WorldWideScience

Sample records for technology validation safety

  1. Validation of innovative technologies and strategies for regulatory safety assessment methods: challenges and opportunities.

    Science.gov (United States)

    Stokes, William S; Wind, Marilyn

    2010-01-01

    Advances in science and innovative technologies are providing new opportunities to develop test methods and strategies that may improve safety assessments and reduce animal use for safety testing. These include high throughput screening and other approaches that can rapidly measure or predict various molecular, genetic, and cellular perturbations caused by test substances. Integrated testing and decision strategies that consider multiple types of information and data are also being developed. Prior to their use for regulatory decision-making, new methods and strategies must undergo appropriate validation studies to determine the extent that their use can provide equivalent or improved protection compared to existing methods and to determine the extent that reproducible results can be obtained in different laboratories. Comprehensive and optimal validation study designs are expected to expedite the validation and regulatory acceptance of new test methods and strategies that will support improved safety assessments and reduced animal use for regulatory testing.

  2. Two Cultures in Modern Science and Technology: For Safety and Validity Does Medicine Have to Update?

    Science.gov (United States)

    Becker, Robert E

    2016-01-11

    Two different scientific cultures go unreconciled in modern medicine. Each culture accepts that scientific knowledge and technologies are vulnerable to and easily invalidated by methods and conditions of acquisition, interpretation, and application. How these vulnerabilities are addressed separates the 2 cultures and potentially explains medicine's difficulties eradicating errors. A traditional culture, dominant in medicine, leaves error control in the hands of individual and group investigators and practitioners. A competing modern scientific culture accepts errors as inevitable, pernicious, and pervasive sources of adverse events throughout medical research and patient care too malignant for individuals or groups to control. Error risks to the validity of scientific knowledge and safety in patient care require systemwide programming able to support a culture in medicine grounded in tested, continually updated, widely promulgated, and uniformly implemented standards of practice for research and patient care. Experiences from successes in other sciences and industries strongly support the need for leadership from the Institute of Medicine's recommended Center for Patient Safely within the Federal Executive branch of government.

  3. Hydrogen Technologies Safety Guide

    Energy Technology Data Exchange (ETDEWEB)

    Rivkin, C. [National Renewable Energy Lab. (NREL), Golden, CO (United States); Burgess, R. [National Renewable Energy Lab. (NREL), Golden, CO (United States); Buttner, W. [National Renewable Energy Lab. (NREL), Golden, CO (United States)

    2015-01-01

    The purpose of this guide is to provide basic background information on hydrogen technologies. It is intended to provide project developers, code officials, and other interested parties the background information to be able to put hydrogen safety in context. For example, code officials reviewing permit applications for hydrogen projects will get an understanding of the industrial history of hydrogen, basic safety concerns, and safety requirements.

  4. A Methodology for Validating Safety Heuristics Using Clinical Simulations: Identifying and Preventing Possible Technology-Induced Errors Related to Using Health Information Systems

    Science.gov (United States)

    Borycki, Elizabeth; Kushniruk, Andre; Carvalho, Christopher

    2013-01-01

    Internationally, health information systems (HIS) safety has emerged as a significant concern for governments. Recently, research has emerged that has documented the ability of HIS to be implicated in the harm and death of patients. Researchers have attempted to develop methods that can be used to prevent or reduce technology-induced errors. Some researchers are developing methods that can be employed prior to systems release. These methods include the development of safety heuristics and clinical simulations. In this paper, we outline our methodology for developing safety heuristics specific to identifying the features or functions of a HIS user interface design that may lead to technology-induced errors. We follow this with a description of a methodological approach to validate these heuristics using clinical simulations. PMID:23606902

  5. Institute for safety technology

    International Nuclear Information System (INIS)

    1991-01-01

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

  6. Development of regulation technologies for software verification and validation of I and C systems important to safety in NPPs

    International Nuclear Information System (INIS)

    Kim, Bok Ryul; Oh, S. H.; Zhu, O. P.; Jeong, C. H.; Hwang, H. S.; Goo, C. S.; Chung, Y. H.

    2000-12-01

    The project has provided the draft regulatory policies and guides regarding the quality assurance of software used to I and C systems important to safety in nuclear power plants, differentiated V and V activities by safety classes which are important elements in ensuring software quality assurance, and suggested V and V techniques to be applied, regulatory guides and checklists for reviewing software important to safety. The project introduced the classification concepts on software quality assurance. The I and C systems important to safety are classified into IC-1, IC-2, IC-3, and Non-IC as based on safety classifications. And the software used to these I and C systems are classified into 3 categories, say, safety-critical software, safety-related software, and non-safety software, in the light of safety importance of functions to be performed. Based upon these safety classifications, the extent of software V and V activities by each class has been differentiated each other. On the other hand, the project has divided software important to safety into newly-developed software and previously-developed software in terms of design and implementation, and provided the draft regulatory guides on each type of software, for instance, newly-developed software, previously-developed software, and software tools

  7. Development of safety related technology and infrastructure for safety assessment

    International Nuclear Information System (INIS)

    Venkat Raj, V.

    1997-01-01

    Development and optimum utilisation of any technology calls for the building up of the necessary infrastructure and backup facilities. This is particularly true for a developing country like India and more so for an advanced technology like nuclear technology. Right from the inception of its nuclear power programme, the Indian approach has been to develop adequate infrastructure in various areas such as design, construction, manufacture, installation, commissioning and safety assessment of nuclear plants. This paper deals with the development of safety related technology and the relevant infrastructure for safety assessment. A number of computer codes for safety assessment have been developed or adapted in the areas of thermal hydraulics, structural dynamics etc. These codes have undergone extensive validation through data generated in the experimental facilities set up in India as well as participation in international standard problem exercises. Side by side with the development of the tools for safety assessment, the development of safety related technology was also given equal importance. Many of the technologies required for the inspection, ageing assessment and estimation of the residual life of various components and equipment, particularly those having a bearing on safety, were developed. This paper highlights, briefly, the work carried out in some of the areas mentioned above. (author)

  8. Alternative food safety intervention technologies

    Science.gov (United States)

    Alternative nonthermal and thermal food safety interventions are gaining acceptance by the food processing industry and consumers. These technologies include high pressure processing, ultraviolet and pulsed light, ionizing radiation, pulsed and radiofrequency electric fields, cold atmospheric plasm...

  9. The predictive validity of safety climate.

    Science.gov (United States)

    Johnson, Stephen E

    2007-01-01

    Safety professionals have increasingly turned their attention to social science for insight into the causation of industrial accidents. One social construct, safety climate, has been examined by several researchers [Cooper, M. D., & Phillips, R. A. (2004). Exploratory analysis of the safety climate and safety behavior relationship. Journal of Safety Research, 35(5), 497-512; Gillen, M., Baltz, D., Gassel, M., Kirsch, L., & Vacarro, D. (2002). Perceived safety climate, job Demands, and coworker support among union and nonunion injured construction workers. Journal of Safety Research, 33(1), 33-51; Neal, A., & Griffin, M. A. (2002). Safety climate and safety behaviour. Australian Journal of Management, 27, 66-76; Zohar, D. (2000). A group-level model of safety climate: Testing the effect of group climate on microaccidents in manufacturing jobs. Journal of Applied Psychology, 85(4), 587-596; Zohar, D., & Luria, G. (2005). A multilevel model of safety climate: Cross-level relationships between organization and group-level climates. Journal of Applied Psychology, 90(4), 616-628] who have documented its importance as a factor explaining the variation of safety-related outcomes (e.g., behavior, accidents). Researchers have developed instruments for measuring safety climate and have established some degree of psychometric reliability and validity. The problem, however, is that predictive validity has not been firmly established, which reduces the credibility of safety climate as a meaningful social construct. The research described in this article addresses this problem and provides additional support for safety climate as a viable construct and as a predictive indicator of safety-related outcomes. This study used 292 employees at three locations of a heavy manufacturing organization to complete the 16 item Zohar Safety Climate Questionnaire (ZSCQ) [Zohar, D., & Luria, G. (2005). A multilevel model of safety climate: Cross-level relationships between organization and group

  10. [Innovative technology and blood safety].

    Science.gov (United States)

    Begue, S; Morel, P; Djoudi, R

    2016-11-01

    If technological innovations are not enough alone to improve blood safety, their contributions for several decades in blood transfusion are major. The improvement of blood donation (new apheresis devices, RFID) or blood components (additive solutions, pathogen reduction technology, automated processing of platelets concentrates) or manufacturing process of these products (by automated processing of whole blood), all these steps where technological innovations were implemented, lead us to better traceability, more efficient processes, quality improvement of blood products and therefore increased blood safety for blood donors and patients. If we are on the threshold of a great change with the progress of pathogen reduction technology (for whole blood and red blood cells), we hope to see production of ex vivo red blood cells or platelets who are real and who open new conceptual paths on blood safety. Copyright © 2016 Elsevier Masson SAS. All rights reserved.

  11. Validity of your safety awareness training

    CERN Multimedia

    DG Unit

    2010-01-01

    AIS is setting up an automatic e-mail reminder system for safety training. You are invited to forward this message to everyone concerned. Reminder: Please check the validity of your Safety courses Since April 2009 the compulsory basic Safety awareness courses (levels 1, 2 and 3) have been accessible on a "self-service" basis on the web (see CERN Bulletin). Participants are required to pass a test at the end of each course. The test is valid for 3 years so courses must be repeated on a regular basis. A system of automatic e-mail reminders already exists for level 4 courses on SIR and will be extended to the other levels shortly. The number of levels you are required to complete depends on your professional category. Activity Personnel concerned Level 1 Level 2 Level 3 Level 4     Basic safety Basic Safety ...

  12. SCALE criticality safety verification and validation package

    International Nuclear Information System (INIS)

    Bowman, S.M.; Emmett, M.B.; Jordan, W.C.

    1998-01-01

    Verification and validation (V and V) are essential elements of software quality assurance (QA) for computer codes that are used for performing scientific calculations. V and V provides a means to ensure the reliability and accuracy of such software. As part of the SCALE QA and V and V plans, a general V and V package for the SCALE criticality safety codes has been assembled, tested and documented. The SCALE criticality safety V and V package is being made available to SCALE users through the Radiation Safety Information Computational Center (RSICC) to assist them in performing adequate V and V for their SCALE applications

  13. AEA Technology safety report 1990

    Energy Technology Data Exchange (ETDEWEB)

    1991-12-01

    AEA Technology is the trading name of the United Kingdom Atomic Energy Authority. Work in support of nuclear power at home and abroad continues to be an important part of our business but as nuclear power has matured AEA Technology has looked beyond its traditional role to other markets worldwide. We are a major commercial enterprise, with an annual turnover of Pound 450 million, selling a variety of technical services and products to customers worldwide. The scope of the business lies in the closely related fields of energy, environment and safety, targeted at both nuclear and non-nuclear markets. We also have a major role in providing innovative technology solutions to assist manufacturing industry. The 1990 report on safety within the Authority is presented here. (author).

  14. AEA Technology safety report 1990

    International Nuclear Information System (INIS)

    1991-12-01

    AEA Technology is the trading name of the United Kingdom Atomic Energy Authority. Work in support of nuclear power at home and abroad continues to be an important part of our business but as nuclear power has matured AEA Technology has looked beyond its traditional role to other markets worldwide. We are a major commercial enterprise, with an annual turnover of Pound 450 million, selling a variety of technical services and products to customers worldwide. The scope of the business lies in the closely related fields of energy, environment and safety, targeted at both nuclear and non-nuclear markets. We also have a major role in providing innovative technology solutions to assist manufacturing industry. The 1990 report on safety within the Authority is presented here. (author)

  15. 78 FR 5866 - Pipeline Safety: Annual Reports and Validation

    Science.gov (United States)

    2013-01-28

    ... DEPARTMENT OF TRANSPORTATION Pipeline and Hazardous Materials Safety Administration [Docket ID PHMSA-2012-0319] Pipeline Safety: Annual Reports and Validation AGENCY: Pipeline and Hazardous Materials... 2012 gas transmission and gathering annual reports, remind pipeline owners and operators to validate...

  16. Development and validation of a remote home safety protocol.

    Science.gov (United States)

    Romero, Sergio; Lee, Mi Jung; Simic, Ivana; Levy, Charles; Sanford, Jon

    2018-02-01

    Environmental assessments and subsequent modifications conducted by healthcare professionals can enhance home safety and promote independent living. However, travel time, expense and the availability of qualified professionals can limit the broad application of this intervention. Remote technology has the potential to increase access to home safety evaluations. This study describes the development and validation of a remote home safety protocol that can be used by a caregiver of an elderly person to video-record their home environment for later viewing and evaluation by a trained professional. The protocol was developed based on literature reviews and evaluations from clinical and content experts. Cognitive interviews were conducted with a group of six caregivers to validate the protocol. The final protocol included step-by-step directions to record indoor and outdoor areas of the home. The validation process resulted in modifications related to safety, clarity of the protocol, readability, visual appearance, technical descriptions and usability. Our final protocol includes detailed instructions that a caregiver should be able to follow to record a home environment for subsequent evaluation by a home safety professional. Implications for Rehabilitation The results of this study have several implications for rehabilitation practice The remote home safety evaluation protocol can potentially improve access to rehabilitation services for clients in remote areas and prevent unnecessary delays for needed care. Using our protocol, a patient's caregiver can partner with therapists to quickly and efficiently evaluate a patient's home before they are released from the hospital. Caregiver narration, which reflects a caregiver's own perspective, is critical to evaluating home safety. In-home safety evaluations, currently not available to all who need them due to access barriers, can enhance a patient's independence and provide a safer home environment.

  17. Validation of Safety-Critical Systems for Aircraft Loss-of-Control Prevention and Recovery

    Science.gov (United States)

    Belcastro, Christine M.

    2012-01-01

    Validation of technologies developed for loss of control (LOC) prevention and recovery poses significant challenges. Aircraft LOC can result from a wide spectrum of hazards, often occurring in combination, which cannot be fully replicated during evaluation. Technologies developed for LOC prevention and recovery must therefore be effective under a wide variety of hazardous and uncertain conditions, and the validation framework must provide some measure of assurance that the new vehicle safety technologies do no harm (i.e., that they themselves do not introduce new safety risks). This paper summarizes a proposed validation framework for safety-critical systems, provides an overview of validation methods and tools developed by NASA to date within the Vehicle Systems Safety Project, and develops a preliminary set of test scenarios for the validation of technologies for LOC prevention and recovery

  18. Validation testing of safety-critical software

    International Nuclear Information System (INIS)

    Kim, Hang Bae; Han, Jae Bok

    1995-01-01

    A software engineering process has been developed for the design of safety critical software for Wolsung 2/3/4 project to satisfy the requirements of the regulatory body. Among the process, this paper described the detail process of validation testing performed to ensure that the software with its hardware, developed by the design group, satisfies the requirements of the functional specification prepared by the independent functional group. To perform the tests, test facility and test software were developed and actual safety system computer was connected. Three kinds of test cases, i.e., functional test, performance test and self-check test, were programmed and run to verify each functional specifications. Test failures were feedback to the design group to revise the software and test results were analyzed and documented in the report to submit to the regulatory body. The test methodology and procedure were very efficient and satisfactory to perform the systematic and automatic test. The test results were also acceptable and successful to verify the software acts as specified in the program functional specification. This methodology can be applied to the validation of other safety-critical software. 2 figs., 2 tabs., 14 refs. (Author)

  19. Development of safety analysis technology for integral reactor

    Energy Technology Data Exchange (ETDEWEB)

    Sim, Suk K.; Song, J. H.; Chung, Y. J. and others

    1999-03-01

    Inherent safety features and safety system characteristics of the SMART integral reactor are investigated in this study. Performance and safety of the SMART conceptual design have been evaluated and confirmed through the performance and safety analyses using safety analysis system codes as well as a preliminary performance and safety analysis methodology. SMART design base events and their acceptance criteria are identified to develop a preliminary PIRT for the SMART integral reactor. Using the preliminary PIRT, a set of experimental program for the thermal hydraulic separate effect tests and the integral effect tests was developed for the thermal hydraulic model development and the system code validation. Safety characteristics as well as the safety issues of the integral reactor has been identified during the study, which will be used to resolve the safety issues and guide the regulatory criteria for the integral reactor. The results of the performance and safety analyses performed during the study were used to feedback for the SMART conceptual design. The performance and safety analysis code systems as well as the preliminary safety analysis methodology developed in this study will be validated as the SMART design evolves. The performance and safety analysis technology developed during the study will be utilized for the SMART basic design development. (author)

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

    International Nuclear Information System (INIS)

    Rutherford, D.A.

    1994-09-01

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

  1. Establishment of Safety Analysis System and Technology for CANDU Reactors

    International Nuclear Information System (INIS)

    Park, Joo Hwan; Rhee, B. W.; Min, B. J.; Kim, H. T.; Kim, W. Y.; Yoon, C.; Chun, J. S.; Cho, M. S.; Jeong, J. Y.; Kang, H. S.

    2007-06-01

    The following 4 research items have been studied to establish a CANDU safety analysis system and to develop the relevant elementary technology for CANDU reactors. First, to improve and validate the CANDU design and operational safety analysis codes, the CANDU physics cell code WIMS-CANDU was improved, and validated, and an analysis of the moderator subcooling and pressure tube integrity has been performed for the large break LOCAs without ECCS. Also a CATHENA model and a CFD model for a post-blowdown fuel channel analysis have been developed and validated against two high temperature thermal-chemical experiments, CS28-1 and 2. Second, to improve the integrated operating system of the CANDU safety analysis codes, an extension has been made to them to include the core and fuel accident analyses, and a web-based CANDU database, CANTHIS version 2.0 was completed. Third, to assess the applicability of the ACR-7 safety analysis methodology to CANDU-6 the ACR-7 safety analysis methods were reviewed and the safety analysis methods of ACR-7 applicable to CANDU-6 were recommended. Last, to supplement and improve the existing CANDU safety analysis procedures, detailed analysis procedures have been prepared for individual accident scenarios. The results of this study can be used to resolve the CANDU safety issues, to improve the current design and operational safety analysis codes, and to technically support the Wolsong site to resolve their problems

  2. Summary: Fusion technology, safety and environmental aspects

    International Nuclear Information System (INIS)

    Matsuda, S.

    2003-01-01

    The year 2002 was in the middle of successive governmental negotiation toward the start of the ITER Construction. The ITER Engineering Design Activities (EDA) continued until July 2001, and most of the highlighted topics were already reported at the last IAEA Fusion Energy Conference in Montreal or in other opportunities. However, the ITER EDA was followed by the Coordinated Technical Activities that provided a lot of qualitative achievements such as, the search for predictions on operation capabilities based on various data bases and analysis, optimization of the design based on its validating technology R and D. As a consequence, at this conference, major contribution in the field of Fusion Technology was again from ITER, and its related topics occupied about 38% of the total number of contributions of 86. In ITER, physics analysis, predictions and heating/current drive technologies are highlighted. Another key feature at this conference was the progress of study toward steady-state operation in both physics and technology research as well as their application to toroidal devices. Several tokamaks and helical devises are under construction or under design, and most of them incorporate super-conducting magnet for their coils. Studies were made for various types of fusion reactors including Spherical Torus, Tokamaks, Helical systems etc., and their common understandings are progressing through their comparative study. Looking in the near term, but beyond ITER, about 20% of the papers were devoted to the fusion materials and blanket development, with the neutron irradiation facilities for the research. Because of the importance of this field to be implemented in parallel with ITER, more contributions would be expected in future. With these themes in mind, the remaining sections of this paper are arranged in the order of 2) ITER, 3) Toroidal Devices under Construction or under Design, 4) Reactor Technology, 5) Safety and Environment, and 6) Conclusion

  3. Establishment of Safety Analysis System and Technology for CANDU Reactors

    International Nuclear Information System (INIS)

    Min, Byung Joo; Kim, W. Y.; Kim, H. T.; Rhee, B. W.; Yoon, C.; Kang, H. S.; Yoo, K. J.

    2005-03-01

    To improve the CANDU design/operation safety analysis codes and the CANDU safety analysis methodology, the following works have been done. From the development of the lattice codes (WIMS/CANDU), the lattice model simulates the real core lattice geometry and the effect of the pressure tube creep to the core lattice parameter has been evaluated. From the development of the 3-dimensional thermal-hydraulic analysis model of the moderator behavior (CFX4-CAMO), validation of the model against STERN Lab experiment has been executed. The butterfly-shaped grid structure and the 3-dimensional flow resistance model for porous media were developed and applied to the moderator analysis for Wolsong units 2/3/4. The single fuel channel analysis codes for blowdown and post-blowdown were unified by CATHENA. The 3-dimensional fuel channel analysis model (CFX-CACH) has been developed for validation of CATHENA fuel channel analysis model. The interlinking analysis system (CANVAS) of the thermal-hydraulic safety analysis codes for the primary heat transport system and containment system has been executed. The database system of core physics and thermal-hydraulics experimental data for safety analysis has been established on the URL: http://CANTHIS.kaeri.re.kr. For documentation and Standardization of the general safety analysis procedure, the general safety analysis procedure is developed and applied to a large break LOCA. The present research results can be utilized for establishment of the independent safety analysis technology and acquisition of the optimal safety analysis technology

  4. Limits on safety in technology

    International Nuclear Information System (INIS)

    Birkhofer, A.

    1984-01-01

    Owing to the difficulty of establishing a clear and generally binding definition of the term ''safety'', an explanation has been given of the five typical and/or most frequently encountered categories of accident causes. Following quantification of the hazards with the aid of safety factors and reliability parameters, examples of component and system failures are discussed from the nuclear engineering sector, together with the results of risk studies. In conclusion the relationship between man and machine is outlined, taking due account of malfunctions and the prevention of hazards and the superordinate problem of technical safety and ethics is also mentioned. (orig.) [de

  5. Validation and verification plan for safety and PRA codes

    International Nuclear Information System (INIS)

    Ades, M.J.; Crowe, R.D.; Toffer, H.

    1991-04-01

    This report discusses a verification and validation (V ampersand V) plan for computer codes used for safety analysis and probabilistic risk assessment calculations. The present plan fulfills the commitments by Westinghouse Savannah River Company (WSRC) to the Department of Energy Savannah River Office (DOE-SRO) to bring the essential safety analysis and probabilistic risk assessment codes in compliance with verification and validation requirements

  6. Validating Virtual Safety Stock Effectiveness through Simulation

    Directory of Open Access Journals (Sweden)

    Maria Elena Nenni

    2013-08-01

    safety stock effectiveness through simulation in an inventory system using a base stock policy with periodic reviews and backorders. This approach can be useful for researchers as well as practitioners who want to model the behaviour of an inventory system under uncertain conditions and verify the opportunity for setting up a virtual safety stock on top of, or instead of, the traditional physical safety stock.

  7. 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.

  8. Modern technologies and food safety

    Directory of Open Access Journals (Sweden)

    Grujić Radoslav

    2003-01-01

    Full Text Available To resolve the problem of lack of food in the World within primary food production, processing and procedures of preserving, new methods have been implemented (implementation of materials for protection, medications utilization of new areas for production purposes, use of GM microorganisms plants, even animals, utilization of food additives, introduction of new procedures of preservation, etc However, these procedures do not always move in the direction of ensuring food safety. Implementation of mentioned procedures creates resistance by consumers. The opinion and the attitude about this issue are very important all over the World. According to recent research performed in last five years, most of the population of developed and semi-developed countries considers food safety a priority, as second place the presence of ingredients that can be harmful for human health and as third the content of nutrients required for normal functioning of the body. The WHO, CAC, WTO and other international institutions support these attitudes of consumers. There is more and more obvious pressure on food producers to preserve the environment, which has resulted in the introduction of production procedures known as "cleaning production".Regardless of which procedure is involved, it is necessary to implement the efficient quality control system and food safety. It is mandatory to request the compulsory implementation of different systems that are defined through the GMR GHR HACCR ISO 9000. In food production, these systems are complementary and only with full implementation of all of them in practice will if be possible to ensure the continuous production of quality and safe products. Food production must be seen as an undisturbed chain: primary production, transport, processing, storage, distribution and consumption. With strict implementation of the mentioned standards in all parts of the chain, the risk of injuries and poisoning of consumers will be decreased to

  9. Proceedings of the driving safety technology forum

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-07-01

    This one day forum focused on improving driving safety in the petroleum industry by introducing new technologies and strategies. The forum featured several keynote addresses on driving safety as well as the Government of Alberta's Tactical Plan and Alberta Road Safety at Work Strategy. Presentations consisted of success stories of new technology or process applications or proposed technology demonstration projects followed by question and answer panels around the following topics: industry and government strategies; driver fatigue management and prevention; driver behaviour and culture change; vehicle monitoring systems and innovative wildlife avoidance techniques. Specific presentations addressed BP's driving safety strategy, in-cabin air quality and truck drivers' health and safety and how Talisman Energy implemented oilfield fleet safety using event driven automated vehicle location technologies. A total of 3 keynote addresses, 3 panel question and answer sessions and 11 presentations were presented at the conference, of which 3 have been catalogued separately for inclusion in this database. refs., tabs., figs.

  10. Safety management in nuclear technology. Proceedings

    International Nuclear Information System (INIS)

    2008-01-01

    At the symposium of TueV Sued AG (Munich, Federal Republic of Germany) held in Munich on 28 and 29 October 2008, the following lectures were held: (1) Fundamental requirements of the management system in nuclear technology - Experiences from the international developments at IAEA and WENRA (M. Herttrich); (2) Information from a comparison of requirements of safety management systems (B. Kallenbach-Herbert); (3) Requirements of a modern management system in German nuclear power plants from the view of nuclear safety (D. Majer); (4) Requirements on safety management in module 8 of the regulations project (M. Maqua); (5) Requirements on the management system in nuclear power plants according to GRS-229 and developments at the KTA 1402 ''Integrated management system for safe operation of nuclear power plants (in progress)'' (C. Verstegen); (6) Experiences from the development and implementation of safety management systems in connection with the works management of a nuclear power plant (K. Ramler); (7) Design of a safety management system of a nuclear power plant in consideration of existing management systems (U. Naumann); (8) Experiences in the utilization and evaluation of a safety management system (J. Ritter); (9) Aspects of leadership of safety management systems (S. Seitz); (10) Management of safety or safety management system? Prevailing or administration? (A. Frischknecht); (11) Change management - strategies for successful transfer of new projects: How can I motivate co-workers for a further development of the safety management system? (U. Schnabel); (12) Requirements concerning indicators in integrated management systems and safety management systems (J. Stiller); (13) Integration of proactive and reactive indicators in the safety management system (B. Fahlbruch); (14) What do indicators show? About the use of indicators by regulatory authorities (A. Kern); (15) Safety management and radiation protection in nuclear technology (K. Grantner); (16) Any more

  11. Safety when dealing with technology

    International Nuclear Information System (INIS)

    Utzelmann, H.D.

    1987-01-01

    There always is a certain hazard involved when man has to do with technology. This applies to all spheres of life where man uses technical systems, as e.g. in the field of traffic and transport, at work, but also at home or during one's leisure time. The book in hand is intended for practice and vocational training and presents a survey of theoretical and practical approaches and aspects of accident prevention, particularly with regard to man and the human factors in the man-machine systems. (orig.) [de

  12. Proceedings of the nuclear criticality technology safety project

    Energy Technology Data Exchange (ETDEWEB)

    Sanchez, R.G. [comp.

    1997-06-01

    This document contains summaries of the most of the papers presented at the 1994 Nuclear Criticality Technology Safety Project (NCTSP) meeting, which was held May 10 and 11 at Williamsburg, Va. The meeting was broken up into seven sessions, which covered the following topics: (1) Validation and Application of Calculations; (2) Relevant Experiments for Criticality Safety; (3) Experimental Facilities and Capabilities; (4) Rad-Waste and Weapons Disassembly; (5) Criticality Safety Software and Development; (6) Criticality Safety Studies at Universities; and (7) Training. The minutes and list of participants of the Critical Experiment Needs Identification Workgroup meeting, which was held on May 9 at the same venue, has been included as an appendix. A second appendix contains the names and addresses of all NCTSP meeting participants. Separate abstracts have been indexed to the database for contributions to this proceedings.

  13. Proceedings of the nuclear criticality technology safety project

    International Nuclear Information System (INIS)

    Sanchez, R.G.

    1997-06-01

    This document contains summaries of the most of the papers presented at the 1994 Nuclear Criticality Technology Safety Project (NCTSP) meeting, which was held May 10 and 11 at Williamsburg, Va. The meeting was broken up into seven sessions, which covered the following topics: (1) Validation and Application of Calculations; (2) Relevant Experiments for Criticality Safety; (3) Experimental Facilities and Capabilities; (4) Rad-Waste and Weapons Disassembly; (5) Criticality Safety Software and Development; (6) Criticality Safety Studies at Universities; and (7) Training. The minutes and list of participants of the Critical Experiment Needs Identification Workgroup meeting, which was held on May 9 at the same venue, has been included as an appendix. A second appendix contains the names and addresses of all NCTSP meeting participants. Separate abstracts have been indexed to the database for contributions to this proceedings

  14. Fuel Cell and Hydrogen Technology Validation | Hydrogen and Fuel Cells |

    Science.gov (United States)

    NREL Fuel Cell and Hydrogen Technology Validation Fuel Cell and Hydrogen Technology Validation The NREL technology validation team works on validating hydrogen fuel cell electric vehicles; hydrogen fueling infrastructure; hydrogen system components; and fuel cell use in early market applications such as

  15. Development and initial validation of an Aviation Safety Climate Scale.

    Science.gov (United States)

    Evans, Bronwyn; Glendon, A Ian; Creed, Peter A

    2007-01-01

    A need was identified for a consistent set of safety climate factors to provide a basis for aviation industry benchmarking. Six broad safety climate themes were identified from the literature and consultations with industry safety experts. Items representing each of the themes were prepared and administered to 940 Australian commercial pilots. Data from half of the sample (N=468) were used in an exploratory factor analysis that produced a 3-factor model of Management commitment and communication, Safety training and equipment, and Maintenance. A confirmatory factor analysis on the remaining half of the sample showed the 3-factor model to be an adequate fit to the data. The results of this study have produced a scale of safety climate for aviation that is both reliable and valid. This study developed a tool to assess the level of perceived safety climate, specifically of pilots, but may also, with minor modifications, be used to assess other groups' perceptions of safety climate.

  16. Physical safety: using of multimedia technology

    International Nuclear Information System (INIS)

    Munoz Garcia, M.

    1995-01-01

    For managing physical safety systems in nuclear power plants sophisticated computer equipment is essential. Standard safety procedure requires systems distributed throughout the plant, especially at security posts: Entrance Door, Access Control Center, Restricted Areas, etc. Besides being highly distributed, computerized physical safety management systems have always been characterized by the need to integrate very different elements. Graphic images have always played a very important role: photographs, fingerprints, signatures, etc. This makes integrated multimedia modules the ideal solution. This presentation describes how safety systems can combine not only still images, but also other multimedia data such as sound and video. It examines methodologies for using this new technology to upgrade high cost computer systems already in operation that can not be replaced. (Author)

  17. NASA's aviation safety research and technology program

    Science.gov (United States)

    Fichtl, G. H.

    1977-01-01

    Aviation safety is challenged by the practical necessity of compromising inherent factors of design, environment, and operation. If accidents are to be avoided these factors must be controlled to a degree not often required by other transport modes. The operational problems which challenge safety seem to occur most often in the interfaces within and between the design, the environment, and operations where mismatches occur due to ignorance or lack of sufficient understanding of these interactions. Under this report the following topics are summarized: (1) The nature of operating problems, (2) NASA aviation safety research, (3) clear air turbulence characterization and prediction, (4) CAT detection, (5) Measurement of Atmospheric Turbulence (MAT) Program, (6) Lightning, (7) Thunderstorm gust fronts, (8) Aircraft ground operating problems, (9) Aircraft fire technology, (10) Crashworthiness research, (11) Aircraft wake vortex hazard research, and (12) Aviation safety reporting system.

  18. Safety and Security Interface Technology Initiative

    International Nuclear Information System (INIS)

    Dr. Michael A. Lehto; Kevin J. Carroll; Dr. Robert Lowrie

    2007-01-01

    Earlier this year, the Energy Facility Contractors Group (EFCOG) was asked to assist in developing options related to acceleration deployment of new security-related technologies to assist meeting design base threat (DBT) needs while also addressing the requirements of 10 CFR 830. NNSA NA-70, one of the working group participants, designated this effort the Safety and Security Interface Technology Initiative (SSIT). Relationship to Workshop Theme. ''Supporting Excellence in Operations Through Safety Analysis'', (workshop theme) includes security and safety personnel working together to ensure effective and efficient operations. One of the specific workshop elements listed in the call for papers is ''Safeguards/Security Integration with Safety''. This paper speaks directly to this theme. Description of Work. The EFCOG Safety Analysis Working Group (SAWG) and the EFCOG Security Working Group formed a core team to develop an integrated process involving both safety basis and security needs allowing achievement of the DBT objectives while ensuring safety is appropriately considered. This effort garnered significant interest, starting with a two day breakout session of 30 experts at the 2006 Safety Basis Workshop. A core team was formed, and a series of meetings were held to develop that process, including safety and security professionals, both contractor and federal personnel. A pilot exercise held at Idaho National Laboratory (INL) in mid-July 2006 was conducted as a feasibility of concept review. Work Results. The SSIT efforts resulted in a topical report transmitted from EFCOG to DOE/NNSA in August 2006. Elements of the report included: Drivers and Endstate, Control Selections Alternative Analysis Process, Terminology Crosswalk, Safety Basis/Security Documentation Integration, Configuration Control, and development of a shared ''tool box'' of information/successes. Specific Benefits. The expectation or end state resulting from the topical report and associated

  19. Elaboration and Validation of the Medication Prescription Safety Checklist 1

    Science.gov (United States)

    Pires, Aline de Oliveira Meireles; Ferreira, Maria Beatriz Guimarães; do Nascimento, Kleiton Gonçalves; Felix, Márcia Marques dos Santos; Pires, Patrícia da Silva; Barbosa, Maria Helena

    2017-01-01

    ABSTRACT Objective: to elaborate and validate a checklist to identify compliance with the recommendations for the structure of medication prescriptions, based on the Protocol of the Ministry of Health and the Brazilian Health Surveillance Agency. Method: methodological research, conducted through the validation and reliability analysis process, using a sample of 27 electronic prescriptions. Results: the analyses confirmed the content validity and reliability of the tool. The content validity, obtained by expert assessment, was considered satisfactory as it covered items that represent the compliance with the recommendations regarding the structure of the medication prescriptions. The reliability, assessed through interrater agreement, was excellent (ICC=1.00) and showed perfect agreement (K=1.00). Conclusion: the Medication Prescription Safety Checklist showed to be a valid and reliable tool for the group studied. We hope that this study can contribute to the prevention of adverse events, as well as to the improvement of care quality and safety in medication use. PMID:28793128

  20. WSRC approach to validation of criticality safety computer codes

    International Nuclear Information System (INIS)

    Finch, D.R.; Mincey, J.F.

    1991-01-01

    Recent hardware and operating system changes at Westinghouse Savannah River Site (WSRC) have necessitated review of the validation for JOSHUA criticality safety computer codes. As part of the planning for this effort, a policy for validation of JOSHUA and other criticality safety codes has been developed. This policy will be illustrated with the steps being taken at WSRC. The objective in validating a specific computational method is to reliably correlate its calculated neutron multiplication factor (K eff ) with known values over a well-defined set of neutronic conditions. Said another way, such correlations should be: (1) repeatable; (2) demonstrated with defined confidence; and (3) identify the range of neutronic conditions (area of applicability) for which the correlations are valid. The general approach to validation of computational methods at WSRC must encompass a large number of diverse types of fissile material processes in different operations. Special problems are presented in validating computational methods when very few experiments are available (such as for enriched uranium systems with principal second isotope 236 U). To cover all process conditions at WSRC, a broad validation approach has been used. Broad validation is based upon calculation of many experiments to span all possible ranges of reflection, nuclide concentrations, moderation ratios, etc. Narrow validation, in comparison, relies on calculations of a few experiments very near anticipated worst-case process conditions. The methods and problems of broad validation are discussed

  1. Validation of calculational methods for nuclear criticality safety - approved 1975

    International Nuclear Information System (INIS)

    Anon.

    1977-01-01

    The American National Standard for Nuclear Criticality Safety in Operations with Fissionable Materials Outside Reactors, N16.1-1975, states in 4.2.5: In the absence of directly applicable experimental measurements, the limits may be derived from calculations made by a method shown to be valid by comparison with experimental data, provided sufficient allowances are made for uncertainties in the data and in the calculations. There are many methods of calculation which vary widely in basis and form. Each has its place in the broad spectrum of problems encountered in the nuclear criticality safety field; however, the general procedure to be followed in establishing validity is common to all. The standard states the requirements for establishing the validity and area(s) of applicability of any calculational method used in assessing nuclear criticality safety

  2. Development of safety analysis technology for LMR

    International Nuclear Information System (INIS)

    Hahn, Do Hee; Kwon, Y. M.; Suk, S. D.

    2002-05-01

    In the present study, the KALIMER safety analysis has been made for the transients considered in the design concept, hypothetical core disruptive accident (HCDA), and containment performance with the establishment of the design basis. Such analyses have not been possible without the computer code improvement, and the experience attained during this research period must have greatly contributed to the achievement of the self reliance in the domestic technology establishment on the safety analysis areas of the conceptual design. The safety analysis codes have been improved to extend their applicable ranges for detailed conceptual design, and a basic computer code system has been established for HCDA analysis. A code-to-code comparison analysis has been performed as a part of code verification attempt, and the leading edge technology of JNC also has been brought for the technology upgrade. In addition, the research and development on the area of the database establishment has been made for the efficient and systematic project implementation of the conceptual design, through performances on the development of a project scheduling management, integration of the individually developed technology, establishment of the product database, and so on, taking into account coupling of the activities conducted in each specific area

  3. Safety evaluations required in the safety regulations for Monju and the validity confirmation of safety evaluation methods

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2013-08-15

    The purposes of this study are to perform the safety evaluations of the fast breeder reactor 'Monju' and to confirm the validity of the safety evaluation methods. In JFY 2012, the following results were obtained. As for the development of safety evaluation methods needed in the safety examination achieved for the reactor establishment permission, development of the analysis codes, such as a core damage analysis code, were carried out according to the plan. As for the development of the safety evaluation method needed for the risk informed safety regulation, the quantification technique of the event tree using the Continuous Markov chain Monte Carlo method (CMMC method) were studied. (author)

  4. Validity of instruments to assess students' travel and pedestrian safety

    Directory of Open Access Journals (Sweden)

    Baranowski Tom

    2010-05-01

    Full Text Available Abstract Background Safe Routes to School (SRTS programs are designed to make walking and bicycling to school safe and accessible for children. Despite their growing popularity, few validated measures exist for assessing important outcomes such as type of student transport or pedestrian safety behaviors. This research validated the SRTS school travel survey and a pedestrian safety behavior checklist. Methods Fourth grade students completed a brief written survey on how they got to school that day with set responses. Test-retest reliability was obtained 3-4 hours apart. Convergent validity of the SRTS travel survey was assessed by comparison to parents' report. For the measure of pedestrian safety behavior, 10 research assistants observed 29 students at a school intersection for completion of 8 selected pedestrian safety behaviors. Reliability was determined in two ways: correlations between the research assistants' ratings to that of the Principal Investigator (PI and intraclass correlations (ICC across research assistant ratings. Results The SRTS travel survey had high test-retest reliability (κ = 0.97, n = 96, p Conclusions These validated instruments can be used to assess SRTS programs. The pedestrian safety behavior checklist may benefit from further formative work.

  5. Validation of the Information/Communications Technology Literacy Test

    Science.gov (United States)

    2016-10-01

    Technical Report 1360 Validation of the Information /Communications Technology Literacy Test D. Matthew Trippe Human Resources Research...TITLE AND SUBTITLE Validation of the Information /Communications Technology Literacy Test 5a. CONTRACT OR GRANT NUMBER W91WAS-09-D-0013 5b...validate a measure of cyber aptitude, the Information /Communications Technology Literacy Test (ICTL), in predicting trainee performance in Information

  6. Applying Digital Technologies to Strengthen Nuclear Safety

    International Nuclear Information System (INIS)

    Huffeteau, S.; Roy, C.

    2016-01-01

    Full text: The paper describes how the development of some information technologies can further contribute to the safety of nuclear facilities and their competitiveness. After repositioning the nuclear industry engineering practices in their historical and economic context, the paper describes five engineering practices or use cases widely developed especially in the aerospace industry: requirement management, business process enforcement by digitization of data and processes, facilities configuration management, engineering information unification, and digital licensing. Information technology (IT) plays a mandatory role for driving this change since IT is now mature enough to handle the level of complexity the nuclear industry requires. While the detailed evaluation of the expecting gains in cost decrease or safety increase can be difficult to quantify, the paper presents illustrative benefits reachable by a development of these practices. (author

  7. Safety and Security Interface Technology Initiative

    Energy Technology Data Exchange (ETDEWEB)

    Dr. Michael A. Lehto; Kevin J. Carroll; Dr. Robert Lowrie

    2007-05-01

    Safety and Security Interface Technology Initiative Mr. Kevin J. Carroll Dr. Robert Lowrie, Dr. Micheal Lehto BWXT Y12 NSC Oak Ridge, TN 37831 865-576-2289/865-241-2772 carrollkj@y12.doe.gov Work Objective. Earlier this year, the Energy Facility Contractors Group (EFCOG) was asked to assist in developing options related to acceleration deployment of new security-related technologies to assist meeting design base threat (DBT) needs while also addressing the requirements of 10 CFR 830. NNSA NA-70, one of the working group participants, designated this effort the Safety and Security Interface Technology Initiative (SSIT). Relationship to Workshop Theme. “Supporting Excellence in Operations Through Safety Analysis,” (workshop theme) includes security and safety personnel working together to ensure effective and efficient operations. One of the specific workshop elements listed in the call for papers is “Safeguards/Security Integration with Safety.” This paper speaks directly to this theme. Description of Work. The EFCOG Safety Analysis Working Group (SAWG) and the EFCOG Security Working Group formed a core team to develop an integrated process involving both safety basis and security needs allowing achievement of the DBT objectives while ensuring safety is appropriately considered. This effort garnered significant interest, starting with a two day breakout session of 30 experts at the 2006 Safety Basis Workshop. A core team was formed, and a series of meetings were held to develop that process, including safety and security professionals, both contractor and federal personnel. A pilot exercise held at Idaho National Laboratory (INL) in mid-July 2006 was conducted as a feasibility of concept review. Work Results. The SSIT efforts resulted in a topical report transmitted from EFCOG to DOE/NNSA in August 2006. Elements of the report included: Drivers and Endstate, Control Selections Alternative Analysis Process, Terminology Crosswalk, Safety Basis

  8. NDE reliability and advanced NDE technology validation

    International Nuclear Information System (INIS)

    Doctor, S.R.; Deffenbaugh, J.D.; Good, M.S.; Green, E.R.; Heasler, P.G.; Hutton, P.H.; Reid, L.D.; Simonen, F.A.; Spanner, J.C.; Vo, T.V.

    1989-01-01

    This paper reports on progress for three programs: (1) evaluation and improvement in nondestructive examination reliability for inservice inspection of light water reactors (LWR) (NDE Reliability Program), (2) field validation acceptance, and training for advanced NDE technology, and (3) evaluation of computer-based NDE techniques and regional support of inspection activities. The NDE Reliability Program objectives are to quantify the reliability of inservice inspection techniques for LWR primary system components through independent research and establish means for obtaining improvements in the reliability of inservice inspections. The areas of significant progress will be described concerning ASME Code activities, re-analysis of the PISC-II data, the equipment interaction matrix study, new inspection criteria, and PISC-III. The objectives of the second program are to develop field procedures for the AE and SAFT-UT techniques, perform field validation testing of these techniques, provide training in the techniques for NRC headquarters and regional staff, and work with the ASME Code for the use of these advanced technologies. The final program's objective is to evaluate the reliability and accuracy of interpretation of results from computer-based ultrasonic inservice inspection systems, and to develop guidelines for NRC staff to monitor and evaluate the effectiveness of inservice inspections conducted on nuclear power reactors. This program started in the last quarter of FY89, and the extent of the program was to prepare a work plan for presentation to and approval from a technical advisory group of NRC staff

  9. 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.

  10. Validity of instruments to assess students' travel and pedestrian safety.

    Science.gov (United States)

    Mendoza, Jason A; Watson, Kathy; Baranowski, Tom; Nicklas, Theresa A; Uscanga, Doris K; Hanfling, Marcus J

    2010-05-18

    Safe Routes to School (SRTS) programs are designed to make walking and bicycling to school safe and accessible for children. Despite their growing popularity, few validated measures exist for assessing important outcomes such as type of student transport or pedestrian safety behaviors. This research validated the SRTS school travel survey and a pedestrian safety behavior checklist. Fourth grade students completed a brief written survey on how they got to school that day with set responses. Test-retest reliability was obtained 3-4 hours apart. Convergent validity of the SRTS travel survey was assessed by comparison to parents' report. For the measure of pedestrian safety behavior, 10 research assistants observed 29 students at a school intersection for completion of 8 selected pedestrian safety behaviors. Reliability was determined in two ways: correlations between the research assistants' ratings to that of the Principal Investigator (PI) and intraclass correlations (ICC) across research assistant ratings. The SRTS travel survey had high test-retest reliability (kappa = 0.97, n = 96, p < 0.001) and convergent validity (kappa = 0.87, n = 81, p < 0.001). The pedestrian safety behavior checklist had moderate reliability across research assistants' ratings (ICC = 0.48) and moderate correlation with the PI (r = 0.55, p = < 0.01). When two raters simultaneously used the instrument, the ICC increased to 0.65. Overall percent agreement (91%), sensitivity (85%) and specificity (83%) were acceptable. These validated instruments can be used to assess SRTS programs. The pedestrian safety behavior checklist may benefit from further formative work.

  11. 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

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

    International Nuclear Information System (INIS)

    Li Duo; Zhang Liangju; Feng Junting

    2008-01-01

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

  13. On-line validation of safety parameters and fault identification

    International Nuclear Information System (INIS)

    Tzanos, C.P.

    1985-01-01

    In many safety-significant off-normal events, the reliability of failure identification and corrective operator actions is limited greatly by the large amount of data that has to be processed and analyzed mentally in a very short time and in a high-stress environment. A data-validation and fault-identification system, that uses computers for continuous plant-information processing and analysis, can enhance plant safety and also improve plant availability. A methodology has been developed that provides validation of safety-significant plant parameter measurements, plant state verification, and fault identification in the presence of many instrumentation failures (including multiple common-cause failures). This paper presents this methodology and some results of its application to a reference LMFBR plant. The basic features of this methodology and the results of its application are summarized

  14. Proceeding of the Fifth Scientific Presentation on Nuclear Safety Technology

    International Nuclear Information System (INIS)

    Suhaemi, Tj.; Sudarno; Sunaryo, G. R.; Supriatna, P.; Antariksawan, A. R.; Sumijanto; Febrianto; Histori; Aliq

    2000-01-01

    The proceedings includes the result of research and development activities on nuclear safety technology that have been done by research Center for Nuclear Safety Technology in 2000 and was presented on June 28, 2000. The proceedings is expected to give illustration of the research result on Nuclear Safety Technology

  15. Proceedings of the Fourth Scientific Presentation on Reactor Safety Technology

    International Nuclear Information System (INIS)

    1999-01-01

    The proceedings includes the result of research and development activities on nuclear safety technology that have been done by research Center for Nuclear Safety Technology in 1998/1999 and was presented on May 5, 1999. The proceedings is expected to give illustration of the research result on Nuclear Safety Technology

  16. Intercomparison and validation of computer codes for thermalhydraulic safety analysis of heavy water reactors

    International Nuclear Information System (INIS)

    2004-08-01

    Activities within the frame of the IAEA's Technical Working Group on Advanced Technologies for HWRs (TWG-HWR) are conducted in a project within the IAEA's subprogramme on nuclear power reactor technology development. The objective of the activities on HWRs is to foster, within the frame of the TWG-HWR, information exchange and co-operative research on technology development for current and future HWRs, with an emphasis on safety, economics and fuel resource sustainability. One of the activities recommended by the TWG-HWR was an international standard problem exercise entitled: Intercomparison and validation of computer codes for thermalhydraulics safety analyses. Intercomparison and validation of computer codes used in different countries for thermalhydraulics safety analyses will enhance the confidence in the predictions made by these codes. However, the intercomparison and validation exercise needs a set of reliable experimental data. The RD-14M Large-Loss Of Coolant Accident (LOCA) test B9401 simulating HWR LOCA behaviour that was conducted by Atomic Energy of Canada Ltd (AECL) was selected for this validation project. This report provides a comparison of the results obtained from six participating countries, utilizing four different computer codes. General conclusions are reached and recommendations made

  17. Development of safety analysis technology for LMR

    International Nuclear Information System (INIS)

    Lee, Y. B.; Kwon, Y. M.; Suk, S. D.

    2005-03-01

    The MATRA-LMR-FB has been developed internally for the damage prevention as well as the safety assessment during a channel blockage accident and, as a the result, the quality of the code becomes comparable to that developed in the leading countries. For a code-to-code comparison, KAERI could have access to the SASSYS-1 through a bilateral collaboration between KAERI and ANL. The study could bring into the reliability improvements both on the reactivity models in the SSC-K and on the SSC-K prediction capability. It finally leads to the completion of the SSC-K version 1.3 resulting from the qualitative and quantitative code-to-code comparison. The preliminary analysis for a metal fueled LMR could also become possible with the MELT-III and the VENUS-II, which had originally been developed for the HCDA analysis with an oxidized fuel, by developing the relevant models For the development of the safety evaluation technology, the safety limits have been set up, and the analyses of the internal and external channel blockages in an assembly have also been performed. Besides, the more reliable analysis results on the key design concepts could be obtained by way of the methodology improvement resulting from the qualitative and quantitative comparison study. For an efficient and systematic control of the main project, the integration of the developed technologies and the establishment of their data base have been pursued. It has gone through the development of the process control with taking account of interfaces among the sub-projects, the overall coordination of the developed technologies, the data base for the design products, and so on

  18. Criticality safety validation of MCNP5 using continuous energy libraries

    International Nuclear Information System (INIS)

    Salome, Jean A.D.; Pereira, Claubia; Assuncao, Jonathan B.A.; Veloso, Maria Auxiliadora F.; Costa, Antonella L.; Silva, Clarysson A.M. da

    2013-01-01

    The study of subcritical systems is very important in the design, installation and operation of various devices, mainly nuclear reactors and power plants. The information generated by these systems guide the decisions to be taken in the executive project, the economic viability and the safety measures to be employed in a nuclear facility. Simulating some experiments from the International Handbook of Evaluated Criticality Safety Benchmark Experiments, the code MCNP5 was validated to nuclear criticality analysis. Its continuous libraries were used. The average values and standard deviation (SD) were evaluated. The results obtained with the code are very similar to the values obtained by the benchmark experiments. (author)

  19. Radiation safety assessment and development of environmental radiation monitoring technology

    CERN Document Server

    Choi, B H; Kim, S G

    2002-01-01

    The Periodic Safety Review(PSR) of the existing nuclear power plants is required every ten years according to the recently revised atomic energy acts. The PSR of Kori unit 1 and Wolsong unit 1 that have been operating more than ten years is ongoing to comply the regulations. This research project started to develop the techniques necessary for the PSR. The project developed the following four techniques at the first stage for the environmental assessment of the existing plants. 1) Establishment of the assessment technology for contamination and accumulation trends of radionuclides, 2) alarm point setting of environmental radiation monitoring system, 3) Development of Radiation Safety Evaluation Factor for Korean NPP, and 4) the evaluation of radiation monitoring system performance and set-up of alarm/warn set point. A dynamic compartment model to derive a relationship between the release rates of gas phase radionuclides and the concentrations in the environmental samples. The model was validated by comparing ...

  20. Validation test case generation based on safety analysis ontology

    International Nuclear Information System (INIS)

    Fan, Chin-Feng; Wang, Wen-Shing

    2012-01-01

    Highlights: ► Current practice in validation test case generation for nuclear system is mainly ad hoc. ► This study designs a systematic approach to generate validation test cases from a Safety Analysis Report. ► It is based on a domain-specific ontology. ► Test coverage criteria have been defined and satisfied. ► A computerized toolset has been implemented to assist the proposed approach. - Abstract: Validation tests in the current nuclear industry practice are typically performed in an ad hoc fashion. This study presents a systematic and objective method of generating validation test cases from a Safety Analysis Report (SAR). A domain-specific ontology was designed and used to mark up a SAR; relevant information was then extracted from the marked-up document for use in automatically generating validation test cases that satisfy the proposed test coverage criteria; namely, single parameter coverage, use case coverage, abnormal condition coverage, and scenario coverage. The novelty of this technique is its systematic rather than ad hoc test case generation from a SAR to achieve high test coverage.

  1. Verification and validation process for the safety software in KNICS

    International Nuclear Information System (INIS)

    Kwon, Kee-Choon; Lee, Jang-Soo; Kim, Jang-Yeol

    2004-01-01

    This paper describes the Verification and Validation (V and V ) process for safety software of Programmable Logic Controller (PLC), Digital Reactor Protection System (DRPS), and Engineered Safety Feature-Component Control System (ESF-CCS) that are being developed in Korea Nuclear Instrumentation and Control System (KNICS) projects. Specifically, it presents DRPS V and V experience according to the software development life cycle. The main activities of DRPS V and V process are preparation of software planning documentation, verification of Software Requirement Specification (SRS), Software Design Specification (SDS) and codes, and testing of the integrated software and the integrated system. In addition, they include software safety analysis and software configuration management. SRS V and V of DRPS are technical evaluation, licensing suitability evaluation, inspection and traceability analysis, formal verification, preparing integrated system test plan, software safety analysis, and software configuration management. Also, SDS V and V of RPS are technical evaluation, licensing suitability evaluation, inspection and traceability analysis, formal verification, preparing integrated software test plan, software safety analysis, and software configuration management. The code V and V of DRPS are traceability analysis, source code inspection, test case and test procedure generation, software safety analysis, and software configuration management. Testing is the major V and V activity of software integration and system integration phase. Software safety analysis at SRS phase uses Hazard Operability (HAZOP) method, at SDS phase it uses HAZOP and Fault Tree Analysis (FTA), and at implementation phase it uses FTA. Finally, software configuration management is performed using Nu-SCM (Nuclear Software Configuration Management) tool developed by KNICS project. Through these activities, we believe we can achieve the functionality, performance, reliability and safety that are V

  2. Lecture Notes on Criticality Safety Validation Using MCNP & Whisper

    Energy Technology Data Exchange (ETDEWEB)

    Brown, Forrest B. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Rising, Michael Evan [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Alwin, Jennifer Louise [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2016-03-11

    Training classes for nuclear criticality safety, MCNP documentation. The need for, and problems surrounding, validation of computer codes and data area considered first. Then some background for MCNP & Whisper is given--best practices for Monte Carlo criticality calculations, neutron spectra, S(α,β) thermal neutron scattering data, nuclear data sensitivities, covariance data, and correlation coefficients. Whisper is computational software designed to assist the nuclear criticality safety analyst with validation studies with the Monte Carlo radiation transport package MCNP. Whisper's methodology (benchmark selection – Ck's, weights; extreme value theory – bias, bias uncertainty; MOS for nuclear data uncertainty – GLLS) and usage are discussed.

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

    International Nuclear Information System (INIS)

    Theenhaus, R.; Wolters, J.

    1987-01-01

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

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

    Science.gov (United States)

    2002-01-01

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

  5. Spectroscopic imaging technologies for online food safety and sanitation inspection

    Science.gov (United States)

    The Environmental Microbial and Food Safety Laboratory, ARS, USDA is one of the leading groups for the development of optoelectronic sensing technologies and methodologies for food quality, safety, and sanitation inspection. High throughput hyperspectral and multispectral imaging techniques use Ram...

  6. Aviation safety and operation problems research and technology

    Science.gov (United States)

    Enders, J. H.; Strickle, J. W.

    1977-01-01

    Aircraft operating problems are described for aviation safety. It is shown that as aircraft technology improves, the knowledge and understanding of operating problems must also improve for economics, reliability and safety.

  7. Safety philosophy and safety technology of the Soviet RBMK reactors

    International Nuclear Information System (INIS)

    Zuend, H.; Jarvis, A.S.; Haennis, H.P.; Tikal, J.

