP 3.1, 2005 regulations and to improve access to disposal guidance

  16. Manche storage Centre. Information report on nuclear safety and radiation protection 2015

    International Nuclear Information System (INIS)

    2016-01-01

    After a presentation of the Manche Storage Centre (CSM), the first French center of surface storage of low- and intermediate-level radioactive wastes, of its history, its buildings and activities, of the multi-layer cover, of the water management system (installation, controls, sampling), this report then describes the measures related to nuclear safety, the management of conventional and nuclear wastes produced by the Centre, the other impacts, the control, maintenance and follow-up of installations, the radiation protection and security of the center, the incidents and accidents that occurred at the facility, and the public information and communication actions. Recommendations of the Health and safety Committee (CHSCT) are reported at the end

  17. Aube storage center. Information report on nuclear safety and radiation protection 2015

    International Nuclear Information System (INIS)

    2016-01-01

    The National Radioactive Waste Management Agency (Andra), was established by the December 1991 Waste Act as a public body in charge of the long-term management of all radioactive waste, under the supervision of the Ministry of Ecology, Energy, Sustainable Development and the Sea (formerly the Ministry of Industry and the Ministry of Environment), and the Ministry of Research. The Andra operates two storage centers in the Aube region (France): the center for short-lived low- and intermediate-level wastes, and the center for very-low-level radioactive wastes. This document is the 2015 activity report of the center for short-lived low- and intermediate-level wastes. It presents a review of the activities of the center: presentation of the installations, safety and radiation protection, security, events or incidents, environmental monitoring and effluents, wastes management, public information, recommendations of the Health and safety Committee (CHSCT)

  18. Aube storage center. Information report on nuclear safety and radiation protection 2016

    International Nuclear Information System (INIS)

    2017-01-01

    The National Radioactive Waste Management Agency (Andra), was established by the December 1991 Waste Act as a public body in charge of the long-term management of all radioactive waste, under the supervision of the Ministry of Ecology, Energy, Sustainable Development and the Sea (formerly the Ministry of Industry and the Ministry of Environment), and the Ministry of Research. The Andra operates two storage centers in the Aube region (France): the center for short-lived low- and intermediate-level wastes, and the center for very-low-level radioactive wastes. This document is the 2016 activity report of the center for short-lived low- and intermediate-level wastes. It presents a review of the activities of the center: presentation of the installations, safety and radiation protection, security, events or incidents, environmental monitoring and effluents, wastes management, public information, recommendations of the Health and safety Committee (CHSCT)

  19. Health Information Technology, Patient Safety, and Professional Nursing Care Documentation in Acute Care Settings.

    Science.gov (United States)

    Lavin, Mary Ann; Harper, Ellen; Barr, Nancy

    2015-04-14

    The electronic health record (EHR) is a documentation tool that yields data useful in enhancing patient safety, evaluating care quality, maximizing efficiency, and measuring staffing needs. Although nurses applaud the EHR, they also indicate dissatisfaction with its design and cumbersome electronic processes. This article describes the views of nurses shared by members of the Nursing Practice Committee of the Missouri Nurses Association; it encourages nurses to share their EHR concerns with Information Technology (IT) staff and vendors and to take their place at the table when nursing-related IT decisions are made. In this article, we describe the experiential-reflective reasoning and action model used to understand staff nurses' perspectives, share committee reflections and recommendations for improving both documentation and documentation technology, and conclude by encouraging nurses to develop their documentation and informatics skills. Nursing issues include medication safety, documentation and standards of practice, and EHR efficiency. IT concerns include interoperability, vendors, innovation, nursing voice, education, and collaboration.

  20. High committee for transparency and information on nuclear safety: meeting of April 29, 2010

    International Nuclear Information System (INIS)

    2010-01-01

    The committee members first discuss the report project concerning the State minister's and OPECST (parliamentary office of scientific and technological choices) chairman's submission regarding the transparency of the nuclear fuel cycle. They discuss the project of a portal web site gathering information on French nuclear power plant operations. They comment the 2009 ASN assessment on medical nuclear activities, the implementation of the Cancer Plan (presentation by the minister of public health, statements by the French nuclear safety authority or ASN, the French institute for radiation protection and nuclear safety or IRSN, and by associations of patients). They discuss the presentation by the ASN of a return on experience after the ATPu event and the presentation by the IRSN of technical form on the criticality risk. Other topics are addressed: extensions of storage sites under construction in La Hague, modification of the Grenelle II bill to improve public consultation in some procedures regarding base nuclear installations

  1. Proceedings of the US Nuclear Regulatory Commission nineteenth water reactor safety information meeting

    International Nuclear Information System (INIS)

    Weiss, A.J.

    1992-04-01

    This three-volume report contains 83 papers out of the 108 that were presented at the Nineteenth Water Reactor Safety Information Meeting held at the Bethesda Marriott Hotel, Bethesda, Maryland, during the week of October 28--30, 1991. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included 14 different papers presented by researchers from Canada, Germany, France, Japan, Sweden, Taiwan, and USSR. This document, Volume 3, presents papers on: Structural engineering; Advanced reactor research; Advanced passive reactors; Human factors research; Human factors issues related to advanced passive light water researchers; Thermal Hydraulics; and Earth sciences. The individual papers have been cataloged separately

  2. Proceedings of the US Nuclear Regulatory Commission nineteenth water reactor safety information meeting

    International Nuclear Information System (INIS)

    Weiss, A.J.

    1992-04-01

    This three-volume report contains 83 papers out of the 108 that were presented at the Nineteenth Water Reactor Safety Information Meeting held at the Bethesda Marriott Hotel, Bethesda, Maryland, during the week of October 28--30, 1991. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included 14 different papers presented by researchers from Canada, Germany, France, Japan, Sweden, Taiwan, and USSR. This document, Volume 2, presents papers on: Severe accident research; Severe accident and policy implementation; and Accident management. The individual papers have been cataloged separately

  3. 2004 annual report. Defense, safety, energy, information, health. CEA in the center of big European challenges

    International Nuclear Information System (INIS)

    2005-01-01

    This document is the 2004 annual report of the French atomic energy commission (CEA). It presents the R and D activities of the CEA in three main domains: 1 - defense and safety, maintaining perenniality of nuclear dissuasion and nuclear safety: supplying nuclear weapons to armies, maintaining dissuasion capability with the simulation program, sharing R and D means with the scientific community and the industrial world, designing and maintaining naval nuclear propulsion reactors, cleansing Marcoule and Pierrelatte facilities, monitoring treaties and fighting against proliferation and terrorism; 2 - energy, developing more competitive and cleaner energy sources: nuclear waste management, optimization of industrial nuclear activities, future nuclear systems and new energy technologies, basic research on energy, radiobiology and toxicology; 3 - information and health, valorizing industry thanks to technological research and supplying new tools for health and medical research: micro- and nano-technologies, software technologies, basic research for industrial innovation, nuclear technologies for health and bio-technologies. (J.S.)

