WorldWideScience

Sample records for safety advancement field

  1. Uranium Mill Tailings Remedial Action Project Safety Advancement Field Effort (SAFE) Program

    Energy Technology Data Exchange (ETDEWEB)

    1994-02-01

    In 1992, the Uranium Mill Tailings Remedial Action (UMTRA) Project experienced several health and safety related incidents at active remediation project sites. As a result, the U.S. Department of Energy (DOE) directed the Technical Assistance Contractor (TAC) to establish a program increasing the DOE`s overall presence at operational remediation sites to identify and minimize risks in operations to the fullest extent possible (Attachments A and B). In response, the TAC, in cooperation with the DOE and the Remedial Action Contractor (RAC), developed the Safety Advancement Field Effort (SAFE) Program.

  2. Uranium Mill Tailings Remedial Action Project Safety Advancement Field Effort (SAFE) Program

    International Nuclear Information System (INIS)

    1994-02-01

    In 1992, the Uranium Mill Tailings Remedial Action (UMTRA) Project experienced several health and safety related incidents at active remediation project sites. As a result, the U.S. Department of Energy (DOE) directed the Technical Assistance Contractor (TAC) to establish a program increasing the DOE's overall presence at operational remediation sites to identify and minimize risks in operations to the fullest extent possible (Attachments A and B). In response, the TAC, in cooperation with the DOE and the Remedial Action Contractor (RAC), developed the Safety Advancement Field Effort (SAFE) Program

  3. Advanced Messaging Concept Development Basic Safety Message

    Data.gov (United States)

    Department of Transportation — Contains all Basic Safety Messages (BSMs) collected during the Advanced Messaging Concept Development (AMCD) field testing program. For this project, all of the Part...

  4. Advanced fuels safety comparisons

    International Nuclear Information System (INIS)

    Grolmes, M.A.

    1977-01-01

    The safety considerations of advanced fuels are described relative to the present understanding of the safety of oxide fueled Liquid Metal Fast Breeder Reactors (LMFBR). Safety considerations important for the successful implementation of advanced fueled reactors must early on focus on the accident energetics issues of fuel coolant interactions and recriticality associated with core disruptive accidents. It is in these areas where the thermal physical property differences of the advanced fuel have the greatest significance

  5. Advancing sustainable safety : National Road Safety Outlook for 2005-2020.

    NARCIS (Netherlands)

    Wegman, F.C.M. & Aarts, L.T. (eds.)

    2006-01-01

    Advancing Sustainable Safety: National Road Safety Outlook for 2005-2020 is the follow-up to Naar een duurzaam veilig wegverkeer [Towards sustainably safe road traffic] (Koornstra et al., 1992). Advancing Sustainable Safety is a critique of Sustainable Safety. In this advanced version, adaptations

  6. Handbook of advanced nuclear hydrogen safety. 1st edition

    International Nuclear Information System (INIS)

    Hino, Ryutaro; Takegami, Hiroaki; Ogawa, Toru

    2017-03-01

    In the aftermath of the Fukushima nuclear accident, safety measures against hydrogen in severe accident has been recognized as a serious technical problem in Japan. Therefore, efforts have begun to form a common knowledge base between nuclear engineers and experts on combustion and explosion, and to secure and improve future nuclear energy safety. As one of such activities, we have prepared the 'Handbook of Advanced Nuclear Hydrogen Safety'. A handbook committee consisting of Japanese experts in the fields of nuclear and combustion-explosion in universities, nuclear companies, electric companies and research institutes was established in 2012. The objective and consents of the handbook were determined, and the outline of the contents was decided. The concepts of the handbook are as follows: to show advanced nuclear hydrogen safety technologies that nuclear engineers should understand, to show hydrogen safety points to make combustion-explosion experts cooperate with nuclear engineers, to expand information on water radiolysis considering the situation from just after the Fukushima accidents and to the waste management necessary for decommissioning after the accident etc. Many experts have participated to manuscript preparation, which was the first step of forming a hydrogen community across the boundaries of fields. The hydrogen community is expected to grow along with its improvement to the knowledge base on nuclear hydrogen safety. (author)

  7. Advances in Predictive Toxicology for Discovery Safety through High Content Screening.

    Science.gov (United States)

    Persson, Mikael; Hornberg, Jorrit J

    2016-12-19

    High content screening enables parallel acquisition of multiple molecular and cellular readouts. In particular the predictive toxicology field has progressed from the advances in high content screening, as more refined end points that report on cellular health can be studied in combination, at the single cell level, and in relatively high throughput. Here, we discuss how high content screening has become an essential tool for Discovery Safety, the discipline that integrates safety and toxicology in the drug discovery process to identify and mitigate safety concerns with the aim to design drug candidates with a superior safety profile. In addition to customized mechanistic assays to evaluate target safety, routine screening assays can be applied to identify risk factors for frequently occurring organ toxicities. We discuss the current state of high content screening assays for hepatotoxicity, cardiotoxicity, neurotoxicity, nephrotoxicity, and genotoxicity, including recent developments and current advances.

  8. Recent advances in systems safety and security

    CERN Document Server

    Stamatescu, Grigore

    2016-01-01

    This book represents a timely overview of advances in systems safety and security, based on selected, revised and extended contributions from the 2nd and 3rd editions of the International Workshop on Systems Safety and Security – IWSSS, held in 2014 and 2015, respectively, in Bucharest, Romania. It includes 14 chapters, co-authored by 34 researchers from 7 countries. The book provides an useful reference from both theoretical and applied perspectives in what concerns recent progress in this area of critical interest. Contributions, broadly grouped by core topic, address challenges related to information theoretic methods for assuring systems safety and security, cloud-based solutions, image processing approaches, distributed sensor networks and legal or risk analysis viewpoints. These are mostly accompanied by associated case studies providing additional practical value and underlying the broad relevance and impact of the field.

  9. Advanced nuclear reactor safety issues and research needs

    International Nuclear Information System (INIS)

    2002-01-01

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

  10. The Nordic safety programme in the nuclear field

    International Nuclear Information System (INIS)

    Wahlstroem, B.; Marcus, F.

    1987-01-01

    Safety of nuclear installations has been a concern of all the Nordic countries, although only Finland and Sweden have selected to build nuclear power plants. It was recognized early that the resources in a single country were limited and previous Nordic cooperation in the nuclear field was therefore followed up through a safety programme which started ten years ago. This research cooperation has been intensified during the years, and today more than 70 organizations in Denmark, Finland, Norway, and Sweden participate. The present programme is the third in a row and it will continue until 1989. Human factors and operational experience are touched upon in the RAS (safety philosophy) and the INF (advanced information technology) subprogrammes. The paper gives a brief overview of the Nordic safety programme in general and the RAS and INF subprogrammes. 11 refs. (author)

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

    International Nuclear Information System (INIS)

    2001-10-01

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

  12. Application of a structural model for advanced analysis in the evaluation of nuclear safety

    International Nuclear Information System (INIS)

    Landesmann, Alexandre; Barros, Francisco Claudio Pereira de; Batista, Eduardo de Miranda

    2003-01-01

    The Advanced Analysis concept, which means the direct consideration of both physical and geometric nonlinear effects in the analysis and design of steel buildings structures, represents the state-of-art in the field of structural analysis by this beginning of the 21 st century. In this context, the present paper presents an Advanced Analysis methodology applied to the Safety Evaluation of high hazardous civil structures. This Safety Evaluation plays an important part in the regulators position as a step in the licensing process performed by CNEN - Brazilian Nuclear Energy Commission. The proposed Advance Analysis procedure is implemented by a refined second-order plastic hinge model. The application of this model allows to carry out: the description of the inelastic structural behavior; the identification of the collapse mechanism; the ultimate load level; structural safety's level and the service ability limit. (author)

  13. Advanced Reactor Safety Program – Stakeholder Interaction and Feedback

    Energy Technology Data Exchange (ETDEWEB)

    Szilard, Ronaldo H. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Smith, Curtis L. [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2014-08-01

    In the Spring of 2013, the Idaho National Laboratory (INL) began discussions with industry stakeholders on how to upgrade our safety analysis capabilities. The focus of these improvements would primarily be on advanced safety analysis capabilities that could help the nuclear industry analyze, understand, and better predict complex safety problems. The current environment in the DOE complex is such that recent successes in high performance computer modeling and simulation could lead the nuclear industry to benefit from these advances, as long as an effort to translate these advances into realistic applications is made. Upgrading the nuclear industry modeling analysis capabilities is a significant effort that would require participation and coordination from all industry segments: research, engineering, vendors, and operations. We focus here on interactions with industry stakeholders to develop sound advanced safety analysis applications propositions that could have a positive impact on industry long term operation, hence advancing the state of nuclear safety.

  14. Issues affecting advanced passive light-water reactor safety analysis

    International Nuclear Information System (INIS)

    Beelman, R.J.; Fletcher, C.D.; Modro, S.M.

    1992-01-01

    Next generation commercial reactor designs emphasize enhanced safety through improved safety system reliability and performance by means of system simplification and reliance on immutable natural forces for system operation. Simulating the performance of these safety systems will be central to analytical safety evaluation of advanced passive reactor designs. Yet the characteristically small driving forces of these safety systems pose challenging computational problems to current thermal-hydraulic systems analysis codes. Additionally, the safety systems generally interact closely with one another, requiring accurate, integrated simulation of the nuclear steam supply system, engineered safeguards and containment. Furthermore, numerical safety analysis of these advanced passive reactor designs wig necessitate simulation of long-duration, slowly-developing transients compared with current reactor designs. The composite effects of small computational inaccuracies on induced system interactions and perturbations over long periods may well lead to predicted results which are significantly different than would otherwise be expected or might actually occur. Comparisons between the engineered safety features of competing US advanced light water reactor designs and analogous present day reactor designs are examined relative to the adequacy of existing thermal-hydraulic safety codes in predicting the mechanisms of passive safety. Areas where existing codes might require modification, extension or assessment relative to passive safety designs are identified. Conclusions concerning the applicability of these codes to advanced passive light water reactor safety analysis are presented

  15. Safety criteria for advanced HTGR concepts

    International Nuclear Information System (INIS)

    Kroeger, W.

    1989-01-01

    It is commonly agreed that advanced HTGR concepts must be licensable, which means that they must fulfil existing regulatory requirements. Furthermore, it is necessary to improve their public acceptance and they must even be suitable for urban sites. Therefore, they should be 'safer' than existing plants, which mainly means with respect to low-frequency or beyond-design severe accidents. Last but not least, the realization of advanced HTGR would be easier if commonly shared safety principles could be stated ensuring this further increased level of safety internationally. These qualitative statements need to be cast into quantitative guidelines which can be used as a rationale for safety evaluation. This paper tries to describe the status reached and to stimulate international activities. (author). 12 refs, 4 figs, 3 tabs

  16. Proceedings of the international topical meeting on advanced reactors safety: Volume 2

    International Nuclear Information System (INIS)

    1997-01-01

    In this volume, 89 papers are grouped under the following headings: advances in research/test reactor safety; advanced reactor accident management and emergency actions; advanced reactors instrumentation/controls/human factors; probabilistic risk/safety and reliability assessments; steam explosion research and issues; advanced reactor severe accident issues and research (analysis and assessments); advanced reactor thermal hydraulics; accelerator-driven source safety; liquid-metal reactor safety; structural assessments and issues; late papers

  17. Safety issues on advanced fuel

    International Nuclear Information System (INIS)

    Gross, H.; Krebs, W.D.

    1998-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-12-01

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

  19. Specification of advanced safety modeling requirements (Rev. 0).

    Energy Technology Data Exchange (ETDEWEB)

    Fanning, T. H.; Tautges, T. J.

    2008-06-30

    The U.S. Department of Energy's Global Nuclear Energy Partnership has lead to renewed interest in liquid-metal-cooled fast reactors for the purpose of closing the nuclear fuel cycle and making more efficient use of future repository capacity. However, the U.S. has not designed or constructed a fast reactor in nearly 30 years. Accurate, high-fidelity, whole-plant dynamics safety simulations will play a crucial role by providing confidence that component and system designs will satisfy established design limits and safety margins under a wide variety of operational, design basis, and beyond design basis transient conditions. Current modeling capabilities for fast reactor safety analyses have resulted from several hundred person-years of code development effort supported by experimental validation. The broad spectrum of mechanistic and phenomenological models that have been developed represent an enormous amount of institutional knowledge that needs to be maintained. Complicating this, the existing code architectures for safety modeling evolved from programming practices of the 1970s. This has lead to monolithic applications with interdependent data models which require significant knowledge of the complexities of the entire code in order for each component to be maintained. In order to develop an advanced fast reactor safety modeling capability, the limitations of the existing code architecture must be overcome while preserving the capabilities that already exist. To accomplish this, a set of advanced safety modeling requirements is defined, based on modern programming practices, that focuses on modular development within a flexible coupling framework. An approach for integrating the existing capabilities of the SAS4A/SASSYS-1 fast reactor safety analysis code into the SHARP framework is provided in order to preserve existing capabilities while providing a smooth transition to advanced modeling capabilities. In doing this, the advanced fast reactor safety models

  20. Specification of advanced safety modeling requirements (Rev. 0)

    International Nuclear Information System (INIS)

    Fanning, T. H.; Tautges, T. J.

    2008-01-01

    The U.S. Department of Energy's Global Nuclear Energy Partnership has lead to renewed interest in liquid-metal-cooled fast reactors for the purpose of closing the nuclear fuel cycle and making more efficient use of future repository capacity. However, the U.S. has not designed or constructed a fast reactor in nearly 30 years. Accurate, high-fidelity, whole-plant dynamics safety simulations will play a crucial role by providing confidence that component and system designs will satisfy established design limits and safety margins under a wide variety of operational, design basis, and beyond design basis transient conditions. Current modeling capabilities for fast reactor safety analyses have resulted from several hundred person-years of code development effort supported by experimental validation. The broad spectrum of mechanistic and phenomenological models that have been developed represent an enormous amount of institutional knowledge that needs to be maintained. Complicating this, the existing code architectures for safety modeling evolved from programming practices of the 1970s. This has lead to monolithic applications with interdependent data models which require significant knowledge of the complexities of the entire code in order for each component to be maintained. In order to develop an advanced fast reactor safety modeling capability, the limitations of the existing code architecture must be overcome while preserving the capabilities that already exist. To accomplish this, a set of advanced safety modeling requirements is defined, based on modern programming practices, that focuses on modular development within a flexible coupling framework. An approach for integrating the existing capabilities of the SAS4A/SASSYS-1 fast reactor safety analysis code into the SHARP framework is provided in order to preserve existing capabilities while providing a smooth transition to advanced modeling capabilities. In doing this, the advanced fast reactor safety models will

  1. Identification and characterization of passive safety system and inherent safety feature building blocks for advanced light-water reactors

    International Nuclear Information System (INIS)

    Forsberg, C.W.

    1989-01-01

    Oak Ridge National Laboratory (ORNL) is investigating passive and inherent safety options for Advanced Light-Water Reactors (ALWRs). A major activity in 1989 includes identification and characterization of passive safety system and inherent safety feature building blocks, both existing and proposed, for ALWRs. Preliminary results of this work are reported herein. This activity is part of a larger effort by the US Department of Energy, reactor vendors, utilities, and others in the United States to develop improved LWRs. The Advanced Boiling Water Reactor (ABWR) program and the Advanced Pressurized Water Reactor (APWR) program have as goals improved, commercially available LWRs in the early 1990s. The Advanced Simplified Boiling Water Reactor (ASBWR) program and the AP-600 program are developing more advanced reactors with increased use of passive safety systems. It is planned that these reactors will become commercially available in the mid 1990s. The ORNL program is an exploratory research program for LWRs beyond the year 2000. Desired long-term goals for such reactors include: (1) use of only passive and inherent safety, (2) foolproof against operator errors, (3) malevolence resistance against internal sabotage and external assault and (4) walkaway safety. The acronym ''PRIME'' [Passive safety, Resilient operation, Inherent safety, Malevolence resistance, and Extended (walkaway) safety] is used to summarize these desired characteristics. Existing passive and inherent safety options are discussed in this document

  2. On the safety performance of the advanced nuclear energy systems

    International Nuclear Information System (INIS)

    Li Shounan

    1999-01-01

    Some features on the safety performances of the Advanced Nuclear Energy Systems are discussed. The advantages and some peculiar problems on the safety of Advanced Nuclear Energy Systems with subcritical nuclear reactor driven by external neutron sources are also pointed out in comparison with conventional nuclear reactors

  3. Passive safety and the advanced liquid metal reactors

    International Nuclear Information System (INIS)

    Hill, D.J.; Pedersen, D.R.; Marchaterre, J.F.

    1988-01-01

    Advanced Liquid Metal Reactors being developed today in the USA are designed to make maximum use of passive safety features. Much of the LMR safety work at Argonne National Laboratory is concerned with demonstrating, both theoretically and experimentally, the effectiveness of the passive safety features. The characteristics that contribute to passive safety are discussed, with particular emphasis on decay heat removal systems, together with examples of Argonne's theoretical and experimental programs in this area

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

    International Nuclear Information System (INIS)

    Vare, Christophe

    2014-01-01

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

  5. A Quantitative Feasibility Study on Potential Safety Improvement Effects of Advanced Safety Features in APR-1400 when Applied to OPR-1000

    Energy Technology Data Exchange (ETDEWEB)

    Ualikhan Zhiyenbayev [KAIST, Daejeon (Korea, Republic of); Chung, Dae Wook [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

    2015-10-15

    This study aims to test the feasibility of the applications using Probabilistic Safety Assessment (PSA). Particularly, three of those advanced safety features are selected as follows: 1. Providing an additional Emergency Diesel Generator (EDG); 2. Increasing the capacity of Class 1E batteries; 3. Placing a Refueling Water Storage Tank (RWST) inside containment, i.e., change from RWST to IRWST. The Advanced Power Reactor 1400 (APR-1400) adopts several advanced safety features compared to its predecessor, the Optimized Power Reactor 1000 (OPR-1000), which includes an additional Emergency Diesel Generator, increase in battery capacity, in-containment refueling water storage tank (IRWST), and so on. Considering the remarkable advantages of these safety features in safety improvement and the design similarities between APR-1400 and OPR-1000, it is feasible to apply key advanced safety features of APR-1400 to OPR-1000 to enhance the safety. The selected safety features are incorporated into OPR-1000 PSA model using the Advanced Information Management System (AIMS) for PSA and CDFs are re-evaluated for each application and combination of three applications. Based on current results, it is concluded that three of key advanced safety features of APR-1400 can be effectively applied to OPR-1000, resulting in considerable safety improvement. In aggregate, three advanced safety features, which are an additional EDG, increased battery capacity and IRWST, can reduce the CDF of OPR-1000 by more than 15% when applied altogether.

  6. A Quantitative Feasibility Study on Potential Safety Improvement Effects of Advanced Safety Features in APR-1400 when Applied to OPR-1000

    International Nuclear Information System (INIS)

    Ualikhan Zhiyenbayev; Chung, Dae Wook

    2015-01-01

    This study aims to test the feasibility of the applications using Probabilistic Safety Assessment (PSA). Particularly, three of those advanced safety features are selected as follows: 1. Providing an additional Emergency Diesel Generator (EDG); 2. Increasing the capacity of Class 1E batteries; 3. Placing a Refueling Water Storage Tank (RWST) inside containment, i.e., change from RWST to IRWST. The Advanced Power Reactor 1400 (APR-1400) adopts several advanced safety features compared to its predecessor, the Optimized Power Reactor 1000 (OPR-1000), which includes an additional Emergency Diesel Generator, increase in battery capacity, in-containment refueling water storage tank (IRWST), and so on. Considering the remarkable advantages of these safety features in safety improvement and the design similarities between APR-1400 and OPR-1000, it is feasible to apply key advanced safety features of APR-1400 to OPR-1000 to enhance the safety. The selected safety features are incorporated into OPR-1000 PSA model using the Advanced Information Management System (AIMS) for PSA and CDFs are re-evaluated for each application and combination of three applications. Based on current results, it is concluded that three of key advanced safety features of APR-1400 can be effectively applied to OPR-1000, resulting in considerable safety improvement. In aggregate, three advanced safety features, which are an additional EDG, increased battery capacity and IRWST, can reduce the CDF of OPR-1000 by more than 15% when applied altogether

  7. Safety related terms for advanced nuclear plants

    International Nuclear Information System (INIS)

    1995-12-01

    The terms considered in this document are in widespread current use without a universal consensus as to their meaning. Other safety related terms are already defined in national or international codes and standards as well as in IAEA's Nuclear Safety Standards Series. Most of the terms in those codes and standards have been defined and used for regulatory purposes, generally for application to present reactor designs. There is no intention to duplicate the description of such regulatory terms here, but only to clarify the terms used for advanced nuclear plants. The following terms are described in this paper: Inherent safety characteristics, passive component, active component, passive systems, active system, fail-safe, grace period, foolproof, fault-/error-tolerant, simplified safety system, transparent safety

  8. Safety related terms for advanced nuclear plants

    International Nuclear Information System (INIS)

    1991-09-01

    The terms considered in this document are in widespread current use without a universal consensus as to their meaning. Other safety related terms are already defined in national or international codes and standards as well as in IAEA's Nuclear Safety Standards Series. Most of the terms in those codes and standards have been defined and used for regulatory purposes, generally for application to present reactor designs. There is no intention to duplicate the description of such regulatory terms here, but only to clarify the terms used for advanced nuclear plants. The following terms are described in this paper: Inherent safety characteristics, passive component, active component, passive systems, active system, fail-safe, grace period, foolproof, fault-/error-tolerant, simplified safety system, transparent safety

  9. Editorial: Advances in healthcare provider and patient training to improve the quality and safety of patient care

    Directory of Open Access Journals (Sweden)

    Elizabeth M. Borycki

    2015-09-01

    Full Text Available This special issue of the Knowledge Management & E-Learning: An International Journal is dedicated to describing “Advances in Healthcare Provider and Patient Training to Improve the Quality and Safety of Patient Care.” Patient safety is an important and fundamental requirement of ensuring the quality of patient care. Training and education has been identified as a key to improving healthcare provider patient safety competencies especially when working with new technologies such as electronic health records and mobile health applications. Such technologies can be harnessed to improve patient safety; however, if not used properly they can negatively impact on patient safety. In this issue we focus on advances in training that can improve patient safety and the optimal use of new technologies in healthcare. For example, use of clinical simulations and online computer based training can be employed both to facilitate learning about new clinical discoveries as well as to integrate technology into day to day healthcare practices. In this issue we are publishing papers that describe advances in healthcare provider and patient training to improve patient safety as it relates to the use of educational technologies, health information technology and on-line health resources. In addition, in the special issue we describe new approaches to training and patient safety including, online communities, clinical simulations, on-the-job training, computer based training and health information systems that educate about and support safer patient care in real-time (i.e. when health professionals are providing care to patients. These educational and technological initiatives can be aimed at health professionals (i.e. students and those who are currently working in the field. The outcomes of this work are significant as they lead to safer care for patients and their family members. The issue has both theoretical and applied papers that describe advances in patient

  10. ATLAS program for advanced thermal-hydraulic safety research

    International Nuclear Information System (INIS)

    Song, Chul-Hwa; Choi, Ki-Yong; Kang, Kyoung-Ho

    2015-01-01

    Highlights: • Major achievements of the ATLAS program are highlighted in conjunction with both developing advanced light water reactor technologies and enhancing the nuclear safety. • The ATLAS data was shown to be useful for the development and licensing of new reactors and safety analysis codes, and also for nuclear safety enhancement through domestic and international cooperative programs. • A future plan for the ATLAS testing is introduced, covering recently emerging safety issues and some generic thermal-hydraulic concerns. - Abstract: This paper highlights the major achievements of the ATLAS program, which is an integral effect test program for both developing advanced light water reactor technologies and contributing to enhancing nuclear safety. The ATLAS program is closely related with the development of the APR1400 and APR"+ reactors, and the SPACE code, which is a best-estimate system-scale code for a safety analysis of nuclear reactors. The multiple roles of ATLAS testing are emphasized in very close conjunction with the development, licensing, and commercial deployment of these reactors and their safety analysis codes. The role of ATLAS for nuclear safety enhancement is also introduced by taking some examples of its contributions to voluntarily lead to multi-body cooperative programs such as domestic and international standard problems. Finally, a future plan for the utilization of ATLAS testing is introduced, which aims at tackling recently emerging safety issues such as a prolonged station blackout accident and medium-size break LOCA, and some generic thermal-hydraulic concerns as to how to figure out multi-dimensional phenomena and the scaling issue.

  11. Physics and safety of advanced research reactors

    International Nuclear Information System (INIS)

    Boening, K.; Hardt, P. von der

    1987-01-01

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

  12. Westinghouse Advances in Passive Plant Safety

    International Nuclear Information System (INIS)

    Bruschi, H. J.; Manager, General; Gerstenhaber, E.

    1993-01-01

    On June 26, 1992, Westinghouse submitted the Ap600 Standard Safety Analysis Report and comprehensive PIRA results to the U. S. NRC for review as part of the Ap600 design certification program. This major milestone was met on time on a schedule set more than 3 years before submittal and is the result of the cooperative efforts of the U. S. Department of Energy (DOE), the Electric Power Requirements Program, and the Westinghouse Ap600 design team. These efforts were initiated in 1985 to develop a 600 MW advanced light water reactor plant design based on specific technical requirements established to provide the safety, simplicity, reliability, and economics necessary for the next generation of nuclear power plants. The Ap600 design achieves the ALRR safety requirements through ample design margins, simplified safety systems based on natural driving forces, and on a human-engineered man-machine interface system. Extensive Probabilistic Risk evolution, have recently shown that even if none of the active defense-in-depth safety systems are available, the passive systems alone meet safety goals. Furthermore, many tests in an extensive test program have begun or have been completed. Early tests show that passive safety perform well and meet design expectations

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

    International Nuclear Information System (INIS)

    Suzuki, Kazuhiko; Ishida, Michihiko

    2005-08-01

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

  14. Holistic safety analysis for advanced nuclear power plants

    International Nuclear Information System (INIS)

    Alvarenga, M.A.B.; Guimaraes, A.C.F.

    1992-01-01

    This paper reviews the basic methodology of safety analysis used in the ANGRA-I and ANGRA-II nuclear power plants, its weaknesses, the problems with public acceptance of the risks, the future of the nuclear energy in Brazil, as well as recommends a new methodology, HOLISTIC SAFETY ANALYSIS, to be used both in the design and licensing phases, for advanced reactors. (author)

  15. Advanced Sensors for Safety and Security

    CERN Document Server

    Khudaverdyan, Surik

    2013-01-01

    This book results from a NATO Advanced Research Workshop titled “Technological Innovations in CBRNE Sensing and Detection for Safety, Security, and Sustainability” held in Yerevan, Armenia in 2012. The objective was to discuss and exchange views as to how fusion of advanced technologies can lead to improved sensors/detectors in support of defense, security, and situational awareness. The chapters range from policy and implementation, advanced sensor platforms using stand-off (THz and optical) and point-contact methods for detection of chemical, nuclear, biological, nuclear and explosive agents and contaminants in water, to synthesis methods for several materials used for sensors.  In view of asymmetric, kinetic, and distributed nature of threat vectors, an emphasis is placed to examine new generation of sensors/detectors that utilize an ecosystems of innovation and advanced sciences convergence in support of effective counter-measures against  CBRNE threats. The book will be of considerable interest and...

  16. Progress in Methodologies for the Assessment of Passive Safety System Reliability in Advanced Reactors. Results from the Coordinated Research Project on Development of Advanced Methodologies for the Assessment of Passive Safety Systems Performance in Advanced Reactors

    International Nuclear Information System (INIS)

    2014-09-01

    Strong reliance on inherent and passive design features has become a hallmark of many advanced reactor designs, including several evolutionary designs and nearly all advanced small and medium sized reactor (SMR) designs. Advanced nuclear reactor designs incorporate several passive systems in addition to active ones — not only to enhance the operational safety of the reactors but also to eliminate the possibility of serious accidents. Accordingly, the assessment of the reliability of passive safety systems is a crucial issue to be resolved before their extensive use in future nuclear power plants. Several physical parameters affect the performance of a passive safety system, and their values at the time of operation are unknown a priori. The functions of passive systems are based on basic physical laws and thermodynamic principals, and they may not experience the same kind of failures as active systems. Hence, consistent efforts are required to qualify the reliability of passive systems. To support the development of advanced nuclear reactor designs with passive systems, investigations into their reliability using various methodologies are being conducted in several Member States with advanced reactor development programmes. These efforts include reliability methods for passive systems by the French Atomic Energy and Alternative Energies Commission, reliability evaluation of passive safety system by the University of Pisa, Italy, and assessment of passive system reliability by the Bhabha Atomic Research Centre, India. These different approaches seem to demonstrate a consensus on some aspects. However, the developers of the approaches have been unable to agree on the definition of reliability in a passive system. Based on these developments and in order to foster collaboration, the IAEA initiated the Coordinated Research Project (CRP) on Development of Advanced Methodologies for the Assessment of Passive Safety Systems Performance in Advanced Reactors in 2008. The

  17. Do provisions to advance chemical facility safety also advance chemical facility security? - An analysis of possible synergies

    OpenAIRE

    Hedlund, Frank Huess

    2012-01-01

    The European Commission has launched a study on the applicability of existing chemical industry safety provisions to enhancing security of chemical facilities covering the situation in 18 EU Member States. This paper reports some preliminary analytical findings regarding the extent to which existing provisions that have been put into existence to advance safety objectives due to synergy effects could be expected advance security objectives as well.The paper provides a conceptual definition of...

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

    International Nuclear Information System (INIS)

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

    2003-01-01

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

  19. Safety significance of ATR [Advanced Test Reactor] passive safety response attributes

    International Nuclear Information System (INIS)

    Atkinson, S.A.

    1989-01-01

    The Advanced Test Reactor (ATR) at the Idaho National Engineering Laboratory was designed with some passive safety response attributes which contribute to the safety posture of the facility. The three passive safety attributes being evaluated in the paper are: (1) In-core and in-vessel natural convection cooling, (2) a passive heat sink capability of the ATR primary coolant system (PCS) for the transfer of decay power from the uninsulated piping to the confinement, and (3) gravity feed of emergency coolant makeup. The safety significance of the ATR passive safety response attributes is that the reactor can passively respond for most transients, given a reactor scram, to provide adequate decay power removal and a significant time for operator action should the normal active heat removal systems and their backup systems both fail. The ATR Interim Level 1 Probabilistic Risk Assessment (PRA) model ands results were used to evaluate the significance to ATR fuel damage frequency (or probability) of the above three passive response attributes. The results of the evaluation indicate that the first attribute is a major safety characteristic of the ATR. The second attribute has a noticeable but only minor safety significance. The third attribute has no significant influence on the ATR Level 1 PRA because of the diversity and redundancy of the ATR firewater injection system (emergency coolant system). 8 refs., 4 figs., 1 tab

  20. Incorporation of advanced accident analysis methodology into safety analysis reports

    International Nuclear Information System (INIS)

    2003-05-01

    The IAEA Safety Guide on Safety Assessment and Verification defines that the aim of the safety analysis should be by means of appropriate analytical tools to establish and confirm the design basis for the items important to safety, and to ensure that the overall plant design is capable of meeting the prescribed and acceptable limits for radiation doses and releases for each plant condition category. Practical guidance on how to perform accident analyses of nuclear power plants (NPPs) is provided by the IAEA Safety Report on Accident Analysis for Nuclear Power Plants. The safety analyses are performed both in the form of deterministic and probabilistic analyses for NPPs. It is customary to refer to deterministic safety analyses as accident analyses. This report discusses the aspects of using the advanced accident analysis methods to carry out accident analyses in order to introduce them into the Safety Analysis Reports (SARs). In relation to the SAR, purposes of deterministic safety analysis can be further specified as (1) to demonstrate compliance with specific regulatory acceptance criteria; (2) to complement other analyses and evaluations in defining a complete set of design and operating requirements; (3) to identify and quantify limiting safety system set points and limiting conditions for operation to be used in the NPP limits and conditions; (4) to justify appropriateness of the technical solutions employed in the fulfillment of predetermined safety requirements. The essential parts of accident analyses are performed by applying sophisticated computer code packages, which have been specifically developed for this purpose. These code packages include mainly thermal-hydraulic system codes and reactor dynamics codes meant for the transient and accident analyses. There are also specific codes such as those for the containment thermal-hydraulics, for the radiological consequences and for severe accident analyses. In some cases, codes of a more general nature such

  1. Design and installation of advanced computer safety related instrumentation

    International Nuclear Information System (INIS)

    Koch, S.; Andolina, K.; Ruether, J.

    1993-01-01

    The rapidly developing area of computer systems creates new opportunities for commercial utilities operating nuclear reactors to improve plant operation and efficiency. Two of the main obstacles to utilizing the new technology in safety-related applications is the current policy of the licensing agencies and the fear of decision making managers to introduce new technologies. Once these obstacles are overcome, advanced diagnostic systems, CRT-based displays, and advanced communication channels can improve plant operation considerably. The article discusses outstanding issues in the area of designing, qualifying, and licensing of computer-based instrumentation and control systems. The authors describe the experience gained in designing three safety-related systems, that include a Programmable Logic Controller (PLC) based Safeguard Load Sequencer for NSP Prairie Island, a digital Containment Isolation monitoring system for TVA Browns Ferry, and a study that was conducted for EPRI/NSP regarding a PLC-based Reactor Protection system. This article presents the benefits to be gained in replacing existing, outdated equipment with new advanced instrumentation

  2. Performance and safety design of the advanced liquid metal reactor

    International Nuclear Information System (INIS)

    Berglund, R.C.; Magee, P.M.; Boardman, C.E.; Gyorey, G.L.

    1991-01-01

    The Advanced Liquid Metal Reactor (ALMR) program led by General Electric is developing, under U.S. Department of Energy sponsorship, a conceptual design for an advanced sodium-cooled liquid metal reactor plant. This design is intended to improve the already excellent level of plant safety achieved by the nuclear power industry while at the same time providing significant reductions in plant construction and operating costs. In this paper, the plant design and performance are reviewed, with emphasis on the ALMR's unique passive design safety features and its capability to utilize as fuel the actinides in LWR spent fuel

  3. The advanced neutron source facility: Safety philosophy and studies

    International Nuclear Information System (INIS)

    Greene, S.R.; Harrington, R.M.