    1986-01-01

    Safety requirements and control in USSR are outlined. Safety criteria and practical application in the case of the RBMK type reactor Chernobyl-4 are discussed. An overview of the Chernobyl-4 reactor accident including its causes is given. Measures to improve the safety of RBMK reactors are described

  8. Investigation on safety of gel decontamination technology

    International Nuclear Information System (INIS)

    Liu Zhihui; Song Fengli; Wang Yongxian; Zhang Taoge

    2014-01-01

    Gel decontamination technology is an advanced decontamination process of metal contaminated by radionuclide. It has the advantages such as simple operation process, high decontaminating factor, etc. But the disadvantages are that it has high spraying pressure and is strongly corrosive, which has safety risk to the operator and equipment. The effect of such factors as spraying pressure on operators was analyzed based on process feature, and it is proposed that it be worthwhile to make further study on the corrosion of gels to spraying equipment, taking into account corrosion feature of gels to stainless steel. Meanwhile, the safety issue was demonstrated on collecting and handling wastes from gel decontamination process. And then, protective measures, study methods, and solutions are put forward. The results show that protection should be strengthened during spraying to reduce the effect of splashing and fogging on workers; the equipment should be cleaned in time to reduce the effect of corrosion, and reducers should be added into waste liquid to eliminate the effect of residual detergent. (authors)

  9. Development of Realistic Safety Analysis Technology for CANDU Reactors

    International Nuclear Information System (INIS)

    Park, Joo Hwan; Rhee, B. W.; Rho, G. H.

    2010-04-01

    The following 3 research items have been studied to develop and establish the realistic safety analysis and the associated technologies for a CANDU reactor. At the first, WIMS-CANDU which is physics cell code for a CANDU has been improved and validated against the physics criticality experiment data transferred through the international cooperation programs. Also an improved physics model to take into account the pressure tube creep was developed and utilized to assess the effects of the pressure tube creep of 0%, 2.5% and 5% diametral increase of pressure tube on core physics parameters. Secondly, the interfacing module between physics and thermal-hydraulics codes has been developed to provide the enhancement of reliability and convenience of the calculation results of the physics parameters such as power coefficient which was calculated by independent code systems. Finally, the important parameters related to the complex heat transfer mechanisms in the crept pressure tubes were identified to find how to improve the existing fuel channel models. One of the important parameters such as the oxidation model of Zr-steam reaction was identified, implemented and verified with the experimental data of the high pressure and temperature fuel channel and its model was utilized for CFD analysis of the crept pressure tube effect on the reactor safety. The results were also provided to validate the CATNENA models of the crept pressure tube and the effects of the pressure tube creep on the blowdown and post-blowdown phase during LOCA was assessed. The results of this study can be used to assess the uncertainty analysis of coolant void reactivity and the effects of the creep deformed pressure tubes on physics/TH/safety issues. Also, those results will be used to improve the current design and operational safety analysis codes, and to technically support the related issues to resolve their problems

  10. 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.

  11. 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.

  12. How Developments in Psychology and Technology Challenge Validity Argumentation

    Science.gov (United States)

    Mislevy, Robert J.

    2016-01-01

    Validity is the sine qua non of properties of educational assessment. While a theory of validity and a practical framework for validation has emerged over the past decades, most of the discussion has addressed familiar forms of assessment and psychological framings. Advances in digital technologies and in cognitive and social psychology have…

  13. Development of inspection safety evaluation technology

    Energy Technology Data Exchange (ETDEWEB)

    Yoon, Seok Chul; Yoon, Yeo Chang; Kim, Jong Soo; Lee, Tae Young; Kim, Chang Ryol; Lee, Hyung Sub; Kim, Jong Soo

    1995-12-01

    The purpose of this project is to protection nation inspector`s over exposure from radiation that can be occurred by inspection activity at nuclear facilities and its environment, and to ensure the safety of inspection activity at the nuclear facilities. To effectively carry out the domestic inspection task to be enforced from 1996, the evaluation for special radiation exposure rate of nuclear facilities, air and surface contamination level, and measurement and monitoring of water contamination level were made to determine whether these measured values exceeded permissible limitations, and to protect the inspector`s over exposure from radiation at domestic nuclear facilities. Management of inspector`s exposure was carried out under assistance of the Department of Health Physics. Performance tests of two gamma detectors, one neutron detector, alpha and beta detector, and gamma spectroscopy analyzer were carried out to control dose on extremity, the characteristic test for extremity dosimeter was carried out and the theoretical calculation of gamma dose conversion factors based on ANSI N13.32 standard was performed. Under the 93+2 program, IAEA began to recognize the necessity of environmental observation technology development of air-borne particulates travelled from long distance location. Associated with the necessity of this technology development, a proposal of international joint research for development of the special radiation measurement and analysis has been prepared. (author). 21 tabs., 24 figs., 20 refs.

  14. The KNICS approach for verification and validation of safety software

    International Nuclear Information System (INIS)

    Cha, Kyung Ho; Sohn, Han Seong; Lee, Jang Soo; Kim, Jang Yeol; Cheon, Se Woo; Lee, Young Joon; Hwang, In Koo; Kwon, Kee Choon

    2003-01-01

    This paper presents verification and validation (VV) to be approached for safety software of POSAFE-Q Programmable Logic Controller (PLC) prototype and Plant Protection System (PPS) prototype, which consists of Reactor Protection System (RPS) and Engineered Safety Features-Component Control System (ESF-CCS) in development of Korea Nuclear Instrumentation and Control System (KNICS). The SVV criteria and requirements are selected from IEEE Std. 7-4.3.2, IEEE Std. 1012, IEEE Std. 1028 and BTP-14, and they have been considered for acceptance framework to be provided within SVV procedures. SVV techniques, including Review and Inspection (R and I), Formal Verification and Theorem Proving, and Automated Testing, are applied for safety software and automated SVV tools supports SVV tasks. Software Inspection Support and Requirement Traceability (SIS-RT) supports R and I and traceability analysis, a New Symbolic Model Verifier (NuSMV), Statemate MAGNUM (STM) ModelCertifier, and Prototype Verification System (PVS) are used for formal verification, and McCabe and Cantata++ are utilized for static and dynamic software testing. In addition, dedication of Commercial-Off-The-Shelf (COTS) software and firmware, Software Safety Analysis (SSA) and evaluation of Software Configuration Management (SCM) are being performed for the PPS prototype in the software requirements phase

  15. Validation study of safety assessment model for radioactive waste disposal

    Energy Technology Data Exchange (ETDEWEB)

    Munakata, Masahiro; Takeda, Seiji; Kimura, Hideo [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    2001-12-01

    The JAERI-AECL collaboration research program has been conducted to validate a groundwater flow and radionuclide transport models for safety assessment. JAERI have developed a geostatistical model for radionuclide transport through a heterogeneous geological media and verify using experimental results of field tracer tests. The simulated tracer plumes explain favorably the experimental tracer plumes. A regional groundwater flow and transport model using site-scale parameter obtained from tracer tests have been verified by comparing simulation results with observation ones of natural environmental tracer. (author)

  16. Building Technologies Program Multi-Year Program Plan Technology Validation and Market Introduction 2008

    Energy Technology Data Exchange (ETDEWEB)

    None, None

    2008-01-01

    Building Technologies Program Multi-Year Program Plan 2008 for technology validation and market introduction, including ENERGY STAR, building energy codes, technology transfer application centers, commercial lighting initiative, EnergySmart Schools, EnergySmar

  17. Safety improvement technologies for nuclear power generation

    International Nuclear Information System (INIS)

    Nishida, Koji; Adachi, Hirokazu; Kinoshita, Hirofumi; Takeshi, Noriaki; Yoshikawa, Kazuhiro; Itou, Kanta; Kurihara, Takao; Hino, Tetsushi

    2015-01-01

    As the Hitachi Group's efforts in nuclear power generation, this paper explains the safety improvement technologies that are currently under development or promotion. As efforts for the decommissioning of Fukushima Daiichi Nuclear Power Station, the following items have been developed. (1) As for the spent fuel removal of Unit 4, the following items have mainly been conducted: removal of the debris piled up on the top surface of existing reactor building (R/B), removal of the debris deposited in spent fuel pool (SFP), and fuel transfer operation by means of remote underwater work. The removal of all spent fuels was completed in 2014. (2) The survey robots inside R/B, which are composed of a basement survey robot to check leaking spots at upper pressure suppression chamber and a floor running robot to check leaking spots in water, were verified with a field demonstration test at Unit 1. These robots were able to find the leaking spots at midair pipe expansion joint. (3) As the survey robot for reactor containment shells, robots of I-letter posture and horizontal U-letter posture were developed, and the survey on the upper part of first-floor grating inside the containment shells was performed. (4) As the facilities for contaminated water measures, sub-drain purification equipment, Advanced Liquid Processing System, etc. were developed and supplied, which are now showing good performance. On the other hand, an advanced boiling water reactor with high safety of the United Kingdom (UK ABWR) is under procedure of approval for introduction. In addition, a next-generation light-water reactor of transuranic element combustion type is under development. (A.O.)

  18. Advanced nuclear reactor safety design technology research in NPIC

    International Nuclear Information System (INIS)

    Yu, H.

    2014-01-01

    After the Fukushima accident happen, Nuclear Power Plants (NPPs) construction has been suspended in China for a time. Now the new regulatory rule has been proposed that the most advanced safety standard must be adopted for the new NPPs and practical elimination of large fission product release by design during the next five plans period. So the advanced reactor research is developing in China. NPIC is engaging on the ACP1000 and ACP100 (Small Module Reactor) design. The main design character will be introduced in this paper. The Passive Combined with Active (PCWA) design was adopted during the ACP1000 design to reduce the core damage frequency (CDF); the Cavity Injection System (CIS) is design to mitigation the consequence of the severe accident. Advance passive safety system was designed to ensure the long term residual heat removal during the Small Module Reactor (SMR). The SMR will be utilized to be the floating reactors, district heating reactor and so on. Besides, the Science and Technology on Reactor System Design Technology Laboratory (LRSDT) also engaged on the fundamental thermal-hydraulic characteristic research in support of the system validation. (author)

  19. System code improvements for modelling passive safety systems and their validation

    Energy Technology Data Exchange (ETDEWEB)

    Buchholz, Sebastian; Cron, Daniel von der; Schaffrath, Andreas [Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) gGmbH, Garching (Germany)

    2016-11-15

    GRS has been developing the system code ATHLET over many years. Because ATHLET, among other codes, is widely used in nuclear licensing and supervisory procedures, it has to represent the current state of science and technology. New reactor concepts such as Generation III+ and IV reactors and SMR are using passive safety systems intensively. The simulation of passive safety systems with the GRS system code ATHLET is still a big challenge, because of non-defined operation points and self-setting operation conditions. Additionally, the driving forces of passive safety systems are smaller and uncertainties of parameters have a larger impact than for active systems. This paper addresses the code validation and qualification work of ATHLET on the example of slightly inclined horizontal heat exchangers, which are e. g. used as emergency condensers (e. g. in the KERENA and the CAREM) or as heat exchanger in the passive auxiliary feed water systems (PAFS) of the APR+.

  20. 78 FR 11902 - Review of Gun Safety Technologies

    Science.gov (United States)

    2013-02-20

    ... DEPARTMENT OF JUSTICE Office of Justice Programs [OJP (NIJ) Docket No. 1615] Review of Gun Safety...'s Plan to reduce gun violence released on January 16, 2013, the U.S. Department of Justice, Office... emerging gun safety technologies and plans to issue a report on the availability and use of those...

  1. Proceedings of the Third Scientific Presentation on Reactor Safety Technology

    International Nuclear Information System (INIS)

    1998-01-01

    These proceedings contains the results of research and development on reactor safety technology which carried out by Reactor Safety Technology Centre, National Atomic Energy Agency, Serpong, Indonesia during 1997/1998 fiscal year. The presentation was held on 13-14 May 1998 at Serpong,Indonesia

  2. Proceeding of the Eighth Scientific Presentation on Nuclear Safety Technology

    International Nuclear Information System (INIS)

    Geni Rina Sunaryo; Sony Tjahjani, D.T.; Anhar Riza Antariksawan; Sudarno; Djoko Hari Nugroho; Roziq Himawan; Ari Satmoko; Histori; Sumijanto

    2003-02-01

    The Proceeding of Scientific Meeting and Presentation is routine activity that held in National Nuclear Energy Agency (BATAN) by Centre for Development of Nuclear Safety Technology for monitoring the research activity which was achieved in BATAN. The aims of the proceeding to able to information and reference for nuclear safety technology. There are 30 papers which separated index. (PPIN)

  3. Occupational Safety Review of High Technology Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Lee Cadwallader

    2005-01-31

    This report contains reviews of operating experiences, selected accident events, and industrial safety performance indicators that document the performance of the major US DOE magnetic fusion experiments and particle accelerators. These data are useful to form a basis for the occupational safety level at matured research facilities with known sets of safety rules and regulations. Some of the issues discussed are radiation safety, electromagnetic energy exposure events, and some of the more widespread issues of working at height, equipment fires, confined space work, electrical work, and other industrial hazards. Nuclear power plant industrial safety data are also included for comparison.

  4. 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

  5. Development Trends in Nuclear Technology and Related Safety Aspects

    International Nuclear Information System (INIS)

    Kuczera, B.; Juhn, P.E.; Fukuda, K.

    2002-01-01

    The IAEA Safety Standards Series include, in a hierarchical manner, the categories of Safety Fundamentals, Safety Requirements and Safety Guides, which define the elements necessary to ensure the safety of nuclear installations. In the same way as nuclear technology and scientific knowledge advance continuously, also safety requirements may change with these advances. Therefore, in the framework of the International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO) one important aspect among others refers to user requirements on the safety of innovative nuclear installations, which may come into operation within the next fifty years. In this respect, the major objectives of the INPRO sub-task 'User Requirements and Nuclear Energy Development Criteria in the Area of Safety' have been: a. to overview existing national and international requirements in the safety area, b. to define high level user requirements in the area of safety of innovative nuclear technologies, c. to compile and to analyze existing innovative reactor and fuel cycle technology enhancement concepts and approaches intended to achieve a high degree of safety, and d. to identify the general areas of safety R and D needs for the establishment of these technologies. During the discussions it became evident that the application of the defence in depth strategy will continue to be the overriding approach for achieving the general safety objective in nuclear power plants and fuel cycle facilities, where the emphasis will be shifted from mitigation of accident consequences more towards prevention of accidents. In this context, four high level user requirements have been formulated for the safety of innovative nuclear reactors and fuel cycles. On this basis safety strategies for innovative reactor designs are highlighted in each of the five levels of defence in depth and specific requirements are discussed for the individual components of the fuel cycle. (authors)

  6. Application of verification and validation on safety parameter display systems

    International Nuclear Information System (INIS)

    Thomas, N.C.

    1983-01-01

    Offers some explanation of how verification and validation (VandV) can support development and licensing of the Safety Parameter Display Systems (SPDS). Advocates that VandV can be more readily accepted within the nuclear industry if a better understanding exists of what the objectives of VandV are and should be. Includes a discussion regarding a reasonable balance of costs and benefits of VandV as applied to the SPDS and to other digital systems. Represents the author's perception of the regulator's perspective based on background information and experience, and discussions with regulators about their current concerns and objectives. Suggests that the introduction of the SPDS into the Control Room is a first step towards growing dependency on use of computers

  7. Introduction into the nuclear safety technologies

    International Nuclear Information System (INIS)

    Nosovskij, A.V.; Vasil'chenko, V.M.; Pavlenko, A.A.; Pis'mennyj, E.N.; Shirokov, S.V.

    2006-01-01

    The theoretical and practical issues of the power and research nuclear reactor safety existing on the territory of Ukraine, the radwaste and nuclear material management objects, as well as the 'Shelter' object, the aspects of the nuclear and radiation safety regulation are considered

  8. Validation of CFD models for hydrogen safety application

    International Nuclear Information System (INIS)

    Nikolaeva, Anna; Skibin, Alexander; Krutikov, Alexey; Golibrodo, Luka; Volkov, Vasiliy; Nechaev, Artem; Nadinskiy, Yuriy

    2015-01-01

    Most accidents involving hydrogen begin with its leakage and spreading in the air and spontaneous detonation, which is accompanied by fire or deflagration of hydrogen mixture with heat and /or shocks, which may cause harm to life and equipment. Outflow of hydrogen in a confined volume and its propagation in the volume is the worst option because of the impact of the insularity on the process of detonation. According to the safety requirements for handling hydrogen specialized systems (ventilation, sprinklers, burners etc.) are required for maintaining the hydrogen concentration less than the critical value, to eliminate the possibility of detonation and flame propagation. In this study, a simulation of helium propagation in a confined space with different methods of injection and ventilation of helium is presented, which is used as a safe replacement of hydrogen in experimental studies. Five experiments were simulated in the range from laminar to developed turbulent with different Froude numbers, which determine the regime of the helium outflow in the air. The processes of stratification and erosion of helium stratified layer were investigated. The study includes some results of OECD/NEA-PSI PANDA benchmark and some results of Gamelan project. An analysis of applicability of various turbulence models, which are used to close the system of equations of momentum transport, implemented in the commercial codes STAR CD, STAR CCM+, ANSYS CFX, was conducted for different mesh types (polyhedral and hexahedral). A comparison of computational studies results with experimental data showed a good agreement. In particular, for transition and turbulent regimes the error of the numerical results lies in the range from 5 to 15% for all turbulence models considered. This indicates applicability of the methods considered for some hydrogen safety problems. However, it should be noted that more validation research should be made to use CFD in Hydrogen safety applications with a wide

  9. Validating Advanced Supply-Chain Technology (VAST)

    Science.gov (United States)

    2004-06-01

    Use philosophy that is so important in today’s procurement environment. Electronic Data Interchange (EDI) and eCommerce is proving to be a major...the STEPwise methodology are particularly encouraging. These new EDI and eCommerce technologies are becoming more important with the customers who...critical assumption is based upon the 55 fact that eCommerce is growing throughout the commercial and military sector and those who are not

  10. Validating a Technology Enhanced Student-Centered Learning Model

    Science.gov (United States)

    Kang, Myunghee; Hahn, Jungsun; Chung, Warren

    2015-01-01

    The Technology Enhanced Student Centered Learning (TESCL) Model in this study presents the core factors that ensure the quality of learning in a technology-supported environment. Although the model was conceptually constructed using a student-centered learning framework and drawing upon previous studies, it should be validated through real-world…

  11. Advanced Energy Validated Photovoltaic Inverter Technology at NREL | Energy

    Science.gov (United States)

    Inverter Technology at NREL Advanced Energy Industries-NREL's first partner at the Energy Systems Integration Facility (ESIF)-validated its advanced photovoltaic (PV) inverter technology using the ESIF's computer screen in a laboratory, with power inverter hardware in the background Photo by Dennis Schroeder

  12. Development of safety analysis technology for LMR

    International Nuclear Information System (INIS)

    Hahn, Do Hee; Kwon, Y. M.; Kim, K. D.

    2000-05-01

    The analysis methodologies as well as the analysis computer code system for the transient, HCDA, and containment performance analyses, which are required for KALIMER safety analyses, have been developed. The SSC-K code has been developed based on SSC-L which is an analysis code for loop type LMR, by improving models necessary for the KALIMER system analysis, and additional models have been added to the code. In addition, HCDA analysis model has been developed and the containment performance analysis code has been also improved. The preliminary basis for the safety analysis has been established, and the preliminary safety analyses for the key design features have been performed. In addition, a state-of-art analysis for LMR PSA and overseas safety and licensing requirements have been reviewed. The design database for the systematic management of the design documents as well as design processes has been established as well

  13. Sensor technology for hazardous cargo transportation safety.

    Science.gov (United States)

    2013-08-01

    The overall goal of this research project was to develop oxidant vapor detection devices that can be : used to ensure the safety of hazardous freight transportation systems. Two nanotechnology-based : systems originally developed for improvised explo...

  14. Development of safety analysis technology for LMR

    Energy Technology Data Exchange (ETDEWEB)

    Hahn, Do Hee; Kwon, Y. M.; Kim, K. D. [and others

    2000-05-01

    The analysis methodologies as well as the analysis computer code system for the transient, HCDA, and containment performance analyses, which are required for KALIMER safety analyses, have been developed. The SSC-K code has been developed based on SSC-L which is an analysis code for loop type LMR, by improving models necessary for the KALIMER system analysis, and additional models have been added to the code. In addition, HCDA analysis model has been developed and the containment performance analysis code has been also improved. The preliminary basis for the safety analysis has been established, and the preliminary safety analyses for the key design features have been performed. In addition, a state-of-art analysis for LMR PSA and overseas safety and licensing requirements have been reviewed. The design database for the systematic management of the design documents as well as design processes has been established as well.

  15. 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.

  16. Elaboration and Validation of the Medication Prescription Safety Checklist.

    Science.gov (United States)

    Pires, Aline de Oliveira Meireles; Ferreira, Maria Beatriz Guimarães; Nascimento, Kleiton Gonçalves do; Felix, Márcia Marques Dos Santos; Pires, Patrícia da Silva; Barbosa, Maria Helena

    2017-08-03

    to elaborate and validate a checklist to identify compliance with the recommendations for the structure of medication prescriptions, based on the Protocol of the Ministry of Health and the Brazilian Health Surveillance Agency. methodological research, conducted through the validation and reliability analysis process, using a sample of 27 electronic prescriptions. the analyses confirmed the content validity and reliability of the tool. The content validity, obtained by expert assessment, was considered satisfactory as it covered items that represent the compliance with the recommendations regarding the structure of the medication prescriptions. The reliability, assessed through interrater agreement, was excellent (ICC=1.00) and showed perfect agreement (K=1.00). the Medication Prescription Safety Checklist showed to be a valid and reliable tool for the group studied. We hope that this study can contribute to the prevention of adverse events, as well as to the improvement of care quality and safety in medication use. elaborar e validar um instrumento tipo checklist para identificar a adesão às recomendações na estrutura das prescrições de medicamentos, a partir do Protocolo do Ministério da Saúde e Agência Nacional de Vigilância Sanitária. pesquisa metodológica, conduzida por meio do processo de validade e análise de confiabilidade, com amostra de 27 prescrições eletrônicas. análises realizadas confirmaram a validade de conteúdo e a confiabilidade da versão do instrumento. A validade de conteúdo, obtida por meio da avaliação de juízes, foi considerada satisfatória por contemplar itens que representam a adesão às recomendações na estrutura das prescrições de medicamentos. A confiabilidade, avaliada por interobservadores, apresentou-se excelente (ICC=1,00) e de concordância perfeita (K=1,00). o instrumento Lista de Verificação de Segurança na Prescrição de Medicamentos demonstrou-se válido e confiável para o grupo estudado. Espera

  17. Applying Sensor-Based Technology to Improve Construction Safety Management.

    Science.gov (United States)

    Zhang, Mingyuan; Cao, Tianzhuo; Zhao, Xuefeng

    2017-08-11

    Construction sites are dynamic and complicated systems. The movement and interaction of people, goods and energy make construction safety management extremely difficult. Due to the ever-increasing amount of information, traditional construction safety management has operated under difficult circumstances. As an effective way to collect, identify and process information, sensor-based technology is deemed to provide new generation of methods for advancing construction safety management. It makes the real-time construction safety management with high efficiency and accuracy a reality and provides a solid foundation for facilitating its modernization, and informatization. Nowadays, various sensor-based technologies have been adopted for construction safety management, including locating sensor-based technology, vision-based sensing and wireless sensor networks. This paper provides a systematic and comprehensive review of previous studies in this field to acknowledge useful findings, identify the research gaps and point out future research directions.

  18. Business of Nuclear Safety Analysis Office, Nuclear Technology Test Center

    International Nuclear Information System (INIS)

    Hayakawa, Masahiko

    1981-01-01

    The Nuclear Technology Test Center established the Nuclear Safety Analysis Office to execute newly the works concerning nuclear safety analysis in addition to the works related to the proving tests of nuclear machinery and equipments. The regulations for the Nuclear Safety Analysis Office concerning its organization, business and others were specially decided, and it started the business formally in August, 1980. It is a most important subject to secure the safety of nuclear facilities in nuclear fuel cycle as the premise of developing atomic energy. In Japan, the strict regulation of safety is executed by the government at each stage of the installation, construction, operation and maintenance of nuclear facilities, based on the responsibility for the security of installers themselves. The Nuclear Safety Analysis Office was established as the special organ to help the safety examination related to the installation of nuclear power stations and others by the government. It improves and puts in order the safety analysis codes required for the cross checking in the safety examination, and carries out safety analysis calculation. It is operated by the cooperation of the Science and Technology Agency and the Agency of Natural Resources and Energy. The purpose of establishment, the operation and the business of the Nuclear Safety Analysis Office, the plan of improving and putting in order of analysis codes, and the state of the similar organs in foreign countries are described. (Kako, I.)

  19. Alternative food safety intervention technologies: flash pasteurization of finfish

    Science.gov (United States)

    Alternative nonthermal and thermal food safety interventions are gaining acceptance by the food processing industry and consumers. These technologies include high pressure processing, ultraviolet and pulsed light, ionizing radiation, pulsed and radiofrequency electric fields, cold atmospheric plasm...

  20. Understanding Student Teachers' Behavioural Intention to Use Technology: Technology Acceptance Model (TAM) Validation and Testing

    Science.gov (United States)

    Wong, Kung-Teck; Osman, Rosma bt; Goh, Pauline Swee Choo; Rahmat, Mohd Khairezan

    2013-01-01

    This study sets out to validate and test the Technology Acceptance Model (TAM) in the context of Malaysian student teachers' integration of their technology in teaching and learning. To establish factorial validity, data collected from 302 respondents were tested against the TAM using confirmatory factor analysis (CFA), and structural equation…

  1. Tests for validation of fast neutron reactors safety

    International Nuclear Information System (INIS)

    Nagata, T.; Yamashita, H.

    2001-01-01

    Japanese scientific research and design enterprises in cooperation with industrial and power generating corporations implement a project on creating a fast neutron reactor of the ultimate safety. One of the basic expected results from such a development is creation of a reactor core structure that is able to eliminate recriticality occurrence in the course of reactor accident involving fuel melting. One of the possible ways to solve this problem is to include pipes (meant for specifying directed (controlled) molten fuel relocation) into fuel assembly structure. In the course of conduction and subsequent implementation of such a design the basic issue is to experimentally confirm the operating capacity of FA having such a structure and that is called FAIDUS. Within EAGLE Project on experimental basis of IAE NNC RK an activity has been started on preparation and conduction of out-of-pile and in-pile tests. During tests a sodium coolant will be used. Studies are conducted by NNC RK in cooperation with the Japanese corporations JAPC and JNC. Basic objective of out-of-pile tests was to obtain preliminary information on fuel relocation behavior under conditions simulating accident involving melting of core consisting of FAIDUS FA, which will help to clarify simulation criteria and to develop the most optimum structure of the experimental channel for reactor experiments conduction. The basic objective of in-pile tests was the experimental confirmation of operating capacity of FAIDUS FA model under reactor conditions. According to the program two tests are planned to be performed at IGR reactor: tests for validation of fast neutron reactor safety, and out-of-pile tests at EAGLE experimental facility without sodium coolant

  2. A verified and efficient approach towards fatigue validation of safety parts

    Energy Technology Data Exchange (ETDEWEB)

    Weihe, Stefan; Weigel, Nicolas [Daimler AG, Stuttgart (Germany); Dressler, Klaus; Speckert, Michael; Feth, Sascha

    2011-07-01

    In the automotive industry, safety parts must be designed according to the state of the art of science and technology such that they do not fail as long as the vehicle is used according to its purpose and misuse of the vehicle does not exceed a reasonably expectable degree. Due to scatter in customer loads and component properties, fatigue validation needs to be based on statistical methods. Mathematically sound methods are devised in order to make the validation process as efficient as possible. They allow considering all test results, including censored test data (e.g. tests suspended due to premature failure of components which are not under consideration). Furthermore, these methods permit adapting the success run criterion successively to the testing process. (orig.)

  3. Patient safety and technology-driven medication

    DEFF Research Database (Denmark)

    Orbæk, Janne; Gaard, Mette; Keinicke Fabricius, Pia

    2015-01-01

    ways of educating nursing students in today's medication administration. AIM: To explore nursing students' experiences and competences with the technology-driven medication administration process. METHODS: 16 pre-graduate nursing students were included in two focus group interviews which were recorded...... for the technology-driven medication process, nursing students face difficulties in identifying and adopting best practices. The impact of using technology on the frequency, type and severity of medication errors; the technologies implications on nursing professionalism and the nurses ability to secure patient...

  4. Adaption and validation of the Safety Attitudes Questionnaire for the Danish hospital setting

    Directory of Open Access Journals (Sweden)

    Kristensen S

    2015-02-01

    Full Text Available Solvejg Kristensen,1–3 Svend Sabroe,4 Paul Bartels,1,5 Jan Mainz,3,5 Karl Bang Christensen6 1The Danish Clinical Registries, Aarhus, Denmark; 2Department of Health Science and Technology, Aalborg University, Aalborg, Denmark; 3Aalborg University Hospital, Psychiatry, Aalborg, Denmark; 4Department of Public Health, Aarhus University, Aarhus, Denmark; 5Department of Clinical Medicine, Aalborg University, Aalborg, Denmark; 6Department of Biostatistics, University of Copenhagen, Copenhagen, Denmark Purpose: Measuring and developing a safe culture in health care is a focus point in creating highly reliable organizations being successful in avoiding patient safety incidents where these could normally be expected. Questionnaires can be used to capture a snapshot of an employee's perceptions of patient safety culture. A commonly used instrument to measure safety climate is the Safety Attitudes Questionnaire (SAQ. The purpose of this study was to adapt the SAQ for use in Danish hospitals, assess its construct validity and reliability, and present benchmark data.Materials and methods: The SAQ was translated and adapted for the Danish setting (SAQ-DK. The SAQ-DK was distributed to 1,263 staff members from 31 in- and outpatient units (clinical areas across five somatic and one psychiatric hospitals through meeting administration, hand delivery, and mailing. Construct validity and reliability were tested in a cross-sectional study. Goodness-of-fit indices from confirmatory factor analysis were reported along with inter-item correlations, Cronbach's alpha (α, and item and subscale scores.Results: Participation was 73.2% (N=925 of invited health care workers. Goodness-of-fit indices from the confirmatory factor analysis showed: c2=1496.76, P<0.001, CFI 0.901, RMSEA (90%CI 0.053 (0.050-0056, Probability RMSEA (p close=0.057. Inter-scale correlations between the factors showed moderate-to-high correlations. The scale stress recognition had significant

  5. Flightdeck Automation Problems (FLAP) Model for Safety Technology Portfolio Assessment

    Science.gov (United States)

    Ancel, Ersin; Shih, Ann T.

    2014-01-01

    NASA's Aviation Safety Program (AvSP) develops and advances methodologies and technologies to improve air transportation safety. The Safety Analysis and Integration Team (SAIT) conducts a safety technology portfolio assessment (PA) to analyze the program content, to examine the benefits and risks of products with respect to program goals, and to support programmatic decision making. The PA process includes systematic identification of current and future safety risks as well as tracking several quantitative and qualitative metrics to ensure the program goals are addressing prominent safety risks accurately and effectively. One of the metrics within the PA process involves using quantitative aviation safety models to gauge the impact of the safety products. This paper demonstrates the role of aviation safety modeling by providing model outputs and evaluating a sample of portfolio elements using the Flightdeck Automation Problems (FLAP) model. The model enables not only ranking of the quantitative relative risk reduction impact of all portfolio elements, but also highlighting the areas with high potential impact via sensitivity and gap analyses in support of the program office. Although the model outputs are preliminary and products are notional, the process shown in this paper is essential to a comprehensive PA of NASA's safety products in the current program and future programs/projects.

  6. Interior LED Lighting Technology. Navy Energy Technology Validation (Techval) Program

    Science.gov (United States)

    2015-09-01

    usually on most of the time. • Consider replacing existing CFL, high-intensity discharge (HID), or halogen lamp light fixtures/ lamps with LED fixtures... lamps . What is the Technology? An LED is a semiconductor-diode that emits light when power is applied. A driver is used, much as a ballast, to...available in integrated luminaires that can be used to replace existing luminaires. LEDs are also available as direct replacement lamps for many

  7. Next Generation Public Safety and Emergency Technologies

    DEFF Research Database (Denmark)

    Bonde, Camilla; Tadayoni, Reza; Skouby, Knud Erik

    2014-01-01

    The paper researches the existing European standards for Public Safety and Emergency (PSE) services (also called Public Protection Disaster Relief “PPDR”), and identifies based on user studies in Denmark conflicts between the current deployments of the standards and the user requirements. The aim...

  8. Aviation Safety Program Atmospheric Environment Safety Technologies (AEST) Project

    Science.gov (United States)

    Colantonio, Ron

    2011-01-01

    Engine Icing: Characterization and Simulation Capability: Develop knowledge bases, analysis methods, and simulation tools needed to address the problem of engine icing; in particular, ice-crystal icing Airframe Icing Simulation and Engineering Tool Capability: Develop and demonstrate 3-D capability to simulate and model airframe ice accretion and related aerodynamic performance degradation for current and future aircraft configurations in an expanded icing environment that includes freezing drizzle/rain Atmospheric Hazard Sensing and Mitigation Technology Capability: Improve and expand remote sensing and mitigation of hazardous atmospheric environments and phenomena

  9. Proceedings of the Nuclear Criticality Technology Safety Workshop

    Energy Technology Data Exchange (ETDEWEB)

    Rene G. Sanchez

    1998-04-01

    This document contains summaries of most of the papers presented at the 1995 Nuclear Criticality Technology Safety Project (NCTSP) meeting, which was held May 16 and 17 at San Diego, Ca. The meeting was broken up into seven sessions, which covered the following topics: (1) Criticality Safety of Project Sapphire; (2) Relevant Experiments For Criticality Safety; (3) Interactions with the Former Soviet Union; (4) Misapplications and Limitations of Monte Carlo Methods Directed Toward Criticality Safety Analyses; (5) Monte Carlo Vulnerabilities of Execution and Interpretation; (6) Monte Carlo Vulnerabilities of Representation; and (7) Benchmark Comparisons.

  10. Technological progress, safety, and the guardian role of inspection

    Energy Technology Data Exchange (ETDEWEB)

    Critchley, O H

    1981-08-01

    Technological innovation is accompanied by unforeseen human consequences as well as benefits, and progress has produced a public awareness of the potential for hazards that has led to efficient safety-inspection procedures. Because no safety procedure is foolproof, the public learns to tolerate certain levels of risk from technology if it concludes that the benefits are worthwhile. The perception of values often transcends simple cost/benefit analysis. Safety technology and regulation developed during the past 50 years has benefited from earlier disastrous accidents enough to give the nuclear power industry an unprecedented safety record. Efforts to understand and anticipate human error have refined the role of inspection without achieving absolute reliability. Well-directed inspections that accept human fallibility will achieve more than design and organizational improvements. 42 references. (DCK)

  11. Development and Validation of a Safety Attitude Scale for Coal Miners in China

    Directory of Open Access Journals (Sweden)

    Xiang Wu

    2017-11-01

    Full Text Available Safety attitude is of vital importance to accident prevention, and the high accident rate in the coal mining industry makes it urgent to undertake research on coal miners’ safety attitude. However, the current literature still lacks a valid and reliable safety attitude measurement scale for coal miners, which stands as a barrier against their safety attitude improvement. In this study, a scale is developed that can be used to measure coal miners’ safety attitude. The preliminary scale was based on an extended literature review. Empirical data were then collected from 725 coal miners using the preliminary scale. Both exploratory and confirmatory factor analyses were undertaken to validate and improve the scale. The final scale, which consists of 17 items, contains four dimensions: management safety commitment, team safety climate, fatalism and work pressure. Results show that this safety attitude scale can effectively measure the safety attitude of coal miners, showing high psychological measurement validity. This paper contributes to the occupational safety research by developing the factor structure and indicator system of coal miners’ safety attitude, thus providing more profound interpretation of this crucial construct in the safety research domain. The measurement scale serves as an important tool for safety attitude benchmarking among different coal mining enterprises and, thus, can boost the overall safety improvement of the whole industry. These findings can facilitate improvement of both theories and practices related to occupational safety attitude.

  12. 75 FR 21602 - Online Safety and Technology Working Group Meeting

    Science.gov (United States)

    2010-04-26

    ... OSTWG is tasked with evaluating industry efforts to promote a safe online environment for children. The... and Technology Working Group Meeting AGENCY: National Telecommunications and Information... public meeting of the Online Safety and Technology Working Group (OSTWG). DATES: The meeting will be held...

  13. 75 FR 1338 - Online Safety and Technology Working Group Meeting

    Science.gov (United States)

    2010-01-11

    ... promote a safe online environment for children. The Act requires the OSTWG to report its findings and... and Technology Working Group Meeting AGENCY: National Telecommunications and Information... public meeting of the Online Safety and Technology Working Group (OSTWG). DATES: The meeting will be held...

  14. National Center for Food Safety and Technology

    Science.gov (United States)

    2013-12-05

    on the Determination of Copper, Iron, Manganese and Zinc in Beef and Goat Liver American Chemical Society (ACS) – September, 2013 22. Meng Xu...addresses key food safety issues facing the country and supports the development of safe food with health-promoting properties from farm to fork. This...Reddy, Renate Reimschuessel. 2013. Proficiency Test on the Determination of Copper, Iron, Manganese and Zinc in Beef and Goat Liver American

  15. International safety standards in a technological age

    International Nuclear Information System (INIS)

    Lawrence, D.J.

    1980-01-01

    Plant design, particularly plant involving pipework, is becoming more complex both in engineering sophistication and in scale of project. Simultaneously, the requirement from both environmental and legislative lobbies is in need of greater attention with regard to all aspects of safety. At the heart of both problems is the need for improved communication for speed, relevancy and accuracy. By the use of computer data banks and software specifically designed for the problem, it is shown how modern communications may be used. (author)

  16. Deterministic Safety Technology for RBMK Reactors

    Directory of Open Access Journals (Sweden)

    F. D'Auria

    2008-01-01

    The paper summarizes the activities performed at NIKIET in Moscow and at University of Pisa (UNIPI in Pisa. A top-down approach is pursued in structuring the executive summary that includes the following sections: (i the safety needed for the RBMK NPP, (ii the roadmap, (iii\tthe adopted computational tools, (iv\tkey findings, (v\tEmphasis is given to the multiple pressure tube rupture (MPTR issue and the individual channel monitoring (ICM proposal.

  17. New technologies and worker safety in western agriculture.

    Science.gov (United States)

    Fenske, Richard A

    2009-01-01

    The New Paths: Health and Safety in Western Agriculture conference, November 11-13, 2008, highlighted the role of technological innovation in agricultural production. The tree fruit industry in the Pacific Northwest has adopted a "technology road map" to reduce production costs and improve efficiency. An agricultural tour provided field demonstrations and discussions on such topics as mobile work platforms in orchards, traumatic and musculoskeletal injuries, and new pest control technologies. Occupational safety and health research will need to adapt to and keep pace with rapid changes in agricultural production processes.

  18. The development of integrated safety assessment technology

    International Nuclear Information System (INIS)

    Yoo, Keon Joong; Park, Chang Kyu; Kim, Tae Un; Han, Sang Hoon; Yang, Joon Eon; Lim, Tae Jin; Han, Jae Joo; Je, Moo Seong; An, Kwang Il; Kim, Shi Dal; Jeong, Jong Tae; Jeong, Kwang Seop; Jin, Yeong Ho; Kim, Dong Ha; Kim, Kil Yoo; Cho, Yeong Kyoon; Jeong, Won Dae; Jang, Seung Cheol; Choi, Yeong; Park, Soo Yong; Seong, Tae Yong; Song, Yong Man; Kang, Dae Il; Park, Jin Hee; Jang, Seon Joo; Hwang, Mi Jeong; Choi, Seon Yeong

    1993-05-01

    For the purpose of developing the integrated PSA methodology and computer codes, Level-1 and Level-2 PSA methodology and tools were reviewed and improved. The Level-1 PSA computer code package KIRAP was improved and released by the name of KIRAP Release 2.0 Several Human reliability analysis and common cause failure analysis methods was reviewed and compared. For the development of Level-2 PSA computer code, several level-1 and Level-2 interface methods and containment event tree development methods were reviewed and compared. And the new technology such as artificial intelligence was reviewed if the technology can be applied to the development of PSA methodology.(Author)

  19. Validation of thermal hydraulic codes for fusion reactors safety

    International Nuclear Information System (INIS)

    Sardain, P.; Gulden, W.; Massaut, V.; Takase, K.; Merill, B.; Caruso, G.

    2006-01-01

    A significant effort has been done worldwide on the validation of thermal hydraulic codes, which can be used for the safety assessment of fusion reactors. This work is an item of an implementing agreement under the umbrella of the International Energy Agency. The European part is supported by EFDA. Several programmes related to transient analysis in water-cooled fusion reactors were run in order to assess the capabilities of the codes to treat the main physical phenomena governing the accidental sequences related to water/steam discharge into the vacuum vessel or the cryostat. The typical phenomena are namely the pressurization of a volume at low initial pressure, the critical flow, the flashing, the relief into an expansion volume, the condensation of vapor in a pressure suppression system, the formation of ice on a cryogenic structure, the heat transfer between walls and fluid in various thermodynamic conditions. · A benchmark exercise has been done involving different types of codes, from homogeneous equilibrium to six equations non-equilibrium models. Several cases were defined, each one focusing on a particular phenomenon. · The ICE (Ingress of Coolant Event) facility has been operated in Japan. It has simulated an in-vessel LOCA and the discharge of steam into a pressure suppression system. · The EVITA (European Vacuum Impingement Test Apparatus) facility has been operated in France. It has simulated ingress of coolant into the cryostat, i.e. into a volume at low initial pressure containing surfaces at cryogenic temperature. This paper gives the main lessons gained from these programs, in particular the possibilities for the improvement of the computer codes, extending their capabilities. For example, the water properties have been extended below the triple point. Ice formation models have been implemented. Work has also been done on condensation models. The remaining needs for R-and-D are also highlighted. (author)

  20. Development of Safety Analysis Technology for Integral Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Sim, S. K. [Korea Atomic Energy Research Institute, Taejeon (Korea); Seul, K. W.; Kim, W. S.; Kim, W. K.; Yun, Y. G.; Ahn, H. J.; Lee, J. S.; Sin, A. D. [Korea Institute of Nuclear Safety, Taejeon (Korea)

    2000-03-01

    The Nuclear Desalination Plant(NDP) is being developed to produce electricity and fresh water, and is expected to locate near population zone. In the aspect of safety, it is required to protect the public and environment from the possible releases of fission products and to prevent the fresh water from the contamination of radioactivity. Thus, in a present study, the safety characteristics of the integral reactor adopting passive and inherent safety features significantly different from existing nuclear power plants were investigated based on the design of foreign and domestic integral reactors. Also, safety requirements applicable to the NDP were analyzed based on the regulatory requirements for current and advanced reactor designs, and use requirements for small-medium size reactors. Based on these analyses, some safety concerns to be considered in the design stage have been identified. They includes the use of proven technology for new safety systems, the systematic classification and selection of design basis accidents, and the safety assurance of desalination-related systems. These efforts to identify and resolve the safety concerns in the design stage will provide the early confidence of SMART safety to designers, and the technical basis to evaluate the safety to reviewers in the future. 8 refs., 20 figs., 4 tabs. (Author)

  1. Workforce perceptions of hospital safety culture: development and validation of the patient safety climate in healthcare organizations survey.

    Science.gov (United States)

    Singer, Sara; Meterko, Mark; Baker, Laurence; Gaba, David; Falwell, Alyson; Rosen, Amy

    2007-10-01

    To describe the development of an instrument for assessing workforce perceptions of hospital safety culture and to assess its reliability and validity. Primary data collected between March 2004 and May 2005. Personnel from 105 U.S. hospitals completed a 38-item paper and pencil survey. We received 21,496 completed questionnaires, representing a 51 percent response rate. Based on review of existing safety climate surveys, we developed a list of key topics pertinent to maintaining a culture of safety in high-reliability organizations. We developed a draft questionnaire to address these topics and pilot tested it in four preliminary studies of hospital personnel. We modified the questionnaire based on experience and respondent feedback, and distributed the revised version to 42,249 hospital workers. We randomly divided respondents into derivation and validation samples. We applied exploratory factor analysis to responses in the derivation sample. We used those results to create scales in the validation sample, which we subjected to multitrait analysis (MTA). We identified nine constructs, three organizational factors, two unit factors, three individual factors, and one additional factor. Constructs demonstrated substantial convergent and discriminant validity in the MTA. Cronbach's alpha coefficients ranged from 0.50 to 0.89. It is possible to measure key salient features of hospital safety climate using a valid and reliable 38-item survey and appropriate hospital sample sizes. This instrument may be used in further studies to better understand the impact of safety climate on patient safety outcomes.

  2. A Framework for Assessment of Aviation Safety Technology Portfolios

    Science.gov (United States)

    Jones, Sharon M.; Reveley, Mary S.

    2014-01-01

    The programs within NASA's Aeronautics Research Mission Directorate (ARMD) conduct research and development to improve the national air transportation system so that Americans can travel as safely as possible. NASA aviation safety systems analysis personnel support various levels of ARMD management in their fulfillment of system analysis and technology prioritization as defined in the agency's program and project requirements. This paper provides a framework for the assessment of aviation safety research and technology portfolios that includes metrics such as projected impact on current and future safety, technical development risk and implementation risk. The paper also contains methods for presenting portfolio analysis and aviation safety Bayesian Belief Network (BBN) output results to management using bubble charts and quantitative decision analysis techniques.

  3. Modeling the Relationship between Safety Climate and Safety Performance in a Developing Construction Industry: A Cross-Cultural Validation Study.

    Science.gov (United States)

    Zahoor, Hafiz; Chan, Albert P C; Utama, Wahyudi P; Gao, Ran; Zafar, Irfan

    2017-03-28

    This study attempts to validate a safety performance (SP) measurement model in the cross-cultural setting of a developing country. In addition, it highlights the variations in investigating the relationship between safety climate (SC) factors and SP indicators. The data were collected from forty under-construction multi-storey building projects in Pakistan. Based on the results of exploratory factor analysis, a SP measurement model was hypothesized. It was tested and validated by conducting confirmatory factor analysis on calibration and validation sub-samples respectively. The study confirmed the significant positive impact of SC on safety compliance and safety participation , and negative impact on number of self-reported accidents/injuries . However, number of near-misses could not be retained in the final SP model because it attained a lower standardized path coefficient value. Moreover, instead of safety participation , safety compliance established a stronger impact on SP. The study uncovered safety enforcement and promotion as a novel SC factor, whereas safety rules and work practices was identified as the most neglected factor. The study contributed to the body of knowledge by unveiling the deviations in existing dimensions of SC and SP. The refined model is expected to concisely measure the SP in the Pakistani construction industry, however, caution must be exercised while generalizing the study results to other developing countries.

  4. Automated Mixed Traffic Vehicle (AMTV) technology and safety study

    Science.gov (United States)

    Johnston, A. R.; Peng, T. K. C.; Vivian, H. C.; Wang, P. K.

    1978-01-01

    Technology and safety related to the implementation of an Automated Mixed Traffic Vehicle (AMTV) system are discussed. System concepts and technology status were reviewed and areas where further development is needed are identified. Failure and hazard modes were also analyzed and methods for prevention were suggested. The results presented are intended as a guide for further efforts in AMTV system design and technology development for both near term and long term applications. The AMTV systems discussed include a low speed system, and a hybrid system consisting of low speed sections and high speed sections operating in a semi-guideway. The safety analysis identified hazards that may arise in a properly functioning AMTV system, as well as hardware failure modes. Safety related failure modes were emphasized. A risk assessment was performed in order to create a priority order and significant hazards and failure modes were summarized. Corrective measures were proposed for each hazard.

  5. Validating the Danish adaptation of the World Health Organization's International Classification for Patient Safety classification of patient safety incident types

    DEFF Research Database (Denmark)

    Mikkelsen, Kim Lyngby; Thommesen, Jacob; Andersen, Henning Boje

    2013-01-01

    Objectives Validation of a Danish patient safety incident classification adapted from the World Health Organizaton's International Classification for Patient Safety (ICPS-WHO). Design Thirty-three hospital safety management experts classified 58 safety incident cases selected to represent all types.......513 (range: 0.193–0.804). Kappa and ICC showed high correlation (r = 0.99). An inverse correlation was found between the prevalence of type and inter-rater reliability. Results are discussed according to four factors known to determine the inter-rater agreement: skill and motivation of raters; clarity...

  6. International exchange on nuclear safety related expert systems: The role of software verification and validation

    International Nuclear Information System (INIS)

    Sun, B.K.H.

    1996-01-01

    An important lesson learned from the Three Mile Island accident is that human errors can be significant contributors to risk. Recent advancement in computer hardware and software technology helped make expert system techniques potentially viable tools for improving nuclear power plant safety and reliability. As part of the general man-machine interface technology, expert systems have recently become increasingly prominent as a potential solution to a number of previously intractable problems in many phases of human activity, including operation, maintenance, and engineering functions. Traditional methods for testing and analyzing analog systems are no longer adequate to handle the increased complexity of software systems. The role of Verification and Validation (V and V) is to add rigor to the software development and maintenance cycle to guarantee the high level confidence needed for applications. Verification includes the process and techniques for confirming that all the software requirements in one stage of the development are met before proceeding on to the next stage. Validation involves testing the integrated software and hardware system to ensure that it reliably fulfills its intended functions. Only through a comprehensive V and V program can a high level of confidence be achieved. There exist many different standards and techniques for software verification and validation, yet they lack uniform approaches that provides adequate levels of practical guidance which can be used by users for nuclear power plant applications. There is a need to unify different approaches for addressing software verification and validation and to develop practical and cost effective guidelines for user and regulatory acceptance. (author). 8 refs

  7. Validation and Verification of Future Integrated Safety-Critical Systems Operating under Off-Nominal Conditions

    Science.gov (United States)

    Belcastro, Christine M.

    2010-01-01

    Loss of control remains one of the largest contributors to aircraft fatal accidents worldwide. Aircraft loss-of-control accidents are highly complex in that they can result from numerous causal and contributing factors acting alone or (more often) in combination. Hence, there is no single intervention strategy to prevent these accidents and reducing them will require a holistic integrated intervention capability. Future onboard integrated system technologies developed for preventing loss of vehicle control accidents must be able to assure safe operation under the associated off-nominal conditions. The transition of these technologies into the commercial fleet will require their extensive validation and verification (V and V) and ultimate certification. The V and V of complex integrated systems poses major nontrivial technical challenges particularly for safety-critical operation under highly off-nominal conditions associated with aircraft loss-of-control events. This paper summarizes the V and V problem and presents a proposed process that could be applied to complex integrated safety-critical systems developed for preventing aircraft loss-of-control accidents. A summary of recent research accomplishments in this effort is also provided.

  8. Validating an infrared thermal switch as a novel access technology

    Directory of Open Access Journals (Sweden)

    Memarian Negar

    2010-08-01

    Full Text Available Abstract Background Recently, a novel single-switch access technology based on infrared thermography was proposed. The technology exploits the temperature differences between the inside and surrounding areas of the mouth as a switch trigger, thereby allowing voluntary switch activation upon mouth opening. However, for this technology to be clinically viable, it must be validated against a gold standard switch, such as a chin switch, that taps into the same voluntary motion. Methods In this study, we report an experiment designed to gauge the concurrent validity of the infrared thermal switch. Ten able-bodied adults participated in a series of 3 test sessions where they simultaneously used both an infrared thermal and conventional chin switch to perform multiple trials of a number identification task with visual, auditory and audiovisual stimuli. Participants also provided qualitative feedback about switch use. User performance with the two switches was quantified using an efficiency measure based on mutual information. Results User performance (p = 0.16 and response time (p = 0.25 with the infrared thermal switch were comparable to those of the gold standard. Users reported preference for the infrared thermal switch given its non-contact nature and robustness to changes in user posture. Conclusions Thermal infrared access technology appears to be a valid single switch alternative for individuals with disabilities who retain voluntary mouth opening and closing.

  9. TEPSS - Technology Enhancement for Passive Safety Systems

    International Nuclear Information System (INIS)

    Hart, J.; Slegers, W.J.M.; Boer, S.L. de; Huggenberger, M.; Lopez Jimenez, J.; Munoz-Cabo Gonzalez, J.L.; Reventos Puigjaner, F.

    2000-01-01

    The objective of the TEPSS project was to make significant additions to the technology base of the European Simplified Boiling Water Reactor (ESBWR). The project focused on mixing and stratification phenomena in large water pools, passive decay heat removal from containments, and effects of aerosol deposition inside a passive heat exchanger. The PSI experimental facility LINX (Large-scale Investigation of Natural Circulation and Mixing) has been used to investigate venting of steam and steam-noncondensable gas mixtures into water pools. The test revealed that no significant steam bypass could be detected when injecting a mixture of steam or air and that mixing was very efficient. In addition to the tests, 3-D numerical computations and initial model development have been performed to study the behaviour of bubble plumes in water pools. The major part of the TEPSS project studied selective aspects of the response technology of modem pressure-suppression type containment designs and of passive-type decay heat removal systems. The work included an experimental phase using the large-scale experimental facility PANDA (Passive Nachwaermeabfuhr und Druckabbau), operated by PSI, where eight experiments successfully have been executed to test the performance of the ESBWR containment configuration. The PANDA tests have been analysed successfully using thermalhydraulic system analysis codes and 3-D CFD codes. The AIDA (Aerosol Impaction and Deposition Analysis) experimental facility of PSI has been used to investigate the degradation of passive decay heat removal due to fission product aerosols deposited on the inside surfaces of the PCC (Passive Containment Cooler) heat exchanger tubes. The one test performed revealed that the degradation of the heat transfer in the PCC tubes due to the deposition of aerosols reached about 20%. The test has been analysed using the MELCOR severe accident analysis code. (author)

  10. Cross-validation of an employee safety climate model in Malaysia.

    Science.gov (United States)

    Bahari, Siti Fatimah; Clarke, Sharon

    2013-06-01

    Whilst substantial research has investigated the nature of safety climate, and its importance as a leading indicator of organisational safety, much of this research has been conducted with Western industrial samples. The current study focuses on the cross-validation of a safety climate model in the non-Western industrial context of Malaysian manufacturing. The first-order factorial validity of Cheyne et al.'s (1998) [Cheyne, A., Cox, S., Oliver, A., Tomas, J.M., 1998. Modelling safety climate in the prediction of levels of safety activity. Work and Stress, 12(3), 255-271] model was tested, using confirmatory factor analysis, in a Malaysian sample. Results showed that the model fit indices were below accepted levels, indicating that the original Cheyne et al. (1998) safety climate model was not supported. An alternative three-factor model was developed using exploratory factor analysis. Although these findings are not consistent with previously reported cross-validation studies, we argue that previous studies have focused on validation across Western samples, and that the current study demonstrates the need to take account of cultural factors in the development of safety climate models intended for use in non-Western contexts. The results have important implications for the transferability of existing safety climate models across cultures (for example, in global organisations) and highlight the need for future research to examine cross-cultural issues in relation to safety climate. Copyright © 2013 National Safety Council and Elsevier Ltd. All rights reserved.

  11. 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.

  12. DNA microarray technology in nutraceutical and food safety.

    Science.gov (United States)

    Liu-Stratton, Yiwen; Roy, Sashwati; Sen, Chandan K

    2004-04-15

    The quality and quantity of diet is a key determinant of health and disease. Molecular diagnostics may play a key role in food safety related to genetically modified foods, food-borne pathogens and novel nutraceuticals. Functional outcomes in biology are determined, for the most part, by net balance between sets of genes related to the specific outcome in question. The DNA microarray technology offers a new dimension of strength in molecular diagnostics by permitting the simultaneous analysis of large sets of genes. Automation of assay and novel bioinformatics tools make DNA microarrays a robust technology for diagnostics. Since its development a few years ago, this technology has been used for the applications of toxicogenomics, pharmacogenomics, cell biology, and clinical investigations addressing the prevention and intervention of diseases. Optimization of this technology to specifically address food safety is a vast resource that remains to be mined. Efforts to develop diagnostic custom arrays and simplified bioinformatics tools for field use are warranted.

  13. Development of the methodology and approaches to validate safety and accident management

    International Nuclear Information System (INIS)

    Asmolov, V.G.

    1997-01-01

    The article compares the development of the methodology and approaches to validate the nuclear power plant safety and accident management in Russia and advanced industrial countries. It demonstrates that the development of methods of safety validation is dialectically related to the accumulation of the knowledge base on processes and events during NPP normal operation, transients and emergencies, including severe accidents. The article describes the Russian severe accident research program (1987-1996), the implementation of which allowed Russia to reach the world level of the safety validation efforts, presents future high-priority study areas. Problems related to possible approaches to the methodological accident management development are discussed. (orig.)

  14. Importance of Computer Model Validation in Pyroprocessing Technology Development

    Energy Technology Data Exchange (ETDEWEB)

    Jung, Y. E.; Li, Hui; Yim, M. S. [Korea Advanced Institute of Science and Technology, Daejeon (Korea, Republic of)

    2014-05-15

    In this research, we developed a plan for experimental validation of one of the computer models developed for ER process modeling, i. e., the ERAD code. Several candidate surrogate materials are selected for the experiment considering the chemical and physical properties. Molten salt-based pyroprocessing technology is being examined internationally as an alternative to treat spent nuclear fuel over aqueous technology. The central process in pyroprocessing is electrorefining(ER) which separates uranium from transuranic elements and fission products present in spent nuclear fuel. ER is a widely used process in the minerals industry to purify impure metals. Studies of ER by using actual spent nuclear fuel materials are problematic for both technical and political reasons. Therefore, the initial effort for ER process optimization is made by using computer models. A number of models have been developed for this purpose. But as validation of these models is incomplete and often times problematic, the simulation results from these models are inherently uncertain.