  4. Preliminary Information on the Vertebrate Fauna (Animalia: Vertebrata of the NATURA2000 Site “Rice Fields Tsalapitsa” (Bulgaria

    Directory of Open Access Journals (Sweden)

    Ivayla L. Klimentova

    2011-12-01

    Full Text Available The study was carried out by tree visits in different areas of the Natura 2000 site “Rice Fields Tsalapitsa” BG 0002086 (West of Plovdiv city, near village of Tsalapitsa. Our preliminary research showed that in the area vertebrates with high conservation status occurred included in the Bulgarian Bidiversity Act, Appendix II and III, Appendix II of the Bern convention, Natura 2000 species list, the Bonn convention, Appendix II, the Convention of the International Trade of Endangered Species, and the list of the International Union for Conservation of the Nature. This information will help in future preparation of the management plan of the Natura 2000 site and showed the need of studies focused on such areas which will help undertaking adequate measures for their proper way of conservation.

  5. Routing - a preliminary study of the use of modern information and communication technology

    International Nuclear Information System (INIS)

    Stjernman, G.

    1992-01-01

    Communication and data transfer to mobile equipment are in a very active developing face. These technologies might be useful in the work on enhancing the safety of dangerous goods transports. The risk at a certain place, when passed by a transport of dangerous goods, is not the same at every moment. Taking this into account when selecting roads for dangerous goods vehicles so that, for every vehicle, the road most suited at the time in question is selected, should give better results than todays practise. The principles of dynamic routeing of dangerous goods are discussed and the needed and available technologies for implementing dynamic routeing are outlined, as are some other aspects of the implementation. (au)

  6. [Leak on underground pipings. Corrosion in containment spray systems at Bugey NPP (Preliminary Information)

    International Nuclear Information System (INIS)

    1996-01-01

    During last refuelling shutdown at BUGEY 3, this year on the fourteenth of February, the plant operator discovered a wide corrosion on the reactor vessel head and its equipments. The reactor head vessel had recently been replaced by a new one since last reactor shutdown in order to treat the vessel head adaptor safety problem. The cause of this corrosion is a small primary leak on this pipe flange. The leak had been found fortuitously during a field inspection of valves while there was not reactor charge, seven months before the reactor was shutdown for refuelling. At this time the primary leak had been leaktighted by closure of a manual valve and the reactor was restarted up

  7. Risk-informing safety reviews for non-reactor nuclear facilities: an example application

    International Nuclear Information System (INIS)

    Mubayi, V.; Yue, M.; Bari, R.A.; Azarm, M.A.; Mukaddam, W.; Good, G.; Gonzalez, F.

    2013-01-01

    This paper describes a methodology used to model potential accidents in fuel cycle facilities that employ chemical processes to separate and purify nuclear materials. The methodology is illustrated with an example that uses event and fault trees to estimate the frequency of a specific energetic reaction that can occur in nuclear material processing facilities. The methodology used probabilistic risk assessment (PRA)-related tools as well as information about the chemical reaction characteristics, information on plant design and operational features, and generic data about component failure rates and human error rates. The accident frequency estimates for the specific reaction can be useful to help to risk-inform a safety review process and assess compliance with regulatory requirements. (authors)

  8. Risk-Informing Safety Reviews for Non-Reactor Nuclear Facilities

    International Nuclear Information System (INIS)

    Mubayi, V.; Azarm, A.; Yue, M.; Mukaddam, W.; Good, G.; Gonzalez, F.; Bari, R.A.

    2011-01-01

    This paper describes a methodology used to model potential accidents in fuel cycle facilities that employ chemical processes to separate and purify nuclear materials. The methodology is illustrated with an example that uses event and fault trees to estimate the frequency of a specific energetic reaction that can occur in nuclear material processing facilities. The methodology used probabilistic risk assessment (PRA)-related tools as well as information about the chemical reaction characteristics, information on plant design and operational features, and generic data about component failure rates and human error rates. The accident frequency estimates for the specific reaction help to risk-inform the safety review process and assess compliance with regulatory requirements.

  9. Risk-Informing Safety Reviews for Non-Reactor Nuclear Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Mubayi, V.; Azarm, A.; Yue, M.; Mukaddam, W.; Good, G.; Gonzalez, F.; Bari, R.A.

    2011-03-13

    This paper describes a methodology used to model potential accidents in fuel cycle facilities that employ chemical processes to separate and purify nuclear materials. The methodology is illustrated with an example that uses event and fault trees to estimate the frequency of a specific energetic reaction that can occur in nuclear material processing facilities. The methodology used probabilistic risk assessment (PRA)-related tools as well as information about the chemical reaction characteristics, information on plant design and operational features, and generic data about component failure rates and human error rates. The accident frequency estimates for the specific reaction help to risk-inform the safety review process and assess compliance with regulatory requirements.

  10. Determination of relevant neuron-neuron connections for neural prosthetics using time-delayed mutual information: tutorial and preliminary results.