    1988-01-01

    The Advanced Neutron Source (ANS) is currently the only new civilian nuclear reactor facility proposed for construction in the United States. Even though the thermal power of this research-oriented reactor is a relatively low 300 MW, the design will undoubtedly receive intense scrutiny before construction is allowed to proceed. Safety studies are already under way to ensure that the maximum degree of safety in incorporated into the design and that the design is acceptable to the Department of Energy (DOE) and can meet the Nuclear Regulatory Commission regulations. This document discusses these safety studies

  4. Advancement on safety management system of nuclear power for safety and non-anxiety of society

    International Nuclear Information System (INIS)

    Yoshikawa, Hidekazu

    2004-01-01

    Advancement on safety management system is investigated to improve safety and non-anxiety of society for nuclear power, from the standpoint of human machine system research. First, the recent progress of R and D works of human machine interface technologies since 1980 s are reviewed and then the necessity of introducing a new approach to promote technical risk communication activity to foster safety culture in nuclear industries. Finally, a new concept of Offsite Operation and Maintenance Support Center (OMSC) is proposed as the core facility to assemble human resources and their expertise in all organizations of nuclear power, for enhancing safety and non-anxiety of society for nuclear power. (author)

  5. Pressure Safety: Advanced Self-Study 30120

    Energy Technology Data Exchange (ETDEWEB)

    Glass, George [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2016-02-29

    Pressure Safety Advance Self-Study (Course 30120) consists of an introduction, five modules, and a quiz. To receive credit in UTrain for completing this course, you must score 80% or better on the 15-question quiz (check UTrain). Directions for initiating the quiz are appended to the end of this training manual. This course contains several links to LANL websites. UTrain might not support active links, so please copy links into the address line in your browser.

  6. The Advanced Light Source (ALS) Radiation Safety System

    International Nuclear Information System (INIS)

    Ritchie, A.; Oldfather, D.; Lindner, A.

    1993-05-01

    The Advanced Light Source (ALS) at the Lawrence Berkeley Laboratory (LBL) is a 1.5 GeV synchrotron light source facility consisting of a 120 keV electron gun, 50 MeV linear accelerator, 1.5 Gev booster synchrotron, 200 meter circumference electron storage ring, and many photon beamline transport systems for research. The Radiation Safety System for the ALS has been designed and built with a primary goal of providing protection against inadvertent personnel exposure to gamma and neutron radiation and, secondarily, to enhance the electrical safety of select magnet power supplies

  7. Improved safety in advanced control complexes, without side effects

    International Nuclear Information System (INIS)

    Harmon, D.L.

    1997-01-01

    If we only look for a moment at the world around us, it is obvious that advances in digital electronic equipment and Human-System Interface (HSI) technology are occurring at a phenomenal pace. This is evidenced from our home entertainment systems to the dashboard and computer-based operation of our new cars. Though the nuclear industry has less vigorously embraced these advances, their application is being implemented through individual upgrades to current generation nuclear plants and as plant-wide control complexes for advanced plants. In both venues modem technology possesses widely touted advantages for improving plant availability as well as safety. The well-documented safety benefits of digital Instrumentation and Controls (I ampersand C) include higher reliability resulting from redundancy and fault tolerance, inherent self-test and self-diagnostic capabilities which have replaced error-prone human tasks, resistance to setpoint drift increasing available operating margins, and the ability to run complex, real-time, computer-based algorithms directly supporting an operator's monitoring and control task requirements. 22 refs., 3 figs., 5 tabs

  8. Safety aspects in high-field magnetic resonance imaging

    International Nuclear Information System (INIS)

    Muehlenweg, M.; Trattnig, S.; Schaefers, G.

    2008-01-01

    With more and more 3 Tesla high-field magnetic resonance (MR) scanners entering clinical routine, the safety notion in MR imaging has also reached a new dimension. The first part of this paper deals with the three most important sources of physical interaction (static magnetic field, gradient and HF fields). The paper discusses the differences compared with the traditional clinical 1.5 T standard scanners, the impact on human beings, the interactions with metallic objects and the relevant safety standards. The second part of the paper examines the issue of MR safety as seen in clinical practice and tries to demonstrate optimization potentials. This includes structural optimization in information distribution and hospital organization as well as test standards and labeling guidelines. (orig.) [de

  9. Advanced research workshop: nuclear materials safety

    International Nuclear Information System (INIS)

    Jardine, L J; Moshkov, M M.

    1999-01-01

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

  10. R and D perspectives on the advanced nuclear safety regulation system

    International Nuclear Information System (INIS)

    Lee, Chang Ju; Ahn, Sang Kyu; Park, Jong Seuk; Chung, Dae Wook; Han, Sang Hoon; Lee, Jung Won

    2009-01-01

    As current licensing process is much desired to be optimized both plant safety and regulatory efficiency, an advanced safety regulation such as risk informed regulation has been come out. Also, there is a need to have a future oriented safety regulation since a lot of new reactors are conceptualized. Keeping pace with these needs, since early 2007, Korean government has launched a new project for preparing an advanced and future oriented nuclear safety regulation system. In order to get practical achievements, the project team sets up such specific research objectives for the development of: implementation program for graded regulation using risk and performance information; multi purpose PSA models for regulatory uses; a technology neutral regulatory framework for future innovative reactors; evaluation procedure of proliferation resistance; and, performance based fire hazard analysis method and evaluation system. This paper introduces major R and D outputs of this project, and provides some perspectives for achieving effectiveness and efficiency of the nuclear regulation system in Korea

  11. R and D perspectives on the advanced nuclear safety regulation system

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Chang Ju; Ahn, Sang Kyu; Park, Jong Seuk; Chung, Dae Wook [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of); Han, Sang Hoon; Lee, Jung Won [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2009-04-15

    As current licensing process is much desired to be optimized both plant safety and regulatory efficiency, an advanced safety regulation such as risk informed regulation has been come out. Also, there is a need to have a future oriented safety regulation since a lot of new reactors are conceptualized. Keeping pace with these needs, since early 2007, Korean government has launched a new project for preparing an advanced and future oriented nuclear safety regulation system. In order to get practical achievements, the project team sets up such specific research objectives for the development of: implementation program for graded regulation using risk and performance information; multi purpose PSA models for regulatory uses; a technology neutral regulatory framework for future innovative reactors; evaluation procedure of proliferation resistance; and, performance based fire hazard analysis method and evaluation system. This paper introduces major R and D outputs of this project, and provides some perspectives for achieving effectiveness and efficiency of the nuclear regulation system in Korea.

  12. Safety issues on advanced fuel

    Energy Technology Data Exchange (ETDEWEB)

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

    1998-05-01

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

  13. Combustion Safety Simplified Test Protocol Field Study

    Energy Technology Data Exchange (ETDEWEB)

    Brand, L. [Gas Technology Inst., Des Plaines, IL (United States); Cautley, D. [Gas Technology Inst., Des Plaines, IL (United States); Bohac, D. [Gas Technology Inst., Des Plaines, IL (United States); Francisco, P. [Gas Technology Inst., Des Plaines, IL (United States); Shen, L. [Gas Technology Inst., Des Plaines, IL (United States); Gloss, S. [Gas Technology Inst., Des Plaines, IL (United States)

    2015-11-01

    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. A survey of state weatherization agencies on combustion safety issues, details of a field data collection instrumentation package, summary of data collected over seven months, data analysis and results are included. The project team collected field data on 11 houses in 2015.

  14. Human-system safety methods for development of advanced air traffic management systems

    International Nuclear Information System (INIS)

    Nelson, William R.

    1999-01-01

    The Idaho National Engineering and Environmental Laboratory (INEEL) is supporting the National Aeronautics and Space Administration in the development of advanced air traffic management (ATM) systems as part of the Advanced Air Transportation Technologies program. As part of this program INEEL conducted a survey of human-system safety methods that have been applied to complex technical systems, to identify lessons learned from these applications and provide recommendations for the development of advanced ATM systems. The domains that were surveyed included offshore oil and gas, commercial nuclear power, commercial aviation, and military. The survey showed that widely different approaches are used in these industries, and that the methods used range from very high-level, qualitative approaches to very detailed quantitative methods such as human reliability analysis (HRA) and probabilistic safety assessment (PSA). In addition, the industries varied widely in how effectively they incorporate human-system safety assessment in the design, development, and testing of complex technical systems. In spite of the lack of uniformity in the approaches and methods used, it was found that methods are available that can be combined and adapted to support the development of advanced air traffic management systems (author) (ml)

  15. Advancing Measurement of Patient Safety Culture

    Science.gov (United States)

    Ginsburg, Liane; Gilin, Debra; Tregunno, Deborah; Norton, Peter G; Flemons, Ward; Fleming, Mark

    2009-01-01

    Objective To examine the psychometric and unit of analysis/strength of culture issues in patient safety culture (PSC) measurement. Data Source Two cross-sectional surveys of health care staff in 10 Canadian health care organizations totaling 11,586 respondents. Study Design A cross-validation study of a measure of PSC using survey data gathered using the Modified Stanford PSC survey (MSI-2005 and MSI-2006); a within-group agreement analysis of MSI-2006 data. Extraction Methods Exploratory factor analyses (EFA) of the MSI-05 survey data and confirmatory factor analysis (CFA) of the MSI-06 survey data; Rwg coefficients of homogeneity were calculated for 37 units and six organizations in the MSI-06 data set to examine within-group agreement. Principal Findings The CFA did not yield acceptable levels of fit. EFA and reliability analysis of MSI-06 data suggest two reliable dimensions of PSC: Organization leadership for safety (α=0.88) and Unit leadership for safety (α=0.81). Within-group agreement analysis shows stronger within-unit agreement than within-organization agreement on assessed PSC dimensions. Conclusions The field of PSC measurement has not been able to meet strict requirements for sound measurement using conventional approaches of CFA. Additional work is needed to identify and soundly measure key dimensions of PSC. The field would also benefit from further attention to strength of culture/unit of analysis issues. PMID:18823446

  16. Safety Assurance for Irradiating Experiments in the Advanced Test Reactor

    Energy Technology Data Exchange (ETDEWEB)

    T. A. Tomberlin; S. B. Grover

    2004-11-01

    The Advanced Test Reactor (ATR), located at the Idaho National Engineering and Environmental Laboratory (INEEL), was specifically designed to provide a high neutron flux test environment for conducting a variety of experiments. This paper addresses the safety assurance process for two general types of experiments conducted in the ATR facility and how the safety analyses for experiments are related to the ATR safety basis. One type of experiment is more routine and generally represents greater risks; therefore, this type of experiment is addressed in more detail in the ATR safety basis. This allows the individual safety analysis for this type of experiment to be more standardized. The second type of experiment is defined in more general terms in the ATR safety basis and is permitted under more general controls. Therefore, the individual safety analysis for the second type of experiment tends to be more unique and is tailored to each experiment.

  17. Safety Assurance for Irradiating Experiments in the Advanced Test Reactor

    International Nuclear Information System (INIS)

    T. A. Tomberlin; S. B. Grover

    2004-01-01

    The Advanced Test Reactor (ATR), located at the Idaho National Engineering and Environmental Laboratory (INEEL), was specifically designed to provide a high neutron flux test environment for conducting a variety of experiments. This paper addresses the safety assurance process for two general types of experiments conducted in the ATR facility and how the safety analyses for experiments are related to the ATR safety basis. One type of experiment is more routine and generally represents greater risks; therefore, this type of experiment is addressed in more detail in the ATR safety basis. This allows the individual safety analysis for this type of experiment to be more standardized. The second type of experiment is defined in more general terms in the ATR safety basis and is permitted under more general controls. Therefore, the individual safety analysis for the second type of experiment tends to be more unique and is tailored to each experiment

  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. Experience related to the safety of advanced LMFBR fuel elements

    International Nuclear Information System (INIS)

    Kerrisk, J.F.

    1975-07-01

    Experiments and experience relative to the safety of advanced fuel elements for the liquid metal fast breeder reactor are reviewed. The design and operating parameters and some of the unique features of advanced fuel elements are discussed breifly. Transient and steady state overpower operation and loss of sodium bond tests and experience are discussed in detail. Areas where information is lacking are also mentioned

  20. Combustion Safety Simplified Test Protocol Field Study

    Energy Technology Data Exchange (ETDEWEB)

    Brand, L [Gas Technology Inst., Des Plaines, IL (United States); Cautley, D. [Gas Technology Inst., Des Plaines, IL (United States); Bohac, D. [Gas Technology Inst., Des Plaines, IL (United States); Francisco, P. [Gas Technology Inst., Des Plaines, IL (United States); Shen, L. [Gas Technology Inst., Des Plaines, IL (United States); Gloss, S. [Gas Technology Inst., Des Plaines, IL (United States)

    2015-11-05

    "9Combustions 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. A survey of state weatherization agencies on combustion safety issues, details of a field data collection instrumentation package, summary of data collected over seven months, data analysis and results are included. The project provides several key results. State weatherization agencies do not generally track combustion safety failures, the data from those that do suggest that there is little actual evidence that combustion safety failures due to spillage from non-dryer exhaust are common and that only a very small number of homes are subject to the failures. The project team collected field data on 11 houses in 2015. Of these homes, two houses that demonstrated prolonged and excessive spillage were also the only two with venting systems out of compliance with the National Fuel Gas Code. The remaining homes experienced spillage that only occasionally extended beyond the first minute of operation. Combustion zone depressurization, outdoor temperature, and operation of individual fans all provide statistically significant predictors of spillage.

  1. The Advanced Light Source (ALS) Radiation Safety System

    International Nuclear Information System (INIS)

    Ritchie, A.L.; Oldfather, D.E.; Lindner, A.F.

    1993-08-01

    The Advanced Light Source (ALS) at the Lawrence Berkeley Laboratory (LBL) is a 1.5 Gev synchrotron light source facility consisting of a 120 kev electron gun, 50 Mev linear accelerator, 1.5 Gev booster synchrotron, 200 meter circumference electron storage ring, and many photon beamline transport systems for research. Figure 1. ALS floor plan. Pairs of neutron and gamma radiation monitors are shown as dots numbered from 1 to 12. The Radiation Safety System for the ALS has been designed and built with a primary goal of providing protection against inadvertent personnel exposure to gamma and neutron radiation and, secondarily, to enhance the electrical safety of select magnet power supplies

  2. Advanced gas cooled reactors - Designing for safety

    International Nuclear Information System (INIS)

    Keen, Barry A.

    1990-01-01

    The Advanced Gas-Cooled Reactor Power Stations recently completed at Heysham in Lancashire, England, and Torness in East Lothian, Scotland represent the current stage of development of the commercial AGR. Each power station has two reactor turbo-generator units designed for a total station output of 2x660 MW(e) gross although powers in excess of this have been achieved and it is currently intended to uprate this as far as possible. The design of both stations has been based on the successful operating AGRs at Hinkley Point and Hunterston which have now been in-service for almost 15 years, although minor changes were made to meet new safety requirements and to make improvements suggested by operating experience. The construction of these new AGRs has been to programme and within budget. Full commercial load for the first reactor at Torness was achieved in August 1988 with the other three reactors following over the subsequent 15 months. This paper summarises the safety principles and guidelines for the design of the reactors and discusses how some of the main features of the safety case meet these safety requirements. The paper also summarises the design problems which arose during the construction period and explains how these problems were solved with the minimum delay to programme

  3. Advanced gas cooled reactors - Designing for safety

    Energy Technology Data Exchange (ETDEWEB)

    Keen, Barry A [Engineering Development Unit, NNC Limited, Booths Hall, Knutsford, Cheshire (United Kingdom)

    1990-07-01

    The Advanced Gas-Cooled Reactor Power Stations recently completed at Heysham in Lancashire, England, and Torness in East Lothian, Scotland represent the current stage of development of the commercial AGR. Each power station has two reactor turbo-generator units designed for a total station output of 2x660 MW(e) gross although powers in excess of this have been achieved and it is currently intended to uprate this as far as possible. The design of both stations has been based on the successful operating AGRs at Hinkley Point and Hunterston which have now been in-service for almost 15 years, although minor changes were made to meet new safety requirements and to make improvements suggested by operating experience. The construction of these new AGRs has been to programme and within budget. Full commercial load for the first reactor at Torness was achieved in August 1988 with the other three reactors following over the subsequent 15 months. This paper summarises the safety principles and guidelines for the design of the reactors and discusses how some of the main features of the safety case meet these safety requirements. The paper also summarises the design problems which arose during the construction period and explains how these problems were solved with the minimum delay to programme.

  4. Safety characteristics of the US advanced liquid metal reactor core

    International Nuclear Information System (INIS)

    Magee, P.M.; Dubberley, A.E.; Gyorey, G.L.; Lipps, A.J.; Wu, T.

    1991-01-01

    The U.S. Advanced Liquid Metal Reactor (ALMR) design employs innovative, passive features to provide an unprecedented level of public safety and the ability to demonstrate this safety to the public. The key features employed in the core design to produce the desired passive safety characteristics are: a small core with a tight restraint system, the use of metallic U-Pu-Zr fuel, control rod withdrawal limiters, and gas expansion modules. In addition, the reactor vessel and closure are designed to have the capability to withstand, with large margins, the maximum possible core disruptive accident without breach and radiological release. (author)

  5. System safety engineering in the development of advanced surface transportation vehicles

    Science.gov (United States)

    Arnzen, H. E.

    1971-01-01

    Applications of system safety engineering to the development of advanced surface transportation vehicles are described. As a pertinent example, the paper describes a safety engineering efforts tailored to the particular design and test requirements of the Tracked Air Cushion Research Vehicle (TACRV). The test results obtained from this unique research vehicle provide significant design data directly applicable to the development of future tracked air cushion vehicles that will carry passengers in comfort and safety at speeds up to 300 miles per hour.

  6. KSC ADVANCED GROUND BASED FIELD MILL V1

    Data.gov (United States)

    National Aeronautics and Space Administration — The Advanced Ground Based Field Mill (AGBFM) network consists of 34 (31 operational) field mills located at Kennedy Space Center (KSC), Florida. The field mills...

  7. Advanced vehicle dynamics of heavy trucks with the perspective of road safety

    Science.gov (United States)

    Trigell, Annika Stensson; Rothhämel, Malte; Pauwelussen, Joop; Kural, Karel

    2017-10-01

    This paper presents state-of-the art within advanced vehicle dynamics of heavy trucks with the perspective of road safety. The most common accidents with heavy trucks involved are truck against passenger cars. Safety critical situations are for example loss of control (such as rollover and lateral stability) and a majority of these occur during speed when cornering. Other critical situations are avoidance manoeuvre and road edge recovery. The dynamic behaviour of heavy trucks have significant differences compared to passenger cars and as a consequence, successful application of vehicle dynamic functions for enhanced safety of trucks might differ from the functions in passenger cars. Here, the differences between vehicle dynamics of heavy trucks and passenger cars are clarified. Advanced vehicle dynamics solutions with the perspective of road safety of trucks are presented, beginning with the topic vehicle stability, followed by the steering system, the braking system and driver assistance systems that differ in some way from that of passenger cars as well.

  8. Studies on environment safety and application of advanced reactor for inland nuclear power plants

    International Nuclear Information System (INIS)

    Wei, L.; Jie, L.

    2014-01-01

    To study environment safety assessment of inland nuclear power plants (NPPs), the impact of environment safety under the normal operation was researched and the environment risk of serious accidents was analyzed. Moreover, the requirements and relevant provisions of site selection between international nuclear power plant and China's are comparatively studied. The conclusion was that the environment safety assessment of inland and coastal nuclear power plant have no essential difference; the advanced reactor can meet with high criteria of environment safety of inland nuclear power plants. In this way, China is safe and feasible to develop inland nuclear power plant. China's inland nuclear power plants will be as big market for advanced reactor. (author)

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

    DEFF Research Database (Denmark)

    Merkelsen, Henrik

    2013-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2012-05-15

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

  11. The advanced neutron source safety approach and plans

    International Nuclear Information System (INIS)

    Harrington, R.M.

    1989-01-01

    The Advanced Neutron Source (ANS) is a user facility for all areas of neutron research proposed for construction at the Oak Ridge National Laboratory. The neutron source is planned to be a 350-MW research reactor. The reactor, currently in conceptual design, will belong to the United States Department of Energy (USDOE). The safety approach and planned elements of the safety program for the ANS are described. The safety approach is to incorporate USDOE requirements [which, by reference, include appropriate requirements from the United States Nuclear Regulatory Commission (USNRC) and other national and state regulatory agencies] into the design, and to utilize probabilistic risk assessment (PRA) techniques during design to achieve extremely low probability of severe core damage. The PRA has already begun and will continue throughout the design and construction of the reactor. Computer analyses will be conducted for a complete spectrum of accidental events, from anticipated events to very infrequent occurrences. 8 refs., 2 tabs

  12. The Advanced Neutron Source safety approach and plans

    International Nuclear Information System (INIS)

    Harrington, R.M.

    1990-01-01

    The Advanced Neutron Source (ANS) is a user facility proposed for construction at the Oak Ridge National Laboratory for all areas of neutron research. The neutron source is planned to be a 350-MW research reactor. The reactor, currently in conceptual design, will belong to the United States Department of Energy (USDOE). The safety approach and planned elements of the safety program for the ANS are described. The safety approach is to incorporate USDOE requirements (which, by reference, include appropriate requirements from the United States Nuclear Regulatory Commission (USNRC) and other national and state regulatory agencies) into the design, and to utilize probabilistic risk assessment (PRA) techniques during design to achieve extremely low probability of severe core damage. The PRA has already begun and will continue throughout the design and construction of the reactor. Computer analyses will be conducted for a complete spectrum of accidental events, from anticipated events to very infrequent occurrences

  13. Advanced-fuel reversed-field pinch reactor (RFPR)

    International Nuclear Information System (INIS)

    Hagenson, R.L.; Krakowski, R.A.

    1981-10-01

    The utilization of deuterium-based fuels offers the potential advantages of greater flexibility in blanket design, significantly reduced tritium inventory, potential reduction in radioactivity level, and utilization of an inexhaustible fuel supply. The conventional DT-fueled Reversed-Field Pinch Reactor (RFPR) designs are reviewed, and the recent extension of these devices to advanced-fuel (catalyzed-DD) operation is presented. Attractive and economically competitive DD/RFPR systems are identified having power densities and plasma parameters comparable to the DT systems. Converting an RFP reactor from DT to DD primarily requires increasing the magnetic field levels a factor of two, still requiring only modest magnet coil fields (less than or equal to 4 T). When compared to the mainline tokamak, the unique advantages of the RFP (e.g., high beta, low fields at the coils, high ohmic-heating power densities, unrestricted aspect ratio) are particularly apparent for the utilization of advanced fuels

  14. Luxury cruise? The safety potential of advanced cruise control.

    NARCIS (Netherlands)

    Oei, H.L.

    2003-01-01

    The principles of advanced cruise control (ACC) are outlined and the requirements for an ACC system are described. An intelligent cruise control system fitted in a Nissan Primera was tested on the road over a 2-week period by 10 drivers, eight of which were experts in road safety. Most test-drives

  15. Participant Assessments of Aviation Safety Inspector Training for Technically Advanced Aircraft

    National Research Council Canada - National Science Library

    Chidester, Thomas; Hackworth, Carla; Knecht, William

    2007-01-01

    .... Currently, Federal Aviation Administration (FAA) aviation safety inspectors are required to inspect technically advanced aircraft, check certified flight instructors, and conduct surveillance of designated pilot examiners who are certifying pilots...

  16. 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)

  17. Advances made in French safety studies on pressurized water reactors

    International Nuclear Information System (INIS)

    Pelce, J.

    1979-01-01

    The programme of French safety studies on reactors is supposed to be known in its main outlines. A few recent results, obtained in different fields are presented. They concern the safety margins evaluation, the contamination transfer and the effect of external aggressions

  18. Safety aspects of advanced fuels irradiations in EBR-II

    International Nuclear Information System (INIS)

    Lehto, W.K.

    1975-09-01

    Basic safety questions such as MFCI, loss-of-Na bond, pin behavior during design basis transients, and failure propagation were evaluated as they pertain to advanced fuels in EBR-II. With the exception of pin response to the unlikely loss-of-flow transient, the study indicates that irradiation of significant numbers of advanced fueled subassemblies in EBR-II should pose no safety problems. The analysis predicts, however, that Na boiling may occur during the postulated design basis unlikely loss-of-flow transient in subassemblies containing He-bonded fuel pins with the larger fuel-clad gaps. The calculations indicate that coolant temperatures at top of core in the limiting S/A's, containing the He bonded pins, would reach approximately 1480 0 F during the transient without application of uncertainty factors. Inclusion of uncertainties could result in temperature predictions which approach coolant boiling temperatures (1640 0 F). Further analysis of He-bonded pins is being done in this potential problem area, e.g., to apply best estimates of uncertainty factors and to determine the sensitivity of the preliminary results to gap conductance

  19. Advanced power reactors with improved safety characteristics

    International Nuclear Information System (INIS)

    Birkhofer, A.

    1994-01-01

    The primary objective of nuclear safety is the protection of individuals, society and environment against radiological hazards from accidental releases of radioactive materials contained in nuclear reactors. Hereto, these materials are enclosed by several successive barriers and the barriers protected against mishaps and accidents by a multi-level system of safety precautions. The evolution of reactor technology continuously improves this concept and its implementation. At a world-wide scale, several advanced reactor concepts are currently being considered, some of them already at a design stage. Essential safety objectives include both further strengthening the prevention of accidents and improving the containment of fission products should an accident occur. The proposed solutions differ considerably with regard to technical principles, plant size and time scales considered for industrial application. Two typical approaches can be distinguished: The first approach basically aims at an evolution of power reactors currently in use, taking into account the findings from safety research and from operation of current plants. This approach makes maximum use of proven technology and operating experience but may nevertheless include new safety features. The corresponding designs are often termed 'large evolutionary'. The second approach consists in more fundamental changes compared to present designs, often with strong emphasis on specific passive features protecting the fuel and fuel cladding barriers. Owing to the nature and capability of those passive features such 'innovative designs' are mostly smaller in power output. The paper describes the basic objectives of such developments and illustrates important technical concepts focusing on next generation plants, i.e. designs to be available for industrial application until the end of this decade. 1 tab. (author)

  20. Launching the dialogue: Safety and innovation as partners for success in advanced manufacturing.

    Science.gov (United States)

    Geraci, C L; Tinkle, S S; Brenner, S A; Hodson, L L; Pomeroy-Carter, C A; Neu-Baker, N

    2018-06-01

    Emerging and novel technologies, materials, and information integrated into increasingly automated and networked manufacturing processes or into traditional manufacturing settings are enhancing the efficiency and productivity of manufacturing. Globally, there is a move toward a new era in manufacturing that is characterized by: (1) the ability to create and deliver more complex designs of products; (2) the creation and use of materials with new properties that meet a design need; (3) the employment of new technologies, such as additive and digital techniques that improve on conventional manufacturing processes; and (4) a compression of the time from initial design concept to the creation of a final product. Globally, this movement has many names, but "advanced manufacturing" has become the shorthand for this complex integration of material and technology elements that enable new ways to manufacture existing products, as well as new products emerging from new technologies and new design methods. As the breadth of activities associated with advanced manufacturing suggests, there is no single advanced manufacturing industry. Instead, aspects of advanced manufacturing can be identified across a diverse set of business sectors that use manufacturing technologies, ranging from the semiconductors and electronics to the automotive and pharmaceutical industries. The breadth and diversity of advanced manufacturing may change the occupational and environmental risk profile, challenge the basic elements of comprehensive health and safety (material, process, worker, environment, product, and general public health and safety), and provide an opportunity for development and dissemination of occupational and environmental health and safety (OEHS) guidance and best practices. It is unknown how much the risk profile of different elements of OEHS will change, thus requiring an evolution of health and safety practices. These changes may be accomplished most effectively through multi

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

    Science.gov (United States)

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

    2017-12-19

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

  2. Advancements in the design of safety-related systems and components of the MARS nuclear plant

    International Nuclear Information System (INIS)

    Caira, M.; Caruso, G.; Naviglio, A.; Sorabella, L.; Farello, C.E.

    1992-01-01

    In the paper, the advancements in the design of safety-related systems and components of the MARS nuclear plant, equipped with a 600 MW th PWR, are described. These advancements are due to the special safety features of this plant, which relies completely on inherent and passive safety. In particular, the new steps of the design of the innovative, completely passive, and with an unlimited autonomy Emergency core Cooling System are described, together with the characteristics of the last version of the steam generator, developed in a new design involving disconnecting components, for a fast erection and an easy maintenance. (author)

  3. Advanced analysis and design for fire safety of steel structures

    CERN Document Server

    Li, Guoqiang

    2013-01-01

    Advanced Analysis and Design for Fire Safety of Steel Structures systematically presents the latest findings on behaviours of steel structural components in a fire, such as the catenary actions of restrained steel beams, the design methods for restrained steel columns, and the membrane actions of concrete floor slabs with steel decks. Using a systematic description of structural fire safety engineering principles, the authors illustrate the important difference between behaviours of an isolated structural element and the restrained component in a complete structure under fire conditions. The book will be an essential resource for structural engineers who wish to improve their understanding of steel buildings exposed to fires. It is also an ideal textbook for introductory courses in fire safety for master’s degree programs in structural engineering, and is excellent reading material for final-year undergraduate students in civil engineering and fire safety engineering. Furthermore, it successfully bridges th...

  4. Field-based systems and advanced diagnostics

    International Nuclear Information System (INIS)

    Eryurek, E.

    1998-01-01

    Detection and characterization of anomalies in an industrial plant provide improved plant availability and plant efficiency thus yielding increased economic efficiency. Traditionally, detection of process anomalies is done at a high-level control system through various signal validation methods. These signal validation techniques rely on data from transmitters, which measure related process variables. Correlating these signals and deducing anomalies often is a very time consuming and a difficult task. Delays in detecting these anomalies can be costly during plant operation. Conventional centralized approaches also suffer from their dependence on detailed mathematical models of the processes. Smart field devices have the advantage of providing the necessary information directly to the control system as anomalies develop during operation of the processes enabling operators to take necessary steps to either prevent an unnecessary shut down before the problem becomes serious or schedule maintenance on the problematic loop. Fisher-Rosemount's PlantWeb TM architecture addresses 'Enhanced Measurement, Advanced Diagnostics and Control in the Field'. PlantWeb TM builds open process management systems by networking intelligent field devices, scalable control and systems platforms, and integrated modular software. A description of PlantWeb TM and how it improves various process conditions and reduces operating cost of a plant as well as a high level description of 'Enhanced Measurement, Advanced Diagnostics and Control in the Field', will be provided in this paper. PlantWeb TM is the trademark for Fisher-Rosemount's new field-based architecture that uses emerging technologies to utilize the power of intelligent field devices and deliver critical process and equipment information to improve plant performance. (author)

  5. An investigation of fluid mixing with safety injection in advanced reactors

    International Nuclear Information System (INIS)

    Cha, Jong Hee; Won, Soon Yean; Chung, Moon Ki; Jun, Hyung Gil

    1994-01-01

    The objective of this work is to investigate the fluid mixing phenomena in aspect of pressurized thermal shock(PTS) in an advanced PWR vessel downcomer during transient cooldown with safety injection. It provides comparison of fluid mixing characteristics between AP 600 DVI, designed by Westinghouse, and ABB CE System 80+ DVI, and the effects of deflector at the reactor downcomer. In order to investigate the fluid mixing phenomena in the downcomer of an advanced PWR, the flow visualization tests and the salt concentration tests were conducted in a 1/7-scale acrylic transparent model, which was designed and built based on AP 600 reactor geometry. The behaviour of the safety injection flow in downcomer associated with mixing phenomenon can be observed during visualization test, and time-dependent mixing rate between safety injection fluid and existing coolant can be determined with concentration test. Visualization tests were performed by the dye injection method. The results of concentration measurements were compared with the calculation using the REMIX code. During the tests, difference between AP 600 DVI flow and ABB CE System 80+ DVI flow and the effect of the deflector were observed

  6. Biological effects of electromagnetic fields and recently updated safety guidelines for strong static magnetic fields

    International Nuclear Information System (INIS)

    Yamaguchi-Sekino, Sachiko; Sekino, Masaki; Ueno, Shoogo

    2011-01-01

    Humans are exposed daily to artificial and naturally occurring magnetic fields that originate from many different sources. We review recent studies that examine the biological effects of and medical applications involving electromagnetic fields, review the properties of static and pulsed electromagnetic fields that affect biological systems, describe the use of a pulsed electromagnetic field in combination with an anticancer agent as an example of a medical application that incorporates an electromagnetic field, and discuss the recently updated safety guidelines for static electromagnetic fields. The most notable modifications to the 2009 International Commission on Non-Ionizing Radiation Protection guidelines are the increased exposure limits, especially for those who work with or near electromagnetic fields (occupational exposure limits). The recommended increases in exposure were determined using recent scientific evidence obtained from animal and human studies. Several studies since the 1994 publication of the guidelines have examined the effects on humans after exposure to high static electromagnetic fields (up to 9.4 tesla), but additional research is needed to ascertain further the safety of strong electromagnetic fields. (author)

  7. Experimental facilities for gas-cooled reactor safety studies. Task group on Advanced Reactor Experimental Facilities (TAREF)

    International Nuclear Information System (INIS)

    2009-01-01

    In 2007, the NEA Committee on the Safety of Nuclear Installations (CSNI) completed a study on Nuclear Safety Research in OECD Countries: Support Facilities for Existing and Advanced Reactors (SFEAR) which focused on facilities suitable for current and advanced water reactor systems. In a subsequent collective opinion on the subject, the CSNI recommended to conduct a similar exercise for Generation IV reactor designs, aiming to develop a strategy for ' better preparing the CSNI to play a role in the planned extension of safety research beyond the needs set by current operating reactors'. In that context, the CSNI established the Task Group on Advanced Reactor Experimental Facilities (TAREF) in 2008 with the objective of providing an overview of facilities suitable for performing safety research relevant to gas-cooled reactors and sodium fast reactors. This report addresses gas-cooled reactors; a similar report covering sodium fast reactors is under preparation. The findings of the TAREF are expected to trigger internationally funded CSNI projects on relevant safety issues at the key facilities identified. Such CSNI-sponsored projects constitute a means for efficiently obtaining the necessary data through internationally co-ordinated research. This report provides an overview of experimental facilities that can be used to carry out nuclear safety research for gas-cooled reactors and identifies priorities for organizing international co-operative programmes at selected facilities. The information has been collected and analysed by a Task Group on Advanced Reactor Experimental Facilities (TAREF) as part of an ongoing initiative of the NEA Committee on the Safety of Nuclear Installations (CSNI) which aims to define and to implement a strategy for the efficient utilisation of facilities and resources for Generation IV reactor systems. (author)

  8. International co-operation in the field of operational safety

    International Nuclear Information System (INIS)

    Dupuis, M.C.