  15. A goal-based approach for qualification of new technologies: Foundations, tool support, and industrial validation

    International Nuclear Information System (INIS)

    Sabetzadeh, Mehrdad; Falessi, Davide; Briand, Lionel; Di Alesio, Stefano

    2013-01-01

    New technologies typically involve innovative aspects that are not addressed by the existing normative standards and hence are not assessable through common certification procedures. To ensure that new technologies can be implemented in a safe and reliable manner, a specific kind of assessment is performed, which in many industries, e.g., the energy sector, is known as Technology Qualification (TQ). TQ aims at demonstrating with an acceptable level of confidence that a new technology will function within specified limits. Expert opinion plays an important role in TQ, both to identify the safety and reliability evidence that needs to be developed and to interpret the evidence provided. Since there are often multiple experts involved in TQ, it is crucial to apply a structured process for eliciting expert opinions, and to use this information systematically when analyzing the satisfaction of the technology's safety and reliability objectives. In this paper, we present a goal-based approach for TQ. Our approach enables analysts to quantitatively reason about the satisfaction of the technology's overall goals and further to identify the aspects that must be improved to increase goal satisfaction. The approach is founded on three main components: goal models, expert elicitation, and probabilistic simulation. We describe a tool, named Modus, that we have developed in support of our approach. We provide an extensive empirical validation of our approach through two industrial case studies and a survey

  16. Proceedings of the Nuclear Criticality Technology and Safety Project Workshop

    Energy Technology Data Exchange (ETDEWEB)

    Sanchez, R.G. [comp.

    1994-01-01

    This report is the proceedings of the annual Nuclear Criticality Technology and Safety Project (NCTSP) Workshop held in Monterey, California, on April 16--28, 1993. The NCTSP was sponsored by the Department of Energy and organized by the Los Alamos Critical Experiments Facility. The report is divided into six sections reflecting the sessions outlined on the workshop agenda.

  17. Proceedings of the Nuclear Criticality Technology and Safety Project Workshop

    International Nuclear Information System (INIS)

    Sanchez, R.G.

    1994-01-01

    This report is the proceedings of the annual Nuclear Criticality Technology and Safety Project (NCTSP) Workshop held in Monterey, California, on April 16--28, 1993. The NCTSP was sponsored by the Department of Energy and organized by the Los Alamos Critical Experiments Facility. The report is divided into six sections reflecting the sessions outlined on the workshop agenda

  18. Socio-technological study for establishing comprehensive nuclear safety system

    International Nuclear Information System (INIS)

    Furuta, Kazuo; Kanno, Taro; Yagi, Ekou; Shuto, Yuki

    2003-01-01

    This paper presents an overview and preliminary results of a research project on social-technology for nuclear safety, which started in October 2001. In particular, emergency response preparedness against nuclear disaster and consensus development will be discussed. The architecture of an emergency response simulator will be given, which is for assessing design of disaster prevention systems. A conceptual model of evacuation behavior of a resident has been constructed from analysis of past disaster cases. As for consensus development, deliberation spaces of actual committee meetings were constructed by analyzing transcripts of the meetings based on an opinion schema. A model of consensus development process has been proposed from the traces of participants' opinions over the deliberation spaces. Such a socio-technological approach will be useful not only for nuclear safety but also for safety of non-nuclear domains and human activities of a high hazard potential; it is expected to contribute to establishing risk-aware society of the future. (author)

  19. Safety technology comments on Cattenom nuclear power station

    International Nuclear Information System (INIS)

    1986-01-01

    The comments are based on the safety report for the identical Flamanville plant, on the contract documents for the DUP and on results of consultancy by the DFK Working Party and on replies from the French side in the context of a German list of questions. The comments refer to the state in spring 1982. According to the agreement made for the catalogue of questions Cattenom/KKP 2, the 1300 MW Philippsburg II nuclear power station is used as a German comparable plant in these comments. Reference is made to the German comparable plant in the description and assessment of important parts of the plant. The main points of the safety technology comments are in the assessment of site characteristics; the safety technology concept; the derivation of radio-active materials and the radiation exposure in the adjacent German area. (orig./HP) [de

  20. Multilevel Safety Climate and Safety Performance in the Construction Industry: Development and Validation of a Top-Down Mechanism

    Directory of Open Access Journals (Sweden)

    Ran Gao

    2016-11-01

    Full Text Available The character of construction projects exposes front-line workers to dangers and accidents. Safety climate has been confirmed to be a predictor of safety performance in the construction industry. This study aims to explore the underlying mechanisms of the relationship between multilevel safety climate and safety performance. An integrated model was developed to study how particular safety climate factors of one level affect those of other levels, and then affect safety performance from the top down. A questionnaire survey was administered on six construction sites in Vietnam. A total of 1030 valid questionnaires were collected from this survey. Approximately half of the data were used to conduct exploratory factor analysis (EFA and the remaining data were submitted to structural equation modeling (SEM. Top management commitment (TMC and supervisors’ expectation (SE were identified as factors to represent organizational safety climate (OSC and supervisor safety climate (SSC, respectively, and coworkers’ caring and communication (CCC and coworkers’ role models (CRM were identified as factors to denote coworker safety climate (CSC. SEM results show that OSC factor is positively related to SSC factor and CSC factors significantly. SSC factor could partially mediate the relationship between OSC factor and CSC factors, as well as the relationship between OSC factor and safety performance. CSC factors partially mediate the relationship between OSC factor and safety performance, and the relationship between SSC factor and safety performance. The findings imply that a positive safety culture should be established both at the organizational level and the group level. Efforts from all top management, supervisors, and coworkers should be provided to improve safety performance in the construction industry.

  1. Multilevel Safety Climate and Safety Performance in the Construction Industry: Development and Validation of a Top-Down Mechanism.

    Science.gov (United States)

    Gao, Ran; Chan, Albert P C; Utama, Wahyudi P; Zahoor, Hafiz

    2016-11-08

    The character of construction projects exposes front-line workers to dangers and accidents. Safety climate has been confirmed to be a predictor of safety performance in the construction industry. This study aims to explore the underlying mechanisms of the relationship between multilevel safety climate and safety performance. An integrated model was developed to study how particular safety climate factors of one level affect those of other levels, and then affect safety performance from the top down. A questionnaire survey was administered on six construction sites in Vietnam. A total of 1030 valid questionnaires were collected from this survey. Approximately half of the data were used to conduct exploratory factor analysis (EFA) and the remaining data were submitted to structural equation modeling (SEM). Top management commitment (TMC) and supervisors' expectation (SE) were identified as factors to represent organizational safety climate (OSC) and supervisor safety climate (SSC), respectively, and coworkers' caring and communication (CCC) and coworkers' role models (CRM) were identified as factors to denote coworker safety climate (CSC). SEM results show that OSC factor is positively related to SSC factor and CSC factors significantly. SSC factor could partially mediate the relationship between OSC factor and CSC factors, as well as the relationship between OSC factor and safety performance. CSC factors partially mediate the relationship between OSC factor and safety performance, and the relationship between SSC factor and safety performance. The findings imply that a positive safety culture should be established both at the organizational level and the group level. Efforts from all top management, supervisors, and coworkers should be provided to improve safety performance in the construction industry.

  2. Development of safety analysis technology for integral reactor; evaluation on safety concerns of integral reactor

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Hee Chul; Kim, Woong Sik; Lee, J. H. [Korea Institute of Nuclear Safety, Taejeon (Korea)

    2002-03-01

    The Nuclear Desalination Plant (NDP) is being developed to produce electricity and fresh water, and is expected to locate near population zone. In the aspect of safety, it is required to protect the public and environment from the possible releases of fission products and to prevent the fresh water from the contamination of radioactivity. Thus, in this study, the safety characteristics of the integral reactor adopting passive and inherent safety features significantly different from existing nuclear power plants were investigated. Also, safety requirements applicable to the NDP were analyzed based on the regulatory requirements for current light water reactor and advanced reactor designs, and user requirements for small-medium size reactors. Based on these analyses, some safety concerns to be considered in the design stage have been identified and discussed. They include the use of proven technology for new safety features, systematic event classification and selection, strengthening containment function, and the safety impacts on desalination-related systems. The study presents the general safety requirements applicable to licensing of an integral reactor and suggests additional regulatory requirements, which need to be developed, based on the direction to resolution of the safety concerns. The efforts to identify and technically resolve the safety concerns in the design stage will provide the early confidence of SMART safety and the technical basis to evaluate the safety to designers and reviewers in the future. Suggestion on the development of additional regulatory requirements will contribute for the regulator to taking actions for licensing of an integral reactor. 66 refs., 5 figs., 24 tabs. (Author)

  3. Assessing systemwide occupational health and safety risks of energy technologies

    International Nuclear Information System (INIS)

    Rowe, M.D.

    1982-01-01

    Input-output modelling is now being used to assess systemwide occupational and public health and safety risks of energy technologies. Some of the advantages and disadvantages of this method are presented and some of its important limitations are discussed. Its primary advantage is that it provides a standard method with which to compare technologies on a consistent basis without extensive economic analysis. Among the disadvantages are limited range of applicability, limited spectrum of health impacts, and inability to identify unusual health impacts unique to a new technology. (author)

  4. Vehicle modeling and duty cycle analysis to validate technology feasibility

    Energy Technology Data Exchange (ETDEWEB)

    Castonguay, S. [National Centre for Advanced Transportation, Saint-Jerome, PQ (Canada)

    2010-07-01

    The National Centre for Advanced Transportation (CNTA) is a non-profit organization with a board consisting of representatives from the transportation industry, public service and public transit organizations, research and teaching institutions, and from municipal and economic development organizations. The objectives of the CNTA are to accelerate the introduction of electric and hybrid vehicles; act as a catalyst in projects; assist in increasing Canadian technology assets; initiate and support electric vehicle conversion projects; increase Canadian business for electric vehicles, hybrid vehicles, and plug-in electric vehicles; and provide a cost-effective solution and aggressive payback for road/off-road vehicles. This presentation provided an overview of the objectives and services of the CNTA. It discussed various road and off-road vehicles, duty cycle and technology of electric vehicles. Specific topics related to the technology were discussed, including configuration; controls and interface; efficiency maps; models and simulation; validation; and support. figs.

  5. The development and validation of a psychological contract of safety scale.

    Science.gov (United States)

    Walker, Arlene

    2010-08-01

    This paper builds on previous research by the author and describes the development and validation of a new measure of the psychological contract of safety. The psychological contract of safety is defined as the beliefs of individuals about reciprocal safety obligations inferred from implicit and explicit promises. A psychological contract is established when an individual believes that perceived employer and employee safety obligations are contingent on each other. A pilot test of the measure is first undertaken with participants from three different occupations: nurses, construction workers, and meat processing workers (N=99). Item analysis is used to refine the measure and provide initial validation of the scale. A larger validation study is then conducted with a participant sample of health care workers (N=424) to further refine the measure and to determine the psychometric properties of the scale. Item and correlational analyses produced the final employer and employee obligations scales, consisting of 21 and 17 items, respectively. Factor analyses identified two underlying dimensions in each scale comparable to that previously established in the organizational literature. These transactional and relational-type obligations provided construct validity of the scale. Internal consistency ratings using Cronbach's alpha found the components of the psychological contract of safety measure to be reliable. The refined and validated psychological contract of safety measure will allow investigation of the positive and negative outcomes associated with fulfilment and breach of the psychological contract of safety in future research. 2010 Elsevier Ltd. All rights reserved.

  6. Patient safety risk factors in minimally invasive surgery : A validation study

    NARCIS (Netherlands)

    Rodrigues, S.P.; Ter Kuile, M.; Dankelman, J.; Jansen, F.W.

    2012-01-01

    This study was conducted to adapt and validate a patient safety (PS) framework for minimally invasive surgery (MIS) as a first step in understanding the clinical relevance of various PS risk factors in MIS. Eight patient safety risk factor domains were identified using frameworks from a systems

  7. Training to Support Standardization and Improvement of Safety I and C Related Verification and Validation Activities

    Energy Technology Data Exchange (ETDEWEB)

    Ammon, G.; Schoenfelder, C.

    2014-07-01

    In recent years AREVA has conducted several measures to enhance the effectiveness of safety I and C related verification and validation activities within nuclear power plant (NPP) new build as well as modernization projects, thereby further strengthening its commitment to achieving the highest level of safety in nuclear facilities. (Author)

  8. Presentations of the PTAC driving safety technology forum

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-07-01

    Issues concerning road safety and driver training in relation to the petroleum industry were the focus of this conference. The results of a driving safety survey from the Petroleum Technology Alliance Canada were presented. High risk driver identification methods were discussed along with coaching case studies, including details of continuous and advanced driver training by various industry members. Road hazard analysis was discussed as an effective means of reducing vehicular incidents. The dangers posed by cell phones were reviewed, as well as issues concerning motor vehicle event data recorders and personal privacy. The safety aspects of global positioning system (GPS) enabled fleet management systems were evaluated. Tactical plans for Alberta's traffic collision fatality and injury reduction strategy were examined. An overview of the Schlumberger Canada Driving Program was presented. The systems and processes used within Halliburton Canada to reinforce safe driving behaviors were reviewed. Real time personnel monitoring was discussed, as well as various asset management technologies. It was suggested that new communications technologies for mobile resource management can improve oilfield fleet safety and productivity. The forum featured 12 presentations, of which 8 have been catalogued separately for inclusion in this database.

  9. Development and validation of educational technology for venous ulcer care.

    Science.gov (United States)

    Benevides, Jéssica Lima; Coutinho, Janaina Fonseca Victor; Pascoal, Liliane Chagas; Joventino, Emanuella Silva; Martins, Mariana Cavalcante; Gubert, Fabiane do Amaral; Alves, Allana Mirella

    2016-04-01

    To develop and validate an educational technology venous ulcers care. Methodological study conducted in five steps: Situational diagnosis; literature review; development of texts, illustrations and layout; apparent and content validity by the Content Validity Index, assessment of Flesch Readability Index; and pilot testing. The developed technology was a type of booklet entitled Booklet for Venous Ulcers Care, consisting of seven topics: Diet and food intake, walking and light exercise, resting with elevated leg, bandage care, compression therapy, family support, and keeping healthy habits. The apparent validity revealed minimal agreement of 85.7% in the clarity and comprehensibility. The total content validity index was 0.97, the Flesch Readability Index was 75%, corresponding to the reading "fairly easy". The pilot test showed that 100% of people with venous ulcers evaluated the text and the illustrations as understandable, as appropriate. The educational technology proved to be valid for the appearance and content with potential for use in clinical practice. Construir e validar uma tecnologia educativa para cuidados com úlcera venosa. Estudo metodológico realizado em cinco fases: diagnóstico situacional; revisão da literatura; desenvolvimento de textos, ilustrações e diagramação; validade de aparência e de conteúdo pelo Índice de Validade de Conteúdo, avaliação do Índice de Legibilidade de Flesch; e teste piloto. A tecnologia desenvolvida foi do tipo cartilha intitulada Cartilha para cuidados com úlcera venosa, constituída de sete tópicos: Alimentação, Caminhadas e exercícios leves, Repouso com a perna elevada, Cuidados com o curativo, Terapia compressiva, Apoio familiar, e manter hábitos saudáveis. A validade aparente revelou concordância mínima de 85,7% na clareza e compreensibilidade. O Índice de Validade de Conteúdo total foi de 0,97, o Índice de legibilidade de Flesch foi de 75%, o que correspondeu à leitura "razoavelmente f

  10. The impact of assay technology as applied to safety assessment in reducing compound attrition in drug discovery.

    Science.gov (United States)

    Thomas, Craig E; Will, Yvonne

    2012-02-01

    Attrition in the drug industry due to safety findings remains high and requires a shift in the current safety testing paradigm. Many companies are now positioning safety assessment at each stage of the drug development process, including discovery, where an early perspective on potential safety issues is sought, often at chemical scaffold level, using a variety of emerging technologies. Given the lengthy development time frames of drugs in the pharmaceutical industry, the authors believe that the impact of new technologies on attrition is best measured as a function of the quality and timeliness of candidate compounds entering development. The authors provide an overview of in silico and in vitro models, as well as more complex approaches such as 'omics,' and where they are best positioned within the drug discovery process. It is important to take away that not all technologies should be applied to all projects. Technologies vary widely in their validation state, throughput and cost. A thoughtful combination of validated and emerging technologies is crucial in identifying the most promising candidates to move to proof-of-concept testing in humans. In spite of the challenges inherent in applying new technologies to drug discovery, the successes and recognition that we cannot continue to rely on safety assessment practices used for decades have led to rather dramatic strategy shifts and fostered partnerships across government agencies and industry. We are optimistic that these efforts will ultimately benefit patients by delivering effective and safe medications in a timely fashion.

  11. Development of safety analysis technology for integral reactor

    International Nuclear Information System (INIS)

    Kim, Hee Cheol; Kim, K. K.; Kim, S. H.

    2002-04-01

    The state-of-the-arts for the integral reactor was performed to investigate the safety features. The safety and performance of SMART were assessed using the technologies developed during the study. For this purpose, the computer code system and the analysis methodology were developed and the safety and performance analyses on SMART basic design were carried out for the design basis event and accident. The experimental facilities were designed for the core flow distribution test and the self-pressurizing pressurizer performance test. The tests on the 2-phase critical flow with non-condensable gas were completed and the results were used to assess the critical flow model. Probabilistic Safety Assessment(PSA) was carried out to evaluate the safety level and to optimize the design by identifying and remedying any weakness in the design. A joint study with KINS was carried out to promote licensing environment. The generic safety issues of integral reactors were identified and the solutions were formulated. The economic evaluation of the SMART desalination plant and the activities related to the process control were carried out in the scope of the study

  12. Technology and Tool Development to Support Safety and Mission Assurance

    Science.gov (United States)

    Denney, Ewen; Pai, Ganesh

    2017-01-01

    The Assurance Case approach is being adopted in a number of safety-mission-critical application domains in the U.S., e.g., medical devices, defense aviation, automotive systems, and, lately, civil aviation. This paradigm refocuses traditional, process-based approaches to assurance on demonstrating explicitly stated assurance goals, emphasizing the use of structured rationale, and concrete product-based evidence as the means for providing justified confidence that systems and software are fit for purpose in safely achieving mission objectives. NASA has also been embracing assurance cases through the concepts of Risk Informed Safety Cases (RISCs), as documented in the NASA System Safety Handbook, and Objective Hierarchies (OHs) as put forth by the Agency's Office of Safety and Mission Assurance (OSMA). This talk will give an overview of the work being performed by the SGT team located at NASA Ames Research Center, in developing technologies and tools to engineer and apply assurance cases in customer projects pertaining to aviation safety. We elaborate how our Assurance Case Automation Toolset (AdvoCATE) has not only extended the state-of-the-art in assurance case research, but also demonstrated its practical utility. We have successfully developed safety assurance cases for a number of Unmanned Aircraft Systems (UAS) operations, which underwent, and passed, scrutiny both by the aviation regulator, i.e., the FAA, as well as the applicable NASA boards for airworthiness and flight safety, flight readiness, and mission readiness. We discuss our efforts in expanding AdvoCATE capabilities to support RISCs and OHs under a project recently funded by OSMA under its Software Assurance Research Program. Finally, we speculate on the applicability of our innovations beyond aviation safety to such endeavors as robotic, and human spaceflight.

  13. Developing a model for hospital inherent safety assessment: Conceptualization and validation.

    Science.gov (United States)

    Yari, Saeed; Akbari, Hesam; Gholami Fesharaki, Mohammad; Khosravizadeh, Omid; Ghasemi, Mohammad; Barsam, Yalda; Akbari, Hamed

    2018-01-01

    Paying attention to the safety of hospitals, as the most crucial institute for providing medical and health services wherein a bundle of facilities, equipment, and human resource exist, is of significant importance. The present research aims at developing a model for assessing hospitals' safety based on principles of inherent safety design. Face validity (30 experts), content validity (20 experts), construct validity (268 examples), convergent validity, and divergent validity have been employed to validate the prepared questionnaire; and the items analysis, the Cronbach's alpha test, ICC test (to measure reliability of the test), composite reliability coefficient have been used to measure primary reliability. The relationship between variables and factors has been confirmed at 0.05 significance level by conducting confirmatory factor analysis (CFA) and structural equations modeling (SEM) technique with the use of Smart-PLS. R-square and load factors values, which were higher than 0.67 and 0.300 respectively, indicated the strong fit. Moderation (0.970), simplification (0.959), substitution (0.943), and minimization (0.5008) have had the most weights in determining the inherent safety of hospital respectively. Moderation, simplification, and substitution, among the other dimensions, have more weight on the inherent safety, while minimization has the less weight, which could be due do its definition as to minimize the risk.

  14. 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.

  15. Validation of Fuel Performance Uncertainty for RIA Safety Analysis

    Energy Technology Data Exchange (ETDEWEB)

    Park, Nam-Gyu; Yoo, Jong-Sung; Jung, Yil-Sup [KEPCO Nuclear Fuel Co., Daejeon (Korea, Republic of)

    2016-10-15

    To achieve this the computer code performance has to be validated based on the experimental results. And for the uncertainty quantification, important uncertainty parameters need to be selected, and combined uncertainty has to be evaluated with an acceptable statistical treatment. And important uncertainty parameters to the rod performance such as fuel enthalpy, fission gas release, cladding hoop strain etc. were chosen through the rigorous sensitivity studies. And their validity has been assessed by utilizing the experimental results, which were tested in CABRI and NSRR. Analysis results revealed that several tested rods were not bounded within combined fuel performance uncertainty. Assessment of fuel performance with an extended fuel power uncertainty on tested rods in NSRR and CABRI has been done. Analysis results showed that several tested rods were not bounded within calculated fuel performance uncertainty. This implies that the currently considered uncertainty range of the parameters is not enough to cover the fuel performance sufficiently.

  16. SCALE system cross-section validation for criticality safety analysis

    International Nuclear Information System (INIS)

    Hathout, A.M.; Westfall, R.M.; Dodds, H.L. Jr.

    1980-01-01

    The purpose of this study is to test selected data from three cross-section libraries for use in the criticality safety analysis of UO 2 fuel rod lattices. The libraries, which are distributed with the SCALE system, are used to analyze potential criticality problems which could arise in the industrial fuel cycle for PWR and BWR reactors. Fuel lattice criticality problems could occur in pool storage, dry storage with accidental moderation, shearing and dissolution of irradiated elements, and in fuel transport and storage due to inadequate packing and shipping cask design. The data were tested by using the SCALE system to analyze 25 recently performed critical experiments

  17. Safety of High Speed Ground Transportation Systems : Analytical Methodology for Safety Validation of Computer Controlled Subsystems : Volume 2. Development of a Safety Validation Methodology

    Science.gov (United States)

    1995-01-01

    This report describes the development of a methodology designed to assure that a sufficiently high level of safety is achieved and maintained in computer-based systems which perform safety cortical functions in high-speed rail or magnetic levitation ...

  18. Validation of Nuclear Criticality Safety Software and 27 energy group ENDF/B-IV cross sections

    International Nuclear Information System (INIS)

    Lee, B.L. Jr.

    1994-08-01

    The validation documented in this report is based on calculations that were executed during June through August 1992, and was completed in June 1993. The statistical analyses in Appendix C and Appendix D were completed in October 1993. This validation gives Portsmouth NCS personnel a basis for performing computerized KENO V.a calculations using the Martin Marietta Nuclear Criticality Safety Software. The first portion of the document outlines basic information in regard to validation of NCSS using ENDF/B-IV 27-group cross sections on the IBM 3090 at ORNL. A basic discussion of the NCSS system is provided, some discussion on the validation database and validation in general. Then follows a detailed description of the statistical analysis which was applied. The results of this validation indicate that the NCSS software may be used with confidence for criticality calculations at the Portsmouth Gaseous Diffusion Plant. When the validation results are treated as a single group, there is 95% confidence that 99.9% of future calculations of similar critical systems will have a calculated K eff > 0.9616. Based on this result the Portsmouth Nuclear Criticality Safety Department has adopted the calculational acceptance criteria that a k eff + 2σ ≤ 0.95 is safety subcritical. The validation of NCSS on the IBM 3090 at ORNL was extended to include NCSS on the IBM 3090 at K-25

  19. A Study on the Construct Validity of Safety Culture Oversight Model for Nuclear Power Operating Organization

    International Nuclear Information System (INIS)

    Jung, Su Jin; Choi, Young Sung; Oh, Jang Jin

    2015-01-01

    In Korea, the safety policy statement declared in 1994 by government stressed the importance of safety culture and licensees were encouraged to manage and conduct their self-assessments. A change in regulatory position about safety culture oversight was made after the event of SBO cover-up in Kori unit 1 and several subsequent falsification events. Since then KINS has been developing licensee's safety culture oversight system including conceptual framework of oversight, prime focus area for oversight, and specific details on regulatory expectations, all of which are based on defence-in-depth (DiD) safety enhancement approach. Development and gathering of performance data which is related to actual 'safety' of nuclear power plant are needed to identify the relationship between safety culture and safety performance. Authors consider this study as pilot which has a contribution on verifying the construct validity of the model and the effectiveness of survey based research. This is the first attempt that the validity of safety culture oversight model has been investigated with empirical data obtained from Korean nuclear power operating organization

  20. A Study on the Construct Validity of Safety Culture Oversight Model for Nuclear Power Operating Organization

    Energy Technology Data Exchange (ETDEWEB)

    Jung, Su Jin; Choi, Young Sung; Oh, Jang Jin [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

    2015-05-15

    In Korea, the safety policy statement declared in 1994 by government stressed the importance of safety culture and licensees were encouraged to manage and conduct their self-assessments. A change in regulatory position about safety culture oversight was made after the event of SBO cover-up in Kori unit 1 and several subsequent falsification events. Since then KINS has been developing licensee's safety culture oversight system including conceptual framework of oversight, prime focus area for oversight, and specific details on regulatory expectations, all of which are based on defence-in-depth (DiD) safety enhancement approach. Development and gathering of performance data which is related to actual 'safety' of nuclear power plant are needed to identify the relationship between safety culture and safety performance. Authors consider this study as pilot which has a contribution on verifying the construct validity of the model and the effectiveness of survey based research. This is the first attempt that the validity of safety culture oversight model has been investigated with empirical data obtained from Korean nuclear power operating organization.

  1. The Safety Culture Enactment Questionnaire (SCEQ): Theoretical model and empirical validation.

    Science.gov (United States)

    de Castro, Borja López; Gracia, Francisco J; Tomás, Inés; Peiró, José M

    2017-06-01

    This paper presents the Safety Culture Enactment Questionnaire (SCEQ), designed to assess the degree to which safety is an enacted value in the day-to-day running of nuclear power plants (NPPs). The SCEQ is based on a theoretical safety culture model that is manifested in three fundamental components of the functioning and operation of any organization: strategic decisions, human resources practices, and daily activities and behaviors. The extent to which the importance of safety is enacted in each of these three components provides information about the pervasiveness of the safety culture in the NPP. To validate the SCEQ and the model on which it is based, two separate studies were carried out with data collection in 2008 and 2014, respectively. In Study 1, the SCEQ was administered to the employees of two Spanish NPPs (N=533) belonging to the same company. Participants in Study 2 included 598 employees from the same NPPs, who completed the SCEQ and other questionnaires measuring different safety outcomes (safety climate, safety satisfaction, job satisfaction and risky behaviors). Study 1 comprised item formulation and examination of the factorial structure and reliability of the SCEQ. Study 2 tested internal consistency and provided evidence of factorial validity, validity based on relationships with other variables, and discriminant validity between the SCEQ and safety climate. Exploratory Factor Analysis (EFA) carried out in Study 1 revealed a three-factor solution corresponding to the three components of the theoretical model. Reliability analyses showed strong internal consistency for the three scales of the SCEQ, and each of the 21 items on the questionnaire contributed to the homogeneity of its theoretically developed scale. Confirmatory Factor Analysis (CFA) carried out in Study 2 supported the internal structure of the SCEQ; internal consistency of the scales was also supported. Furthermore, the three scales of the SCEQ showed the expected correlation

  2. Development and validation of a new safety climate scale for petrochemical industries.

    Science.gov (United States)

    Jafari, Mohammad Javad; Eskandari, Davood; Valipour, Firouz; Mehrabi, Yadollah; Charkhand, Hossein; Mirghotbi, Mostafa

    2017-01-01

    While a considerable body of research has studied safety climate and its role as a leading indicator of organizational safety, much of this work has been conducted with Western manufacturing samples. The current study puts emphasis on the cross-validation of a safety climate model in the non-Western industrial context of Iranian petrochemical industries. The current study was performed in one petrochemical company in Iran. The scale was developed through conducting a literature review followed by a qualitative study with expert participation. After performing a screening process, the initial number of items on the scale was reduced to 68. Ten dimensions (including management commitment, workers' empowerment, communication, blame culture, safety training, job satisfaction, interpersonal relationship, supervision, continuous improvement, and reward system) together with 37 items were extracted from the exploratory factor analysis (EFA) to measure safety climate. Acceptable ranges of internal consistency statistics for the sub-scales were observed. Confirmatory factor analysis (CFA) confirmed the construct validity of the developed safety climate scale for the petrochemical industry workers. The results of reliability showed that the Cronbach's alpha coefficient for the designed scale was 0.94. The ICC was obtained 0.92. This study created a valid and reliable scale for measuring safety climate in petrochemical industries.

  3. SDL-Based Protocol Validation for the Integrated Safety Communication Network in Nuclear Power Plants

    International Nuclear Information System (INIS)

    Kim, Jung-hun; Kim, Dong-hoon; Lee, Dong-young; Park, Sung-woo

    2006-01-01

    The communication protocol in nuclear power plants needs to be validated systematically to avoid the critical situation that may be caused by its own faults. We establish the methodology to validate the protocol designed for the Integrated Safety Communication Networks (ISCN) of Korea Nuclear Instrumentation and Control System (KNICS). The ISCN protocol is specified using the formal description technique called the SDL. The validation of ISCN protocol is done via the Simulator and Validator, both of which are main functions provided by the SDL

  4. Development of regulatory technology for thermal-hydraulic safety analysis

    International Nuclear Information System (INIS)

    Bang, Young Seok; Lee, S. H.; Ryu, Y. H.

    2001-02-01

    The present study aims to develop the regulation capability in thermal-hydraulic safety analysis which was required for the reasonable safety regulation in the current NPP, the next generation reactors, and the future-type reactors. The fourth fiscal year of the first phase of the research was focused on the following research topics: Investigation on the current status of the thermal-hydraulic safety analysis technology outside and inside of the country; Review on the improved features of the thermal-hydraulic safety analysis regulatory audit code, RELAP5/MOD3; Assessments of code with LOFT L9-3 ATWS experiment and LSTF SB-SG-10 multiple SGTR experiment; Application of the RELAP5/CANDU code to analyses of SLB and LBLOCA and evaluation of its effect on safety; Application of the code to IAEA PHWR ISP analysis; Assessments of RELAP5 and TRAC with UPTF downcomer injection test and Analysis of LBLOCA with RELAP5 for the performance evaluation of KNGR DVI; Setup of a coupled 3-D kinetics and thermal-hydraulics and application it to a reactivity accident analysis; and Extension of database and improvement of plant input decks. For supporting the resolution of safety issues, loss of RHR event during midloop operation was analyzed for Kori Unit 3, issues on high burnup fuel were reviewed and performance of FRAPCON-3 assessed. Also MSLB was analyzed to figure out the sensitivity of downcomer temperature supporting the PTS risk evaluation of Kori Unit 1. Thermal stratification in pipe was analyzed using the method proposed. And a method predicting the thermal-hydraulic performance of IRWST of KNGR was explored. The PWR ECCS performance criteria was issued as a MOST Article 200-19.and a regulatory guide on evaluation methodology was improved to cover concerns raised from the related licensing review process

  5. Advancing medication infusion safety through the clinical integration of technology.

    Science.gov (United States)

    Gerhart, Donald; O'Shea, Kristen; Muller, Sharon

    2013-01-01

    Adverse drug events resulting from errors in prescribing or administering medications are preventable. Within a hospital system, numerous technologies are employed to address the common sources of medication error, including the use of electronic medical records, physician order entry, smart infusion pumps, and barcode medication administration systems. Infusion safety is inherently risky because of the high-risk medications administered and the lack of integration among the stand-alone systems in most institutions. Intravenous clinical integration (IVCI) is a technology that connects electronic medical records, physician order entry, smart infusion pumps, and barcode medication administration systems. It combines the safety features of an automatically programmed infusion pump (drug, concentration, infusion rate, and patient weight, all auto-programmed into the device) with software that provides visibility to real-time clinical infusion data. Our article describes the characteristics of IVCI at WellSpan Health and its impact on patient safety. The integrated infusion system has the capability of reducing medication errors, improving patient care, reducing in-facility costs, and supporting asset management. It can enhance continuous quality improvement efforts and efficiency of clinical work flow. After implementing IVCI, the institution realized a safer patient environment and a more streamlined work flow for pharmacy and nursing.

  6. Criticality safety validation: Simple geometry, single unit 233U systems

    International Nuclear Information System (INIS)

    Putman, V.L.

    1997-06-01

    Typically used LMITCO criticality safety computational methods are evaluated for suitability when applied to INEEL 233 U systems which reasonably can be modeled as simple-geometry, single-unit systems. Sixty-seven critical experiments of uranium highly enriched in 233 U, including 57 aqueous solution, thermal-energy systems and 10 metal, fast-energy systems, were modeled. These experiments include 41 cylindrical and 26 spherical cores, and 41 reflected and 26 unreflected systems. No experiments were found for intermediate-neutron-energy ranges, or with interstitial non-hydrogenous materials typical of waste systems, mixed 233 U and plutonium, or reflectors such as steel, lead, or concrete. No simple geometry experiments were found with cubic or annular cores, or approximating infinite sea systems. Calculations were performed with various tools and methodologies. Nine cross-section libraries, based on ENDF/B-IV, -V, or -VI.2, or on Hansen-Roach source data, were used with cross-section processing methods of MCNP or SCALE. The k eff calculations were performed with neutral-particle transport and Monte Carlo methods of criticality codes DANT, MCNP 4A, and KENO Va

  7. Understanding Student Teachers’ Behavioural Intention to Use Technology: Technology Acceptance Model (TAM Validation and Testing

    Directory of Open Access Journals (Sweden)

    Kung-Teck, Wong

    2013-01-01

    Full Text Available This study sets out to validate and test the Technology Acceptance Model (TAM in the context of Malaysian student teachers’ integration of their technology in teaching and learning. To establish factorial validity, data collected from 302 respondents were tested against the TAM using confirmatory factor analysis (CFA, and structural equation modelling (SEM was used for model comparison and hypotheses testing. The goodness-of-fit test of the analysis shows partial support of the applicability of the TAM in a Malaysian context. Overall, the TAM accounted for 37.3% of the variance in intention to use technology among student teachers and of the five hypotheses formulated, four are supported. Perceived usefulness is a significant influence on attitude towards computer use and behavioural intention. Perceived ease of use significantly influences perceived usefulness, and finally, behavioural intention is found to be influenced by attitude towards computer use. The findings of this research contribute to the literature by validating the TAM in the Malaysian context and provide several prominent implications for the research and practice of technology integration development.

  8. Improving mine safety technology and training: establishing US global leadership

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-12-15

    In 2006, the USA's record of mine safety was interrupted by fatalities that rocked the industry and caused the National Mining Association and its members to recommit to returning the US underground coal mining industry to a global mine safety leadership role. This report details a comprehensive approach to increase the odds of survival for miners in emergency situations and to create a culture of prevention of accidents. Among its 75 recommendations are a need to improve communications, mine rescue training, and escape and protection of miners. Section headings of the report are: Introduction; Review of mine emergency situations in the past 25 years: identifying and addressing the issues and complexities; Risk-based design and management; Communications technology; Escape and protection strategies; Emergency response and mine rescue procedures; Training for preparedness; Summary of recommendations; and Conclusions. 37 refs., 3 figs., 5 apps.

  9. Safety technology for air-cooled heat exchangers

    International Nuclear Information System (INIS)

    Kawai, Masafumi; Miyamoto, Hitoshi

    2011-01-01

    The air-cooled heat exchanger is a device that enables a large amount of heat exchange (cooling) by utilizing the atmosphere as a stable and infinite heat sink. It is widely used in general industrial plants, and nowadays it is also utilized in nuclear facilities. This type of exchanger is advantageous in that it can be constructed in any location without having to be near the sea or rivers. It can be operated safely if a natural disaster, such as a tsunami or flood, occurs, thus contributing to the safety of the mother facility. IHI's air-cooled heat exchangers are designed to ensure safe operation and withstand a large earthquake or severe atmospheric conditions. This report describes the technologies used to establish these safety features and their performance. (author)

  10. Nuclear Criticality Technology and Safety Project parameter study database

    International Nuclear Information System (INIS)

    Toffer, H.; Erickson, D.G.; Samuel, T.J.; Pearson, J.S.

    1993-03-01

    A computerized, knowledge-screened, comprehensive database of the nuclear criticality safety documentation has been assembled as part of the Nuclear Criticality Technology and Safety (NCTS) Project. The database is focused on nuclear criticality parameter studies. The database has been computerized using dBASE III Plus and can be used on a personal computer or a workstation. More than 1300 documents have been reviewed by nuclear criticality specialists over the last 5 years to produce over 800 database entries. Nuclear criticality specialists will be able to access the database and retrieve information about topical parameter studies, authors, and chronology. The database places the accumulated knowledge in the nuclear criticality area over the last 50 years at the fingertips of a criticality analyst

  11. Radio Frequency Identification (RFID) technology and patient safety

    Science.gov (United States)

    Ajami, Sima; Rajabzadeh, Ahmad

    2013-01-01

    Background: Radio frequency identification (RFID) systems have been successfully applied in areas of manufacturing, supply chain, agriculture, transportation, healthcare, and services to name a few. However, the different advantages and disadvantages expressed in various studies of the challenges facing the technology of the use of the RFID technology have been met with skepticism by managers of healthcare organizations. The aim of this study was to express and display the role of RFID technology in improving patient safety and increasing the impact of it in healthcare. Materials and Methods: This study was non-systematical review, which the literature search was conducted with the help of libraries, books, conference proceedings, PubMed databases and also search engines available at Google, Google scholar in which published between 2004 and 2013 during Febuary 2013. We employed the following keywords and their combinations; RFID, healthcare, patient safety, medical errors, and medication errors in the searching areas of title, keywords, abstract, and full text. Results: The preliminary search resulted in 68 articles. After a careful analysis of the content of each paper, a total of 33 papers was selected based on their relevancy. Conclusion: We should integrate RFID with hospital information systems (HIS) and electronic health records (EHRs) and support it by clinical decision support systems (CDSS), it facilitates processes and reduce medical, medication and diagnosis errors. PMID:24381626

  12. Radio Frequency Identification (RFID) technology and patient safety.

    Science.gov (United States)

    Ajami, Sima; Rajabzadeh, Ahmad

    2013-09-01

    Radio frequency identification (RFID) systems have been successfully applied in areas of manufacturing, supply chain, agriculture, transportation, healthcare, and services to name a few. However, the different advantages and disadvantages expressed in various studies of the challenges facing the technology of the use of the RFID technology have been met with skepticism by managers of healthcare organizations. The aim of this study was to express and display the role of RFID technology in improving patient safety and increasing the impact of it in healthcare. This study was non-systematical review, which the literature search was conducted with the help of libraries, books, conference proceedings, PubMed databases and also search engines available at Google, Google scholar in which published between 2004 and 2013 during Febuary 2013. We employed the following keywords and their combinations; RFID, healthcare, patient safety, medical errors, and medication errors in the searching areas of title, keywords, abstract, and full text. The preliminary search resulted in 68 articles. After a careful analysis of the content of each paper, a total of 33 papers was selected based on their relevancy. We should integrate RFID with hospital information systems (HIS) and electronic health records (EHRs) and support it by clinical decision support systems (CDSS), it facilitates processes and reduce medical, medication and diagnosis errors.

  13. Radio Frequency Identification (RFID technology and patient safety

    Directory of Open Access Journals (Sweden)

    Sima Ajami

    2013-01-01

    Full Text Available Background: Radio frequency identification (RFID systems have been successfully applied in areas of manufacturing, supply chain, agriculture, transportation, healthcare, and services to name a few. However, the different advantages and disadvantages expressed in various studies of the challenges facing the technology of the use of the RFID technology have been met with skepticism by managers of healthcare organizations. The aim of this study was to express and display the role of RFID technology in improving patient safety and increasing the impact of it in healthcare. Materials and Methods: This study was non-systematical review, which the literature search was conducted with the help of libraries, books, conference proceedings, PubMed databases and also search engines available at Google, Google scholar in which published between 2004 and 2013 during Febuary 2013. We employed the following keywords and their combinations; RFID, healthcare, patient safety, medical errors, and medication errors in the searching areas of title, keywords, abstract, and full text. Results: The preliminary search resulted in 68 articles. After a careful analysis of the content of each paper, a total of 33 papers was selected based on their relevancy. Conclusion: We should integrate RFID with hospital information systems (HIS and electronic health records (EHRs and support it by clinical decision support systems (CDSS, it facilitates processes and reduce medical, medication and diagnosis errors.

  14. Safety technology: Emergency equipment and sea rescue techniques

    Energy Technology Data Exchange (ETDEWEB)

    1986-06-01

    In June 1986, a two day workshop was convened to review mobile offshore drilling unit (MODU) evacuation research and development (R D) requirements for programs currently sponsored by the Marine Engineering Committee for PERD (Panel on Energy Research and Development) task 6.2. The proceedings of the workshop are presented in terms of: evacuation technology needs; a review of current R D projects for their relevance to the technological needs; recommended changes to current projects where warranted; and recommended priority R D projects that are not presently being undertaken to meet the evacuation technology needs. Current R D projects reviewed include: preferred orientation and displacement (PROD) lifeboat launching, personal transfer baskets, arctic escape system (AES), fast rescue craft (FRC), helicopter survival suits, diving bell emergency heaters, working immersion suits, diving bell emergency ascent system, undersea robotics systems and DCIEM decompression tables. It was concluded that gaps in offshore safety/evacuation capability cannot be adequately addressed by one or two major projects. Rather, a wider range of problems exist that require attention through a greater financial commitment than is presently the case. Government-industry cooperation in this field is required. Overall, the projects were judged to have been well planned, managed, and relevant to offshore safety needs. The only exception was a feeling that diving related projects consummed a disproportionate share of the available funding. Further, there was some reservation that the robotics study was outside the 6.2 PERD R D mandate. A list of recommendations is presented. 1 tab.

  15. Validation of computer codes used in the safety analysis of Canadian research reactors

    International Nuclear Information System (INIS)

    Bishop, W.E.; Lee, A.G.

    1998-01-01

    AECL has embarked on a validation program for the suite of computer codes that it uses in performing the safety analyses for its research reactors. Current focus is on codes used for the analysis of the two MAPLE reactors under construction at Chalk River but the program will be extended to include additional codes that will be used for the Irradiation Research Facility. The program structure is similar to that used for the validation of codes used in the safety analyses for CANDU power reactors. (author)

  16. A safety-critical java technology compatibility kit

    DEFF Research Database (Denmark)

    Søndergaard, Hans; Korsholm, Stephan E.; Ravn, Anders Peter

    2014-01-01

    In order to claim conformance with a given Java Specification Request (JSR), a Java implementation has to pass all tests in an associated Technology Compatibility Kit (TCK). This paper presents development of test cases and tools for the draft Safety-Critical Java (SCJ) specification. In previous...... work we have shown how the Java Modeling Language (JML) is applied to specify conformance constraints for SCJ, and how JML-related tools may assist in generating and executing tests. Here we extend this work with a layout for concrete test cases including checking of results in a simplified version...

  17. Using tablet technology in operational radiation safety applications.

    Science.gov (United States)

    Phillips, Andrew; Linsley, Mark; Houser, Mike

    2013-11-01

    Tablet computers have become a mainstream product in today's personal, educational, and business worlds. These tablets offer computing power, storage, and a wide range of available products to meet nearly every user need. To take advantage of this new computing technology, a system was developed for the Apple iPad (Apple Inc. 1 Infinite Loop Cupertino, CA 95014) to perform health and safety inspections in the field using editable PDFs and saving them to a database while keeping the process easy and paperless.

  18. Some Findings from Thermal-Hydraulic Validation Tests for SMART Passive Safety System

    Energy Technology Data Exchange (ETDEWEB)

    Park, Hyun Sik; Bae, Hwang; Ryu, Sung-Uk; Ryu, Hyobong; Shin, Yong-Cheol; Min, Kyoung-Ho; Yi, Sung-Jae [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2014-10-15

    To satisfy the domestic and international needs for nuclear safety improvement after the Fukushima accident, an effort to improve its safety has been studied, and a Passive Safety System (PSS) for SMART has been designed. In addition, an Integral Test Loop for the SMART design (SMART-ITL, or FESTA) has been constructed and it finished its commissioning tests in 2012. Consequently, a set of Design Base Accident (DBA) scenarios have been simulated using SMARTITL. Recently, a test program to validate the performance of the SMART PSS was launched and its scaled-down test facility was additionally installed at the existing SMART-ITL facility. In this paper, some findings from the validation tests for the SMART PSS will be summarized. The acquired data will be used to validate the safety analysis code and its related models, to evaluate the performance of SMART PSS, and to provide base data during the application phase of SDA revision and construction licensing. A test program to validate the performance of SMARS PSS was launched with an additional scaleddown test facility of SMART PSS, which will be installed at the existing SMART-ITL facility. In this paper, some findings from the validation tests of the SMART passive safety system during 2013-2014 were summarized. They include a couple of SMART PSS tests using active pumps and several 1-train SMART PSS tests. From the test results it was estimated that the SMART PSS has sufficient cooling capability to deal with the SBLOCA scenario of SMART. During the SBLOCA scenario, in the CMT the water layer inventory was well stratified thermally and the safety injection water was injected efficiently into the RPV from the initial period and cools down the RCS properly.

  19. 'Speaking up' about patient safety concerns and unprofessional behaviour among residents: validation of two scales.

    Science.gov (United States)

    Martinez, William; Etchegaray, Jason M; Thomas, Eric J; Hickson, Gerald B; Lehmann, Lisa Soleymani; Schleyer, Anneliese M; Best, Jennifer A; Shelburne, Julia T; May, Natalie B; Bell, Sigall K

    2015-11-01

    To develop and test the psychometric properties of two new survey scales aiming to measure the extent to which the clinical environment supports speaking up about (a) patient safety concerns and (b) unprofessional behaviour. Residents from six large US academic medical centres completed an anonymous, electronic survey containing questions regarding safety culture and speaking up about safety and professionalism concerns. Confirmatory factor analysis supported two separate, one-factor speaking up climates (SUCs) among residents; one focused on patient safety concerns (SUC-Safe scale) and the other focused on unprofessional behaviour (SUC-Prof scale). Both scales had good internal consistency (Cronbach's α>0.70) and were unique from validated safety and teamwork climate measures (rspeaking up behaviour about safety and professionalism concerns (r=0.21, pspeaking up behaviour among residents. These two scales may fill an existing gap in residency and safety culture assessments by measuring the openness of communication about safety and professionalism concerns, two important aspects of safety culture that are under-represented in existing metrics. Published by the BMJ Publishing Group Limited. For permission to use (where not already granted under a licence) please go to http://group.bmj.com/group/rights-licensing/permissions.

  20. Development of reliability-based safety enhancement technology

    International Nuclear Information System (INIS)

    Kim, Kil Yoo; Han, Sang Hoon; Jang, Seung Cherl

    2002-04-01

    This project aims to develop critical technologies and the necessary reliability DB for maximizing the economics in the NPP operation with keeping the safety using the information of the risk (or reliability). For the research goal, firstly the four critical technologies(Risk Informed Tech. Spec. Optimization, Risk Informed Inservice Testing, On-line Maintenance, Maintenance Rule) for RIR and A have been developed. Secondly, KIND (Korea Information System for Nuclear Reliability Data) has been developed. Using KIND, YGN 3,4 and UCN 3,4 component reliability DB have been established. A reactor trip history DB for all NPP in Korea also has been developed and analyzed. Finally, a detailed reliability analysis of RPS/ESFAS for KNSP has been performed. With the result of the analysis, the sensitivity analysis also has been performed to optimize the AOT/STI of tech. spec. A statistical analysis procedure and computer code have been developed for the set point drift analysis

  1. Safety in nuclear technology through introduction of internationally binding agreements

    International Nuclear Information System (INIS)

    1987-01-01

    Presents the Verband Deutscher Elektrotechniker (VDE) views in favour of continued utilisation of nuclear energy for electrical power generation. Nuclear energy helps to conserve finite natural resources of coal, oil, and gas for future generations, and avoids the considerable amount of environmental pollution produced by coal-burning power stations. Risks arise in every technology, but these must be considered in relation to the utility of the technology. Development of other forms of energy conversion must continue, but use of nuclear energy at the present time cannot be avoided without incurring great adverse economic and environmental pollution consequences. Safety aspects must be the object of committed and continuous research, and must be internationally agreed. (H.V.H.)

  2. Research program on nuclear technology and nuclear safety

    International Nuclear Information System (INIS)

    Dreier, J.

    2010-04-01

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

  3. Validation of a functional model for integration of safety into process system design

    DEFF Research Database (Denmark)

    Wu, J.; Lind, M.; Zhang, X.

    2015-01-01

    with the process system functionalities as required for the intended safety applications. To provide the scientific rigor and facilitate the acceptance of qualitative modelling, this contribution focuses on developing a scientifically based validation method for functional models. The Multilevel Flow Modeling (MFM...

  4. Validation of risk-based performance indicators: Safety system function trends

    International Nuclear Information System (INIS)

    Boccio, J.L.; Vesely, W.E.; Azarm, M.A.; Carbonaro, J.F.; Usher, J.L.; Oden, N.

    1989-10-01

    This report describes and applies a process for validating a model for a risk-based performance indicator. The purpose of the risk-based indicator evaluated, Safety System Function Trend (SSFT), is to monitor the unavailability of selected safety systems. Interim validation of this indicator is based on three aspects: a theoretical basis, an empirical basis relying on statistical correlations, and case studies employing 25 plant years of historical data collected from five plants for a number of safety systems. Results using the SSFT model are encouraging. Application of the model through case studies dealing with the performance of important safety systems shows that statistically significant trends in, and levels of, system performance can be discerned which thereby can provide leading indications of degrading and/or improving performances. Methods for developing system performance tolerance bounds are discussed and applied to aid in the interpretation of the trends in this risk-based indicator. Some additional characteristics of the SSFT indicator, learned through the data-collection efforts and subsequent data analyses performed, are also discussed. The usefulness and practicality of other data sources for validation purposes are explored. Further validation of this indicator is noted. Also, additional research is underway in developing a more detailed estimator of system unavailability. 9 refs., 18 figs., 5 tabs

  5. Report of the 17th international workshop on nuclear safety and simulation technology (IWNSST17)

    International Nuclear Information System (INIS)

    Yoshikawa, Hidekazu

    2014-01-01

    The 17th International Workshop on Nuclear Safety and Simulation Technology (IWNSST17) was held in January 21, 2014 at Kyoto University, in Kyoto, Japan. This one-day workshop was motivated to exploit advanced safety researches for nuclear power plant (NPP) , by a unique synergetic collaboration of basically two different disciplines: material science and systems sciences. There were ten invited presentations at the ISSNP2013, and the subject of the presentations ranges from (1) material corrosion issue of NPP components, (2) application of augmented reality technology for NPP decommission, (3) functional modeling method for plant control system, (4) intrinsic understanding of Fukushima Daiichi accident phenomena based on simple physical model, (5) system reliability evaluation method for PWR safety system, (6) automatic control system design for small modular reactor, and (7) validation of computerized human-machine interface and digital I and C for PWR plant. This article provides the overview of the IWNSST17 with giving condensed summaries of all invited presentations given by international experts. (author)

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

    International Nuclear Information System (INIS)

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

    2003-01-01

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

  7. Adaption and validation of the Safety Attitudes Questionnaire for the Danish hospital setting

    DEFF Research Database (Denmark)

    Kristensen, Solvejg; Sabroe, Svend; Bartels, Paul

    2015-01-01

    PURPOSE: Measuring and developing a safe culture in health care is a focus point in creating highly reliable organizations being successful in avoiding patient safety incidents where these could normally be expected. Questionnaires can be used to capture a snapshot of an employee's perceptions...... of patient safety culture. A commonly used instrument to measure safety climate is the Safety Attitudes Questionnaire (SAQ). The purpose of this study was to adapt the SAQ for use in Danish hospitals, assess its construct validity and reliability, and present benchmark data. MATERIALS AND METHODS: The SAQ...... tested in a cross-sectional study. Goodness-of-fit indices from confirmatory factor analysis were reported along with inter-item correlations, Cronbach's alpha (α), and item and subscale scores. RESULTS: Participation was 73.2% (N=925) of invited health care workers. Goodness-of-fit indices from...

  8. Development and validation of a predictive technology for creep closure of underground rooms in salt

    International Nuclear Information System (INIS)

    Munson, D.E.; DeVries, K.L.

    1991-07-01

    Because of the concern for public health and safety, when compared to normal engineering practice, radioactive waste repositories have quite unusual requirements governing performance assessment. In part, performance assessment requires prediction of time-dependent or creep response of the repository hundreds to thousands of years into the future. In salt, one specific need is to predict, with confidence, the time at which the repository rooms creep closed sufficiently to encapsulate the waste and seal the repository. Thus, a major task of the Waste Isolation Pilot Plant (WIPP) Program is to develop and validate this predictive technology to calculate creep of repository rooms in the bedded salt deposits of Southeastern New Mexico. 19 refs., 15 figs., 2 tabs

  9. Sensitivity and uncertainty analyses applied to criticality safety validation. Volume 2

    International Nuclear Information System (INIS)

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

    1999-01-01

    This report presents the application of sensitivity and uncertainty (S/U) analysis methodologies developed in Volume 1 to the code/data validation tasks of a criticality safety computational study. Sensitivity and uncertainty analysis methods were first developed for application to fast reactor studies in the 1970s. This work has revitalized and updated the existing S/U computational capabilities such that they can be used as prototypic modules of the SCALE code system, which contains criticality analysis tools currently in use by criticality safety practitioners. After complete development, simplified tools are expected to be released for general use. The methods for application of S/U and generalized linear-least-square methodology (GLLSM) tools to the criticality safety validation procedures were described in Volume 1 of this report. Volume 2 of this report presents the application of these procedures to the validation of criticality safety analyses supporting uranium operations where enrichments are greater than 5 wt %. Specifically, the traditional k eff trending analyses are compared with newly developed k eff trending procedures, utilizing the D and c k coefficients described in Volume 1. These newly developed procedures are applied to a family of postulated systems involving U(11)O 2 fuel, with H/X values ranging from 0--1,000. These analyses produced a series of guidance and recommendations for the general usage of these various techniques. Recommendations for future work are also detailed

  10. The real-world safety potential of connected vehicle technology.

    Science.gov (United States)

    Doecke, Sam; Grant, Alex; Anderson, Robert W G

    2015-01-01

    This article estimates the safety potential of a current commercially available connected vehicle technology in real-world crashes. Data from the Centre for Automotive Safety Research's at-scene in-depth crash investigations in South Australia were used to simulate the circumstances of real-world crashes. A total of 89 crashes were selected for inclusion in the study. The crashes were selected as representative of the most prevalent crash types for injury or fatal crashes and had potential to be mitigated by connected vehicle technology. The trajectory, speeds, braking, and impact configuration of the selected in-depth cases were replicated in a software package and converted to a file format allowing "replay" of the scenario in real time as input to 2 Cohda Wireless MK2 onboard units. The Cohda Wireless onboard units are a mature connected vehicle technology that has been used in both the German simTD field trial and the U.S. Department of Transport's Safety Pilot project and have been tuned for low false alarm rates when used in the real world. The crash replay was achieved by replacing each of the onboard unit Global Positioning System (GPS) inputs with the simulated data of each of the involved vehicles. The time at which the Cohda Wireless threat detection software issued an elevated warning was used to calculate a new impact speed using 3 different reaction scenarios and 2 levels of braking. It was found that between 37 and 86% of the simulated crashes could be avoided, with highest percentage due a fully autonomous system braking at 0.7 g. The same system also reduced the impact speed relative to the actual crash in all cases. Even when a human reaction time of 1.2 s and moderate braking of 0.4 g was assumed, the impact speed was reduced in 78% of the crashes. Crash types that proved difficult for the threat detection engine were head-on crashes where the approach angle was low and right turn-opposite crashes. These results indicate that connected vehicle

  11. Next generation safety performance monitoring at signalized intersections using connected vehicle technology.

    Science.gov (United States)

    2014-08-01

    Crash-based safety evaluation is often hampered by randomness, lack of timeliness, and rarity of crash : occurrences. This is particularly the case for technology-driven safety improvement projects that are : frequently updated or replaced by newer o...