    Science.gov (United States)

    Taghva, Alexander; Song, Dong; Hampson, Robert E; Deadwyler, Sam A; Berger, Theodore W

    2012-12-01

    Identification of functional dependence among neurons is a necessary component in both the rational design of neural prostheses as well as in the characterization of network physiology. The objective of this article is to provide a tutorial for neurosurgeons regarding information theory, specifically time-delayed mutual information, and to compare time-delayed mutual information, an information theoretic quantity based on statistical dependence, with cross-correlation, a commonly used metric for this task in a preliminary analysis of rat hippocampal neurons. Spike trains were recorded from rats performing delayed nonmatch-to-sample task using an array of electrodes surgically implanted into the hippocampus of each hemisphere of the brain. In addition, spike train simulations of positively correlated neurons, negatively correlated neurons, and neurons correlated by nonlinear functions were generated. These were evaluated by time-delayed mutual information (MI) and cross-correlation. Application of time-delayed MI to experimental data indicated the optimal bin size for information capture in the CA3-CA1 system was 40 ms, which may provide some insight into the spatiotemporal nature of encoding in the rat hippocampus. On simulated data, time-delayed MI showed peak values at appropriate time lags in positively correlated, negatively correlated, and complexly correlated data. Cross-correlation showed peak and troughs with positively correlated and negatively correlated data, but failed to capture some higher order correlations. Comparison of time-delayed MI to cross-correlation in identification of functionally dependent neurons indicates that the methods are not equivalent. Time-delayed MI appeared to capture some interactions between CA3-CA1 neurons at physiologically plausible time delays missed by cross-correlation. It should be considered as a method for identification of functional dependence between neurons and may be useful in the development of neural

  11. Preliminary Study for Application of the New Safety Goal related with the Limitation of Cs-137 release

    Energy Technology Data Exchange (ETDEWEB)

    Seo, Mi Ro; Shin, Tae Young [KHNP CRI, Daejeon (Korea, Republic of)

    2016-10-15

    In the New Safety Goal, it is clearly stated that the Probabilistic Safety Assessment (PSA) should be performed with the proper technical appropriateness, the detail, and the scope in accordance with the integrated risk assessment against the accident for the nuclear power plants. This requirement is known to be come from the provision for preventing the long term ground contamination due to the release of radioactive material. However, there were so many concerns that this goal is so severe that the current design, even in the case of the constructing nuclear power plants, cannot meet this criterion. Especially for the operating nuclear power plants, since there were no mitigation facilities against the severe accident at the design stages, the application of this new goal is known to be much severe that the constructing nuclear power plants and it is necessary to develop the alternative methods to strengthen the safety of the operating nuclear power plants. The purpose of this study is to review the new safety goal from the view point of severe accident analysis and probabilistic safety assessment, and to find the appropriate methods in order to meet that goal for the operating nuclear power plants. In order to strengthen the safety for domestic nuclear power plants, all of the domestic operating nuclear power plants are required to prepare the Accident Management Plan within 3 years. Also, this Accident Management Plan should meet the New Safety Goal including the requirement that the sum of the accident frequency that the release of the radioactive nuclide Cs- 137 to the environment exceeds the 100TBq should be less than 1.0E-6/RY. Since the operating nuclear power plants was not designed against the severe accident and they have the limited exclusive mitigation facilities, it is not easy to meet the New Safety Goal. So, it is necessary to develop the alternative methods to meet the New Safety Goal. In this study, the amount of Cs-137 released to the

  12. Preliminary Study for Application of the New Safety Goal related with the Limitation of Cs-137 release

    International Nuclear Information System (INIS)

    Seo, Mi Ro; Shin, Tae Young

    2016-01-01

    In the New Safety Goal, it is clearly stated that the Probabilistic Safety Assessment (PSA) should be performed with the proper technical appropriateness, the detail, and the scope in accordance with the integrated risk assessment against the accident for the nuclear power plants. This requirement is known to be come from the provision for preventing the long term ground contamination due to the release of radioactive material. However, there were so many concerns that this goal is so severe that the current design, even in the case of the constructing nuclear power plants, cannot meet this criterion. Especially for the operating nuclear power plants, since there were no mitigation facilities against the severe accident at the design stages, the application of this new goal is known to be much severe that the constructing nuclear power plants and it is necessary to develop the alternative methods to strengthen the safety of the operating nuclear power plants. The purpose of this study is to review the new safety goal from the view point of severe accident analysis and probabilistic safety assessment, and to find the appropriate methods in order to meet that goal for the operating nuclear power plants. In order to strengthen the safety for domestic nuclear power plants, all of the domestic operating nuclear power plants are required to prepare the Accident Management Plan within 3 years. Also, this Accident Management Plan should meet the New Safety Goal including the requirement that the sum of the accident frequency that the release of the radioactive nuclide Cs- 137 to the environment exceeds the 100TBq should be less than 1.0E-6/RY. Since the operating nuclear power plants was not designed against the severe accident and they have the limited exclusive mitigation facilities, it is not easy to meet the New Safety Goal. So, it is necessary to develop the alternative methods to meet the New Safety Goal. In this study, the amount of Cs-137 released to the

  13. Information need about the safety of the final disposal of nuclear waste. Information receiver's views in Eurajoki, Kuhmo and Aeaenekoski municipalities

    International Nuclear Information System (INIS)

    Hautakangas, H.

    1997-03-01

    The study analyses the public's information need about the safety issues related to the final disposal of spent nuclear fuel generated by the Finnish nuclear power stations. Locals in three municipalities that are studied as possible sites for final disposal were interviewed for the study. Earlier studies made in Finland had indicated that the public's knowledge about safety issues related to the final disposal was almost opposite to the findings of the natural sciences. Also, the public had expressed a wish to receive more information from the safety authority, the Finnish Centre for Radiation and Nuclear Safety (STUK). This study therefore had two basic objectives: To find out what kind of safety information the locals need and what the safety authority's role could be in providing information. The main results show interest and need especially for information concerning the disposal phases taking place on the ground level, such as nuclear waste transportation and encapsulation. Also, the interviews show a clear need and desire for an impartial actor such as STUK in the information and communication process. (author) (107 refs.)

  14. Risk-Informed Safety Assurance and Probabilistic Assessment of Mission-Critical Software-Intensive Systems

    Science.gov (United States)

    Guarro, Sergio B.