    1988-10-01

    Operational safety in nuclear power plants is without doubt a field where international co-operation is in constant progress. Accounting for over 80 per cent of the 400 reactors in service throughout the world, the menber countries of the OECD Nuclear Energy Agency (NEA) are constantly striving to improve the exchange and use of the wealth of information to be gained not just from power plant accidents and incidents but from the routine operation of these facilities. The Committee on the Safety of Nuclear Installations (CSNI) helps the Steering Committee for Nuclear Energy to meet the NEA's objectives in the safety field, namely: - to promote co-operation between the safety bodies of member countries - to contribute to the safety and regulation of nuclear activities. The CSNI relies on the technical back-up of several different working groups made up of experts appointed by the member countries. For the past three years I have had the honour of chairing Principal Working Group 1 (PWG 1), which deals with operating experience and human factor. It is in this capacity that I will attempt to outline the group's various activities and its findings illustrated by a few examples

  9. Advanced Range Safety System for High Energy Vehicles

    Science.gov (United States)

    Claxton, Jeffrey S.; Linton, Donald F.

    2002-01-01

    The advanced range safety system project is a collaboration between the National Aeronautics and Space Administration and the United States Air Force to develop systems that would reduce costs and schedule for safety approval for new classes of unmanned high-energy vehicles. The mission-planning feature for this system would yield flight profiles that satisfy the mission requirements for the user while providing an increased quality of risk assessment, enhancing public safety. By improving the speed and accuracy of predicting risks to the public, mission planners would be able to expand flight envelopes significantly. Once in place, this system is expected to offer the flexibility of handling real-time risk management for the high-energy capabilities of hypersonic vehicles including autonomous return-from-orbit vehicles and extended flight profiles over land. Users of this system would include mission planners of Space Launch Initiative vehicles, space planes, and other high-energy vehicles. The real-time features of the system could make extended flight of a malfunctioning vehicle possible, in lieu of an immediate terminate decision. With this improved capability, the user would have more time for anomaly resolution and potential recovery of a malfunctioning vehicle.

  10. Near-field performance of the advanced cold process canister

    International Nuclear Information System (INIS)

    Werme, L.

    1990-09-01

    A near-field performance evaluation of an Advanced Cold Process Canister for spent fuel disposal has been performed jointly by TVO, Finland and SKB, Sweden. The canister consists of a steel canister as a load bearing element, with an outer corrosion shield of copper. The canister design was originally proposed by TVO. In the analysis, as well internal (ie corrosion processes from the inside of the canister) as external processes (mechanical and chemical) have been considered both prior to and after canister breach. Throughout the analysis, present day underground conditions has been assumed to persist during the service life of the canister. The major conclusions for the evaluation are: Internal processes cannot cause the canister breach under foreseen conditions, ie localized corrosion for the steel or copper canisters can be dismissed as a failure mechanism. The evaluation of the effects of processes outside the canister indicate that there is no rapid mechanism to endanger the integrity of the canister. Consequently the service life of the canister will be several million years. This factor will ensure the safety of the concept. (orig.)

  11. Proving autonomous vehicle and advanced driver assistance systems safety : final research report.

    Science.gov (United States)

    2016-02-15

    The main objective of this project was to provide technology for answering : crucial safety and correctness questions about verification of autonomous : vehicle and advanced driver assistance systems based on logic. : In synergistic activities, we ha...

  12. The integrated code system CASCADE-3D for advanced core design and safety analysis

    International Nuclear Information System (INIS)

    Neufert, A.; Van de Velde, A.

    1999-01-01

    The new program system CASCADE-3D (Core Analysis and Safety Codes for Advanced Design Evaluation) links some of Siemens advanced code packages for in-core fuel management and accident analysis: SAV95, PANBOX/COBRA and RELAP5. Consequently by using CASCADE-3D the potential of modern fuel assemblies and in-core fuel management strategies can be much better utilized because safety margins which had been reduced due to conservative methods are now predicted more accurately. By this innovative code system the customers can now take full advantage of the recent progress in fuel assembly design and in-core fuel management.(author)

  13. Advances in high field laser physics

    CERN Document Server

    Sheng, Zhengming; Chen, Liming; Lu, Wei; Shen, Baifei

    2019-01-01

    High field laser physics emerged with the advent of ultrashort intense lasers about 25 years ago. It has developed into a frontier of cross-disciplinary studies, covering attosecond X-ray physics, particle accelerator physics, and physics of inertial confined fusion, etc., with prospects of wide applications. Because this is a new and rapidly developing field, so far there are only 2-3 related books available. There are a few review articles in some journals, which are limited to specific topics in high field physics. There are quite a few conference proceedings in this field, which are the collections of papers presented at conferences. In this book, a few leading experts working on different subjects in this field are invited to introduce the key topics in high field laser physics, which cover the involved fundamental physics, the recent advances, as well as the prospects of future applications. It shall be very useful to graduate students, young researchers, and people who want to have an overview of thi...

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-11-01

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

  15. Vacuum source-field correlations and advanced waves in quantum optics

    Directory of Open Access Journals (Sweden)

    Adam Stokes

    2018-01-01

    Full Text Available The solution to the wave equation as a Cauchy problem with prescribed fields at an initial time $t=0$ is purely retarded. Similarly, in the quantum theory of radiation the specification of Heisenberg picture photon annihilation and creation operators at time $t \\gt 0$ in terms of operators at $t=0$ automatically yields purely retarded source-fields. However, we show that two-time quantum correlations between the retarded source-fields of a stationary dipole and the quantum vacuum-field possess advanced wave-like contributions. Despite their advanced nature, these correlations are perfectly consistent with Einstein causality. It is shown that while they do not significantly contribute to photo-detection amplitudes in the vacuum state, they do effect the statistics of measurements involving the radiative force experienced by a point charge in the field of the dipole. Specifically, the dispersion in the charge's momentum is found to increase with time. This entails the possibility of obtaining direct experimental evidence for the existence of advanced waves in physical reality, and provides yet another signature of the quantum nature of the vacuum.

  16. Safety design analyses of Korea Advanced Liquid Metal Reactor

    International Nuclear Information System (INIS)

    Suk, S.D.; Park, C.K.

    2000-01-01

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

  17. Foundational development of an advanced nuclear reactor integrated safety code

    International Nuclear Information System (INIS)

    Clarno, Kevin; Lorber, Alfred Abraham; Pryor, Richard J.; Spotz, William F.; Schmidt, Rodney Cannon; Belcourt, Kenneth; Hooper, Russell Warren; Humphries, Larry LaRon

    2010-01-01

    This report describes the activities and results of a Sandia LDRD project whose objective was to develop and demonstrate foundational aspects of a next-generation nuclear reactor safety code that leverages advanced computational technology. The project scope was directed towards the systems-level modeling and simulation of an advanced, sodium cooled fast reactor, but the approach developed has a more general applicability. The major accomplishments of the LDRD are centered around the following two activities. (1) The development and testing of LIME, a Lightweight Integrating Multi-physics Environment for coupling codes that is designed to enable both 'legacy' and 'new' physics codes to be combined and strongly coupled using advanced nonlinear solution methods. (2) The development and initial demonstration of BRISC, a prototype next-generation nuclear reactor integrated safety code. BRISC leverages LIME to tightly couple the physics models in several different codes (written in a variety of languages) into one integrated package for simulating accident scenarios in a liquid sodium cooled 'burner' nuclear reactor. Other activities and accomplishments of the LDRD include (a) further development, application and demonstration of the 'non-linear elimination' strategy to enable physics codes that do not provide residuals to be incorporated into LIME, (b) significant extensions of the RIO CFD code capabilities, (c) complex 3D solid modeling and meshing of major fast reactor components and regions, and (d) an approach for multi-physics coupling across non-conformal mesh interfaces.

  18. Foundational development of an advanced nuclear reactor integrated safety code.

    Energy Technology Data Exchange (ETDEWEB)

    Clarno, Kevin (Oak Ridge National Laboratory, Oak Ridge, TN); Lorber, Alfred Abraham; Pryor, Richard J.; Spotz, William F.; Schmidt, Rodney Cannon; Belcourt, Kenneth (Ktech Corporation, Albuquerque, NM); Hooper, Russell Warren; Humphries, Larry LaRon

    2010-02-01

    This report describes the activities and results of a Sandia LDRD project whose objective was to develop and demonstrate foundational aspects of a next-generation nuclear reactor safety code that leverages advanced computational technology. The project scope was directed towards the systems-level modeling and simulation of an advanced, sodium cooled fast reactor, but the approach developed has a more general applicability. The major accomplishments of the LDRD are centered around the following two activities. (1) The development and testing of LIME, a Lightweight Integrating Multi-physics Environment for coupling codes that is designed to enable both 'legacy' and 'new' physics codes to be combined and strongly coupled using advanced nonlinear solution methods. (2) The development and initial demonstration of BRISC, a prototype next-generation nuclear reactor integrated safety code. BRISC leverages LIME to tightly couple the physics models in several different codes (written in a variety of languages) into one integrated package for simulating accident scenarios in a liquid sodium cooled 'burner' nuclear reactor. Other activities and accomplishments of the LDRD include (a) further development, application and demonstration of the 'non-linear elimination' strategy to enable physics codes that do not provide residuals to be incorporated into LIME, (b) significant extensions of the RIO CFD code capabilities, (c) complex 3D solid modeling and meshing of major fast reactor components and regions, and (d) an approach for multi-physics coupling across non-conformal mesh interfaces.

  19. AN ADVANCED TOOL FOR APPLIED INTEGRATED SAFETY MANAGEMENT

    Energy Technology Data Exchange (ETDEWEB)

    Potts, T. Todd; Hylko, James M.; Douglas, Terence A.

    2003-02-27

    WESKEM, LLC's Environmental, Safety and Health (ES&H) Department had previously assessed that a lack of consistency, poor communication and using antiquated communication tools could result in varying operating practices, as well as a failure to capture and disseminate appropriate Integrated Safety Management (ISM) information. To address these issues, the ES&H Department established an Activity Hazard Review (AHR)/Activity Hazard Analysis (AHA) process for systematically identifying, assessing, and controlling hazards associated with project work activities during work planning and execution. Depending on the scope of a project, information from field walkdowns and table-top meetings are collected on an AHR form. The AHA then documents the potential failure and consequence scenarios for a particular hazard. Also, the AHA recommends whether the type of mitigation appears appropriate or whether additional controls should be implemented. Since the application is web based, the information is captured into a single system and organized according to the >200 work activities already recorded in the database. Using the streamlined AHA method improved cycle time from over four hours to an average of one hour, allowing more time to analyze unique hazards and develop appropriate controls. Also, the enhanced configuration control created a readily available AHA library to research and utilize along with standardizing hazard analysis and control selection across four separate work sites located in Kentucky and Tennessee. The AHR/AHA system provides an applied example of how the ISM concept evolved into a standardized field-deployed tool yielding considerable efficiency gains in project planning and resource utilization. Employee safety is preserved through detailed planning that now requires only a portion of the time previously necessary. The available resources can then be applied to implementing appropriate engineering, administrative and personal protective equipment

  20. Nordic projects in the field of nuclear safety

    International Nuclear Information System (INIS)

    Soerensen, H.C.

    1989-07-01

    This report describes the work in 1988 within the Nordic program concerning nuclear safety 1985-1989. The report has the form of a handbook meant for those in Scandinavia who are involeved in nuclear safety, and it is based on statements from the constituent subject fields of the program. The first chapter is a short summary of the work and results over the year. In the next chapter an account is given of the ongoing projects within each of the subject fields. An economic survey of the entire program and a list of the reports and articles published in 1988 is included in the publicaltion as well. Chapter 5 is a complete list of adresses comprising participants, project managers, program coordinators and members of the advirosy group. (SH)

  1. Nordic projects in the field of nuclear safety

    International Nuclear Information System (INIS)

    Soerensen, H.C.

    1988-05-01

    This report deseribes the work in 1987 within the Nordic program concerning nuclear safety 1985-1989. The report has the form of a handbook meant for those in Scandinavia who are involved in nuclear safety, and it is based on statements from the constituent subject fields of the program. The first chapter is a short summary of the work and results over the year. In the next chapter an account is given of the ongoing projects within each of the subject fields. An economic survey of the entire program and a list of the reports and articles published in 1987 is included in the publication as well. Chapter 5 is a complete list of adresses comprising participants, project managers, program coordinators and members of the advisory group. (SH) 74 refs

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-03-01

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

  3. Proposal for a advanced PWR core with adequate characteristics for passive safety concept

    International Nuclear Information System (INIS)

    Perrotta, Jose Augusto

    1999-01-01

    This work presents a discussion upon the suitable from an advanced PWR core, classified by the EPRI as 'Passive PWR' (advanced reactor with passive safety concept to power plants with less than 600 MW electrical power). The discussion upon the type of core is based on nuclear fuel engineering concepts. Discussion is made on type of fuel materials, structural materials, geometric shapes and manufacturing process that are suitable to produce fuel assemblies which give good performance for this type of reactors. The analysis is guided by the EPRI requirements for Advanced Light Water Reactor (ALWR). By means of comparison, the analysis were done to Angra 1 (old type of 600 MWe PWR class), and the design of the Westinghouse Advanced PWR-AP600. It was verified as a conclusion of this work that the modern PWR fuels are suitable for advanced PWR's Nevertheless, this work presents a technical alternative to this kind of fuel, still using UO 2 as fuel, but changing its cylindrical form of pellets and pin type fuel element to plane shape pallets and plate type fuel element. This is not a novelty fuel, since it was used in the 50's at Shippingport Reactor and as an advanced version by CEA of France in the 70's. In this work it is proposed a new mechanical assembly design for this fuel, which can give adequate safety and operational performance to the core of a 'Passive PWR'. (author)

  4. IAEA activities in the field of research reactors safety

    International Nuclear Information System (INIS)

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

    2004-01-01

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

  5. Field Programmable Gate Array-based I and C Safety System

    International Nuclear Information System (INIS)

    Kim, Hyun Jeong; Kim, Koh Eun; Kim, Young Geul; Kwon, Jong Soo

    2014-01-01

    Programmable Logic Controller (PLC)-based I and C safety system used in the operating nuclear power plants has the disadvantages of the Common Cause Failure (CCF), high maintenance costs and quick obsolescence, and then it is necessary to develop the other platform to replace the PLC. The Field Programmable Gate Array (FPGA)-based Instrument and Control (I and C) safety system is safer and more economical than Programmable Logic Controller (PLC)-based I and C safety system. Therefore, in the future, FPGA-based I and C safety system will be able to replace the PLC-based I and C safety system in the operating and the new nuclear power plants to get benefited from its safety and economic advantage. FPGA-based I and C safety system shall be implemented and verified by applying the related requirements to perform the safety function

  6. Field Programmable Gate Array-based I and C Safety System

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Hyun Jeong; Kim, Koh Eun; Kim, Young Geul; Kwon, Jong Soo [KEPCO, Daejeon (Korea, Republic of)

    2014-08-15

    Programmable Logic Controller (PLC)-based I and C safety system used in the operating nuclear power plants has the disadvantages of the Common Cause Failure (CCF), high maintenance costs and quick obsolescence, and then it is necessary to develop the other platform to replace the PLC. The Field Programmable Gate Array (FPGA)-based Instrument and Control (I and C) safety system is safer and more economical than Programmable Logic Controller (PLC)-based I and C safety system. Therefore, in the future, FPGA-based I and C safety system will be able to replace the PLC-based I and C safety system in the operating and the new nuclear power plants to get benefited from its safety and economic advantage. FPGA-based I and C safety system shall be implemented and verified by applying the related requirements to perform the safety function.

  7. A Historical View and Vision into the Future of the Field of Safety Pharmacology.

    Science.gov (United States)

    Bass, Alan S; Hombo, Toshiyasu; Kasai, Chieko; Kinter, Lewis B; Valentin, Jean-Pierre

    2015-01-01

    research organizations. This movement has created the opportunity for the safety pharmacology discipline to come "full circle" and return to the drug discovery arena (target identification through clinical candidate selection) to contribute to the mitigation of the high rate of candidate drug failure through better compound selection decision making. Finally, the changing focus of science and losses in didactic training of scientists in whole animal physiology and pharmacology have revealed a serious gap in the future availability of qualified individuals to apply the principles of safety pharmacology in support of drug discovery and development. This is a significant deficiency that at present is only partially met with academic and professional society programs advancing a minimal level of training. In summary, with the exception that the future availability of suitably trained scientists is a critical need for the field that remains to be effectively addressed, the prospects for the future of safety pharmacology are hopeful and promising, and challenging for those individuals who want to assume this responsibility. What began in the early part of the new millennium as a relatively simple model of testing to assure the safety of Phase I clinical subjects and patients from acute deleterious effects on life-supporting organ systems has grown with experience and time to a science that mobilizes the principles of cellular and molecular biology and attempts to predict acute adverse events and those associated with long-term treatment. These challenges call for scientists with a broad range of in-depth scientific knowledge and an ability to adapt to a dynamic and forever changing industry. Identifying individuals who will serve today and training those who will serve in the future will fall to all of us who are committed to this important field of science.

  8. Safety and emergency preparedness considerations for geotechnical field operations

    Energy Technology Data Exchange (ETDEWEB)

    Wemple, R.P.

    1989-04-01

    The GEO Energy Technology Department at Sandia National Laboratories is involved in several remote-site drilling and/or experimental operations each year. In 1987, the Geothermal Research Division of the Department developed a general set of Safe Operating Procedures (SOPs) that could be applied to a variety of projects. This general set is supplemented by site-specific SOPs as needed. Effective field operations require: integration of safety and emergency preparedness planning with overall project planning, training of field personnel and inventorying of local emergency support resources, and, developing a clear line of responsibility and authority to enforce the safety requirements. Copies of SOPs used in recent operations are included as examples of working documents for the reader.

  9. Conceptual safety design analysis of Korea advanced liquid metal reactor

    International Nuclear Information System (INIS)

    Suk, S. D.; Park, C. K.

    1999-01-01

    The national long-term R and D program, updated in 1977, requires Korea Atomic Energy Research Institute (KAERI) to complete by the year 2006 the basic design of Korea Advanced Liquid Metal Reactor (KALIMER), along with supporting R and D work, with the capability of resolving the issue of spent fuel storage as well as with significantly enhanced safety. KALIMER is a 150 Mwe pool-type sodium cooled prototype reactor that uses metallic fuel. The conceptual design is currently under way to establish a self-consistent design meeting a set of major safety design requirements for accident prevention. Some of the current emphasis includes those for inherent and passive means of negative reactivity insertion and decay heat removal, high shutdown reliability, prevention of and protection from sodium chemical reaction, and high seismic margin, among others. All of these requirements affect the reactor design significantly and involve extensive supporting R and D programs. This paper summarizes some of the results of conceptual engineering and design analyses performed for the safety of KALIMER in the area of inherent safety, passive decay heat removal, sodium water reaction, and seismic isolation. (author)

  10. Advanced Photon Source experimental beamline Safety Assessment Document: Addendum to the Advanced Photon Source Accelerator Systems Safety Assessment Document (APS-3.2.2.1.0)

    International Nuclear Information System (INIS)

    1995-01-01

    This Safety Assessment Document (SAD) addresses commissioning and operation of the experimental beamlines at the Advanced Photon Source (APS). Purpose of this document is to identify and describe the hazards associated with commissioning and operation of these beamlines and to document the measures taken to minimize these hazards and mitigate the hazard consequences. The potential hazards associated with the commissioning and operation of the APS facility have been identified and analyzed. Physical and administrative controls mitigate identified hazards. No hazard exists in this facility that has not been previously encountered and successfully mitigated in other accelerator and synchrotron radiation research facilities. This document is an updated version of the APS Preliminary Safety Analysis Report (PSAR). During the review of the PSAR in February 1990, the APS was determined to be a Low Hazard Facility. On June 14, 1993, the Acting Director of the Office of Energy Research endorsed the designation of the APS as a Low Hazard Facility, and this Safety Assessment Document supports that designation

  11. Comparison of a Traditional Probabilistic Risk Assessment Approach with Advanced Safety Analysis

    Energy Technology Data Exchange (ETDEWEB)

    Smith, Curtis L; Mandelli, Diego; Zhegang Ma

    2014-11-01

    As part of the Light Water Sustainability Program (LWRS) [1], the purpose of the Risk Informed Safety Margin Characterization (RISMC) [2] Pathway research and development (R&D) is to support plant decisions for risk-informed margin management with the aim to improve economics, reliability, and sustain safety of current NPPs. In this paper, we describe the RISMC analysis process illustrating how mechanistic and probabilistic approaches are combined in order to estimate a safety margin. We use the scenario of a “station blackout” (SBO) wherein offsite power and onsite power is lost, thereby causing a challenge to plant safety systems. We describe the RISMC approach, illustrate the station blackout modeling, and contrast this with traditional risk analysis modeling for this type of accident scenario. We also describe our approach we are using to represent advanced flooding analysis.

  12. Motorcycle That See: Multifocal Stereo Vision Sensor for Advanced Safety Systems in Tilting Vehicles

    Directory of Open Access Journals (Sweden)

    Gustavo Gil

    2018-01-01

    Full Text Available Advanced driver assistance systems, ADAS, have shown the possibility to anticipate crash accidents and effectively assist road users in critical traffic situations. This is not the case for motorcyclists, in fact ADAS for motorcycles are still barely developed. Our aim was to study a camera-based sensor for the application of preventive safety in tilting vehicles. We identified two road conflict situations for which automotive remote sensors installed in a tilting vehicle are likely to fail in the identification of critical obstacles. Accordingly, we set two experiments conducted in real traffic conditions to test our stereo vision sensor. Our promising results support the application of this type of sensors for advanced motorcycle safety applications.

  13. Motorcycles that See: Multifocal Stereo Vision Sensor for Advanced Safety Systems in Tilting Vehicles

    Science.gov (United States)

    2018-01-01

    Advanced driver assistance systems, ADAS, have shown the possibility to anticipate crash accidents and effectively assist road users in critical traffic situations. This is not the case for motorcyclists, in fact ADAS for motorcycles are still barely developed. Our aim was to study a camera-based sensor for the application of preventive safety in tilting vehicles. We identified two road conflict situations for which automotive remote sensors installed in a tilting vehicle are likely to fail in the identification of critical obstacles. Accordingly, we set two experiments conducted in real traffic conditions to test our stereo vision sensor. Our promising results support the application of this type of sensors for advanced motorcycle safety applications. PMID:29351267

  14. Motorcycle That See: Multifocal Stereo Vision Sensor for Advanced Safety Systems in Tilting Vehicles.

    Science.gov (United States)

    Gil, Gustavo; Savino, Giovanni; Piantini, Simone; Pierini, Marco

    2018-01-19

    Advanced driver assistance systems, ADAS, have shown the possibility to anticipate crash accidents and effectively assist road users in critical traffic situations. This is not the case for motorcyclists, in fact ADAS for motorcycles are still barely developed. Our aim was to study a camera-based sensor for the application of preventive safety in tilting vehicles. We identified two road conflict situations for which automotive remote sensors installed in a tilting vehicle are likely to fail in the identification of critical obstacles. Accordingly, we set two experiments conducted in real traffic conditions to test our stereo vision sensor. Our promising results support the application of this type of sensors for advanced motorcycle safety applications.

  15. Standardization of Safety Checklists for Sport Fields in Schools

    Directory of Open Access Journals (Sweden)

    S. Arghami

    2015-01-01

    Full Text Available Introduction: Nowadays in all human societies, sport is considered as a human-training matter, which often occurs in sport fields. Many people, including students in schools, occasionally deal with these fields. Therefore, a standard tool is required to frequently inspection of sport fields. The aim of this study was to standardize checklists for sport fields in schools. .Material and Method: This study is a kind of tool and technique evaluation was done in Zanjan in 2013. The studied population included indoor and outdoor sport fields in governmental boys’ high schools in Zanjan city. The checklists’ items selected based on existing regulations, standards and relevant studies. Standardization of all tools was done applying the face and content validity and reliability tests. .Result: The primary checklist for outdoor sport fields in high schools, which considered by the expert panel, consisted of 75 items. Based on CVI (2 to 3.9 and CVR (.5 to .78, modifications were done and 6 more items were added. And the same process for the primary checklist for outdoor sports fields (85 items was repeated. Based on CVI (2 to 3.9 and CVR (.5 to .78, items increased to 92.  .Conclusion: The safety checklist for sport fields in schools are matched with the properties of them. The safety checklist developed in this study has an acceptable reliability and validity for useful applying in sport field inspections.

  16. EDUCATION IN THE FIELD safety of human life AND THE SUSTAINABLE DEVELOPMENT

    Directory of Open Access Journals (Sweden)

    M. A. Kartavykh

    2016-01-01

    Full Text Available The publication purpose - pedagogical design of education of bachelors in the field safety of human life in the context of ideas of a sustainable development as one of the modern and perspective directions of the higher education. Philosophical and methodological, scientific and technical and pedagogical aspects of provisions of the concept of a sustainable development are opened. It is shown that the greatest potential for realization of ideas of a sustainable development the invariant subject matter the " Safety of human life " studied by future bachelors irrespective of the direction and a profile of preparation possesses. The fundamental principles of education in the field safety of human life of future bachelors are formulated. Key functions of education of bachelors in the field of health and safety are defined: valuable and orientation, teoretiko-world outlook, it is constructive - activity, it is reflexive - estimated. The methodical tasks approaching the project to specific sociocultural and pedagogical conditions are opened: definition of target reference points, modular structuring content of education, development of procedural and technological features of creation of educational activity; diagnostics of results. The idea of a didactic cycle at development of the content of education in the field safety of human life is proved and opened. The educations of future bachelors got in the course of approbation results in the field safety of human life in the context of ideology of sustainable (safe development allow to speak about efficiency of the chosen scientific and methodological and organizational and technological bases and to project new models of practical experience in conditions of providing optimum ways of productive pedagogical interaction.

  17. Advances in electron dosimetry of irregular fields

    International Nuclear Information System (INIS)

    Mendez V, J.

    1998-01-01

    In this work it is presented an advance in Electron dosimetry of irregular fields for beams emitted by linear accelerators. At present diverse methods exist which are coming to apply in the Radiotherapy centers. In this work it is proposed a method for irregular fields dosimetry. It will be allow to calculate the dose rate absorbed required for evaluating the time for the treatment of cancer patients. Utilizing the results obtained by the dosimetric system, it has been possible to prove the validity of the method describe for 12 MeV energy and for square field 7.5 x 7.5 cm 2 with percentile error less than 1 % . (Author)

  18. ELECTROMAGNETIC SAFETY OF ELECTRIC TRANSPORT SYSTEMS: MAIN SOURCES AND PARAMETERS OF MAGNETIC FIELDS

    Directory of Open Access Journals (Sweden)

    N. G. Ptitsyna

    2013-03-01

    Full Text Available Magnetic fields produced by electric drive vehicles may break electromagnetic safety. For electromagnetic safety and electromagnetic compatibility knowledge about characteristics and sources of magnetic fields in the electric transport is necessary. The article deals with analysis of available data about magnetic fields in electric cars and comparison with results of our measurements carried out in the other types of electrified transport systems.

  19. 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

  20. Process safety improvement-Quality and target zero

    Energy Technology Data Exchange (ETDEWEB)

    Van Scyoc, Karl [Det Norske Veritas (U.S.A.) Inc., DNV Energy Solutions, 16340 Park Ten Place, Suite 100, Houston, TX 77084 (United States)], E-mail: karl.van.scyoc@dnv.com

    2008-11-15

    Process safety practitioners have adopted quality management principles in design of process safety management systems with positive effect, yet achieving safety objectives sometimes remain a distant target. Companies regularly apply tools and methods which have roots in quality and productivity improvement. The 'plan, do, check, act' improvement loop, statistical analysis of incidents (non-conformities), and performance trending popularized by Dr. Deming are now commonly used in the context of process safety. Significant advancements in HSE performance are reported after applying methods viewed as fundamental for quality management. In pursuit of continual process safety improvement, the paper examines various quality improvement methods, and explores how methods intended for product quality can be additionally applied to continual improvement of process safety. Methods such as Kaizen, Poke yoke, and TRIZ, while long established for quality improvement, are quite unfamiliar in the process safety arena. These methods are discussed for application in improving both process safety leadership and field work team performance. Practical ways to advance process safety, based on the methods, are given.

  1. Process safety improvement-Quality and target zero

    International Nuclear Information System (INIS)

    Van Scyoc, Karl

    2008-01-01

    Process safety practitioners have adopted quality management principles in design of process safety management systems with positive effect, yet achieving safety objectives sometimes remain a distant target. Companies regularly apply tools and methods which have roots in quality and productivity improvement. The 'plan, do, check, act' improvement loop, statistical analysis of incidents (non-conformities), and performance trending popularized by Dr. Deming are now commonly used in the context of process safety. Significant advancements in HSE performance are reported after applying methods viewed as fundamental for quality management. In pursuit of continual process safety improvement, the paper examines various quality improvement methods, and explores how methods intended for product quality can be additionally applied to continual improvement of process safety. Methods such as Kaizen, Poke yoke, and TRIZ, while long established for quality improvement, are quite unfamiliar in the process safety arena. These methods are discussed for application in improving both process safety leadership and field work team performance. Practical ways to advance process safety, based on the methods, are given

  2. Process safety improvement--quality and target zero.

    Science.gov (United States)

    Van Scyoc, Karl

    2008-11-15

    Process safety practitioners have adopted quality management principles in design of process safety management systems with positive effect, yet achieving safety objectives sometimes remain a distant target. Companies regularly apply tools and methods which have roots in quality and productivity improvement. The "plan, do, check, act" improvement loop, statistical analysis of incidents (non-conformities), and performance trending popularized by Dr. Deming are now commonly used in the context of process safety. Significant advancements in HSE performance are reported after applying methods viewed as fundamental for quality management. In pursuit of continual process safety improvement, the paper examines various quality improvement methods, and explores how methods intended for product quality can be additionally applied to continual improvement of process safety. Methods such as Kaizen, Poke yoke, and TRIZ, while long established for quality improvement, are quite unfamiliar in the process safety arena. These methods are discussed for application in improving both process safety leadership and field work team performance. Practical ways to advance process safety, based on the methods, are given.

  3. Advances in global development and deployment of small modular reactors and incorporating lessons learned from the Fukushima Daiichi accident into the designs of engineered safety features of advanced reactors

    International Nuclear Information System (INIS)

    Hadid Subki, M.; )

    2014-01-01

    The IAEA has been facilitating the Member States in incorporating the lessons-learned from the Fukushima Dai-ichi Accident into the designs of engineered safety features of advanced reactors, including small modular reactors. An extended assessment is required to address challenges for advancing reactor safety in the new evolving generation of SMR plants to preserve the historic lessons in safety, through: assuring the diversity in emergency core cooling systems following loss of onsite AC power; ensuring diversity in reactor depressurization following a transient or accident; confirming independence in reactor trip and safety systems for sensors, power supplies and actuation systems, and finally diversity in maintaining containment integrity following a severe accident

  4. Reliability and safety engineering

    CERN Document Server

    Verma, Ajit Kumar; Karanki, Durga Rao

    2016-01-01

    Reliability and safety are core issues that must be addressed throughout the life cycle of engineering systems. Reliability and Safety Engineering presents an overview of the basic concepts, together with simple and practical illustrations. The authors present reliability terminology in various engineering fields, viz.,electronics engineering, software engineering, mechanical engineering, structural engineering and power systems engineering. The book describes the latest applications in the area of probabilistic safety assessment, such as technical specification optimization, risk monitoring and risk informed in-service inspection. Reliability and safety studies must, inevitably, deal with uncertainty, so the book includes uncertainty propagation methods: Monte Carlo simulation, fuzzy arithmetic, Dempster-Shafer theory and probability bounds. Reliability and Safety Engineering also highlights advances in system reliability and safety assessment including dynamic system modeling and uncertainty management. Cas...

  5. Progress in design, research and development and testing of safety systems for advanced water cooled reactors. Proceedings of a technical committee meeting

    International Nuclear Information System (INIS)

    1996-04-01

    The meeting covered the following topics: Developments in design of safety-related heat removal components and systems for advanced water cooled reactors; status of test programmes on heat removal components and systems of new designs; range of validity and extrapolation of test results for the qualification of design/licensing computer models and codes for advanced water cooled reactors; future needs and trends in testing of safety systems for advanced water cooled reactors. Tests of heat removal safety systems have been conducted by various groups supporting the design, testing and certification of advanced water cooled reactors. The Technical Committee concluded that the reported test results generally confirm the predicted performance features of the advanced designs. Refs, figs, tabs

  6. Progress in design, research and development and testing of safety systems for advanced water cooled reactors. Proceedings of a technical committee meeting

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-04-01

    The meeting covered the following topics: Developments in design of safety-related heat removal components and systems for advanced water cooled reactors; status of test programmes on heat removal components and systems of new designs; range of validity and extrapolation of test results for the qualification of design/licensing computer models and codes for advanced water cooled reactors; future needs and trends in testing of safety systems for advanced water cooled reactors. Tests of heat removal safety systems have been conducted by various groups supporting the design, testing and certification of advanced water cooled reactors. The Technical Committee concluded that the reported test results generally confirm the predicted performance features of the advanced designs. Refs, figs, tabs.

  7. Safety evaluation in the development of medical devices and combination products

    CERN Document Server

    Gad, Shayne C

    2008-01-01

    Capturing the growth of the global medical device market in recent years, this practical new guide is essential for all who are responsible for ensuring safety in the use and manufacture of medical devices. It has been extensively updated to reflect significant advances, incorporating combination products and helpful case examples of current real-life problems in the field.The Third Edition explores these key current trends:global device marketscontinually advancing technologythe increasing harmonization of device safety regulation worldwideEach aspect of safety evaluation is considered in ter

  8. Advancements in the field of personality development.

    Science.gov (United States)

    De Fruyt, Filip; Van Leeuwen, Karla

    2014-07-01

    A summary is provided what the fields of personality and developmental psychology had to offer each other the past decade, reflected in the eleven contributions enclosed in this special issue. Strengths and opportunities to further advance the field are identified, including the extension of general trait with maladaptive trait models, the use of alternative methods to assess personality, and the adoption of configural approaches to describe traits in individuals, beyond more traditional person-centered approaches. Copyright © 2014 The Foundation for Professionals in Services for Adolescents. Published by Elsevier Ltd. All rights reserved.

  9. Advancing the Science of Developmental Neurotoxicity (DNT) Testing for Better Safety Evaluation

    DEFF Research Database (Denmark)

    Bal-Price, Anna; Coecke, Sandra; Costa, Lucio

    2012-01-01

    Bal-Price AK, Coecke S, Costa L, Crofton KM, Fritsche E, Goldberg A, Grandjean P, Lein PJ, Li A, Lucchini R, Mundy WR, Padilla S, Persico A, Seiler AEM, Kreysa J. Conference Report: Advancing the Science of Developmental Neurotoxicity (DNT) Testing for Better Safety Evaluation. Altex 2012: 29: 202-15....