  12. Non-clinical models: validation, study design and statistical consideration in safety pharmacology.

    Science.gov (United States)

    Pugsley, M K; Towart, R; Authier, S; Gallacher, D J; Curtis, M J

    2010-01-01

    The current issue of the Journal of Pharmacological and Toxicological Methods (JPTM) focuses exclusively on safety pharmacology methods. This is the 7th year the Journal has published on this topic. Methods and models that specifically relate to methods relating to the assessment of the safety profile of a new chemical entity (NCE) prior to first in human (FIH) studies are described. Since the Journal started publishing on this topic there has been a major effort by safety pharmacologists, toxicologists and regulatory scientists within Industry (both large and small Pharma as well as Biotechnology companies) and also from Contract Research Organizations (CRO) to publish the surgical details of the non-clinical methods utilized but also provide important details related to standard and non-standard (or integrated) study models and designs. These details from core battery and secondary (or ancillary) drug safety assessment methods used in drug development programs have been the focus of these special issues and have been an attempt to provide validation of methods. Similarly, the safety pharmacology issues of the Journal provide the most relevant forum for scientists to present novel and modified methods with direct applicability to determination of drug safety-directly to the safety pharmacology scientific community. The content of the manuscripts in this issue includes the introduction of additional important surgical methods, novel data capture and data analysis methods, improved study design and effects of positive control compounds with known activity in the model. Copyright 2010 Elsevier Inc. All rights reserved.

  13. Linguistic Validation and Cultural Adaptation of Bulgarian Version of Hospital Survey on Patient Safety Culture (HSOPSC).

    Science.gov (United States)

    Stoyanova, Rumyana; Dimova, Rositsa; Tarnovska, Miglena; Boeva, Tatyana

    2018-05-20

    Patient safety (PS) is one of the essential elements of health care quality and a priority of healthcare systems in most countries. Thus the creation of validated instruments and the implementation of systems that measure patient safety are considered to be of great importance worldwide. The present paper aims to illustrate the process of linguistic validation, cross-cultural verification and adaptation of the Bulgarian version of the Hospital Survey on Patient Safety Culture (B-HSOPSC) and its test-retest reliability. The study design is cross-sectional. The HSOPSC questionnaire consists of 42 questions, grouped in 12 different subscales that measure patient safety culture. Internal con-sistency was assessed using Cronbach's alpha. The Wilcoxon signed-rank test and the split-half method were used; the Spear-man-Brown coefficient was calculated. The overall Cronbach's alpha for B-HSOPSC is 0.918. Subscales 7 Staffing and 12 Overall perceptions of safety had the lowest coefficients. The high reliability of the instrument was confirmed by the Split-half method (0.97) and ICC-coefficient (0.95). The lowest values of Spearmen-Broun coefficients were found in items A13 and A14. The study offers an analysis of the results of the linguistic validation of the B-HSOPSC and its test-retest reliability. The psychometric characteristics of the questions revealed good validity and reliability, except two questions. In the future, the instrument will be administered to the target population in the main study so that the psychometric properties of the instrument can be verified.

  14. Aviation safety and automation technology for subsonic transports

    Science.gov (United States)

    Albers, James A.

    1991-01-01

    Discussed here are aviation safety human factors and air traffic control (ATC) automation research conducted at the NASA Ames Research Center. Research results are given in the areas of flight deck and ATC automations, displays and warning systems, crew coordination, and crew fatigue and jet lag. Accident investigation and an incident reporting system that is used to guide the human factors research is discussed. A design philosophy for human-centered automation is given, along with an evaluation of automation on advanced technology transports. Intelligent error tolerant systems such as electronic checklists are discussed along with design guidelines for reducing procedure errors. The data on evaluation of Crew Resource Management (CRM) training indicates highly significant positive changes in appropriate flight deck behavior and more effective use of available resources for crew members receiving the training.

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

    International Nuclear Information System (INIS)

    Kusakabe, Masashi; Kumagaya, Tadafusa; Minohara, Shinichi

    2010-01-01

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

  16. Proceeding of the 7. Seminar on Technology and Safety of Nuclear Power Plants and Nuclear Facilities

    International Nuclear Information System (INIS)

    Hastowo, Hudi; Antariksawan, Anhar R.; Soetrisnanto, Arnold Y; Jujuratisbela, Uju; Aziz, Ferhat; Su'ud, Zaki; Suprawhardana, M. Salman

    2002-02-01

    The seventh proceedings of seminar safety and technology of nuclear power plant and nuclear facilities, held by National Nuclear Energy Agency. The Aims of seminar is to exchange and disseminate information about safety and nuclear Power Plant Technology and Nuclear Facilities consist of technology; high temperature reactor and application for national development sustain able and high technology. This seminar level all aspects technology, Power Reactor research reactor, high temperature reactor and nuclear facilities. The article is separated by index

  17. The Taskload-Efficiency-Safety-Buffer Triangle--development and validation with air traffic management.

    Science.gov (United States)

    Kallus, K Wolfgang; Hoffmann, Peter; Winkler, Hildegard; Vormayr, Elisabeth M

    2010-02-01

    The Taskload-Efficiency-Safety-Buffer Triangle (TEST) was developed as a new computerised scaling tool for quickly visualising changes in and trade-offs between the three critical factors that determine the work situation of air traffic management (ATM), i.e. taskload, efficiency and safety-buffers. Based on a task analysis of ATM and backed up by the stress-strain model, an easy-to-interpret triangle was constructed and validated both in simulated and real ATM workplaces. Results from the validation studies show that TEST does not only reflect the most relevant task characteristics, but also provides additional insights in the controllers' working styles. The TEST tool can make ATM safety surveys more efficient and help supervisors to decide about optimal times for opening or closing additional sectors. Statement of Relevance: TEST is a new tool to assess taskload, efficiency and safety-buffers in a joint scaling. It reflects increases in taskload and effects of taskload on safety-buffers and efficiency, as well as trade-offs in opposite directions. This tool might be very useful to check sector capacity in ATM and other high risk environments.

  18. Assessing the safety attitudes questionnaire (SAQ), German language version in Swiss university hospitals - a validation study

    Science.gov (United States)

    2013-01-01

    Background Improving patient safety has become a major focus of clinical care and research over the past two decades. An institution’s patient safety climate represents an essential component of ensuring a safe environment and thereby can be vital to the prevention of adverse events. Covering six patient safety related factors, the Safety Attitudes Questionnaire (SAQ) is a validated and widely used instrument to measure the patient safety climate in clinical areas. The objective of this study was to assess the psychometric properties of the German language version of the SAQ. Methods A survey was carried out in two University Hospitals in Switzerland in autumn 2009 where the SAQ was distributed to a sample of 406 nurses and physicians in medical and surgical wards. Following the American Educational Research Association guidelines, we tested the questionnaire validity by levels of evidence: content validity, internal structure and relations to other variables. Confirmatory factor analysis was used to examine factor structure. Cronbach’s alphas and inter-item correlations were calculated to examine internal consistency reliability. Results A total of 319 questionnaires were completed representing an overall response rate of 78.6%. For three items, the item content validity index was <0.75. Confirmatory factor analysis showed acceptable model fit (RMSEA = 0.045; CFI = 0.944) for the six-factor model. Additional exploratory factor analysis could not identify a better factor model. SAQ factor scores showed positive correlations with the Safety Organizing Scale (r = .56 - .72). The SAQ German version showed moderate to strong internal consistency reliability indices (Cronbach alpha = .65 - .83). Conclusions The German language version of the SAQ demonstrated acceptable to good psychometric properties and therefore shows promise to be a sound instrument to measure patient safety climate in Swiss hospital wards. However, the low item content validity and large number

  19. Maximising harm reduction in early specialty training for general practice: validation of a safety checklist.

    Science.gov (United States)

    Bowie, Paul; McKay, John; Kelly, Moya

    2012-06-21

    Making health care safer is a key policy priority worldwide. In specialty training, medical educators may unintentionally impact on patient safety e.g. through failures of supervision; providing limited feedback on performance; and letting poorly developed behaviours continue unchecked. Doctors-in-training are also known to be susceptible to medical error. Ensuring that all essential educational issues are addressed during training is problematic given the scale of the tasks to be undertaken. Human error and the reliability of local systems may increase the risk of safety-critical topics being inadequately covered. However adherence to a checklist reminder may improve the reliability of task delivery and maximise harm reduction. We aimed to prioritise the most safety-critical issues to be addressed in the first 12-weeks of specialty training in the general practice environment and validate a related checklist reminder. We used mixed methods with different groups of GP educators (n=127) and specialty trainees (n=9) in two Scottish regions to prioritise, develop and validate checklist content. Generation and refinement of checklist themes and items were undertaken on an iterative basis using a range of methods including small group work in dedicated workshops; a modified-Delphi process; and telephone interviews. The relevance of potential checklist items was rated using a 4-point scale content validity index to inform final inclusion. 14 themes (e.g. prescribing safely; dealing with medical emergency; implications of poor record keeping; and effective & safe communication) and 47 related items (e.g. how to safety-net face-to-face or over the telephone; knowledge of practice systems for results handling; recognition of harm in children) were judged to be essential safety-critical educational issues to be covered. The mean content validity index ratio was 0.98. A checklist was developed and validated for educational supervisors to assist in the reliable delivery of

  20. Validation study on reliability analysis of main safety system in Nuclear Power Plant

    Energy Technology Data Exchange (ETDEWEB)

    Cho, Nam Jin; Cho, Chang Keun; Kim, Yong Hui; Kim, Tae Hyeong; Hong, Seo Kee; Park, Keon Woo; Park, Chang Jea [Korea Advanced Institute of Science and Technology, Taejon (Korea, Republic of); Cheong, Woo Sik [Institute for Advanced Engineering, Yongin (Korea, Republic of); Park, Moon Kyu [KEPRI, Taejon (Korea, Republic of)

    1993-12-15

    The scope and contents of this validation study are to review the design changes of the four main safety systems in Wolsong 2/3/4 Nuclear Power Plants, to review the consideration of the above design changes in the AECL reports, the structure of fault trees, and the data base used in the quantification of the fault trees, to quantify the unavailabilities of main safety systems and check them if they meet the requirements, and to recommend desirable design changes in the emergency core cooling system to reduce the unavailability.

  1. Results of a survey on accident and safety analysis codes, benchmarks, verification and validation methods

    International Nuclear Information System (INIS)

    Lee, A.G.; Wilkin, G.B.

    1995-01-01

    This report is a compilation of the information submitted by AECL, CIAE, JAERI, ORNL and Siemens in response to a need identified at the 'Workshop on R and D Needs' at the IGORR-3 meeting. The survey compiled information on the national standards applied to the Safety Quality Assurance (SQA) programs undertaken by the participants. Information was assembled for the computer codes and nuclear data libraries used in accident and safety analyses for research reactors and the methods used to verify and validate the codes and libraries. Although the survey was not comprehensive, it provides a basis for exchanging information of common interest to the research reactor community

  2. Verification and validation of the safety parameter display system for nuclear power plant

    International Nuclear Information System (INIS)

    Zhang Yuanfang

    1993-05-01

    During the design and development phase of the safety parameter display system for nuclear power plant, a verification and validation (V and V) plan has been implemented to improve the quality of system design. The V and V activities are briefly introduced, which were executed in four stages of feasibility research, system design, code development and system integration and regulation. The evaluation plan and the process of implementation as well as the evaluation conclusion of the final technical validation for this system are also presented in detail

  3. International validation of safety analyses for nuclear power plants; Mednarodno preverjanje varnostnih analiz za jedrske elektrane

    Energy Technology Data Exchange (ETDEWEB)

    Gregoric, N; Mavko, B [Institut ' Jozef Stefan' Ljubljana (Yugoslavia)

    1988-07-01

    Paper describes the participation of 'J.Stefan' Institute in international standard problems for validation of modeling and programs for safety analysis. Listed are main international experimental facilities for collecting data basic for understanding of physical phenomena, code development and validation of modelling and programs. Since the results of international standard problem analyses are published in a joint final report, it is simple to asses the conformance of the results of a particular group with the experiment. Good results from three international exercises done so far, have encouraged the group to currently participate in OECD-ISP-22 which is a model of the Italian three loop PWR. (author)

  4. The development of technologies of safety analysis for LMR ('03)

    International Nuclear Information System (INIS)

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

    2004-03-01

    The developmental objectives of the project, 'The development of safety analysis techniques in LMR', are the code development for the subchannel blockage analysis, the code development for the system transient analysis, the code development for the HCDA(Hypothetical Core Disruptive Accident) analysis, the preliminary safety analysis for KALIMER-600 equipped with the components of new concepts, and the establishment of data base. The purpose of the analysis for subchannel blockage in the subassembly of LMR is to represent quantitatively that the maximum damage due to the accident is within the safety criteria. The computational program should be developed to simulate the thermal hydraulic phenomena and to verify the safety of LMR for the accident. For the purpose, the hybrid scheme has been implemented into the MATRA-LMR code based on the upwind scheme to analyze the various flow fields occurred in the subchannel blockage accident. The turbulent mixing models using the CFX code were assessed to compute more precisely the heat transfer between subchannels. Through this assessment, empirical correction factors of 1.7 for the heat conduction, 0.006 for the turbulent mixing coefficient were obtained. The distributed resistance model instead of wire forcing function has been developed to represent the more exact flow field due to wire-wrap. Other models, such as heat conductor model and various turbulent mixing model, have been implemented into the MATRA-LMR. The ORNL THORS 19-Pin FFM-5B tests have been assessed to validate above new models using the improved MATRA-LMR. The results using MATRA-LMR were well agreed with the experimental data. The subchannel blockage accidents which assumed to be occurred at the three locations for the conceptual plant of KALIMER-600 have been analysed according to blockage size using the MATRA-LMR code. The results of calculations for the design basis events which 6 subchannels were blocked showed the margins of the 290 7.dog. C up to the

  5. Advancing rig design: latest rig technologies improving efficiency and safety

    Energy Technology Data Exchange (ETDEWEB)

    Greenaway, R.

    1997-12-01

    Recent advances in drilling rig technologies that improve the ways for finding oil and natural gas, and are also solving some safety and transportation problems, have been reviewed. The coiled tubing drilling rig developed by joint venture TransOcean Ensign Drilling Technology was one of the innovations described. It is able to run a three-and-a-quarter inch coiled tubing, the only system capable of doing this in a land-based application. Tesco Corporation`s new casing drilling rig, which is expected to lower the cost of moving the rig, and Brinkerhoff Drilling`s new generation modular (NGM)-rig, claimed to be the most mobile rig in North America, are other new developments worthy of note. Tesco`s casing drilling rig has the potential to reduce drilling costs by as much as 30 to 40 per cent, while the NGM-rig could reduce rig mobilization time by 50 to 80 per cent, and the number of wells drilled by the same rig could increase by 20 per cent, due to the NGM-rig`s versatility and flexibility.

  6. Development and Validation of Information Technology Mentor Teacher Attitude Scale: A Pilot Study

    Science.gov (United States)

    Saltan, Fatih

    2015-01-01

    The aim of this study development and validation of a teacher attitude scale toward Information Technology Mentor Teachers (ITMT). ITMTs give technological support to other teachers for integration of technology in their lessons. In the literature, many instruments have been developed to measure teachers' attitudes towards the technological tools…

  7. The development of advanced instrumentation and control technology -The development of verification and validation technology for instrumentation and control in NPPs-

    International Nuclear Information System (INIS)

    Kwon, Kee Choon; Ham, Chang Sik; Lee, Byung Sun; Kim, Jung Taek; Park, Won Man; Park, Jae Chang; Lee, Jang Soo; Um, Heung Sub; Kim, Jang Yul; Ryoo, Chan Hoh; Joo, Jae Yoon; Song, Soon Ja

    1995-07-01

    We collected and analyzed the domestic/international codes, standards and guidelines to develop high reliable software verification and validation methodology which is satisfied to our real situation. The three major parts of work are performed that is the construction of the frame for high reliable software development environment, establishment of high reliable software development methodology and study for the basic technology related to safety-critical software. These three parts are tightly coupled each other to achieve self-reliable software verification and validation technology for digital I and C in NPPs. The configuration of hardware and software are partly performed using requirements which is developed in first stage for the development of I and C test facility. In hardware part, expanded interface using VXI bus and driving software is completed. The main program for math, modelling and supervisor program for instructions are developed. 27 figs, 22 tabs, 69 refs. (Author)

  8. The development of advanced instrumentation and control technology -The development of verification and validation technology for instrumentation and control in NPPs-

    Energy Technology Data Exchange (ETDEWEB)

    Kwon, Kee Choon; Ham, Chang Sik; Lee, Byung Sun; Kim, Jung Taek; Park, Won Man; Park, Jae Chang; Lee, Jang Soo; Um, Heung Sub; Kim, Jang Yul; Ryoo, Chan Hoh; Joo, Jae Yoon; Song, Soon Ja [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1995-07-01

    We collected and analyzed the domestic/international codes, standards and guidelines to develop high reliable software verification and validation methodology which is satisfied to our real situation. The three major parts of work are performed that is the construction of the frame for high reliable software development environment, establishment of high reliable software development methodology and study for the basic technology related to safety-critical software. These three parts are tightly coupled each other to achieve self-reliable software verification and validation technology for digital I and C in NPPs. The configuration of hardware and software are partly performed using requirements which is developed in first stage for the development of I and C test facility. In hardware part, expanded interface using VXI bus and driving software is completed. The main program for math, modelling and supervisor program for instructions are developed. 27 figs, 22 tabs, 69 refs. (Author).

  9. IAEA programme to support development and validation of advanced design and safety analysis codes

    Energy Technology Data Exchange (ETDEWEB)

    Choi, J., E-mail: J.H.Choi@iaea.org [International Atomic Energy Agency, Vienna (Austria)

    2013-07-01

    The International Atomic Energy Agency (IAEA) has been organized many international collaboration programs to support the development and validation of design and safety analysis computer codes for nuclear power plants. These programs are normally implemented with a frame of Coordinated Research Project (CRP) or International Collaborative Standard Problem (ICSP). This paper introduces CRPs and ICSPs currently being organized or recently completed by IAEA for this purpose. (author)

  10. Development and validation of mass spectrometry-based methods for food quality and food safety assessment

    OpenAIRE

    Bignardi, Chiara

    2014-01-01

    In this PhD thesis, analytical chemistry plays a significant role in the assessment of food quality and safety; in particular, three different topics have been addressed to and they are presented into three chapters in which different analytical methodologies have been developed, validated and applied successfully in different topics of food chemistry research. The first chapter is focused on an innovative analytical technique, capillary zone electrophoresis coupled to tandem mass spectrom...

  11. [Development and validation of the Korean patient safety culture scale for nursing homes].

    Science.gov (United States)

    Yoon, Sook Hee; Kim, Byungsoo; Kim, Se Young

    2013-06-01

    The purpose of this study was to develop a tool to evaluate patient safety culture in nursing homes and to test its validity and reliability. A preliminary tool was developed through interviews with focus group, content validity tests, and a pilot study. A nationwide survey was conducted from February to April, 2011, using self-report questionnaires. Participants were 982 employees in nursing homes. Data were analyzed using Cronbach's alpha, item analysis, factor analysis, and multitrait/multi-Item analysis. From the results of the analysis, 27 final items were selected from 49 items on the preliminary tool. Items with low correlation with total scale were excluded. The 4 factors sorted by factor analysis contributed 63.4% of the variance in the total scale. The factors were labeled as leadership, organizational system, working attitude, management practice. Cronbach's alpha for internal consistency was .95 and the range for the 4 factors was from .86 to .93. The results of this study indicate that the Korean Patient Safety Culture Scale has reliability and validity and is suitable for evaluation of patient safety culture in Korean nursing homes.

  12. Method and practice on safety software verification and validation for digital reactor protection system

    International Nuclear Information System (INIS)

    Li Duo; Zhang Liangju; Feng Junting

    2010-01-01

    The key issue arising from digitalization of reactor protection system for Nuclear Power Plant (NPP) is in essence, how to carry out Verification and Validation (V and V), to demonstrate and confirm the software is reliable enough to perform reactor safety functions. Among others the most important activity of software V and V process is unit testing. This paper discusses the basic concepts on safety software V and V and the appropriate technique for software unit testing, focusing on such aspects as how to ensure test completeness, how to establish test platform, how to develop test cases and how to carry out unit testing. The technique discussed herein was successfully used in the work of unit testing on safety software of a digital reactor protection system. (author)

  13. Evaluating driver reactions to new vehicle technologies intended to increase safety and mobility across the lifespan.

    Science.gov (United States)

    2013-05-01

    Personal vehicle manufactures are introducing a wide range of new technologies that are : intended to increase the safety, comfort, and mobility of drivers of all ages. Examples range from : semi-autonomous technologies such as adaptive cruise contro...

  14. The design and validation of advanced operator support systems for a role in plant safety

    International Nuclear Information System (INIS)

    Hughes, G.

    1989-06-01

    Advanced operator support systems have the potential of making a significant contribution to plant safety. This note reviews the different support functions required, the specification of performance criteria and possible approaches for system validation. The importance of the different functions that can be provided is related to the stage of the accident sequence. Also, because of the restricted reliability of any single system, subdivision of the systems is suggested in order to make the maximum contribution at a number of sequential stages. In this way it should be possible to make a significant claim for reduced operator error over the full accident progression, from incipient fault to disaster. The use of performance criteria currently associated with the classification of safety-grade trip systems (e.g. detection failure probability) would seem to provide a sound basis for validation. The validation of systems is seen as a significant task which will rely on the use of design and training-simulator data together with specific plant measurements. Expert systems appear to present particular problems for validation. (author)

  15. A Vision of Quantitative Imaging Technology for Validation of Advanced Flight Technologies

    Science.gov (United States)

    Horvath, Thomas J.; Kerns, Robert V.; Jones, Kenneth M.; Grinstead, Jay H.; Schwartz, Richard J.; Gibson, David M.; Taylor, Jeff C.; Tack, Steve; Dantowitz, Ronald F.

    2011-01-01

    Flight-testing is traditionally an expensive but critical element in the development and ultimate validation and certification of technologies destined for future operational capabilities. Measurements obtained in relevant flight environments also provide unique opportunities to observe flow phenomenon that are often beyond the capabilities of ground testing facilities and computational tools to simulate or duplicate. However, the challenges of minimizing vehicle weight and internal complexity as well as instrumentation bandwidth limitations often restrict the ability to make high-density, in-situ measurements with discrete sensors. Remote imaging offers a potential opportunity to noninvasively obtain such flight data in a complementary fashion. The NASA Hypersonic Thermodynamic Infrared Measurements Project has demonstrated such a capability to obtain calibrated thermal imagery on a hypersonic vehicle in flight. Through the application of existing and accessible technologies, the acreage surface temperature of the Shuttle lower surface was measured during reentry. Future hypersonic cruise vehicles, launcher configurations and reentry vehicles will, however, challenge current remote imaging capability. As NASA embarks on the design and deployment of a new Space Launch System architecture for access beyond earth orbit (and the commercial sector focused on low earth orbit), an opportunity exists to implement an imagery system and its supporting infrastructure that provides sufficient flexibility to incorporate changing technology to address the future needs of the flight test community. A long term vision is offered that supports the application of advanced multi-waveband sensing technology to aid in the development of future aerospace systems and critical technologies to enable highly responsive vehicle operations across the aerospace continuum, spanning launch, reusable space access and global reach. Motivations for development of an Agency level imagery

  16. Improving radiopharmaceutical supply chain safety by implementing bar code technology.

    Science.gov (United States)

    Matanza, David; Hallouard, François; Rioufol, Catherine; Fessi, Hatem; Fraysse, Marc

    2014-11-01

    The aim of this study was to describe and evaluate an approach for improving radiopharmaceutical supply chain safety by implementing bar code technology. We first evaluated the current situation of our radiopharmaceutical supply chain and, by means of the ALARM protocol, analysed two dispensing errors that occurred in our department. Thereafter, we implemented a bar code system to secure selected key stages of the radiopharmaceutical supply chain. Finally, we evaluated the cost of this implementation, from overtime, to overheads, to additional radiation exposure to workers. An analysis of the events that occurred revealed a lack of identification of prepared or dispensed drugs. Moreover, the evaluation of the current radiopharmaceutical supply chain showed that the dispensation and injection steps needed to be further secured. The bar code system was used to reinforce product identification at three selected key stages: at usable stock entry; at preparation-dispensation; and during administration, allowing to check conformity between the labelling of the delivered product (identity and activity) and the prescription. The extra time needed for all these steps had no impact on the number and successful conduct of examinations. The investment cost was reduced (2600 euros for new material and 30 euros a year for additional supplies) because of pre-existing computing equipment. With regard to the radiation exposure to workers there was an insignificant overexposure for hands with this new organization because of the labelling and scanning processes of radiolabelled preparation vials. Implementation of bar code technology is now an essential part of a global securing approach towards optimum patient management.

  17. Ella-V and technology usage technology usage in an english language and literacy acquisition validation randomized controlled trial study

    OpenAIRE

    Roisin P. Corcoran; Steven M. Ross; Beverly J. Irby; Fuhui Tong; Rafael Lara-Alecio; Cindy Guerrero

    2014-01-01

    This paper describes the use of technology to provide virtual professional development (VPD) for teachers and to conduct classroom observations in a study of English Language Learner (ELL) instruction in grades K–3. The technology applications were part of a cluster randomized control trial (RCT) design for a federally funded longitudinal validation study of a particular program, English Language and Literacy Acquisition-Validation, ELLA- V, to determine its degree of impact on English oral l...

  18. Validation of a pre-existing safety climate scale for the Turkish furniture manufacturing industry.

    Science.gov (United States)

    Akyuz, Kadri Cemil; Yildirim, Ibrahim; Gungor, Celal

    2018-03-22

    Understanding the safety climate level is essential to implement a proactive safety program. The objective of this study is to explore the possibility of having a safety climate scale for the Turkish furniture manufacturing industry since there has not been any scale available. The questionnaire recruited 783 subjects. Confirmatory factor analysis (CFA) tested a pre-existing safety scale's fit to the industry. The CFA indicated that the structures of the model present a non-satisfactory fit with the data (χ 2  = 2033.4, df = 314, p ≤ 0.001; root mean square error of approximation = 0.08, normed fit index = 0.65, Tucker-Lewis index = 0.65, comparative fit index = 0.69, parsimony goodness-of-fit index = 0.68). The results suggest that a new scale should be developed and validated to measure the safety climate level in the Turkish furniture manufacturing industry. Due to the hierarchical structure of organizations, future studies should consider a multilevel approach in their exploratory factor analyses while developing a new scale.

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

    International Nuclear Information System (INIS)

    Ets, A.R.

    1993-01-01

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

  20. 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

  1. 78 FR 12065 - National Institute for Occupational Safety and Health Personal Protective Technology for...

    Science.gov (United States)

    2013-02-21

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

  2. [Validation of a questionnaire to evaluate patient safety in clinical laboratories].

    Science.gov (United States)

    Giménez Marín, Ángeles; Rivas-Ruiz, Francisco

    2012-01-01

    The aim of this study was to prepare, pilot and validate a questionnaire to evaluate patient safety in the specific context of clinical laboratories. A specific questionnaire on patient safety in the laboratory, with 62 items grouped into six areas, was developed, taking into consideration the diverse human and laboratory contextual factors which may contribute to producing errors. A pilot study of 30 interviews was carried out, including validity and reliability analyses using principal components factor analysis and Cronbach's alpha. Subsequently, 240 questionnaires were sent to 21 hospitals, followed by a test-retest of 41 questionnaires with the definitive version. The sample analyzed was composed of 225 questionnaires (an overall response rate of 80%). Of the 62 items initially assessed, 17 were eliminated due to non-compliance with the criteria established before the principal components factor analysis was performed. For the 45 remaining items, 12 components were identified, with an cumulative variance of 69.5%. In seven of the 10 components with two or more items, Cronbach's alpha was higher than 0.7. The questionnaire items assessed in the test-retest were found to be stable. We present the first questionnaire with sufficiently proven validity and reliability for evaluating patient safety in the specific context of clinical laboratories. This questionnaire provides a useful instrument to perform a subsequent macrostudy of hospital clinical laboratories in Spain. The questionnaire can also be used to monitor and promote commitment to patient safety within the search for continuous quality improvement. Copyright © 2011 SESPAS. Published by Elsevier Espana. All rights reserved.

  3. 76 FR 39811 - International Center for Technology Assessment and the Center for Food Safety; Noxious Weed...

    Science.gov (United States)

    2011-07-07

    ... dated July 18, 2002, the International Center for Technology Assessment and the Center for Food Safety... Inspection Service [Docket No. APHIS-2011-0081] International Center for Technology Assessment and the Center for Food Safety; Noxious Weed Status of Kentucky Bluegrass Genetically Engineered for Herbicide...

  4. Assessing the validity of road safety evaluation studies by analysing causal chains.

    Science.gov (United States)

    Elvik, Rune

    2003-09-01

    This paper discusses how the validity of road safety evaluation studies can be assessed by analysing causal chains. A causal chain denotes the path through which a road safety measure influences the number of accidents. Two cases are examined. One involves chemical de-icing of roads (salting). The intended causal chain of this measure is: spread of salt --> removal of snow and ice from the road surface --> improved friction --> shorter stopping distance --> fewer accidents. A Norwegian study that evaluated the effects of salting on accident rate provides information that describes this causal chain. This information indicates that the study overestimated the effect of salting on accident rate, and suggests that this estimate is influenced by confounding variables the study did not control for. The other case involves a traffic club for children. The intended causal chain in this study was: join the club --> improve knowledge --> improve behaviour --> reduce accident rate. In this case, results are rather messy, which suggests that the observed difference in accident rate between members and non-members of the traffic club is not primarily attributable to membership in the club. The two cases show that by analysing causal chains, one may uncover confounding factors that were not adequately controlled in a study. Lack of control for confounding factors remains the most serious threat to the validity of road safety evaluation studies.

  5. Sensitivity and uncertainty analyses applied to criticality safety validation, methods development. Volume 1

    International Nuclear Information System (INIS)

    Broadhead, B.L.; Hopper, C.M.; Childs, R.L.; Parks, C.V.

    1999-01-01

    This report presents the application of sensitivity and uncertainty (S/U) analysis methodologies to the code/data validation tasks of a criticality safety computational study. Sensitivity and uncertainty analysis methods were first developed for application to fast reactor studies in the 1970s. This work has revitalized and updated the available S/U computational capabilities such that they can be used as prototypic modules of the SCALE code system, which contains criticality analysis tools currently used by criticality safety practitioners. After complete development, simplified tools are expected to be released for general use. The S/U methods that are presented in this volume are designed to provide a formal means of establishing the range (or area) of applicability for criticality safety data validation studies. The development of parameters that are analogous to the standard trending parameters forms the key to the technique. These parameters are the D parameters, which represent the differences by group of sensitivity profiles, and the ck parameters, which are the correlation coefficients for the calculational uncertainties between systems; each set of parameters gives information relative to the similarity between pairs of selected systems, e.g., a critical experiment and a specific real-world system (the application)

  6. Validation of an Instrument to Measure Students' Motivation and Self-Regulation towards Technology Learning

    Science.gov (United States)

    Liou, Pey-Yan; Kuo, Pei-Jung

    2014-01-01

    Background: Few studies have examined students' attitudinal perceptions of technology. There is no appropriate instrument to measure senior high school students' motivation and self-regulation toward technology learning among the current existing instruments in the field of technology education. Purpose: The present study is to validate an…

  7. The technology for safety I and C systems in nuclear power plants: the SPINLINE 3 solution

    International Nuclear Information System (INIS)

    Rebreyend, P.; Burel, J.-P.

    2000-01-01

    The SPINLINE 3 technology is the latest digital technology produced by Schneider to offer the most adequate solution to safety I and C systems, particularly for modernisation of VVER reactors. This technology developed in co-operation with FRAMATOME has the great advantage of more than 200 reactors x years of cumulated experience in the field of digital safety systems. The design criteria mainly devoted to achieve the most stringent safety requirement are also combined with the economic objectives in term of investment, maintenance and long term operation. The SPINLINE 3 technology is fully supported by the activity on the French Nuclear Program with 59 NPPs in operation. (author)

  8. International report to validate criticality safety calculations for fissile material transport

    International Nuclear Information System (INIS)

    Whitesides, G.E.

    1984-01-01

    During the past three years a Working Group established by the Organization for Economic Co-operation and Development's Nuclear Energy Agency (OECD-NEA) in Paris, France, has been studying the validity and applicability of a variety of criticality safety computer programs and their associated nuclear data for the computation of the neutron multiplication factor, k/sub eff/, for various transport packages used in the fuel cycle. The principal objective of this work has been to provide an internationally acceptable basis for the licensing authorities in a country to honor licensing approvals granted by other participating countries. Eleven countries participated in the initial study which consisted of examining criticality safety calculations for packages designed for spent light water reactor fuel transport. This paper presents a summary of this study which has been completed and reported in an OECD-NEA Report No. CSNI-71. The basic goal of this study was to outline a satisfactory validation procedure for this particular application. First, a set of actual critical experiments were chosen which contained the various material and geometric properties present in typical LWR transport containers. Secondly, calculations were made by each of the methods in order to determine how accurately each method reproduced the experimental values. This successful effort in developing a benchmark procedure for validating criticality calculations for spent LWR transport packages along with the successful intercomparison of a number of methods should provide increased confidence by licensing authorities in the use of these methods for this area of application. 4 references, 2 figures

  9. Assessment of reliability and validity of a new safety culture questionnaire

    Directory of Open Access Journals (Sweden)

    A.A. Farshad

    2010-04-01

    Full Text Available Background and aims   As a Development of Industrial process, human, environment, equipment, material and validity of system has been exposed to hazardous conditions. Regards of 32.3 percent of occupations in industries, this study focused on risk assessment of foundry unit by energy trace and barrier analysis (ETBA method and presented approaches to control of accident.     Methods   the recent study is as a case study one to risk assessment in a foundry unit in Qazvin industrial city in1387. In this study risks were founded by ETBA method and evaluated by MILSTD- 882B. Data were collected by direct observations, interview with workers and supervisor and engineers, walking-talking through method, documents investigation of operational processors, preventive maintenances, equipment technical properties, accidental and medical documents. Finally ETBA worksheets completed.     Results   totally 154 risks has been found. 40 from total are been unacceptable risk, 68 unfavorable and also 46 acceptable but with remediation action. Casting workshop had risks more than other workshops (with 74 identified risks.Potential and heat energies were founded as most   hazardous energies, with respectively 51 and 38 risk cases.     Conclusion   This study recommended to be done actions for identification and control risk, such as: safety training, occupation training, preventive maintenance, contract safety, safety  communication and safety audit group.  

  10. Formal verification and validation of the safety-critical software in a digital reactor protection system

    International Nuclear Information System (INIS)

    Kwon, K. C.; Park, G. Y.

    2006-01-01

    This paper describes the Verification and Validation (V and V) activities for the safety-critical software in a Digital Reactor Protection System (DRPS) that is being developed through the Korea nuclear instrumentation and control system project. The main activities of the DRPS V and V process are a preparation of the software planning documentation, a verification of the software according to the software life cycle, a software safety analysis and a software configuration management. The verification works for the Software Requirement Specification (SRS) of the DRPS consist of a technical evaluation, a licensing suitability evaluation, a inspection and traceability analysis, a formal verification, and preparing a test plan and procedure. Especially, the SRS is specified by the formal specification method in the development phase, and the formal SRS is verified by a formal verification method. Through these activities, we believe we can achieve the functionality, performance, reliability, and safety that are the major V and V objectives of the nuclear safety-critical software in a DRPS. (authors)

  11. Proceedings of the workshop on integral experiment covariance data for critical safety validation

    Energy Technology Data Exchange (ETDEWEB)

    Stuke, Maik (ed.)

    2016-04-15

    For some time, attempts to quantify the statistical dependencies of critical experiments and to account for them properly in validation procedures were discussed in the literature by various groups. Besides the development of suitable methods especially the quality and modeling issues of the freely available experimental data are in the focus of current discussions, carried out for example in the Expert Group on Uncertainty Analysis for Criticality Safety Assessment (UACSA) of the OECD-NEA Nuclear Science Committee. The same committee compiles and publishes also the freely available experimental data in the International Handbook of Evaluated Criticality Safety Benchmark Experiments. Most of these experiments were performed as series and might share parts of experimental setups leading to correlated results. The quality of the determination of these correlations and the underlying covariance data depend strongly on the quality of the documentation of experiments.

  12. Proceedings of the workshop on integral experiment covariance data for critical safety validation

    International Nuclear Information System (INIS)

    Stuke, Maik

    2016-04-01

    For some time, attempts to quantify the statistical dependencies of critical experiments and to account for them properly in validation procedures were discussed in the literature by various groups. Besides the development of suitable methods especially the quality and modeling issues of the freely available experimental data are in the focus of current discussions, carried out for example in the Expert Group on Uncertainty Analysis for Criticality Safety Assessment (UACSA) of the OECD-NEA Nuclear Science Committee. The same committee compiles and publishes also the freely available experimental data in the International Handbook of Evaluated Criticality Safety Benchmark Experiments. Most of these experiments were performed as series and might share parts of experimental setups leading to correlated results. The quality of the determination of these correlations and the underlying covariance data depend strongly on the quality of the documentation of experiments.

  13. Trustworthy Variant Derivation with Translation Validation for Safety Critical Product Lines

    DEFF Research Database (Denmark)

    Iosif-Lazăr, Alexandru Florin; Wasowski, Andrzej

    2016-01-01

    Software product line (SPL) engineering facilitates development of entire families of software products with systematic reuse. Model driven SPLs use models in the design and development process. In the safety critical domain, validation of models and testing of code increases the quality...... of the products altogether. However, to maintain this trustworthiness it is necessary to know that the SPL tools, which manipulate models and code to derive concrete product variants, do not introduce errors in the process. We propose a general technique of checking correctness of product derivation tools through...... translation validation. We demonstrate it using Featherweight VML—a core language for separate variability modeling relying on a single kind of variation point to define transformations of artifacts seen as object models. We use Featherweight VML with its semantics as a correctness specification...

  14. Analysis of Aviation Safety Reporting System Incident Data Associated With the Technical Challenges of the Vehicle Systems Safety Technology Project

    Science.gov (United States)

    Withrow, Colleen A.; Reveley, Mary S.

    2014-01-01

    This analysis was conducted to support the Vehicle Systems Safety Technology (VSST) Project of the Aviation Safety Program (AVsP) milestone VSST4.2.1.01, "Identification of VSST-Related Trends." In particular, this is a review of incident data from the NASA Aviation Safety Reporting System (ASRS). The following three VSST-related technical challenges (TCs) were the focus of the incidents searched in the ASRS database: (1) Vechicle health assurance, (2) Effective crew-system interactions and decisions in all conditions; and (3) Aircraft loss of control prevention, mitigation, and recovery.

  15. 75 FR 15484 - Railroad Safety Technology Program Grant Program

    Science.gov (United States)

    2010-03-29

    ... governments for projects that have a public benefit of improved railroad safety and efficiency. The program... State and local governments for projects * * * that have a public benefit of improved safety and network... minimum 20 percent grantee cost share (cash or in-kind) match requirement. DATES: FRA will begin accepting...

  16. Application of VR and HF technologies for improving industrial safety

    NARCIS (Netherlands)

    Loupos, K.; Christopoulos, D.; Vezzadini, L.; Hoekstra, W.; Salem, W.; Chung, P.W.H.

    2007-01-01

    Safety in industrial environments can nowadays be regarded as an issue of major importance. Large amounts of money are spent by industries on this matter in order to improve safety in all levels, by reducing risks of causing damages to equipment, human injuries or even fatalities. Virtual Reality

  17. Health Information Technology Usability Evaluation Scale (Health-ITUES) for Usability Assessment of Mobile Health Technology: Validation Study.

    Science.gov (United States)

    Schnall, Rebecca; Cho, Hwayoung; Liu, Jianfang

    2018-01-05

    Mobile technology has become a ubiquitous technology and can be particularly useful in the delivery of health interventions. This technology can allow us to deliver interventions to scale, cover broad geographic areas, and deliver technologies in highly tailored ways based on the preferences or characteristics of users. The broad use of mobile technologies supports the need for usability assessments of these tools. Although there have been a number of usability assessment instruments developed, none have been validated for use with mobile technologies. The goal of this work was to validate the Health Information Technology Usability Evaluation Scale (Health-ITUES), a customizable usability assessment instrument in a sample of community-dwelling adults who were testing the use of a new mobile health (mHealth) technology. A sample of 92 community-dwelling adults living with HIV used a new mobile app for symptom self-management and completed the Health-ITUES to assess the usability of the app. They also completed the Post-Study System Usability Questionnaire (PSSUQ), a widely used and well-validated usability assessment tool. Correlations between these scales and each of the subscales were assessed. The subscales of the Health-ITUES showed high internal consistency reliability (Cronbach alpha=.85-.92). Each of the Health-ITUES subscales and the overall scale was moderately to strongly correlated with the PSSUQ scales (r=.46-.70), demonstrating the criterion validity of the Health-ITUES. The Health-ITUES has demonstrated reliability and validity for use in assessing the usability of mHealth technologies in community-dwelling adults living with a chronic illness. ©Rebecca Schnall, Hwayoung Cho, Jianfang Liu. Originally published in JMIR Mhealth and Uhealth (http://mhealth.jmir.org), 05.01.2018.

  18. A critical overview of safety-related and technological criteria for nuclear fuel

    International Nuclear Information System (INIS)

    Lahodova, M.; Valach, M.

    2000-10-01

    A detailed overview of the safety criteria, methods of analysis and computer codes used in OECD countries is presented. A critical analysis of the validity of criteria in the high burnup domain was performed, and recommendations for testing their validity based on available experimental data are put forth. (author)

  19. Are measurements of patient safety culture and adverse events valid and reliable? Results from a cross sectional study.

    Science.gov (United States)

    Farup, Per G

    2015-05-02

    The association between measurements of the patient safety culture and the "true" patient safety has been insufficiently documented, and the validity of the tools used for the measurements has been questioned. This study explored associations between the patient safety culture and adverse events, and evaluated the validity of the tools. In 2008/2009, a survey on patient safety culture was performed with Hospital Survey on Patient Safety Culture (HSOPSC) in two medical departments in two geographically separated hospitals of Innlandet Hospital Trust. Later, a retrospective analysis of adverse events during the same period was performed with the Global Trigger Tool (GTT). The safety culture and adverse events were compared between the departments. 185 employees participated in the study, and 272 patient records were analysed. The HSOPSC scores were lower and adverse events less prevalent in department 1 than in department 2. In departments 1 and 2 the mean HSOPSC scores (SD) were at the unit level 3.62 (0.42) and 3.90 (0.37) (p culture and adverse events. Until the criterion validity of the tools for measuring patient safety culture and tracking of adverse events have been further evaluated, measurement of patient safety culture could not be used as a proxy for the "true" safety.

  20. Validation of nuclear criticality safety software and 27 energy group ENDF/B-IV cross sections. Revision 1

    International Nuclear Information System (INIS)

    Lee, B.L. Jr.; D'Aquila, D.M.

    1996-01-01

    The original validation report, POEF-T-3636, was documented in August 1994. The document was based on calculations that were executed during June through August 1992. The statistical analyses in Appendix C and Appendix D were completed in October 1993. This revision is written to clarify the margin of safety being used at Portsmouth for nuclear criticality safety calculations. This validation gives Portsmouth NCS personnel a basis for performing computerized KENO V.a calculations using the Lockheed Martin Nuclear Criticality Safety Software. The first portion of the document outlines basic information in regard to validation of NCSS using ENDF/B-IV 27-group cross sections on the IBM3090 at ORNL. A basic discussion of the NCSS system is provided, some discussion on the validation database and validation in general. Then follows a detailed description of the statistical analysis which was applied. The results of this validation indicate that the NCSS software may be used with confidence for criticality calculations at the Portsmouth Gaseous Diffusion Plant. For calculations of Portsmouth systems using the specified codes and systems covered by this validation, a maximum k eff including 2σ of 0.9605 or lower shall be considered as subcritical to ensure a calculational margin of safety of 0.02. The validation of NCSS on the IBM 3090 at ORNL was extended to include NCSS on the IBM 3090 at K-25

  1. Proposal for a technology-neutral safety approach for new reactor designs

    International Nuclear Information System (INIS)

    2007-09-01

    Many states are considering an expansion of their nuclear power generation programmes. Many of the technologies and concepts are new and innovative. The current design and licensing rules are applicable to mostly large water reactors and there are no accepted rules in place for design, safety assessment and licensing for new innovative nuclear power plants. This TECDOC proposes a (new) safety approach and a methodology to generate technology-neutral (i.e. independent of reactor technology) safety requirements and a 'safe design' for advanced and innovative reactors. The experience gained in decades of design and licensing, combined with the development of risk-based concepts, has provided insights that will form the basis for new safety rules and requirements. Many lessons learned acknowledge the importance of such concepts as safety goals and defence in depth and the benefits of integrating risk insights early in an iterative design process. A new safety approach will incorporate many of the new developments in these concepts. For example, the probabilistic elements of defence in depth will help define the cumulative provisions to compensate for uncertainty and incompleteness of our knowledge of accident initiation and progression. This TECDOC also identifies areas of work, which will require further definition, research and development and guidance on application. This publication is to be used as a guide to developing a new technology-neutral safety approach, and as a guide in the application of methodologies to define the safety requirements for an innovative reactor designs. The method proposes an integration of deterministic and probabilistic considerations with established principles and concepts such as safety goals and defence in depth. The TECDOC recommends that the structure of the new technology-neutral main pillars for the design and licensing of innovative nuclear reactors be developed following a top-down approach to reflect a newer risk-informed and

  2. Electrically Driven Thermal Management: Flight Validation, Experiment Development, Future Technologies

    Science.gov (United States)

    Didion, Jeffrey R.

    2018-01-01

    Electrically Driven Thermal Management is an active research and technology development initiative incorporating ISS technology flight demonstrations (STP-H5), development of Microgravity Science Glovebox (MSG) flight experiment, and laboratory-based investigations of electrically based thermal management techniques. The program targets integrated thermal management for future generations of RF electronics and power electronic devices. This presentation reviews four program elements: i.) results from the Electrohydrodynamic (EHD) Long Term Flight Demonstration launched in February 2017 ii.) development of the Electrically Driven Liquid Film Boiling Experiment iii.) two University based research efforts iv.) development of Oscillating Heat Pipe evaluation at Goddard Space Flight Center.

  3. Safety Performance Indicator for alcohol in road accidents--international comparison, validity and data quality.

    Science.gov (United States)

    Assum, Terje; Sørensen, Michael

    2010-03-01

    Safety Performance Indicators, SPIs, are developed for various areas within road safety such as speed, car occupant protection, alcohol and drugs, vehicle safety, etc. SPIs can be used to indicate the road safety situation and to compare road safety performance between countries and over time and to understand the process leading to accidents, helping to select the measures to reduce them. This article describes an alcohol SPI defined as the percentage of fatalities resulting from accidents involving at least one driver impaired by alcohol. The calculation of the alcohol SPI for 26 European countries shows that the SPI varies from 4.4% in Bulgaria to 72.2% in Italy. These results raise the question if the results reflect the real situation or if there is a methodological explanation. To answer this question three different studies were carried out: comparison with other alcohol SPIs, in-depth studies of data quality in seven selected countries, and a study of correlations between the SPI and influencing factors. These studies indicate clearly that there is a need to improve quality of the data used for the alcohol SPI. Most importantly, the total number of drivers involved in fatal accidents, the number tested for alcohol and the number not tested, should be reported, in addition to the number of alcohol positive and negative drivers among those tested. Until these improvements are made, the validity of this SPI seems poor and comparison of the alcohol SPI results across countries should be made with caution. Copyright 2009 Elsevier Ltd. All rights reserved.

  4. The Sandia MEMS Passive Shock Sensor : FY08 testing for functionality, model validation, and technology readiness.

    Energy Technology Data Exchange (ETDEWEB)

    Walraven, Jeremy Allen; Blecke, Jill; Baker, Michael Sean; Clemens, Rebecca C.; Mitchell, John Anthony; Brake, Matthew Robert; Epp, David S.; Wittwer, Jonathan W.

    2008-10-01

    This report summarizes the functional, model validation, and technology readiness testing of the Sandia MEMS Passive Shock Sensor in FY08. Functional testing of a large number of revision 4 parts showed robust and consistent performance. Model validation testing helped tune the models to match data well and identified several areas for future investigation related to high frequency sensitivity and thermal effects. Finally, technology readiness testing demonstrated the integrated elements of the sensor under realistic environments.

  5. Connecting Technological Innovation in Artificial Intelligence to Real-world Medical Practice through Rigorous Clinical Validation: What Peer-reviewed Medical Journals Could Do

    Science.gov (United States)

    2018-01-01

    Artificial intelligence (AI) is projected to substantially influence clinical practice in the foreseeable future. However, despite the excitement around the technologies, it is yet rare to see examples of robust clinical validation of the technologies and, as a result, very few are currently in clinical use. A thorough, systematic validation of AI technologies using adequately designed clinical research studies before their integration into clinical practice is critical to ensure patient benefit and safety while avoiding any inadvertent harms. We would like to suggest several specific points regarding the role that peer-reviewed medical journals can play, in terms of study design, registration, and reporting, to help achieve proper and meaningful clinical validation of AI technologies designed to make medical diagnosis and prediction, focusing on the evaluation of diagnostic accuracy efficacy. Peer-reviewed medical journals can encourage investigators who wish to validate the performance of AI systems for medical diagnosis and prediction to pay closer attention to the factors listed in this article by emphasizing their importance. Thereby, peer-reviewed medical journals can ultimately facilitate translating the technological innovations into real-world practice while securing patient safety and benefit.

  6. Connecting Technological Innovation in Artificial Intelligence to Real-world Medical Practice through Rigorous Clinical Validation: What Peer-reviewed Medical Journals Could Do.

    Science.gov (United States)

    Park, Seong Ho; Kressel, Herbert Y

    2018-05-28

    Artificial intelligence (AI) is projected to substantially influence clinical practice in the foreseeable future. However, despite the excitement around the technologies, it is yet rare to see examples of robust clinical validation of the technologies and, as a result, very few are currently in clinical use. A thorough, systematic validation of AI technologies using adequately designed clinical research studies before their integration into clinical practice is critical to ensure patient benefit and safety while avoiding any inadvertent harms. We would like to suggest several specific points regarding the role that peer-reviewed medical journals can play, in terms of study design, registration, and reporting, to help achieve proper and meaningful clinical validation of AI technologies designed to make medical diagnosis and prediction, focusing on the evaluation of diagnostic accuracy efficacy. Peer-reviewed medical journals can encourage investigators who wish to validate the performance of AI systems for medical diagnosis and prediction to pay closer attention to the factors listed in this article by emphasizing their importance. Thereby, peer-reviewed medical journals can ultimately facilitate translating the technological innovations into real-world practice while securing patient safety and benefit.

  7. Prioritization of tasks in the draft LWR safety technology program plan. Final report

    International Nuclear Information System (INIS)

    Lim, E.Y.; Miller, W.J.; Parkinson, W.J.; Ritzman, R.L.; vonHerrmann, J.L.; Wood, P.J.

    1980-05-01

    The purpose of this report is to describe both the approach taken and the results produced in the SAI effort to prioritize the tasks in the Sandia draft LWR Safety Technology Program Plan. This work used the description of important safety issues developed in the Reactor Safety Study (2) to quantify the effect of safety improvements resulting from a research and development program on the risk from nuclear power plants. Costs of implementation of these safety improvements were also estimated to allow a presentation of the final results in a value (i.e., risk reduction) vs. impact (i.e., implementation costs) matrix

  8. Analytical methodology for safety validation of computer controlled subsystems. Volume 1 : state-of-the-art and assessment of safety verification/validation methodologies

    Science.gov (United States)

    1995-09-01

    This report describes the development of a methodology designed to assure that a sufficiently high level of safety is achieved and maintained in computer-based systems which perform safety critical functions in high-speed rail or magnetic levitation ...

  9. KAERI software verification and validation guideline for developing safety-critical software in digital I and C system of NPP

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Jang Yeol; Lee, Jang Soo; Eom, Heung Seop

    1997-07-01

    This technical report is to present V and V guideline development methodology for safety-critical software in NPP safety system. Therefore it is to present V and V guideline of planning phase for the NPP safety system in addition to critical safety items, for example, independence philosophy, software safety analysis concept, commercial off the shelf (COTS) software evaluation criteria, inter-relationships between other safety assurance organizations, including the concepts of existing industrial standard, IEEE Std-1012, IEEE Std-1059. This technical report includes scope of V and V guideline, guideline framework as part of acceptance criteria, V and V activities and task entrance as part of V and V activity and exit criteria, review and audit, testing and QA records of V and V material and configuration management, software verification and validation plan production etc., and safety-critical software V and V methodology. (author). 11 refs.

  10. KAERI software verification and validation guideline for developing safety-critical software in digital I and C system of NPP

    International Nuclear Information System (INIS)

    Kim, Jang Yeol; Lee, Jang Soo; Eom, Heung Seop.

    1997-07-01

    This technical report is to present V and V guideline development methodology for safety-critical software in NPP safety system. Therefore it is to present V and V guideline of planning phase for the NPP safety system in addition to critical safety items, for example, independence philosophy, software safety analysis concept, commercial off the shelf (COTS) software evaluation criteria, inter-relationships between other safety assurance organizations, including the concepts of existing industrial standard, IEEE Std-1012, IEEE Std-1059. This technical report includes scope of V and V guideline, guideline framework as part of acceptance criteria, V and V activities and task entrance as part of V and V activity and exit criteria, review and audit, testing and QA records of V and V material and configuration management, software verification and validation plan production etc., and safety-critical software V and V methodology. (author). 11 refs

  11. Development and Validation of a Short-Form Safety Net Medical Home Scale.

    Science.gov (United States)

    Nocon, Robert S; Gunter, Kathryn E; Gao, Yue; Lee, Sang Mee; Chin, Marshall H

    2017-12-01

    To develop a short-form Safety Net Medical Home Scale (SNMHS) for assessing patient-centered medical home (PCMH) capability in safety net clinics. National surveys of federally qualified health centers (FQHCs). Interviews with FQHC directors. We constructed three short-form SNMHS versions and examined correlations with full SNMHS and related primary care assessments. We tested usability with FQHC directors and reviewed scale development with an advisory group. Federally qualified health center surveys were administered in 2009 and 2013, by mail and online. Usability testing was conducted through telephone interviews with FQHC directors in 2013. Six-, 12-, and 18-question short-form SNMHS versions had Pearson correlations with full scale of 0.84, 0.92, and 0.96, respectively. All versions showed a level of convergent validity with other primary care assessment scales comparable to the full SNMHS. User testers found short forms to be low-burden, though missing some PCMH concepts. Advisory group members expressed caution over missing concepts and appropriate use of short-form self-assessments. Short-form versions of SNMHS showed strong correlations with full scale and may be useful for brief assessment of safety net PCMH capability. Each short-form SNMHS version may be appropriate for different research, quality improvement, and assessment purposes. © Health Research and Educational Trust.

  12. Validation of a preclinical spinal safety model: effects of intrathecal morphine in the neonatal rat.

    Science.gov (United States)

    Westin, B David; Walker, Suellen M; Deumens, Ronald; Grafe, Marjorie; Yaksh, Tony L

    2010-07-01

    Preclinical studies demonstrate increased neuroapoptosis after general anesthesia in early life. Neuraxial techniques may minimize potential risks, but there has been no systematic evaluation of spinal analgesic safety in developmental models. We aimed to validate a preclinical model for evaluating dose-dependent efficacy, spinal cord toxicity, and long-term function after intrathecal morphine in the neonatal rat. Lumbar intrathecal injections were performed in anesthetized rats aged postnatal day (P) 3, 10, and 21. The relationship between injectate volume and segmental spread was assessed postmortem and by in vivo imaging. To determine the antinociceptive dose, mechanical withdrawal thresholds were measured at baseline and 30 min after intrathecal morphine. To evaluate toxicity, doses up to the maximum tolerated were administered, and spinal cord histopathology, apoptosis, and glial response were evaluated 1 and 7 days after P3 or P21 injection. Sensory thresholds and gait analysis were evaluated at P35. Intrathecal injection can be reliably performed at all postnatal ages and injectate volume influences segmental spread. Intrathecal morphine produced spinally mediated analgesia at all ages with lower dose requirements in younger pups. High-dose intrathecal morphine did not produce signs of spinal cord toxicity or alter long-term function. The therapeutic ratio for intrathecal morphine (toxic dose/antinociceptive dose) was at least 300 at P3 and at least 20 at P21 (latter doses limited by side effects). These data provide relative efficacy and safety for comparison with other analgesic preparations and contribute supporting evidence for the validity of this preclinical neonatal safety model.