    2010-01-01

    This report validates and documents the detailed features and practical application of the framework for software intensive digital systems risk assessment and risk-informed safety assurance presented in the NASA PRA Procedures Guide for Managers and Practitioner. This framework, called herein the "Context-based Software Risk Model" (CSRM), enables the assessment of the contribution of software and software-intensive digital systems to overall system risk, in a manner which is entirely compatible and integrated with the format of a "standard" Probabilistic Risk Assessment (PRA), as currently documented and applied for NASA missions and applications. The CSRM also provides a risk-informed path and criteria for conducting organized and systematic digital system and software testing so that, within this risk-informed paradigm, the achievement of a quantitatively defined level of safety and mission success assurance may be targeted and demonstrated. The framework is based on the concept of context-dependent software risk scenarios and on the modeling of such scenarios via the use of traditional PRA techniques - i.e., event trees and fault trees - in combination with more advanced modeling devices such as the Dynamic Flowgraph Methodology (DFM) or other dynamic logic-modeling representations. The scenarios can be synthesized and quantified in a conditional logic and probabilistic formulation. The application of the CSRM method documented in this report refers to the MiniAERCam system designed and developed by the NASA Johnson Space Center.

  15. Radiological consequence analysis. Report on the work package 10. Preliminary safety analysis for the site Gorleben; Radiologische Konsequenzanalyse. Bericht zum Arbeitspaket 10. Vorlaeufige Sicherheitsanalyse fuer den Standort Gorleben

    Energy Technology Data Exchange (ETDEWEB)

    Larue, Juergen; Baltes, Bruno; Fischer, Heidemarie; Frieling, Gerd; Kock, Ingo; Navarro, Martin; Seher, Holger

    2013-02-15

    Work package 10 of the preliminary safety analysis for the site Gorleben concerns the analysis of release scenarios and the radiological consequences. The report includes the description of the applied methodology, the concept for the mathematical description of scenarios, the variety of scenarios for the radiological consequence analysis with the definition of the reference scenario. The database for the calculation covers geology and hydrology, the final repository concept and the process of the final disposal system. The used models were the one-phase transport model MARINE and the two-phase transport model TOUGH2. The report summarizes the results including an evaluation of the realization of the demonstration concept with respect to solution transport, fluid transport, robustness of the modeling results and analogy discussion to other disposal variants (i.e. borehole disposal and storage of transport or storage casks).

  16. WINRE '92 - 3rd workshop on information management in nuclear safety, radiation protection, and environmental protection

    International Nuclear Information System (INIS)

    Hoepfner, K.A.

    1993-01-01

    The workshop puts much emphasis on the exchange of experience between experts from the West and from the Central and Eastern European countries. The representatives from the various countries and organisations are going to introduce their respective data banks, products, or services. The combination of papers and practical presentations will provide all with a qualified and comprehensive insight into the tried and tested as well as the new information management technologies in the specialist areas of nuclear safety, radiation protection, and environmental protection. Furthermore, it should also contribute to the promotion of the transfer of know-how between experts throughout the whole of Europe. (orig./DG)

  17. Safety of high speed ground transportation systems: X2000 US demonstration vehicle dynamics trials, preliminary test report. Report for October 1992-January 1993

    Energy Technology Data Exchange (ETDEWEB)

    Whitten, B.T.; Kesler, J.K.

    1993-01-01

    The report documents the procedures, events, and results of vehicle dynamic tests carried out on the ASEA-Brown Boveri (ABB) X2000 tilt body trainset in the US between October 1992 and January 1993. These tests, sponsored by Amtrak and supported by the FRA, were conducted to assess the suitability of the X2000 trainset for safe operation at elevated cant deficiencies and speeds in Amtrak's Northeast Corridor under existing track conditions in a revenue service demonstration. The report describes the safety criteria against which the performance of the X2000 test train was examined, the instrumentation used, the test locations, and the track conditions. Preliminary results are presented from tests conducted on Amtrak lines between Philadelphia and Harrisburg, PA, and between Washington DC and New York NY, in which cant deficiencies of 12.5 inches and speeds of 154 mph were reached in a safe and controlled manner. The significance of the results is discussed, and preliminary conclusions and recommendations are presented.

  18. Development of a Preliminary Model for Evaluating Occupational Health and Safety Risk Management Maturity in Small and Medium-Sized Enterprises

    Directory of Open Access Journals (Sweden)

    Bilal Kaassis

    2018-02-01

    Full Text Available Management of occupational health and safety (OHS risks is a crucial component of any business. Numerous investigations have shown that work-related injuries and deaths occur disproportionately in small-to-medium-sized enterprises (SMEs and that this is clearly due to deficient management of OHS risks. The main goal of this work is to develop a base of indicators suitable for evaluating OHS risk management maturity in industrial SMEs. A preliminary model is then proposed for this evaluation, based on a small number of relevant indicators selected from a careful bibliographic review. The work begins with a critical review of the literature and analysis of known concepts, methods, tools and models of measurement of risk analysis maturity in order to extract relevant indicators. The most suitable indicators are then grouped to form the basis of a preliminary model for evaluating OHS risk management maturity in the SME setting. Our findings will help managers of SMEs make sound decisions in their quest to improve the OHS performance of their businesses.

  19. Food safety in the domestic environment: the effect of consumer risk information on human disease risks.

    Science.gov (United States)

    Nauta, Maarten J; Fischer, Arnout R H; van Asselt, Esther D; de Jong, Aarieke E I; Frewer, Lynn J; de Jonge, Rob

    2008-02-01

    The improvement of food safety in the domestic environment requires a transdisciplinary approach, involving interaction between both the social and natural sciences. This approach is applied in a study on risks associated with Campylobacter on broiler meat. First, some web-based information interventions were designed and tested on participant motivation and intentions to cook more safely. Based on these self-reported measures, the intervention supported by the emotion "disgust" was selected as the most promising information intervention. Its effect on microbial cross-contamination was tested by recruiting a set of participants who prepared a salad with chicken breast fillet carrying a known amount of tracer bacteria. The amount of tracer that could be recovered from the salad revealed the transfer and survival of Campylobacter and was used as a measure of hygiene. This was introduced into an existing risk model on Campylobacter in the Netherlands to assess the effect of the information intervention both at the level of exposure and the level of human disease risk. We showed that the information intervention supported by the emotion "disgust" alone had no measurable effect on the health risk. However, when a behavioral cue was embedded within the instruction for the salad preparation, the risk decreased sharply. It is shown that a transdisciplinary approach, involving research on risk perception, microbiology, and risk assessment, is successful in evaluating the efficacy of an information intervention in terms of human health risks. The approach offers a novel tool for science-based risk management in the area of food safety.

  20. Preliminary safety assessments in construction of the pilot industrial facility for final disposal of low and intermediate radioactive waste in the archipelago Novaya Zemlya

    International Nuclear Information System (INIS)

    Lopatin, V.V.; Lobanov, N.F.; Mankin, V.I.; Karamushka, V.P.; Ostroborodov, V.V.