  10. Thermohydraulic and safety analysis on China advanced research reactor under station blackout accident

    International Nuclear Information System (INIS)

    Tian Wenxi; Qiu Suizheng; Su Guanghui; Jia Dounan; Liu Xingmin; Zhang Jianwei

    2007-01-01

    A thermohydraulic and safety analysis code-TSACC has been developed using Fortran90 language to evaluate the transient thermohydraulic behavior of the China advanced research reactor (CARR) under station blackout accident (SBA). For the development of TSACC, a series of corresponding mathematical and physical models were applied. Point reactor neutron kinetics model was adopted for solving the reactor power. All possible flow and heat transfer conditions under station blackout accident were considered and the optional correlations were supplied. The usual finite difference method was abandoned and the integral technique was adopted to evaluate the temperature field of the plate type fuel elements. A new simple and convenient equation was proposed for the resolution of the transient behaviors of the main pump instead of the complicated four-quadrant model. Gear method and Adams method were adopted alternately for a better solution to the stiff differential equations describing the dynamic behavior of the CARR. The computational result of TSACC showed the adequacy of the safety margin of CARR under SBA. For the purpose of Verification and Validation (V and V), the simulated results of TSACC were compared with those of RELAP5/MOD3 and a good agreement was obtained. The adoption of modular programming techniques enables TASCC to be applied to other reactors by easily modifying the corresponding function modules

  11. Abstract of results of safety study. Nuclear fuel cycle field in fiscal 2003

    International Nuclear Information System (INIS)

    2004-11-01

    This report descried the results of studies of nuclear fuel cycle field (nuclear fuel facilities, seismic design, all subjects of environmental radiation and waste disposal, and subjects on nuclear fuel cycle in probabilistic safety assessment) in fiscal 2003 on the basis of the principle project of safety study (from fiscal 2001 to 2005). It consists of four chapters; the first chapter is outline of the principle of project, the second is objects and subjects of safety study in the nuclear fuel cycle field, the third list of questionnaire of results of safety study and the forth investigation of results of safety study in fiscal 2003. There are 49 lists, which include 22 reports on the nuclear fuel facility, one on the seismic design, 4 on the probabilistic safety assessment, 7 on the environmental radiation and 15 on the waste disposal. (S.Y.)

  12. Advanced ultrasonic field system: a status report

    International Nuclear Information System (INIS)

    Mikesell, C.R.; Beller, L.S.

    1984-02-01

    An advanced ultrasonic system was developed to obtain highly reproducible inspection data and to overcome certain limitations encountered with the manual scanning method. Experience from field operations from 1976 through 1980 is discussed. The scope includes a description of the computer controlled system, personnel training, inservice inspections, data analysis, and current upgrading of the system

  13. IAEA safety standards and approach to safety of advanced reactors

    International Nuclear Information System (INIS)

    Gasparini, M.

    2004-01-01

    The paper presents an overview of the IAEA safety standards including their overall structure and purpose. A detailed presentation is devoted to the general approach to safety that is embodied in the current safety requirements for the design of nuclear power plants. A safety approach is proposed for the future. This approach can be used as reference for a safe design, for safety assessment and for the preparation of the safety requirements. The method proposes an integration of deterministic and risk informed concepts in the general frame of a generalized concept of safety goals and defence in depth. This methodology may provide a useful tool for the preparation of safety requirements for the design and operation of any kind of reactor including small and medium sized reactors with innovative safety features.(author)

  14. Advanced Test Reactor Safety Basis Upgrade Lessons Learned Relative to Design Basis Verification and Safety Basis Management

    International Nuclear Information System (INIS)

    G. L. Sharp; R. T. McCracken

    2004-01-01

    The Advanced Test Reactor (ATR) is a pressurized light-water reactor with a design thermal power of 250 MW. The principal function of the ATR is to provide a high neutron flux for testing reactor fuels and other materials. The reactor also provides other irradiation services such as radioisotope production. The ATR and its support facilities are located at the Test Reactor Area of the Idaho National Engineering and Environmental Laboratory (INEEL). An audit conducted by the Department of Energy's Office of Independent Oversight and Performance Assurance (DOE OA) raised concerns that design conditions at the ATR were not adequately analyzed in the safety analysis and that legacy design basis management practices had the potential to further impact safe operation of the facility.1 The concerns identified by the audit team, and issues raised during additional reviews performed by ATR safety analysts, were evaluated through the unreviewed safety question process resulting in shutdown of the ATR for more than three months while these concerns were resolved. Past management of the ATR safety basis, relative to facility design basis management and change control, led to concerns that discrepancies in the safety basis may have developed. Although not required by DOE orders or regulations, not performing design basis verification in conjunction with development of the 10 CFR 830 Subpart B upgraded safety basis allowed these potential weaknesses to be carried forward. Configuration management and a clear definition of the existing facility design basis have a direct relation to developing and maintaining a high quality safety basis which properly identifies and mitigates all hazards and postulated accident conditions. These relations and the impact of past safety basis management practices have been reviewed in order to identify lessons learned from the safety basis upgrade process and appropriate actions to resolve possible concerns with respect to the current ATR safety

  15. Advanced safety management systems for maintenance of pipeline integrity

    International Nuclear Information System (INIS)

    Borysiewicz, M.; Potempski, S.

    2005-01-01

    One of the duties of the pipeline's operator is to introduce means for protection of human safety and the environment. This should be reflected in preparation of comprehensive Risk Management System with its key element Activity Programme for Management of Pipeline Integrity. In the paper such programme has been described taking into account law regulations and practical activities undertaken in technologically advanced countries (mainly USA and EU), where such solutions are implemented in routine operations. Possible solutions of realization of all elements of the programme, as well as information on utilization of computer aided support have been also included. (authors)

  16. Using level-I PRA for enhanced safety of the advanced neutron source reactor

    International Nuclear Information System (INIS)

    Ramsey, C.T.; Linn, M.A.

    1995-01-01

    The phase-1, level-I probabilistic risk assessment (PRA) of the Advanced Neutron Source (ANS) reactor has been completed as part of the conceptual design phase of this proposed research facility. Since project inception, PRA and reliability concepts have been an integral part of the design evolutions contributing to many of the safety features in the current design. The level-I PRA has been used to evaluate the internal events core damage frequency against project goals and to identify systems important to safety and availability, and it will continue to guide and provide support to accident analysis, both severe and nonsevere. The results also reflect the risk value of defense-in-depth safety features in reducing the likelihood of core damage

  17. Advanced technologies and atomic energy

    International Nuclear Information System (INIS)

    1995-01-01

    The expert committee on the research 'Application of advanced technologies to nuclear power' started the activities in fiscal year 1994 as one of the expert research committees of Atomic Energy Society of Japan. The objective of its foundation is to investigate the information on the advanced technologies related to atomic energy and to promote their practice. In this fiscal year, the advanced technologies in the fields of system and safety, materials and measurement were taken up. The second committee meeting was held in March, 1995. In this report, the contents of the lectures at the committee meeting and the symposium are compiled. The topics in the symposium were the meaning of advanced technologies, the advanced technologies and atomic energy, human factors and control and safety systems, robot technology and microtechnology, and functionally gradient materials. Lectures were given at two committee meetings on the development of atomic energy that has come to the turning point, the development of advanced technologies centering around ULSI, the present problems of structural fine ceramics and countermeasures of JFCC, the material analysis using laser plasma soft X-ray, and the fullerene research of advanced technology development in Power Reactor and Nuclear Fuel Development Corporation. (K.I.)

  18. Using field feedback to estimate failure rates of safety-related systems

    International Nuclear Information System (INIS)

    Brissaud, Florent

    2017-01-01

    The IEC 61508 and IEC 61511 functional safety standards encourage the use of field feedback to estimate the failure rates of safety-related systems, which is preferred than generic data. In some cases (if “Route 2_H” is adopted for the 'hardware safety integrity constraints”), this is even a requirement. This paper presents how to estimate the failure rates from field feedback with confidence intervals, depending if the failures are detected on-line (called 'detected failures', e.g. by automatic diagnostic tests) or only revealed by proof tests (called 'undetected failures'). Examples show that for the same duration and number of failures observed, the estimated failure rates are basically higher for “undetected failures” because, in this case, the duration observed includes intervals of time where it is unknown that the elements have failed. This points out the need of using a proper approach for failure rates estimation, especially for failures that are not detected on-line. Then, this paper proposes an approach to use the estimated failure rates, with their uncertainties, for PFDavg and PFH assessment with upper confidence bounds, in accordance with IEC 61508 and IEC 61511 requirements. Examples finally show that the highest SIL that can be claimed for a safety function can be limited by the 90% upper confidence bound of PFDavg or PFH. The requirements of the IEC 61508 and IEC 61511 relating to the data collection and analysis should therefore be properly considered for the study of all safety-related systems. - Highlights: • This paper deals with requirements of the IEC 61508 and IEC 61511 for using field feedback to estimate failure rates of safety-related systems. • This paper presents how to estimate the failure rates from field feedback with confidence intervals for failures that are detected on-line. • This paper presents how to estimate the failure rates from field feedback with confidence intervals for failures that are only revealed by

  19. Field Test of the World Health Organization Multi-Professional Patient Safety Curriculum Guide

    Science.gov (United States)

    Farley, Donna; Zheng, Hao; Rousi, Eirini; Leotsakos, Agnès

    2015-01-01

    Introduction Although the importance of training in patient safety has been acknowledged for over a decade, it remains under-utilized and under-valued in most countries. WHO developed the Multi-professional Patient Safety Curriculum Guide to provide schools with the requirements and tools for incorporating patient safety in education. It was field tested with 12 participating schools across the six WHO regions, to assess its effectiveness for teaching patient safety to undergraduate and graduate students in a global variety of settings. Methods The evaluation used a combined prospective/retrospective design to generate formative information on the experiences of working with the Guide and summative information on the impacts of the Guide. Using stakeholder interviews and student surveys, data were gathered from each participating school at three times: the start of the field test (baseline), soon after each school started teaching, and soon after each school finished teaching. Results Stakeholders interviewed were strongly positive about the Guide, noting that it emphasized universally important patient safety topics, was culturally appropriate for their countries, and gave credibility and created a focus on patient safety at their schools. Student perceptions and attitudes regarding patient safety improved substantially during the field test, and their knowledge of the topics they were taught doubled, from 10.7% to 20.8% of correct answers on the student survey. Discussion This evaluation documented the effectiveness of the Curriculum Guide, for both ease of use by schools and its impacts on improving the patient safety knowledge of healthcare students. WHO should be well positioned to refine the contents of the Guide and move forward in encouraging broader use of the Guide globally for teaching patient safety. PMID:26406893

  20. Field Test of the World Health Organization Multi-Professional Patient Safety Curriculum Guide.

    Science.gov (United States)

    Farley, Donna; Zheng, Hao; Rousi, Eirini; Leotsakos, Agnès

    2015-01-01

    Although the importance of training in patient safety has been acknowledged for over a decade, it remains under-utilized and under-valued in most countries. WHO developed the Multi-professional Patient Safety Curriculum Guide to provide schools with the requirements and tools for incorporating patient safety in education. It was field tested with 12 participating schools across the six WHO regions, to assess its effectiveness for teaching patient safety to undergraduate and graduate students in a global variety of settings. The evaluation used a combined prospective/retrospective design to generate formative information on the experiences of working with the Guide and summative information on the impacts of the Guide. Using stakeholder interviews and student surveys, data were gathered from each participating school at three times: the start of the field test (baseline), soon after each school started teaching, and soon after each school finished teaching. Stakeholders interviewed were strongly positive about the Guide, noting that it emphasized universally important patient safety topics, was culturally appropriate for their countries, and gave credibility and created a focus on patient safety at their schools. Student perceptions and attitudes regarding patient safety improved substantially during the field test, and their knowledge of the topics they were taught doubled, from 10.7% to 20.8% of correct answers on the student survey. This evaluation documented the effectiveness of the Curriculum Guide, for both ease of use by schools and its impacts on improving the patient safety knowledge of healthcare students. WHO should be well positioned to refine the contents of the Guide and move forward in encouraging broader use of the Guide globally for teaching patient safety.

  1. RISMC advanced safety analysis project plan: FY2015 - FY2019. Light Water Reactor Sustainability Program

    International Nuclear Information System (INIS)

    Szilard, Ronaldo H; Smith, Curtis L; Youngblood, Robert

    2014-01-01

    In this report, the Advanced Safety Analysis Program (ASAP) objectives and value proposition is described. ASAP focuses on modernization of nuclear power safety analysis (tools, methods and data); implementing state-of-the-art modeling techniques (which include, for example, enabling incorporation of more detailed physics as they become available); taking advantage of modern computing hardware; and combining probabilistic and mechanistic analyses to enable a risk informed safety analysis process. The modernized tools will maintain the current high level of safety in our nuclear power plant fleet, while providing an improved understanding of safety margins and the critical parameters that affect them. Thus, the set of tools will provide information to inform decisions on plant modifications, refurbishments, and surveillance programs, while improving economics. The set of tools will also benefit the design of new reactors, enhancing safety per unit cost of a nuclear plant. As part of the discussion, we have identified three sets of stakeholders, the nuclear industry, the Department of Energy (DOE), and associated oversight organizations. These three groups would benefit from ASAP in different ways. For example, within the DOE complex, the possible applications that are seen include the safety of experimental reactors, facility life extension, safety-by-design in future generation advanced reactors, and managing security for the storage of nuclear material. This report provides information in five areas: (1) A value proposition (@@@why is this important?@@@) that will make the case for stakeholder's use of the ASAP research and development (R&D) products; (2) An identification of likely end users and pathway to adoption of enhanced tools by the end-users; (3) A proposed set of practical and achievable @@use case@@@ demonstrations; (4) A proposed plan to address ASAP verification and validation (V&V) needs; and (5) A proposed schedule for the multi-year ASAP.

  2. Balanced Design of Safety Systems of CAREM Advanced Reactor

    International Nuclear Information System (INIS)

    Grinblat, Pablo; Gimenez, Marcelo; Schlamp, Miguel

    2003-01-01

    Nuclear Power Plants must meet the performance that the market and the population demand in order to be part of the electricity supply industry.It is related mainly with the results of reactor's economy and safety.New advances in the methodology developed for reactor economic optimization analyzing its safety at an early engineering stage, aiming at balancing these important features of the design, are presented in this work.In particular, the coupling that appears when dimensioning the Emergency Injection System, the Residual Heat Removal System and the containment height of CAREM reactor is described.The new models appended to the computer code that embodies the methodology to balance de designs are shown.Finally the results obtained with the optimizations when applying it are presented.Furthermore, a criterion to establish the maximal diameter for acceptable breaks in RPV's penetrations arises from this work.The application of the methodology and the computer code developed turns out to prove the advantages they provide to reactor design so that the plants are properly balanced and optimized

  3. Safety features and research needs of westinghouse advanced reactors

    International Nuclear Information System (INIS)

    Carelli, M.D.; Winters, J.W.; Cummins, W.E.; Bruschi, H.J.

    2002-01-01

    The three Westinghouse advanced reactors - AP600, AP1000 and IRIS - are at different levels of readiness. AP600 has received a Design Certification, its larger size version AP1000 is currently in the design certification process and IRIS has just completed its conceptual design and will initiate soon a licensing pre-application. The safety features of the passive designs AP600/AP1000 are presented, followed by the features of the more revolutionary IRIS, a small size modular integral reactor. A discussion of the IRIS safety by design approach is given. The AP600/AP1000 design certification is backed by completed testing and development which is summarized, together with a research program currently in progress which will extend AP600 severe accident test data to AP1000 conditions. While IRIS will of course rely on applicable AP600/1000 data, a very extensive testing campaign is being planned to address all the unique aspects of its design. Finally, IRIS plans to use a risk-informed approach in its licensing process. (authors)

  4. Advancement of Tools Supporting Improvement of Work Safety in Selected Industrial Company

    Science.gov (United States)

    Gembalska-Kwiecień, Anna

    2018-03-01

    In the presented article, the advancement of tools to improve the safety of work in the researched industrial company was taken into consideration. Attention was paid to the skillful analysis of the working environment, which includes the available technologies, work organization and human capital. These factors determine the development of the best prevention activities to minimize the number of accidents.

  5. APROSYS: future safety needs actions today

    NARCIS (Netherlands)

    Schijndel-de Nooij, M. van

    2008-01-01

    Secondary (or passive) safety constitutes one of the most important strategies to reduce the traffic trauma problem. The European R&D needs in this field are partially dealt with in a large European co-operative R&D project called APROSYS (Advanced Protection Systems) supported by the European

  6. Seismic PSA implementation standards by AESJ and the utilization of the advanced safety examination guideline for seismic design for nuclear power plant

    International Nuclear Information System (INIS)

    Ebisawa, Katsumi; Hibino, Kenta

    2008-01-01

    The Advanced Safety Examination Guideline for Seismic Design for Nuclear Power Plant (the advanced safety examination guideline) was worked out on September 19, 2006. In this paper, a summary of the method of probability theory in the advanced safety examination guideline and the Seismic PSA Implementation Standards is stated. On utilization of the probability theory for the advanced safety examination guideline, the uncertainty resulting from the process of the decision of the basic design earthquake ground motion (Ss) is stated to be considered using the proper method. The references of the extra probability for evaluation of earthquake hazard and combination of the working load and the earthquake load are stated. Definition, evaluation method and effort to lower the 'residual risks', and relation between the residual risks and the extra probability of Ss are described. A summary of the earthquake-resistant design for nuclear power facilities is explained by the old guideline. (S.Y.)

  7. Improvement And Development Of The Motivation System In The Occupational And Industrial Safety Field

    Science.gov (United States)

    Pavlov, Arkhip; Gavrilov, Dmitrij

    2017-11-01

    This paper discusses one of the main problems in labour and industrial management in the occupational and industrial safety field - motivation to work safely. The problem is complex and should be solved by a set of measures, where the assignment of responsibility to employees for the results of their work is absent, including in the field of labour protection and industrial safety. In accordance with the obligatory management principles, employees' work resolves to the strict implementation of the actions prescribed by the regulations. The responsibility for the negative result rests with the person who enacted or instructs employees. Thus, the employee is practically exempt from responsibility for the final result. One of the possible solutions to this problem is to put an assignment of responsibility on the employees for the results of their activities also in the occupational and industrial safety field. This is illustrated by the experience of other states, particularly of Australia. In conclusion suggestions for improvement and development of the motivation system in the field of occupational and industrial safety.

  8. Improvement And Development Of The Motivation System In The Occupational And Industrial Safety Field

    Directory of Open Access Journals (Sweden)

    Pavlov Arkhip

    2017-01-01

    Full Text Available This paper discusses one of the main problems in labour and industrial management in the occupational and industrial safety field - motivation to work safely. The problem is complex and should be solved by a set of measures, where the assignment of responsibility to employees for the results of their work is absent, including in the field of labour protection and industrial safety. In accordance with the obligatory management principles, employees' work resolves to the strict implementation of the actions prescribed by the regulations. The responsibility for the negative result rests with the person who enacted or instructs employees. Thus, the employee is practically exempt from responsibility for the final result. One of the possible solutions to this problem is to put an assignment of responsibility on the employees for the results of their activities also in the occupational and industrial safety field. This is illustrated by the experience of other states, particularly of Australia. In conclusion suggestions for improvement and development of the motivation system in the field of occupational and industrial safety.

  9. Advances in safety related maintenance

    International Nuclear Information System (INIS)

    2000-03-01

    The maintenance of systems, structures and components in nuclear power plants (NPPs) plays an important role in assuring their safe and reliable operation. Worldwide, NPP maintenance managers are seeking to reduce overall maintenance costs while maintaining or improving the levels of safety and reliability. Thus, the issue of NPP maintenance is one of the most challenging aspects of nuclear power generation. There is a direct relation between safety and maintenance. While maintenance alone (apart from modifications) will not make a plant safer than its original design, deficient maintenance may result in either an increased number of transients and challenges to safety systems or reduced reliability and availability of safety systems. The confidence that NPP structures, systems and components will function as designed is ultimately based on programmes which monitor both their reliability and availability to perform their intended safety function. Because of this, approaches to monitor the effectiveness of maintenance are also necessary. An effective maintenance programme ensures that there is a balance between the improvement in component reliability to be achieved and the loss of component function due to maintenance downtime. This implies that the safety level of an NPP should not be adversely affected by maintenance performed during operation. The nuclear industry widely acknowledges the importance of maintenance in NPP safety and operation and therefore devotes great efforts to develop techniques, methods and tools to aid in maintenance planning, follow-up and optimization, and in assuring the effectiveness of maintenance

  10. Pivotal ERIVANCE basal cell carcinoma (BCC) study: 12-month update of efficacy and safety of vismodegib in advanced BCC.

    Science.gov (United States)

    Sekulic, Aleksandar; Migden, Michael R; Lewis, Karl; Hainsworth, John D; Solomon, James A; Yoo, Simon; Arron, Sarah T; Friedlander, Philip A; Marmur, Ellen; Rudin, Charles M; Chang, Anne Lynn S; Dirix, Luc; Hou, Jeannie; Yue, Huibin; Hauschild, Axel

    2015-06-01

    Primary analysis from the pivotal ERIVANCE BCC study resulted in approval of vismodegib, a Hedgehog pathway inhibitor indicated for treatment of adults with metastatic or locally advanced basal cell carcinoma (BCC) that has recurred after surgery or for patients who are not candidates for surgery or radiation. An efficacy and safety analysis was conducted 12 months after primary analysis. This was a multinational, multicenter, nonrandomized, 2-cohort study in patients with measurable and histologically confirmed locally advanced or metastatic BCC taking oral vismodegib (150 mg/d). Primary outcome measure was objective response rate (complete and partial responses) assessed by independent review facility. After 12 months of additional follow-up, median duration of exposure to vismodegib was 12.9 months. Objective response rate increased from 30.3% to 33.3% in patients with metastatic disease, and from 42.9% to 47.6% in patients with the locally advanced form. Median duration of response in patients with locally advanced BCC increased from 7.6 to 9.5 months. No new safety signals emerged with extended treatment duration. Limitations include low prevalence of advanced BCC and challenges of designing a study with heterogenous manifestations. The 12-month update of the study confirms the efficacy and safety of vismodegib in management of advanced BCC. Copyright © 2015 American Academy of Dermatology, Inc. Published by Elsevier Inc. All rights reserved.

  11. Editorial: Advances in healthcare provider and patient training to improve the quality and safety of patient care

    OpenAIRE

    Elizabeth M. Borycki

    2015-01-01

    This special issue of the Knowledge Management & E-Learning: An International Journal is dedicated to describing “Advances in Healthcare Provider and Patient Training to Improve the Quality and Safety of Patient Care.” Patient safety is an important and fundamental requirement of ensuring the quality of patient care. Training and education has been identified as a key to improving healthcare provider patient safety competencies especially when working with new technologies such as electronic ...

  12. On the Use of Safety Certification Practices in Autonomous Field Robot Software Development

    DEFF Research Database (Denmark)

    Mogensen, Johann Thor Ingibergsson; Schultz, Ulrik Pagh; Kuhrmann, Marco

    2015-01-01

    reactions or performance in malfunctioning systems, and influence industry regarding software development and project management. However, academia seemingly did not reach the same degree of utilisation of standards. This paper presents the findings from a systematic mapping study in which we study...... the state-of-the-art in developing software for safety-critical software for autonomous field robots. The purpose of the study is to identify practices used for the development of autonomous field robots and how these practices relate to available safety standards. Our findings from reviewing 49 papers show...... on the quest for suitable approaches to develop safety-critical software, awaiting appropriate standards for this support....

  13. Advanced Test Reactor (ATR) Facility 10CFR830 Safety Basis Related to Facility Experiments

    International Nuclear Information System (INIS)

    Tomberlin, T.A.

    2002-01-01

    The Idaho National Engineering and Environmental Laboratory (INEEL) Advanced Test Reactor (ATR), a DOE Category A reactor, was designed to provide an irradiation test environment for conducting a variety of experiments. The ATR Safety Analysis Report, determined by DOE to meet the requirements of 10 CFR 830, Subpart B, provides versatility in types of experiments that may be conducted. This paper addresses two general types of experiments in the ATR facility and how safety analyses for experiments are related to the ATR safety basis. One type of experiment is more routine and generally represents greater risks; therefore this type of experiment is addressed with more detail in the safety basis. This allows individual safety analyses for these experiments to be more routine and repetitive. The second type of experiment is less defined and is permitted under more general controls. Therefore, individual safety analyses for the second type of experiment tend to be more unique from experiment to experiment. Experiments are also discussed relative to ''major modifications'' and DOE-STD-1027-92. Application of the USQ process to ATR experiments is also discussed

  14. Advances in methods and applications of reliability and safety analysis

    International Nuclear Information System (INIS)

    Fieandt, J.; Hossi, H.; Laakso, K.; Lyytikaeinen, A.; Niemelae, I.; Pulkkinen, U.; Pulli, T.

    1986-01-01

    The know-how of the reliability and safety design and analysis techniques of Vtt has been established over several years in analyzing the reliability in the Finnish nuclear power plants Loviisa and Olkiluoto. This experience has been later on applied and developed to be used in the process industry, conventional power industry, automation and electronics. VTT develops and transfers methods and tools for reliability and safety analysis to the private and public sectors. The technology transfer takes place in joint development projects with potential users. Several computer-aided methods, such as RELVEC for reliability modelling and analysis, have been developed. The tool developed are today used by major Finnish companies in the fields of automation, nuclear power, shipbuilding and electronics. Development of computer-aided and other methods needed in analysis of operating experience, reliability or safety is further going on in a number of research and development projects

  15. Safety design features for current UK advanced gas-cooled reactors

    Energy Technology Data Exchange (ETDEWEB)

    Yellowlees, J. M.; Cobb, E. C. [Nuclear Power Co. (Risley) Ltd. (UK)

    1981-01-15

    The nuclear power stations planned for Heysham II and Torness will each have twin 660 MW(e) Advanced Gas-cooled Reactors (AGR) based on the design of those which have been operating at Hinkley Point 'B' and Hunterston 'B' since 1976. This paper has described the way in which the shutdown and cooling systems for the Heysham II and Torness AGRs have been selected in order to meet current UK safety requirements. Fault tree analyses have been used to identify the credible fault sequences, the probabilities of which have been calculated. By this means the relative importance of the various protective systems has been established and redundancy and reliability requirements identified. This systematic approach has led to a balanced design giving protection over the complete spectrum of fault sequences. Current safety requirements for thermal reactors in the UK and particular requirements in the design of the Heysham II and Torness reactors are discussed.

  16. Safety design features for current UK advanced gas-cooled reactors

    International Nuclear Information System (INIS)

    Yellowlees, J.M.; Cobb, E.C.

    1981-01-01

    The nuclear power stations planned for Heysham II and Torness will each have twin 660 MW(e) Advanced Gas-cooled Reactors (AGR) based on the design of those which have been operating at Hinkley Point 'B' and Hunterston 'B' since 1976. This paper has described the way in which the shutdown and cooling systems for the Heysham II and Torness AGRs have been selected in order to meet current UK safety requirements. Fault tree analyses have been used to identify the credible fault sequences, the probabilities of which have been calculated. By this means the relative importance of the various protective systems has been established and redundancy and reliability requirements identified. This systematic approach has led to a balanced design giving protection over the complete spectrum of fault sequences. Current safety requirements for thermal reactors in the UK and particular requirements in the design of the Heysham II and Torness reactors are discussed

  17. Damped time advance methods for particles and EM fields

    International Nuclear Information System (INIS)

    Friedman, A.; Ambrosiano, J.J.; Boyd, J.K.; Brandon, S.T.; Nielsen, D.E. Jr.; Rambo, P.W.

    1990-01-01

    Recent developments in the application of damped time advance methods to plasma simulations include the synthesis of implicit and explicit ''adjustably damped'' second order accurate methods for particle motion and electromagnetic field propagation. This paper discusses this method

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

    International Nuclear Information System (INIS)

    Monteleone, S.

    1994-04-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1994-04-01

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

  20. Safety related terms for advanced nuclear plants; Terminos relacionados con la seguridad para centrales nucleares avanzadas

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-12-01

    The terms considered in this document are in widespread current use without a universal consensus as to their meaning. Other safety related terms are already defined in national or international codes and standards as well as in IAEA's Nuclear Safety Standards Series. Most of the terms in those codes and standards have been defined and used for regulatory purposes, generally for application to present reactor designs. There is no intention to duplicate the description of such regulatory terms here, but only to clarify the terms used for advanced nuclear plants. The following terms are described in this paper: Inherent safety characteristics, passive component, active component, passive systems, active system, fail-safe, grace period, foolproof, fault-/error-tolerant, simplified safety system, transparent safety.

  1. Safety Design Strategy for the Advanced Test Reactor Emergency Firewater Injection System Replacement Project

    International Nuclear Information System (INIS)

    Duckwitz, Noel

    2011-01-01

    In accordance with the requirements of U.S. Department of Energy (DOE) Order 413.3B, 'Program and Project Management for the Acquisition of Capital Assets,' safety must be integrated into the design process for new or major modifications to DOE Hazard Category 1, 2, and 3 nuclear facilities. The intended purpose of this requirement involves the handling of hazardous materials, both radiological and chemical, in a way that provides adequate protection to the public, workers, and the environment. Requirements provided in DOE Order 413.3B and DOE Order 420.1B, 'Facility Safety,' and the expectations of DOE-STD-1189-2008, 'Integration of Safety into the Design Process,' provide for identification of hazards early in the project and use of an integrated team approach to design safety into the facility. This safety design strategy provides the basic safety-in-design principles and concepts that will be used for the Advanced Test Reactor Reliability Sustainment Project. While this project does not introduce new hazards to the ATR, it has the potential for significant impacts to safety-related systems, structures, and components that are credited in the ATR safety basis and are being replaced. Thus the project has been determined to meet the definition of a major modification and is being managed accordingly.

  2. Safety issues and updates under MR environments

    Energy Technology Data Exchange (ETDEWEB)

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

    2017-04-15

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

  3. Perspectives of expert systems in the field of reactor safety

    International Nuclear Information System (INIS)

    Bastl, W.

    1989-01-01

    The furure potential of expert systems is based on the following factors: the efficient storage of information in the knowledge basis, the efficient use of comprehensive information bases, the interactive approach, the rapid production of prototypes. The main problems which are encountered at present relate to the input of knowledge derived from experience, the qualification of the contents of the knowledge bases and to the interfacing to technical processes, as real time work is required in such cases. However, the practical use of expert systems in reactor safety is expected to make considerable progress. The following preferred fields should be mentioned: knowledge bases and analysis tools for safety investigations, diagnostic and practising systems for safe operation and, above all in the field of accident management, trainers, in-situ guiding systems or information systems in supraregional guiding centers. (orig./DG) [de

  4. Progress of nuclear safety research-2004

    International Nuclear Information System (INIS)

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

    2005-03-01

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

  5. SWR 1000: an advanced boiling water reactor with passive safety features

    International Nuclear Information System (INIS)

    Brettschuh, W.

    1999-01-01

    The SWR 1000, an advanced BWR, is being developed by Siemens under contract from Germany's electric utilities and with the support of European partners. The project is currently in the basic design phase to be concluded in mid-1999 with the release of a site-independent safety report and costing analysis. The development goals for the project encompass competitive costs, use of passive safety systems to further reduce probabilities of occurrence of severe accidents, assured control of accidents so no emergency response actions for evacuation of the local population are needed, simplification of plant systems based on operator experience, and planning and design based on German codes, standards and specifications put forward by the Franco-German Reactor Safety Commission for future nuclear power plants equipped with PWRs, as well as IAEA specifications and the European Utility Requirements. These goals led to a plant concept with a low power density core, with large water inventories stored above the core inside the reactor pressure vessel, in the pressure suppression pool, and in other locations. All accident situations arising from power operation can be controlled by passive safety features without rise in core temperature and with a grace period of more than three days. In addition, postulated core melt is controlled by passive equipment. All new passive systems have been successfully tested for function and performance using large-scale components in experimental testing facilities at PSI in Switzerland and at the Juelich Research Centre in Germany. In addition to improvements of the safety systems, the plant's operating systems have been simplified based on operating experience. The design's safety concept, simplified operating systems and 48 months construction time yield favourable plant construction costs. The level of concept maturity required to begin offering the SWR 1000 on the power generation market is anticipated to be reached, as planned in the year

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

    International Nuclear Information System (INIS)

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

    1990-01-01

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

  7. The Impact of Advanced Age on Driving Safety in Adults with Medical Conditions.

    Science.gov (United States)

    Moon, Sanghee; Ranchet, Maud; Akinwuntan, Abiodun Emmanuel; Tant, Mark; Carr, David Brian; Raji, Mukaila Ajiboye; Devos, Hannes

    2018-01-01

    Adults aged 85 and older, often referred to as the oldest-old, are the fastest-growing segment of the population. The rapidly increasing number of older adults with chronic and multiple medical conditions poses challenges regarding their driving safety. To investigate the effect of advanced age on driving safety in drivers with medical conditions. We categorized 3,425 drivers with preexisting medical conditions into four age groups: middle-aged (55-64 years, n = 1,386), young-old (65-74 years, n = 1,013), old-old (75-84 years, n = 803), or oldest-old (85 years and older, n = 223). All underwent a formal driving evaluation. The outcome measures included fitness to drive recommendation by the referring physician, comprehensive fitness to drive decision from an official driving evaluation center, history of motor vehicle crashes (MVCs), and history of traffic violations. The oldest-old reported more cardiopulmonary and visual conditions, but less neurological conditions than the old-old. Compared to the middle-aged, the oldest-old were more likely to be considered unfit to drive by the referring physicians (odds ratio [OR] = 4.47, 95% confidence interval [CI] 2.20-9.10) and by the official driving evaluation center (OR = 2.74, 95% CI 1.87-4.03). The oldest-old reported more MVCs (OR = 2.79, 95% CI 1.88-4.12) compared to the middle-aged. Advanced age adversely affected driving safety outcomes. The oldest-old are a unique age group with medical conditions known to interfere with safe driving. Driving safety strategies should particularly target the oldest-old since they are the fastest-growing group and their increased frailty is associated with severe or fatal injuries due to MVCs. © 2018 S. Karger AG, Basel.

  8. International Cooperation of the Republic of Croatia in the Field of Nuclear Safety

    International Nuclear Information System (INIS)

    Novosel, N.; Rosandic, L.