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

    International Nuclear Information System (INIS)

    1990-01-01

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

  14. Generation of integral experiment covariance data and their impact on criticality safety validation

    Energy Technology Data Exchange (ETDEWEB)

    Stuke, Maik; Peters, Elisabeth; Sommer, Fabian

    2016-11-15

    The quantification of statistical dependencies in data of critical experiments and how to account for them properly in validation procedures has been discussed in the literature by various groups. However, these subjects are still an active topic in the Expert Group on Uncertainty Analysis for Criticality Safety Assessment (UACSA) of the OECDNEA Nuclear Science Committee. The latter compiles and publishes the freely available experimental data collection, the International Handbook of Evaluated Criticality Safety Benchmark Experiments, ICSBEP. Most of the experiments were performed as series and share parts of experimental setups, consequently leading to correlation effects in the results. The correct consideration of correlated data seems to be inevitable if the experimental data in a validation procedure is limited or one cannot rely on a sufficient number of uncorrelated data sets, e.g. from different laboratories using different setups. The general determination of correlations and the underlying covariance data as well as the consideration of them in a validation procedure is the focus of the following work. We discuss and demonstrate possible effects on calculated k{sub eff}'s, their uncertainties, and the corresponding covariance matrices due to interpretation of evaluated experimental data and its translation into calculation models. The work shows effects of various modeling approaches, varying distribution functions of parameters and compares and discusses results from the applied Monte-Carlo sampling method with available data on correlations. Our findings indicate that for the reliable determination of integral experimental covariance matrices or the correlation coefficients a detailed study of the underlying experimental data, the modeling approach and assumptions made, and the resulting sensitivity analysis seems to be inevitable. Further, a Bayesian method is discussed to include integral experimental covariance data when estimating an

  15. Generation of integral experiment covariance data and their impact on criticality safety validation

    International Nuclear Information System (INIS)

    Stuke, Maik; Peters, Elisabeth; Sommer, Fabian

    2016-11-01

    The quantification of statistical dependencies in data of critical experiments and how to account for them properly in validation procedures has been discussed in the literature by various groups. However, these subjects are still an active topic in the Expert Group on Uncertainty Analysis for Criticality Safety Assessment (UACSA) of the OECDNEA Nuclear Science Committee. The latter compiles and publishes the freely available experimental data collection, the International Handbook of Evaluated Criticality Safety Benchmark Experiments, ICSBEP. Most of the experiments were performed as series and share parts of experimental setups, consequently leading to correlation effects in the results. The correct consideration of correlated data seems to be inevitable if the experimental data in a validation procedure is limited or one cannot rely on a sufficient number of uncorrelated data sets, e.g. from different laboratories using different setups. The general determination of correlations and the underlying covariance data as well as the consideration of them in a validation procedure is the focus of the following work. We discuss and demonstrate possible effects on calculated k eff 's, their uncertainties, and the corresponding covariance matrices due to interpretation of evaluated experimental data and its translation into calculation models. The work shows effects of various modeling approaches, varying distribution functions of parameters and compares and discusses results from the applied Monte-Carlo sampling method with available data on correlations. Our findings indicate that for the reliable determination of integral experimental covariance matrices or the correlation coefficients a detailed study of the underlying experimental data, the modeling approach and assumptions made, and the resulting sensitivity analysis seems to be inevitable. Further, a Bayesian method is discussed to include integral experimental covariance data when estimating an application

  16. Safety of light water reactors. Risks of nuclear technology

    International Nuclear Information System (INIS)

    Veser, Anke; Schlueter, Franz-Hermann; Raskob, Wolfgang; Landman, Claudia; Paesler-Sauer, Juergen; Kessler, Guenter

    2012-01-01

    The book on the safety of light-water reactors includes the following chapters: Part I: Physical and technical safety concept of actual German and future European light-water reactors: (1) Worldwide operated nuclear power plants in 2011, (2) Some reactor physical fundamentals. (3) Nuclear power plants in Germany. (4) Radioactive exposure due to nuclear power plants. (5) Safety concept of light-water reactors. (6) Probabilistic analyses and risk studies. (7) Design of light-water reactors against external incidents. (8) Risk comparison of nuclear power plants and other energy systems. (9) Evaluation of risk studies using the improved (new) safety concept for LWR. (19) The severe reactor accidents of Three Mile Island, Chernobyl and Fukushima. Part II: Safety of German LWR in case of a postulated aircraft impact. (11) Literature. (12) Review of requirements and actual design. (13) Incident scenarios. (14) Load approach for aircraft impact. (15) Demonstration of the structural behavior in case of aircraft impact. (16) Special considerations. (17) Evaluation of the safety state of German and foreign nuclear power plants. Part III: ROSOS as example for a computer-based decision making support system for the severe accident management. (19) Literature. (20) Radiological fundamentals, accident management, modeling of the radiological situation. (21) The decision making support system RODOS. (22) RODOS and the Fukushima accident. (23) Recent developments in the radiological emergency management in the European frame.

  17. Validation and Verification (V&V) of Safety-Critical Systems Operating Under Off-Nominal Conditions

    Science.gov (United States)

    Belcastro, Christine M.

    2012-01-01

    Loss of control (LOC) remains one of the largest contributors to aircraft fatal accidents worldwide. Aircraft LOC accidents are highly complex in that they can result from numerous causal and contributing factors acting alone or more often in combination. Hence, there is no single intervention strategy to prevent these accidents. Research is underway at the National Aeronautics and Space Administration (NASA) in the development of advanced onboard system technologies for preventing or recovering from loss of vehicle control and for assuring safe operation under off-nominal conditions associated with aircraft LOC accidents. The transition of these technologies into the commercial fleet will require their extensive validation and verification (V&V) and ultimate certification. The V&V of complex integrated systems poses highly significant technical challenges and is the subject of a parallel research effort at NASA. This chapter summarizes the V&V problem and presents a proposed process that could be applied to complex integrated safety-critical systems developed for preventing aircraft LOC accidents. A summary of recent research accomplishments in this effort is referenced.

  18. VATE: VAlidation of high TEchnology based on large database analysis by learning machine

    NARCIS (Netherlands)

    Meldolesi, E; Van Soest, J; Alitto, A R; Autorino, R; Dinapoli, N; Dekker, A; Gambacorta, M A; Gatta, R; Tagliaferri, L; Damiani, A; Valentini, V

    2014-01-01

    The interaction between implementation of new technologies and different outcomes can allow a broad range of researches to be expanded. The purpose of this paper is to introduce the VAlidation of high TEchnology based on large database analysis by learning machine (VATE) project that aims to combine

  19. Factors in Decisions to Make, Purchase, and Use On-board Safety Technologies

    Science.gov (United States)

    2005-12-01

    In support of its goal to reduce large truck-related fatalities and crashes, FMCSA plans to facilitate the deployment of Intelligent Vehicle Initiative (IVI) technologies that have shown a potential to improve the safety of commercial vehicle operati...

  20. 78 FR 17140 - Upholstered Furniture Fire Safety Technology; Meeting and Request for Comments

    Science.gov (United States)

    2013-03-20

    ... retardant (FR) chemicals, specialty fibers/fabrics without FR chemicals, inherently fire resistant materials... Furniture Fire Safety Technology; Meeting and Request for Comments AGENCY: Consumer Product Safety... Commission (CPSC, Commission, or we) is announcing its intent to hold a meeting on upholstered furniture fire...

  1. 76 FR 31350 - Cruise Vessel Safety and Security Act of 2010, Available Technology

    Science.gov (United States)

    2011-05-31

    ... DEPARTMENT OF HOMELAND SECURITY Coast Guard [Docket No. USCG-2011-0357] Cruise Vessel Safety and Security Act of 2010, Available Technology AGENCY: Coast Guard, DHS. ACTION: Notice of request for comments... Security and Safety Act of 2010(CVSSA), specifically related to video recording and overboard detection...

  2. Proceedings of the First Seminar on Radiation Safety Technology and Nuclear Biomedicine

    International Nuclear Information System (INIS)

    Suprihadi, Topo

    2003-01-01

    The First Seminar on Radiation Safety Technology and Nuclear Biomedicine was held on 10-11 April 2001 at the Center for Research and Development of Radiation Safety and Nuclear Biomedicine have presented 19 papers about upgrading manpower resources, researcher, investigator, manager, and user of nuclear facilities, to go out against free market era

  3. Development of Strategic Technology Road map for Establishing Safety Infrastructure of Fusion Energy

    International Nuclear Information System (INIS)

    Han, B. S.; Cho, S. H.; Kam, S. C.; Kim, K. T.

    2009-01-01

    The Korean Government established an 'Act for the Promotion of Fusion Energy Development (APFED)' and formulated a 'Strategy Promotion Plan for Fusion Energy Development.' KINS has carried out a safety review of KSTAR (Korea Superconducting Tokamak Advanced Research), for which an application for use was received in 2002 and the license was issued in August 2007. With respect to the APFED, 'Atomic Energy Acts (AEAs)' shall apply in the fusion safety regulation. However the AEAs are not applicable because they aim for dealing with nuclear energy. In this regard, this study was planned to establish safety infrastructure for fusion energy and to develop technologies necessary for verifying the safety. The purpose of this study is to develop a 'Strategic Technology Roadmap (STR) for establishing safety infrastructure of the fusion energy', which displays the content and development schedule and strategy for developing the laws, safety goals and principles, and safety standards applicable for fusion safety regulation, and core technology required for safety regulation of fusion facilities

  4. 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.

  5. STUDY ON SAFETY TECHNOLOGY SCHEME OF THE UNMANNED HELICOPTER

    Directory of Open Access Journals (Sweden)

    Z. Lin

    2013-08-01

    Full Text Available Nowadays the unmanned helicopter is widely used for its' unique strongpoint, however, the high failure rate of unmanned helicopter seriously limits its further application and development. For solving the above problems, in this paper, the reasons for the high failure rate of unmanned helicopter is analyzed and the corresponding solution schemes are proposed. The main problem of the failure cause of the unmanned helicopter is the aircraft engine fault, and the failure cause of the unmanned helicopter is analyzed particularly. In order to improving the safety performance of unmanned helicopter system, the scheme of adding the safety parachute system to the unmanned helicopter system is proposed and introduced. These schemes provide the safety redundancy of the unmanned helicopter system and lay on basis for the unmanned helicopter applying into residential areas.

  6. Validation Study on the MCC-based Technology

    International Nuclear Information System (INIS)

    Park, Sungkeun; Lee, Dowhan; Kang, Shincheul; Choi, Hyunwoo; Chai, Jangbom

    2006-01-01

    KEPRI and M and D Corporation has developed a methodology, called the NEST I (Non-intrusive Evaluation of Stem Thrust), for determining the stem thrust for a Motor Operated Valve (MOV) based on the motor torque and the stem displacement. The motor torque is determined using another method called NEET (Non-intrusive Evaluation of Electric Torque) which uses the voltage and current data from three phases to obtain the motor torque. The stem displacement is obtained from the voltage and current data along with the nameplate information of the motor, actuator and stem. The motor data (voltage, current and coil current) are measured using MOVIDS (Motor Operated Valve Intelligent Diagnostic System). The motor torque is determined using a NEET algorithm and the stem thrust is calculated using the NEST I method. The goal of this testing was to obtain data from operation of a MOV and to compare the actual measured thrust with the thrust calculated using the NEET / NEST I methods and therefore validate the NEET / NEST I methods

  7. Technology development of maintenance optimization and reliability analysis for safety features in nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Tae Woon; Choi, Seong Soo; Lee, Dong Gue; Kim, Young Il

    1999-12-01

    The reliability data management system (RDMS) for safety systems of PHWR type plants has been developed and utilized in the reliability analysis of the special safety systems of Wolsong Unit 1,2 with plant overhaul period lengthened. The RDMS is developed for the periodic efficient reliability analysis of the safety systems of Wolsong Unit 1,2. In addition, this system provides the function of analyzing the effects on safety system unavailability if the test period of a test procedure changes as well as the function of optimizing the test periods of safety-related test procedures. The RDMS can be utilized in handling the requests of the regulatory institute actively with regard to the reliability validation of safety systems. (author)

  8. Development and validation of three-dimensional CFD techniques for reactor safety applications. Final report

    International Nuclear Information System (INIS)

    Buchholz, Sebastian; Palazzo, Simone; Papukchiev, Angel; Scheurer Martina

    2016-12-01

    The overall goal of the project RS 1506 ''Development and Validation of Three Dimensional CFD Methods for Reactor Safety Applications'' is the validation of Computational Fluid Dynamics (CFD) software for the simulation of three -dimensional thermo-hydraulic heat and fluid flow phenomena in nuclear reactors. For this purpose a wide spectrum of validation and test cases was selected covering fluid flow and heat transfer phenomena in the downcomer and in the core of pressurized water reactors. In addition, the coupling of the system code ATHLET with the CFD code ANSYS CFX was further developed and validated. The first choice were UPTF experiments where turbulent single- and two-phase flows were investigated in a 1:1 scaled model of a German KONVOI reactor. The scope of the CFD calculations covers thermal mixing and stratification including condensation in single- and two-phase flows. In the complex core region, the flow in a fuel assembly with spacer grid was simulated as defined in the OECD/NEA Benchmark MATIS-H. Good agreement are achieved when the geometrical and physical boundary conditions were reproduced as realistic as possible. This includes, in particular, the consideration of heat transfer to walls. The influence of wall modelling on CFD results was investigated on the TALL-3D T01 experiment. In this case, the dynamic three dimensional fluid flow and heat transfer phenomena were simulated in a Generation IV liquid metal cooled reactor. Concurrently to the validation work, the coupling of the system code ATHLET with the ANSYS CFX software was optimized and expanded for two-phase flows. Different coupling approaches were investigated, in order to overcome the large difference between CPU-time requirements of system and CFD codes. Finally, the coupled simulation system was validated by applying it to the simulation of the PSI double T-junction experiment, the LBE-flow in the MYRRA Spallation experiment and a demonstration test case simulating a pump trip

  9. LESSONS LEARNED IN DEVELOPMENT OF THE HANFORD SWOC MASTER DOCUMENTED SAFETY ANALYSIS (MDSA) and IMPLEMENTATION VALIDATION REVIEW (IVR)

    International Nuclear Information System (INIS)

    MORENO, M.R.

    2004-01-01

    DOE set clear expectations on a cost-effective approach for achieving compliance with the Nuclear Safety Management requirements (20 CFR 830, Nuclear Safety Rule), which ensured long-term benefit to Hanford, via issuance of a nuclear safety strategy in February 2003. To facilitate implementation of these expectations, tools were developed to streamline and standardize safety analysis and safety document development with the goal of a shorter and more predictable DOE approval cycle. A Hanford Safety Analysis and Risk Assessment Handbook (SARAH) was approved to standardize methodologies for development of safety analyses. A Microsoft Excel spreadsheet (RADIDOSE) was approved for the evaluation of radiological consequences for accident scenarios often postulated at Hanford. Standard safety management program chapters were approved for use as a means of compliance with the programmatic chapters of DOE-STD-3009, ''Preparation Guide for U.S. Department of Energy Nonreactor Nuclear Facility Safety Analysis Reports''. An in-process review was developed between DOE and the Contractor to facilitate DOE approval and provide early course correction. The new Documented Safety Analysis (DSA) developed to address the operations of four facilities within the Solid Waste Operations Complex (SWOC) necessitated development of an Implementation Validation Review (IVR) process. The IVR process encompasses the following objectives: safety basis controls and requirements are adequately incorporated into appropriate facility documents and work instructions, facility personnel are knowledgeable of controls and requirements, and the DSA/TSR controls have been implemented. Based on DOE direction and safety analysis tools, four waste management nuclear facilities were integrated into one safety basis document. With successful completion of implementation of this safety document, lessons-learned from the in-process review, safety analysis tools and IVR process were documented for future action

  10. Results of a survey on accident and safety analysis codes, benchmarks, verification and validation methods

    International Nuclear Information System (INIS)

    Lee, A.G.; Wilkin, G.B.

    1996-03-01

    During the 'Workshop on R and D needs' at the 3rd Meeting of the International Group on Research Reactors (IGORR-III), the participants agreed that it would be useful to compile a survey of the computer codes and nuclear data libraries used in accident and safety analyses for research reactors and the methods various organizations use to verify and validate their codes and libraries. Five organizations, Atomic Energy of Canada Limited (AECL, Canada), China Institute of Atomic Energy (CIAE, People's Republic of China), Japan Atomic Energy Research Institute (JAERI, Japan), Oak Ridge National Laboratories (ORNL, USA), and Siemens (Germany) responded to the survey. The results of the survey are compiled in this report. (author) 36 refs., 3 tabs

  11. New reactor technology: safety improvements in nuclear power systems.

    Science.gov (United States)

    Corradini, M L

    2007-11-01

    Almost 450 nuclear power plants are currently operating throughout the world and supplying about 17% of the world's electricity. These plants perform safely, reliably, and have no free-release of byproducts to the environment. Given the current rate of growth in electricity demand and the ever growing concerns for the environment, nuclear power can only satisfy the need for electricity and other energy-intensive products if it can demonstrate (1) enhanced safety and system reliability, (2) minimal environmental impact via sustainable system designs, and (3) competitive economics. The U.S. Department of Energy with the international community has begun research on the next generation of nuclear energy systems that can be made available to the market by 2030 or earlier, and that can offer significant advances toward these challenging goals; in particular, six candidate reactor system designs have been identified. These future nuclear power systems will require advances in materials, reactor physics, as well as thermal-hydraulics to realize their full potential. However, all of these designs must demonstrate enhanced safety above and beyond current light water reactor systems if the next generation of nuclear power plants is to grow in number far beyond the current population. This paper reviews the advanced Generation-IV reactor systems and the key safety phenomena that must be considered to guarantee that enhanced safety can be assured in future nuclear reactor systems.

  12. Safety and Liability in the New Technology Laboratory

    Science.gov (United States)

    Haynie, W. J., III

    2009-01-01

    All laboratories, even modern high-tech ones, have some degree of hazard potential. It is the teacher's responsibility to make the lab as safe as possible and to do all that is reasonable and prudent to prevent accidents. The teacher's goal should be to insure the safety of every student. This goal is met best via well-planned instruction and…

  13. 78 FR 66987 - Railroad Safety Technology Program Grant Program

    Science.gov (United States)

    2013-11-07

    ... carriers, railroad suppliers, and State and local governments for projects that have a public benefit of... projects . . . that have a public benefit of improved safety and network efficiency.'' To be eligible for... million. This grant program has a maximum 80-percent Federal and minimum 20-percent grantee cost share...

  14. Miles, speed, and technology: Traffic safety under oligopolistic insurance

    NARCIS (Netherlands)

    Dementieva, M.; Verhoef, E.T.

    2016-01-01

    We study road safety when insurance companies have market power, and can influence drivers' behavior via insurance premiums. We obtain first- and second-best premiums for different insurance market structures. The insurance program consists of an insurance premium, and marginal dependencies of that

  15. 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.

  16. Laser technology to manage periodontal disease: a valid concept?

    Science.gov (United States)

    Low, Samuel B; Mott, Angie

    2014-06-01

    Present day dental lasers can create oral environments conducive for periodontal repair. With the bacterial etiology of periodontitis and the resulting host inflammatory reaction, clinicians continue to search for therapeutic modalities to assist in the non-surgical management of periodontal disease. Traditional chairside therapies consist of mechanical debridement with manual and/or ultrasonic instrumentation with the objective of removing calculus, biofilm, and endotoxin from tooth root surfaces. Decreasing the microbial stimuli and associated end products decreases the inflammatory reaction and allows the host an opportunity to regenerate tissue through wound healing. The purpose of this article is to examine whether dental lasers, which have been in use for the past 3 decades, may augment traditional non-surgical periodontal therapy. Review of research publications related to lasers and non-surgical periodontics with attention focused on systematic studies. Studies utilizing laser technology may demonstrate positive effects on 1) selectively decreasing the biofilm environment, 2) removing calculus deposits and neutralizing endotoxin, 3) removing sulcular epithelium to assist in reattachment and decreased pocket depth, and 4) biostimulation for enhanced wound healing. Comparisons of studies to determine the difference between lasers and their respective effects on the periodontium are difficult to assess due to a wide variation of laser protocols. Copyright © 2014 Elsevier Inc. All rights reserved.

  17. Development and validation of safety climate scales for mobile remote workers using utility/electrical workers as exemplar.

    Science.gov (United States)

    Huang, Yueng-Hsiang; Zohar, Dov; Robertson, Michelle M; Garabet, Angela; Murphy, Lauren A; Lee, Jin

    2013-10-01

    The objective of this study was to develop and test the reliability and validity of a new scale designed for measuring safety climate among mobile remote workers, using utility/electrical workers as exemplar. The new scale employs perceived safety priority as the metric of safety climate and a multi-level framework, separating the measurement of organization- and group-level safety climate items into two sub-scales. The question of the emergence of shared perceptions among remote workers was also examined. For the initial survey development, several items were adopted from a generic safety climate scale and new industry-specific items were generated based on an extensive literature review, expert judgment, 15-day field observations, and 38 in-depth individual interviews with subject matter experts (i.e., utility industry electrical workers, trainers and supervisors of electrical workers). The items were revised after 45 cognitive interviews and a pre-test with 139 additional utility/electrical workers. The revised scale was subsequently implemented with a total of 2421 workers at two large US electric utility companies (1560 participants for the pilot company and 861 for the second company). Both exploratory (EFA) and confirmatory factor analyses (CFA) were adopted to finalize the items and to ensure construct validity. Reliability of the scale was tested based on Cronbach's α. Homogeneity tests examined whether utility/electrical workers' safety climate perceptions were shared within the same supervisor group. This was followed by an analysis of the criterion-related validity, which linked the safety climate scores to self-reports of safety behavior and injury outcomes (i.e., recordable incidents, missing days due to work-related injuries, vehicle accidents, and near misses). Six dimensions (Safety pro-activity, General training, Trucks and equipment, Field orientation, Financial Investment, and Schedule flexibility) with 29 items were extracted from the EFA to

  18. Integral test facilities for validation of the performance of passive safety systems and natural circulation

    International Nuclear Information System (INIS)

    Choi, J. H.

    2010-10-01

    Passive safety systems are becoming an important component in advanced reactor designs. This has led to an international interest in examining natural circulation phenomena as this may play an important role in the operation of these passive safety systems. Understanding reactor system behaviour is a challenging process due to the complex interactions between components and associated phenomena. Properly scaled integral test facilities can be used to explore these complex interactions. In addition, system analysis computer codes can be used as predictive tools in understanding the complex reactor system behaviour. However, before the application of system analysis computer codes for reactor design, it is capability in making predictions needs to be validated against the experimental data from a properly scaled integral test facility. The IAEA has organized a coordinated research project (CRP) on natural circulation phenomena, modeling and reliability of passive systems that utilize natural circulation. This paper is a part of research results from this CRP and describes representative international integral test facilities that can be used for data collection for reactor types in which natural circulation may play an important role. Example experiments were described along with the analyses of these example cases in order to examine the ability of system codes to model the phenomena that are occurring in the test facilities. (Author)

  19. Validation study of computer code SPHINCS for sodium fire safety evaluation of fast reactor

    International Nuclear Information System (INIS)

    Yamaguchi, Akira; Tajima, Yuji

    2003-01-01

    A computer code SPHINCS solves coupled phenomena of thermal hydraulics and sodium fire based on a multi-zone model. It deals with an arbitrary number of rooms, each of which is connected mutually by doorways and penetrations. With regard to the combustion phenomena, a flame sheet model and a liquid droplet combustion model are used for pool and spray fires, respectively, with the chemical equilibrium model based on the Gibbs free energy minimization method. The chemical reaction and mass and heat transfer are solved interactively. A specific feature of SPHINCS is detailed representation of thermalhydraulics of a sodium pool and a steel liner, which is placed on the floor to prevent sodium-concrete contact. The authors analyzed a series of pool combustion experiments, in which gas and liner temperatures are measured in detail. It has been found that good agreement is obtained and the SPHINCS code has been validated with regard to pool combustion phenomena. Further research needs are identified for pool spreading modeling considering thermal deformation of steel liner and measurement of pool fluidity property as a mixture of liquid sodium and reaction products. The SPHINCS code is to be used mainly in the safety evaluation of the consequence of a sodium fire accident in a liquid metal cooled fast reactor as well as fire safety analysis in general

  20. Research on Occupational Safety, Health Management and Risk Control Technology in Coal Mines.

    Science.gov (United States)

    Zhou, Lu-Jie; Cao, Qing-Gui; Yu, Kai; Wang, Lin-Lin; Wang, Hai-Bin

    2018-04-26

    This paper studies the occupational safety and health management methods as well as risk control technology associated with the coal mining industry, including daily management of occupational safety and health, identification and assessment of risks, early warning and dynamic monitoring of risks, etc.; also, a B/S mode software (Geting Coal Mine, Jining, Shandong, China), i.e., Coal Mine Occupational Safety and Health Management and Risk Control System, is developed to attain the aforementioned objectives, namely promoting the coal mine occupational safety and health management based on early warning and dynamic monitoring of risks. Furthermore, the practical effectiveness and the associated pattern for applying this software package to coal mining is analyzed. The study indicates that the presently developed coal mine occupational safety and health management and risk control technology and the associated software can support the occupational safety and health management efforts in coal mines in a standardized and effective manner. It can also control the accident risks scientifically and effectively; its effective implementation can further improve the coal mine occupational safety and health management mechanism, and further enhance the risk management approaches. Besides, its implementation indicates that the occupational safety and health management and risk control technology has been established based on a benign cycle involving dynamic feedback and scientific development, which can provide a reliable assurance to the safe operation of coal mines.

  1. Radio Frequency Identification (RFID) technology and patient safety

    OpenAIRE

    Ajami, Sima; Rajabzadeh, Ahmad

    2013-01-01

    Background: Radio frequency identification (RFID) systems have been successfully applied in areas of manufacturing, supply chain, agriculture, transportation, healthcare, and services to name a few. However, the different advantages and disadvantages expressed in various studies of the challenges facing the technology of the use of the RFID technology have been met with skepticism by managers of healthcare organizations. The aim of this study was to express and display the role of RFID techno...

  2. Monograph on safety in high power and high energy advanced technologies and medical applications of lasers

    International Nuclear Information System (INIS)

    2016-01-01

    This monograph is intended for creating awareness amongst the safety and health professionals of nuclear and radiation facilities on hazards involved in high power and high energy advanced technologies as well as on how development of advanced technologies can benefit the common people

  3. State-of-the-art WEB -technologies and ecological safety of nuclear power engineering facilities

    International Nuclear Information System (INIS)

    Batij, V.G.; Batij, E.V.; Rud'ko, V.M.; Kotlyarov, V.T.

    2004-01-01

    Prospects of web-technologies using in the field of improvement radiation safety level of nuclear power engineering facilities is seen. It is shown that application of such technologies will enable entirely using the data of all information systems of radiation control

  4. Independent assembly technology for DCS safety equipment in nuclear power plant

    International Nuclear Information System (INIS)

    Hao Aixia

    2014-01-01

    A independent assembly technology of identification and verification was proposed, which included special process, wiring process and verification process. The safety reliability and practicability of the proposed technology were verified according to the application in FirmSys assembly implemented by China Techenergy Co., Ltd. (author)

  5. Proceedings of the Fifth Seminar on Technology of Nuclear Materials Safety

    International Nuclear Information System (INIS)

    Indro Yuwono; Nababan, Binsar; Suharyanta

    2004-11-01

    Proceedings of the Fifth Seminar on Technology of Nuclear Material Safety all aspect of research activity concerning the role of physical protection, nuclear safeguards technology and international convection in supporting the establishment of Nuclear Power Plant in Indonesia. There are 16 articles which have separated index. (PPIN)

  6. Validation of an instrument to measure students' motivation and self-regulation towards technology learning

    Science.gov (United States)

    Liou, Pey-Yan; Kuo, Pei-Jung

    2014-05-01

    Background:Few studies have examined students' attitudinal perceptions of technology. There is no appropriate instrument to measure senior high school students' motivation and self-regulation toward technology learning among the current existing instruments in the field of technology education. Purpose:The present study is to validate an instrument for assessing senior high school students' motivation and self-regulation towards technology learning. Sample:A total of 1822 Taiwanese senior high school students (1020 males and 802 females) responded to the newly developed instrument. Design and method:The Motivation and Self-regulation towards Technology Learning (MSRTL) instrument was developed based on the previous instruments measuring students' motivation and self-regulation towards science learning. Exploratory and confirmatory factor analyses were utilized to investigate the structure of the items. Cronbach's alpha was applied for measuring the internal consistency of each scale. Furthermore, multivariate analysis of variance was used to examine gender differences. Results:Seven scales, including 'Technology learning self-efficacy,' 'Technology learning value,' 'Technology active learning strategies,' 'Technology learning environment stimulation,' 'Technology learning goal-orientation,' 'Technology learning self-regulation-triggering,' and 'Technology learning self-regulation-implementing' were confirmed for the MSRTL instrument. Moreover, the results also showed that male and female students did not present the same degree of preference in all of the scales. Conclusions:The MSRTL instrument composed of seven scales corresponding to 39 items was shown to be valid based on validity and reliability analyses. While male students tended to express more positive and active performance in the motivation scales, no gender differences were found in the self-regulation scales.

  7. DEVELOPMENT OF RISK-BASED AND TECHNOLOGY-INDEPENDENT SAFETY CRITERIA FOR GENERATION IV SYSTEMS

    Energy Technology Data Exchange (ETDEWEB)

    William E. Kastenberg; Edward Blandford; Lance Kim

    2009-03-31

    This project has developed quantitative safety goals for Generation IV (Gen IV) nuclear energy systems. These safety goals are risk based and technology independent. The foundations for a new approach to risk analysis has been developed, along with a new operational definition of risk. This project has furthered the current state-of-the-art by developing quantitative safety goals for both Gen IV reactors and for the overall Gen IV nuclear fuel cycle. The risk analysis approach developed will quantify performance measures, characterize uncertainty, and address a more comprehensive view of safety as it relates to the overall system. Appropriate safety criteria are necessary to manage risk in a prudent and cost-effective manner. This study is also important for government agencies responsible for managing, reviewing, and for approving advanced reactor systems because they are charged with assuring the health and safety of the public.

  8. DEVELOPMENT OF RISK-BASED AND TECHNOLOGY-INDEPENDENT SAFETY CRITERIA FOR GENERATION IV SYSTEMS

    International Nuclear Information System (INIS)

    Kastenberg, William E.; Blandford, Edward; Kim, Lance

    2009-01-01

    This project has developed quantitative safety goals for Generation IV (Gen IV) nuclear energy systems. These safety goals are risk based and technology independent. The foundations for a new approach to risk analysis has been developed, along with a new operational definition of risk. This project has furthered the current state-of-the-art by developing quantitative safety goals for both Gen IV reactors and for the overall Gen IV nuclear fuel cycle. The risk analysis approach developed will quantify performance measures, characterize uncertainty, and address a more comprehensive view of safety as it relates to the overall system. Appropriate safety criteria are necessary to manage risk in a prudent and cost-effective manner. This study is also important for government agencies responsible for managing, reviewing, and for approving advanced reactor systems because they are charged with assuring the health and safety of the public

  9. How should we assess the safety of IVF technologies?

    Science.gov (United States)

    Brison, Daniel R; Roberts, Stephen A; Kimber, Susan J

    2013-12-01

    Clinical IVF treatment was established over 30 years ago through pioneering work by Edwards and Steptoe and other teams around the world and is now considered routine treatment. However, the pace of scientific and technological advances means that IVF practitioners can now access an increasing array of new and invasive technologies. The examples are many but include: extended embryo culture, development of media to include growth factors, developments in genetic screening, use of time-lapse technology and the advent of vitrification of embryos and oocytes. In parallel, wider scientific and medical advances are raising our awareness of the potential impact of assisted reproduction technology on areas such as embryonic development, gene expression and genomic imprinting and the developmental origins of health and disease. A recently suggested paradigm for assessing new technologies in IVF includes development in animal models such as rodents and large animals, preclinical research with human gametes and embryos donated to research, prospective clinical trials in IVF and, finally, follow-up studies of IVF children. In this paper, we describe efforts to address key areas of this pathway, namely preclinical research using human gametes/embryos and long-term, follow-up studies of the health of assisted reproduction children. Copyright © 2013 Reproductive Healthcare Ltd. Published by Elsevier Ltd. All rights reserved.

  10. Simulator platform for fast reactor operation and safety technology demonstration

    International Nuclear Information System (INIS)

    Vilim, R.B.; Park, Y.S.; Grandy, C.; Belch, H.; Dworzanski, P.; Misterka, J.

    2012-01-01

    A simulator platform for visualization and demonstration of innovative concepts in fast reactor technology is described. The objective is to make more accessible the workings of fast reactor technology innovations and to do so in a human factors environment that uses state-of-the art visualization technologies. In this work the computer codes in use at Argonne National Laboratory (ANL) for the design of fast reactor systems are being integrated to run on this platform. This includes linking reactor systems codes with mechanical structures codes and using advanced graphics to depict the thermo-hydraulic-structure interactions that give rise to an inherently safe response to upsets. It also includes visualization of mechanical systems operation including advanced concepts that make use of robotics for operations, in-service inspection, and maintenance.

  11. Simulator platform for fast reactor operation and safety technology demonstration

    Energy Technology Data Exchange (ETDEWEB)

    Vilim, R. B.; Park, Y. S.; Grandy, C.; Belch, H.; Dworzanski, P.; Misterka, J. (Nuclear Engineering Division)

    2012-07-30

    A simulator platform for visualization and demonstration of innovative concepts in fast reactor technology is described. The objective is to make more accessible the workings of fast reactor technology innovations and to do so in a human factors environment that uses state-of-the art visualization technologies. In this work the computer codes in use at Argonne National Laboratory (ANL) for the design of fast reactor systems are being integrated to run on this platform. This includes linking reactor systems codes with mechanical structures codes and using advanced graphics to depict the thermo-hydraulic-structure interactions that give rise to an inherently safe response to upsets. It also includes visualization of mechanical systems operation including advanced concepts that make use of robotics for operations, in-service inspection, and maintenance.

  12. 2003 Castor seminar - 120 tons of high technology for safety

    International Nuclear Information System (INIS)

    Anon.

    2003-01-01

    Castor (Cask for Storage and Transport of Radioactive Material) has become a symbol of the pros and cons of nuclear power in the public debate. Actually, what is Castor, and what is the technology behind this name? Siempelkamp Nukleartechnik and the Gesellschaft fuer Nuklearbehaelter mbH (GNB) invited interested parties to a presentation of the concept, technology, and manufacture on the occasion of the 2003 Castor Seminar. There was the possibility, among other events, to attend the casting process of a Castor cask at the Krefeld foundry of Siempelkamp. GNB offered a visit to its Muelheim works where the final assembly of the Castor cask could be observed. (orig.)

  13. Improving truck safety: Potential of weigh-in-motion technology

    Directory of Open Access Journals (Sweden)

    Bernard Jacob

    2010-07-01

    Full Text Available Trucks exceeding the legal mass limits increase the risk of traffic accidents and damage to the infrastructure. They also result in unfair competition between transport modes and companies. It is therefore important to ensure truck compliance to weight regulation. New technologies are being developed for more efficient overload screening and enforcement. Weigh-in-Motion (WIM technologies allow trucks to be weighed in the traffic flow, without any disruption to operations. Much progress has been made recently to improve and implement WIM systems, which can contribute to safer and more efficient operation of trucks.

  14. Validation of the Impact of Health Information Technology (I-HIT) Scale: an international collaborative.

    Science.gov (United States)

    Dykes, Patricia C; Hurley, Ann C; Brown, Suzanne; Carr, Robyn; Cashen, Margaret; Collins, Rita; Cook, Robyn; Currie, Leanne; Docherty, Charles; Ensio, Anneli; Foster, Joanne; Hardiker, Nicholas R; Honey, Michelle L L; Killalea, Rosaleen; Murphy, Judy; Saranto, Kaija; Sensmeier, Joyce; Weaver, Charlotte

    2009-01-01

    In 2005, the Healthcare Information Management Systems Society (HIMSS) Nursing Informatics Community developed a survey to measure the impact of health information technology (HIT), the I-HIT Scale, on the role of nurses and interdisciplinary communication in hospital settings. In 2007, nursing informatics colleagues from Australia, England, Finland, Ireland, New Zealand, Scotland and the United States formed a research collaborative to validate the I-HIT across countries. All teams have completed construct and face validation in their countries. Five out of six teams have initiated reliability testing by practicing nurses. This paper reports the international collaborative's validation of the I-HIT Scale completed to date.

  15. Technology Solutions Case Study: Combustion Safety Simplified Test Protocol

    Energy Technology Data Exchange (ETDEWEB)

    L. Brand, D. Cautley, D. Bohac, P. Francisco, L. Shen, and S. Gloss

    2015-12-01

    Combustions safety is an important step in the process of upgrading homes for energy efficiency. There are several approaches used by field practitioners, but researchers have indicated that the test procedures in use are complex to implement and provide too many false positives. Field failures often mean that the house is not upgraded until after remediation or not at all, if not include in the program. In this report the PARR and NorthernSTAR DOE Building America Teams provide a simplified test procedure that is easier to implement and should produce fewer false positives.

  16. Development of safety enhancement technology of containment building

    International Nuclear Information System (INIS)

    Seo, Jeong Moon; Choun, Y. S.; Choi, I. K.

    2002-04-01

    This study consists of four research areas, (1) Seismic safety assessment, (2) Aging assessment of a containment building, (3) Prediction of long-term behavior and analysis of a containment building, (4) Performance verification of a containment building. In the seismic safety assessment area, responses of a containment building were monitored and the analysis method was verified. Also performed are the identification of earthquake characteristics and improvement of the seismic fragility analysis method. In the area of aging assessment of a containment building, we developed aging management code SLMS and database. Aging tests were performed for containment building materials and aging models were developed. Techniques for investigation, detection, and evaluation of aging were developed. In the area of prediction of long-term behavior and analysis of a containment building, we developed a non-linear structural analysis code NUCAS and material models. In the area of performance verification of a containment building, we analyzed the crack behavior of a containment wall and the behavior of the containment under internal pressure. We also improved the ISI methods for prestressed containment

  17. 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

  18. Novel technology to prepare oral formulations for preclinical safety studies.

    Science.gov (United States)

    Niwa, Toshiyuki; Hashimoto, Naofumi

    2008-02-28

    A novel method to prepare oral formulations, normally suspended dosage form, for preclinical safety studies in animals has been developed using a rotation/revolution mixer. Small hard balls made of zirconia were added to the mixing process to evaluate effectiveness in making a high quality suspension. The driving with balls loaded in the cylindrical container (vessel) of the mixer was quite efficient in dispersing and milling the particles of the active pharmaceutical ingredient (API) in an aqueous medium. The API powder and a small amount of oral aqueous medium (vehicle) were successfully mixed by the spinning motion of the balls in the vessel as though the paste-like suspension was kneaded with a mortar and pestle. It was found that the milled suspension with the mean size of 10-20microm could be prepared, in addition finer milling of less than 10microm could be achieved by selecting the material of vessel. Optimum driving conditions including mixing time, size and quantity of balls, and the standard operational procedure was established using compounds varying in physicochemical properties. The particle size and quantitative analysis by HPLC showed that the resultant suspension was well-milled and highly homogeneous with the nearly intended concentration of API. The proposed method established by this experiment could be applied to the actual safety studies in the real preparation scale of oral suspension.

  19. Safety Lead Optimization and Candidate Identification: Integrating New Technologies into Decision-Making.

    Science.gov (United States)

    Dambach, Donna M; Misner, Dinah; Brock, Mathew; Fullerton, Aaron; Proctor, William; Maher, Jonathan; Lee, Dong; Ford, Kevin; Diaz, Dolores

    2016-04-18

    Discovery toxicology focuses on the identification of the most promising drug candidates through the development and implementation of lead optimization strategies and hypothesis-driven investigation of issues that enable rational and informed decision-making. The major goals are to [a] identify and progress the drug candidate with the best overall drug safety profile for a therapeutic area, [b] remove the most toxic drugs from the portfolio prior to entry into humans to reduce clinical attrition due to toxicity, and [c] establish a well-characterized hazard and translational risk profile to enable clinical trial designs. This is accomplished through a framework that balances the multiple considerations to identify a drug candidate with the overall best drug characteristics and provides a cogent understanding of mechanisms of toxicity. The framework components include establishing a target candidate profile for each program that defines the qualities of a successful candidate based on the intended therapeutic area, including the risk tolerance for liabilities; evaluating potential liabilities that may result from engaging the therapeutic target (pharmacology-mediated or on-target) and that are chemical structure-mediated (off-target); and characterizing identified liabilities. Lead optimization and investigation relies upon the integrated use of a variety of technologies and models (in silico, in vitro, and in vivo) that have achieved a sufficient level of qualification or validation to provide confidence in their use. We describe the strategic applications of various nonclinical models (established and new) for a holistic and integrated risk assessment that is used for rational decision-making. While this review focuses on strategies for small molecules, the overall concepts, approaches, and technologies are generally applicable to biotherapeutics.

  20. Safety philiosophies in technology-related law discussed for the example of atomic energy law

    International Nuclear Information System (INIS)

    Rossnagel, A.

    1993-01-01

    In practice, legal ruling and its technical implementation stand isolated side by side. Taking the example of atomic energy law, the reasons for this situation and the significance of the deficit in the legal control of technology are examined. It is discussed how the controlling capacity of the law can be increased through the legal implementation of safety philosophies for technology. The paper deals with the problematic realtionship between technical and legal norms, with safety philosophies in the sense of mental approaches, safety concepts or safety postulates and their legal significance, and with the safety philosophy adhered to by the authorities and courts. The following learning processes in safety philosophy are described: new concepts of protection within the field of determinism, probabilistic safety concepts as well as concepts for the reduction of damage potential. Altogether it can be stated that the safety philosophy currently adhered to in Federal German licensing practice is not the only possible one; rather, that there are many different ways of conceptualizing, stipulating and checking technical safety. At least in the field of atomic energy law, this insight has a twofold significance: de lege lata there are several ways of operationalizing the licence requirements laid down in Article 7 of the Atomic Energy Law and the legally defined requirements for a licence withdrawal with the aid of technical licensing criteria. In all cases the legal wording is indeterminate and does not prescribe any specific safety philosophy. De lege ferenda it must be noted that amendments to the Atomic Energy Law entail a regularization of safety philosophy. This is a political necessity if the Atomic Energy Law is to be developed further and thus maintained as a modern security law. (orig.) [de

  1. 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.

  2. Adaptive Seat Energy Absorbers for Enhanced Crash Safety: Technology Demonstration

    Science.gov (United States)

    2016-08-01

    is no pressing need for MREA refinement. However, should an increase in MREA yield force be desired, the project team explored 2 simple refinements...team developed a servo motor controller and data acquisition program using dSPACE real-time system. From the preliminary test, the preloaded Terfenol...Technology; 1940. b Oberg E, editor. Machinery’s handbook: eighteenth edition. Norwalk (CT): Industrial Press ; 1968. c Quayle JP, editor. Kempe’s

  3. An Integrated Safety Analysis Methodology for Emerging Air Transport Technologies

    Science.gov (United States)

    Kostiuk, Peter F.; Adams, Milton B.; Allinger, Deborah F.; Rosch, Gene; Kuchar, James

    1998-01-01

    The continuing growth of air traffic will place demands on NASA's Air Traffic Management (ATM) system that cannot be accommodated without the creation of significant delays and economic impacts. To deal with this situation, work has begun to develop new approaches to providing a safe and economical air transportation infrastructure. Many of these emerging air transport technologies will represent radically new approaches to ATM, both for ground and air operations.

  4. Leaving patients to their own devices? Smart technology, safety and therapeutic relationships.

    Science.gov (United States)

    Ho, Anita; Quick, Oliver

    2018-03-06

    This debate article explores how smart technologies may create a double-edged sword for patient safety and effective therapeutic relationships. Increasing utilization of health monitoring devices by patients will likely become an important aspect of self-care and preventive medicine. It may also help to enhance accurate symptom reports, diagnoses, and prompt referral to specialist care where appropriate. However, the development, marketing, and use of such technology raise significant ethical implications for therapeutic relationships and patient safety. Drawing on lessons learned from other direct-to-consumer health products such as genetic testing, this article explores how smart technology can also pose regulatory challenges and encourage overutilization of healthcare services. In order for smart technology to promote safer care and effective therapeutic encounters, the technology and its utilization must be safe. This article argues for unified regulatory guidelines and better education for both healthcare providers and patients regarding the benefits and risks of these devices.

  5. The technological safety in facilities that manage radioactive sources

    International Nuclear Information System (INIS)

    Lizcano, D.

    2014-10-01

    The sealed radioactive sources are used inside a wide range of applications in the medicine, industry and investigation around the world. These sources can contain a great radionuclides variety, exhibiting a wide spectrum of activities and radiological half lives. This way, we can find pattern sources of radionuclides as Americium-241, Plutonium-238, Plutonium-239, Thorium-228 and Thorium-230, etc., with some activity of kBq in research laboratories, Iridium-192 and Cesium-137 sources used in brachytherapy with GBq activities, until sources with P Bq activities in industrial irradiators of Cobalt-60 and Cesium-137. This document approach the physical safety that entities like the IAEA recommends for the facilities that contain sealed sources, especially the measures that are taking in the Instituto Nacional de Investigaciones Nucleares (ININ) and others government facilities. (Author)

  6. Development, use, and validation of the CFD tool FLACS for hydrogen safety studies

    Energy Technology Data Exchange (ETDEWEB)

    Middha, Prankul

    2010-07-01

    Computational Fluid Dynamics (CFD) calculations for gas explosion safety have been widely used for doing risk assessments within the oil and gas industry for more than a decade. Based on predicted consequences of a range of potential accident scenarios a risk level is predicted. The development of applications using hydrogen as a clean energy carrier has accelerated in recent years, and hydrogen may be used widely in future. Due to the very high reactivity of hydrogen, safe handling is critical. To be able to perform proper consequence modeling as a part of a risk assessment, it is essential to be able to model the physical processes well. CFD tools have the potential to model the relevant physics and predict well, but without proper user guidelines based on extensive validation work, very mixed prediction capability can be expected. This paper deals with the development and validation of the CFD tool FLACS for hydrogen safety applications. Significant validation work against several experiments has been carried out in order to increase the confidence of predictions of scenarios relevant to hydrogen safety. The validation studies have included dispersion, explosion and combined dispersion and explosion studies. A range of different dispersion experiments is simulated, including low momentum releases in a garage, sub-sonic jets in a garage with stratification effects and subsequent slow diffusion, low momentum and subsonic horizontal jets influenced by buoyancy, and free jets from high-pressure vessels. LH2 releases are also considered. Some of the simulations are performed as blind predictions. FLACS uses a utility program in order to model releases from high-pressure reservoirs. Work has been carried out in order to extend the models in the utility program in order to include real gas effects. Validation against explosion experiments in geometries ranging from smooth and obstructed pipes, refueling station, tunnel, vented vessels, jet-ignited lane, etc. have been

  7. Application of the Digital Image Technology in the Visual Monitoring and Prediction of Shuttering Construction Safety

    Science.gov (United States)

    Ummin, Okumura; Tian, Han; Zhu, Haiyu; Liu, Fuqiang

    2018-03-01

    Construction safety has always been the first priority in construction process. The common safety problem is the instability of the template support. In order to solve this problem, the digital image measurement technology has been contrived to support real-time monitoring system which can be triggered if the deformation value exceed the specified range. Thus the economic loss could be reduced to the lowest level.

  8. Review of Risk Reduction Methods using Probabilistic Safety Assessment Insights and Improved Technology

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Eun-Chan; Choi, Byung-Pil [Korea Hydro and Nuclear Power Co., Daejeon (Korea, Republic of)

    2016-10-15

    As seen in the process of the periodic safety review of domestic nuclear power plants, the risk management objectives such as core damage frequency and large early release frequency are not easy to be met without continuous safety improvements and the integratoin of the improved technologies into the PSA evaluation methodologies. Because external event analyses have a protion of uncertainty factors in the current analysis methodologies, the technical efforts in various perspectives.

  9. Validation of the Domains of Creativity Scale for Nigerian Preservice Science, Technology, and Mathematics Teachers

    Science.gov (United States)

    Awofala, Adeneye O. A.; Fatade, Alfred O.

    2015-01-01

    Introduction: Investigation into the factor structure of Domains of Creativity Scale has been on for sometimes now. The purpose of this study was to test the validity of the Kaufman Domains of Creativity Scale on Nigerian preservice science, technology, and mathematics teachers. Method: Exploratory and confirmatory factor analyses were performed…

  10. Proceedings of the 9. National Seminar on Technology and Safety of Nuclear Power Plants and Nuclear Facilities

    International Nuclear Information System (INIS)

    Antariksawan, Anhar R.; Soetrisnanto, Arnold Y; Aziz, Ferhat; Untoro, Pudji; Su'ud, Zaki; Zarkasi, Amin Santoso; Lasman, As Natio

    2003-08-01

    The ninth proceedings of seminar safety and technology of nuclear power plant and nuclear facilities held by National Nuclear Energy Agency and PLN-JTK. The aims of seminar is to exchange and disseminate information about Safety and Nuclear Power Plant Technology and Nuclear Facilities consist of Technology High Temperature Reactor and Application for National Development Sustainable and High Technology. This seminar cover all aspects Technology, Power Reactor, Research Reactor High Temperature Reactor and Nuclear Facilities. There are 20 articles have separated index

  11. Assistive technology for visually impaired women for use of the female condom: a validation study

    Directory of Open Access Journals (Sweden)

    Luana Duarte Wanderley Cavalcante

    2015-02-01

    Full Text Available OBJECTIVE To validate assistive technology for visually impaired women to learn how to use the female condom. METHOD a methodological development study conducted on a web page, with data collection between May and October 2012. Participants were 14 judges; seven judges in sexual and reproductive health (1st stage and seven in special education (2nd stage. RESULTS All items have reached the adopted parameter of 70% agreement. In Stage 1 new materials were added to represent the cervix, and instructions that must be heard twice were included in the 2nd stage. CONCLUSION The technology has been validated and is appropriate for its objectives, structure / presentation and relevance. It is an innovative, low cost and valid instrument for promoting health and one which may help women with visual disabilities to use the female condom.

  12. First evidence on the validity and reliability of the Safety Organizing Scale-Nursing Home version (SOS-NH).

    Science.gov (United States)

    Ausserhofer, Dietmar; Anderson, Ruth A; Colón-Emeric, Cathleen; Schwendimann, René

    2013-08-01

    The Safety Organizing Scale is a valid and reliable measure on safety behaviors and practices in hospitals. This study aimed to explore the psychometric properties of the Safety Organizing Scale-Nursing Home version (SOS-NH). In a cross-sectional analysis of staff survey data, we examined validity and reliability of the 9-item Safety SOS-NH using American Educational Research Association guidelines. This substudy of a larger trial used baseline survey data collected from staff members (n = 627) in a variety of work roles in 13 nursing homes (NHs) in North Carolina and Virginia. Psychometric evaluation of the SOS-NH revealed good response patterns with low average of missing values across all items (3.05%). Analyses of the SOS-NH's internal structure (eg, comparative fit indices = 0.929, standardized root mean square error of approximation = 0.045) and consistency (composite reliability = 0.94) suggested its 1-dimensionality. Significant between-facility variability, intraclass correlations, within-group agreement, and design effect confirmed appropriateness of the SOS-NH for measurement at the NH level, justifying data aggregation. The SOS-NH showed discriminate validity from one related concept: communication openness. Initial evidence regarding validity and reliability of the SOS-NH supports its utility in measuring safety behaviors and practices among a wide range of NH staff members, including those with low literacy. Further psychometric evaluation should focus on testing concurrent and criterion validity, using resident outcome measures (eg, patient fall rates). Copyright © 2013 American Medical Directors Association, Inc. All rights reserved.

  13. Validation of KENO V.a for criticality safety calculations involving WR-1 fast-neutron fuel arrangements

    Energy Technology Data Exchange (ETDEWEB)

    Gauld, I. C.

    1991-07-15

    The KENO V.a criticality safety code, used with the SCALE 27-energy-group ENDF/B-IV-based cross-section library, has been validated for low-enriched uranium carbide (UC) WR-1 fast-neutron (FN) fuel arrangements. Because of a lack of relevant experimental data for UC fuel in the published literature, the validation is based primarily on calculational comparisons with critical experiments for fuel types with a range of enrichments and densities that cover those of the FN UC fuel. The ability of KENO V.a to handle the unique annular pin arrangement of the WR-1 FN fuel bundle was established using a comparison with the MCNP3B code used with a continuous-energy ENDF/B-V-based cross-section library. This report is part of the AECL--10146 report series documenting the validation of the KENO V.a criticality safety code.

  14. Thermal-hydraulics technological strategy roadmap for LWR safety improvement and development

    International Nuclear Information System (INIS)

    Nakamura, Hideo; Arai, Kenji; Oikawa, Hirohide

    2015-01-01

    New version of the Thermal-Hydraulics Safety Evaluation Fundamental Technology Enhancement Strategy Roadmap (TH-RM) was developed by the Atomic Energy Society of Japan (AESJ) for LWR safety improvement and development. The 1st version of TH-RM was prepared in 2009 under collaboration of utilities, vendors, universities, research institutes and technical support organizations (TSO) for regulatory body. The revision was made by three sub-working groups (SWGs) by considering the lessons learned from the Fukushima Daiichi Accident. The 'safety assessment' SWG pursued development of computer codes for safety assessment. The 'fundamental technology' SWG pursued safety improvement and risk reduction via accident management (AM) measures by referring the technical map for severe accident (SA) established by the 'severe accident' SWG. Phenomena and components for counter-measures and/or proper prediction are identified by going through SA progression in both reactor and spent-fuel pool of PWR and BWR. Twelve important technology development subjects were identified, which include melt coolability enhancement to maintain integrity of containment vessel. Fact Sheet was developed to describe each of identified and selected R and D subjects. External hazards are also considered how to cope with from thermal-hydraulic safety point of view. This paper summarizes the revised TH-RM with several examples and future perspectives. (author)

  15. Integrating Safety with Science,Technology and Innovation at Los Alamos National Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    Rich, Bethany M [Los Alamos National Laboratory

    2012-04-02

    The mission of Los Alamos National Laboratory (LANL) is to develop and apply science, technology and engineering solutions to ensure the safety, security, and reliability of the U.S. nuclear deterrent; reduce global threats; and solve emerging national security challenges. The most important responsibility is to direct and conduct efforts to meet the mission with an emphasis on safety, security, and quality. In this article, LANL Environmental, Safety, and Health (ESH) trainers discuss how their application and use of a kinetic learning module (learn by doing) with a unique fall arrest system is helping to address one the most common industrial safety challenges: slips and falls. A unique integration of Human Performance Improvement (HPI), Behavior Based Safety (BBS) and elements of the Voluntary Protection Program (VPP) combined with an interactive simulator experience is being used to address slip and fall events at Los Alamos.

  16. 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.

  17. Digital technology strengthens EDF's nuclear safety

    International Nuclear Information System (INIS)

    Dupin, Ludovic

    2016-01-01

    This article proposes an overview of the development of the use of various and new digital technologies of information and communication by EDF to train its nuclear operators, field technicians who are maintaining nuclear power plants, personnel in charge of risk management, and so on. Trainees are using tablets with augmented reality software, serious games, virtual reality helmets, and also digital simulators to learn how to control a reactor. More practical training also exists: people are taught how to practically and correctly assemble tubes for example

  18. [Comparison of validity and safety between holmium: YAG laser and traditional surgery in partial nephrectomy].

    Science.gov (United States)

    Bi, Sheng; Xia, Ming

    2015-08-11

    To compare the validity and safety between holmium: YAG laser and traditional surgery in partial nephrectomy. A total of 28 patients were divided into two groups (holmium: YAG laser group without renal artery clamping and traditional surgery group with renal artery clamping). The intraoperative blood loss, total operative time, renal artery clamping time, postoperative hospital stay, separated renal function, postoperative complications and depth of tissue injury were recorded. The intraoperative blood loss, total operative time, renal artery clamping time, postoperative hospital stay, separated renal function, postoperative complications and depth of tissue injury were 80 ml, 77 min, 0 min, 7.4 days, 35 ml/min, 0, 0.9 cm, respectively, in holmium: YAG laser group. And in traditional surgery group were 69 ml, 111 min, 25.5 min, 7.3 days, 34 ml/min, 0, 2.0 cm, respectively. The differences of total operative time, renal artery clamping time and depth of tissue injury between two groups were statistically significant. The others were not statistically significant. Holmium: YAG laser is effective and safe in partial nephrectomy. It can decrease the total operative time, minimize the warm ischemia time and enlarge the extent of surgical excision.