    1999-01-01

    This presentation discusses a preliminary safety evaluation of radioactive waste burial at the experimental plant located on Novaya Zemlya. The issues considered are (1) the main provisions on radioactive waste burial in permafrost rock, (2) mining, geological and geocryological conditions at the experimental works' operating site, (3) the main properties of solid and solidified radioactive wastes, (4) the main parameters of the experimental works, (5) preliminary evaluation of safety. The evaluation includes the main requirements to geocryologic characteristics of the permafrost rock intended for waste burial and analyses the seasonal mining-geological and geocryological conditions in the area of the experimental works. The area is situated within the limits of the southern Novozemelsky anticlinorium composed of the Silurian, Devonian and carboniferous rocks of the Paleozoic group. It is mainly limestone and dolomite, showing in rock sequence the layers, benches and horizons of clay shales, aleurolites, conglomerates and magmatic rocks covered with a thin Quaternary sedimentary mantle on the surface. The area is characterised by a confluent continuous layer no less than 300 m thick, seasonal thawing depth 0.5-2.0 m, annual zero temperature variations 10-15 m by the depth, and mean annual rock temperature of -4.5 - 5.0 C. The plant is an independent enterprise supplied with all the required services for industrial and communal/living purposes. The evaluation studies two possible scenarios for accidents during transport of waste to Novaya Zemlya, and the consequences of damage to the plant caused by the impact of a celestial body/flying object, by a catastrophic earthquake, and the effect of global climate warming in the Arctic area

  1. Information report on nuclear safety and radiation protection of MELOX - Issue 2014

    International Nuclear Information System (INIS)

    2015-06-01

    Published in compliance with the French code of the environment, this report first presents different aspects of the MELOX plant which produces MOX fuel: location and environment, history of basic nuclear installation or INB 151, presentation of the nuclear operator and of the industrial operator, assets of MOX fuel, MOX customers, regulatory framework of the MELOX plant, policy for sustainable development and continuous progress. It addresses the various measures regarding nuclear safety and radiation protection: general overview of nuclear safety in France, presentation of the Areva's nuclear safety Charter, measures adopted in MELOX, review for 2014 and perspectives for 2015. The next part addresses nuclear events: presentation of the INES scale and of the event declaration procedure, review of events declared in 2014 and regarding MELOX. The report gives an overview of activities and measures regarding protection and control of the environment: environmental management, consumption of natural resources, control of effluent releases, measurement of the impact on the environment, waste management, and perspectives for 2015. The last chapter reviews the actions undertaken in the field of transparency and information. Recommendations of the CHSCT are reported

  2. Information report on nuclear safety and radiation protection of the SOMANU site - Issue 2014

    International Nuclear Information System (INIS)

    2015-01-01

    Published in compliance with the French code of the environment, this report first presents different aspects of the SOMANU plant which is dedicated to the maintenance of materials and equipment from nuclear installations: location and environment, history, description of activities, regulatory framework. It describes the various measures regarding nuclear safety and radiation protection: general principles of nuclear safety, organization, presentation of the Areva's nuclear safety Charter, inspections and controls, measures regarding radiation protection. The next part addresses nuclear events which occurred on this site and had to be declared. The report gives an overview of activities and measures regarding the management of releases and the control of the environment. The next part addresses waste management: general considerations on radioactive waste management in France, description and classification of radioactive wastes present in the INB, management of conventional wastes. The management of other impacts is also reported. The last chapter reviews the actions undertaken in the field of transparency and information. Recommendations of the CHSCT are reported

  3. Information report on nuclear safety and radiation protection of MELOX - Issue 2013

    International Nuclear Information System (INIS)

    2014-06-01

    Published in compliance with the French code of the environment, this report first presents different aspects of the MELOX plant which produces MOX fuel: location and environment, history of basic nuclear installation or INB 151, presentation of the nuclear operator and of the industrial operator, assets of MOX fuel, MOX customers, regulatory framework of the MELOX plant, policy for sustainable development and continuous progress. It addresses the various measures regarding nuclear safety and radiation protection: general overview of nuclear safety in France, presentation of the Areva's nuclear safety Charter, measures adopted in MELOX, review for 2013 and perspectives for 2014. The next part addresses nuclear events: presentation of the INES scale and of the event declaration procedure, review of events declared in 2013 and regarding MELOX. The report gives an overview of activities and measures regarding protection and control of the environment: environmental management, consumption of natural resources, control of effluent releases, measurement of the impact on the environment, waste management, and perspectives for 2014. The last chapter reviews the actions undertaken in the field of transparency and information. Recommendations of the CHSCT are reported

  4. Information report on nuclear safety and radiation protection of the Romans site - Issue 2014

    International Nuclear Information System (INIS)

    2015-06-01

    In compliance with the French Code of the Environment, this annual document describes the arrangements regarding nuclear safety and radiation protection, reports incidents and accidents of nuclear safety and radiation protection which must be declared according to this Code and which occurred within the installation, as well as the actions undertaken to limit their development and the consequences for people health for the environment, describes the nature and results of measurements of radioactive and not radioactive releases by the installation in the environment, describes the nature and quantities of radioactive wastes which are warehoused on the installation site as well as measures to limit their volume and their impact on health and on the environment, notably in soils and waters. After a presentation of the AREVA plant located in Romans-sur-Isere which comprises two basic nuclear installations (INB) and where fuel assemblies are manufactured, the different parts of this report address the measures regarding nuclear safety and radiation protection, nuclear events according to the INES scale, the management of releases by the different installations of this site and the control of the environment, the management of radioactive wastes, and the actions undertaken regarding information and transparency. Recommendations of the CHSCT are also reported

  5. Information report on nuclear safety and radiation protection of MELOX - Issue 2012

    International Nuclear Information System (INIS)