    2010-01-01

    International cooperation of the Republic of Croatia in the field of nuclear safety can be divided in two parts - political part, for which the Ministry of Foreign Affairs and European Integration is responsible, and technical part, for which the State Office for Nuclear Safety is responsible, in cooperation with other state administration bodies, where applicable. According to the Nuclear Safety Act (OG 73/2003) the State Office for Nuclear Safety: 'coordinates technical cooperation with the International Atomic Energy Agency for all participants from the Republic of Croatia'; 'fulfills the obligations which the Republic of Croatia has assumed through international conventions and bilateral agreements concerning nuclear safety and the application of protective measures aimed at the non-proliferation of nuclear weapons' and 'cooperates with international organizations and associations in the area of nuclear safety, and appoints its own expert representatives to take part in the work of such organizations and associations or to monitor their work'. In this paper various aspects of the technical cooperation with the International Atomic Energy Agency, as well as international conventions and bilateral agreements in the field of nuclear safety, will be presented. Also, cooperation with other international organizations and associations in the nuclear area, such as Nuclear Suppliers Group, Zangger Committee, Wassenaar Arrangement, Comprehensive Nuclear-Test-Ban Treaty Organization, Euratom and certain civil expert groups of NATO, will be described.(author).

  9. System safety education focused on flight safety

    Science.gov (United States)

    Holt, E.

    1971-01-01

    The measures necessary for achieving higher levels of system safety are analyzed with an eye toward maintaining the combat capability of the Air Force. Several education courses were provided for personnel involved in safety management. Data include: (1) Flight Safety Officer Course, (2) Advanced Safety Program Management, (3) Fundamentals of System Safety, and (4) Quantitative Methods of Safety Analysis.

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

    International Nuclear Information System (INIS)

    2001-10-01

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

  11. The safety designs for the TITAN reversed-field pinch reactor study

    International Nuclear Information System (INIS)

    Wong, C.P.C.; Cheng, E.T.; Creedon, R.L.; Hoot, C.G.; Schultz, K.R.; Grotz, S.P.; Blanchard, J.; Sharafat, S.; Najmabadi, F.

    1989-01-01

    TITAN is a study to investigate the potential of the reversed-field pinch concept as a compact, high-power density energy system. Two reactor concepts were developed, a self-cooled lithium design with vanadium structure and an aqueous solution loop-in-pool design, both operating at 18 MW/m 2 . The key safety features of the TITAN-I lithium-vanadium blanket design are in material selection, fusion power core configuration selection, lithium piping connections, and passive lithium drain tank system. Based on these safety features and results from accident evaluation, TITAN-I can at least be rated at a level 3 of safety assurance. For the TITAN-II aqueous loop-in-pool design, the key passive feature is the complete submersion of the fusion power core and the corresponding primary coolant loop system into a pool of low temperature water. Based on this key safety design feature, the TITAN-II design can be rated at a level 2 of safety assurance. (orig.)

  12. The safety designs for the TITAN reversed-field pinch reactor study

    International Nuclear Information System (INIS)

    Wong, C.P.C.; Cheng, E.T.; Creedon, R.L.; Hoot, C.G.; Schultz, K.R.; Grotz, S.P.; Blanchard, J.P.; Sharafat, S.; Najmabadi, F.

    1988-01-01

    TITAN is a study to investigate the potential of the reversed-field pinch concept as a compact, high-power density energy system. Two reactor concepts were developed, a self-cooled lithium design with vanadium structure and an aqueous solution loop-in-pool design, both operating at 18 MW/m 2 . The key safety features of the TITAN-I lithium-vanadium blanket design are in material selection, fusion power core configuration selection, lithium piping connections and passive lithium drain tank system. Based on these safety features and results from accident evaluation, TITAN-I can at least be rated as level 3 of safety assurance. For the TITAN-II aqueous loop-in-pool design, the key passive feature is the complete submersion of the fusion power core and the corresponding primary coolant loop system into a pool of low temperature water. Based on this key safety design feature, the TITAN-II design can be rated as level 2 of safety assurance. 7 refs., 2 figs

  13. Proceedings of the GCNEP-IAEA course on natural circulation phenomena and passive safety systems in advanced water cooled reactors. V.1

    International Nuclear Information System (INIS)

    2014-01-01

    The current status and prospect, economics, advanced designs and applications of reactors in operation and construction, safety of advanced water cooled reactors is discussed. Papers relevant to INIS are indexed separately

  14. Proceedings of the GCNEP-IAEA course on natural circulation phenomena and passive safety systems in advanced water cooled reactors. V.2

    International Nuclear Information System (INIS)

    2014-01-01

    The current status and prospect, economics, advanced designs and applications of reactors in operation and construction, safety of advanced water cooled reactors is discussed. Papers relevant to INIS are indexed separately

  15. Relevance of passive safety testing at the fast flux test facility to advanced liquid metal reactors - 5127

    International Nuclear Information System (INIS)

    Wootan, D.W.; Omberg, R.P.

    2015-01-01

    Significant cost and safety improvements can be realized in advanced liquid metal reactor (LMR) designs by emphasizing inherent or passive safety through crediting the beneficial reactivity feedbacks associated with core and structural movement. This passive safety approach was adopted for the Fast Flux Test Facility (FFTF), and an experimental program was conducted to characterize the structural reactivity feedback. Testing at the Rapsodie and EBR-II reactors had demonstrated the beneficial effect of reactivity feedback caused by changes in fuel temperature and core geometry mechanisms in a liquid metal fast reactor in a holistic sense. The FFTF passive safety testing program was developed to examine how specific design elements influenced dynamic reactivity feedback in response to a reactivity input and to demonstrate the scalability of reactivity feedback results from smaller cores like Rapsodie and EBR-II to reactor cores that were more prototypic in scale to reactors of current interest. The U.S. Department of Energy, Office of Nuclear Energy Advanced Reactor Technology program is in the process of preserving, protecting, securing, and placing in electronic format information and data from the FFTF, including the core configurations and data collected during the passive safety tests. Evaluation of these actual test data could provide insight to improve analytical methods which may be used to support future licensing applications for LMRs. (authors)

  16. Near-field performance of the advanced cold process canister

    International Nuclear Information System (INIS)

    Werme, L.

    1991-12-01

    A near-field performance evaluation of an advanced cold process canister for spent fuel disposal has been performed jointly by TVO, Finland and SKB, Sweden. The canister consists of a steel canister as a load bearing element, with an outer corrosion shield of copper. In the analysis, as well internal (ie corrosion processes from the inside of the canister) as external processes (mechanical and chemical) have been considered both prior to and after canister breach. The major conclusions for the evaluation are: Internal processes cannot cause the canister breach under foreseen conditions, ie local-iced corrosion for the steel or copper canisters can be dismissed as a failure mechanism; The evaluation of the effects of processed outside the canister indicate that there is no rapid mechanism to endanger the integrity of the canister. Consequently the service life of the canister will be several million years. For completeness also evaluation of post-failure behaviour was carried out. Analyses were focussed on low probability phenomena from faults in canisters. Some items were identified where further research is justified in order to increase knowledge of the phenomena and thus strengthen the confidence of safety margins. However, it can be concluded that the risks of these scenarios can be judged to be acceptable. This is due to the fact that firstly, the probability of occurrence of most of these scenarios can be controlled to a large extent through technical measures. Secondly, these analyses indicated that the consequences would not be severe

  17. Obtaining laser safety at a synchrotron radiation user facility: The Advanced Light Source

    International Nuclear Information System (INIS)

    Barat, K.

    1996-01-01

    The Advanced Light Source (ALS) is a US national facility for scientific research and development located at the Lawrence Berkeley National Laboratory in California. The ALS delivers the world's brightest synchrotron radiation in the far ultraviolet and soft X-ray regions of the spectrum. As a user facility it is available to researchers from industry, academia, and laboratories from around the world. Subsequently, a wide range of safety concerns become involved. This article relates not only to synchrotron facilities but to any user facility. A growing number of US centers are attracting organizations and individuals to use the equipment on site, for a fee. This includes synchrotron radiation and/or free electron facilities, specialty research centers, and laser job shops. Personnel coming to such a facility bring with them a broad spectrum of safety cultures. Upon entering, the guests must accommodate to the host facility safety procedures. This article describes a successful method to deal with that responsibility

  18. Probabilistic methods in the field of reactor safety in Germany

    Energy Technology Data Exchange (ETDEWEB)

    Birkhofer, A [Technische Univ. Muenchen (Germany, F.R.). Lehrstuhl fuer Reaktordynamik und Reaktorsicherheit

    1979-01-01

    The present status and future prospects in Germany of reliability, as well as risk analysis, in the field of reactor safety are examined. The development of analytical methods with respect to the available data base is reviewed with consideration of the roles of reliability codes, component data, common mode failures, human influence, structural analysis and process computers. Some examples of the application of probability assessments are discussed and the extension of reliability analysis beyond the loss-of-coolant accident is considered. In the case of risk analysis, the object is to determine not only the probability of failure of systems but also the probability and extent of possible consequences. Some risk studies under investigation in Germany and the methodology of risk analysis are discussed. Reliability and risk analysis are involved to an increasing extent in safety research and licensing procedures and their influence in other fields such as the public perception of risk is also discussed.

  19. 1. Vienna central european seminar on particle physics and quantum field theory. Advances in quantum field theory. Program

    International Nuclear Information System (INIS)

    Hueffel, H.

    2004-01-01

    The new seminar series 'Vienna central European seminar on particle physics and quantum field theory' has been created 2004 and is intended to provide interactions between leading researchers and junior physicists. This year 'Advances in quantum field theory' has been chosen as subject and is centred on field theoretic aspects of string dualities. The lectures mainly focus on these aspects of string dualities. Further lectures regarding supersymmetric gauge theories, quantum gravity and noncommutative field theory are presented. The vast field of research concerning string dualities justifies special attention to their effects on field theory. (author)

  20. Advanced concepts in particle and field theory

    CERN Document Server

    Hübsch, Tristan

    2015-01-01

    Uniting the usually distinct areas of particle physics and quantum field theory, gravity and general relativity, this expansive and comprehensive textbook of fundamental and theoretical physics describes the quest to consolidate the basic building blocks of nature, by journeying through contemporary discoveries in the field, and analysing elementary particles and their interactions. Designed for advanced undergraduates and graduate students and abounding in worked examples and detailed derivations, as well as including historical anecdotes and philosophical and methodological perspectives, this textbook provides students with a unified understanding of all matter at the fundamental level. Topics range from gauge principles, particle decay and scattering cross-sections, the Higgs mechanism and mass generation, to spacetime geometries and supersymmetry. By combining historically separate areas of study and presenting them in a logically consistent manner, students will appreciate the underlying similarities and...

  1. French safety authority projects in the field of research and test reactors

    International Nuclear Information System (INIS)

    Saint Raymond, P.; Duthe, M.; Abou Yehia, H.

    2001-01-01

    This paper gives an outline of some actions initiated by the French safety authority in the field of research and test reactors. An important action concerns the definition of the authorisation criteria for the implementation of experiments in these reactors. In particular, it is necessary to define clearly in which conditions an experiment may be authorised internally by the operating organisation or needs a formal approval by the safety authority. The practice related to the systematic safety reassessment of old facilities and the regulatory provisions associated with the decommissioning are presented after a discussion on the ageing issues. (author)

  2. Reliability prediction for the vehicles equipped with advanced driver assistance systems (ADAS and passive safety systems (PSS

    Directory of Open Access Journals (Sweden)

    Balbir S. Dhillon

    2012-10-01

    Full Text Available The human error has been reported as a major root cause in road accidents in today’s world. The human as a driver in road vehicles composed of human, mechanical and electrical components is constantly exposed to changing surroundings (e.g., road conditions, environmentwhich deteriorate the driver’s capacities leading to a potential accident. The auto industries and transportation authorities have realized that similar to other complex and safety sensitive transportation systems, the road vehicles need to rely on both advanced technologies (i.e., Advanced Driver Assistance Systems (ADAS and Passive Safety Systems (PSS (e.g.,, seatbelts, airbags in order to mitigate the risk of accidents and casualties. In this study, the advantages and disadvantages of ADAS as active safety systems as well as passive safety systems in road vehicles have been discussed. Also, this study proposes models that analyze the interactions between human as a driver and ADAS Warning and Crash Avoidance Systems and PSS in the design of vehicles. Thereafter, the mathematical models have been developed to make reliability prediction at any given time on the road transportation for vehicles equipped with ADAS and PSS. Finally, the implications of this study in the improvement of vehicle designs and prevention of casualties are discussed.

  3. Advanced Rooftop Control (ARC) Retrofit: Field-Test Results

    Energy Technology Data Exchange (ETDEWEB)

    Wang, Weimin; Katipamula, Srinivas; Ngo, Hung; Underhill, Ronald M.; Taasevigen, Danny J.; Lutes, Robert G.

    2013-07-31

    The multi-year research study was initiated to find solutions to improve packaged equipment operating efficiency in the field. Pacific Northwest National Laboratory (PNNL), with funding from the U.S. Department of Energy’s (DOE’s) Building Technologies Office (BTO) and Bonneville Power Administration (BPA) conducted this research, development and demonstration (RD&D) study. Packaged equipment with constant speed supply fans is designed to provide ventilation at the design rate at all times when the fan is operating as required by building code. Although there are a number of hours during the day when a building may not be fully occupied or the need for ventilation is lower than designed, the ventilation rate cannot be adjusted easily with a constant speed fan. Therefore, modulating the supply fan in conjunction with demand controlled ventilation (DCV) will not only reduce the coil energy but also reduce the fan energy. The objective of this multi-year research, development and demonstration project was to determine the magnitude of energy savings achievable by retrofitting existing packaged rooftop air conditioners with advanced control strategies not ordinarily used for packaged units. First, through detailed simulation analysis, it was shown that significant energy (between 24% and 35%) and cost savings (38%) from fan, cooling and heating energy consumption could be realized when packaged air conditioning units with gas furnaces are retrofitted with advanced control packages (combining multi-speed fan control, integrated economizer controls and DCV). The simulation analysis also showed significant savings for heat pumps (between 20% and 60%). The simulation analysis was followed by an extensive field test of a retrofittable advanced rooftop unit (RTU) controller.

  4. External Magnetic Field Reduction Techniques for the Advanced Stirling Radioisotope Generator

    Science.gov (United States)

    Niedra, Janis M.; Geng, Steven M.

    2013-01-01

    Linear alternators coupled to high efficiency Stirling engines are strong candidates for thermal-to-electric power conversion in space. However, the magnetic field emissions, both AC and DC, of these permanent magnet excited alternators can interfere with sensitive instrumentation onboard a spacecraft. Effective methods to mitigate the AC and DC electromagnetic interference (EMI) from solenoidal type linear alternators (like that used in the Advanced Stirling Convertor) have been developed for potential use in the Advanced Stirling Radioisotope Generator. The methods developed avoid the complexity and extra mass inherent in data extraction from multiple sensors or the use of shielding. This paper discusses these methods, and also provides experimental data obtained during breadboard testing of both AC and DC external magnetic field devices.

  5. Savannah River Site management response plan for chemical safety vulnerability field assessment. Revision 1

    International Nuclear Information System (INIS)

    Kahal, E.J.; Murphy, S.L.; Salaymeh, S.R.

    1994-09-01

    As part of the U.S. Department of Energy's (DOE) initiative to identify potential chemical safety vulnerabilities in the DOE complex, the Chemical Safety Vulnerability Core Working Group issued a field verification assessment report. While the report concluded that Savannah River Site (SRS) is moving in a positive direction, the report also identified five chemical safety vulnerabilities with broad programmatic impact that are not easily nor quickly remedied. The May 1994 SRS Management Response Plan addressed the five SRS vulnerabilities identified in the field assessment report. The SRS response plan listed observations supporting the vulnerabilities and any actions taken or planned toward resolution. Many of the observations were resolved by simple explanations, such as the existence of implementation plans for Safety Analysis Report updates. Recognizing that correcting individual observations does not suffice in remedying the vulnerabilities, a task team was assembled to address the broader programmatic issues and to recommend corrective actions

  6. High field MRI: safety and protection problems related to the installation and the management of a 4T equipment

    International Nuclear Information System (INIS)

    Russo, A.; Speranza, A.; DELIA, R.; ANTOLINI, R.; FERRARI, P.; FILIPPI, M.

    2006-01-01

    The Physics Department of Trento University (Italy), in collaboration with Bruker Biospin decided to set up a 4 T MR system for research in the neurological field as well as on the biological effects of high field MRI. Nowadays the number of similar apparatus set up in the world is very low, several of these operate in the USA, some in Australia and one in Israel. Due to the very low diffusion of these equipments and to the few knowledge today available about the biological effects by clinical application of high field MRI, the problems related to the installation of the apparatus from the safety point of view are not well standardized. Therefore, in Trento, it has been necessary to deal with many problems regarding the set up of the MRI apparatus, taking also into account the current law in Italy with respect the safety and protection in MRI applications. In the present paper the Authors show the carried out studies and analyses, in relation to the organization of the safety aspects. These studies have resulted in arranging specific guidelines for: working in controlled way; emergency procedures for the patient advanced life support; procedures for the protocol of patient protection; rules for the safety of the operators, patients and general public. The carried out analyses have mainly taken into account the danger identification and the risk evaluation. For this reason it was set up a test protocol regarding:the performing tests, the very detailed test modalities for their periodic performance and the test sequence. For the patient safety and protection it has been necessary to put care, in the first step of the survey, to the subjects in critical situations, due to: working activity, clinical history, health conditions of the patient at the moment of the examination. So it has been necessary to set up an anamnesis questionnaire for the patient, finalized to spot: (1) the patients with particular contraindications for the MR examination; (2) the patients which

  7. High field MRI: safety and protection problems related to the installation and the management of a 4T equipment

    Energy Technology Data Exchange (ETDEWEB)

    Russo, A.; Speranza, A. [National Research Council, Institute of Bioimaging and Biostructures- Dep.of Biomorphological and Functional Sciences - University Federico II, Napoli (Italy); DELIA, R. [University of Rome - Medicine and Surgery Faculty - La Sapienza Sez. Rieti (Italy); ANTOLINI, R. [University of Trento - Department of Physics, Trento (Italy); FERRARI, P. [University of Trento - Direction of Polo di Rovereto, Trento (Italy); FILIPPI, M. [University of Trento Prevention and Protection Service, Trento (Italy)

    2006-07-01

    The Physics Department of Trento University (Italy), in collaboration with Bruker Biospin decided to set up a 4 T MR system for research in the neurological field as well as on the biological effects of high field MRI. Nowadays the number of similar apparatus set up in the world is very low, several of these operate in the USA, some in Australia and one in Israel. Due to the very low diffusion of these equipments and to the few knowledge today available about the biological effects by clinical application of high field MRI, the problems related to the installation of the apparatus from the safety point of view are not well standardized. Therefore, in Trento, it has been necessary to deal with many problems regarding the set up of the MRI apparatus, taking also into account the current law in Italy with respect the safety and protection in MRI applications. In the present paper the Authors show the carried out studies and analyses, in relation to the organization of the safety aspects. These studies have resulted in arranging specific guidelines for: working in controlled way; emergency procedures for the patient advanced life support; procedures for the protocol of patient protection; rules for the safety of the operators, patients and general public. The carried out analyses have mainly taken into account the danger identification and the risk evaluation. For this reason it was set up a test protocol regarding:the performing tests, the very detailed test modalities for their periodic performance and the test sequence. For the patient safety and protection it has been necessary to put care, in the first step of the survey, to the subjects in critical situations, due to: working activity, clinical history, health conditions of the patient at the moment of the examination. So it has been necessary to set up an anamnesis questionnaire for the patient, finalized to spot: (1) the patients with particular contraindications for the MR examination; (2) the patients which

  8. NATO Advanced Study Institute on Atoms in Strong Fields

    CERN Document Server

    Clark, Charles; Nayfeh, Munir

    1990-01-01

    This book collects the lectures given at the NATO Advanced Study Institute on "Atoms in Strong Fields", which took place on the island of Kos, Greece, during the two weeks of October 9-21,1988. The designation "strong field" applies here to an external electromagnetic field that is sufficiently strong to cause highly nonlinear alterations in atomic or molecular struc­ ture and dynamics. The specific topics treated in this volume fall into two general cater­ gories, which are those for which strong field effects can be studied in detail in terrestrial laboratories: the dynamics of excited states in static or quasi-static electric and magnetic fields; and the interaction of atoms and molecules with intense laser radiation. In both areas there exist promising opportunities for research of a fundamental nature. An electric field of even a few volts per centimeter can be very strong on the atom­ ic scale, if it acts upon a weakly bound state. The study of Rydberg states with high reso­ lution laser spectroscop...

  9. A review of the safety implications of magnetic resonance imaging at field strengths of 3 Tesla and above

    International Nuclear Information System (INIS)

    Crook, Neil; Robinson, Leslie

    2009-01-01

    Rationale: Diagnostic imaging is being driven by technological developments particularly so in the field of Magnetic Resonance Imaging (MRI). Electromagnetic fields used to produce images are becoming much stronger and switched more rapidly and it is essential that safety advice remains appropriate and current. Using a systematic methodology, this review aims to identify the clinical safety implications in performing MRI at field strengths of 3 Tesla (T) and above and determine whether the current clinical safety guidelines are appropriate. Method: References were sourced from The Cochrane Library, Centre for Reviews and Dissemination Science Direct, PubMed and Google Scholar. Related websites searched included The British Institute of Radiology, Society of Radiographers, Royal College of Radiologists, The Institution of Engineering and Technology, IMRSER (Institute for Magnetic Resonance Safety, Education, and Research), MagNet (NHS PASA). References supplied in retrieved papers were also checked for potential relevance. The use of consistent search terminology and inclusion and exclusion criteria ensured quality and provided rigour to conclusions drawn. Conclusion: According to the literature retrieved, the current body of knowledge has allowed safety guidelines to be established for patient safety and these are both appropriate and valid at field strengths of 3 T.

  10. Preapplication safety evaluation report for the Sodium Advanced Fast Reactor (SAFR) liquid-metal reactor

    International Nuclear Information System (INIS)

    King, T.L.; Landry, R.R.; Throm, E.D.; Wilson, J.N.

    1991-12-01

    This safety evaluation report (SER) presents the final results of a preapplication design review for the Sodium Advanced Fast Reactor (SAFR) liquid metal reactor (Project 673). The SAFR conceptual design was submitted by the US Department of Energy (DOE) in accordance with the US Nuclear Regulatory Commission (NRC) ''Statement of Policy for the Regulation of Advanced Nuclear Power Plants'' (51 FR 24643 which provides for the early Commission review and interaction). The standard SAFR plant design consists of four identical reactor modules, referred to as ''paks,'' each with a thermal output rating of 900 MWt, coupled with four steam turbine-generator sets. The total electrical output was held to be 1400 MWe. This SER represents the NRC staff's preliminary technical evaluation of the safety features in the SAFR design. It must be recognized that final conclusions in all matters discussed in this SER require approval by the Commission. During the NRC staff review of the SAFR conceptual design, DOE terminated work on this design in September 1988. This SER documents the work done to that date and no additional work is planned for the SAFR

  11. Charged-particle beam: a safety mandate

    International Nuclear Information System (INIS)

    Young, K.C.

    1983-01-01

    The Advanced Test Accelerator (ATA) is a recent development in the field of charged particle beam research at Lawrence Livermore National Laboratory. With this experimental apparatus, researchers will characterize intense pulses of electron beams propagated through air. Inherent with the ATA concept was the potential for exposure to hazards, such as high radiation levels and hostile breathing atmospheres. The need for a comprehensive safety program was mandated; a formal system safety program was implemented during the project's conceptual phase. A project staff position was created for a safety analyst who would act as a liaison between the project staff and the safety department. Additionally, the safety analyst would be responsible for compiling various hazards analyses reports, which formed the basis of th project's Safety Analysis Report. Recommendations for safety features from the hazards analysis reports were incorporated as necessary at appropriate phases in project development rather than adding features afterwards. The safety program established for the ATA project faciliated in controlling losses and in achieving a low-level of acceptable risk

  12. Safety targets and public risk perceptions in the nuclear field - technical treadmill or institutional responses?

    International Nuclear Information System (INIS)

    Wynne, B.

    1989-01-01

    The context of our treatment of risk perceptions and safety targets is the apparently wide gap between expert judgements of 'objective risks' and public perceptions of those risks. In the nuclear field the latter appear to so multiply the objective risks as seen by the experts, as to make safety targets vastly too strict (whether for routine discharges or for large accidents), thus design extravagantly expensive on any 'rational' criteria. In recent years the nuclear industry has come to terms more with the public perceptions problem, and has accepted that it is legitimate to exercise different, more severe and costly safety standards in the nuclear field if that is what society wants, as it appears to do. Whilst retaining the conviction that this is scientifically unwarranted, the industry has therefore reconciled itself somewhat to more stringent technical safety targets. (author)

  13. The feasibility and safety of high-intensity focused ultrasound combined with low-dose external beam radiotherapy as supplemental therapy for advanced prostate cancer following hormonal therapy.

    Science.gov (United States)

    Wu, Rui-Yi; Wang, Guo-Min; Xu, Lei; Zhang, Bo-Heng; Xu, Ye-Qing; Zeng, Zhao-Chong; Chen, Bing

    2011-05-01

    The aim of this study was to investigate the feasibility and safety of high-intensity focused ultrasound (HIFU) combined with (+) low-dose external beam radiotherapy (LRT) as supplemental therapy for advanced prostate cancer (PCa) following hormonal therapy (HT). Our definition of HIFU+LRT refers to treating primary tumour lesions with HIFU in place of reduced field boost irradiation to the prostate, while retaining four-field box irradiation to the pelvis in conventional-dose external beam radiotherapy (CRT). We performed a prospective, controlled and non-randomized study on 120 patients with advanced PCa after HT who received HIFU, CRT, HIFU+LRT and HT alone, respectively. CT/MR imaging showed the primary tumours and pelvic lymph node metastases visibly shrank or even disappeared after HIFU+LRT treatment. There were significant differences among four groups with regard to overall survival (OS) and disease-specific survival (DSS) curves (P = 0.018 and 0.015). Further comparison between each pair of groups suggested that the long-term DSS of the HIFU+LRT group was higher than those of the other three groups, but there was no significant difference between the HIFU+LRT group and the CRT group. Multivariable Cox's proportional hazard model showed that both HIFU+LRT and CRT were independently associated with DSS (P = 0.001 and 0.035) and had protective effects with regard to the risk of death. Compared with CRT, HIFU+LRT significantly decreased incidences of radiation-related late gastrointestinal (GI) and genitourinary (GU) toxicity grade ≥ II. In conclusion, long-term survival of patients with advanced PCa benefited from strengthening local control of primary tumour and regional lymph node metastases after HT. As an alternative to CRT, HIFU+LRT showed good efficacy and better safety.

  14. Safety Design Strategy for the Advanced Test Reactor Diesel Bus (E-3) and Switchgear Replacement Project

    International Nuclear Information System (INIS)

    Duckwitz, Noel

    2011-01-01

    In accordance with the requirements of U.S. Department of Energy (DOE) Order 413.3B, 'Program and Project Management for the Acquisition of Capital Assets,' safety must be integrated into the design process for new or major modifications to DOE Hazard Category 1, 2, and 3 nuclear facilities. The intended purpose of this requirement involves the handling of hazardous materials, both radiological and chemical, in a way that provides adequate protection to the public, workers, and the environment. Requirements provided in DOE Order 413.3B and DOE Order 420.1B, 'Facility Safety,' and the expectations of DOE-STD-1189-2008, 'Integration of Safety into the Design Process,' provide for identification of hazards early in the project and use of an integrated team approach to design safety into the facility. This safety design strategy provides the basic safety-in-design principles and concepts that will be used for the Advanced Test Reactor Reliability Sustainment Project. While this project does not introduce new hazards to the ATR, it has the potential for significant impacts to safety-related systems, structures, and components that are credited in the ATR safety basis and are being replaced. Thus the project has been determined to meet the definition of a major modification and is being managed accordingly.

  15. Safety evaluation report of hot cell facilities for demonstration of advanced spent fuel conditioning process

    International Nuclear Information System (INIS)

    You, Gil Sung; Choung, W. M.; Ku, J. H.; Cho, I. J.; Kook, D. H.; Park, S. W.; Bek, S. Y.; Lee, E. P.

    2004-10-01

    The advanced spent fuel conditioning process(ACP) proposed to reduce the overall volume of the PWR spent fuel and improve safety and economy of the long-term storage of spent fuel. In the next phase(2004∼2006), the hot test will be carried out for verification of the ACP in a laboratory scale. For the hot test, the hot cell facilities of α- type and auxiliary facilities are required essentially for safe handling of high radioactive materials. As the hot cell facilities for demonstration of the ACP, a existing hot cell of β- type will be refurbished to minimize construction expenditures of hot cell facility. Up to now, the detail design of hot cell facilities and process were completed, and the safety analysis was performed to substantiate secure of conservative safety. The design data were submitted for licensing which was necessary for construction and operation of hot cell facilities. The safety investigation of KINS on hot cell facilities was completed, and the license for construction and operation of hot cell facilities was acquired already from MOST. In this report, the safety analysis report submitted to KINS was summarized. And also, the questionnaires issued from KINS and answers of KAERI in process of safety investigation were described in detail

  16. Advanced nuclear power systems: Design, technology, safety and strategies for their deployment

    International Nuclear Information System (INIS)

    1994-01-01

    The objectives of the symposium were to provide high level decision makers with an overview of the discussion concerning the need for nuclear power and salient features of advanced nuclear power systems; a forum for discussing the design objectives and safety approaches for such systems and the views of regulatory bodies; a forum for identifying barriers to the deployment of these systems and for reviewing strategies to overcome these barriers; and a forum for reviewing options for international cooperation in the development and deployment of such systems. Refs, figs and tabs

  17. Front-line ownership: generating a cure mindset for patient safety.

    Science.gov (United States)

    Zimmerman, Brenda; Reason, Paige; Rykert, Liz; Gitterman, Leah; Christian, Jennifer; Gardam, Michael

    2013-01-01

    Great advances have been made in standardization and human factors engineering that have reduced variability and increased reliability in healthcare. As important as these advances are, the authors believe there is another important but largely ignored layer to the safety story in healthcare that has prevented us from progressing. In the field of infection prevention and control (IPAC), despite great attempts over several decades to improve compliance with hand hygiene, surveillance, environmental cleaning, isolation protocols and other control measures, very significant challenges remain. We believe this failure is in part due to the power gradients, often dysfunctional relationships and lack of safety mindfulness that exist in hospitals and healthcare more generally. Furthermore, safety culture requires different approaches and considerable ongoing attentiveness. If this is the case, and the authors contend in this paper that it is, then the role of the front line is much more important than many of our healthcare safety and IPAC approaches suggest. Copyright © 2013 Longwoods Publishing.

  18. Report of the Advanced Neutron Source (ANS) safety workshop, Knoxville, Tennessee, October 25--26, 1988

    International Nuclear Information System (INIS)

    Buchanan, J.R.; Dumont, J.N.; Kendrick, C.M.; Row, T.H.; Thompson, P.B.; West, C.D.; Marchaterre, J.F.; Muhlheim, M.D.; McBee, M.R.

    1988-12-01

    On October 25--26, 1988, about 60 people took part in an Advanced Neutron Source (ANS) Safety Workshop, organized in cooperation with the Oak Ridge Operations (ORO) Office of the Department of Energy (DOE) and held in Knoxville, Tennessee. After a plenary session at which ANS Project staff presented status reports on the ANS design, research and development (R and D), and safety analysis efforts, the workshop broke into three working groups, each covering a different topic: Environmental and Waste Management, Applicable Regulatory Safety Criteria and Goals, and Reactor Concepts. Each group was asked to review the Project's approach to safety-related issues and to provide guidance on future reactor safety needs or directions for the Project. With the help of able chairmen, assisted by reporters and secretarial support, the working groups were extremely successful. Draft reports from each group were prepared before the workshop closed, and the major findings of each group were presented for review and discussion by the entire workshop attendance. This report contains the final version of the group reports, incorporating the results of the overall review by all the workshop participants

  19. Safety evaluation of advance street name signs

    Science.gov (United States)

    2009-06-01

    The Federal Highway Administration (FHWA) organized a pooled fund study of 26 States to evaluate low-cost safety strategies as part of its strategic highway safety effort. The objective of the pooled fund study was to estimate the safety effectivenes...

  20. Safety aspects of the US advanced LMR [liquid metal reactor] design

    International Nuclear Information System (INIS)

    Pedersen, D.R.; Gyorey, G.L.; Marchaterre, J.F.; Rosen, S.

    1989-01-01

    The cornerstones of the United States Advanced Liquid Metal Cooled Reactor (ALMR) program sponsored by the Department of Energy are: the plant design program at General Electric based on the PRISM (Power Reactor Innovative Small Module) concept, and the Integral Fast Reactor program (IFR) at Argonne National Laboratory (ANL). The goal of the US program is to produce a standard, commercial ALMR, including the associated fuel cycle. This paper discusses the US regulatory framework for design of an ALMR, safety aspects of the IFR program at ANL, the IFR fuel cycle and actinide recycle, and the ALMR plant design program at GE. 6 refs., 5 figs

  1. Safety culture in the nuclear field

    International Nuclear Information System (INIS)

    2005-09-01

    The council of IAEA governors ratified twelve elemental principles of physical protection of nuclear matters and installations. These principles will be included in the future updating of the international convention on the physical protection. The F basic principle proposes a definition of the safety culture and recommends that its implementation and its perenniality to be a reality in the concerned organisms.It appears as necessary to precise the concept of safety culture. The twelve principles are as follow: A State liability, B liability during international transports, C legislative and regulatory framework, D competent authority, E operators liability, F safety culture, G threats, H graduated approach, I deep defence, J assurance of the quality, K emergency plan, L confidentiality. The present document is complementary of INSAG-4, 1991 (safety series number 75, INSAG-4 safety culture, a report by the international nuclear safety advisory group, IAEA, 1991) that presents a concept of safety culture. It proposes also, in a particular chapter, the comparisons( common points and specificities) between safety culture and security culture. (N.C.)

  2. Present status of nuclear power safety studies in JAERI

    International Nuclear Information System (INIS)

    1989-01-01

    Japan Atomic Energy Research Institute carries out the safety research required for ensuring safety accompanying the development and utilization of atomic energy, dividing the roles with industrial circules, universities and other public research institutes. First, it carries out the research based on the yearly program of safety research, in which the subjects of safety research that the state should execute are decided. Next, it carries out a series of the safety verification test on atomic energy facilities entrusted by the state using the special account for power source development promotion countermeasures. Besides, it carries out the safety research on the specific subjects entrusted by outside organizations. The object and range of atomic energy safety at present are roughly divided into four fields, that is, nuclear power stations, nuclear fuel facilities, waste treatment and disposal, and environmental radioactivity. In order to advance the research effectively, in addition to the generalization department and the execution department, various committees are organized. In 1988, about 260 persons engaged in these four research fields, and the budget for fiscal year 1988 was about 17.4 billion yen. (K.I.)