  19. Development of Necessary Technology for localizing of Nuclear Safety Grade I and C System

    International Nuclear Information System (INIS)

    Kwon, Kee Choon; Jang, Tong Il; Kim, Jung Tack

    2010-08-01

    Through KNICS and Nu-Tech 2012, a MMIS(Man-Machine Interface System) package for nuclear plants was localized and is expected to be applied to SUN 1,2 plants. This study is aimed to support the application of the MMIS package including the following technologies that meet strengthened regulation requirements and enhanced utility's performance requirements to nuclear plants. - Dedication to safety-grade computers and real time operating systems - The broadband communication network for safety information - Application of the automatic test for safety systems - Application of programmable logic controllers to nuclear plants - Development strategy for an integrated SW development tool for control device

  20. Development of Necessary Technology for Safety Grade I and C System

    International Nuclear Information System (INIS)

    Lee, Dong Young; Jang, Tong Il; Kim, Jung Tack

    2010-08-01

    Through KNICS and Nu-Tech 2012, a MMIS(Man-Machine Interface System) package for nuclear plants was localized and is expected to be applied to SUN 1,2 plants. This study is aimed to support the application of the MMIS package including the following technologies that meet strengthened regulation requirements and enhanced utility's performance requirements to nuclear plants. - Dedication to safety-grade computers - The broadband communication network for safety information - Application of the automatic test for safety systems - Application of programmable logic controllers to nuclear plant

  1. Review of literature on the TMI accident and correlation to the LWR Safety Technology Program

    Energy Technology Data Exchange (ETDEWEB)

    Miller, W.J.

    1980-05-01

    This report is the result of approximately two man-months of effort devoted to assimilating and comprehending significant publicly available material related to Three Mile Island Unit 2 and events during and subsequent to the accident experienced on March 28, 1979. Those events were then correlated with the Preliminary LWR Safety Technology Program Plan (Preliminary Program Plan) prepared for the US Department of Energy by Sandia National Lab. This report is being submitted simultaneously with the SAI report entitled Preliminary Prioritization of Tasks in the Draft LWR Safety Technology Program Plan.

  2. Review of literature on the TMI accident and correlation to the LWR Safety Technology Program

    International Nuclear Information System (INIS)

    Miller, W.J.

    1980-05-01

    This report is the result of approximately two man-months of effort devoted to assimilating and comprehending significant publicly available material related to Three Mile Island Unit 2 and events during and subsequent to the accident experienced on March 28, 1979. Those events were then correlated with the Preliminary LWR Safety Technology Program Plan (Preliminary Program Plan) prepared for the US Department of Energy by Sandia National Lab. This report is being submitted simultaneously with the SAI report entitled Preliminary Prioritization of Tasks in the Draft LWR Safety Technology Program Plan

  3. Ella-V and technology usage technology usage in an english language and literacy acquisition validation randomized controlled trial study

    Directory of Open Access Journals (Sweden)

    Roisin P. Corcoran

    2014-12-01

    Full Text Available This paper describes the use of technology to provide virtual professional development (VPD for teachers and to conduct classroom observations in a study of English Language Learner (ELL instruction in grades K–3. The technology applications were part of a cluster randomized control trial (RCT design for a federally funded longitudinal validation study of a particular program, English Language and Literacy Acquisition-Validation, ELLA- V, to determine its degree of impact on English oral language/literacy, reading, and science across 63 randomly assigned urban, suburban, and rural schools (first year of implementation. ELLA-V also examines the impact of bimonthly VPD for treatment teachers compared to comparison group teachers on pedagogical skills, measured by sound observation instruments, and on student achievement, measured by state/national English language/literacy/reading tests and a national science test. This study features extensive technology use via virtual observations, bimonthly VPD, and randomly assigned treatment and control schools with students served in English as second language (ESL instructional time. The study design and methodology are discussed relativeto the specialized uses of technology and issues involving the evaluation of technology’s contribution to the intervention of interest and of the efficient, cost-effective execution of the study.

  4. Development of Seismic Safety Assessment Technology for Containment Structure

    Energy Technology Data Exchange (ETDEWEB)

    Jang, J.B.; Suh, Y.P.; Lee, J.R. [Korea Electric Power Research Institute, Taejon (Korea)

    2002-07-01

    This final report is made based on the research results of seismic analysis and seismic margin assessment field, carried out during 3rd stage ('01.4.1{approx}'02.3.31) under financial support of MOST(Ministry of Science and Technology). The objective of this research is to develop the soil - structure interaction analysis technique with high reliability, the main research subjects, performed during 3rd stage are as follows. 1) Preparation of user's guide manual for SSI analysis with high accuracy. 2) Sensitivity analysis of effective shear strain and seismic input motion. 3) Database construction of Hualien earthquake recorded data. (author). 21 refs., 27 figs., 2 tabs.

  5. The development of safety assessment technology for the radwaste disposal

    International Nuclear Information System (INIS)

    Han, Kyong Won; Cho, Won Jin; Lee, Han Soo; Lee, Jai Wan; Park, Chung Kyun; Lee, Myun Joo; Cho, Young Hwan; Choi, Heui Joo; Lee, Youn Myoung; Park, Hee Sung

    1989-02-01

    This report is composed of three parts. In part I, an improved radwaste disposal safety assessment code named SADROCM, was developed by upgrading the existing SADROC. A numerical approach was adopted for the simulation of diffusion into rock pore and advection in the fracture. Also quantification of resaturation time in repository was obtained by introducing theoretical resaturation model and groundwater flow model. In radiation dose model the calculated dose by existing model was compared with that by LIMCAL code. Part II resulted in several findings. Regarding the leaching of radionuclide, two steps were observed. It was identified that in the initial step, radionuclide leaching occurred at the surface of solidified waste, and then leaching proceeded by dissolution and diffusion of radionuclide from inside of the solidified waste.The results of the sorption experiments on Cs, Co, Sr for the rock samples from four regions, showed that Kd value of F-site quartz-porphery was the lowest, and that of B-site Rhyolitic tuff the highest. E-site granite, M-site granite gneiss showed medium sorption capacities. The Kd values of each radionuclide were in the following order: Cs > Co > Sr . For the radionuclide migration through fractured rock, examination of hydraulic dispersion model and channeling model was carried out to simulate the dispersion phenomena through the fractured rock. In part III, optimum model was established which allows mathematical prediction of the container corrosion rate and leach rate.Based on this model, the equations were obtained to predict corrosion rate and radionuclide leach rate. A good agreement of these equations and existing experimental data was considered to be an indication that it can be used effectively for the estimation of long-term leaching. (Author)

  6. Beyond usability: designing effective technology implementation systems to promote patient safety.

    Science.gov (United States)

    Karsh, B-T

    2004-10-01

    Evidence is emerging that certain technologies such as computerized provider order entry may reduce the likelihood of patient harm. However, many technologies that should reduce medical errors have been abandoned because of problems with their design, their impact on workflow, and general dissatisfaction with them by end users. Patient safety researchers have therefore looked to human factors engineering for guidance on how to design technologies to be usable (easy to use) and useful (improving job performance, efficiency, and/or quality). While this is a necessary step towards improving the likelihood of end user satisfaction, it is still not sufficient. Human factors engineering research has shown that the manner in which technologies are implemented also needs to be designed carefully if benefits are to be realized. This paper reviews the theoretical knowledge on what leads to successful technology implementation and how this can be translated into specifically designed processes for successful technology change. The literature on diffusion of innovations, technology acceptance, organisational justice, participative decision making, and organisational change is reviewed and strategies for promoting successful implementation are provided. Given the rapid and ever increasing pace of technology implementation in health care, it is critical for the science of technology implementation to be understood and incorporated into efforts to improve patient safety.

  7. Current status and prospect of radiation technology for the safety and security of food

    International Nuclear Information System (INIS)

    Byun, Myung Woo

    2009-01-01

    Since 1960, radiation technology (RT), which had been known as the method eliminating the biologically hazardous factors of the products in the food, medical, pharmaceutical and cosmetic industries, was comprehensively investigated. The safety of food irradiation has been throughout evaluated with scientific experiments. Recently, RT has been associated with other high technologies such as biotechnology and nanotechnology, and resulted in the innovative products. Through these fusion technology with RT, the new items with high functionality and value will be shown. But, until now, consumers' acceptance on radiation is still the problem to be solved for further development. To make the consumer correctly understand RT, the benefits and defects of RT should be informed and there should be the legislated policy for the industrialization of RT by government. Therefore, this review will introduce the current status of food irradiation in the world, the safety and national agreements and the recent results from radiation fusion technology, and suggest the further work

  8. Training in nuclear safety and technology at Ciemat (Spain)

    International Nuclear Information System (INIS)

    Galan, M.; Rodriguez, M.; Hernando, E.

    2006-01-01

    Fission nuclear energy acceptance has suffered great change from its discovery. During 50 s and 70 s, was worldwide approved but a high social repulse is experimented nowadays in some societies. This fact has led to a contradictory situation in the world. We can find some countries where the majority of their electric energy is produced in nuclear power plants (NPPs). In Europe, France produces over the 75% of the electric energy consumed, moreover, in Asia, new NPPs are being constructed in China, Japan or India; but on the contrary, other countries, such as Spain, has signed the nuclear moratorium. The result of this situation has conducted to a lower interest in nuclear training at universities and few implementation of superior studies in Nuclear Technology. But nuclear and radioactive installations are still opened and need qualified staff. The training Unit of C.I.E.M.A.T. has been organizing courses on nuclear energy and radiation protection for more than 30 years and develops all the educational program which has been required by Spanish Radiation Protection Education. Within the training courses variety, a course of about 68 E.C.T.S. (following Bologna Process, 1999) to permit young graduated to be specialized in this area, has been organised. E.C.T.S. credits indicate the average student work load to successfully complete a course. 68 E.C.T.S. represents, in terms of workload, near one year of study. The programme contents subjects like Fission, Fusion, NPPs Operation and Control, Nuclear Fuel and Cycle. At a more interdisciplinary level, the programme also provides knowledge in other fields of application such as Nuclear Medicine, Radiation Effects, Radiation Protection, Shielding against Radiation, Material Science, Radiation Measurements and Instruments, Waste Management and Decommissioning, Environmental Impact of NPPs and National and International Regulation. The theoretical schedules are completed by practical sessions on computational codes

  9. Safety handling of beryllium for fusion technology R and D

    International Nuclear Information System (INIS)

    Yoshida, Hiroshi; Okamoto, Makoto; Terai, Takayuki; Odawara, Osamu; Ashibe, Kusuo; Ohara, Atsushi.

    1992-07-01

    Feasibility of beryllium use as a blanket neutron multiplier, first wall and plasma facing material has been studied for the D-T burning experiment reactors such as ITER. Various experimental work of beryllium and its compounds will be performed under the conditions of high temperature and high energy particle exposure simulating fusion reactor conditions. Beryllium is known as a hazardous substance and its handling has been carefully controlled by various health and safe guidances and/or regulations in many countries. Japanese regulations for hazardous substance provide various guidelines on beryllium for the protection of industrial workers and environment. This report was prepared for the safe handling of beryllium in a laboratory scale experiments for fusion technology R and D such as blanket development. Major items in this report are; (1) Brief review of guidances and regulations in USA, UK and Japan. (2) Safe handling and administration manuals at beryllium facilities in INEL, LANL and JET. (3) Conceptual design study of beryllium handling facility for small to mid-scale blanket R and D. (4) Data on beryllium toxicity, example of clinical diagnosis of beryllium disease, and environmental occurence of beryllium. (5) Personnel protection tools of Japanese Industrial Standard for hazardous substance. (author) 61 refs

  10. Safety (management and technology). Safety of chemical materials; Anzen (manejimento to tekunoroji). Kagaku busshitsu no anzensei

    Energy Technology Data Exchange (ETDEWEB)

    Yoshida, T. [Hosei Univ., Tokyo (Japan). Faculty of Engineering

    1994-08-05

    In chemical materials there exist hazardous materials causing health damages, environmental pollution, fires and explosions. The hazard analysis has been noted as a means for preventing accidents due to chemical materials. This means leads to an effective method of recognizing hazard, evaluating the risk, and lowering the degree of hazard to an allowable level. This paper describes a hazard analysis of autoreactive materials, out of chemical materials causing fires and explosions, which may react by theirselves and cause accidents. In particular, an example is introduced in which this hazard analysis method is adapted to an experimental production of the next generation gas generating agent for automobile collision safety air-bags. In this manufacturing process, in kneading and granulating processes where lots of materials are handled, materials are used in a moistened state, thus countermeasures for preventing occurrence of combustion and explosion being taken. 5 refs., 2 figs., 4 tabs.

  11. Assessing the Safety Attitudes Questionnaire (SAQ), German language version in Swiss university hospitals--a validation study.

    Science.gov (United States)

    Zimmermann, Natalie; Küng, Kaspar; Sereika, Susan M; Engberg, Sandra; Sexton, Bryan; Schwendimann, René

    2013-09-10

    Improving patient safety has become a major focus of clinical care and research over the past two decades. An institution's patient safety climate represents an essential component of ensuring a safe environment and thereby can be vital to the prevention of adverse events. Covering six patient safety related factors, the Safety Attitudes Questionnaire (SAQ) is a validated and widely used instrument to measure the patient safety climate in clinical areas. The objective of this study was to assess the psychometric properties of the German language version of the SAQ. A survey was carried out in two University Hospitals in Switzerland in autumn 2009 where the SAQ was distributed to a sample of 406 nurses and physicians in medical and surgical wards. Following the American Educational Research Association guidelines, we tested the questionnaire validity by levels of evidence: content validity, internal structure and relations to other variables. Confirmatory factor analysis was used to examine factor structure. Cronbach's alphas and inter-item correlations were calculated to examine internal consistency reliability. A total of 319 questionnaires were completed representing an overall response rate of 78.6%. For three items, the item content validity index was <0.75. Confirmatory factor analysis showed acceptable model fit (RMSEA = 0.045; CFI = 0.944) for the six-factor model. Additional exploratory factor analysis could not identify a better factor model. SAQ factor scores showed positive correlations with the Safety Organizing Scale (r = .56-.72). The SAQ German version showed moderate to strong internal consistency reliability indices (Cronbach alpha = .65-.83). The German language version of the SAQ demonstrated acceptable to good psychometric properties and therefore shows promise to be a sound instrument to measure patient safety climate in Swiss hospital wards. However, the low item content validity and large number of missing responses for several items suggest

  12. Using game technologies to improve the safety of construction plant operations.

    Science.gov (United States)

    Guo, Hongling; Li, Heng; Chan, Greg; Skitmore, Martin

    2012-09-01

    Many accidents occur world-wide in the use of construction plant and equipment, and safety training is considered by many to be one of the best approaches to their prevention. However, current safety training methods/tools are unable to provide trainees with the hands-on practice needed. Game technology-based safety training platforms have the potential to overcome this problem in a virtual environment. One such platform is described in this paper - its characteristics are analysed and its possible contribution to safety training identified. This is developed and tested by means of a case study involving three major pieces of construction plant, which successfully demonstrates that the platform can improve the process and performance of the safety training involved in their operation. This research not only presents a new and useful solution to the safety training of construction operations, but illustrates the potential use of advanced technologies in solving construction industry problems in general. Copyright © 2011 Elsevier Ltd. All rights reserved.

  13. 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

  14. Work safety in the light of technological progress in mining. [Poland, accident and technology assessment for period 1950 to 1972

    Energy Technology Data Exchange (ETDEWEB)

    Stecko, R.

    1976-01-01

    This paper discusses positive and negative aspects of technological progress in black coal mining in Poland in the period from 1950 to 1972 on the basis of statistical data supplied by various institutions. Twenty three indexes characterizing both work safety and technological progress in underground coal mines are used. Equations of linear and non-linear even regression and equations of linear and non-linear multiple regression are derived on the basis of statistical records of 23 years. The equations are used to estimate indexes of work safety on the basis of technical progress indexes. It is suggested that from among 8 indexes characterizing work safety 4 are most useful and important: danger index, absenteeism index, frequency of underground fire index, and frequency of rock burst index. Analysis of the regression equation shows that technological progress in underground coal mines in Poland has caused a decrease in indexes describing: frequency of work accidents, frequency of underground fires, frequency of rock burst, and danger of underground work; and an increase in indexes characterizing: seriousness of work accidents, and absenteeism caused by work accidents. (84 refs.)

  15. Development of safety evaluation technology for fire and explosion in reprocessing plant

    International Nuclear Information System (INIS)

    Miura, Akihiko

    2005-01-01

    Based on some lessons learned from the accidents in the reprocessing plant all over the world, Japan Nuclear Cycle Development Institute (JNC) has researched and developed the safety technologies for the reprocessing plants and its related facilities. This paper describes some accidental information around the reprocessing plants and its related research activities in JNC. (author)

  16. CAD/CAE-technologies application for assessment of passenger safety on railway transport in emergency

    Science.gov (United States)

    Antipin, D. Ya; Shorokhov, S. G.; Bondarenko, O. I.

    2018-03-01

    A possibility of using current software products realizing CAD/CAE-technologies for the assessment of passenger safety in emergency cases on railway transport has been analyzed. On the basis of the developed solid computer model of an anthropometric dummy, the authors carried out an analysis of possible levels of passenger injury during accident collision of a train with an obstacle.

  17. 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

  18. Cultural factors influencing safety need to be addressed in design and operation of technology.

    Science.gov (United States)

    Meshkati, N

    1996-10-01

    Cultural factors which influence aviation safety in aircraft design, air traffic control, and human factors training are examined. Analysis of the Avianca Flight 052 crash in New York in January, 1990, demonstrates the catastrosphic effects cultural factors can play. Cultural factors include attitude toward work and technology, organizational hierarchy, religion, and population stereotyping.

  19. An Examination of Safety Management Systems and Aviation Technologies in the Helicopter Emergency Medical Services Industry

    Science.gov (United States)

    Buckner, Steven A.

    The Helicopter Emergency Medical Service (HEMS) industry has a significant role in the transportation of injured patients, but has experienced more accidents than all other segments of the aviation industry combined. With the objective of addressing this discrepancy, this study assesses the effect of safety management systems implementation and aviation technologies utilization on the reduction of HEMS accident rates. Participating were 147 pilots from Federal Aviation Regulations Part 135 HEMS operators, who completed a survey questionnaire based on the Safety Culture and Safety Management System Survey (SCSMSS). The study assessed the predictor value of SMS implementation and aviation technologies to the frequency of HEMS accident rates with correlation and multiple linear regression. The correlation analysis identified three significant positive relationships. HEMS years of experience had a high significant positive relationship with accident rate (r=.90; paviation technologies from a systems engineering application. Recommendations for practice included the adoption of existing regulatory guidance for a SMS program. A qualitative analysis was also recommended for future study SMS implementation and HEMS accident rate from the pilot's perspective. A quantitative longitudinal study would further explore inferential relationships between the study variables. Current strategies should include the increased utilization of available aviation technology resources as this proactive stance may be beneficial for the establishment of an effective safety culture within the HEMS industry.

  20. 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…

  1. 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.

  2. Application of Proteomics in Food Technology and Food Biotechnology: Process Development, Quality Control and Product Safety

    Directory of Open Access Journals (Sweden)

    Dajana Gašo-Sokač

    2010-01-01

    Full Text Available Human food is a very complex biological mixture and food processing and safety are very important and essential disciplines. Proteomics technology using different high-performance separation techniques such as two-dimensional gel electrophoresis, one-dimensional and multidimensional chromatography, combined with high-resolution mass spectrometry has the power to monitor the protein composition of foods and their changes during the production process. The use of proteomics in food technology is presented, especially for characterization and standardization of raw materials, process development, detection of batch-to-batch variations and quality control of the final product. Further attention is paid to the aspects of food safety, especially regarding biological and microbial safety and the use of genetically modified foods.

  3. Rising calls for food safety. Radiation technology becomes a timely answer

    International Nuclear Information System (INIS)

    Loaharanu, Paisan

    2001-01-01

    Food safety has become an issue of high priority to many governments. Well publicized cases have shown that an outbreak of a major foodborne disease can have health, political, and economic consequences. Coupled with the increasing interest and publicity by the media, public awareness and concerns about food safety have reached a new height. Issues related to mad cow disease, and genetically modified food have attracted further attention and concern. Awareness of risks involving microbiological contamination of food has increased significantly in the past decade. There have been several major foodborne disease outbreaks caused by various pathogenic bacteria and parasites and widespread coverage by the media. The outbreaks have focused closer attention on food processing technologies to ensure the safety and quality of food. This article reports on developments for the application of irradiation technology for food processing, which has been approved for use in more than 40 countries

  4. SAFETY

    CERN Multimedia

    M. Plagge, C. Schaefer and N. Dupont

    2013-01-01

    Fire Safety – Essential for a particle detector The CMS detector is a marvel of high technology, one of the most precise particle measurement devices we have built until now. Of course it has to be protected from external and internal incidents like the ones that can occur from fires. Due to the fire load, the permanent availability of oxygen and the presence of various ignition sources mostly based on electricity this has to be addressed. Starting from the beam pipe towards the magnet coil, the detector is protected by flooding it with pure gaseous nitrogen during operation. The outer shell of CMS, namely the yoke and the muon chambers are then covered by an emergency inertion system also based on nitrogen. To ensure maximum fire safety, all materials used comply with the CERN regulations IS 23 and IS 41 with only a few exceptions. Every piece of the 30-tonne polyethylene shielding is high-density material, borated, boxed within steel and coated with intumescent (a paint that creates a thick co...

  5. Advanced testing and validation centre gets electric vehicle technology to market faster

    Energy Technology Data Exchange (ETDEWEB)

    Astil, T.; Girard, F. [National Research Council of Canada, Vancouver, BC (Canada). Inst. for Fuel Cell Innovation

    2010-07-01

    The National Research Council (NRC) Institute for Fuel Cell Innovation is advancing Canada's clean energy advantage through NRC's technology cluster initiatives, which help Canadian small and medium enterprises achieve commercialization breakthroughs in key sectors. This presentation discussed the technology evaluation program (TEP) offered by the NRC Institute for Fuel Cell Innovation. The presentation discussed the TEPs mission, advanced testing and validation centre (ATVC), previous ATVC clients, environmental chamber, dynamometer, vibration table, electrochemical battery testing, and electrochemical testing laboratory. The ATVC is a specialized and safe environment for objective, reliable and accurate standardized testing applications of electric vehicle technologies. It offers independent test services to external organizations, making it easier to prove that electric vehicle technologies will perform under specific operating conditions. figs.

  6. 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

  7. Analysis of Aviation Safety Reporting System Incident Data Associated with the Technical Challenges of the Atmospheric Environment Safety Technology Project

    Science.gov (United States)

    Withrow, Colleen A.; Reveley, Mary S.

    2014-01-01

    This study analyzed aircraft incidents in the NASA Aviation Safety Reporting System (ASRS) that apply to two of the three technical challenges (TCs) in NASA's Aviation Safety Program's Atmospheric Environment Safety Technology Project. The aircraft incidents are related to airframe icing and atmospheric hazards TCs. The study reviewed incidents that listed their primary problem as weather or environment-nonweather between 1994 and 2011 for aircraft defined by Federal Aviation Regulations (FAR) Parts 121, 135, and 91. The study investigated the phases of flight, a variety of anomalies, flight conditions, and incidents by FAR part, along with other categories. The first part of the analysis focused on airframe-icing-related incidents and found 275 incidents out of 3526 weather-related incidents over the 18-yr period. The second portion of the study focused on atmospheric hazards and found 4647 incidents over the same time period. Atmospheric hazards-related incidents included a range of conditions from clear air turbulence and wake vortex, to controlled flight toward terrain, ground encounters, and incursions.

  8. A new principle for low-cost hydrogen sensors for fuel cell technology safety

    Energy Technology Data Exchange (ETDEWEB)

    Liess, Martin [Rhein Main University of Applied Sciences, Rüsselsheim, Wiesbaden (Germany)

    2014-03-24

    Hydrogen sensors are of paramount importance for the safety of hydrogen fuel cell technology as result of the high pressure necessary in fuel tanks and its low explosion limit. I present a novel sensor principle based on thermal conduction that is very sensitive to hydrogen, highly specific and can operate on low temperatures. As opposed to other thermal sensors it can be operated with low cost and low power driving electronics. On top of this, as sensor element a modified standard of-the shelf MEMS thermopile IR-sensor can be used. The sensor principle presented is thus suited for the future mass markets of hydrogen fuel cell technology.S.

  9. 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

  10. [Care with the child's health and validation of an educational technology for riverside families].

    Science.gov (United States)

    Teixeira, Elizabeth; de Almeida Siqueira, Aldo; da Silva, Joselice Pereira; Lavor, Lília Cunha

    2011-01-01

    This study aimed to assess the knowledge and ways of caring for the child health 0-5 years between riverine (Phase 1), and to validate an educational technology (Phase 2). It was carried out a descriptive qualitative study. With the mothers, focus groups and content analysis were used, and with judges-specialists and target-public-applied, forms. The study revealed that the concern with the care of a child between the riverine families permeates the adversity daily, with dedication and commitment of these families in maintaining the health of their children. The sensitivity listening of mothers indicated the need for a closer relationship between nursing professionals and family. The validation of the educational technology was convergent, within the parameters considered adequate.

  11. Validation of smart sensor technologies for instrument calibration reduction in nuclear power plants

    International Nuclear Information System (INIS)

    Hashemian, H.M.; Mitchell, D.W.; Petersen, K.M.; Shell, C.S.

    1993-01-01

    This report presents the preliminary results of a research and development project on the validation of new techniques for on-line testing of calibration drift of process instrumentation channels in nuclear power plants. These techniques generally involve a computer-based data acquisition and data analysis system to trend the output of a large number of instrument channels and identify the channels that have drifted out of tolerance. This helps limit the calibration effort to those channels which need the calibration, as opposed to the current nuclear industry practice of calibrating essentially all the safety-related instrument channels at every refueling outage

  12. 11-th International conference Nuclear power safety and nuclear education - 2009. Abstracts. Part 1. Session: Safety of nuclear technology; Innovative nuclear systems and fuel cycle; Nuclear knowledge management

    International Nuclear Information System (INIS)

    2009-01-01

    The book includes abstracts of the 11-th International conference Nuclear power safety and nuclear education - 2009 (29 Sep - 2 Oct, 2009, Obninsk). Problems of safety of nuclear technology are discussed, innovative nuclear systems and fuel cycles are treated. Abstracts on professional education for nuclear power and industry are presented. Nuclear knowledge management are discussed

  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. Technology and Safety of Nuclear Power Plant Based on Environment for Supporting Continuous Development

    International Nuclear Information System (INIS)

    Subki, M. Iyos R.; Arbie, Bakri; Lasman, As Natio; Azis, Ferhat

    2000-01-01

    The world has witnessed rapid changes in the last two and a half centuries. Entering the new century and millennium, many expects that drastic changes will happen, especially in the field of science and technology. With all its challenge and opportunity, the progress in science and technology is expected to result in innovative technologies to fulfil human needs for energy in the future. Because the energy supply can potentially increase the air pollution and cause global warming, the choice of energy technology must be made wisely. NPPs employ high and reliable technology with good safety records. It has been known as clean, environmental friendly, and relatively economic source of energy. Moreover, the design of advanced reactor and that of the coming generation is practically catastrophe-free and proliferation resistant, besides producing minimal waste. For that reason, nuclear power should be considered as an alternative source of energy which can support sustainable development

  15. The assessment of technological and safety aspects of small power reactor SMART

    International Nuclear Information System (INIS)

    Antariksawan, A.R.; Ekariansyah, Andi S.; Sony, D.T.; Suharno; Hastowo, Hudi

    2002-01-01

    This paper describes and discusses the technology and safety of small nuclear power plant SMART. The reactor SMART produces 300 MWth of power is cooled and moderated with light water and integral PWR type developed by KAERI. At present, the development activities had reached the end of basic design stage. The concept design of reactor SMART is based on safety enhancement, economic competitiveness and high performance. The fuel is uranium oxide with approximately 5% w/o enrichment. The safety characteristics of the core are shown with low power density around 62.6 W/cc, high negative reactivity coefficient, and high shutdown and thermal margin. Besides the inherent safety characteristics, SMART is equipped with engineered safety features and severe accident management system which are in compliance with the IAEA recommendations. The application of SMART for dual-purpose produces 90 Mwe and 40,000 to fresh water a day. Based on the technology and core characteristics of the reactor SMART, it is very interesting to be deeply assessed

  16. Aviation Trends Related to Atmospheric Environment Safety Technologies Project Technical Challenges

    Science.gov (United States)

    Reveley, Mary S.; Withrow, Colleen A.; Barr, Lawrence C.; Evans, Joni K.; Leone, Karen M.; Jones, Sharon M.

    2014-01-01

    Current and future aviation safety trends related to the National Aeronautics and Space Administration's Atmospheric Environment Safety Technologies Project's three technical challenges (engine icing characterization and simulation capability; airframe icing simulation and engineering tool capability; and atmospheric hazard sensing and mitigation technology capability) were assessed by examining the National Transportation Safety Board (NTSB) accident database (1989 to 2008), incidents from the Federal Aviation Administration (FAA) accident/incident database (1989 to 2006), and literature from various industry and government sources. The accident and incident data were examined for events involving fixed-wing airplanes operating under Federal Aviation Regulation (FAR) Parts 121, 135, and 91 for atmospheric conditions related to airframe icing, ice-crystal engine icing, turbulence, clear air turbulence, wake vortex, lightning, and low visibility (fog, low ceiling, clouds, precipitation, and low lighting). Five future aviation safety risk areas associated with the three AEST technical challenges were identified after an exhaustive survey of a variety of sources and include: approach and landing accident reduction, icing/ice detection, loss of control in flight, super density operations, and runway safety.

  17. Outage Risk Assessment and Management (ORAM) technology to improve outage safety and economics

    International Nuclear Information System (INIS)

    Kalra, S.P.

    2004-01-01

    The Electric Power Research Institute (EPRI) has undertaken an aggressive program, called ORAM (Outage Risk Assessment and Management), to provide utilities with tools and technology to assist in managing risk during the planning and conduct of outages. The ORAM program consists of the following 6 steps: i) Perform utility surveys and visits on shutdown risk management needs, ii) Perform probabilistic shutdown safety assessments (PSSAs) to identify generic insights that can be incorporated into risk management guidelines and identify selected areas for the development of contingency actions, iii) Develop risk management guidelines (RMG's) that provide a systematic approach to the planning and conduct of outages from a safety perspective. Incorporate insights from the shutdown safety assessments and other operating experience into the RMG's. iv) Develop selected contingency actions including a thermalhydraulic tool kit to address higher risk time periods and activities identified in the shutdown safety assessments, v) Develop computer software that integrates all of the above capability into an easy to use tool for effective shutdown operation management for utilities, vi) Provide assistance in the transfer of this technology and the application of these tools. This paper briefly describes the technical approach and tools developed under EPRI's ORAM program and its applications for improving outage safety and economics. (author)

  18. Technology Development, Evaluation, and Application (TDEA) FY 2001 Progress Report Environment, Safety, and Health (ESH) Division

    Energy Technology Data Exchange (ETDEWEB)

    L.G. Hoffman; K. Alvar; T. Buhl; E. Foltyn; W. Hansen; B. Erdal; P. Fresquez; D. Lee; B. Reinert

    2002-05-01

    This progress report presents the results of 11 projects funded ($500K) in FY01 by the Technology Development, Evaluation, and Application (TDEA) Committee of the Environment, Safety, and Health Division (ESH). Five projects fit into the Health Physics discipline, 5 projects are environmental science and one is industrial hygiene/safety. As a result of their TDEA-funded projects, investigators have published sixteen papers in professional journals, proceedings, or Los Alamos reports and presented their work at professional meetings. Supplement funds and in-kind contributions, such as staff time, instrument use, and workspace, were also provided to TDEA-funded projects by organizations external to ESH Divisions.

  19. The Space Technology-7 Disturbance Reduction System Precision Control Flight Validation Experiment Control System Design

    Science.gov (United States)

    O'Donnell, James R.; Hsu, Oscar C.; Maghami, Peirman G.; Markley, F. Landis

    2006-01-01

    As originally proposed, the Space Technology-7 Disturbance Reduction System (DRS) project, managed out of the Jet Propulsion Laboratory, was designed to validate technologies required for future missions such as the Laser Interferometer Space Antenna (LISA). The two technologies to be demonstrated by DRS were Gravitational Reference Sensors (GRSs) and Colloidal MicroNewton Thrusters (CMNTs). Control algorithms being designed by the Dynamic Control System (DCS) team at the Goddard Space Flight Center would control the spacecraft so that it flew about a freely-floating GRS test mass, keeping it centered within its housing. For programmatic reasons, the GRSs were descoped from DRS. The primary goals of the new mission are to validate the performance of the CMNTs and to demonstrate precise spacecraft position control. DRS will fly as a part of the European Space Agency (ESA) LISA Pathfinder (LPF) spacecraft along with a similar ESA experiment, the LISA Technology Package (LTP). With no GRS, the DCS attitude and drag-free control systems make use of the sensor being developed by ESA as a part of the LTP. The control system is designed to maintain the spacecraft s position with respect to the test mass, to within 10 nm/the square root of Hz over the DRS science frequency band of 1 to 30 mHz.

  20. 77 FR 50723 - Verification, Validation, Reviews, and Audits for Digital Computer Software Used in Safety...

    Science.gov (United States)

    2012-08-22

    ... regulations with respect to software verification and auditing of digital computer software used in the safety... Standards and Records,'' which requires, in part, that a quality assurance program be established and implemented to provide adequate assurance that systems and components important to safety will satisfactorily...

  1. Reliability and validity of a scale to measure consumer attitudes regarding the private food safety certification of restaurants.

    Science.gov (United States)

    Uggioni, Paula Lazzarin; Salay, Elisabete

    2012-04-01

    Validated and reliable instruments for measuring consumer attitudes regarding food quality certifications are lacking, but the measurement of consumer attitude could be an important tool for understanding consumer behavior. Thus the objective of this study was to develop an instrument for measuring consumer attitudes regarding private food safety certifications for commercial restaurants. To this end, the following steps were carried out: development of the interview items; complete pilot testing; item analyses (influence of social desirability and total-item correlation); reliability test (internal consistency and test-retest); and validity assessment (content and discriminative validity and exploratory and confirmatory factor analysis). The subjects, all over the age of 18 and drawn from six non-probabilistic samples (n=7-350) in the city of Campinas, Brazil, were all subjected to an interview. The final scale included 24 items and had a Cronbach's alpha coefficient of 0.79 and a content validation coefficient of 0.99, both within acceptable limits. The confirmatory factor analysis validated a model with five factors and the final instrument discriminated reasonably well between the groups and showed satisfactory reproducibility (r=0.955). Furthermore, the scale validity and reliability were satisfactory, suggesting it could also be applied to future studies. Copyright © 2011 Elsevier Ltd. All rights reserved.

  2. Study of fieldbus technology confiability when applied in a Sterilization plant control and safety systems

    International Nuclear Information System (INIS)

    Karma, D.; Sampa, M.H.O.; Rela, P.R.

    2001-01-01

    Several sterilization processes have been used in these years for treatment of countless products. Some processes use high temperatures, thermal shocks and chemical agents. With the discovery of the ionizing radiation and its posterior technological developments turned possible the application of that process, in 1960, also in the sterilization, denominated radiation sterilization. This process became also applied in another areas of health and industrial as food conservation, gemstones enhancement and others. The radiation sterilization requests an effective control and it needs a high level of safety. The commercial use of the computers applied in industrial automation provides and the domain of new technologies in this field provides news applications then new designs now is possible. The Fieldbus technology, a new digital communication protocol, like a Local Area Network, can be an alternative in the cobalt-60 irradiation plant. This paper show preliminary study about confiability in systems using Fieldbus technology. This technology was simulated in sterilization plant control and safety systems and the fail probability was quantified using Fail Tree Analysis Method. Fieldbus technology can be used in sterilization plants because the confiability in this systems is like PLCs and relays systems, was the conclusion

  3. [A simplified occupational health and safety management system designed for small enterprises. Initial validation results].

    Science.gov (United States)

    Bacchi, Romana; Veneri, L; Ghini, P; Caso, Maria Alessandra; Baldassarri, Giovanna; Renzetti, F; Santarelli, R

    2009-01-01

    Occupational Health and Safety Management Systems (OHSMS) are known to be effective in improving safety at work. Unfortunately they are often too resource-heavy for small businesses. The aim of this project was to develop and test a simplified model of OHSMS suitable for small enterprises. The model consists of 7 procedures and various operating forms and check lists, that guide the enterprise in managing safety at work. The model was tested in 15 volunteer enterprises. In most of the enterprises two audits showed increased awareness and participation of workers; better definition and formalisation of respon sibilities in 8 firms; election of Union Safety Representatives in over one quarter of the enterprises; improvement of safety equipment. The study also helped identify areas where the model could be improved by simplification of unnecessarily complex and redundant procedures.

  4. Applying the Precaution Adoption Process Model to the Acceptance of Mine Safety and Health Technologies.

    Science.gov (United States)

    Haas, Emily J

    2018-03-01

    Mineworkers are continually introduced to protective technologies on the job. Yet, their perceptions toward the technologies are often not addressed until they are actively trying to use them, which may halt safe technology adoption and associated work practices. This study explored management and worker perspectives toward three technologies to forecast adoption and behavioral intention on the job. Interviews and focus groups were conducted with 21 mineworkers and 19 mine managers to determine the adoption process stage algorithm for workers and managers, including perceived barriers to using new safety and health technologies. Differences between workers and managers were revealed in terms of readiness, perceptions, and initial trust in using technologies. Workers, whether they had or had not used a particular technology, still had negative perceptions toward its use in the initial introduction and integration at their mine site, indicating a lengthy time period needed for full adoption. The key finding from these results is that a carefully considered and extended introduction of technology for workers in Stage 3 (undecided to act) is most important to promote progression to Stage 5 (decided to act) and to avoid Stage 4 (decided not to act). In response, organizational management may need to account for workers' particular stage algorithm, using the Precaution Adoption Process Model, to understand how to tailor messages about protective technologies, administer skill-based trainings and interventions that raise awareness and knowledge, and ultimately encourage safe adoption of associated work practices.

  5. Instrument for assessing mobile technology acceptability in diabetes self-management: a validation and reliability study.

    Science.gov (United States)

    Frandes, Mirela; Deiac, Anca V; Timar, Bogdan; Lungeanu, Diana

    2017-01-01

    Nowadays, mobile technologies are part of everyday life, but the lack of instruments to assess their acceptability for the management of chronic diseases makes their actual adoption for this purpose slow. The objective of this study was to develop a survey instrument for assessing patients' attitude toward and intention to use mobile technology for diabetes mellitus (DM) self-management, as well as to identify sociodemographic characteristics and quality of life factors that affect them. We first conducted the documentation and instrument design phases, which were subsequently followed by the pilot study and instrument validation. Afterward, the instrument was administered 103 patients (median age: 37 years; range: 18-65 years) diagnosed with type 1 or type 2 DM, who accepted to participate in the study. The reliability and construct validity were assessed by computing Cronbach's alpha and using factor analysis, respectively. The instrument included statements about the actual use of electronic devices for DM management, interaction between patient and physician, attitude toward using mobile technology, and quality of life evaluation. Cronbach's alpha was 0.9 for attitude toward using mobile technology and 0.97 for attitude toward using mobile device applications for DM self-management. Younger patients (Spearman's ρ =-0.429; P higher education level (Kendall's τ =0.51; P mobile assistive applications for DM control. Moreover, patients with a higher quality of life presented a significantly more positive attitude toward using modern technology (Spearman's ρ =0.466; P mobile technology for DM self-management. Additionally, we found that even if most of the patients showed positive attitude toward mobile applications, only a moderate level of intention to indeed use them was observed. Moreover, the study indicated that barriers were truthfulness and easiness to use.

  6. Contributions to nuclear safety and radiation technologies in Ukraine by the Science and Technology Center in Ukraine (STCU)

    International Nuclear Information System (INIS)

    Taranenko, L.; Janouch, F.; Owsiacki, L.

    2001-01-01

    This paper presents Science and Technology Center in Ukraine (STCU) activities devoted to furthering nuclear and radiation safety, which is a prioritized STCU area. The STCU, an intergovernmental organization with the principle objective of non-proliferation, administers financial support from the USA, Canada, and the EU to Ukrainian projects in various scientific and technological areas; coordinates projects; and promotes the integration of Ukrainian scientists into the international scientific community, including involving western collaborators. The paper focuses on STCU's largest project to date 'Program Supporting Y2K Readiness at Ukrainian NPPs' initiated in April 1999 and designed to address possible Y2K readiness problems at 14 Ukrainian nuclear reactors. Other presented projects demonstrate a wide diversity of supported directions in the fields of nuclear and radiation safety, including reactor material improvement ('Improved Zirconium-Based Elements for Nuclear Reactors'), information technologies for nuclear industries ('Ukrainian Nuclear Data Bank in Slavutich'), and radiation health science ('Diagnostics and Treatment of Radiation-Induced Injuries of Human Biopolymers').

  7. Contributions to nuclear safety and radiation technologies in Ukraine by the Science and Technology Center in Ukraine (STCU)

    Energy Technology Data Exchange (ETDEWEB)

    Taranenko, L. E-mail: lyubov@stcu.kiev.ua; Janouch, F.; Owsiacki, L

    2001-06-01

    This paper presents Science and Technology Center in Ukraine (STCU) activities devoted to furthering nuclear and radiation safety, which is a prioritized STCU area. The STCU, an intergovernmental organization with the principle objective of non-proliferation, administers financial support from the USA, Canada, and the EU to Ukrainian projects in various scientific and technological areas; coordinates projects; and promotes the integration of Ukrainian scientists into the international scientific community, including involving western collaborators. The paper focuses on STCU's largest project to date 'Program Supporting Y2K Readiness at Ukrainian NPPs' initiated in April 1999 and designed to address possible Y2K readiness problems at 14 Ukrainian nuclear reactors. Other presented projects demonstrate a wide diversity of supported directions in the fields of nuclear and radiation safety, including reactor material improvement ('Improved Zirconium-Based Elements for Nuclear Reactors'), information technologies for nuclear industries ('Ukrainian Nuclear Data Bank in Slavutich'), and radiation health science ('Diagnostics and Treatment of Radiation-Induced Injuries of Human Biopolymers')

  8. Thermal-hydraulic codes validation for safety analysis of NPPs with RBMK

    International Nuclear Information System (INIS)

    Brus, N.A.; Ioussoupov, O.E.

    2000-01-01

    This work is devoted to validation of western thermal-hydraulic codes (RELAP5/MOD3 .2 and ATHLET 1.1 Cycle C) in application to Russian designed light water reactors. Such validation is needed due to features of RBMK reactor design and thermal-hydraulics in comparison with PWR and BWR reactors, for which these codes were developed and validated. These validation studies are concluded with a comparison of calculation results of modeling with the thermal-hydraulics codes with the experiments performed earlier using the thermal-hydraulics test facilities with the experimental data. (authors)

  9. Development of Basic Key Technologies for Gen IV SFR Safety Evaluation

    International Nuclear Information System (INIS)

    Jeong, Hae Yong; Kwon, Young Min; Kim, Tae Woon; Park, Soo Yong; Suk, Soo Dong; Lee, Kwi Lim; Lee, Yong Bum; Chang, Won Pyo; Ha, Kwi Seok; Hahn, Sang Hoon

    2010-07-01

    Safety issues and design requirements on control rod worth were identified through the evaluation of safety design characteristics and the preliminary safety evaluation. This results will be taken into account for the conceptual design studies of the demonstration reactor in the next stage. The Level-1 Pasa has been performed and a quantitative Cdf value was produced for the selected design from the several candidates. The inherent safety characteristics of the selected design were evaluated through the DBE and ATWS analyses. A surrogate material for Tru has been selected which is applicable to the study of liquidus/solidus temperature test for the metallic fuel containing Tru. A methodology for the regression analysis with surrogate material has been developed and valuable data on metal fuel liquidus/solidus temperature have been measured. A simple mechanistic model describing a bending of subassemblies has been formulated based on the foreign test data and existing models. Its applicability has been evaluated for the Phenix design. New criteria of the core damage for the SFR PSA were identified. The list of initiating events, system response event tree, and core response event tree, which constitute a PSA methodology for an SFR, have been introduced. By developing the SFR PIRT, phenomenological model features, which have to be satisfied in a safety code, were defined and the PIRT results were applied to the design of the PDRC test facility. Bases for a safety evaluation methodology for the SFR DBEs have been also prepared. A draft version of the topical report on the code for local fault analysis has been completed. Since 2007, the MARS-LMR code has been developed and assessments for model validation with the test data from EBR-II and Phenix reactor have been continued. The code has been applied to the evaluation of passive safety of a conceptual design of Gen IV SFR

  10. Proceedings of the 8. National Seminar on Technology and Safety of Nuclear Power Plants and Nuclear Facilities

    International Nuclear Information System (INIS)

    Antariksawan, Anhar R.; Soetrisnanto, Arnold Y.; Aziz, Ferhat; Untoro, Pudji; Su'ud, Zaki; Zarkasi, Amin Santosa; Umar, Faraz H.; Teguh Bambang; Hafnan, M.; Mustafa, Bustani; Rosfian, H.

    2002-10-01

    The eight proceeding of National Seminar on Technology and Safety of Nuclear Power Plant and Nuclear Facilities held by National Atomic Energy Agency and University of Trisakti. The aims of Seminar is to exchange and disseminate information about safety and nuclear Power Plant Temperature Reactor and Application for National Development sustain able and High Technology. This Seminar covers all aspect Technology, Power Reactor : Research Reactor; High Temperature Reactor and Nuclear Facilities. There are 33 articles have separated index

  11. Examination of the bases for proposed innovations in reactor safety technology

    International Nuclear Information System (INIS)

    Moses, D.L.

    1986-01-01

    This paper employs the criteria for evaluations from the Nuclear Power Option Viability Study to examine the bases for proposed innovations in light water reactor safety technology. These bases for innovation fall into four broad categories as follows: (1) virtually exclusive reliance on passive safety features to preclude core damage in all situations, (2) design simplification using some passive safety features to reduce the frequency of core damage to less than about 10 -6 per reactor-year, (3) passive containment to preclude releases from any accident, and (4) designing to limit licensing attention to one or at least a few systems. Of these, only the first two, and perhaps only the second, hold significant promise for providing for the viability of advanced light water reactors

  12. 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...

  13. Anticipated development of radiation safety corresponding to utilization of nuclear technology in Vietnam

    International Nuclear Information System (INIS)

    Tran, Toan Ngoc; Le, Thiem Ngoc

    2010-01-01

    In the past, due to the limited application of radiation and radioisotope in the national economic branches, radiation safety was not paid much attention to in Vietnam. However, according to the Strategy for Peaceful Utilization of Atomic Energy up to 2020 approved by the Prime Minister on January 3, 2006 the application of radiation and radioisotopes as well as nuclear power in Vietnam is expected increasing strongly and widely, then radiation safety should be developed correspondingly. This paper presents the history of radiation protection, the current status and prospect of utilization of atomic energy and the anticipated development of the national radiation safety system to meet the demand of utilization of nuclear technology in Vietnam. (author)

  14. Some problems of neutron source multiplication method for site measurement technology in nuclear critical safety

    International Nuclear Information System (INIS)

    Shi Yongqian; Zhu Qingfu; Hu Dingsheng; He Tao; Yao Shigui; Lin Shenghuo

    2004-01-01

    The paper gives experiment theory and experiment method of neutron source multiplication method for site measurement technology in the nuclear critical safety. The measured parameter by source multiplication method actually is a sub-critical with source neutron effective multiplication factor k s , but not the neutron effective multiplication factor k eff . The experiment research has been done on the uranium solution nuclear critical safety experiment assembly. The k s of different sub-criticality is measured by neutron source multiplication experiment method, and k eff of different sub-criticality, the reactivity coefficient of unit solution level, is first measured by period method, and then multiplied by difference of critical solution level and sub-critical solution level and obtained the reactivity of sub-critical solution level. The k eff finally can be extracted from reactivity formula. The effect on the nuclear critical safety and different between k eff and k s are discussed

  15. Fundamentals of automotive and engine technology standard drives, hybrid drives, brakes, safety systems

    CERN Document Server

    2014-01-01

    Hybrid drives and the operation of hybrid vehicles are characteristic of contemporary automotive technology. Together with the electronic driver assistant systems, hybrid technology is of the greatest importance and both cannot be ignored by today’s car drivers. This technical reference book provides the reader with a firsthand comprehensive description of significant components of automotive technology. All texts are complemented by numerous detailed illustrations. Contents History of the automobile.- History of the Diesel engine.- Areas of use for Diesel engines.- Basic principles of the Diesel engine.- Basic principles of Diesel fuel-injection.- Basic principles of the gasoline engine.- Inductive ignition system.- Transmissions for motor vehicles.- Motor vehicle safety.- Basic principles of vehicle dynamics.- Car braking systems.- Vehicle electrical systems.- Overview of electrical and electronic systems in the vehicle.- Control of gasoline engines.- Control of Diesel engines.- Lighting technology.- Elec...

  16. Implementing technology to improve medication safety in healthcare facilities: a literature review.

    Science.gov (United States)

    Hidle, Unn

    Medication errors remain one of the most common causes of patient injuries in the United States, with detrimental outcomes including adverse reactions and even death. By developing a better understanding of why and how medication errors occur, preventative measures may be implemented including technological advances. In this literature review, potential methods of reducing medication errors were explored. Furthermore, technology tools available for medication orders and administration are described, including advantages and disadvantages of each system. It was found that technology can be an excellent aid in improving safety of medication administration. However, computer technology cannot replace human intellect and intuition. Nurses should be involved when implementing any new computerized system in order to obtain the most appropriate and user-friendly structure.

  17. A comparative study on the effective safety of nuclear technology in Korea

    Energy Technology Data Exchange (ETDEWEB)

    Soh, Young Jin [Daegu University, Daegu (Korea); Kim, Young Pyoung [Korea University, Seoul (Korea); Jung, Yoon Soo [Myoungji University, Seoul (Korea); Chung, Ik Jae; Choi, Byung Sun [Seoul National University, Seoul (Korea)

    2001-12-01

    The main purpose of this research is to analyze Korean perception of nuclear risk in comparison with other technological risks. In order to understand the characteristics of risk perception, the concept of 'effective safety' is clarified and defined. This research also covers such issues as relative riskiness of major risks, risk attitude, risk attribution, behavioral pattern for risky situation, and risk knowledge. A nation-wide survey was conducted for this study with a sample size of 1870. It was based on the purposive quota sampling to compare nuclear risk and other technological risks selected are 6 groups of risk; nuclear risk, environmental risk, traffic risk, chemical materials, industrial safety, and other recent risks. Accross these groups, a total of 25 risks are examined. 52 refs., 14 figs., 125 tabs. (Author)

  18. 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.

  19. The International Science and Technology Center (ISTC) and ISTC projects related to nuclear safety. Information review

    International Nuclear Information System (INIS)

    Tocheny, Lev V.

    2003-01-01

    The ISTC is an intergovernmental organization created ten years ago by Russia, USA, EU and Japan in Moscow. The Center supports numerous science and technology projects in different areas, from biotechnologies and environmental problems to all aspects of nuclear studies, including those focused on the development of effective innovative concepts and technologies in the nuclear field, in general, and for improvement of nuclear safety, in particular. The presentation addresses some technical results of the ISTC projects as well as methods and approaches employed by the ISTC to foster close international collaboration and manage projects towards fruitful results. (author)

  20. Review and assessments of potential environmental, health and safety impacts of MHD technology. Final draft

    Energy Technology Data Exchange (ETDEWEB)

    1978-01-01

    The purpose of this document is to develop an environmental, health and safety (EH and S) assessment and begin a site - specific assessment of these and socio - economic impacts for the magnetohydrodynamics program of the United States Department of Energy. This assessment includes detailed scientific and technical information on the specific EH and S issues mentioned in the MHD Environmental Development Plan. A review of current literature on impact-related subjects is also included. This document addresses the coal-fired, open-cycle MHD technology and reviews and assesses potential EH and S impacts resulting from operation of commercially-installed technology.

  1. Increasing the quality and safety of meat products through high technology methods during their storage

    International Nuclear Information System (INIS)

    Miteva, D.; Nacheva, I.; Georgieva, L.

    2008-01-01

    The aim of this study was to increase the quality and safety of different meat products by applying two high technology methods – lyophilization and gamma-irradiation. Object of study were chicken, pork and beef meat products. The organoleptic, physicochemical and microbiological properties after lyophilization, irradiation with gamma-rays and during the preservation of the samples were studied. The results indicated that the application of the two original technologies for preservation could ensure qualitative and long-lasting preservation of meat products with excellently preserved taste and organoleptic properties

  2. Triangulation and the importance of establishing valid methods for food safety culture evaluation.

    Science.gov (United States)

    Jespersen, Lone; Wallace, Carol A

    2017-10-01

    The research evaluates maturity of food safety culture in five multi-national food companies using method triangulation, specifically self-assessment scale, performance documents, and semi-structured interviews. Weaknesses associated with each individual method are known but there are few studies in food safety where a method triangulation approach is used for both data collection and data analysis. Significantly, this research shows that individual results taken in isolation can lead to wrong conclusions, resulting in potentially failing tactics and wasted investments. However, by applying method triangulation and reviewing results from a range of culture measurement tools it is possible to better direct investments and interventions. The findings add to the food safety culture paradigm beyond a single evaluation of food safety culture using generic culture surveys. Copyright © 2017. Published by Elsevier Ltd.

  3. Embedding technology into inter-professional best practices in home safety evaluation.

    Science.gov (United States)

    Burns, Suzanne Perea; Pickens, Noralyn Davel

    2017-08-01

    To explore inter-professional home evaluators' perspectives and needs for building useful and acceptable decision-support tools for the field of home modifications. Twenty semi-structured interviews were conducted with a range of home modification professionals from different regions of the United States. The interview transcripts were analyzed with a qualitative, descriptive, perspective approach. Technology supports current best practice and has potential to inform decision making through features that could enhance home evaluation processes, quality, efficiency and inter-professional communication. Technological advances with app design have created numerous opportunities for the field of home modifications. Integrating technology and inter-professional best practices will improve home safety evaluation and intervention development to meet client-centred and societal needs. Implications for rehabilitation Understanding home evaluators technology needs for home safety evaluations contributes to the development of app-based assessments. Integrating inter-professional perspectives of best practice and technological needs in an app for home assessments improves processes. Novice and expert home evaluators would benefit from decision support systems embedded in app-based assessments. Adoption of app-based assessment would improve efficiency while remaining client-centred.

  4. Safety awareness educational topics for the construction of power transmission systems with smart grid technologies

    Directory of Open Access Journals (Sweden)

    Bryan Hubbard

    2013-09-01

    Full Text Available Power transmission facilities in the U.S. are undergoing a transformation due to the increased use of distributed generation sources such as wind and solar power.  The current power grid system is also antiquated and in need of substantial retrofits to make it more efficient and reliable.  The new energy transmission system being designed and built to optimize power delivery is known as “Smart Grid”.  The increased activity in the construction of power transmission facilities and installation of new technologies into the current power system raises potential safety concerns.  Existing construction management curriculum may include general information about safety training, but does not typically include information about this specialized sector.  The objective of this study was to work with industry to identify key safety topics appropriate for inclusion in an introductory industrial construction course.  Results of interviews with industry identified numerous hazards that are not typically covered in typical construction curricula.  A joint undergraduate and graduate course in industrial construction was created to address these and additional concepts. A survey of the students was performed to determine the effectiveness of the course and also to determine their thoughts about the smart grid technologies and safety training. Information on electrical system hazards is presented along with results of the student surveys.

  5. SAFETY CRITERION IN ASSESSING THE IMPORTANCE OF AN ELEMENT IN THE COMPLEX TECHNOLOGICAL SYSTEM RELIABILITY STRUCTURE

    Directory of Open Access Journals (Sweden)

    Leszek CHYBOWSKI

    2012-01-01

    Full Text Available The paper presents the need to develop a description of the importance of the technological systems reliability structure elements in terms of security of the system. Basic issues related to the exploration of weak links and important elements in the system as well as a proposal to develop the current approach to assessing the importance of the system components have been presented. Moreover, the differences between the unreliability of suitability and unreliability of safety have been pointed out.

  6. Analysis on Pollution Factors in Asparagus Production and Research on Safety Production Technology

    OpenAIRE

    Ma, Liping; Hao, Bianqing; Qiao, Xiongwu

    2013-01-01

    Based on the analysis on the infection degree, infection law and influencing factors of the main diseases on asparagus and the analysis on the pollution factors in asparagus production such as blind pesticide use, atmospheric pollution and acid rain, the pollution of soil and fertilizer, this article proposes asparagus safety production technologies which include the selection of disease-resistant variety and suitable planting field, scientific and reasonable disease control, balanced fertili...

  7. Prospects of cloud technology development: information safety and personal data protection in cloud media

    International Nuclear Information System (INIS)

    Malyuk, A.A.; Ozhered, I.V.