    2013-06-01

    Published in compliance with the French code of the environment, this report first presents different aspects of the MELOX plant which produces MOX fuel: location and environment, history of basic nuclear installation or INB 151, presentation of the nuclear operator and of the industrial operator, assets of MOX fuel, MOX customers, regulatory framework of the MELOX plant, policy for sustainable development and continuous progress. It addresses the various measures regarding nuclear safety and radiation protection: general overview of nuclear safety in France, presentation of the Areva's nuclear safety Charter, measures adopted in MELOX, review for 2012 and perspectives for 2013. The next part addresses nuclear events: presentation of the INES scale and of the event declaration procedure, review of events declared in 2012 and regarding MELOX. The report gives an overview of activities and measures regarding protection and control of the environment: environmental management, consumption of natural resources, control of effluent releases, measurement of the impact on the environment, waste management, and perspectives for 2013. The last chapter reviews the actions undertaken in the field of transparency and information. Recommendations of the CHSCT are reported

  6. Information report on nuclear safety and radiation protection of the Romans site - Issue 2012

    International Nuclear Information System (INIS)

    2013-06-01

    In compliance with the French Code of the Environment, this annual document describes the arrangements regarding nuclear safety and radiation protection, reports incidents and accidents of nuclear safety and radiation protection which must be declared according to this Code and which occurred within the installation, as well as the actions undertaken to limit their development and the consequences for people health for the environment, describes the nature and results of measurements of radioactive and not radioactive releases by the installation in the environment, describes the nature and quantities of radioactive wastes which are warehoused on the installation site as well as measures to limit their volume and their impact on health and on the environment, notably in soils and waters. After a presentation of the AREVA plant located in Romans-sur-Isere which comprises two basic nuclear installations (INB) and where fuel assemblies are manufactured, the different parts of this report address the measures regarding nuclear safety and radiation protection, nuclear events according to the INES scale, the management of releases by the different installations of this site and the control of the environment, the management of radioactive wastes, and the actions undertaken regarding information and transparency. Recommendations of the CHSCT are also reported

  7. Information report on nuclear safety and radiation protection of the Romans site - Issue 2013

    International Nuclear Information System (INIS)

    2014-06-01

    In compliance with the French Code of the Environment, this annual document describes the arrangements regarding nuclear safety and radiation protection, reports incidents and accidents of nuclear safety and radiation protection which must be declared according to this Code and which occurred within the installation, as well as the actions undertaken to limit their development and the consequences for people health for the environment, describes the nature and results of measurements of radioactive and not radioactive releases by the installation in the environment, describes the nature and quantities of radioactive wastes which are warehoused on the installation site as well as measures to limit their volume and their impact on health and on the environment, notably in soils and waters. After a presentation of the AREVA plant located in Romans-sur-Isere which comprises two basic nuclear installations (INB) and where fuel assemblies are manufactured, the different parts of this report address the measures regarding nuclear safety and radiation protection, nuclear events according to the INES scale, the management of releases by the different installations of this site and the control of the environment, the management of radioactive wastes, and the actions undertaken regarding information and transparency. Recommendations of the CHSCT are also reported

  8. Latino immigrant day laborer perceptions of occupational safety and health information preferences.

    Science.gov (United States)

    Díaz Fuentes, Claudia M; Martinez Pantoja, Leonardo; Tarver, Meshawn; Geschwind, Sandy A; Lara, Marielena

    2016-06-01

    We address immigrant day laborers' experiences with occupational safety in the construction industry in New Orleans, and opinions about content and method of communication for educational interventions to reduce occupational risks. In 2011, we conducted seven focus groups with 48 Spanish-speaking day laborers (8 women, 40 men, 35 years on average). Focus group results are based on thematic analysis. Most employers did not provide safety equipment, threatened to dismiss workers who asked for it, and did not provide health insurance. Attitudes toward accepting unsafe work conditions varied. Women faced lower pay and hiring difficulties than men. Day laborers preferred audio format over written, and content about consequences from and equipment for different jobs/exposures. Day laborers have common occupational experiences, but differences existed by gender, literacy and sense of control over safety. Day laborer information preferences and use of media needs further studying. Am. J. Ind. Med. 59:476-485, 2016. © 2016 Wiley Periodicals, Inc. © 2016 Wiley Periodicals, Inc.

  9. Information report on nuclear safety and radiation protection of the SOMANU site - Issue 2012

    International Nuclear Information System (INIS)

    2013-06-01

    Published in compliance with the French code of the environment, this report first presents different aspects of the SOMANU plant which is dedicated to the maintenance of materials and equipment from nuclear installations: location and environment, history, description of activities, regulatory framework. It describes the various measures regarding nuclear safety and radiation protection: general principles of nuclear safety, organization, presentation of the Areva's nuclear safety Charter, inspections and controls, measures regarding radiation protection. The next part addresses nuclear events which occurred on this site and had to be declared. The report gives an overview of activities and measures regarding the management of releases and the control of the environment. The next part addresses waste management: generalities on radioactive waste management in France, description and classification of radioactive wastes present in the INB, management of conventional wastes. The management of other impacts is also reported. The last chapter reviews the actions undertaken in the field of transparency and information. Recommendations of the CHSCT are reported

  10. An online network tool for quality information to answer questions about occupational safety and health: usability and applicability

    NARCIS (Netherlands)

    Rhebergen, Martijn D. F.; Hulshof, Carel T. J.; Lenderink, Annet F.; van Dijk, Frank J. H.

    2010-01-01

    Common information facilities do not always provide the quality information needed to answer questions on health or health-related issues, such as Occupational Safety and Health (OSH) matters. Barriers may be the accessibility, quantity and readability of information. Online Question & Answer (Q&A)

  11. An Online Network Tool for Quality Information to Answer Questions about Occupational Safety and Health: Usability and Applicability

    NARCIS (Netherlands)

    Rhebergen, M.D.F.; Hulshof, C.T.J.; Lenderink, A.F.; van Dijk, F.J.H.