  3. Advanced accumulator for PWR

    International Nuclear Information System (INIS)

    Ichimura, Taiki; Chikahata, Hideyuki

    1997-01-01

    Advanced accumulators have been incorporated into the APWR design in order to simplify the safety system configuration and to improve reliability. The advanced accumulators refill the reactor vessel with a large discharge flow rate in a large LOCA, then switch to a small flow rate to continue safety injection for core reflooding. The functions of the conventional accumulator and the low head safety injection pump are integrated into this advanced accumulator. Injection performance tests simulating LOCA conditions and visualization tests for new designs have been carried out. This paper describes the APWR ECCS configuration, the advanced accumulator design and some of the injection performance and visualization test results. It was verified that the flow resistance of the advanced accumulator is independent of the model scale. The similarity law and performance data of the advanced accumulator for applying APWR was established. (author)

  4. Advanced field-solver techniques for RC extraction of integrated circuits

    CERN Document Server

    Yu, Wenjian

    2014-01-01

    Resistance and capacitance (RC) extraction is an essential step in modeling the interconnection wires and substrate coupling effect in nanometer-technology integrated circuits (IC). The field-solver techniques for RC extraction guarantee the accuracy of modeling, and are becoming increasingly important in meeting the demand for accurate modeling and simulation of VLSI designs. Advanced Field-Solver Techniques for RC Extraction of Integrated Circuits presents a systematic introduction to, and treatment of, the key field-solver methods for RC extraction of VLSI interconnects and substrate coupling in mixed-signal ICs. Various field-solver techniques are explained in detail, with real-world examples to illustrate the advantages and disadvantages of each algorithm. This book will benefit graduate students and researchers in the field of electrical and computer engineering, as well as engineers working in the IC design and design automation industries. Dr. Wenjian Yu is an Associate Professor at the Department of ...

  5. 76 FR 70953 - Pipeline Safety: Safety of Gas Transmission Pipelines

    Science.gov (United States)

    2011-11-16

    ... DEPARTMENT OF TRANSPORTATION Pipeline and Hazardous Materials Safety Administration 49 CFR Part 192 [Docket ID PHMSA-2011-0023] RIN 2137-AE72 Pipeline Safety: Safety of Gas Transmission Pipelines AGENCY: Pipeline and Hazardous Materials Safety Administration (PHMSA); DOT. ACTION: Advance notice of...

  6. 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.

  7. Progress of nuclear safety research. 2002

    Energy Technology Data Exchange (ETDEWEB)

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

    2002-11-01

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

  8. Progress of nuclear safety research - 2005

    International Nuclear Information System (INIS)

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

    2006-03-01

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

  9. Advance of the National Program of Radiological Protection and Safety for medical diagnostic with X-rays

    International Nuclear Information System (INIS)

    Verdejo S, M.

    1999-01-01

    The National Program of Radiological Protection and Safety for medical diagnostic with X-ray (Programa Nacional de Proteccion y Seguridad Radiologica para diagnostico medico con rayos X) was initiated in the General Direction of Environmental Health (Direccion General de Salud Ambiental) in 1995. Task coordinated with different dependences of the Public Sector in collaboration between the Secretary of Health (Secretaria de Salud), the National Commission of Nuclear Safety and Safeguards (Comision Nacional de Seguridad Nuclear y Salvaguardias) and, the National Institute of Nuclear Research (Instituto Nacional de Investigaciones Nucleares). The surveillance to the fulfilment of the standardization in matter of Radiological Protection and Safety in the medical diagnostic with X-rays has been obtained for an important advance in the Public sector and it has been arousing interest in the Private sector. (Author)

  10. Advances in dynamic and mean field games theory, applications, and numerical methods

    CERN Document Server

    Viscolani, Bruno

    2017-01-01

    This contributed volume considers recent advances in dynamic games and their applications, based on presentations given at the 17th Symposium of the International Society of Dynamic Games, held July 12-15, 2016, in Urbino, Italy. Written by experts in their respective disciplines, these papers cover various aspects of dynamic game theory including mean-field games, stochastic and pursuit-evasion games, and computational methods for dynamic games. Topics covered include Pedestrian flow in crowded environments Models for climate change negotiations Nash Equilibria for dynamic games involving Volterra integral equations Differential games in healthcare markets Linear-quadratic Gaussian dynamic games Aircraft control in wind shear conditions Advances in Dynamic and Mean-Field Games presents state-of-the-art research in a wide spectrum of areas. As such, it serves as a testament to the continued vitality and growth of the field of dynamic games and their applications. It will be of interest to an interdisciplinar...

  11. The Los Alamos Laser Acceleration of Particles Workshop and beginning of the advanced accelerator concepts field

    Science.gov (United States)

    Joshi, C.

    2012-12-01

    The first Advanced Acceleration of Particles-AAC-Workshop (actually named Laser Acceleration of Particles Workshop) was held at Los Alamos in January 1982. The workshop lasted a week and divided all the acceleration techniques into four categories: near field, far field, media, and vacuum. Basic theorems of particle acceleration were postulated (later proven) and specific experiments based on the four categories were formulated. This landmark workshop led to the formation of the advanced accelerator R&D program in the HEP office of the DOE that supports advanced accelerator research to this day. Two major new user facilities at Argonne and Brookhaven and several more directed experimental efforts were built to explore the advanced particle acceleration schemes. It is not an exaggeration to say that the intellectual breadth and excitement provided by the many groups who entered this new field provided the needed vitality to then recently formed APS Division of Beams and the new online journal Physical Review Special Topics-Accelerators and Beams. On this 30th anniversary of the AAC Workshops, it is worthwhile to look back at the legacy of the first Workshop at Los Alamos and the fine groundwork it laid for the field of advanced accelerator concepts that continues to flourish to this day.

  12. International Cooperation of the Republic of Croatia in the Field of Radiological and Nuclear Safety

    International Nuclear Information System (INIS)

    Novosel, N.

    2011-01-01

    International cooperation of the Republic of Croatia in the field of radiological and nuclear safety can be divided in two parts - political part, for which the Ministry of Foreign Affairs and European Integration is responsible, and technical part, for which the State Office for Radiological and Nuclear Safety is responsible. According to the Radiological and Nuclear Safety Act (OG 28/10) the State Office for Radiological and Nuclear Safety: ''coordinates technical cooperation with the International Atomic Energy Agency for all participants from the Republic of Croatia''; ''fulfils the obligations which the Republic of Croatia has assumed through international conventions and bilateral agreements concerning protection against ionising radiation, nuclear safety and the application of protective measures aimed at the non-proliferation of nuclear weapons'' and ''cooperates with international and domestic organisations and associations in the area of protection against ionising radiation and nuclear safety, and appoints its own expert representatives to take part in the work of such organisations and associations or to monitor their work''. In this paper various aspects of the technical cooperation with the International Atomic Energy Agency, as well as international conventions and bilateral agreements in the field of radiological and nuclear safety, are presented. Also, cooperation with other international organizations and associations in the area of radiological and nuclear safety, such as Nuclear Suppliers Group, the Zangger Committee, the Wassenaar Arrangement, Comprehensive Nuclear-Test-Ban Treaty Organization, Euratom and certain civil expert groups of NATO, is described. (author)

  13. Epidermal electronics with advanced capabilities in near-field communication.

    Science.gov (United States)

    Kim, Jeonghyun; Banks, Anthony; Cheng, Huanyu; Xie, Zhaoqian; Xu, Sheng; Jang, Kyung-In; Lee, Jung Woo; Liu, Zhuangjian; Gutruf, Philipp; Huang, Xian; Wei, Pinghung; Liu, Fei; Li, Kan; Dalal, Mitul; Ghaffari, Roozbeh; Feng, Xue; Huang, Yonggang; Gupta, Sanjay; Paik, Ungyu; Rogers, John A

    2015-02-25

    Epidermal electronics with advanced capabilities in near field communications (NFC) are presented. The systems include stretchable coils and thinned NFC chips on thin, low modulus stretchable adhesives, to allow seamless, conformal contact with the skin and simultaneous capabilities for wireless interfaces to any standard, NFC-enabled smartphone, even under extreme deformation and after/during normal daily activities. © 2014 WILEY-VCH Verlag GmbH & Co. KGaA, Weinheim.

  14. How could intelligent safety transport systems enhance safety ?

    NARCIS (Netherlands)

    Wiethoff, M. Heijer, T. & Bekiaris, E.

    2017-01-01

    In Europe, many deaths and injured each years are the cost of today's road traffic. Therefore, it is wise to look for possible solutions for enhancing traffic safety. Some Advanced Driver Assistance Systems (ADAS) are expected to increase safety, but they may also evoke new safety hazards. Only

  15. Pulsed electric field processing for fruit and vegetables

    Science.gov (United States)

    This month’s column reviews the theory and current applications of pulsed electric field (PEF) processing for fruits and vegetables to improve their safety and quality. This month’s column coauthor, Stefan Toepfl, is advanced research manager at the German Institute of Food Technologies and professo...

  16. Labour analgesia: Recent advances

    Science.gov (United States)

    Pandya, Sunil T

    2010-01-01

    Advances in the field of labour analgesia have tread a long journey from the days of ether and chloroform in 1847 to the present day practice of comprehensive programme of labour pain management using evidence-based medicine. Newer advances include introduction of newer techniques like combined spinal epidurals, low-dose epidurals facilitating ambulation, pharmacological advances like introduction of remifentanil for patient-controlled intravenous analgesia, introduction of newer local anaesthetics and adjuvants like ropivacaine, levobupivacaine, sufentanil, clonidine and neostigmine, use of inhalational agents like sevoflourane for patient-controlled inhalational analgesia using special vaporizers, all have revolutionized the practice of pain management in labouring parturients. Technological advances like use of ultrasound to localize epidural space in difficult cases minimizes failed epidurals and introduction of novel drug delivery modalities like patient-controlled epidural analgesia (PCEA) pumps and computer-integrated drug delivery pumps have improved the overall maternal satisfaction rate and have enabled us to customize a suitable analgesic regimen for each parturient. Recent randomized controlled trials and Cochrane studies have concluded that the association of epidurals with increased caesarean section and long-term backache remains only a myth. Studies have also shown that the newer, low-dose regimes do not have a statistically significant impact on the duration of labour and breast feeding and also that these reduce the instrumental delivery rates thus improving maternal and foetal safety. Advances in medical technology like use of ultrasound for localizing epidural space have helped the clinicians to minimize the failure rates, and many novel drug delivery modalities like PCEA and computer-integrated PCEA have contributed to the overall maternal satisfaction and safety. PMID:21189877

  17. Efficacy and safety evaluation of icotinib in patients with advanced non-small cell lung cancer.

    Science.gov (United States)

    Gu, Aiqin; Shi, Chunlei; Xiong, Liwen; Chu, Tianqing; Pei, Jun; Han, Baohui

    2013-02-01

    To evaluate the efficacy and safety of icotinib hydrochloride in patients with advanced non-small cell lung cancer (NSCLC). A total of 89 patients with stage IIIB or IV NSCLC received icotinib at a dose of 125 mg administered 3 times a day. Icotinib treatment was continued until disease progression or development of unacceptable toxicity. A total of 89 patients were assessable. In patients treated with icotinib, the overall response rate (RR) was 36.0% (32/89), and the disease control rate (DCR) was 69.7% (62/89). RR and DCR were significantly improved in patients with adenocarcinoma versus non-adenocarcinoma (Picotinib hydrochloride in the treatment of advanced NSCLC is efficacious and safe, and its toxic effects are tolerable.

  18. Nuclear Safety Charter

    International Nuclear Information System (INIS)

    2008-01-01

    The AREVA 'Values Charter' reaffirmed the priority that must be given to the requirement for a very high level of safety, which applies in particular to the nuclear field. The purpose of this Nuclear Safety Charter is to set forth the group's commitments in the field of nuclear safety and radiation protection so as to ensure that this requirement is met throughout the life cycle of the facilities. It should enable each of us, in carrying out our duties, to commit to this requirement personally, for the company, and for all stakeholders. These commitments are anchored in organizational and action principles and in complete transparency. They build on a safety culture shared by all personnel and maintained by periodic refresher training. They are implemented through Safety, Health, and Environmental management systems. The purpose of these commitments, beyond strict compliance with the laws and regulations in force in countries in which we operate as a group, is to foster a continuous improvement initiative aimed at continually enhancing our overall performance as a group. Content: 1 - Organization: responsibility of the group's executive management and subsidiaries, prime responsibility of the operator, a system of clearly defined responsibilities that draws on skilled support and on independent control of operating personnel, the general inspectorate: a shared expertise and an independent control of the operating organization, an organization that can be adapted for emergency management. 2 - Action principles: nuclear safety applies to every stage in the plant life cycle, lessons learned are analyzed and capitalized through the continuous improvement initiative, analyzing risks in advance is the basis of Areva's safety culture, employees are empowered to improve nuclear Safety, the group is committed to a voluntary radiation protection initiative And a sustained effort in reducing waste and effluent from facility Operations, employees and subcontractors are treated

  19. Measurement and modeling of out-of-field doses from various advanced post-mastectomy radiotherapy techniques

    Science.gov (United States)

    Yoon, Jihyung; Heins, David; Zhao, Xiaodong; Sanders, Mary; Zhang, Rui

    2017-12-01

    More and more advanced radiotherapy techniques have been adopted for post-mastectomy radiotherapies (PMRT). Patient dose reconstruction is challenging for these advanced techniques because they increase the low out-of-field dose area while the accuracy of out-of-field dose calculations by current commercial treatment planning systems (TPSs) is poor. We aim to measure and model the out-of-field radiation doses from various advanced PMRT techniques. PMRT treatment plans for an anthropomorphic phantom were generated, including volumetric modulated arc therapy with standard and flattening-filter-free photon beams, mixed beam therapy, 4-field intensity modulated radiation therapy (IMRT), and tomotherapy. We measured doses in the phantom where the TPS calculated doses were lower than 5% of the prescription dose using thermoluminescent dosimeters (TLD). The TLD measurements were corrected by two additional energy correction factors, namely out-of-beam out-of-field (OBOF) correction factor K OBOF and in-beam out-of-field (IBOF) correction factor K IBOF, which were determined by separate measurements using an ion chamber and TLD. A simple analytical model was developed to predict out-of-field dose as a function of distance from the field edge for each PMRT technique. The root mean square discrepancies between measured and calculated out-of-field doses were within 0.66 cGy Gy-1 for all techniques. The IBOF doses were highly scattered and should be evaluated case by case. One can easily combine the measured out-of-field dose here with the in-field dose calculated by the local TPS to reconstruct organ doses for a specific PMRT patient if the same treatment apparatus and technique were used.

  20. Strategies of training as a part of radiation protection and nuclear safety in the 21st century

    International Nuclear Information System (INIS)

    Tafuni, O.

    2009-01-01

    Elaboration of national strategies and national training system is one of the main direction in the field of radio protection and nuclear safety in the Republic of Moldova. Necessary seminars and advanced training courses are held in the country and abroad, as well as the educational and informational materials are published to obtain these objectives. Scientific personnel of high educational institutions and specialists in the field of nuclear safety take part in accomplishment of the strategy. The demands of International and European organizations in this field are taken into consideration

  1. Radiation safety in nuclear industry in retrospect and perspective

    International Nuclear Information System (INIS)

    Pan Ziqiang

    1993-01-01

    More than 30 years have passed since the starting up of nuclear industry in China from the early 1950's. Over the past 30-odd years, nuclear industry has always kept a good record in China thanks to the policy of 'quality first, safety first' clearly put forward for nuclear industry from the outset and a lot of suitable effective measures taken over that period. Internationally, there is rapid progress in radiation protection and nuclear safety (hereafter refereed to as radiation safety) and a number of new concepts in the field of radiation protection have been advanced. Nuclear industry is developing based on the international standardization. To ensure the further development of nuclear utility, radiation safety needs to be further strengthened

  2. An open-label extension study to evaluate the safety of ropinirole prolonged release in Chinese patients with advanced Parkinson's disease.

    Science.gov (United States)

    Zhang, Zhenxin; Wang, Jian; Zhang, Xiaoying; Chen, Shengdi; Wang, Zhenfu; Zhang, Baorong; Liu, Chunfeng; Qu, Qiumin; Cheng, Yan; Zhu, Rongxuan; Li, Jie; Hu, Jingqiu; Cai, Meng

    2015-04-01

    This open-label extension (OLE) study evaluated the safety profile of ropinirole prolonged release (PR) administered for 24 weeks as adjunctive to levodopa in Chinese patients with advanced Parkinson's disease (PD). This was a 24 week, flexible-dose, OLE study in Chinese patients with advanced PD who received 24 week treatment with ropinirole PR in the preceding double-blind (DB), phase III study (NCT01154166) and had no break in receiving study treatment while switching from the DB study to the OLE study. In the OLE study, patients received ropinirole PR once daily, starting with 2 mg/d and increasing up to 8 mg/d at week 4 (2 mg increment/week); if tolerable, the dose could be further increased in 4 mg increments up to 24 mg/d according to clinical judgment. There were no efficacy assessments. Safety assessments included monitoring adverse events (AEs), neurological examination, Gambling Symptom Assessment Scale questionnaire, liver chemistry, and laboratory tests. Of the 295 enrolled patients, 282 completed the study. The most common reason for withdrawal was AEs (n = 9, 3.1%). The mean duration to ropinirole PR treatment was 173.1 days and an overall median daily dose of ropinirole was 8 mg (range: 2-24 mg). Overall, 114 (38.6%) patients experienced on-treatment AEs; the most frequent reported AEs ( ≥ 2%) were dyskinesia (6.1%), dizziness (4.1%), nausea (3.4%), hallucinations (3.4%), somnolence (2.7%) and decreased weight (2.4%). Sixty-eight patients (23.1%) experienced treatment-related AEs. Six patients experienced serious AEs (SAEs), of which hallucination was determined to be a treatment-related SAE. There were no other significant safety findings. No new safety signals for ropinirole were identified. The safety profile of ropinirole was consistent with the preceding DB study and also with the established safety profile for ropinirole. Results support the long-term use of ropinirole PR as an adjunctive to levodopa in Chinese patients

  3. A level playing field-obtaining consistent cost estimates for advanced reactor designs

    International Nuclear Information System (INIS)

    Hudson, C.R.; Rohm, H.H.; Humphreys, J.R.

    1987-01-01

    A level playing field in sports is necessary to avoid a situation in which a team has an unfair advantage over its competition. Similarly, rules and guidelines for developing cost estimates can be established which, in effect, provide a level playing field whereby cost estimates for advanced power plant concepts can be presented on a consistent and equitable basis. As an example, consider the capital costs shown in Table 1. Both sets of cost are for the exact same power plant; Estimate 1 is expressed in constant dollars while Estimate 2 is presented in nominal or as-spent dollars. As shown, the costs in Table 1 are not directly comparable. Similar problems can be introduced as a result of differing assumptions in any number of parameters including the scope of the cost estimate, inflation/escalation and interest rates, contingency costs, and site location. Of course, the motivation for having consistent cost estimates is to permit comparison among various concepts. As the U.S. Department of Energy sponsors research and development work on several advanced reactor concepts in which expected cost is a key evaluation parameter, the emphasis in this particular endeavor has been in promoting the comparability of advanced reactor cost estimates among themselves and to existing power plant types. To continue with the analogy, the idea is to lay out the playing field and the rules of the contest such that each team participates in the match on an equal basis with the final score being solely determined by the inherent strengths and abilities of the teams. A description of the playing field and some of the more important rules will now be provided

  4. Development of the advanced CANDU technology

    International Nuclear Information System (INIS)

    Suk, Soo Dong; Min, Byung Joo; Na, Y. H.; Lee, S. Y.; Choi, J. H.; Lee, B. C.; Kim, S. N.; Jo, C. H.; Paik, J. S.; On, M. R.; Park, H. S.; Kim, S. R.

    1997-07-01

    The purpose of this study is to develop the advanced design technology to improve safety, operability and economy and to develop and advanced safety evaluation system. More realistic and reasonable methodology and modeling was employed to improve safety margin in containment analysis. Various efforts have been made to verify the CATHENA code which is the major safety analysis code for CANDU PHWR system. Fully computerized prototype ECCS was developed. The feasibility study and conceptual design of the distributed digital control system have been performed as well. The core characteristics of advanced fuel cycle, fuel management and power upgrade have been studied to determine the advanced core. (author). 77 refs., 51 tabs., 108 figs

  5. Development of the advanced CANDU technology

    Energy Technology Data Exchange (ETDEWEB)

    Suk, Soo Dong; Min, Byung Joo [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of); Na, Y H; Lee, S Y; Choi, J H; Lee, B C; Kim, S N; Jo, C H; Paik, J S; On, M R; Park, H S; Kim, S R [Korea Electric Power Co., Taejon (Korea, Republic of)

    1997-07-01

    The purpose of this study is to develop the advanced design technology to improve safety, operability and economy and to develop and advanced safety evaluation system. More realistic and reasonable methodology and modeling was employed to improve safety margin in containment analysis. Various efforts have been made to verify the CATHENA code which is the major safety analysis code for CANDU PHWR system. Fully computerized prototype ECCS was developed. The feasibility study and conceptual design of the distributed digital control system have been performed as well. The core characteristics of advanced fuel cycle, fuel management and power upgrade have been studied to determine the advanced core. (author). 77 refs., 51 tabs., 108 figs.

  6. Fieldcrest Cannon, Inc. Advanced Technical Preparation. Statistical Process Control (SPC). Safety Section: Modules 1-3. Instructor Book.

    Science.gov (United States)

    Averitt, Sallie D.

    These three modules, which were developed for use by instructors in a manufacturing firm's advanced technical preparation program, contain the materials required to present the safety section of the plant's adult-oriented, job-specific competency-based training program. The 3 modules contain 12 lessons on the following topics: lockout/tagout…

  7. Reports on BMBF-sponsored research projects in the field of reactor safety. Reporting period 1 July - 31 December 1995

    International Nuclear Information System (INIS)

    1996-01-01

    The Gesellschaft fuer Anlagen- und Reaktorsicherheit informs of the status of LWR tasks and projects on the safety of advanced reactors. Each progress report represents a compilation of individual reports about objectives, the work performed, the results, and the next steps of the works. The individual reports of quality assurance, safety of reactor component, emergency core cooling, lors of coolant, meltdown, fission product release, risk and reliability, are classified according to projects to the reactor safety research program. Another table uses the same classification system as applied in the nuclear safety index of the CEC. (DG)

  8. Dosimetric evaluation of tomography and four-box field conformal radiotherapy in locally advanced rectal cancer

    International Nuclear Information System (INIS)

    Yu, Mina; Lee, Hyo Chun; Chung, Mi Joo; Kim, Sung Hwan; Lee, Jong Hoon; Jang, Hong Seok; Jeon, Dong Min; Cheon, Geum Seong

    2013-01-01

    To report the results of dosimetric comparison between intensity-modulated radiotherapy (IMRT) using Tomotherapy and four-box field conformal radiotherapy (CRT) for pelvic irradiation of locally advanced rectal cancer. Twelve patients with locally advanced rectal cancer who received a short course preoperative chemoradiotherapy (25 Gy in 5 fractions) on the pelvis using Tomotherapy, between July 2010 and December 2010, were selected. Using their simulation computed tomography scans, Tomotherapy and four-box field CRT plans with the same dose schedule were evaluated, and dosimetric parameters of the two plans were compared. For the comparison of target coverage, we analyzed the mean dose, Vn Gy, Dmin, Dmax, radical dose homogeneity index (rDHI), and radiation conformity index (RCI). For the comparison of organs at risk (OAR), we analyzed the mean dose. Tomotherapy showed a significantly higher mean target dose than four-box field CRT (p 0.001). But, V26.25 Gy and V27.5 Gywere not significantly different between the two modalities. Tomotherapy showed higher Dmax and lower Dmin. The Tomotherapy plan had a lower rDHI than four-box field CRT (p = 0.000). Tomotherapy showed better RCI than four-box field CRT (p = 0.007). For OAR, the mean irradiated dose was significantly lower in Tomotherapy than four-box field CRT. In locally advanced rectal cancer, Tomotherapy delivers a higher conformal radiation dose to the target and reduces the irradiated dose to OAR than four-box field CRT.

  9. Dosimetric evaluation of tomography and four-box field conformal radiotherapy in locally advanced rectal cancer

    Energy Technology Data Exchange (ETDEWEB)

    Yu, Mina; Lee, Hyo Chun; Chung, Mi Joo; Kim, Sung Hwan; Lee, Jong Hoon [Dept. of Radiation Oncology, St. Vincent' s Hospital, The Catholic University of Korea College of Medicine, Suwon (Korea, Republic of); Jang, Hong Seok; Jeon, Dong Min; Cheon, Geum Seong [Dept. of Radiation Oncology, Seoul St. Mary' s Hospital, The Catholic University of Korea College of Medicine, Seoul (Korea, Republic of)

    2013-12-15

    To report the results of dosimetric comparison between intensity-modulated radiotherapy (IMRT) using Tomotherapy and four-box field conformal radiotherapy (CRT) for pelvic irradiation of locally advanced rectal cancer. Twelve patients with locally advanced rectal cancer who received a short course preoperative chemoradiotherapy (25 Gy in 5 fractions) on the pelvis using Tomotherapy, between July 2010 and December 2010, were selected. Using their simulation computed tomography scans, Tomotherapy and four-box field CRT plans with the same dose schedule were evaluated, and dosimetric parameters of the two plans were compared. For the comparison of target coverage, we analyzed the mean dose, Vn Gy, Dmin, Dmax, radical dose homogeneity index (rDHI), and radiation conformity index (RCI). For the comparison of organs at risk (OAR), we analyzed the mean dose. Tomotherapy showed a significantly higher mean target dose than four-box field CRT (p 0.001). But, V26.25 Gy and V27.5 Gywere not significantly different between the two modalities. Tomotherapy showed higher Dmax and lower Dmin. The Tomotherapy plan had a lower rDHI than four-box field CRT (p = 0.000). Tomotherapy showed better RCI than four-box field CRT (p = 0.007). For OAR, the mean irradiated dose was significantly lower in Tomotherapy than four-box field CRT. In locally advanced rectal cancer, Tomotherapy delivers a higher conformal radiation dose to the target and reduces the irradiated dose to OAR than four-box field CRT.

  10. 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

  11. Integrated vehicle-based safety systems light-vehicle field operational test key findings report.

    Science.gov (United States)

    2011-01-01

    "This document presents key findings from the light-vehicle field operational test conducted as part of the Integrated Vehicle-Based Safety Systems program. These findings are the result of analyses performed by the University of Michigan Transportat...

  12. Development of a tool of probabilistic safety analysis for advanced nuclear reactors

    International Nuclear Information System (INIS)

    Hidalgo H, F.E.; Fran N, P.

    2007-01-01

    It is developing a tool to explain in a simple way in that it consists the Probabilistic Safety Analysis (APS) and at the same time to facilitate the comparison among the different designs of advanced nuclear reactors starting from their safety systems. This tool for teaching contemplates all the workspaces in an APS, but it is deepened only in what is the development of accident sequences and systems models. At the moment its have incorporated three types of advanced reactors, ABWR, ESBWR, and the HTGR and they are compared among if and with a BWR like that of Laguna Verde. This tool is carried out in Visual Basic code because it is a platform that can be used in any Windows atmosphere and for their easy programming. The system includes a tree of events developed for this purpose for a research HTGR built in Japan (HTTR) to have a point of comparison of the same one with other reactors of previous generations. It is that in the fourth generation reactors the measure of frequency of core damage doesn't make the same sense that for reactors of previous generations, which is due to its passive safety systems and its design type of the fuel, that which makes indispensable the development of another type of risk measure. The tree of events is presented for the initiator event 'the rupture of the main pipe' that causes the depressurization of the HTTR reactor. In this article it was concluded that it is necessary to evaluate the accident until reaching to the liberation of fission products that one knows in APS like an APS study level 1 and level 2 together. The final states developed starting from the possible phenomena that happen in these scenarios are presented. For this, its are considered flaws of all the mitigation systems that intervene in this accident. The tree of events developed for this work and the definition of the final states contributes to the development of as carrying out an APS for fourth generation reactors, with the purpose of developing an APS

  13. ADX: a high field, high power density, Advanced Divertor test eXperiment

    Science.gov (United States)

    Vieira, R.; Labombard, B.; Marmar, E.; Irby, J.; Shiraiwa, S.; Terry, J.; Wallace, G.; Whyte, D. G.; Wolfe, S.; Wukitch, S.; ADX Team

    2014-10-01

    The MIT PSFC and collaborators are proposing an advanced divertor experiment (ADX) - a tokamak specifically designed to address critical gaps in the world fusion research program on the pathway to FNSF/DEMO. This high field (6.5 tesla, 1.5 MA), high power density (P/S ~ 1.5 MW/m2) facility would utilize Alcator magnet technology to test innovative divertor concepts for next-step DT fusion devices (FNSF, DEMO) at reactor-level boundary plasma pressures and parallel heat flux densities while producing high performance core plasma conditions. The experimental platform would also test advanced lower hybrid current drive (LHCD) and ion-cyclotron range of frequency (ICRF) actuators and wave physics at the plasma densities and magnetic field strengths of a DEMO, with the unique ability to deploy launcher structures both on the low-magnetic-field side and the high-field side - a location where energetic plasma-material interactions can be controlled and wave physics is most favorable for efficient current drive, heating and flow drive. This innovative experiment would perform plasma science and technology R&D necessary to inform the conceptual development and accelerate the readiness-for-deployment of FNSF/DEMO - in a timely manner, on a cost-effective research platform. Supported by DE-FC02-99ER54512.

  14. 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.

  15. 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)

  16. ACR-700 advanced technologies

    International Nuclear Information System (INIS)

    Tapping, R.L.; Turner, C.W.; Yu, S.K.W.; Olmstead, R.; Speranzini, R.A.

    2004-01-01

    A successful advanced reactor plant will have optimized economics including reduced operating and maintenance costs, improved performance, and enhanced safety. Incorporating improvements based on advanced technologies ensures cost, safety and operational competitiveness of the ACR-700. These advanced technologies include modern configuration management; construction technologies; operational technology for the control centre and information systems for plant monitoring and analysis. This paper summarizes the advanced technologies used to achieve construction and operational improvements to enhance plant economic competitiveness, advances in the operational technology used for reactor control, and presents the development of the Smart CANDU suite of tools and its application to existing operating reactors and to the ACR-700. (author)

  17. Silicon microelectronic field-emissive devices for advanced display technology

    Science.gov (United States)

    Morse, J. D.

    1993-03-01

    Field-emission displays (FED's) offer the potential advantages of high luminous efficiency, low power consumption, and low cost compared to AMLCD or CRT technologies. An LLNL team has developed silicon-point field emitters for vacuum triode structures and has also used thin-film processing techniques to demonstrate planar edge-emitter configurations. LLNL is interested in contributing its experience in this and other FED-related technologies to collaborations for commercial FED development. At LLNL, FED development is supported by computational capabilities in charge transport and surface/interface modeling in order to develop smaller, low-work-function field emitters using a variety of materials and coatings. Thin-film processing, microfabrication, and diagnostic/test labs permit experimental exploration of emitter and resistor structures. High field standoff technology is an area of long-standing expertise that guides development of low-cost spacers for FEDS. Vacuum sealing facilities are available to complete the FED production engineering process. Drivers constitute a significant fraction of the cost of any flat-panel display. LLNL has an advanced packaging group that can provide chip-on-glass technologies and three-dimensional interconnect generation permitting driver placement on either the front or the back of the display substrate.

  18. ARIES-AT: An advanced tokamak, advanced technology fusion power plant

    International Nuclear Information System (INIS)

    Najmabadi, F.; Jardin, S.C.; Tillack, M.; Waganer, L.M.

    2001-01-01

    The ARIES-AT study was initiated to assess the potential of high-performance tokamak plasmas together with advanced technology in a fusion power plant. Several avenues were pursued in order to arrive at plasmas with a higher β and better bootstrap alignment compared to ARIES-RS that led to plasmas with higher β N and β. Advanced technologies that are examined in detail include: (1) Possible improvements to the overall system by using high-temperature superconductors, (2) Innovative SiC blankets that lead to a high thermal cycle efficiency of ∼60%; and (3) Advanced manufacturing techniques which aim at producing near-finished products directly from raw material, resulting in low-cost, and reliable components. The 1000-MWe ARIES-AT design has a major radius of 5.4 m, minor radius of 1.3 M, a toroidal β of 9.2% (β N =6.0) and an on-axis field of 5.6 T. The plasma current is 13 MA and the current drive power is 24 MW. The ARIES-AT study shows that the combination of advanced tokamak modes and advanced technology leads to attractive fusion power plant with excellent safety and environmental characteristics and with a cost of electricity (5c/kWh), which is competitive with those projected for other sources of energy. (author)

  19. Ameliorative design for CARR safety rod drive mechanism

    International Nuclear Information System (INIS)

    Zhu Xuewei; Luo Zhong; Zhen Jianxiao; Wang Yulin

    2014-01-01

    The problem of safety rod accident dropped during C commissioning phase for China Advanced Research Reactor (CARR) was analyzed, and the reason was that the solenoid valve in safety rod drive mechanism (SRDM) driven loop was breakdown because of long-playing work. To solve this safe hidden trouble, SRDM was redesigned, and a new type of 'hydro lifting-hydro and electromagnetic holding' SRDM was presented, using Ansoft Maxwell to make a finite element analysis on new SRDM, working out electromagnetic field distribution and electromagnetic force of new SRDM. The results show that the value of electromagnetic force produced by electromagnetic force holding unit reaches 2.12 times about the weight of safety rod drive line, and it has some margins. (authors)

  20. Two-field and drift-flux models with application to nuclear reactor safety

    International Nuclear Information System (INIS)

    Travis, J.R.