    2013-01-01

    Proper definitions are given and an architecture is proposed for the model of cloud computing. Approaches that can ensure the safety on each level of the architecture are considered. Special attention is given to issues related to the confidence of providers, authentic user identification, and data encoding, juridical issues that are encountered in the use of this technology, prospects of its implementation, and further development of cloud computing [ru

  8. Development and Validation of Web-Based Courseware for Junior Secondary School Basic Technology Students in Nigeria

    Directory of Open Access Journals (Sweden)

    Amosa Isiaka Gambari

    2018-02-01

    Full Text Available This research aimed to develop and validate a web-based courseware for junior secondary school basic technology students in Nigeria. In this study, a mixed method quantitative pilot study design with qualitative components was used to test and ascertain the ease of development and validation of the web-based courseware. Dick and Carey instructional system design model was adopted for developing the courseware. Convenience sampling technique was used in selecting the three content, computer and educational technology experts to validate the web-based courseware. Non-randomized and non-equivalent Junior secondary school students from two schools were used for field trial validation. Four validating instruments were employed in conducting this study: (i Content Validation Assessment Report (CVAR; (ii Computer Expert Validation Assessment Report (CEAR; (iii Educational Technology Experts Validation Assessment Report (ETEVAR; and (iv Students Validation Questionnaire (SVQ. All the instruments were face and content validated. SVQ was pilot tested and reliability coefficient of 0.85 was obtained using Cronbach Alpha. CVAR, CEAR, ETEVAR were administered on content specialists, computer experts, and educational technology experts, while SVQ was administered on 83 JSS students from two selected secondary schools in Minna. The findings revealed that the process of developing web-based courseware using Dick and Carey Instructional System Design was successful. In addition, the report from the validating team revealed that the web-based courseware is valuable for learning basic technology. It is therefore recommended that web-based courseware should be produced to teach basic technology concepts on large scale.

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

    International Nuclear Information System (INIS)

    1986-11-01

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

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

    International Nuclear Information System (INIS)

    1986-06-01

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

  11. The validity of visual acuity assessment using mobile technology devices in the primary care setting.

    Science.gov (United States)

    O'Neill, Samuel; McAndrew, Darryl J

    2016-04-01

    The assessment of visual acuity is indicated in a number of clinical circumstances. It is commonly conducted through the use of a Snellen wall chart. Mobile technology developments and adoption rates by clinicians may potentially provide more convenient methods of assessing visual acuity. Limited data exist on the validity of these devices and applications. The objective of this study was to evaluate the assessment of distance visual acuity using mobile technology devices against the commonly used 3-metre Snellen chart in a primary care setting. A prospective quantitative comparative study was conducted at a regional medical practice. The visual acuity of 60 participants was assessed on a Snellen wall chart and two mobile technology devices (iPhone, iPad). Visual acuity intervals were converted to logarithm of minimum angle of resolution (logMAR) scores and subjected to intraclass correlation coefficient (ICC) assessment. The results show a high level of general agreement between testing modality (ICC 0.917 with a 95% confidence interval of 0.887-0.940). The high level of agreement of visual acuity results between the Snellen wall chart and both mobile technology devices suggests that clinicians can use this technology with confidence in the primary care setting.

  12. Contributions of the food irradiation technology to the nutritional and alimentary safety

    International Nuclear Information System (INIS)

    Ferreira, Sonia Regina Schauffert

    1999-01-01

    This work is a bibliographic review about the contributions of the food irradiation technology on nutritional and alimentary safety. Subjected to research and development for more than 60 years, these technology was approved by a jointly FAO/WHO/IAEA Expert Committees in 1980 with the conclusion that the irradiation of food up to an overall average dose of 10 kGy present no toxicological hazard and introduce no special nutritional or microbiological problems. Following these conclusions general standards and practices for food irradiation were adopted by the Codex Alimentarium Commission in 1983, opening the possibilities for internal applications and international commerce of irradiated food in many countries. Radiation from radioisotopes sources, electron accelerators or X-ray generators can be applied to food in order to reduce the microbial load, insect disinfestation, improving the shelf life extension of the products. Absorbed doses up to 10 kGy level do not introduce significant alterations in the macro or micro nutrients contents or in the sensorial characteristic of irradiated food. Although food safety can be related with many other important topics, irradiation technology improving food quality, reducing food spoilage during preservation and preventing problems related with food borne disease present a good potential to contribute with the foment and guaranty of the nutritional and alimentary safety. (author)

  13. Validation studies of thermal-hydraulic code for safety analysis of nuclear power plants

    International Nuclear Information System (INIS)

    Haapalehto, T.

    1995-01-01

    The thesis gives an overview of the validation process for thermal-hydraulic system codes and it presents in more detail the assessment and validation of the French code CATHARE for VVER calculations. Three assessment cases are presented: loop seal clearing, core reflooding and flow in a horizontal steam generator. The experience gained during these assessment and validation calculations has been used to analyze the behavior of the horizontal steam generator and the natural circulation in the geometry of the Loviisa nuclear power plant. Large part of the work has been performed in cooperation with the CATHARE-team in Grenoble, France. (41 refs., 11 figs., 8 tabs.)

  14. 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...

  15. ECOLOGY SAFETY TECHNOLOGIES OF UNCONVENTIONAL OIL RESERVES RECOVERY FOR SUSTAINABLE OIL AND GAS INDUSTRY DEVELOPMENT

    Directory of Open Access Journals (Sweden)

    Viacheslav Zyrin

    2016-09-01

    Full Text Available The problem of effective technology for heavy oil recovery nowadays has a great importance, because of worsening geological conditions of the developed deposits, decreasing recovery factor, increasing the part of heavy oil. For the future sustainable development of oil producing industry the involved technologies must require energy effectiveness and ecological safety. The paper proves the enhanced oil recovery methods necessity for heavy oil deposits, highlighted thermal technologies as the most effective. But traditional thermal treatment technologies is a source of air pollutant emission, such as CO, NO etc. The calculation of emissions for traditional steam generator is provided. Besides, the paper shows the effectiveness of electrical enhanced oil recovery methods. The advantages of associated gas as a fuel for cogeneration plants is shown. The main approaches to implementation of carbon dioxide sequestration technologies in the oil and gas industry of Russia are defined. Conceptual view of СО2-EOR technologies potential within the context of sustainable development of oil and gas industry are presented. On the basis of the conducted research a number of scientific research and practical areas of the CCS technology development are revealed.

  16. Cost-Effective ISS Space-Environment Technology Validation of Advanced Roll-Out Solar Array (ROSA), Phase II

    Data.gov (United States)

    National Aeronautics and Space Administration — DSS proposes to systematically mature, mitigate risk for; and perform hardware-based ground validations / demonstrations of a low-cost, high technology payoff,...

  17. Validation of the Dutch language version of the Safety Attitudes Questionnaire (SAQ-NL).

    Science.gov (United States)

    Haerkens, Marck Htm; van Leeuwen, Wouter; Sexton, J Bryan; Pickkers, Peter; van der Hoeven, Johannes G

    2016-08-15

    As the first objective of caring for patients is to do no harm, patient safety is a priority in delivering clinical care. An essential component of safe care in a clinical department is its safety climate. Safety climate correlates with safety-specific behaviour, injury rates, and accidents. Safety climate in healthcare can be assessed by the Safety Attitudes Questionnaire (SAQ), which provides insight by scoring six dimensions: Teamwork Climate, Job Satisfaction, Safety Climate, Stress Recognition, Working Conditions and Perceptions of Management. The objective of this study was to assess the psychometric properties of the Dutch language version of the SAQ in a variety of clinical departments in Dutch hospitals. The Dutch version (SAQ-NL) of the SAQ was back translated, and analyzed for semantic characteristics and content. From October 2010 to November 2015 SAQ-NL surveys were carried out in 17 departments in two university and seven large non-university teaching hospitals in the Netherlands, prior to a Crew Resource Management human factors intervention. Statistical analyses were used to examine response patterns, mean scores, correlations, internal consistency reliability and model fit. Cronbach's α's and inter-item correlations were calculated to examine internal consistency reliability. One thousand three hundred fourteen completed questionnaires were returned from 2113 administered to health care workers, resulting in a response rate of 62 %. Confirmatory Factor Analysis revealed the 6-factor structure fit the data adequately. Response patterns were similar for professional positions, departments, physicians and nurses, and university and non-university teaching hospitals. The SAQ-NL showed strong internal consistency (α = .87). Exploratory analysis revealed differences in scores on the SAQ dimensions when comparing different professional positions, when comparing physicians to nurses and when comparing university to non-university hospitals. The SAQ

  18. Exploiting pluripotent stem cell technology for drug discovery, screening, safety, and toxicology assessments.

    Science.gov (United States)

    McGivern, Jered V; Ebert, Allison D

    2014-04-01

    In order for the pharmaceutical industry to maintain a constant flow of novel drugs and therapeutics into the clinic, compounds must be thoroughly validated for safety and efficacy in multiple biological and biochemical systems. Pluripotent stem cells, because of their ability to develop into any cell type in the body and recapitulate human disease, may be an important cellular system to add to the drug development repertoire. This review will discuss some of the benefits of using pluripotent stem cells for drug discovery and safety studies as well as some of the recent applications of stem cells in drug screening studies. We will also address some of the hurdles that need to be overcome in order to make stem cell-based approaches an efficient and effective tool in the quest to produce clinically successful drug compounds. Copyright © 2013 Elsevier B.V. All rights reserved.

  19. Linguistic Validation and Cultural Adaptation of Bulgarian Version of Hospital Survey on Patient Safety Culture (HSOPSC

    Directory of Open Access Journals (Sweden)

    Rumyana Stoyanova

    2018-05-01

    CONCLUSION: The study offers an analysis of the results of the linguistic validation of the B-HSOPSC and its test-retest reliability. The psychometric characteristics of the questions revealed good validity and reliability, except two questions. In the future, the instrument will be administered to the target population in the main study so that the psychometric properties of the instrument can be verified.

  20. Validation and Assessment of a Technology Familiarity Score in Patients Attending a Symptomatic Breast Clinic.

    Science.gov (United States)

    O'Brien, C; Kelly, J; Lehane, E A; Livingstone, V; Cotter, B; Butt, A; Kelly, L; Corrigan, M A

    2015-10-01

    New media technologies (computers, mobile phones and the internet) have the potential to transform the healthcare information needs of patients with breast disease (Ferlay et al. in Eur J Cancer 49:1374-1403, 2013). However, patients' current level of use and their willingness to accept new media for education and communication remain unknown. This was a single-centre clinic-based prospective cross-sectional study. A previously developed instrument was modified, validated and tested on patients attending a symptomatic breast clinic. The instrument was evaluated on 200 symptomatic breast patients. The commonest outlets for education were staff (95 %), leaflets (69 %) and websites (59 %). Websites are more likely to be consulted by younger patients (higher education were more likely to favour apps, websites and email (p technology use among breast patients is expanding as expected along generational trends. As such its' further integration into healthcare systems can potentially ameliorate patient education and communication.

  1. Cloud/Fog Computing System Architecture and Key Technologies for South-North Water Transfer Project Safety

    Directory of Open Access Journals (Sweden)

    Yaoling Fan

    2018-01-01

    Full Text Available In view of the real-time and distributed features of Internet of Things (IoT safety system in water conservancy engineering, this study proposed a new safety system architecture for water conservancy engineering based on cloud/fog computing and put forward a method of data reliability detection for the false alarm caused by false abnormal data from the bottom sensors. Designed for the South-North Water Transfer Project (SNWTP, the architecture integrated project safety, water quality safety, and human safety. Using IoT devices, fog computing layer was constructed between cloud server and safety detection devices in water conservancy projects. Technologies such as real-time sensing, intelligent processing, and information interconnection were developed. Therefore, accurate forecasting, accurate positioning, and efficient management were implemented as required by safety prevention of the SNWTP, and safety protection of water conservancy projects was effectively improved, and intelligential water conservancy engineering was developed.

  2. Study on safety classifications of software used in nuclear power plants and distinct applications of verification and validation activities in each class

    International Nuclear Information System (INIS)

    Kim, B. R.; Oh, S. H.; Hwang, H. S.; Kim, D. I.

    2000-01-01

    This paper describes the safety classification regarding instrumentation and control (I and C) systems and their software used in nuclear power plants, provides regulatory positions for software important to safety, and proposes verification and validation (V and V) activities applied differently in software classes which are important elements in ensuring software quality assurance. In other word, the I and C systems important to safety are classified into IC-1, IC-2, IC-3, and Non-IC and their software are classified into safety-critical, safety-related, and non-safety software. Based upon these safety classifications, the extent of software V and V activities in each class is differentiated each other. In addition, the paper presents that the software for use in I and C systems important to safety is divided into newly-developed and previously-developed software in terms of design and implementation, and provides the regulatory positions on each type of software

  3. The Theory of Planned Behavior (TPB) and Pre-Service Teachers' Technology Acceptance: A Validation Study Using Structural Equation Modeling

    Science.gov (United States)

    Teo, Timothy; Tan, Lynde

    2012-01-01

    This study applies the theory of planned behavior (TPB), a theory that is commonly used in commercial settings, to the educational context to explain pre-service teachers' technology acceptance. It is also interested in examining its validity when used for this purpose. It has found evidence that the TPB is a valid model to explain pre-service…

  4. AVIATION SAFETY CULTURE MEASUREMENT MODEL FIT VALIDATION OF A SURVEY FOR THE AVIATION MAINTENANCE REPAIR ORGANIZATIONS

    OpenAIRE

    Vahap ÖNEN

    2017-01-01

    It is believed that safety is the major issue for the aviation industry. According to Boeing Study %15 of the fatal accidents are incurred by maintenance sources related. On the other hand, from the last ten years safety management system which firstly introduced by ICAO became popular in the aviation industry. In the beginning, enforcement by ICAO Annex 19 then following it consequtively by EASA’s regulation, at the same time issued many advisory circulars by FAA that SMS entried in force an...

  5. Fuel pin transient behavior technology applied to safety analyses. Presentation to AEC Regulatory Staff 4th Regulatory Briefing on safety technology, Washington, D.C., November 19--20, 1974

    International Nuclear Information System (INIS)

    1974-11-01

    Information is presented concerning LMFBR fuel pin performance requirements and evaluation; fuels behavior codes with safety interfaces; performance evaluations; ex-reactor materials and simulation tests; models for fuel pin failure; and summary of continuing fuels technology tasks. (DCC)

  6. Study of fieldbus technology applied in a sterilization plant control and safety systems

    International Nuclear Information System (INIS)

    Karam Junior, Dib

    2000-01-01

    Several sterilization processes have been used in these years for treatment of countless products. Some processes use high temperatures, thermal shocks and chemical agents. With the discovery of the ionizing radiation and its posterior technological developments turned possible application of that process, in 1960, also in the the sterilization, denominated radiation sterilization. This process became also applied in another areas of health and industrial as food conservation, gemstones enhancement and others. The radiation sterilization requests an effective control and it needs a high level of safety. The commercial use of the computers applied in industrial automation provides and the domain of new technologies in this field provides new applications then new designs now is possible. The Fieldbus technology, a new digital communication protocol, like a Local Area Network, can be an alternative in the cobalt-60 irradiation plant. The present work suggests, evaluates, qualifies and quantifies this possibility. (author)

  7. 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.)

  8. Validating a measure to assess factors that affect assistive technology use by students with disabilities in elementary and secondary education.

    Science.gov (United States)

    Zapf, Susan A; Scherer, Marcia J; Baxter, Mary F; H Rintala, Diana

    2016-01-01

    The purpose of this study was to measure the predictive validity, internal consistency and clinical utility of the Matching Assistive Technology to Child & Augmentative Communication Evaluation Simplified (MATCH-ACES) assessment. Twenty-three assistive technology team evaluators assessed 35 children using the MATCH-ACES assessment. This quasi-experimental study examined the internal consistency, predictive validity and clinical utility of the MATCH-ACES assessment. The MATCH-ACES assessment predisposition scales had good internal consistency across all three scales. A significant relationship was found between (a) high student perseverance and need for assistive technology and (b) high teacher comfort and interest in technology use (p = (0).002). Study results indicate that the MATCH-ACES assessment has good internal consistency and validity. Predisposition characteristics of student and teacher combined can influence the level of assistive technology use; therefore, assistive technology teams should assess predisposition factors of the user when recommending assistive technology. Implications for Rehabilitation Educational and medical professionals should be educated on evidence-based assistive technology assessments. Personal experience and psychosocial factors can influence the outcome use of assistive technology. Assistive technology assessments must include an intervention plan for assistive technology service delivery to measure effective outcome use.

  9. Methodology and tools for independent verification and validation of computerized I and C systems important to safety

    International Nuclear Information System (INIS)

    Lindner, A.; Miedl, H.

    1998-01-01

    Modular software based I and C systems are state-of-the-art in industrial automation. For I and C systems important to safety in nuclear power plants, software based systems are also more and more applied. According to existing national and international guidelines and standards, the assessment of these systems calls for appropriate test methods and tools. By use of tools quality of the assessment process should be improved and expense should be limited. The paper outlines the structure of the independent verification and validation (V and V) process of the Teleperm XS system and the lessons learnt from this process. Furthermore, tools are discussed used for V and V of the Teleperm XS software. The recently developed tool VALIDATOR, dedicated to V and V of the plant specific I and C functions is described in more detail. We consider V and V of the basic software components and the system software to be required only once, but the C source codes of the plant specific functional diagrams have to be checked for each application separately. The VALIDATOR is designed to perform this task. It gives evidence of compliance of the automatically generated C source codes with the graphical design of the functional diagrams in reasonable time and with acceptable costs. The working method, performance and results of the VALIDATOR are shown by means of an actual example. (author)

  10. An update to inplace testing of safety/relief valves utilizing lift assist technology

    International Nuclear Information System (INIS)

    Heorman, K.R.

    1992-01-01

    Inplace testing of safety and relief valves with lift-assist devices has received mixed reviews from nuclear power plant testing personnel. While many plants use the technology, most limit its use to testing main steam safety valves (even though both OM-1-1981 and PTC 25.3-1976 allow its use for several different service applications). Test coordinator concerns regarding the technology range from lift set point accuracy and repeatability to the quality of the test result output. In addition, OM-1-1981 and PTC 25.3-1976 differ in their approach to the technology. The reasons for the differences between PTC 25.3-1976 and OM-1-1981 are discussed along with additional considerations applicable to the use of the technology in testing liquid service valves. This paper shows that lift assist technology is capable of determining lift set points within the accuracy requirements of OM-1 and PTC 25.3. It also demonstrates that the technology should not be limited to compressible service systems. Also, improvements in test repeatability and output quality are discussed as a function of the assist device design used and valve characteristics. Lift assist testing is often preferred over inplace testing that uses direct system pressure. It is often more cost efficient than bench testing because it does not require removal of critical systems from service and transportation of components. Also, duplicating system temperatures and other environmental factors is not an issue during inplace testing. Valve testing that once required an outage and maintenance period can now be conducted prior to such periods. This approach minimizes the possibility of failures becoming critical path limiting items

  11. The Validity of Warrantless Searches under the Occupational Safety and Health Act of 1970

    Science.gov (United States)

    Shanks, Michael D.

    1975-01-01

    One of the most controversial federal acts providing for random administrative searches is the Occupational Safety and Health Act of 1970 (OSHA). The author reviews the search and seizure law and concludes that abandonment of Fourth Amendment rights should not be predicated on the mere convenience of even a justifiable regulatory scheme. (JT)

  12. Application of Advanced Technology to Improve Plant Performance. Safety and Performance in Current NPPs

    International Nuclear Information System (INIS)

    Hashemian, H.M.

    2011-01-01

    Advances in computer technologies, signal processing, analytical modeling, and the advent of wireless sensors have provided the nuclear industry with ample means to automate and optimize maintenance activities and improve safety, efficiency, and availability, while reducing costs and radiation exposure to maintenance personnel. This paper provides a review of these developments and presents examples of their use in the nuclear power industry and the financial and safety benefits that they have produced. As the current generation of nuclear power plants have passed their mid-life, increased monitoring of their health is critical to their safe operation. This is especially true now that license renewal of nuclear power plants has accelerated, allowing some plants to operate up to 60 years or more. Furthermore, many utilities are maximizing their power output through uprating projects and retrofits. This puts additional demand and more stress on the plant equipment such as the instrumentation and control (I and C) systems and the reactor internal components making them more vulnerable to the effects of aging, degradation, and failure. In the meantime, the nuclear power industry is working to reduce generation costs by adopting condition-based maintenance strategies and automation of testing activities. These developments have stimulated great interest in on-line monitoring (OLM) technologies and new diagnostic and prognostic methods to anticipate, identify, and resolve equipment and process problems and ensure plant safety, efficiency, and immunity to accidents. The foundation for much of the required technologies has already been established through 40 years of research and development (R and D) efforts performed by numerous organizations, scientists, and engineers around the world including the author. This paper provides examples of these technologies and demonstrates how the gap between some of the more important R and D efforts and end users have been filled

  13. Enhanced operational safety of BWRs by advanced computer technology and human engineering

    International Nuclear Information System (INIS)

    Tomizawa, T.; Fukumoto, A.; Neda, T.; Toda, Y.; Takizawa, Y.

    1984-01-01

    In BWR nuclear power plants, where unit capacity is increasing and the demand for assured safety is growing, it has become important for the information interface between man and machine to work smoothly. Efforts to improve man-machine communication have been going on for the past ten years in Japan. Computer facilities and colour CRT display systems are amongst the most useful new methods. Advanced computer technology has been applied to operating plants and found to be very helpful for safe operation. A display monitoring system (DMS) is in operation in a 1100 MW(e) BWR plant. A total combination test was successfully completed on the 'plant operation by displayed information and automation' system (PODIA) in February 1983 before shipment to the site. The objective of this test was to verify the improved qualification of the newly developed advanced PODIA man-machine system by this enlarged fabrication test concept. In addition, the development of special graphics displays for the main control room and technical support centre to assist operators in assessing plant safety and diagnosing problems is required to meet post-TMI regulations. For this purpose, a prototype safety parameter display system (called Toshiba SPDS) with two colour CRT displays and a computer (TOSBAC-7/70) was developed in 1981 as an independent safety monitoring system. The PODIA and SPDS are now independent systems, but their combination has been found to be more useful and valuable for nuclear power plant safety. The paper discusses supervisory and operational concepts in the advanced main control room including SPDS, and describes the PODIA and SPDS verification tests including the valuable experience obtained after improvements in the qualification of these systems had been made to satisfactory operational safety levels. (author)

  14. Development and Validation of Protein Microarray Technology for Simultaneous Inflammatory Mediator Detection in Human Sera

    Directory of Open Access Journals (Sweden)

    Senthooran Selvarajah

    2014-01-01

    Full Text Available Biomarkers, including cytokines, can help in the diagnosis, prognosis, and prediction of treatment response across a wide range of disease settings. Consequently, the recent emergence of protein microarray technology, which is able to quantify a range of inflammatory mediators in a large number of samples simultaneously, has become highly desirable. However, the cost of commercial systems remains somewhat prohibitive. Here we show the development, validation, and implementation of an in-house microarray platform which enables the simultaneous quantitative analysis of multiple protein biomarkers. The accuracy and precision of the in-house microarray system were investigated according to the Food and Drug Administration (FDA guidelines for pharmacokinetic assay validation. The assay fell within these limits for all but the very low-abundant cytokines, such as interleukin- (IL- 10. Additionally, there were no significant differences between cytokine detection using our microarray system and the “gold standard” ELISA format. Crucially, future biomarker detection need not be limited to the 16 cytokines shown here but could be expanded as required. In conclusion, we detail a bespoke protein microarray system, utilizing well-validated ELISA reagents, that allows accurate, precise, and reproducible multiplexed biomarker quantification, comparable with commercial ELISA, and allowing customization beyond that of similar commercial microarrays.

  15. Using smartphone technology to deliver a virtual pedestrian environment: usability and validation.

    Science.gov (United States)

    Schwebel, David C; Severson, Joan; He, Yefei

    2017-09-01

    Various programs effectively teach children to cross streets more safely, but all are labor- and cost-intensive. Recent developments in mobile phone technology offer opportunity to deliver virtual reality pedestrian environments to mobile smartphone platforms. Such an environment may offer a cost- and labor-effective strategy to teach children to cross streets safely. This study evaluated usability, feasibility, and validity of a smartphone-based virtual pedestrian environment. A total of 68 adults completed 12 virtual crossings within each of two virtual pedestrian environments, one delivered by smartphone and the other a semi-immersive kiosk virtual environment. Participants completed self-report measures of perceived realism and simulator sickness experienced in each virtual environment, plus self-reported demographic and personality characteristics. All participants followed system instructions and used the smartphone-based virtual environment without difficulty. No significant simulator sickness was reported or observed. Users rated the smartphone virtual environment as highly realistic. Convergent validity was detected, with many aspects of pedestrian behavior in the smartphone-based virtual environment matching behavior in the kiosk virtual environment. Anticipated correlations between personality and kiosk virtual reality pedestrian behavior emerged for the smartphone-based system. A smartphone-based virtual environment can be usable and valid. Future research should develop and evaluate such a training system.

  16. Development and validation of a septoplasty training model using 3-dimensional printing technology.

    Science.gov (United States)

    AlReefi, Mahmoud A; Nguyen, Lily H P; Mongeau, Luc G; Haq, Bassam Ul; Boyanapalli, Siddharth; Hafeez, Nauman; Cegarra-Escolano, Francois; Tewfik, Marc A

    2017-04-01

    Providing alternative training modalities may improve trainees' ability to perform septoplasty. Three-dimensional printing has been shown to be a powerful tool in surgical training. The objectives of this study were to explain the development of our 3-dimensional (3D) printed septoplasty training model, to assess its face and content validity, and to present evidence supporting its ability to distinguish between levels of surgical proficiency. Imaging data of a patient with a nasal septal deviation was selected for printing. Printing materials reproducing the mechanical properties of human tissues were selected based on literature review and prototype testing. Eight expert rhinologists, 6 senior residents, and 6 junior residents performed endoscopic septoplasties on the model and completed a postsimulation survey. Performance metrics in quality (final product analysis), efficiency (time), and safety (eg, perforation length, nares damage) were recorded and analyzed in a study-blind manner. The model was judged to be anatomically correct and the steps performed realistic, with scores of 4.05 ± 0.82 and 4.2 ± 1, respectively, on a 5-point Likert scale. Ninety-two percent of residents desired the simulator to be integrated into their teaching curriculum. There was a significant difference (p simulator training models for septoplasty. Our model incorporates 2 different materials mixed into the 3 relevant consistencies necessary to simulate septoplasty. Our findings provide evidence supporting the validity of the model. © 2016 ARS-AAOA, LLC.

  17. Surveying wearable human assistive technology for life and safety critical applications: standards, challenges and opportunities.

    Science.gov (United States)

    Alam, Muhammad Mahtab; Ben Hamida, Elyes

    2014-05-23

    In this survey a new application paradigm life and safety for critical operations and missions using wearable Wireless Body Area Networks (WBANs) technology is introduced. This paradigm has a vast scope of applications, including disaster management, worker safety in harsh environments such as roadside and building workers, mobile health monitoring, ambient assisted living and many more. It is often the case that during the critical operations and the target conditions, the existing infrastructure is either absent, damaged or overcrowded. In this context, it is envisioned that WBANs will enable the quick deployment of ad-hoc/on-the-fly communication networks to help save many lives and ensuring people's safety. However, to understand the applications more deeply and their specific characteristics and requirements, this survey presents a comprehensive study on the applications scenarios, their context and specific requirements. It explores details of the key enabling standards, existing state-of-the-art research studies, and projects to understand their limitations before realizing aforementioned applications. Application-specific challenges and issues are discussed comprehensively from various perspectives and future research and development directions are highlighted as an inspiration for new innovative solutions. To conclude, this survey opens up a good opportunity for companies and research centers to investigate old but still new problems, in the realm of wearable technologies, which are increasingly evolving and getting more and more attention recently.

  18. Validation test of advanced technology for IPV nickel-hydrogen flight cells: Update

    Science.gov (United States)

    Smithrick, John J.; Hall, Stephen W.

    1992-01-01

    Individual pressure vessel (IPV) nickel-hydrogen technology was advanced at NASA Lewis and under Lewis contracts with the intention of improving cycle life and performance. One advancement was to use 26 percent potassium hydroxide (KOH) electrolyte to improve cycle life. Another advancement was to modify the state-of-the-art cell design to eliminate identified failure modes. The modified design is referred to as the advanced design. A breakthrough in the low-earth-orbit (LEO) cycle life of IPV nickel-hydrogen cells has been previously reported. The cycle life of boiler plate cells containing 26 percent KOH electrolyte was about 40,000 LEO cycles compared to 3,500 cycles for cells containing 31 percent KOH. The boiler plate test results are in the process of being validated using flight hardware and real time LEO testing at the Naval Weapons Support Center (NWSC), Crane, Indiana under a NASA Lewis Contract. An advanced 125 Ah IPV nickel-hydrogen cell was designed. The primary function of the advanced cell is to store and deliver energy for long-term, LEO spacecraft missions. The new features of this design are: (1) use of 26 percent rather than 31 percent KOH electrolyte; (2) use of a patented catalyzed wall wick; (3) use of serrated-edge separators to facilitate gaseous oxygen and hydrogen flow within the cell, while still maintaining physical contact with the wall wick for electrolyte management; and (4) use of a floating rather than a fixed stack (state-of-the-art) to accommodate nickel electrode expansion due to charge/discharge cycling. The significant improvements resulting from these innovations are: extended cycle life; enhanced thermal, electrolyte, and oxygen management; and accommodation of nickel electrode expansion. The advanced cell design is in the process of being validated using real time LEO cycle life testing of NWSC, Crane, Indiana. An update of validation test results confirming this technology is presented.

  19. Validation of the Leap Motion Controller using markered motion capture technology.

    Science.gov (United States)

    Smeragliuolo, Anna H; Hill, N Jeremy; Disla, Luis; Putrino, David

    2016-06-14

    The Leap Motion Controller (LMC) is a low-cost, markerless motion capture device that tracks hand, wrist and forearm position. Integration of this technology into healthcare applications has begun to occur rapidly, making validation of the LMC׳s data output an important research goal. Here, we perform a detailed evaluation of the kinematic data output from the LMC, and validate this output against gold-standard, markered motion capture technology. We instructed subjects to perform three clinically-relevant wrist (flexion/extension, radial/ulnar deviation) and forearm (pronation/supination) movements. The movements were simultaneously tracked using both the LMC and a marker-based motion capture system from Motion Analysis Corporation (MAC). Adjusting for known inconsistencies in the LMC sampling frequency, we compared simultaneously acquired LMC and MAC data by performing Pearson׳s correlation (r) and root mean square error (RMSE). Wrist flexion/extension and radial/ulnar deviation showed good overall agreement (r=0.95; RMSE=11.6°, and r=0.92; RMSE=12.4°, respectively) with the MAC system. However, when tracking forearm pronation/supination, there were serious inconsistencies in reported joint angles (r=0.79; RMSE=38.4°). Hand posture significantly influenced the quality of wrist deviation (P<0.005) and forearm supination/pronation (P<0.001), but not wrist flexion/extension (P=0.29). We conclude that the LMC is capable of providing data that are clinically meaningful for wrist flexion/extension, and perhaps wrist deviation. It cannot yet return clinically meaningful data for measuring forearm pronation/supination. Future studies should continue to validate the LMC as updated versions of their software are developed. Copyright © 2016 Elsevier Ltd. All rights reserved.

  20. Prediction of Safety Stock Using Fuzzy Time Series (FTS and Technology of Radio Frequency Identification (RFID for Stock Control at Vendor Managed Inventory (VMI

    Directory of Open Access Journals (Sweden)

    Mashuri Chamdan

    2018-01-01

    Full Text Available This research was conducted by prediction of safety stock using Fuzzy Time Series (FTS and technology of Radio Frequency Identification (RFID for stock control at Vendor Managed Inventory (VMI. Well-controlled stock influenced company revenue and minimized cost. It discussed about information system of safety stock prediction developed through programming language of PHP. Input data consisted of demand got from automatic, online and real time acquisition using technology of RFID, then, sent to server and stored at online database. Furthermore, data of acquisition result was predicted by using algorithm of FTS applying universe of discourse defining and fuzzy sets determination. Fuzzy set result was continued to division process of universe of discourse in order to be to final step. Prediction result was displayed at information system dashboard developed. By using 60 data from demand data, prediction score was 450.331 and safety stock was 135.535. Prediction result was done by error deviation validation using Mean Square Percent Error of 15%. It proved that FTS was good enough in predicting demand and safety stock for stock control. For deeper analysis, researchers used data of demand and universe of discourse U varying at FTS to get various result based on test data used.

  1. Prediction of Safety Stock Using Fuzzy Time Series (FTS) and Technology of Radio Frequency Identification (RFID) for Stock Control at Vendor Managed Inventory (VMI)

    Science.gov (United States)

    Mashuri, Chamdan; Suryono; Suseno, Jatmiko Endro

    2018-02-01

    This research was conducted by prediction of safety stock using Fuzzy Time Series (FTS) and technology of Radio Frequency Identification (RFID) for stock control at Vendor Managed Inventory (VMI). Well-controlled stock influenced company revenue and minimized cost. It discussed about information system of safety stock prediction developed through programming language of PHP. Input data consisted of demand got from automatic, online and real time acquisition using technology of RFID, then, sent to server and stored at online database. Furthermore, data of acquisition result was predicted by using algorithm of FTS applying universe of discourse defining and fuzzy sets determination. Fuzzy set result was continued to division process of universe of discourse in order to be to final step. Prediction result was displayed at information system dashboard developed. By using 60 data from demand data, prediction score was 450.331 and safety stock was 135.535. Prediction result was done by error deviation validation using Mean Square Percent Error of 15%. It proved that FTS was good enough in predicting demand and safety stock for stock control. For deeper analysis, researchers used data of demand and universe of discourse U varying at FTS to get various result based on test data used.

  2. Utah ITS/CVO business plan : using technology to maximize highway safety and improve government and industry productivity

    Science.gov (United States)

    1997-12-31

    This plan was produced to maximize highway safety and increase government and industry productivity through the application of Intelligent Transportation System/Commercial Vehicle Operations (ITS/CVO) technologies to support regulatory and enforcemen...

  3. Book of extended synopses. International symposium on advanced nuclear power systems. Design, technology, safety and strategies for their deployment

    International Nuclear Information System (INIS)

    1993-01-01

    During the symposium the design, technology, safety and strategy for the development of advanced nuclear power systems were discussed. 20 papers were presented at the symposium. A separate abstract was prepared for each of these papers. Refs

  4. Analysis of the impact of correlated benchmark experiments on the validation of codes for criticality safety analysis

    International Nuclear Information System (INIS)

    Bock, M.; Stuke, M.; Behler, M.

    2013-01-01

    The validation of a code for criticality safety analysis requires the recalculation of benchmark experiments. The selected benchmark experiments are chosen such that they have properties similar to the application case that has to be assessed. A common source of benchmark experiments is the 'International Handbook of Evaluated Criticality Safety Benchmark Experiments' (ICSBEP Handbook) compiled by the 'International Criticality Safety Benchmark Evaluation Project' (ICSBEP). In order to take full advantage of the information provided by the individual benchmark descriptions for the application case, the recommended procedure is to perform an uncertainty analysis. The latter is based on the uncertainties of experimental results included in most of the benchmark descriptions. They can be performed by means of the Monte Carlo sampling technique. The consideration of uncertainties is also being introduced in the supplementary sheet of DIN 25478 'Application of computer codes in the assessment of criticality safety'. However, for a correct treatment of uncertainties taking into account the individual uncertainties of the benchmark experiments is insufficient. In addition, correlations between benchmark experiments have to be handled correctly. For example, these correlations can arise due to different cases of a benchmark experiment sharing the same components like fuel pins or fissile solutions. Thus, manufacturing tolerances of these components (e.g. diameter of the fuel pellets) have to be considered in a consistent manner in all cases of the benchmark experiment. At the 2012 meeting of the Expert Group on 'Uncertainty Analysis for Criticality Safety Assessment' (UACSA) of the OECD/NEA a benchmark proposal was outlined that aimed for the determination of the impact on benchmark correlations on the estimation of the computational bias of the neutron multiplication factor (k eff ). The analysis presented here is based on this proposal. (orig.)

  5. Nuclear technology and reactor safety engineering. The situation ten years after the Chernobyl reactor accident

    International Nuclear Information System (INIS)

    Birkhofer, A.

    1996-01-01

    Ten years ago, on April 26, 1986 the most serious accident ever in the history of nuclear tgechnology worldwide happened in unit 4 of the nuclear power plant in Chernobyl in the Ukraine, this accident unveiling to the world at large that the Soviet reactor design lines are bearing unthought of safety engineering deficits. The dimensions of this reactor accident on site, and the radioactive fallout spreading far and wide to many countries in Europe, vividly nourished the concern of great parts of the population in the Western world about the safety of nuclear technology, and re-instigated debates about the risks involved and their justification. Now that ten years have elapsed since the accident, it is appropriate to strike a balance and analyse the situation today. The number of nuclear power plants operating worldwide has been growing in the last few years and this trend will continue, primarily due to developments in Asia. The Chernobyl reactor accident has pushed the international dimension of reactor safety to the foreground. Thus the Western world had reason enough to commit itself to enhancing the engineered safety of reactors in East Europe. The article analyses some of the major developments and activities to date and shows future perspectives. (orig.) [de

  6. Technology, safety and costs of decommissioning a Reference Boiling Water Reactor Power Station. Main report. Volume 1

    Energy Technology Data Exchange (ETDEWEB)

    Oak, H.D.; Holter, G.M.; Kennedy, W.E. Jr.; Konzek, G.J.

    1980-06-01

    Technology, safety and cost information is given for the conceptual decommissioning of a large (1100MWe) boiling water reactor (BWR) power station. Three approaches to decommissioning, immediate dismantlement, safe storage with deferred dismantlement and entombment, were studied to obtain comparisons between costs, occupational radiation doses, potential dose to the public and other safety impacts. It also shows the sensitivity of decommissioning safety and costs to the power rating of a BWR in the range of 200 to 1100 MWe.

  7. Whole blood pathogen reduction technology and blood safety in sub-Saharan Africa: A systematic review with regional discussion

    OpenAIRE

    Nkohkwo, Asa?ah; Agbor, Gabriel; Asongalem, Emmanuel; Tagny, Claude; Asonganyi, Tazoacha

    2016-01-01

    Background: Despite vast improvements in transfusion services in sub-Saharan Africa over the last decade, there remain serious concerns on the safety and adequacy of the blood supply across the region. Objective: This review paper ascertains the role of pathogen reduction technology (PRT) in improving blood safety and supply adequacy in the region. Method: The state of blood safety in sub-Saharan Africa was reviewed. Meetings, seminars and correspondence were undertaken with key clinic...

  8. Technology, safety and costs of decommissioning a reference small mixed oxide fuel fabrication plant. Volume 1. Main report

    Energy Technology Data Exchange (ETDEWEB)

    Jenkins, C. E.; Murphy, E. S.; Schneider, K J

    1979-01-01

    Detailed technology, safety and cost information are presented for the conceptual decommissioning of a reference small mixed oxide fuel fabrication plant. Alternate methods of decommissioning are described including immediate dismantlement, safe storage for a period of time followed by dismantlement and entombment. Safety analyses, both occupational and public, and cost evaluations were conducted for each mode.

  9. 47{sup th} Annual meeting on nuclear technology (AMNT 2016). Key topic / Enhanced safety and operation excellence

    Energy Technology Data Exchange (ETDEWEB)

    Traichel, Anke [NUKEM Technologies Engineering Services GmbH, Alzenau (Germany). Dept. of Safety Engineering and Assessment / Proposals Engineering

    2017-04-15

    Summary report on the Key Topic ''Enhanced Safety and Operation Excellence'' Technical Session ''Safety, IT, Hazards and PSA'' of the 47th Annual Meeting on Nuclear Technology (AMNT 2016) held in Hamburg, 10 to 12 May 2016.

  10. Practices and Exploration on Competition of Molecular Biological Detection Technology among Students in Food Quality and Safety Major

    Science.gov (United States)

    Chang, Yaning; Peng, Yuke; Li, Pengfei; Zhuang, Yingping

    2017-01-01

    With the increasing importance in the application of the molecular biological detection technology in the field of food safety, strengthening education in molecular biology experimental techniques is more necessary for the culture of the students in food quality and safety major. However, molecular biology experiments are not always in curricula…

  11. Impact of Recent Trends in Information and Communication Technology on the Validity of the Construct Information Literacy in Higher Education

    NARCIS (Netherlands)

    A.A.J. (Jos) van Helvoort

    2010-01-01

    The objective of this paper is a reflective discussion on the validity of the construct Information Literacy in the perspective of changing information and communication technologies. The research question that will be answered is: what is the impact of technological developments on the relevance of

  12. Development of the safety evaluation system in the respects of organizational factors and workers' consciousness. Pt. 1. Study of validities of functions for necessary evaluation and results obtained

    International Nuclear Information System (INIS)

    Takano, Kenichi; Tsuge, Tadafumi; Hasegawa, Naoko; Hirose, Ayako; Sasou, Kunihide

    2002-01-01

    CRIEPI decided to develop the safety evaluation system to investigate the safety level of the industrial sites due to questionnaires of organizational climate, safety managements, and workers' safety consciousness to workers. This report describes the questionnaire survey to apply to the domestic nuclear power plant for using obtained results as a fundamental data in order to construct the safety evaluation system. This system will be used for promoting safety culture in organizations of nuclear power plants. The questionnaire survey was conducted to 14 nuclear power stations for understanding the present status relating to safety issues. This questionnaire involves 122 items classified into following three categories: (1) safety awareness and behavior of plant personnel; (2) safety management; (3) organizational climate, based on the model considering contributing factor groups to safety culture. Obtained results were analyzed by statistical method to prepare functions of evaluation. Additionally, by applying a multivariate analysis, it was possible to extract several crucial factors influencing safety performance and to find a comprehensive safety indicator representing total organizational safety level. Significant relations were identified between accident rates (both labor accidents and facility failures) and above comprehensive safety indicator. Next, 122 questionnaire items were classified into 20 major safety factors to grasp the safety profiles of each site. This profile is considered as indicating the features of each site and also indicating the direction of progress for improvement of safety situation in the site. These findings can be reflected in developing the safety evaluation system, by confirming the validity of the evaluation method and giving specific functions. (author)

  13. Field studies of safety security rescue technologies through training and response activities

    Science.gov (United States)

    Murphy, Robin R.; Stover, Sam

    2006-05-01

    This paper describes the field-oriented philosophy of the Institute for Safety Security Rescue Technology (iSSRT) and summarizes the activities and lessons learned during calendar year 2005 of its two centers: the Center for Robot-Assisted Search and Rescue and the NSF Safety Security Rescue industry/university cooperative research center. In 2005, iSSRT participated in four responses (La Conchita, CA, Mudslides, Hurricane Dennis, Hurricane Katrina, Hurricane Wilma) and conducted three field experiments (NJTF-1, Camp Hurricane, Richmond, MO). The lessons learned covered mobility, operator control units, wireless communications, and general reliability. The work has collectively identified six emerging issues for future work. Based on these studies, a 10-hour, 1 continuing education unit credit course on rescue robotics has been created and is available. Rescue robots and sensors are available for loan upon request.

  14. Recognizing nurse stakeholder dissonance as a critical determinant of patient safety in new healthcare information technologies.

    Science.gov (United States)

    Samaras, Elizabeth A; Real, Sara D; Curtis, Amber M; Meunier, Tessa S

    2012-01-01

    Proper identification of all stakeholders and the comprehensive assessment of their evolving and often conflicting Needs, Wants, and Desires (NWDs) is a fundamental principle of human factors science and human-centered systems engineering; it is not yet a consistent element in development and deployment of new health information technologies (HIT). As the single largest group of healthcare professionals, nurses are critical stakeholders for these new technologies. Careful analysis can reveal nurse stakeholder dissonance (NSD) when integrating new technologies into the healthcare environment. Stakeholder dissonance is a term that describes the conflict between the NWDs of different stakeholders which, if left unresolved, can result in dissatisfaction, workarounds, errors, and threats to patient safety. Three case studies drawn from the authors' experience in a variety of acute-care settings where new HITs have been recently deployed are examined to illustrate the concept of NSD. Conflicting NWDs, other stakeholders, and possible root causes of the NSD are analyzed and mapped to threats to patient safety. Lessons learned, practical guidance for anticipating, identifying, and mitigating NSD, future research and implications for HFE and nursing practice are discussed.

  15. Molecular characterization, technological properties and safety aspects of enterococci from 'Hussuwa', an African fermented sorghum product.

    Science.gov (United States)

    Yousif, N M K; Dawyndt, P; Abriouel, H; Wijaya, A; Schillinger, U; Vancanneyt, M; Swings, J; Dirar, H A; Holzapfel, W H; Franz, C M A P

    2005-01-01

    To identify enterococci from Hussuwa, a Sudanese fermented sorghum product, and determine their technological properties and safety for possible inclusion in a starter culture preparation. Twenty-two Enterococcus isolates from Hussuwa were identified as Enterococcus faecium by using phenotypic and genotypic tests such as 16S rDNA gene sequencing, RAPD-PCR and restriction fragment length polymorphism of the 16S/23S intergenic spacer region fingerprinting. Genotyping revealed that strains were not clonally related and exhibited a considerable degree of genomic diversity. Some strains possessed useful technological properties such as production of bacteriocins and H2O2 or utilization of raffinose and stachyose. None produced alpha-amylase or tannase. A safety investigation revealed that all strains were susceptible to the antibiotics ampicillin, gentamicin, chloramphenicol, tetracycline and streptomycin, but some were resistant to ciprofloxacin, erythromycin, penicillin and vancomycin. Production of biogenic amines or presence of genes encoding virulence determinants occurred in some strains. Enterococcus faecium strains are associated with fermentation of Sudanese Hussuwa. Some strains exhibited useful technological properties such as production of antimicrobial agents and fermentation of indigestible sugars, which may aid in stabilizing and improving the digestibility of the product respectively. Enterococci were shown to play a role in the fermentation of African foods. While beneficial properties of these bacteria are indicated, their presence in this food may also imply a hygienic risk as a result of antimicrobial resistances or presence of virulence determinants.

  16. An example of the validation of DYNA3D for nuclear plant safety assessment

    International Nuclear Information System (INIS)

    Andress, J.C.; Neilson, A.J.

    1987-09-01

    Although the design of AGR on-load refuelling equipment is such that dropped fuel-assembly faults are virtually incredible in practice, consideration of the safety consequences of such events is necessary. A short programme of drop tests has been conducted by the CEGB to verify computer codes used in the safety assessment. The tests involved dropping solid steel billets onto typical steel standpipes. This paper presents a comparison of experimental results and pre-test DYNA3D predictions carried out at Winfrith, for an experiment in which a 3-d response of the standpipe was generated. The overall response, in terms of standpipe displacements and billet accelerations, was correctly predicted. However, local surface strains on the standpipe were overestimated in some regions as a result of minor inaccuracies in material properties and impact location. (author)

  17. Development and validation of the computer technology literacy self-assessment scale for Taiwanese elementary school students.

    Science.gov (United States)

    Chang, Chiung-Sui

    2008-01-01

    The purpose of this study was to describe the development and validation of an instrument to identify various dimensions of the computer technology literacy self-assessment scale (CTLS) for elementary school students. The instrument included five CTLS dimensions (subscales): the technology operation skills, the computer usages concepts, the attitudes toward computer technology, the learning with technology, and the Internet operation skills. Participants were 1,539 elementary school students in Taiwan. Data analysis indicated that the instrument developed in the study had satisfactory validity and reliability. Correlations analysis supported the legitimacy of using multiple dimensions in representing students' computer technology literacy. Significant differences were found between male and female students, and between grades on some CTLS dimensions. Suggestions are made for use of the instrument to examine complicated interplays between students' computer behaviors and their computer technology literacy.

  18. Developing and establishing the validity and reliability of the perceptions toward Aviation Safety Action Program (ASAP) and Line Operations Safety Audit (LOSA) questionnaires

    Science.gov (United States)

    Steckel, Richard J.

    Aviation Safety Action Program (ASAP) and Line Operations Safety Audits (LOSA) are voluntary safety reporting programs developed by the Federal Aviation Administration (FAA) to assist air carriers in discovering and fixing threats, errors and undesired aircraft states during normal flights that could result in a serious or fatal accident. These programs depend on voluntary participation of and reporting by air carrier pilots to be successful. The purpose of the study was to develop and validate a measurement scale to measure U.S. air carrier pilots' perceived benefits and/or barriers to participating in ASAP and LOSA programs. Data from these surveys could be used to make changes to or correct pilot misperceptions of these programs to improve participation and the flow of data. ASAP and LOSA a priori models were developed based on previous research in aviation and healthcare. Sixty thousand ASAP and LOSA paper surveys were sent to 60,000 current U.S. air carrier pilots selected at random from an FAA database of pilot certificates. Two thousand usable ASAP and 1,970 usable LOSA surveys were returned and analyzed using Confirmatory Factor Analysis. Analysis of the data using confirmatory actor analysis and model generation resulted in a five factor ASAP model (Ease of use, Value, Improve, Trust and Risk) and a five factor LOSA model (Value, Improve, Program Trust, Risk and Management Trust). ASAP and LOSA data were not normally distributed, so bootstrapping was used. While both final models exhibited acceptable fit with approximate fit indices, the exact fit hypothesis and the Bollen-Stine p value indicated possible model mis-specification for both ASAP and LOSA models.

  19. Preparation of safety regulatory requirements for new technology like digital system

    International Nuclear Information System (INIS)

    Ito, Juichiro; Takita, Masami

    2011-01-01

    The current regulatory requirements on digital instrumentation and control system have been reviewed by JNES, considering international trend discussed in DICWG (Digital Instrumentation and Control Working Group) of MDEP (Multinational Design Evaluation Program). MDEP DICWG held in OECD/NEA (Organisation for Economic Co-operation and Development/Nuclear Energy Agency) gives the opportunity to identify the convergence of applicable standards. The working group's activities include: identifying and prioritising the member countries' challenges, practices, and needs regarding standards and regulatory guidance regarding digital instrumentation and control; identifying areas of importance and needs for convergence of existing standards and guidance or development of new standards; sharing of information; and identifying common positions among the member countries for areas of particular importance and need. The DICWG drafted common positions on specific issues which are based on the existing standards, national regulatory guidance, best practices, and group inputs using an agreed upon process and framework. Five general common positions are under discussion in this fiscal year. Simplicity in Design, Software Common Cause Failures, Software Tools, Data communication, Verification and Validation throughout the life cycle of safety systems using digital computers. In addition, the technical evaluation of standards of the Japan Electric Association about digital system for safety was made to support NISA (Nuclear and Industrial Safety Agency). (author)

  20. Technological and safety properties display biodiversity among enterococci isolated from two Egyptian cheeses, "Ras" and "Domiati".

    Science.gov (United States)

    Malek, Reine; El-Attar, Aisha; Mohamed, Mariam; Anwar, Shimaa; El-Soda, Morsi; Béal, Catherine

    2012-02-15

    The technological and safety properties of 35 indigenous strains of Enterococcus faecium isolated from two Egyptian cheeses were characterised in order to determine their ability for rational manufacture of diversified and typical dairy products in the Middle East. A great diversity was observed within the 35 strains on the basis of their technological properties. A statistical analysis made it possible to distribute the 35 strains of E. faecium into different groups. Three groups were identified in terms of their acidification activity, measured by the Cinac system: a group of strains that quickly acidified milk, a second that moderately acidified milk, and a last cluster that revealed weak acidification activity. On the basis of texturing properties that were evaluated using a texturometer and a viscometer, a cluster of strains produced viscous and firm gels, a second cluster included fairly viscous, firm and cohesive gels, and a last group generated slightly viscous, but firm and very cohesive gels. By considering the aroma profiles that were determined by gas chromatography coupled with mass spectrometry, four clusters were identified. One cluster displayed a high dimethyl disulfide level, a second group of strains was highly aromatic, a third cluster led to typical "lactic" products, and the last cluster made it possible to obtain low aromatic products. None of the 35 strains proved to be β-haemolytic on the basis of the characterisation of their safety properties. The resistance to 20 antibiotics was assessed by the disc diffusion method. The 35 isolates were sensitive to 12 antibiotics, and among them, one isolate was resistant to only two antibiotics (nalixidic acid and streptomycin). The resistance to eight antibiotics was strain-dependant. Finally, this study demonstrates that some indigenous strains of E. faecium displayed interesting technological properties for cheese manufacture, together with good safety characteristics. They could be useful for the

  1. Cookstove options for safety and health: Comparative analysis of technological and usability attributes

    International Nuclear Information System (INIS)

    Kimemia, David; Van Niekerk, Ashley

    2017-01-01

    Energy use in low-income households in South Africa is considerably more hazardous than in middle to high-income households. Poverty is a key underlying factor. However, poor quality domestic energy technologies, including stoves, heaters and light sources contribute to this vulnerability. The problem is compounded by behavioural and environmental factors. Since cooking is a key energy-using chore, access to efficient, safe and versatile stoves portend safety improvements. This paper reports on a comparative analysis of eleven technological and usability attributes (CO emissions, firepower, efficiency, fuel toxicity, fuel cost, stove price, controllability, durability, availability, temperature of touchable-parts, and mechanical stability) of commercially available stoves that utilise four energy sources (kerosene, methanol, ethanol gel, and LPG). The ensuing discussion serves as a guide to enable the selection of the best-fit stove-fuel combination for low-income households. The findings indicate that LPG stoves have comparatively better overall rankings for cleanliness, firepower, safety, and durability. This analysis highlights that no combustion technology is risk-proof and there remains a burden on users to exercise diligence. We recommend that South Africa adopts an affirmative policy and strategic actions that discourage the use of kerosene as a household combustion fuel, and promotes the adoption of LPG as a safer and practical alternative. - Highlights: • Inefficient fuel combustion stoves raise risk profile in energy-poor households. • This study uses quantitative methods to compare the attributes of four stove types. • LPG stoves have comparatively better ranking for emissions, safety, and durability. • Transformative policies and strategies are required to promote safe, clean stoves.

  2. Development of safety analysis codes and experimental validation for a very high temperature gas-cooled reactor Final report

    International Nuclear Information System (INIS)

    Chang Oh

    2006-01-01

    The very high-temperature gas-cooled reactor (VHTR) is envisioned as a single- or dual-purpose reactor for electricity and hydrogen generation. The concept has average coolant temperatures above 900 C and operational fuel temperatures above 1250 C. The concept provides the potential for increased energy conversion efficiency and for high-temperature process heat application in addition to power generation. While all the High Temperature Gas Cooled Reactor (HTGR) concepts have sufficiently high temperature to support process heat applications, such as coal gasification, desalination or cogenerative processes, the VHTR's higher temperatures allow broader applications, including thermochemical hydrogen production. However, the very high temperatures of this reactor concept can be detrimental to safety if a loss-of-coolant accident (LOCA) occurs. Following the loss of coolant through the break and coolant depressurization, air will enter the core through the break by molecular diffusion and ultimately by natural convection, leading to oxidation of the in-core graphite structure and fuel. The oxidation will accelerate heatup of the reactor core and the release of toxic gases (CO and CO2) and fission products. Thus, without any effective countermeasures, a pipe break may lead to significant fuel damage and fission product release. Prior to the start of this Korean/United States collaboration, no computer codes were available that had been sufficiently developed and validated to reliably simulate a LOCA in the VHTR. Therefore, we have worked for the past three years on developing and validating advanced computational methods for simulating LOCAs in a VHTR. Research Objectives As described above, a pipe break may lead to significant fuel damage and fission product release in the VHTR. The objectives of this Korean/United States collaboration were to develop and validate advanced computational methods for VHTR safety analysis. The methods that have been developed are now

  3. Development of safety analysis codes and experimental validation for a very high temperature gas-cooled reactor Final report

    Energy Technology Data Exchange (ETDEWEB)

    Chang Oh

    2006-03-01

    The very high-temperature gas-cooled reactor (VHTR) is envisioned as a single- or dual-purpose reactor for electricity and hydrogen generation. The concept has average coolant temperatures above 9000C and operational fuel temperatures above 12500C. The concept provides the potential for increased energy conversion efficiency and for high-temperature process heat application in addition to power generation. While all the High Temperature Gas Cooled Reactor (HTGR) concepts have sufficiently high temperature to support process heat applications, such as coal gasification, desalination or cogenerative processes, the VHTR’s higher temperatures allow broader applications, including thermochemical hydrogen production. However, the very high temperatures of this reactor concept can be detrimental to safety if a loss-of-coolant accident (LOCA) occurs. Following the loss of coolant through the break and coolant depressurization, air will enter the core through the break by molecular diffusion and ultimately by natural convection, leading to oxidation of the in-core graphite structure and fuel. The oxidation will accelerate heatup of the reactor core and the release of toxic gasses (CO and CO2) and fission products. Thus, without any effective countermeasures, a pipe break may lead to significant fuel damage and fission product release. Prior to the start of this Korean/United States collaboration, no computer codes were available that had been sufficiently developed and validated to reliably simulate a LOCA in the VHTR. Therefore, we have worked for the past three years on developing and validating advanced computational methods for simulating LOCAs in a VHTR. Research Objectives As described above, a pipe break may lead to significant fuel damage and fission product release in the VHTR. The objectives of this Korean/United States collaboration were to develop and validate advanced computational methods for VHTR safety analysis. The methods that have been developed are now

  4. Development of Safety Analysis Codes and Experimental Validation for a Very High Temperature Gas-Cooled Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Chang, H. Oh, PhD; Cliff Davis; Richard Moore

    2004-11-01

    The very high temperature gas-cooled reactors (VHTGRs) are those concepts that have average coolant temperatures above 900 degrees C or operational fuel temperatures above 1250 degrees C. These concepts provide the potential for increased energy conversion efficiency and for high-temperature process heat application in addition to power generation and nuclear hydrogen generation. While all the High Temperature Gas Cooled Reactor (HTGR) concepts have sufficiently high temperatures to support process heat applications, such as desalination and cogeneration, the VHTGR's higher temperatures are suitable for particular applications such as thermochemical hydrogen production. However, the high temperature operation can be detrimental to safety following a loss-of-coolant accident (LOCA) initiated by pipe breaks caused by seismic or other events. Following the loss of coolant through the break and coolant depressurization, air from the containment will enter the core by molecular diffusion and ultimately by natural convection, leading to oxidation of the in-core graphite structures and fuel. The oxidation will release heat and accelerate the heatup of the reactor core. Thus, without any effective countermeasures, a pipe break may lead to significant fuel damage and fission product release. The Idaho National Engineering and Environmental Laboratory (INEEL) has investigated this event for the past three years for the HTGR. However, the computer codes used, and in fact none of the world's computer codes, have been sufficiently developed and validated to reliably predict this event. New code development, improvement of the existing codes, and experimental validation are imperative to narrow the uncertaninty in the predictions of this type of accident. The objectives of this Korean/United States collaboration are to develop advanced computational methods for VHTGR safety analysis codes and to validate these computer codes.