    2010-01-01

    ABSTRACT: BACKGROUND: Common information facilities do not always provide the quality information needed to answer questions on health or health-related issues, such as Occupational Safety and Health (OSH) matters. Barriers may be the accessibility, quantity and readability of information. Online

  12. Study of Occupational Safety and Health Audit on Facilities at Ungku Omar College, Universiti Kebangsaan Malaysia (UKM): A Preliminary Analysis

    Science.gov (United States)

    Ariffin, Kadir; Ahmad, Shaharuddin; Aiyub, Kadaruddin; Awang, Azhan; Aziz, Azmi; Mohamad, Lukman Z.; Mamat, Samsu Adabi

    2010-01-01

    Occupational safety and health (OSH) in Universiti Kebangsaan Malaysia (UKM) is being considered as an important program to measure employee and student welfare and well-being. During academic session, apart from attending lectures, laboratory works, tutorial and library search, majority of students spend most of their time in residential…

  13. Joint SKI and SSI review of SKB preliminary safety assessment of repository for long-lived low- and intermediate-level waste. Review report

    International Nuclear Information System (INIS)

    2001-03-01

    SKI and SSI find that SKB's first proper safety assessment of the SFL 3-5 repositories provides a valuable springboard for continued efforts in this field. Even though the safety assessment is relatively limited in scope, it has numerous merits. The specific problems associated with the chosen repository concept for SFL 3-5 are discussed in a generally transparent manner. On the other hand, the authorities consider that SKB have only partly achieved the expressed goal of studying the significance of the current repository design and the choice of site. The greatest deficiency consists in that neither internal disturbances (such as considerable cracking or degradation of concrete structures) nor external disturbances (such as the effects of climate changes and glaciation) have been addressed in a thorough manner. A coherent report justifying the design choice from a long-term safety perspective is, in large part, not found here. SKI and SSI recommend that SKB provide a comparison with other possible SFL 3-5 repository designs. Depending upon, among other factors, what geospheric and biospheric conditions are assumed, SKB have shown that the calculated dose values could be relatively high for certain cases. More realistic assessments would be needed to draw reasonable comparisons between different sites, and to evaluate the importance of different nuclides in different contexts. Our review of SKBs preliminary safety assessment indicates that a great deal of research and development work remains to be done before the level of knowledge in this field is comparable with that associated with the final repository for spent fuel. This is reflected with unanimity in the international expert committee's review, and in the consultants' reviews. SKI and SSI wish to point out in particular the fact that comparison with SFR is of limited value, since the safety associated with SFL 3- 5 must be assessed on a much longer time scale. SKI and SSI find it remarkable that SKB have

  14. Risk-Informed Balancing Of Safety, Nonproliferation, And Economics For The SFR

    International Nuclear Information System (INIS)

    Apostolakis, George; Driscoll, Michael; Golay, Michael; Kadak, Andrew; Todreas, Neil; Aldmir, Tunc; Denning, Richard; Lineberry, Michael

    2011-01-01

    A substantial barrier to the implementation of Sodium-cooled Fast Reactor (SFR) technology in the short term is the perception that they would not be economically competitive with advanced light water reactors. With increased acceptance of risk-informed regulation, the opportunity exists to reduce the costs of a nuclear power plant at the design stage without applying excessive conservatism that is not needed in treating low risk events. In the report, NUREG-1860, the U.S. Nuclear Regulatory Commission describes developmental activities associated with a risk-informed, scenario-based technology neutral framework (TNF) for regulation. It provides quantitative yardsticks against which the adequacy of safety risks can be judged. We extend these concepts to treatment of proliferation risks. The objective of our project is to develop a risk-informed design process for minimizing the cost of electricity generation within constraints of adequate safety and proliferation risks. This report describes the design and use of this design optimization process within the context of reducing the capital cost and levelized cost of electricity production for a small (possibly modular) SFR. Our project provides not only an evaluation of the feasibility of a risk-informed design process but also a practical test of the applicability of the TNF to an actual advanced, non-LWR design. The report provides results of five safety related and one proliferation related case studies of innovative design alternatives. Applied to previously proposed SFR nuclear energy system concepts We find that the TNF provides a feasible initial basis for licensing new reactors. However, it is incomplete. We recommend improvements in terms of requiring acceptance standards for total safety risks, and we propose a framework for regulation of proliferation risks. We also demonstrate methods for evaluation of proliferation risks. We also suggest revisions to scenario-specific safety risk acceptance standards

  15. RISK-INFORMED BALANCING OF SAFETY, NONPROLIFERATION, AND ECONOMICS FOR THE SFR

    Energy Technology Data Exchange (ETDEWEB)

    Apostolakis, George; Driscoll, Michael; Golay, Michael; Kadak, Andrew; Todreas, Neil; Aldmir, Tunc; Denning, Richard; Lineberry, Michael

    2011-10-20

    A substantial barrier to the implementation of Sodium-cooled Fast Reactor (SFR) technology in the short term is the perception that they would not be economically competitive with advanced light water reactors. With increased acceptance of risk-informed regulation, the opportunity exists to reduce the costs of a nuclear power plant at the design stage without applying excessive conservatism that is not needed in treating low risk events. In the report, NUREG-1860, the U.S. Nuclear Regulatory Commission describes developmental activities associated with a risk-informed, scenario-based technology neutral framework (TNF) for regulation. It provides quantitative yardsticks against which the adequacy of safety risks can be judged. We extend these concepts to treatment of proliferation risks. The objective of our project is to develop a risk-informed design process for minimizing the cost of electricity generation within constraints of adequate safety and proliferation risks. This report describes the design and use of this design optimization process within the context of reducing the capital cost and levelized cost of electricity production for a small (possibly modular) SFR. Our project provides not only an evaluation of the feasibility of a risk-informed design process but also a practical test of the applicability of the TNF to an actual advanced, non-LWR design. The report provides results of five safety related and one proliferation related case studies of innovative design alternatives. Applied to previously proposed SFR nuclear energy system concepts We find that the TNF provides a feasible initial basis for licensing new reactors. However, it is incomplete. We recommend improvements in terms of requiring acceptance standards for total safety risks, and we propose a framework for regulation of proliferation risks. We also demonstrate methods for evaluation of proliferation risks. We also suggest revisions to scenario-specific safety risk acceptance standards

  16. Safety of information in electronic equipment influenced by the charged space particles

    Directory of Open Access Journals (Sweden)

    Ksenia Gennad’evna Sizova

    2016-10-01

    Full Text Available A version of the existing evaluation method of electronic equipment to the influence of charged space particles causing single event effects for the purpose of improving the accuracy of calculation in the field of information safety is suggested. On the basis of the existing and modified methods radiation tolerance of real payload spacecraft responsible for the security of transmitted information are defined. The results of comparison are introduced. Significant differences not only in quantitative but also in qualitative character of tolerance indicators are revealed. It is demonstrated that the modified method allows to take into account the functional complexity of the hardware and the application efficiency of the sophisticated single event effects protection tools. To confirm the applicability of the modified method of equipment tolerance evaluation method to the influence of charged space particles causing single event effects proposals to the procedure of ground tests of the payload and the space experiment are developed.