    1986-01-01

    The ideas of the two-field (6 equation model) and drift-flux (4 equation model) description of two-phase flows are presented. Several example calculations relating to reactor safety are discussed and comparisons of the numerical results and experimental data are shown to be in good agreement. 16 refs., 32 figs

  1. Current status of environmental, health, and safety issues of electrochemical capacitors for advanced vehicle applications

    Energy Technology Data Exchange (ETDEWEB)

    Vimmerstedt, L J; Hammel, C J

    1997-04-01

    Electrochemical capacitors are a candidate for traction power assists in hybrid electric vehicles (HEVs). Other advanced automotive applications, while not the primary focus of current development efforts, are also possible. These include load leveling high-energy batteries, power conditioning electronics, electrically hated catalysts, electric power steering, and engine starter power. Higher power and longer cycle life are expected for electrochemical capacitors than for batteries. Evaluation of environmental, health, and safety (EH and S) issues of electrochemical capacitors is an essential part of the development and commercialization of electrochemical capacitors for advanced vehicles. This report provides an initial EH and S assessment. This report presents electrochemical capacitor electrochemistry, materials selection, intrinsic material hazards, mitigation of those hazards, environmental requirements, pollution control options, and shipping requirements. Most of the information available for this assessment pertains to commercial devices intended for application outside the advanced vehicle market and to experiment or prototype devices. Electrochemical capacitors for power assists in HEVs are not produced commercially now. Therefore, materials for advanced vehicle electrochemical capacitors may change, and so would the corresponding EH and S issues. Although changes are possible, this report describes issues for likely electrochemical capacitor designs.

  2. The Role of the Regulator in the Field of Safety Culture to Shun Nuclear Accident

    International Nuclear Information System (INIS)

    Kandil, M.M.

    2016-01-01

    The 2011 accident at the Fukushima Daiichi nuclear power plant in Japan has, as might be expected, led to improvements in equipment at plants around the world that have fortified safety systems and allowed for better protection against rare, extreme natural events. Equally important to the process of improving nuclear safety is the emphasis placed on implementing quality improvements to the human side of nuclear safety, a crucial element that is often not considered by those outside the nuclear sector. Ensuring nuclear reactor safety is not only a question of physical protection against all credible threats, enhancing robustness of important safety systems and increasing redundancy of back-up power and water cooling systems, but also one of making certain that qualified and trained staff are supported by effective procedures. However, these assets are valued only in an organizational culture that places a premium on ensuring high levels of safety, or implementing what is called an effective “nuclear safety culture”. Principles, characteristics and factors for effective safety culture are to great extent similar between licencees and regulatory bodies and can be applied for developing RB’s safety. Safety is the primary purpose of the regulatory body, Regulator plays a significant role in the field of nuclear safety even though the prime responsibility for safety belongs to the operator, and it is the regulator which actually decides what is considered to be safe. In order to effectively implement the international principle of high level of nuclear safety, nuclear safety culture should be clearly named as an objective in international nuclear legal acts and the regulator’s responsibility for promotion of nuclear safety culture should be established. What is more difficult for the regulator is finding the right balance of firmness but fairness in dealing with the operator. In addition to enforcing safety regulations, the regulator should have a positive

  3. CSNI collective statement on support facilities for existing and advanced reactors. The function of OECD/Nea joint projects Nea committee on the safety of nuclear installations (CSNI)

    International Nuclear Information System (INIS)

    2008-01-01

    The NEA Committee on the Safety of Nuclear Installations (CSNI) has recently completed a study on the availability and utilisation of facilities supporting safety studies for current and advanced nuclear power reactors. The study showed that significant steps had been undertaken in the past several years in support of safety test facilities, mainly by conducting multinational joint projects centered on the capability of unique test facilities worldwide. Given the positive experience of the safety research projects, it has been recommended that efforts be made to prioritize technical issues associated with advanced (Generation IV) reactor designs and to develop options on how to efficiently obtain the necessary data through internationally co-ordinated research, preparing a gradual extension of safety research beyond the needs set by currently operating reactors. This statement constitutes a reference for future CSNI activities and for safety authorities, R and D centres and industry for internationally co-ordinated research initiatives in the nuclear safety research area. (author)

  4. Advanced korean industrial safety and health policy with risk assessment.

    Science.gov (United States)

    Kwon, Hyuckmyun; Cho, Jae Hyun; Moon, Il; Choi, Jaewook; Park, Dooyong; Lee, Youngsoon

    2010-09-01

    This article describes a systematic roadmap master plan for advanced industrial safety and health policy in Korea, with an emphasis on. Since Korean industries had first emergence of industrial safety and health policy in 1953, enormous efforts have been made on upgrading the relevant laws in order to reflect real situation of industrial work environment in accordance with rapid changes of Korean and global business over three decades. Nevertheless, current policy has major defects; too much techniques-based articles, diverged contents in less organization, combined enforcement and punishments and finally enforcing regulations full of commands and control. These deficiencies have make it difficult to accommodate changes of social, industrial and employment environment in customized fashion. The approach to the solution must be generic at the level of paradigm-shift rather than local modifications and enhancement. The basic idea is to establish a new system integrated with a risk assessment scheme, which encourages employers to apply to their work environment under comprehensive responsibility. The risk assessment scheme is designed to enable to inspect employers' compliances afterwards. A project comprises four yearly phases based on applying zones; initially designating and operating a specified risk zone, gradually expanding the special zones during a period of 3 years (2010-2012) and the final zone expanded to entire nation. In each phase, the intermediate version of the system is updated through a process of precise and unbiased validation in terms of its operability, feasibility and sustainability with building relevant infrastructures as needed.

  5. Considerations on monitoring needs of advanced, passive safety light water reactors for severe accident management

    International Nuclear Information System (INIS)

    Bava, G.; Zambardi, F.

    1992-01-01

    This paper deals with problems concerning information and related instrumentation needs for Accident Management (AM), with special emphasis on Severe Accidents (SA) in the new advanced, passive safety Light Water Reactors (PLWR), presently in a development stage. The passive safety conception adopted in the plants concerned goes parallel with a deeper consideration of SA, that reflects the need of increasing the plant resistance against conditions going beyond traditional ''design basis accidents''. Further, the role of Accident Management (AM) is still emphasized as last step of the defence in depth concept, in spite of the design efforts aimed to reduce human factor importance; as a consequence, the availability of pertinent information on actual plant conditions remains a necessary premise for performing preplanned actions. This information is essential to assess the evolution of the accident scenarios, to monitor the performances of the safety systems, to evaluate the ultimate challenge to the plant safety, and to implement the emergency operating procedures and the emergency plans. Based on these general purposes, the impact of the new conception on the monitoring structure is discussed, furthermore reference is made to the accident monitoring criteria applied in current plants to evaluate the requirements for possible solutions. (orig.)

  6. Plasma nanofabrication and nanomaterials safety

    International Nuclear Information System (INIS)

    Han, Z J; Levchenko, I; Kumar, S; Yajadda, M M A; Yick, S; Seo, D H; Martin, P J; Ostrikov, K; Peel, S; Kuncic, Z

    2011-01-01

    The fast advances in nanotechnology have raised increasing concerns related to the safety of nanomaterials when exposed to humans, animals and the environment. However, despite several years of research, the nanomaterials safety field is still in its infancy owing to the complexities of structural and surface properties of these nanomaterials and organism-specific responses to them. Recently, plasma-based technology has been demonstrated as a versatile and effective way for nanofabrication, yet its health and environment-benign nature has not been widely recognized. Here we address the environmental and occupational health and safety effects of various zero- and one-dimensional nanomaterials and elaborate the advantages of using plasmas as a safe nanofabrication tool. These advantages include but are not limited to the production of substrate-bound nanomaterials, the isolation of humans from harmful nanomaterials, and the effective reforming of toxic and flammable gases. It is concluded that plasma nanofabrication can minimize the hazards in the workplace and represents a safe way for future nanofabrication technologies.

  7. Progress with situation assessment and risk prediction in advanced driver assistance systems : A survey

    NARCIS (Netherlands)

    Rendon-Velez, E.; Horváth, I.; Opiyo, E.Z.

    2009-01-01

    In the field of automotive safety, advanced driver assistance systems (ADAS) are receiving growing attention. Effective ADAS requires awareness of the actual driving situation, a reliable assessment of the risks, and making rapid decisions on assisting actions. This paper reviews the current

  8. Progress of nuclear safety research. 2003

    International Nuclear Information System (INIS)

    Anoda, Yoshinari; Amagai, Masaki; Tobita, Tohru

    2004-03-01

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

  9. Safety and reliability of pressure components with special emphasis on advanced methods of NDT. Vol. 2

    International Nuclear Information System (INIS)

    1986-01-01

    The 12 papers discuss topics of strength and safety in the field of materials technology and engineering. Conclusions for NPP component safety and materials are drawn. Measurements and studies relate to fracture mechanics methods (oscillation, burst, material strength, characteristics). The dynamic analysis of the behaviour of large test specimens, the influence of load velocity on crack resistance curve and the development of forged parts from austenitic steel for fast breeder reactors are presented. (DG) [de

  10. The Development of a Safety Assessment Approach and Its Implication on the Advanced Nuclear Fuel Cycle

    International Nuclear Information System (INIS)

    Hwang, Yong Soo; Kang, Chul Hyung

    2010-01-01

    The development of Advanced Nuclear Fuel Cycle (ANFC) technology is essential to meet the national mission for energy independence via a nuclear option in Korea. The action target is to develop environmentally friendly, cost-effective measures to reduce the burden of long term disposal. The proper scenarios regarding potential radionuclide release from a repository have been developed in this study based on the Advanced Korean Reference Disposal System (A-KRS). To predict safety for the various scenarios, a new assessment code based on the GoldSim software has also been developed. Deterministic analysis indicates an environmental benefit from the ANFC as long as the solid wastes from the ANFC act as a proper barrier

  11. Advanced chemistry management system to optimize BWR chemistry control

    International Nuclear Information System (INIS)

    Maeda, K.; Nagasawa, K.

    2002-01-01

    BWR plant chemistry control has close relationships among nuclear safety, component reliability, radiation field management and fuel integrity. Advanced technology is required to improve chemistry control [1,3,6,7,10,11]. Toshiba has developed TACMAN (Toshiba Advanced Chemistry Management system) to support BWR chemistry control. The TACMAN has been developed as response to utilities' years of requirements to keep plant operation safety, reliability and cost benefit. The advanced technology built into the TACMAN allows utilities to make efficient chemistry control and to keep cost benefit. TACMAN is currently being used in response to the needs for tools those plant chemists and engineers could use to optimize and identify plant chemistry conditions continuously. If an incipient condition or anomaly is detected at early stage, root causes evaluation and immediate countermeasures can be provided. Especially, the expert system brings numerous and competitive advantages not only to improve plant chemistry reliability but also to standardize and systematize know-how, empirical knowledge and technologies in BWR chemistry This paper shows detail functions of TACMAN and practical results to evaluate actual plant. (authors)

  12. 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

  13. 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

  14. Review of advanced driver assistance systems (ADAS)

    Science.gov (United States)

    Ziebinski, Adam; Cupek, Rafal; Grzechca, Damian; Chruszczyk, Lukas

    2017-11-01

    New cars can be equipped with many advanced safety solutions. Airbags, seatbelts and all of the essential passive safety parts are standard equipment. Now cars are often equipped with new advanced active safety systems that can prevent accidents. The functions of the Advanced Driver Assistance Systems are still growing. A review of the most popular available technologies used in ADAS and descriptions of their application areas are discussed in this paper.

  15. NATO Advanced Study Institute on Advanced Nanotechnologies for Detection and Defence

    CERN Document Server

    Tsiulyanu, Dumitru; Popov, Cyril; Kulisch, Wilhelm; Advanced nanotechnologies for detection and defence against CBRN agents

    2018-01-01

    This volume gives a broad overview of advanced technologies for detection and defence against chemical, biological, radiological and nuclear (CBRN) agents. It provides chapters addressing the preparation and characterization of different nanoscale materials (metals, oxides, glasses, polymers, carbon-based, etc.) and their applications in fields related to security and safety. In addition, it presents an interdisciplinary approach as the contributors come from different areas of research, such as physics, chemistry, engineering, materials science and biology. A major feature of the book is the combination of longer chapters introducing the basic knowledge on a certain topic, and shorter contributions highlighting specific applications in different security areas.

  16. Worldwide advanced nuclear power reactors with passive and inherent safety: What, why, how, and who

    International Nuclear Information System (INIS)

    Forsberg, C.W.; Reich, W.J.

    1991-09-01

    The political controversy over nuclear power, the accidents at Three Mile Island (TMI) and Chernobyl, international competition, concerns about the carbon dioxide greenhouse effect and technical breakthroughs have resulted in a segment of the nuclear industry examining power reactor concepts with PRIME safety characteristics. PRIME is an acronym for Passive safety, Resilience, Inherent safety, Malevolence resistance, and Extended time after initiation of an accident for external help. The basic ideal of PRIME is to develop power reactors in which operator error, internal sabotage, or external assault do not cause a significant release of radioactivity to the environment. Several PRIME reactor concepts are being considered. In each case, an existing, proven power reactor technology is combined with radical innovations in selected plant components and in the safety philosophy. The Process Inherent Ultimate Safety (PIUS) reactor is a modified pressurized-water reactor, the Modular High Temperature Gas-Cooled Reactor (MHTGR) is a modified gas-cooled reactor, and the Advanced CANDU Project is a modified heavy-water reactor. In addition to the reactor concepts, there is parallel work on super containments. The objective is the development of a passive ''box'' that can contain radioactivity in the event of any type of accident. This report briefly examines: why a segment of the nuclear power community is taking this new direction, how it differs from earlier directions, and what technical options are being considered. A more detailed description of which countries and reactor vendors have undertaken activities follows. 41 refs

  17. Advanced reactor concepts and safety

    International Nuclear Information System (INIS)

    Lipsett, J.J.

    1988-06-01

    The need for some consistency in the terms used to describe the evolution of methods for ensuring the safety of nuclear reactors has been identified by the IAEA. This is timely since there appears to be a danger that the precision of many valuable words is being diluted and that a new jargon may appear that will confuse rather than aid the communication of important but possibly diverse philosophies and concepts. Among the difficulties faced by the nuclear industry is promoting and gaining a widespread understanding of the risks actually posed by nuclear reactors. In view of the importance of communication to both the public and to the technical community generally, the starting point for the definition of terms must be with dictionary meanings and common technical usage. The nuclear engineering community should use such words in conformance with the whole technical world. This paper addresses many of the issues suggested in the invitation to meet and also poses some additional issues for consideration. Some examples are the role of the operator in either enhancing or degrading safety and how the meaning or interpretation of the word 'safety' can be expected to change during the next few decades. It is advantageous to use criteria against which technologies and ongoing operating performance can be judged provided that the criteria are generic and not specific to particular reactor concepts. Some thoughts are offered on the need to frame the criteria carefully so that innovative solutions and concepts are fostered, not stifled

  18. The main goals and principles of nuclear and radiation safety

    International Nuclear Information System (INIS)

    Huseynov, V.

    2015-01-01

    The use of modern radiation technology expands in various fields of human activity. The most advanced approach, methods and technologies and also radiation technologies are of great importance in industrial, medical, agricultural, construction, science, education, and etc. areas of the fastest growing Azerbaijan Republic. Ensuring of nuclear and radiation safety, safety standards, main principles and conception of safety play a crucial role. The following ten principles are taken as a basis to ensure safety measures. 1. Responsible for ensuring safety; 2. The role of government; 3. Leadership and management of security interests; 4. Devices and justification of activity; 5. Optimization of preservation; 6. Limiting of risks for physical persons; 7. The protection of present and future generations; 8. The prevention of accidents; 9. Emergency preparedness and response; 10. Reducing of risks of existing and unregulated radiation protection measures. The safety principles are applied together

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1995-06-01

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

  20. Recent Advance in Organic Spintronics and Magnetic Field Effect

    Science.gov (United States)

    Valy Vardeny, Z.

    2013-03-01

    In this talk several important advances in the field of Organic Spintronics and magnetic field effect (MFE) of organic films and optoelectronic devices that have occurred during the past two years from the Utah group will be surveyed and discussed. (i) Organic Spintronics: We demonstrated spin organic light emitting diode (spin-OLED) using two FM injecting electrodes, where the electroluminescence depends on the mutual orientation of the electrode magnetization directions. This development has opened up research studies into organic spin-valves (OSV) in the space-charge limited current regime. (ii) Magnetic field effect: We demonstrated that the photoinduced absorption spectrum in organic films (where current is not involved) show pronounced MFE. This unravels the underlying mechanism of the MFE in organic devices, to be more in agreement with the field of MFE in Biochemistry. (iii) Spin effects in organic optoelectronic devices: We demonstrated that certain spin 1/2 radical additives to donor-acceptor blends substantially enhance the power conversion efficiency of organic photovoltaic (OPV) solar cells. This effect shows that studies of spin response and MFE in OPV devices are promising. In collaboration with T. Nguyen, E. Ehrenfreund, B. Gautam, Y. Zhang and T. Basel. Supported by the DOE grant 04ER46109 ; NSF Grant # DMR-1104495 and MSF-MRSEC program DMR-1121252 [2,3].

  1. Advanced nuclear systems. Review study

    International Nuclear Information System (INIS)

    Liebert, Wolfgang; Glaser, Alexander; Pistner, Christoph; Baehr, Roland; Hahn, Lothar

    1999-04-01

    The task of this review study is to from provide an overview of the developments in the field of the various advanced nuclear systems, and to create the basis for more comprehensive studies of technology assessment. In an overview the concepts for advanced nuclear systems pursued worldwide are subdivided into eight subgroups. A coarse examination raster (set pattern) is developed to enable a detailed examination of the selected systems. In addition to a focus on enhanced safety features, further aspects are also taken into consideration, like the lowering of the proliferation risk, the enhancement of the economic competitiveness of the facilities and new usage possibilities (for instance concerning the relaxation of the waste disposal problem or the usage of alternative fuels to uranium). The question about the expected time span for realization and the discussion about the obstacles on the way to a commercially usable reactor also play a substantial role as well as disposal requirements as far as they can be presently recognized. In the central chapter of this study, the documentation of the representatively selected concepts is evaluated as well as existing technology assessment studies and expert opinions. In a few cases where this appears to be necessary, according technical literature, further policy advisory reports, expert statements as well as other relevant sources are taken into account. Contradictions, different assessments and dissents in the literature as well as a few unsettled questions are thus indicated. The potential of advanced nuclear systems with respect to economical and societal as well as environmental objectives cannot exclusively be measured by the corresponding intrinsic or in comparison remarkable technical improvements. The acceptability of novel or improved systems in nuclear technology will have to be judged by their convincing solutions for the crucial questions of safety, nuclear waste and risk of proliferation of nuclear weapons

  2. Para-aortic lymphadenectomy in advanced stage cervical cancer, a protocol for comparing safety, feasibility and diagnostic accuracy of surgical staging versus PET-CT; PALDISC trial.

    Science.gov (United States)

    Tax, Casper; Abbink, Karin; Rovers, Maroeska M; Bekkers, Ruud L M; Zusterzeel, Petra L M

    2018-01-01

    Currently, a PET-CT is used to assess the need for extended field radiotherapy of para-aortic lymph nodes (PALN) in International Federation of Gynaecology and Obstetrics (FIGO) stage IB2, IIA2-IVA (locally advanced stage) cervical cancer. A small study established a sensitivity and specificity estimate for PALN metastases of 50% (95% CI; 7-93%) and 83% (95% CI; 52-98%), respectively. Surgical staging of PALN may lead to a higher diagnostic accuracy. However, surgical staging of para-aortic lymph nodes in locally advanced stage cervical cancer is not common practice. Therefore, a phase 2 randomised controlled trial is needed to assess its safety and feasibility. In addition to standard imaging (MRI or CT scan) with PET-CT, 30 adult women with FIGO stage IB2, IIA2-IVA cervical cancer will be randomised to receive either surgical staging or usual PET-CT staging. Administering extended field radiotherapy will be based on lymphadenectomy results for the intervention group and on the PET-CT results for the control group. Follow-up visits at 0, 3, 6, 9 and 12 months will assess health-related quality of life and progression-free survival.Primary safety and feasibility outcomes of surgical staging will be assessed by calculating means with 95% confidence intervals for duration of surgery, number of complications, blood loss, nodal yield after para-aortic lymphadenectomy and treatment delay due to surgical staging. Secondary patient-centred outcomes on quality of life and first year survival will be documented and compared between the two groups. Estimates of sensitivity, specificity and negative and positive predictive values of MRI, PET-CT and surgical staging will be presented with 95% CI.. All analysis will be performed according to the intention to treat principle. This study will assess safety and feasibility, expressed as the number and severity of complications, effect on quality of life and the treatment delay due to surgically staging para-aortic lymph nodes in

  3. Study on personnel qualification for non-destructive tests in the field of reactor safety

    International Nuclear Information System (INIS)

    Trusch, K.; Wuestenberg, H.

    1977-01-01

    The training system for non-destructive testing is described, and the available and necessary personnel is analyzed; the personnel required for reactor safety problems is treated separately. On this basis, the subjects discussed in the study - available personnel, personnel requirements, training, training requirements, and suggestions for realisation - are treated in a general manner to begin with and afterwards with a view to specific problems of reactor safety. The methods employed are adapted to this situation. To obtain the necessary empirical data, questionnaires were set up and distributed, and experts in selected business companies and institutions were interviewed who work in the field of reactor safety or do same training in non-destructive testing. (orig.) [de

  4. Advances in safety countermeasures at the Tomari NPP of Hokkaido Electric Power on the basis of Fukushima Daiichi NPP accident. Fire protection and other advances

    International Nuclear Information System (INIS)

    Shibata, Taku; Dasai, Katsumi

    2014-01-01

    Fire protections for the nuclear power plants have been based on the fire laws and the conventional guide. After Fukushima Daiichi NPP accident, many safety countermeasures - also about Fire Protection - have been discussed in the Japanese authorities. This paper shows our present activities in the Tomari NPP about the fire protections from the view points of Fire Prevention, Fire Detection/Suppression Systems and Fire Protection, and other advances. (author)

  5. The JRC-ITU approach to the safety of advanced nuclear fuel cycles

    Energy Technology Data Exchange (ETDEWEB)

    Fanghaenel, T.; Rondinella, V.V.; Somers, J.; Konings, R.; Erdmann, N.; Uffelen, P. van; Glatz, J.P. [European Commission, Joint Research Centre - JRC, Institute for Transuranium Elements - ITU, Postfach 2340, 76125 Karlsruhe (Germany)

    2013-07-01

    The JRC-ITU safety studies of advanced fuels and cycles adopt two main axes. First the full exploitation of still available and highly relevant knowledge and samples from past fuel preparation and irradiation campaigns (complementing the limited number of ongoing programmes). Secondly, the shift of focus from simple property measurement towards the understanding of basic mechanisms determining property evolution and behaviour of fuel compounds during normal, off-normal and accident conditions. The final objective of the second axis is the determination of predictive tools applicable to systems and conditions different from those from which they were derived. State of the art experimental facilities, extensive networks of partnerships and collaboration with other organizations worldwide, and a developing programme for training and education are essential in this approach. This strategy has been implemented through various programs and projects. The SUPERFACT programme constitutes the main body of existing knowledge on the behavior in-pile of MOX fuel containing minor actinides. It encompassed all steps of a closed fuel cycle. Another international project investigating the safety of a closed cycle is METAPHIX. In this case a U-Pu19-Zr10 metal alloy containing Np, Am and Cm constitutes the fuel. 9 test pins have been prepared and irradiated. In addition to the PIE (Post Irradiation Examination), pyrometallurgical separation of the irradiated fuel has been performed, to demonstrate all the steps of a multiple recycling closed cycle and characterize their safety relevant aspects. Basic studies like thermodynamic fuel properties, fuel-cladding-coolant interactions have also been carried out at JRC-ITU.

  6. Responsibility for managing and legal consequences in the field of industrial safety

    International Nuclear Information System (INIS)

    Buedenbender, U.

    1987-01-01

    The object of industrial safety is to protect the aspirations, the life and the health of the employee from injury and by accident prevention in the field to combat dangers to life and health. The necessity for industrial safety is just as uncontentious as the objectives pursued by it. There is also a humanitarian connotation here since the health and welfare of employees are of central importance. In addition, economic aspects have to be taken into consideration, for industrial accidents mean unnecessary industrial costs which can have not insignificant economic consequences. Boards of directors, heads of various departments in the hierarchy, also the members of those departments must be absolutely clear as to what are the requirements for industrial safety in detail, what consequences arise for the introduction and organization of industrial processes right through the organization of the enterprise itself and how in this respect responsibilities are to be allocated to those affected. (orig.) [de

  7. Advances in industrial ergonomics and safety I

    Energy Technology Data Exchange (ETDEWEB)

    Mital, A. (ed.) (University of Cincinnati, Cincinnati, OH (USA). Dept. of Mechanical and Industrial Engineering, Ergonomics Research Lab.)

    1989-01-01

    125 papers are presented under the session headings: industrial ergonomics - programs and applications; applied work physiology; occupational biomechanics; engineering anthropometry; work and protective clothing; hand tools; human-computer interface; theory and practice of industrial safety; human perception and performance; human strengths; industrial noise and vibration; machine guarding and industrial machine safety; manual materials handling; modelling for safety and health; occupational injuries and health problems; policies and standards; quality control and inspection; rehabilitation and designing for the disabled; work duration and fatigue; and work and work place design. Includes papers on static and dynamic back strength of underground coal miners, and slip and fall accidents during equipment maintenance in the surface mining industry.

  8. Jet outflow and open field line measurements on the C-2U advanced beam-driven field-reversed configuration plasma experiment.

    Science.gov (United States)

    Sheftman, D; Gupta, D; Roche, T; Thompson, M C; Giammanco, F; Conti, F; Marsili, P; Moreno, C D

    2016-11-01

    Knowledge and control of the axial outflow of plasma particles and energy along open-magnetic-field lines are of crucial importance to the stability and longevity of the advanced beam-driven field-reversed configuration plasma. An overview of the diagnostic methods used to perform measurements on the open field line plasma on C-2U is presented, including passive Doppler impurity spectroscopy, microwave interferometry, and triple Langmuir probe measurements. Results of these measurements provide the jet ion temperature and axial velocity, electron density, and high frequency density fluctuations.

  9. Vacuum magnetic field and modular coil system of the advanced stellarator Wendelstein VII-AS

    International Nuclear Information System (INIS)

    Rau, F.; Kisslinger, J.; Wobig, H.

    1982-06-01

    The vacuum field and the modular coils of the advanced stellarator WENDELSTEIN VII-AS are described. Each of the five field periods contains 9 different twisted coils, one of them with increased dimensions and current in order to provide sufficient access. The standard vacuum field configuration (B=3 T, t=0.39, aspect ratio approx. equal to 10, low shear, and magnetic well) can be varied by toroidal and vertical fields, or by changing independently the current in the large special coils. From a study of magnetic field perturbations some estimates are derived for the admissible coil tolerances. (orig.)

  10. Advancing the framework for considering the effects of climate change on worker safety and health.

    Science.gov (United States)

    Schulte, P A; Bhattacharya, A; Butler, C R; Chun, H K; Jacklitsch, B; Jacobs, T; Kiefer, M; Lincoln, J; Pendergrass, S; Shire, J; Watson, J; Wagner, G R

    2016-11-01

    In 2009, a preliminary framework for how climate change could affect worker safety and health was described. That framework was based on a literature search from 1988-2008 that supported seven categories of climate-related occupational hazards: (1) increased ambient temperature; (2) air pollution; (3) ultraviolet radiation exposure; (4) extreme weather; (5) vector-borne diseases and expanded habitats; (6) industrial transitions and emerging industries; and (7) changes in the built environment. This article reviews the published literature from 2008-2014 in each of the seven categories. Additionally, three new topics related to occupational safety and health are considered: mental health effects, economic burden, and potential worker safety and health impacts associated with the nascent field of climate intervention (geoengineering). Beyond updating the literature, this article also identifies key priorities for action to better characterize and understand how occupational safety and health may be associated with climate change events and ensure that worker health and safety issues are anticipated, recognized, evaluated, and mitigated. These key priorities include research, surveillance, risk assessment, risk management, and policy development. Strong evidence indicates that climate change will continue to present occupational safety and health hazards, and this framework may be a useful tool for preventing adverse effects to workers.

  11. A Post Closure Safety Assessment for Radioactive Wastes from Advanced nuclear fuel Cycle

    International Nuclear Information System (INIS)

    Kang, Chul Hyung; Hwang, Yong Soo

    2010-01-01

    KAERI has developed the KIEP-21 (Korean, Innovative, Environmentally Friendly, and Proliferation Resistant System for the 21st Century). It is an advanced nuclear fuel cycle option with a pyro-process and a GEN-IV SFR. A pyro-process consists of two distinctive processes, an electrolytic reduction process and an electro-refining and winning process. When the pyro-process is applied, it generates five streams of wastes. To compare pyro-process advantage over the direct disposal of Spent Nuclear Fuel (SNF), the PWR SNF of the 45,000 MWD burn-up has been assumed. A safety assessment model for pyro-process wastes and representative results are presented in this report

  12. Integrated vehicle-based safety systems light-vehicle field operational test, methodology and results report.

    Science.gov (United States)

    2010-12-01

    "This document presents the methodology and results from the light-vehicle field operational test conducted as part of the Integrated Vehicle-Based Safety Systems program. These findings are the result of analyses performed by the University of Michi...

  13. Advanced Korean Industrial Safety and Health Policy with Risk Assessment

    Directory of Open Access Journals (Sweden)

    Hyuckmyun Kwon

    2010-09-01

    Full Text Available This article describes a systematic roadmap master plan for advanced industrial safety and health policy in Korea, with an emphasis on. Since Korean industries had first emergence of industrial safety and health policy in 1953, enormous efforts have been made on upgrading the relevant laws in order to reflect real situation of industrial work environment in accordance with rapid changes of Korean and global business over three decades. Nevertheless, current policy has major defects; too much techniques-based articles, diverged contents in less organization, combined enforcement and punishments and finally enforcing regulations full of commands and control. These deficiencies have make it difficult to accommodate changes of social, industrial and employment environment in customized fashion. The approach to the solution must be generic at the level of paradigm- shift rather than local modifications and enhancement. The basic idea is to establish a new system integrated with a risk assessment scheme, which encourages employers to apply to their work environment under comprehensive responsibility. The risk assessment scheme is designed to enable to inspect employers’ compliances afterwards. A project comprises four yearly phases based on applying zones; initially designating and operating a specified risk zone, gradually expanding the special zones during a period of 3 years (2010-2012 and the final zone expanded to entire nation. In each phase, the intermediate version of the system is updated through a process of precise and unbiased validation in terms of its operability, feasibility and sustainability with building relevant infrastructures as needed.

  14. ADX: a high field, high power density, advanced divertor and RF tokamak

    Science.gov (United States)

    LaBombard, B.; Marmar, E.; Irby, J.; Terry, J. L.; Vieira, R.; Wallace, G.; Whyte, D. G.; Wolfe, S.; Wukitch, S.; Baek, S.; Beck, W.; Bonoli, P.; Brunner, D.; Doody, J.; Ellis, R.; Ernst, D.; Fiore, C.; Freidberg, J. P.; Golfinopoulos, T.; Granetz, R.; Greenwald, M.; Hartwig, Z. S.; Hubbard, A.; Hughes, J. W.; Hutchinson, I. H.; Kessel, C.; Kotschenreuther, M.; Leccacorvi, R.; Lin, Y.; Lipschultz, B.; Mahajan, S.; Minervini, J.; Mumgaard, R.; Nygren, R.; Parker, R.; Poli, F.; Porkolab, M.; Reinke, M. L.; Rice, J.; Rognlien, T.; Rowan, W.; Shiraiwa, S.; Terry, D.; Theiler, C.; Titus, P.; Umansky, M.; Valanju, P.; Walk, J.; White, A.; Wilson, J. R.; Wright, G.; Zweben, S. J.

    2015-05-01

    The MIT Plasma Science and Fusion Center and collaborators are proposing a high-performance Advanced Divertor and RF tokamak eXperiment (ADX)—a tokamak specifically designed to address critical gaps in the world fusion research programme on the pathway to next-step devices: fusion nuclear science facility (FNSF), fusion pilot plant (FPP) and/or demonstration power plant (DEMO). This high-field (⩾6.5 T, 1.5 MA), high power density facility (P/S ˜ 1.5 MW m-2) will test innovative divertor ideas, including an ‘X-point target divertor’ concept, at the required performance parameters—reactor-level boundary plasma pressures, magnetic field strengths and parallel heat flux densities entering into the divertor region—while simultaneously producing high-performance core plasma conditions that are prototypical of a reactor: equilibrated and strongly coupled electrons and ions, regimes with low or no torque, and no fuelling from external heating and current drive systems. Equally important, the experimental platform will test innovative concepts for lower hybrid current drive and ion cyclotron range of frequency actuators with the unprecedented ability to deploy launch structures both on the low-magnetic-field side and the high-magnetic-field side—the latter being a location where energetic plasma-material interactions can be controlled and favourable RF wave physics leads to efficient current drive, current profile control, heating and flow drive. This triple combination—advanced divertors, advanced RF actuators, reactor-prototypical core plasma conditions—will enable ADX to explore enhanced core confinement physics, such as made possible by reversed central shear, using only the types of external drive systems that are considered viable for a fusion power plant. Such an integrated demonstration of high-performance core-divertor operation with steady-state sustainment would pave the way towards an attractive pilot plant, as envisioned in the ARC concept

  15. The unitary conformal field theory behind 2D Asymptotic Safety

    Energy Technology Data Exchange (ETDEWEB)

    Nink, Andreas; Reuter, Martin [Institute of Physics, PRISMA & MITP, Johannes Gutenberg University Mainz,Staudingerweg 7, D-55099 Mainz (Germany)

    2016-02-25

    Being interested in the compatibility of Asymptotic Safety with Hilbert space positivity (unitarity), we consider a local truncation of the functional RG flow which describes quantum gravity in d>2 dimensions and construct its limit of exactly two dimensions. We find that in this limit the flow displays a nontrivial fixed point whose effective average action is a non-local functional of the metric. Its pure gravity sector is shown to correspond to a unitary conformal field theory with positive central charge c=25. Representing the fixed point CFT by a Liouville theory in the conformal gauge, we investigate its general properties and their implications for the Asymptotic Safety program. In particular, we discuss its field parametrization dependence and argue that there might exist more than one universality class of metric gravity theories in two dimensions. Furthermore, studying the gravitational dressing in 2D asymptotically safe gravity coupled to conformal matter we uncover a mechanism which leads to a complete quenching of the a priori expected Knizhnik-Polyakov-Zamolodchikov (KPZ) scaling. A possible connection of this prediction to Monte Carlo results obtained in the discrete approach to 2D quantum gravity based upon causal dynamical triangulations is mentioned. Similarities of the fixed point theory to, and differences from, non-critical string theory are also described. On the technical side, we provide a detailed analysis of an intriguing connection between the Einstein-Hilbert action in d>2 dimensions and Polyakov’s induced gravity action in two dimensions.