  5. Applications of ZigBee Technology in the Safety Monitoring System of Low Gas Pipeline Transportation

    Directory of Open Access Journals (Sweden)

    Wei Deyu

    2015-01-01

    Full Text Available The existing safety monitoring system of low gas pipeline transportation establishes a wired communication network monitoring system mainly on the basis of industrial bus. It has problems such as large transmission signal attenuation, complex wiring, high-labor intensity, inconvenient installation and maintenance, high maintenance cost, and so on. Featuring low cost, power-saving, reliability, stability and flexibility, the wireless sensor network established by ZigBee wireless communication technology can realize the real-time all-dimensional dynamic monitoring on parameters of low gas pipeline transportation system and overcome the shortcomings and deficiencies of wired network system.

  6. Technology Development, Evaluation, and Application (TDEA) FY 1999 Progress Report, Environment, Safety, and Health (ESH) Division

    Energy Technology Data Exchange (ETDEWEB)

    Larry G. Hoffman

    2000-12-01

    This progress report presents the results of 10 projects funded ($500K) in FY99 by the Technology Development, Evaluation, and Application (TDEA) Committee of the Environment, Safety, and Health Division. Five are new projects for this year; seven projects have been completed in their third and final TDEA-funded year. As a result of their TDEA-funded projects, investigators have published thirty-four papers in professional journals, proceedings, or Los Alamos reports and presented their work at professional meetings. Supplemental funds and in-kind contributions, such as staff time, instrument use, and work space, were also provided to TDEA-funded projects by organizations external to ESH Division.

  7. Technology Development, Evaluation, and Application (TDEA) FY 1999 Progress Report, Environment, Safety, and Health (ESH) Division

    International Nuclear Information System (INIS)

    Hoffman, Larry G.

    2000-01-01

    This progress report presents the results of 10 projects funded ($500K) in FY99 by the Technology Development, Evaluation, and Application (TDEA) Committee of the Environment, Safety, and Health Division. Five are new projects for this year; seven projects have been completed in their third and final TDEA-funded year. As a result of their TDEA-funded projects, investigators have published thirty-four papers in professional journals, proceedings, or Los Alamos reports and presented their work at professional meetings. Supplemental funds and in-kind contributions, such as staff time, instrument use, and work space, were also provided to TDEA-funded projects by organizations external to ESH Division

  8. Validation of detailed thermal hydraulic models used for LMR safety and for improvement of technical specifications

    Energy Technology Data Exchange (ETDEWEB)

    Dunn, F.E.

    1995-12-31

    Detailed steady-state and transient coolant temperatures and flow rates from an operating reactor have been used to validate the multiple pin model in the SASSYS-1 liquid metal reactor systems analysis code. This multiple pin capability can be used for explicit calculations of axial and lateral temperature distributions within individual subassemblies. Thermocouples at a number of axial locations and in a number of different coolant sub-channels m the XXO9 instrumented subassembly in the EBR-II reactor provided temperature data from the Shutdown Heat Removal Test (SHRT) series. Flow meter data for XXO9 and for the overall system are also available from these tests. Results of consistent SASSYS-1 multiple pin analyses for both the SHRT-45 loss-of-flow-without-scram-test and the S14RT-17 protected loss-of-flow test agree well with the experimental data, providing validation of the SASSYS-1 code over a wide range of conditions.

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

    International Nuclear Information System (INIS)

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

    2009-04-01

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

  10. Validation of programmable industrial automation systems for safety critical applications in NPP's dynamic testing

    International Nuclear Information System (INIS)

    Haapanen, P.; Korhonen, J.

    1995-01-01

    The safety assessment of programmable automation systems can not totally be based on conventional probabilistic methods because of the difficulties in quantification of the reliability of the software as well as the hardware. Additional means shall therefore be used to gain more confidence on the system dependability. One central confidence building measure is the independent dynamic testing of the completed system. An automated test harness is needed to run the required large amount of test cases in a restricted time span. The prototype dynamic testing harness for programmable digital systems developed at the Technical Research Centre of Finland (VTT) is described in the presentation. (12 refs., 2 figs., 2 tabs.)

  11. Validation of programmable industrial automation systems for safety critical applications in NPP's; dynamic testing

    International Nuclear Information System (INIS)

    Haapanen, P.; Korhonen, J.

    1995-01-01

    The safety assessment of programmable automation systems cannot be totally be based on conventional probabilistic methods because of the difficulties in quantification of the reliability of the software as well as the hardware. Additional means shall therefore be used to gain more confidence on the system dependability. One central confidence building measure is the independent dynamic testing of the completed system. An automated test harness is needed to run the required large amount of test cases in a restricted time span. This paper describes a prototype dynamic testing harness for programmable digital systems developed at VTT. (author). 12 refs, 2 figs, 2 tabs

  12. Discussion on runoff purification technology of highway bridge deck based on water quality safety

    Science.gov (United States)

    Tan, Sheng-guang; Liu, Xue-xin; Zou, Guo-ping; Xiong, Xin-zhu; Tao, Shuang-cheng

    2018-06-01

    Aiming at the actual problems existing, including a poor purification effect of highway bridge runoff collection and treatment system across sensitive water and necessary manual emergency operation, three kinds of technology, three pools system of bridge runoff purification, the integral pool of bridge runoff purification and ecological planting tank, are put forward by optimizing the structure of purification unit and system setting. At the same time, we come up with an emergency strategy for hazardous material leakage basing on automatic identification and remote control of traffic accidents. On the basis of combining these with the optimized pool structure, sensitive water safety can be guaranteed and water pollution, from directly discharging of bridge runoff, can be decreased. For making up for the shortages of green highway construction technology, the technique has important reference value.

  13. Radiation technology in finishing process improves health, safety and environment (HSE) in the furniture manufacturing industry

    International Nuclear Information System (INIS)

    Ahmad Shakri Mat Seman

    1999-01-01

    In furniture manufacturing, processes like cross cutting, molding, planning, shaping, turning, assembling and finishing are involved. The most significant types of negative impact of these processes are such as dust emission, noise, hazardous work, health risk, emission of organic solvent, toxic chemicals emission and chemical waste. In the finishing process, a number of negative effects that will cause health, safety and environmental (HSE) performance. This article highlights the environmental problems in the furniture finishing processes and how the radiation technology can reduce these negative impacts. The drawbacks that hamper the manufacturers from adopting this technology are also discussed. The objective of the paper is to create the awareness among the industrialist and consumers on the HSE hazardous in furniture finishing and steps can be taken to improve

  14. Identifying performance gaps in hydrogen safety sensor technology for automotive and stationary applications

    International Nuclear Information System (INIS)

    Boon-Brett, L.; Bousek, J.; Black, G.; Moretto, P.; Castello, P.; Huebert, T.; Banach, U.

    2010-01-01

    A market survey has been performed of commercially available hydrogen safety sensors, resulting in a total sample size of 53 sensors from 21 manufacturers. The technical specifications, as provided by the manufacturer, have been collated and are displayed herein as a function of sensor working principle. These specifications comprise measuring range, response and recovery times, ambient temperature, pressure and relative humidity, power consumption and lifetime. These are then compared against known performance targets for both automotive and stationary applications in order to establish in how far current technology satisfies current requirements of sensor end users. Gaps in the performance of hydrogen sensing technologies are thus identified and areas recommended for future research and development. (author)

  15. The use of a cubesat to validate technological bricks in space

    Science.gov (United States)

    Rakotonimbahy, E.; Vives, S.; Dohlen, K.; Savini, G.; Iafolla, V.

    2017-11-01

    In the framework of the FP7 program FISICA (Far Infrared Space Interferometer Critical Assessment), we are developing a cubesat platform which will be used for the validation in space of two technological bricks relevant for FIRI. The first brick is a high-precision accelerometer which could be used in a future space mission as fundamental element for the dynamic control loop of the interferometer. The second brick is a miniaturized version of an imaging multi-aperture telescope. Ultimately, such an instrument could be composed of numerous space-born mirror segments flying in precise formation on baselines of hundreds or thousands of meters, providing high-resolution glimpses of distant worlds. We are proposing to build a very first space-born demonstrator of such an instrument which will fit into the limited resources of one cubesat. In this paper, we will describe the detailed design of the cubesat hosting the two payloads.

  16. Polysomnographic validation of a wireless dry headband technology for sleep monitoring in healthy young adults.

    Science.gov (United States)

    Tonetti, Lorenzo; Cellini, Nicola; de Zambotti, Massimiliano; Fabbri, Marco; Martoni, Monica; Fábregas, Stephan E; Stegagno, Luciano; Natale, Vincenzo

    2013-06-13

    The present study aimed to explore the validity and reliability of a wireless dry headband technology for sleep monitoring (WS), through a comparison with concurrent polysomnographic (PSG) recording in healthy young adults. Eleven volunteers (7 females; mean age±SD: 24.75±3.62years) took part in the study, wearing the WS for two overnight PSG recordings in the sleep laboratory. The WS was compared to PSG in the identification of wake, light, deep and REM sleep. The WS sensitivity and specificity were 97.6% and 56.1%, respectively. The WS agreement with PSG, measured by Cohen's kappa, was 0.56 for light sleep, 0.70 for deep sleep, and 0.67 for REM sleep. The present results showed that the agreement ranged from moderate to high between PSG and the WS, while wakefulness detection was observed to be a limitation of the WS. Copyright © 2013 Elsevier Inc. All rights reserved.

  17. CERESVis: A QC Tool for CERES that Leverages Browser Technology for Data Validation

    Science.gov (United States)

    Chu, C.; Sun-Mack, S.; Heckert, E.; Chen, Y.; Doelling, D.

    2015-12-01

    In this poster, we are going to present three user interfaces that CERES team uses to validate pixel-level data. Besides our home grown tools, we will aslo present the browser technology that we use to provide interactive interfaces, such as jquery, HighCharts and Google Earth. We pass data to the users' browsers and use the browsers to do some simple computations. The three user interfaces are: Thumbnails -- it displays hundrends images to allow users to browse 24-hour data files in few seconds. Multiple-synchronized cursors -- it allows users to compare multiple images side by side. Bounding Boxes and Histograms -- it allows users to draw multiple bounding boxes on an image and the browser computes/display the histograms.

  18. Development and validation of science, technology, engineering and mathematics (STEM) based instructional material

    Science.gov (United States)

    Gustiani, Ineu; Widodo, Ari; Suwarma, Irma Rahma

    2017-05-01

    This study is intended to examine the development and validation of simple machines instructional material that developed based on Science, Technology, Engineering and Mathematics (STEM) framework that provides guidance to help students learn and practice for real life and enable individuals to use knowledge and skills they need to be an informed citizen. Sample of this study consist of one class of 8th grader at a junior secondary school in Bandung, Indonesia. To measure student learning, a pre-test and post-test were given before and after implementation of the STEM based instructional material. In addition, a questionnaire of readability was given to examine the clarity and difficulty level of each page of instructional material. A questionnaire of students' response towards instructional material given to students and teachers at the end of instructional material reading session to measure layout aspects, content aspects and utility aspects of instructional material for being used in the junior secondary school classroom setting. The results show that readability aspect and students' response towards STEM based instructional material of STEM based instructional material is categorized as very high. Pretest and posttest responses revealed that students retained significant amounts information upon completion of the STEM instructional material. Student overall learning gain is 0.67 which is categorized as moderate. In summary, STEM based instructional material that was developed is valid enough to be used as educational materials necessary for conducting effective STEM education.

  19. Multi-Evaporator Miniature Loop Heat Pipe for Small Spacecraft Thermal Control. Part 1; New Technologies and Validation Approach

    Science.gov (United States)

    Ku, Jentung; Ottenstein, Laura; Douglas, Donya; Hoang, Triem

    2010-01-01

    Under NASA s New Millennium Program Space Technology 8 (ST 8) Project, four experiments Thermal Loop, Dependable Microprocessor, SAILMAST, and UltraFlex - were conducted to advance the maturity of individual technologies from proof of concept to prototype demonstration in a relevant environment , i.e. from a technology readiness level (TRL) of 3 to a level of 6. This paper presents the new technologies and validation approach of the Thermal Loop experiment. The Thermal Loop is an advanced thermal control system consisting of a miniature loop heat pipe (MLHP) with multiple evaporators and multiple condensers designed for future small system applications requiring low mass, low power, and compactness. The MLHP retains all features of state-of-the-art loop heat pipes (LHPs) and offers additional advantages to enhance the functionality, performance, versatility, and reliability of the system. Details of the thermal loop concept, technical advances, benefits, objectives, level 1 requirements, and performance characteristics are described. Also included in the paper are descriptions of the test articles and mathematical modeling used for the technology validation. An MLHP breadboard was built and tested in the laboratory and thermal vacuum environments for TRL 4 and TRL 5 validations, and an MLHP proto-flight unit was built and tested in a thermal vacuum chamber for the TRL 6 validation. In addition, an analytical model was developed to simulate the steady state and transient behaviors of the MLHP during various validation tests. Capabilities and limitations of the analytical model are also addressed.

  20. Does applying technology throughout the medication use process improve patient safety with antineoplastics?

    Science.gov (United States)

    Bubalo, Joseph; Warden, Bruce A; Wiegel, Joshua J; Nishida, Tess; Handel, Evelyn; Svoboda, Leanne M; Nguyen, Lam; Edillo, P Neil

    2014-12-01

    antineoplastic population, benefit from many other technologies may have to be inferred based on data from other patient populations. As health systems begin to widely adopt and implement new technologies it is important to critically assess their effectiveness in improving patient safety. © The Author(s) 2013 Reprints and permissions: sagepub.co.uk/journalsPermissions.nav.

  1. Wireless Sensing Based on RFID and Capacitive Technologies for Safety in Marble Industry Process Control

    Directory of Open Access Journals (Sweden)

    Fabrizio Iacopetti

    2013-01-01

    Full Text Available This paper presents wireless sensing systems to increase safety and robustness in industrial process control, particularly in industrial machines for marble slab working. The process is performed by abrasive or cutting heads activated independently by the machine controller when the slab, transported on a conveyer belt, is under them. Current slab detection systems are based on electromechanical or optical devices at the machine entrance stage, suffering from deterioration and from the harsh environment. Slab displacement or break inside the machine due to the working stress may result in safety issues and damages to the conveyer belt due to incorrect driving of the working tools. The experimented contactless sensing techniques are based on four RFID and two capacitive sensing technologies and on customized hardware/software. The proposed solutions aim at overcoming some limitations of current state-of-the-art detection systems, allowing for reliable slab detection, outside and/or inside the machine, while maintaining low complexity and at the same time robustness to industrial harsh conditions. The proposed sensing devices may implement a wireless or wired sensor network feeding detection data to the machine controller. Data integrity check and process control algorithms have to be implemented for the safety and reliability of the overall industrial process.

  2. Implementing new technologies for public safety communication: competing frequency demands and standardization issues

    Science.gov (United States)

    Stevens, Kathryn J.

    1997-01-01

    Attempting to incorporate new technology into an existing environment is often very difficult. The problems are lengthy to resolve, wrought with confusion and seldom turn out like anyone expected. This document represents an overview of one such attempt. It outlines the general areas of concern which could be affected by a transition, and potential problems that may be encountered as a result of the effort. Over the past several decades, many local, state and federal agencies are pressing for more efficient use of frequency spectrums. The urgency of this issue has grown due to the demands of several groups wanting access to these channels for commercial use. Pager systems, cellular telephones, radio systems for private businesses all demand more space. Public safety agencies are starting to fear their needs will diminish in importance as the available channel spectrums are consumed by commercial ventures. How to share these channels, purchase appropriate equipment to meet your needs, and stay within a reasonable budget are not easy tasks. Public safety agencies who rely on communication networks in the performance of their jobs also know why encryption is important. Protecting the rights of citizens as police exchange information over the air, maintaining the integrity of an investigation and officer safety are all concerns police must address each time they use a radio.

  3. The deep geologic repository technology programme: toward a geoscience basis for understanding repository safety

    International Nuclear Information System (INIS)

    Jensen, M.R.

    2007-01-01

    Within the Deep Geologic Repository Technology Programme (DGRTP) several Geoscience activities are focused on advancing the understanding of groundwater flow system evolution and geochemical stability in a Canadian Shield setting as affected by long-term climate change. A key aspect is developing confidence in predictions of groundwater flow patterns and residence times as they relate to the safety of a deep geologic repository for used nuclear fuel waste. This is being achieved through a coordinated multi-disciplinary approach intent on: i) demonstrating coincidence between independent geo-scientific data; ii) improving the traceability of geo-scientific data and its interpretation within a conceptual descriptive model(s); iii) improving upon methods to assess and demonstrate robustness in flow domain prediction(s) given inherent flow domain uncertainties (i.e. spatial chemical/physical property distributions, boundary conditions) in time and space; and iv) improving awareness amongst geo-scientists as to the utility of various geo-scientific data in supporting a safety case for a deep geologic repository. This multi-disciplinary DGRTP approach is yielding an improved understanding of groundwater flow system evolution and stability in Canadian Shield settings that is further contributing to the geo-scientific basis for understanding and communicating aspects of DGR safety. (author)

  4. California Diploma Project Technical Report III: Validity Study--Validity Study of the Health Sciences and Medical Technology Standards

    Science.gov (United States)

    McGaughy, Charis; Bryck, Rick; de Gonzalez, Alicia

    2012-01-01

    This study is a validity study of the recently revised version of the Health Science Standards. The purpose of this study is to understand how the Health Science Standards relate to college and career readiness, as represented by survey ratings submitted by entry-level college instructors of health science courses and industry representatives. For…

  5. Progress report projects in the field of nuclear safety sponsered by the Federal Minister for Research and Technology

    International Nuclear Information System (INIS)

    1980-03-01

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

  6. Report on the projects in the field of reactor safety sponsored by the Federal Ministry for Research and Technology

    International Nuclear Information System (INIS)

    1978-12-01

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

  7. Construction Process Simulation and Safety Analysis Based on Building Information Model and 4D Technology

    Institute of Scientific and Technical Information of China (English)

    HU Zhenzhong; ZHANG Jianping; DENG Ziyin

    2008-01-01

    Time-dependent structure analysis theory has been proved to be more accurate and reliable com-pared to commonly used methods during construction. However, so far applications are limited to partial pe-riod and part of the structure because of immeasurable artificial intervention. Based on the building informa-tion model (BIM) and four-dimensional (4D) technology, this paper proposes an improves structure analysis method, which can generate structural geometry, resistance model, and loading conditions automatically by a close interlink of the schedule information, architectural model, and material properties. The method was applied to a safety analysis during a continuous and dynamic simulation of the entire construction process.The results show that the organic combination of the BIM, 4D technology, construction simulation, and safety analysis of time-dependent structures is feasible and practical. This research also lays a foundation for further researches on building lifecycle management by combining architectural design, structure analy-sis, and construction management.

  8. A review on lithium-ion power battery thermal management technologies and thermal safety

    Science.gov (United States)

    An, Zhoujian; Jia, Li; Ding, Yong; Dang, Chao; Li, Xuejiao

    2017-10-01

    Lithium-ion power battery has become one of the main power sources for electric vehicles and hybrid electric vehicles because of superior performance compared with other power sources. In order to ensure the safety and improve the performance, the maximum operating temperature and local temperature difference of batteries must be maintained in an appropriate range. The effect of temperature on the capacity fade and aging are simply investigated. The electrode structure, including electrode thickness, particle size and porosity, are analyzed. It is found that all of them have significant influences on the heat generation of battery. Details of various thermal management technologies, namely air based, phase change material based, heat pipe based and liquid based, are discussed and compared from the perspective of improving the external heat dissipation. The selection of different battery thermal management (BTM) technologies should be based on the cooling demand and applications, and liquid cooling is suggested being the most suitable method for large-scale battery pack charged/discharged at higher C-rate and in high-temperature environment. The thermal safety in the respect of propagation and suppression of thermal runaway is analyzed.

  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. The responsible for the radiological safety in the industry. Between the environment work and the technology

    International Nuclear Information System (INIS)

    Truppa, Walter Adrian

    2005-01-01

    Within the industrial applications of sealed radioactive sources, there are two clearly defined branches for which these materials are used: radioactive sources used in fixed and mobile equipment. These devices are used in a myriad of applications and each time with more technological advanced systems. This requires a permanent improvement on the training of the responsible, and introduces a mandatory exchange to other groups of intervention during the useful life of the device. Accident risks during the use of the equipment, although its rate of occurrence is low, are related to mistakes during operation, improper use, maintenance performed by staff without knowledge, human failures or oversights and incidents occurring during transport. All these risks are surrounded by different groups of factors that influence during the safe use of radioactive material within the installation. So, it is evidenced the importance of implementing aspects of the 'Safety Culture' and evaluations of suitability of the person responsible for radiation safety. In this paper we will refer to all the concepts that surround the election of the head of radioactive material, the factors involved during the operation, their training, the obligations of the installation, and responsible for environment and the technology

  11. Challenges in safety regulation of R and D activities for advanced technologies in DAE units

    International Nuclear Information System (INIS)

    Shukla, Dinesh Kumar

    2016-01-01

    DAE is engaged in intensive research and developmental activities, especially for advanced technologies such as accelerators, lasers, supercomputers, advanced materials and instrumentation. The starting point of an R and D project might be a hypothesis to be tested, problem to be solved, or the performance of an item to be improved, and there may be many possible solutions and technologies that could be used. R and D is quite different from designing, constructing, operating a plant. In these, precisely described result can be defined from the beginning and can be described in design specifications, process descriptions and procedures. However, while established procedures may be available to begin an R and D project, deviation from these procedures may occur often as a legitimate component of the conduct of R and D. Nevertheless, the R and D activities have to be performed in a manner which provides assurance that safety requirements are adequately addressed. Hence, the regulatory approach for enforcing the safety regulation in such facilities is also not as rigid as those for an operating industry. This paper is aimed to discuss some of the key challenges in regulating such R and D activities and also attempts to suggest a way forward. (author)

  12. Feasibility study and uncertainties in the validation of an existing safety-related control circuit with the ISO 13849-1:2006 design standard

    International Nuclear Information System (INIS)

    Jocelyn, Sabrina; Baudoin, James; Chinniah, Yuvin; Charpentier, Philippe

    2014-01-01

    In industry, machine users and people who modify or integrate equipment often have to evaluate the safety level of a safety-related control circuit that they have not necessarily designed. The modifications or integrations may involve work to make an existing machine that does not comply with normative or regulatory specifications safe. However, how can a circuit performing a safety function be validated a posteriori? Is the validation exercise feasible? What are the difficulties and limitations of such a procedure? The aim of this article is to answer these questions by presenting a validation study of a safety function of an existing machine. A plastic injection molding machine is used for this study, as well as standard ISO 13849-1:2006. Validation consists of performing an a posteriori (post-design) estimation of the performance level of the safety function. The procedure is studied for two contexts of use of the machine: in industry, and in laboratory. The calculations required by the ISO standard were done using Excel, followed by SIStema software. It is shown that, based on the context of use, the estimated performance level was different for the same safety-related circuit. The variability in the results is explained by the assumptions made by the person undertaking the validation without the involvement of the machine designer. - Highlights: • Validation of the performance level of a safety function is undertaken. • An injection molding machine and ISO 13849-1:2006 standard are used for the procedure. • The procedure is undertaken for two contexts of use of the machine. • In this study, the performance level depends on the context of use. • The assumptions made throughout the study partially explain this difference

  13. Design and implementation of safety traceability system for candied fruits based on two-dimension code technology

    Directory of Open Access Journals (Sweden)

    ZHAO Kun

    2014-12-01

    Full Text Available Traceability is the basic principle of food safety.A food safety traceability system based on QR code and cloud computing technology was introduced in this paper.First of all we introduced the QR code technology and the concept of traceability.And then through the field investigation,we analyzed the traceability process.At the same time,we designed the system and database were found,and the consumer experiencing technology is studied.Finally we expounded the traceability information collection,transmission and final presentation style and expected the future development of traceability system.

  14. Aircraft Loss-of-Control: Analysis and Requirements for Future Safety-Critical Systems and Their Validation

    Science.gov (United States)

    Belcastro, Christine M.

    2011-01-01

    Loss of control remains one of the largest contributors to fatal aircraft accidents worldwide. Aircraft loss-of-control accidents are complex, resulting from numerous causal and contributing factors acting alone or more often in combination. Hence, there is no single intervention strategy to prevent these accidents. This paper summarizes recent analysis results in identifying worst-case combinations of loss-of-control accident precursors and their time sequences, a holistic approach to preventing loss-of-control accidents in the future, and key requirements for validating the associated technologies.

  15. The safety R and D for GEN-IV reactors in the European nuclear energy technology platform strategic research agenda

    International Nuclear Information System (INIS)

    Bruna, G.

    2009-01-01

    In the fall 2007 EC launched the Sustainable Nuclear Energy Technology Platform (SNE-TP). The SNE-TP governing board set-up three working groups (WG): 1) Strategic Research Agenda (SRA) WG, in charge of drafting road-maps to support research, development and demonstration for current and future NPPs; 2) Deployment Strategy (DS) WG, in charge of defining the research road-map implementation and 3) Education, Training and Knowledge management (ETKM) WG, which was aimed at issuing proposal to reinforce European education and attract young in the nuclear field. The SRA WG was mandated to prepare the SRA vision document based on the preliminary road-map sketched in the document published by the Commission earlier in 2007. The SRA WG was originally organized in 5 sub-groups covering specific topics (1) GEN II and III, III+, including Advanced LWR, 2) Advanced Fuel Cycle for waste minimization and resource optimization; 3) GEN IV Fast Systems (SFR, LFR, GFR, ADS); 4) GEN IV (V) HTR and non-electricity-production applications; 5) New Nuclear Large Research Infrastructures) and 5 other sub-groups dealing with more generic cross-cutting research activities applicable to many specific topics, namely: 1) Structural material research; 2) modeling, simulation and methods, including physical data and tools and means for qualification and validation; 3) Reactor Safety, including severe accidents and human factor; 4) Advanced Driver and Minor Actinide Fuels: science and properties; 5) Pre-normative Research, Codes and Standards.The present paper is mainly aimed at summarizing the content of the SRA Safety sub-chapter focusing on GEN-IV aspects

  16. Human resource development program for nuclear safety and security in Tokyo Institute of Technology

    International Nuclear Information System (INIS)

    Han, Chi Young; Sagara, Hiroshi; Nagasaka, Hideo

    2014-01-01

    The Academy for Global Nuclear Safety and Security Agent was established at Tokyo Institute of Technology in 2011, to develop global nuclear human resources in the field of 3S (Safety, Security, and Safeguards) as a Program for Leading Graduate Schools supported by MEXT (Ministry of Education, Culture, Sports, Science and Technology). New courses of nuclear safety and security were developed in addition to the existing nuclear engineering program; 1) Environmental Dynamics of Radioactive Nuclides; Numerical simulation of the environmental dispersion of radioactive materials released from hypothetical nuclear accidents and evaluation of the public exposure are performed, by using a computer-based emergency response system, to have students predict the environmental dispersion of radionuclides and radiological consequence by nuclear accidents. 2) Measurement of Environmental Radiation; Students acquire hands-on experiences measuring environmental radiation contamination caused by the nuclear accident in Fukushima with multiple types of radiation detectors. Environmental samples are collected and analyzed for isotope identification and its spatial distribution. 3) Simulation of Severe Nuclear Accidents; The evaluation results of Fukushima accident progression are discussed as well as typical sever accidents that threaten the integrity of reactor vessel. Students simulate BWR (Boiling Water Cooled Reactor) transients, design basis accidents, and severe accidents by using simulators. 4) Nuclear Security Training; Design of physical protection systems, its fundamental physics, and regulatory frameworks are covered and students gain the practical experiences by use of intrusion detection systems at JAEA (Japan Atomic Energy Agency), and by numerical simulation of hydro-dynamics of structure material and nuclear material criticality at the university. (author)

  17. Aircraft Loss of Control: Problem Analysis for the Development and Validation of Technology Solutions

    Science.gov (United States)

    Belcastro, Christine M.; Newman, Richard L.; Crider, Dennis A.; Klyde, David H.; Foster, John V.; Groff, Loren

    2016-01-01

    Aircraft loss of control (LOC) is a leading cause of fatal accidents across all transport airplane and operational classes. LOC can result from a wide spectrum of precursors (or hazards), often occurring in combination. Technologies developed for LOC prevention and recovery must therefore be effective under a wide variety of conditions and uncertainties, including multiple hazards, and the validation process must provide a means of assessing system effectiveness and coverage of these hazards. This paper provides a detailed description of a methodology for analyzing LOC as a dynamics and control problem for the purpose of developing effective technology solutions. The paper includes a definition of LOC based on several recent publications, a detailed description of a refined LOC accident analysis process that is illustrated via selected example cases, and a description of planned follow-on activities for identifying future potential LOC risks and the development of LOC test scenarios. Some preliminary considerations for LOC of Unmanned Aircraft Systems (UAS) and for their safe integration into the National Airspace System (NAS) are also discussed.

  18. Light Water Reactor Sustainability Program Reactor Safety Technologies Pathway Technical Program Plan

    Energy Technology Data Exchange (ETDEWEB)

    Corradini, M. L. [Univ. of Wisconsin, Madison, WI (United States); Peko, D. [US Dept. of Energy, Washington, DC (United States); Farmer, M. [Argonne National Lab. (ANL), Argonne, IL (United States); Rempe, J. [Rempe and Associates LLC, Idaho Falls, ID (United States); Humrickhouse, P. [Idaho National Lab. (INL), Idaho Falls, ID (United States); O' Brien, J. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Robb, K. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Gauntt, R. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Osborn, D. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2016-06-01

    In the aftermath of the March 2011 multi-unit accident at the Fukushima Daiichi nuclear power plant (Fukushima), the nuclear community has been reassessing certain safety assumptions about nuclear reactor plant design, operations and emergency actions, particularly with respect to extreme events that might occur and that are beyond each plant’s current design basis. Because of our significant domestic investment in nuclear reactor technology (99 operating reactors in the fleet of commercial LWRs with five under construction), the United States has been a major leader internationally in these activities. The U.S. nuclear industry is voluntarily pursuing a number of additional safety initiatives. The NRC continues to evaluate and, where deemed appropriate, establish new requirements for ensuring adequate protection of public health and safety in the occurrence of low probability events at nuclear plants; (e.g., mitigation strategies for beyond design basis events initiated by external events like seismic or flooding initiators). The DOE has also played a major role in the U.S. response to the Fukushima accident. Initially, DOE worked with the Japanese and the international community to help develop a more complete understanding of the Fukushima accident progression and its consequences, and to respond to various safety concerns emerging from uncertainties about the nature of and the effects from the accident. DOE R&D activities are focused on providing scientific and technical insights, data, analyses methods that ultimately support industry efforts to enhance safety. These activities are expected to further enhance the safety performance of currently operating U.S. nuclear power plants as well as better characterize the safety performance of future U.S. plants. In pursuing this area of R&D, DOE recognizes that the commercial nuclear industry is ultimately responsible for the safe operation of licensed nuclear facilities. As such, industry is considered the primary

  19. Light Water Reactor Sustainability Program: Reactor Safety Technologies Pathway Technical Program Plan

    Energy Technology Data Exchange (ETDEWEB)

    Corradini, M. L. [Univ. of Wisconsin, Madison, WI (United States)

    2015-06-01

    In the aftermath of the March 2011 multi-unit accident at the Fukushima Daiichi nuclear power plant (Fukushima), the nuclear community has been reassessing certain safety assumptions about nuclear reactor plant design, operations and emergency actions, particularly with respect to extreme events that might occur and that are beyond each plant’s current design basis. Because of our significant domestic investment in nuclear reactor technology (99 operating reactors in the fleet of commercial LWRs with five under construction), the United States has been a major leader internationally in these activities. The U.S. nuclear industry is voluntarily pursuing a number of additional safety initiatives. The NRC continues to evaluate and, where deemed appropriate, establish new requirements for ensuring adequate protection of public health and safety in the occurrence of low probability events at nuclear plants; (e.g., mitigation strategies for beyond design basis events initiated by external events like seismic or flooding initiators). The DOE has also played a major role in the U.S. response to the Fukushima accident. Initially, DOE worked with the Japanese and the international community to help develop a more complete understanding of the Fukushima accident progression and its consequences, and to respond to various safety concerns emerging from uncertainties about the nature of and the effects from the accident. DOE R&D activities are focused on providing scientific and technical insights, data, analyses methods that ultimately support industry efforts to enhance safety. These activities are expected to further enhance the safety performance of currently operating U.S. nuclear power plants as well as better characterize the safety performance of future U.S. plants. In pursuing this area of R&D, DOE recognizes that the commercial nuclear industry is ultimately responsible for the safe operation of licensed nuclear facilities. As such, industry is considered the primary

  20. The role of CFD combustion modeling in hydrogen safety management-II: Validation based on homogeneous hydrogen-air experiments

    Energy Technology Data Exchange (ETDEWEB)

    Sathiah, Pratap, E-mail: sathiah@nrg.eu [Nuclear Research and Consultancy Group (NRG), Westerduinweg 3, 1755 ZG Petten (Netherlands); Haren, Steven van, E-mail: vanharen@nrg.eu [Nuclear Research and Consultancy Group (NRG), Westerduinweg 3, 1755 ZG Petten (Netherlands); Komen, Ed, E-mail: komen@nrg.eu [Nuclear Research and Consultancy Group (NRG), Westerduinweg 3, 1755 ZG Petten (Netherlands); Roekaerts, Dirk, E-mail: d.j.e.m.roekaerts@tudelft.nl [Department of Multi-Scale Physics, Delft University of Technology, P.O. Box 5, 2600 AA Delft (Netherlands)

    2012-11-15

    Highlights: Black-Right-Pointing-Pointer A CFD based method is proposed for the simulation of hydrogen deflagration. Black-Right-Pointing-Pointer A dynamic grid adaptation method is proposed to resolve turbulent flame brush thickness. Black-Right-Pointing-Pointer The predictions obtained using this method is in good agreement with the static grid method. Black-Right-Pointing-Pointer TFC model results are in good agreement with large-scale homogeneous hydrogen-air experiments. - Abstract: During a severe accident in a PWR, large quantities of hydrogen can be generated and released into the containment. The generated hydrogen, when mixed with air, can lead to hydrogen combustion. The dynamic pressure loads resulting from hydrogen combustion can be detrimental to the structural integrity of the reactor safety systems and the reactor containment. Therefore, accurate prediction of these pressure loads is an important safety issue. In a previous article, we presented a CFD based method to determine these pressure loads. This CFD method is based on the application of a turbulent flame speed closure combustion model. The validation analyses in our previous paper demonstrated that it is of utmost importance to apply successive mesh and time step refinement in order to get reliable results. In this article, we first determined to what extent the required computational effort required for our CFD approach can be reduced by the application of adaptive mesh refinement, while maintaining the accuracy requirements. Experiments performed within a small fan stirred explosion bomb were used for this purpose. It could be concluded that adaptive grid adaptation is a reliable and efficient method for usage in hydrogen deflagration analyses. For the two-dimensional validation analyses, the application of dynamic grid adaptation resulted in a reduction of the required computational effort by about one order of magnitude. In a second step, the considered CFD approach including adaptive

  1. The Westinghouse AP1000 plant design: a generation III+ reactor with unique proven passive safety technology

    International Nuclear Information System (INIS)

    Demetri, K. J.; Leipner, C. I.; Marshall, M. L.

    2015-09-01

    The AP1000 plant is an 1100-M We pressurized water reactor with passive safety features and extensive plant simplifications and standardization that simplify construction, operation, maintenance, safety, and cost. The AP1000 plant is based on proven pressurized water reactor (PWR) technology, with an emphasis on safety features that rely solely on natural forces. These passive safety features are combined with simple, active, defense-in-depth systems used during normal plant operations which also provide the first level of defense against more probable events. This paper focuses on specific safety and licensing topics: the AP1000 plant robustness to be prepared for extreme events that may lead to catastrophic loss of infrastructure, such as the Fukushima Dai-ichi event, and the AP1000 plant compliance with the safety objectives for new plants. The first deployment of the AP1000 plant formally began in July 2007 when Westinghouse Electric Company and its consortium partner, the Shaw Group, signed contracts for four AP1000 units on coastal sites of Sanmen and Haiyang, China. Both sites have the planned ability to accommodate at least six AP1000 units; construction is largely concurrent for all four units. Additionally, the United States (U.S.) Nuclear Regulatory Commission (NRC) issued combined licenses (COLs) to allow Southern Nuclear Operating Company (SNC) and South Carolina Electric and Gas Company (SCE and G) to construct and operate AP1000 plants. Within this paper, the various factors that contribute to an unparalleled level of design, construction, delivery, and licensing certainty for any new AP1000 plant projects are described. These include: 1) How the AP1000 plant design development and reviews undertaken in the United States, China and Europe increase licensing certainty. 2) How the AP1000 passive plant robustness against extreme events that result in large loss of infrastructure further contributes to the licensing certainty in a post

  2. The Westinghouse AP1000 plant design: a generation III+ reactor with unique proven passive safety technology

    Energy Technology Data Exchange (ETDEWEB)

    Demetri, K. J.; Leipner, C. I.; Marshall, M. L., E-mail: demetrkj@westinghouse.com [Westinghouse Electric Company, 1000 Westinghouse Drive, Cranberry Township, PA 16066 (United States)

    2015-09-15

    The AP1000 plant is an 1100-M We pressurized water reactor with passive safety features and extensive plant simplifications and standardization that simplify construction, operation, maintenance, safety, and cost. The AP1000 plant is based on proven pressurized water reactor (PWR) technology, with an emphasis on safety features that rely solely on natural forces. These passive safety features are combined with simple, active, defense-in-depth systems used during normal plant operations which also provide the first level of defense against more probable events. This paper focuses on specific safety and licensing topics: the AP1000 plant robustness to be prepared for extreme events that may lead to catastrophic loss of infrastructure, such as the Fukushima Dai-ichi event, and the AP1000 plant compliance with the safety objectives for new plants. The first deployment of the AP1000 plant formally began in July 2007 when Westinghouse Electric Company and its consortium partner, the Shaw Group, signed contracts for four AP1000 units on coastal sites of Sanmen and Haiyang, China. Both sites have the planned ability to accommodate at least six AP1000 units; construction is largely concurrent for all four units. Additionally, the United States (U.S.) Nuclear Regulatory Commission (NRC) issued combined licenses (COLs) to allow Southern Nuclear Operating Company (SNC) and South Carolina Electric and Gas Company (SCE and G) to construct and operate AP1000 plants. Within this paper, the various factors that contribute to an unparalleled level of design, construction, delivery, and licensing certainty for any new AP1000 plant projects are described. These include: 1) How the AP1000 plant design development and reviews undertaken in the United States, China and Europe increase licensing certainty. 2) How the AP1000 passive plant robustness against extreme events that result in large loss of infrastructure further contributes to the licensing certainty in a post

  3. Assessment of technologies for hazardous waste site remediation: Non-treatment technologies and pilot scale facility implementation -- excavation -- storage technology -- safety analysis and review statement. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Johnson, H.R.; Overbey, W.K. Jr.; Koperna, G.J. Jr.

    1994-02-01

    The purpose of this study is to assess the state-of-the-art of excavation technology as related to environmental remediation applications. A further purpose is to determine which of the excavation technologies reviewed could be used by the US Corp of Engineers in remediating contaminated soil to be excavated in the near future for construction of a new Lock and Dam at Winfield, WV. The study is designed to identify excavation methodologies and equipment which can be used at any environmental remediation site but more specifically at the Winfield site on the Kanawha River in Putnam County, West Virginia. A technical approach was determined whereby a functional analysis was prepared to determine the functions to be conducted during the excavation phase of the remediation operations. A number of excavation technologies were identified from the literature. A set of screening criteria was developed that would examine the utility and ranking of the technologies with respect to the operations that needed to be conducted at the Winfield site. These criteria were performance, reliability, implementability, environmental safety, public health, and legal and regulatory compliance. The Loose Bulk excavation technology was ranked as the best technology applicable to the Winfield site. The literature was also examined to determine the success of various methods of controlling fugitive dust. Depending upon any changes in the results of chemical analyses, or prior remediation of the VOCs from the vadose zone, consideration should be given to testing a new ``Pneumatic Excavator`` which removes the VOCs liberated during the excavation process as they outgas from the soil. This equipment however would not be needed on locations with low levels of VOC emissions.

  4. Assessment of technologies for hazardous waste site remediation: Non-treatment technologies and pilot scale facility implementation -- excavation -- storage technology -- safety analysis and review statement

    International Nuclear Information System (INIS)

    Johnson, H.R.; Overbey, W.K. Jr.; Koperna, G.J. Jr.

    1994-02-01

    The purpose of this study is to assess the state-of-the-art of excavation technology as related to environmental remediation applications. A further purpose is to determine which of the excavation technologies reviewed could be used by the US Corp of Engineers in remediating contaminated soil to be excavated in the near future for construction of a new Lock and Dam at Winfield, WV. The study is designed to identify excavation methodologies and equipment which can be used at any environmental remediation site but more specifically at the Winfield site on the Kanawha River in Putnam County, West Virginia. A technical approach was determined whereby a functional analysis was prepared to determine the functions to be conducted during the excavation phase of the remediation operations. A number of excavation technologies were identified from the literature. A set of screening criteria was developed that would examine the utility and ranking of the technologies with respect to the operations that needed to be conducted at the Winfield site. These criteria were performance, reliability, implementability, environmental safety, public health, and legal and regulatory compliance. The Loose Bulk excavation technology was ranked as the best technology applicable to the Winfield site. The literature was also examined to determine the success of various methods of controlling fugitive dust. Depending upon any changes in the results of chemical analyses, or prior remediation of the VOCs from the vadose zone, consideration should be given to testing a new ''Pneumatic Excavator'' which removes the VOCs liberated during the excavation process as they outgas from the soil. This equipment however would not be needed on locations with low levels of VOC emissions

  5. Analysis of Aviation Safety Reporting System Incident Data Associated with the Technical Challenges of the System-Wide Safety and Assurance Technologies Project

    Science.gov (United States)

    Withrow, Colleen A.; Reveley, Mary S.

    2015-01-01

    The Aviation Safety Program (AvSP) System-Wide Safety and Assurance Technologies (SSAT) Project asked the AvSP Systems and Portfolio Analysis Team to identify SSAT-related trends. SSAT had four technical challenges: advance safety assurance to enable deployment of NextGen systems; automated discovery of precursors to aviation safety incidents; increasing safety of human-automation interaction by incorporating human performance, and prognostic algorithm design for safety assurance. This report reviews incident data from the NASA Aviation Safety Reporting System (ASRS) for system-component-failure- or-malfunction- (SCFM-) related and human-factor-related incidents for commercial or cargo air carriers (Part 121), commuter airlines (Part 135), and general aviation (Part 91). The data was analyzed by Federal Aviation Regulations (FAR) part, phase of flight, SCFM category, human factor category, and a variety of anomalies and results. There were 38 894 SCFM-related incidents and 83 478 human-factorrelated incidents analyzed between January 1993 and April 2011.

  6. Development of a test rig and its application for validation and reliability testing of safety-critical software

    Energy Technology Data Exchange (ETDEWEB)

    Thai, N D; McDonald, A M [Atomic Energy of Canada Ltd., Mississauga, ON (Canada)

    1996-12-31

    This paper describes a versatile test rig developed by AECL for functional testing of safety-critical software used in the process trip computers of the Wolsong CANDU stations. The description covers the hardware and software aspects of the test rig, the test language and its interpreter, and other major testing software utilities such as the test oracle, sampler and profiler. The paper also discusses the application of the rig in the final stages of testing of the process trip computer software, namely validation and reliability tests. It shows how random test cases are generated, test scripts prepared and automatically run on the test rig. The versatility of the rig is further demonstrated in other types of testing such as sub-system tests, verification of the test oracle, testing of newly-developed test script, self-test and calibration. (author). 5 tabs., 10 figs.

  7. Development of a test rig and its application for validation and reliability testing of safety-critical software

    International Nuclear Information System (INIS)

    Thai, N.D.; McDonald, A.M.

    1995-01-01

    This paper describes a versatile test rig developed by AECL for functional testing of safety-critical software used in the process trip computers of the Wolsong CANDU stations. The description covers the hardware and software aspects of the test rig, the test language and its interpreter, and other major testing software utilities such as the test oracle, sampler and profiler. The paper also discusses the application of the rig in the final stages of testing of the process trip computer software, namely validation and reliability tests. It shows how random test cases are generated, test scripts prepared and automatically run on the test rig. The versatility of the rig is further demonstrated in other types of testing such as sub-system tests, verification of the test oracle, testing of newly-developed test script, self-test and calibration. (author). 5 tabs., 10 figs

  8. Development and Validation of Web-based Courseware for Junior Secondary School Basic Technology Students in Nigeria

    OpenAIRE

    Anunobi, Anunobi; Njedeka, Vivian; Gambari, Gambari; Isiaka, Amosa; Abdullahi, Abdullahi; Bashiru, Mohammed; Alabi, Alabi; Omotayo, Thomas

    2018-01-01

    This research aimed to develop and validate a web-based courseware for junior secondary school basic technology students in Nigeria. In this study, a mixed method quantitative pilot study design with qualitative components was used to test and ascertain the ease of development and validation of the web-based courseware. Dick and Carey instructional system design model was adopted for developing the courseware. Convenience sampling technique was used in selecting the three content, computer an...

  9. Development and Validation of Web-Based Courseware for Junior Secondary School Basic Technology Students in Nigeria

    OpenAIRE

    Amosa Isiaka Gambari

    2018-01-01

    This research aimed to develop and validate a web-based courseware for junior secondary school basic technology students in Nigeria. In this study, a mixed method quantitative pilot study design with qualitative components was used to test and ascertain the ease of development and validation of the web-based courseware. Dick and Carey instructional system design model was adopted for developing the courseware. Convenience sampling technique was used in selecting the three content, computer an...

  10. Computer Games as Virtual Environments for Safety-Critical Software Validation

    Directory of Open Access Journals (Sweden)

    Štefan Korečko

    2017-01-01

    Full Text Available Computer games became an inseparable part of everyday life in modern society and the time people spend playing them every day is increasing. This trend caused a noticeable research activity focused on utilizing the time spent playing in a meaningful way, for example to help solving scientific problems or tasks related to computer systems development. In this paper we present one contribution to this activity, a software system consisting of a modified version of the Open Rails train simulator and an application called TS2JavaConn, which allows to use separately developed software controllers with the simulator. The system is intended for validation of controllers developed by formal methods. The paper describes the overall architecture of the system and operation of its components. It also compares the system with other approaches to purposeful utilization of computer games, specifies suitable formal methods and illustrates its intended use on an example.

  11. How much software verification and validation is adequate for nuclear safety?

    International Nuclear Information System (INIS)

    Fujii, R.U.

    1994-01-01

    For over 26 years, software verification and validation (V ampersand V) has been applied to major DOD weapon systems, especially nuclear weapon systems, to ensure that the software is free of catastrophic software errors. Software V ampersand V is a systems engineering discipline that evaluates the software as part of the entire system including hardware, human operators, and other interfacing software. When applied from a systems perspective, software V ampersand V has been proven to be an effective technique for the early detection and correction of errors. Several V ampersand V cost/benefit case studies for the Rome Air Development Center have shown that the dollar savings of the early detection of errors clearly offset the cost of the software V ampersand V

  12. Safety, reliability, and validity of a physiologic definition of bronchopulmonary dysplasia.

    Science.gov (United States)

    Walsh, Michele C; Wilson-Costello, Deanna; Zadell, Arlene; Newman, Nancy; Fanaroff, Avroy

    2003-09-01

    Bronchopulmonary dysplasia (BPD) is the focus of many intervention trials, yet the outcome measure when based solely on oxygen administration may be confounded by differing criteria for oxygen administration between physicians. Thus, we wished to define BPD by a standardized oxygen saturation monitoring at 36 weeks corrected age, and compare this physiologic definition with the standard clinical definition of BPD based solely on oxygen administration. A total of 199 consecutive very low birthweight infants (VLBW, 501 to 1500 g birthweight) were assessed prospectively at 36+/-1 weeks corrected age. Neonates on positive pressure support or receiving >30% supplemental oxygen were assigned the outcome BPD. Those receiving or =88% for 60 minutes) or "BPD" (saturation reliability, test-retest reliability, and validity of the physiologic definition vs the clinical definition were assessed. A total of 199 VLBW were assessed, of whom 45 (36%) were diagnosed with BPD by the clinical definition of oxygen use at 36 weeks corrected age. The physiologic definition identified 15 infants treated with oxygen who successfully passed the saturation monitoring test in room air. The physiologic definition diagnosed BPD in 30 (24%) of the cohort. All infants were safely studied. The test was highly reliable (inter-rater reliability, kappa=1.0; test-retest reliability, kappa=0.83) and highly correlated with discharge home in oxygen, length of hospital stay, and hospital readmissions in the first year of life. The physiologic definition of BPD is safe, feasible, reliable, and valid and improves the precision of the diagnosis of BPD. This may be of benefit in future multicenter clinical trials.

  13. Preparation of safety regulatory requirements for new technology like digital system

    International Nuclear Information System (INIS)

    2012-01-01

    The current regulatory requirements on digital instrumentation and control system have been reviewed by JNES, considering international trend discussed in DICWG of MDEP. MDEP DICWG held in OECD/NEA gives the opportunity to identify the convergence of applicable standards. The working group's activities include: identifying and prioritising the member countries' challenges, practices, and needs regarding standards and regulatory guidance on digital instrumentation and control; identifying areas of importance and needs for convergence of existing standards and guidance or development of new standards; sharing of information; and identifying common positions among the member countries for areas of particular importance and need. The DICWG drafted common positions on specific issues which are based on the existing standards, national regulatory guidance, best practices, and group inputs using an agreed process and framework. The following two general common positions are discussed and to be issued in this fiscal year. Verification and Validation throughout the life cycle of safety systems using digital computers. The Impact of Cyber Security Features on Digital I and C Safety Systems. (author)

  14. CAMS prototype extension: Integration of data acquisition, signal validation, tracking simulator, predictive simulator, state identification, and probabilistic safety assessment

    International Nuclear Information System (INIS)

    Fantoni, Paolo; Iguchi, Yukihiro; Meyer, Geir; Soerensen, Aimar; Van Dyck, Claude

    1996-04-01

    CAMS (Computerized Accident Management Support) is a system that will provide assistance to the staff in the control room, in the technical support centre, and in a national safety centre. These three groups of users do not need the same type of support. Support is offered in identification of the plant state, in assessment of the future development of the accident, and in planning of accident mitigation strategies. Last year the predictive part of the system was tested at a safety exercise arranged by the Swedish Nuclear Inspectorate, and found to be a useful tool, with potential for further development. Now, new methods are added in signal validation, state identification, tracking simulation, predictive simulation, risk monitoring, and man-machine interface design. A prototype will be demonstrated at Loen in May 1996. This prototype is still under development. The purpose of this prototype is to test those methods in a simulated environment to verify that the developed functions, using different techniques, can work together producing the desired result in an efficient way. The plan is to test these techniques at power plants. During the CAMS design, a considerable effort has been given to maintain the generality of the CAMS concept; although the referenced process has been so far a BWR nuclear plant, the use of this structure and design can be applied to other processes, including non-nuclear processes. The research programme is carried out in close cooperation with member organizations (author)

  15. Validation of cross-contamination control in biological safety cabinet for biotech/pharmaceutical manufacturing process.

    Science.gov (United States)

    Hu, Shih-Cheng; Shiue, Angus; Tu, Jin-Xin; Liu, Han-Yang; Chiu, Rong-Ben

    2015-12-01

    For class II, type A2 biological safety cabinets (BSC), NSF/ANSI Standard 49 should be conformed in cabinet airflow velocity derivation, particle contamination, and aerodynamic flow properties. However, there exists a potential problem. It has been built that the cabinet air flow stabilize is influenced by the quantity of downflow of air and the height above the cabinet exhaust opening. Three air downflow quantities were compared as an operating apparatus was placed from 20 to 40 cm above the bench of the cabinet. The results show that the BSC air downflow velocity is a function of increased sampling height, displaying that containment is improvingly permitted over product protection as the sampling height decreases. This study investigated the concentration gradient of particles at various heights and downflow air quantity from the bench of the BSC. Experiment results indicate that performance near the bench was better than in the rest of the BSC. In terms of height, the best cleanliness was measured at a height of 10 cm over the bench; it reduced actually with add in height. The empirical curves accommodate, founded on the concentration gradient of particle created was elaborated for evaluating the particle concentration at different heights and downflow air quantity from the source of the bench of the BSC. The particle image velocimetry system applied for BSC airflow research to fix amount of airflow patterns and air distribution measurement and results of measurements show how obstructions can greatly influence the airflow and contaminant transportation in a BSC.

  16. Criticality safety validation: Simple geometry, single unit {sup 233}U systems

    Energy Technology Data Exchange (ETDEWEB)

    Putman, V.L.

    1997-06-01

    Typically used LMITCO criticality safety computational methods are evaluated for suitability when applied to INEEL {sup 233}U systems which reasonably can be modeled as simple-geometry, single-unit systems. Sixty-seven critical experiments of uranium highly enriched in {sup 233}U, including 57 aqueous solution, thermal-energy systems and 10 metal, fast-energy systems, were modeled. These experiments include 41 cylindrical and 26 spherical cores, and 41 reflected and 26 unreflected systems. No experiments were found for intermediate-neutron-energy ranges, or with interstitial non-hydrogenous materials typical of waste systems, mixed {sup 233}U and plutonium, or reflectors such as steel, lead, or concrete. No simple geometry experiments were found with cubic or annular cores, or approximating infinite sea systems. Calculations were performed with various tools and methodologies. Nine cross-section libraries, based on ENDF/B-IV, -V, or -VI.2, or on Hansen-Roach source data, were used with cross-section processing methods of MCNP or SCALE. The k{sub eff} calculations were performed with neutral-particle transport and Monte Carlo methods of criticality codes DANT, MCNP 4A, and KENO Va.

  17. Reports on the projects in the field of reactor safety sponsored by the Federal Ministry for Research and Technology

    International Nuclear Information System (INIS)

    1977-11-01

    Investigations on the safety of Light Water Reactors (LWR) being performed in the framework of the Research Program Reactor Safety (RS-projects) are sponsored by the BMFT (Federal Minister for Research and Technology), Bundesminister fuer Forschung und Technologie. Objective of this program is to investigate in greater detail the safety margins of nuclear energy plants and their systems and the further development of safety technology. The GRS (Reactor Safety Association), Gesellschaft fuer Reaktorsicherheit mbH, by order of BMFT, informs continuously of the status of these investigations within the series 'GRS-F-Fortschrittsberichte' (GRS-F-Progress Reports). Each progress report represents a compilation of individual reports about the different projects of the search program. The individual reports are prepared by the contractors themselves as a documentation of their progress in work and published by the GRS-FB (Research Coordination Department), Forschungsbetreuung at the GRS, within the framework of general information of the progress in reactor safety research. Each report describes the work performed, the results and the next steps of the work. The individual reports are attached to the classification system established by the CEC (Commission of the European Communities). The GRS-F-Progress Reports also include a list of the current investigations arranged according to the projects of the BMFT-Research Program Reactor Safety. This compilation, in addition to the LWR-investigations, also contains first contributions on the safety of advanced reactors. (orig.) [de

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

    International Nuclear Information System (INIS)

    1979-12-01

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

  19. Reports on research projects in the field of reactor safety sponsored by the Federal Ministry for research and technology

    International Nuclear Information System (INIS)

    1979-09-01

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

  20. Reports on the research projects in the field of nuclear safety sponsored by the Federal Ministry for Research and Technology

    International Nuclear Information System (INIS)

    1980-06-01

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