  17. The Radiation Safety Information Computational Center (RSICC): A Resource for Nuclear Science Applications

    International Nuclear Information System (INIS)

    Kirk, Bernadette Lugue

    2009-01-01

    The Radiation Safety Information Computational Center (RSICC) has been in existence since 1963. RSICC collects, organizes, evaluates and disseminates technical information (software and nuclear data) involving the transport of neutral and charged particle radiation, and shielding and protection from the radiation associated with: nuclear weapons and materials, fission and fusion reactors, outer space, accelerators, medical facilities, and nuclear waste management. RSICC serves over 12,000 scientists and engineers from about 100 countries. An important activity of RSICC is its participation in international efforts on computational and experimental benchmarks. An example is the Shielding Integral Benchmarks Archival Database (SINBAD), which includes shielding benchmarks for fission, fusion and accelerators. RSICC is funded by the United States Department of Energy, Department of Homeland Security and Nuclear Regulatory Commission.

  18. Design and Development of a Linked Open Data-Based Health Information Representation and Visualization System: Potentials and Preliminary Evaluation

    Science.gov (United States)

    Kauppinen, Tomi; Keßler, Carsten; Fritz, Fleur

    2014-01-01

    Background Healthcare organizations around the world are challenged by pressures to reduce cost, improve coordination and outcome, and provide more with less. This requires effective planning and evidence-based practice by generating important information from available data. Thus, flexible and user-friendly ways to represent, query, and visualize health data becomes increasingly important. International organizations such as the World Health Organization (WHO) regularly publish vital data on priority health topics that can be utilized for public health policy and health service development. However, the data in most portals is displayed in either Excel or PDF formats, which makes information discovery and reuse difficult. Linked Open Data (LOD)—a new Semantic Web set of best practice of standards to publish and link heterogeneous data—can be applied to the representation and management of public level health data to alleviate such challenges. However, the technologies behind building LOD systems and their effectiveness for health data are yet to be assessed. Objective The objective of this study is to evaluate whether Linked Data technologies are potential options for health information representation, visualization, and retrieval systems development and to identify the available tools and methodologies to build Linked Data-based health information systems. Methods We used the Resource Description Framework (RDF) for data representation, Fuseki triple store for data storage, and Sgvizler for information visualization. Additionally, we integrated SPARQL query interface for interacting with the data. We primarily use the WHO health observatory dataset to test the system. All the data were represented using RDF and interlinked with other related datasets on the Web of Data using Silk—a link discovery framework for Web of Data. A preliminary usability assessment was conducted following the System Usability Scale (SUS) method. Results We developed an LOD

  19. Design and development of a linked open data-based health information representation and visualization system: potentials and preliminary evaluation.

    Science.gov (United States)

    Tilahun, Binyam; Kauppinen, Tomi; Keßler, Carsten; Fritz, Fleur

    2014-10-25

    Healthcare organizations around the world are challenged by pressures to reduce cost, improve coordination and outcome, and provide more with less. This requires effective planning and evidence-based practice by generating important information from available data. Thus, flexible and user-friendly ways to represent, query, and visualize health data becomes increasingly important. International organizations such as the World Health Organization (WHO) regularly publish vital data on priority health topics that can be utilized for public health policy and health service development. However, the data in most portals is displayed in either Excel or PDF formats, which makes information discovery and reuse difficult. Linked Open Data (LOD)-a new Semantic Web set of best practice of standards to publish and link heterogeneous data-can be applied to the representation and management of public level health data to alleviate such challenges. However, the technologies behind building LOD systems and their effectiveness for health data are yet to be assessed. The objective of this study is to evaluate whether Linked Data technologies are potential options for health information representation, visualization, and retrieval systems development and to identify the available tools and methodologies to build Linked Data-based health information systems. We used the Resource Description Framework (RDF) for data representation, Fuseki triple store for data storage, and Sgvizler for information visualization. Additionally, we integrated SPARQL query interface for interacting with the data. We primarily use the WHO health observatory dataset to test the system. All the data were represented using RDF and interlinked with other related datasets on the Web of Data using Silk-a link discovery framework for Web of Data. A preliminary usability assessment was conducted following the System Usability Scale (SUS) method. We developed an LOD-based health information representation, querying

  20. A two-step approach for the preliminary evaluation of the thermal-hydraulics and safety of the ELSY open square core design

    International Nuclear Information System (INIS)

    Meloni, Paride; Bandini, Giacomino; Polidori, Massimiliano; Cervone, Antonio; Manservisi, Sandro

    2009-01-01

    Several innovative solutions for a liquid metal fast reactor design have been investigated in the EURATOM Sixth Framework Programme and an open-assembly core design for the ELSY (European Lead-cooled System) reactor has been proposed by ENEA. The development of this new reactor, based on innovative neutronic and safety considerations, requires a new approach to the thermal-hydraulic (T/H) core design. In this paper a new two-step approach of the T/H analysis for this open-assembly core is presented and, in particular is used for the evaluation of the preliminary core design of a 1500 MW lead fast reactor with open square lattice and three fuel radial zones with different levels of enrichment. In the first step a preliminary thermal-hydraulic and safety evaluation of the core neutronic design is investigated by using a one-dimensional RELAP5 model for independent channel analysis. Then two and three-dimensional effects are taken into account by using a dedicated tool for the evaluation of assembly mixing effects. The RELAP5 model, based on pressure loss and heat transfer correlations available for heavy liquid metal flows in rod bundle, consists of completely independent assemblies and therefore it can be used for a conservative evaluation of the thermal-hydraulics of the core reactor. Due to the open-lattice configuration, the two and three-dimensional effects are important and they are taken into account by using a simplified three-dimensional numerical model of an open square lattice reactor core, developed with the purpose of analyzing the whole core behavior. The numerical simulation is performed at assembly length level taking into account the local fluctuations of turbulent viscosity and energy exchange coefficients at sub-channel level through transfer operators based on parametric coefficients. A preliminary evaluation of the mixing effects between assembly flows on the temperature field has been performed by using an average assembly turbulent viscosity