  16. Leveling the field: The role of training, safety programs, and knowledge management systems in fostering inclusive field settings

    Science.gov (United States)

    Starkweather, S.; Crain, R.; Derry, K. R.

    2017-12-01

    Knowledge is empowering in all settings, but plays an elevated role in empowering under-represented groups in field research. Field research, particularly polar field research, has deep roots in masculinized and colonial traditions, which can lead to high barriers for women and minorities (e.g. Carey et al., 2016). While recruitment of underrepresented groups into polar field research has improved through the efforts of organizations like the Association of Polar Early Career Scientists (APECS), the experiences and successes of these participants is often contingent on the availability of specialized training opportunities or the quality of explicitly documented information about how to survive Arctic conditions or how to establish successful measurement protocols in harsh environments. In Arctic field research, knowledge is often not explicitly documented or conveyed, but learned through "experience" or informally through ad hoc advice. The advancement of field training programs and knowledge management systems suggest two means for unleashing more explicit forms of knowledge about field work. Examples will be presented along with a case for how they level the playing field and improve the experience of field work for all participants.

  17. Management of advanced pancreatic cancer with gemcitabine plus erlotinib: efficacy and safety results in clinical practice.

    Science.gov (United States)

    Diaz Beveridge, Robert; Alcolea, Vicent; Aparicio, Jorge; Segura, Ángel; García, Jose; Corbellas, Miguel; Fonfría, María; Giménez, Alejandra; Montalar, Joaquin

    2014-01-10

    The combination of gemcitabine and erlotinib is a standard first-line treatment for unresectable, locally advanced or metastatic pancreatic cancer. We reviewed our single centre experience to assess its efficacy and toxicity in clinical practice. Clinical records of patients with unresectable, locally advanced or metastatic pancreatic cancer who were treated with the combination of gemcitabine and erlotinib were reviewed. Univariate survival analysis and multivariate analysis were carried out to indentify independent predictors factors of overall survival. Our series included 55 patients. Overall disease control rate was 47%: 5% of patients presented complete response, 20% partial response and 22% stable disease. Median overall survival was 8.3 months). Cox regression analysis indicated that performance status and locally advanced versus metastatic disease were independent factors of overall survival. Patients who developed acne-like rash toxicity, related to erlotinib administration, presented a higher survival than those patients who did not develop this toxicity. Gemcitabine plus erlotinib doublet is active in our series of patients with advanced pancreatic cancer. This study provides efficacy and safety results similar to those of the pivotal phase III clinical trial that tested the same combination.

  18. Qualitative Content Analysis of Coworkers' Safety Reports of Unprofessional Behavior by Physicians and Advanced Practice Professionals.

    Science.gov (United States)

    Martinez, William; Pichert, James W; Hickson, Gerald B; Braddy, Casey H; Brown, Amy J; Catron, Thomas F; Moore, Ilene N; Stampfle, Morgan R; Webb, Lynn E; Cooper, William O

    2018-03-15

    The aims of the study were to develop a valid and reliable taxonomy of coworker reports of alleged unprofessional behavior by physicians and advanced practice professionals and determine the prevalence of reports describing particular types of unprofessional conduct. We conducted qualitative content analysis of coworker reports of alleged unprofessional behavior by physicians and advanced practice professionals to create a standardized taxonomy. We conducted a focus group of experts in medical professionalism to assess the taxonomy's face validity. We randomly selected 120 reports (20%) of the 590 total reports submitted through the medical center's safety event reporting system between June 2015 and September 2016 to measure interrater reliability of taxonomy codes and estimate the prevalence of reports describing particular types of conduct. The initial taxonomy contained 22 codes organized into the following four domains: competent medical care, clear and respectful communication, integrity, and responsibility. All 10 experts agreed that the four domains reflected essential elements of medical professionalism. Interrater reliabilities for all codes and domains had a κ value greater than the 0.60 threshold for good reliability. Most reports (60%, 95% confidence interval = 51%-69%) described disrespectful or offensive communication. Nine codes had a prevalence of less than 1% and were folded into their respective domains resulting in a final taxonomy composed of 13 codes. The final taxonomy represents a useful tool with demonstrated validity and reliability, opening the door for reliable analysis and systems to promote accountability and behavior change. Given the safety implications of unprofessional behavior, understanding the typology of coworker observations of unprofessional behavior may inform organization strategies to address this threat to patient safety.

  19. Transformation Laplacian metamaterials: recent advances in manipulating thermal and dc fields

    International Nuclear Information System (INIS)

    Han, Tiancheng; Qiu, Cheng-Wei

    2016-01-01

    The full control of single or even multiple physical fields has attracted intensive research attention in the past decade, thanks to the development of metamaterials and transformation optics. Significant progress has been made in vector fields (e.g., optics, electromagnetics, and acoustics), leading to a host of strikingly functional metamaterials, such as invisibility cloaks, illusion devices, concentrators, and rotators. However, metamaterials in vector fields, designed through coordinate transformation of Maxwell’s equations, usually require extreme parameters and impose challenges on the actual realization. In this context, metamaterials in scalar fields (e.g., thermal and dc fields), which are mostly governed by the Laplace equation, lead to more plausible and facile implementations, since there are native insulators and excellent conductors (serving as two extreme cases). This paper therefore is particularly dedicated to reviewing the most recent advances in Laplacian metamaterials in manipulating thermal (both transient and steady states) and dc fields, separately and (or) simultaneously. We focus on the theory, design, and realization of thermal/dc functional metamaterials that can be used to control heat flux and electric current at will. We also provide an outlook toward the challenges and future directions in this fascinating area. (review)

  20. Transformation Laplacian metamaterials: recent advances in manipulating thermal and dc fields

    Science.gov (United States)

    Han, Tiancheng; Qiu, Cheng-Wei

    2016-04-01

    The full control of single or even multiple physical fields has attracted intensive research attention in the past decade, thanks to the development of metamaterials and transformation optics. Significant progress has been made in vector fields (e.g., optics, electromagnetics, and acoustics), leading to a host of strikingly functional metamaterials, such as invisibility cloaks, illusion devices, concentrators, and rotators. However, metamaterials in vector fields, designed through coordinate transformation of Maxwell’s equations, usually require extreme parameters and impose challenges on the actual realization. In this context, metamaterials in scalar fields (e.g., thermal and dc fields), which are mostly governed by the Laplace equation, lead to more plausible and facile implementations, since there are native insulators and excellent conductors (serving as two extreme cases). This paper therefore is particularly dedicated to reviewing the most recent advances in Laplacian metamaterials in manipulating thermal (both transient and steady states) and dc fields, separately and (or) simultaneously. We focus on the theory, design, and realization of thermal/dc functional metamaterials that can be used to control heat flux and electric current at will. We also provide an outlook toward the challenges and future directions in this fascinating area.

  1. Anthropology in Agricultural Health and Safety Research and Intervention.

    Science.gov (United States)

    Arcury, Thomas

    2017-01-01

    Agriculture remains a dangerous industry, even as agricultural science and technology continue to advance. Research that goes beyond technological changes to address safety culture and policy are needed to improve health and safety in agriculture. In this commentary, I consider the potential for anthropology to contribute to agricultural health and safety research by addressing three aims: (1) I briefly consider what the articles in this issue of the Journal of Agromedicine say about anthropologists in agricultural health and safety; (2) I discuss what anthropologists can add to agricultural health and safety research; and (3) I examine ways in which anthropologists can participate in agricultural health and safety research. In using their traditions of rigorous field research to understand how those working in agriculture perceive and interpret factors affecting occupational health and safety (their "emic" perspective), and translating this perspective to improve the understanding of occupational health professionals and policy makers (an "etic" perspective), anthropologists can expose myths that limit improvements in agricultural health and safety. Addressing significant questions, working with the most vulnerable agricultural communities, and being outside establishment agriculture provide anthropologists with the opportunity to improve health and safety policy and regulation in agriculture.

  2. Advanced human-system interface design review guidelines

    International Nuclear Information System (INIS)

    O'Hara, J.M.

    1990-01-01

    Advanced, computer-based, human-system interface designs are emerging in nuclear power plant control rooms as a result of several factors. These include: (1) incorporation of new systems such as safety parameter display systems, (2) backfitting of current control rooms with new technologies when existing hardware is no longer supported by equipment vendors, and (3) development of advanced control room concepts. Control rooms of the future will be developed almost exclusively with advanced instrumentation and controls based upon digital technology. In addition, the control room operator will be interfacing with more intelligent systems which will be capable of providing information processing support to the operator. These developments may have significant implications for plant safety in that they will greatly affect the operator's role in the system as well as the ways in which he interacts with it. At present, however, the only guidance available to the Nuclear Regulatory Commission (NRC) for the review of control room-operator interfaces is NUREG-0700. It is a document which was written prior to these technological changes and is, therefore, tailored to the technologies used in traditional control rooms. Thus, the present guidance needs to be updated since it is inadequate to serve as the basis for NRC staff review of such advanced or hybrid control room designs. The objective of the project reported in this paper is to develop an Advanced Control Room Design Review Guideline suitable for use in performing human factors reviews of advanced operator interfaces. This guideline will take the form of a portable, interactive, computer-based document that may be conveniently used by an inspector in the field, as well as a text-based document

  3. Patterns of failure after involved field radiotherapy for locally advanced esophageal squamous cell carcinoma.

    Science.gov (United States)

    Li, Duo-Jie; Li, Hong-Wei; He, Bin; Wang, Geng-Ming; Cai, Han-Fei; Duan, Shi-Miao; Liu, Jing-Jing; Zhang, Ya-Jun; Cui, Zhen; Jiang, Hao

    2016-01-01

    To retrospectively analyze the patterns of failure and the treatment effects of involved-field irradiation (IFI) on patients treated with locally advanced esophageal squamous cell carcinoma (ESCC) and to determine whether IFI is practicable in these patients. A total of 79 patients with locally advanced ESCC underwent three dimensional conformal (3D)CRT) or intensity modulated radiotherapy (IMRT) using IFI or elective nodal irradiation (ENI) according to the target volume. The patterns of failure were defined as local/regional, in-field, out)of)field regional lymph node (LN) and distant failure. With a median follow)up of 32.0 months, failures were observed in 66 (83.6%) patients. The cumulative incidence of local/regional failure (55.8 vs 52.8%) and in)field regional lymph node failure (25.6 vs 19.4%) showed no statistically significant difference between the IFI and the ENI group (p=0.526 and 0.215, respectively). Out)of)field nodal relapse rate of only 7.0% was seen in the IFI group. Three)year survival rates for the ENI and IFI group were 22.2 and 18.6%, respectively (p=0.240), and 3)year distant metastasis rates were 27.8 and 32.6%, respectively (p=0.180). The lung V10, V20, V30 and mean lung dose of the ENI group were greater than those of the IFI group, while the mean lung dose and V10 had statistically significant difference. The patterns of failure and survival rates in the IFI group were similar as in the ENI group; the regional recurrence and distant metastasis are the main cause of treatment failure. IFI is feasible for locally advanced ESCC. Further investigation is needed to increase local control and decrease distant metastasis in these patients.

  4. Safety and human factors impacts of introducing quality management into high-risk industries: A field study

    International Nuclear Information System (INIS)

    Chollet, M.G.; Normier, C.; Girault, M.; Tasset, D.

    2002-01-01

    The Institute for Radiological Protection and Nuclear Safety has undertaken a study for getting a better understanding, especially in terms of Safety and Human Factors, of the changes caused by the progressive deployment of the Quality Management in French high risk industries. This study is based on both theoretical elements from the human sciences and management and practical elements from the field, collected from interviews in large French industrial sites involved in integrating this management method. The results show frequent discrepancies between theory, which is very positive and production-oriented, and reality, which is more complex and subtle, ever looking for trade-offs between production requirements and safety constraints. Thus, each step forward announced in the literature may be matched by possible steps backward in terms of safety on the ground. Where, in theory, processes enable practices to be mastered, in practice they can reduce autonomy and fossilize know-how. Where theoretically continuous improvement stimulates and strengthens performances, in reality it can also generate stress and deadlock. Where theoretically personal commitment and collective responsibility work towards all-out performance, in reality they can also operate to conceal safety deviations and infringements. The assessment of Quality Management processes in the nuclear field will benefit from these results raised from theoretical review and confirmed by similar management changes. (author)

  5. Status and some safety philosophies of the China advanced research reactor CARR

    International Nuclear Information System (INIS)

    Luzheng Yuan

    2001-01-01

    The existing two research reactors, HWRR (heavy water research reactor) and SPR (swimming pool reactor), have been operated by China Institute of Atomic Energy (CIAE) since, respectively, 1958 and 1964, and are both in extending service and facing the aging problem. It is expected that they will be out of service successively in the beginning decade of the 21 st century. A new, high performance and multipurpose research reactor called China advanced research reactor (CARR) will replace these two reactors. This new reactor adopts the concept of inverse neutron trap compact core structure with light water as coolant and heavy water as the outer reflector. Its design goal is as follows: under the nuclear power of 60MW, the maximum unperturbed thermal neutron flux in peripheral D 2 O reflector not less than 8 x 10 14 n/cm 2 . s while in central experimental channel, if the central cell to be replaced by an experimental channel, the corresponding value not less than 1 x 10 15 n/cm 2 . s. The main applications for this research reactor will cover RI production, neutron scattering experiments, NAA and its applications, neutron photography, NTD for monocrystaline silicon and applications on reactor engineering technology. By the end of 1999, the preliminary design of CARR was completed, then the draft of preliminary safety analysis report (PSAR) was submitted to the relevant authority at the end of 2000 for being reviewed. Now, the CARR project has entered the detail design phase and safety reviewing procedure for obtaining the construction permit from the relevant licensing authority. This paper will only briefly introduce some aspects of safety philosophy of CARR design and PSAR. (orig.)

  6. Advances in industrial ergonomics and safety II

    Energy Technology Data Exchange (ETDEWEB)

    Das, B [ed.; Technical University of Nova Scotia, Halifax, NS (Canada). Dept. of Industrial Engineering

    1990-01-01

    135 papers were presented at the conference in 20 sessions with the following headings: aging and industrial performance; back injury and rehabilitation; bioinstrumentation and electromyography; cumulative trauma disorders; engineering anthropometry; equipment design and ergonomics; human computer interaction; human performance and worker satisfaction; human strength and testing; industrial accidents and prevention; industrial biomechanics; injuries in health care; manual materials handling; noise and vibration effects; occupational health and safety; robotics and agricultural machinery safety; statistics and modelling in ergonomics; work environment; workplace safety analysis; and workstation design. Papers are included entitled: A model for analyzing mining machine illumination systems' by R.L. Unger, A.F. Glowacki and E.W. Rossi, 'Ergonomic design guidelines for underground coal mining equipment by E.J. Conway and R. Unger, and Hot work environment and human strain - a relation proposed by K. Bhattacharya and S. Raja.

  7. Advances in industrial ergonomics and safety II

    Energy Technology Data Exchange (ETDEWEB)

    Das, B. (ed.) (Technical University of Nova Scotia, Halifax, NS (Canada). Dept. of Industrial Engineering)

    1990-01-01

    135 papers were presented at the conference in 20 sessions with the following headings: aging and industrial performance; back injury and rehabilitation; bioinstrumentation and electromyography; cumulative trauma disorders; engineering anthropometry; equipment design and ergonomics; human computer interaction; human performance and worker satisfaction; human strength and testing; industrial accidents and prevention; industrial biomechanics; injuries in health care; manual materials handling; noise and vibration effects; occupational health and safety; robotics and agricultural machinery safety; statistics and modelling in ergonomics; work environment; workplace safety analysis; and workstation design. Papers are included entitled: A model for analyzing mining machine illumination systems' by R.L. Unger, A.F. Glowacki and E.W. Rossi, 'Ergonomic design guidelines for underground coal mining equipment by E.J. Conway and R. Unger, and Hot work environment and human strain - a relation proposed by K. Bhattacharya and S. Raja.

  8. Approaches to passive safety in advanced thermal reactors

    International Nuclear Information System (INIS)

    Moses, D.L.

    1986-01-01

    Since 1980, there has been a proliferation of thermal reactor designs which incorporate passive safety features. The evolution of this trend is briefly traced, and the nature of various passive safety features is discussed with regard to how they have been incorporated into evolving design concepts. The key aspects of the passive safety features include reduced core power density, enhanced passive heat sinks, inherent assured shutdown mechanisms, elimination/minimization of potential leak paths from the primary coolant systems, enhanced robustness of fuel elements and improved coolant chemistry and component materials. An increased reliance on purely passive safety features typically translates into larger reactor structures at reduced power ratings. Proponents of the most innovative concepts seek to offset the increased costs by simplifying licensing requirements and reducing construction time

  9. Integrated vehicle-based safety systems (IVBSS) : light vehicle platform field operational test data analysis plan.

    Science.gov (United States)

    2009-12-22

    This document presents the University of Michigan Transportation Research Institutes plan to : perform analysis of data collected from the light vehicle platform field operational test of the : Integrated Vehicle-Based Safety Systems (IVBSS) progr...

  10. Integrated vehicle-based safety systems (IVBSS) : heavy truck platform field operational test data analysis plan.

    Science.gov (United States)

    2009-11-23

    This document presents the University of Michigan Transportation Research Institutes plan to perform : analysis of data collected from the heavy truck platform field operational test of the Integrated Vehicle- : Based Safety Systems (IVBSS) progra...

  11. Balance of safety versus economics

    International Nuclear Information System (INIS)

    Board, J.A.; Acero, M.

    1996-01-01

    The paper looks at the strength of the case for improving safety over and above those safety standards which are currently accepted for the majority of current nuclear power plant, and assesses the cost premium that has to be paid for advanced designs with enhanced safety features. The risks associated with current nuclear plant have already been reduced to very low levels, and further preventative measures, whose cost would be out of proportion to the remaining risks, should be challenged. In this respect two issues need to be addressed: 'What is the premium to be paid for enhanced safety?' and 'How safety is safe enough?'. For a given reactor size, the premium for introducing enhanced safety in an 'advanced' reactor could be of the order of 20 %. For early plants in a series the premium would be significantly higher, due in part to the need to recover the FOAK costs. The recommendations of INSAG-3 would seem to be a good basis for defining 'What is Safe Enough' and improvements over and above these risk levels should be unnecessary unless they can be achieved at very low cost. It is concluded that the best of the current 'basic' designs are acceptably safe and the availability of 'advanced' designs should not preclude the future licensing of 'basic' designs, provided that they have introduced cost effective modifications which reflect the lessons learned from TMI and technological advances such as the use of micro-processors in control and protection systems. 'Advanced' designs have their place where the price level for electricity is higher, or become higher as environmental pressures (carbon tax) or scarcity of fossil fuels force up the price of electricity. In addition a utility may favour an 'advanced' design because they place value on its higher security of investment and the improved operational performance that has been introduced in developing the advanced designs. (authors)

  12. Modular High Temperature Gas-Cooled Reactor Safety Basis and Approach

    Energy Technology Data Exchange (ETDEWEB)

    David Petti; Jim Kinsey; Dave Alberstein

    2014-01-01

    Various international efforts are underway to assess the safety of advanced nuclear reactor designs. For example, the International Atomic Energy Agency has recently held its first Consultancy Meeting on a new cooperative research program on high temperature gas-cooled reactor (HTGR) safety. Furthermore, the Generation IV International Forum Reactor Safety Working Group has recently developed a methodology, called the Integrated Safety Assessment Methodology, for use in Generation IV advanced reactor technology development, design, and design review. A risk and safety assessment white paper is under development with respect to the Very High Temperature Reactor to pilot the Integrated Safety Assessment Methodology and to demonstrate its validity and feasibility. To support such efforts, this information paper on the modular HTGR safety basis and approach has been prepared. The paper provides a summary level introduction to HTGR history, public safety objectives, inherent and passive safety features, radionuclide release barriers, functional safety approach, and risk-informed safety approach. The information in this paper is intended to further the understanding of the modular HTGR safety approach. The paper gives those involved in the assessment of advanced reactor designs an opportunity to assess an advanced design that has already received extensive review by regulatory authorities and to judge the utility of recently proposed new methods for advanced reactor safety assessment such as the Integrated Safety Assessment Methodology.

  13. Development of the advanced CANDU technology -Development of basic technology for HWR design

    International Nuclear Information System (INIS)

    Seok, Ho Cheon; Seok, Soo Dong; Lee, Sang Yong

    1996-07-01

    It is believed that it is easier for Korea to become self-reliant in PHWR technology than in PWR technology, mainly because of the lower design pressure and temperature and because of the simplicity, economy, flexibility of the fuel cycle in comparison with PWR systems. Even though one has no doubt about the safety and the economics of the PHWR's that are now being operated or constructed in Korea. It is necessary to develop the advanced design technology for even safer and more economical PHWR systems to overcome the ever growing international resistance to sharing of nuclear technology and to meet the even more stringent requirements for the future public acceptance of nuclear power. This study is to develop the more advance design technology compared to the existing one, especially in the field of reactor physics, safety systems and safety evaluation to realize the above requirements. 71 tabs., 147 figs., 143 refs. (Author)

  14. Development of the advanced CANDU technology -Development of basic technology for HWR design-

    Energy Technology Data Exchange (ETDEWEB)

    Suk, Hoh Chun; Lee, Sang Yong; Suk, Soo Dong [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1995-07-01

    It is believed that it is easier for Korea to become self-reliant in PHWR technology than in PWR technology, mainly because of the lower design pressure and temperature and because of the simplicity, economy, flexibility of the fuel cycle in comparison with PWR systems. Even though one has no doubt about the safety and the economics of the PHWR`s that are now being operated or constructed in Korea, it is necessary to develop the advanced design technology for even safer and more economical PHWR systems to overcome the ever growing international resistance to sharing of nuclear technology and to meet the even more stringent requirements for the future public acceptance of nuclear power. This study is to develop the more advance design technology compared to the existing one, by performing in-depth studies especially in the field of reactor physics, safety systems and safety evaluation to realize the above requirements. 90 figs, 50 tabs, 38 refs. (Author).

  15. Development of the advanced CANDU technology -Development of basic technology for HWR design-

    International Nuclear Information System (INIS)

    Suk, Hoh Chun; Lee, Sang Yong; Suk, Soo Dong

    1995-07-01

    It is believed that it is easier for Korea to become self-reliant in PHWR technology than in PWR technology, mainly because of the lower design pressure and temperature and because of the simplicity, economy, flexibility of the fuel cycle in comparison with PWR systems. Even though one has no doubt about the safety and the economics of the PHWR's that are now being operated or constructed in Korea, it is necessary to develop the advanced design technology for even safer and more economical PHWR systems to overcome the ever growing international resistance to sharing of nuclear technology and to meet the even more stringent requirements for the future public acceptance of nuclear power. This study is to develop the more advance design technology compared to the existing one, by performing in-depth studies especially in the field of reactor physics, safety systems and safety evaluation to realize the above requirements. 90 figs, 50 tabs, 38 refs. (Author)

  16. Software Safety and Security

    CERN Document Server

    Nipkow, T; Hauptmann, B

    2012-01-01

    Recent decades have seen major advances in methods and tools for checking the safety and security of software systems. Automatic tools can now detect security flaws not only in programs of the order of a million lines of code, but also in high-level protocol descriptions. There has also been something of a breakthrough in the area of operating system verification. This book presents the lectures from the NATO Advanced Study Institute on Tools for Analysis and Verification of Software Safety and Security; a summer school held at Bayrischzell, Germany, in 2011. This Advanced Study Institute was

  17. The selection of field component reliability data for use in nuclear safety studies

    International Nuclear Information System (INIS)

    Coxson, B.A.; Tabaie, Mansour

    1990-01-01

    The paper reviews the user requirements for field component failure data in nuclear safety studies, and the capability of various data sources to satisfy these requirements. Aspects such as estimating the population of items exposed to failure, incompleteness, and under-reporting problems are discussed. The paper takes as an example the selection of component reliability data for use in the Pre-Operational Safety Report (POSR) for Sizewell 'B' Power Station, where field data has in many cases been derived from equipment other than that to be procured and operated on site. The paper concludes that the main quality sought in the available data sources for such studies is the ability to examine failure narratives in component reliability data systems for equipment performing comparable duties to the intended plant application. The main benefit brought about in the last decade is the interactive access to data systems which are adequately structured with regard to the equipment covered, and also provide a text-searching capability of quality-controlled event narratives. (author)

  18. The advancement of a new human factors report--'The Unique Report'--facilitating flight crew auditing of performance/operations as part of an airline's safety management system.

    Science.gov (United States)

    Leva, M C; Cahill, J; Kay, A M; Losa, G; McDonald, N

    2010-02-01

    This paper presents the findings of research relating to the specification of a new human factors report, conducted as part of the work requirements for the Human Integration into the Lifecycle of Aviation Systems project, sponsored by the European Commission. Specifically, it describes the proposed concept for a unique report, which will form the basis for all operational and safety reports completed by flight crew. This includes all mandatory and optional reports. Critically, this form is central to the advancement of improved processes and technology tools, supporting airline performance management, safety management, organisational learning and knowledge integration/information-sharing activities. Specifically, this paper describes the background to the development of this reporting form, the logic and contents of this form and how reporting data will be made use of by airline personnel. This includes a description of the proposed intelligent planning process and the associated intelligent flight plan concept, which makes use of airline operational and safety analyses information. Primarily, this new reporting form has been developed in collaboration with a major Spanish airline. In addition, it has involved research with five other airlines. Overall, this has involved extensive field research, collaborative prototyping and evaluation of new reports/flight plan concepts and a number of evaluation activities. Participants have included both operational and management personnel, across different airline flight operations processes. Statement of Relevance: This paper presents the development of a reporting concept outlined through field research and collaborative prototyping within an airline. The resulting reporting function, embedded in the journey log compiled at the end of each flight, aims at enabling employees to audit the operations of the company they work for.

  19. Terms for describing new, advanced nuclear power plants

    International Nuclear Information System (INIS)

    1997-04-01

    The IAEA's Division of Nuclear Power and the Fuel Cycle (then the Division of Nuclear Power) took an initiative in this field some years ago when work was initiated in the area of ''safety related terms'' by its International Working Group on Advanced Technologies for Water Cooled Reactors. This activity drew on advice from reactor design organizations, research institutes and government organizations, and aimed at helping eliminate confusion and misuse of safety related terms in widespread use, clarifying technical thinking regarding these terms, and improving nuclear power acceptability by providing precisely described technical meanings to them. After discussion also in the International Working Groups for Gas Cooled Reactors and Fast Reactors, the work resulted in the publication in September 1991 of IAEA-TECDOC-626, entitled ''Safety Related Terms for Advanced Nuclear Plants'', which has become a widely used publication. The present TECDOC has been prepared using the same approach to obtain advice from involved parties. Drafts of this report have been reviewed by the International Working Groups on Water Cooled Reactors, Fast Reactors and Gas Cooled Reactors, as well as by the IAEA's International Fusion Research Council (IFRC). The comments and suggestions received have been evaluated and utilized for producing the present TECDOC. 3 figs

  20. 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.

  1. Safety research program of NUCEF

    International Nuclear Information System (INIS)

    Naito, Y.

    1996-01-01

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

  2. Recent Advances in In Vitro Fertilization: Proteomics, Secretomics, Metabolomics and In Vitro Maturation

    Directory of Open Access Journals (Sweden)

    Ercan Baştu

    2013-03-01

    Full Text Available Since its first successful result in 1978, clinicians and researchers have been working on increasing the efficiency and safety of in vitro fertilization (IVF. As a result of advances in technology and understanding of human reproduction, IVF success rates have increased while high-order multiple pregnancy (triplets and more rates have decreased. On the other, there is opportunity for further improvement as many couples still face ‘unexplained infertility’ and high rates of twin pregnancies. Latest technologic and scientific improvements in IVF are promising. The aim of this review is to present the latest advances in the fields of proteomics, secretomics, metabolomics and oocyte culture, how they can potentially improve embryo selection and in vitro maturation (IVM and subsequently their possible impact on the safety and efficacy of IVF.

  3. Looking back on safety management in construction of advanced thermal nuclear power plant 'Fugen'

    International Nuclear Information System (INIS)

    Emori, Kengo

    1979-01-01

    The safety management of the advanced thermal nuclear power plant ''Fugen'' during the period from the preparation of plant construction in October, 1970, to the full power operation in March, 1979, is looked back and explained. Any large human and material accidents did not occur during the long construction time. The total numbers of persons and hours were 1.397 x 10 6 workers and 11.55 x 10 6 hours, respectively. The number of labor accidents was twenty with no dead person, the number of loss days was 645 days, the number of accident rate was 1.73, the intensity rate was 0.06, and the mean rate of labor accidents per year per 1000 workers was 6.4. The radiation exposure dose was 65.27 man-rem for the managed 1804 workers in total, during the testing and operating periods. These data show that the safety management for ''Fugen'' is very excellent, considering the following special features: 1) there were many works which were carried out for the first time, 2) the construction of the plant was conducted by five contractors taking partial charge, there were many kinds of construction works, the construction and testing periods were long, and the workers had to go to the site from Tsuruga city by car and bus. The organization of preventing disasters, the concrete implementation items for safety management, including the planning of activities, various meetings, patrol, education and training, the honoring system, the prevention of traffic accident and so on, and the results of actual safety management are explained with the reflection. (Nakai, Y.)

  4. Modifying locally the safety profile to improve the confinement of magnetic field lines in tokamak plasmas

    International Nuclear Information System (INIS)

    Constantinescu, D.; Firpo, M.-C.

    2012-01-01

    Using Hamiltonian models for the magnetic field lines, we propose a methodology to improve their confinement through the creation of transport barriers. A local modification of the safety profile creating a low-shear zone is shown to be sufficient to locally enhance drastically the regularity of the magnetic field lines without requesting a reversed shear. The optimal benefits of low-shear are obtained when the value q 0 of the safety profile in the low-shear zone is sufficiently far from the main resonance values m/n with low m and n, in the case of large enough values of those (m, n) mode amplitudes. A practical implementation in tokamak plasmas should involve electron cyclotron current drive to locally modify the magnetic shear. (paper)

  5. Directions for model building from asymptotic safety

    Science.gov (United States)

    Bond, Andrew D.; Hiller, Gudrun; Kowalska, Kamila; Litim, Daniel F.

    2017-08-01

    Building on recent advances in the understanding of gauge-Yukawa theories we explore possibilities to UV-complete the Standard Model in an asymptotically safe manner. Minimal extensions are based on a large flavor sector of additional fermions coupled to a scalar singlet matrix field. We find that asymptotic safety requires fermions in higher representations of SU(3) C × SU(2) L . Possible signatures at colliders are worked out and include R-hadron searches, diboson signatures and the evolution of the strong and weak coupling constants.

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

    International Nuclear Information System (INIS)

    Suzuki, Kazuhiko; Shimada, Yukiyasu

    2001-03-01

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

  7. The PBMR fuel plant: Proven technology in an advanced safety environment

    International Nuclear Information System (INIS)

    Braehler, G.; Froschauer, K.; Welbers, P.; Boyes, D.

    2008-01-01

    The PBMR Fuel Plant (PFP), to be constructed at the Pelindaba site near Johannesburg will fuel the first South African Pebble Bed Modular Reactor. The qualification of the PBMR fuel shall be based on past experience with fuel which was produced in the German NUKEM/HOBEG plant and irradiated in the German AVR reactor. Accordingly, the PFP must produce the same fuel as the German plant did, and consequently, the design of the PFP has in essence to be a copy of the NUKEM/HOBEG plant. As a reminder this plant had been operated in accordance with the German regulatory rules which were defined in the years 1970/80. Since then, the requirements with regard to radiological protection, criticality safety and emission control have been significantly tightened, and of course the PFP must be designed in accordance with the most advanced international norms and standards. The implications which follow from these two potentially conflicting requirements, as defined above, are highlighted, and technical solutions are presented. Hence, the change from administrative criticality safety control to technical control, i.e. the application of safe geometry as far as possible. and the introduction of technical solutions for the remaining safe mass regime will be described. A lot of equipment in the Kernel area and in the recycling areas needed to be redesigned in safe geometry. The sensitive processes for Kernel Calcining, for the Coating and the Over-coating remain under safe mass regime, but the safety against criticality is completely independent from staff activities and based on technical measures. A new concept for safe storage of large volumes of Uranium-containing liquids has been developed. Also, the change from relatively open handling of Uranium to the application of containment enclosures wherever release of radioactivity into the room atmosphere is possible, will be addressed. This change required redesign of all process steps requiring the handling of dry Uranium oxides

  8. Generating a city's first report on bicyclist safety: lessons from the field.

    Science.gov (United States)

    Lopez, Dahianna S; Hemenway, David

    2017-08-03

    For cities aiming to create a useful surveillance system for bicycle injuries, a common challenge is that city crash reporting is scattered, faulty or non-existent. We document some of the lessons we learnt in helping the city of Boston, Massachusetts, USA, do the following: (1) Create a prototype for a comprehensive police crash data set (2) Produce the city's first cyclist safety report, (3) Make crash data available to the public and (4) Generate policy recommendations for both specific roadside improvements and for sustainable changes to the police department's crash reporting database. We provided research and technical assistance to government partners to generate the report and used participant-observation field notes to generate the list of learnt lessons. After the release of the report, the city implemented immediate activities aimed at making an effort to prevent injuries, including: (1) Furnishing over 1800 taxis with stickers to prevent 'dooring,' (2) Adding pavement markings at trolley tracks to decrease the likelihood that cyclists would fall from getting their wheels lodged in the tracks, (3) Conducting targeted enforcement of traffic laws and (4) Working directly with state and federal agencies to fund a more comprehensive surveillance system. As of January of 2017, nearly 4 years after its public release, 19 170 users have viewed the crash data set 23 247 times. Some of the lessons include finding and using committed champions, prioritising the use of existing data, creating opportunities to bridge divisions between stakeholders, partnering with local universities for assistance with advanced analytics and using deliverables, such as a cyclist safety report, to advocate for sustainability. Providing an initial report on bicycle crashes in Boston served to identify specific problems, showed the value of a data system, and provided a blueprint for an improved data system. Building a useful surveillance system depends in no small part on the

  9. Reflecting on the politics of federal worker health and safety protections, 1962-2012: an interview with Donald Elisburg.

    Science.gov (United States)

    Weinstock, Deborah

    2013-01-01

    Donald Elisburg has spent his career advocating on behalf of workers. Trained as a labor lawyer, Mr. Elisburg has legal, legislative, policy development, and executive management experience in the fields of labor standards, workers' compensation, environmental and occupational safety and health, wages and hours, and employment and training. In the interview, Elisburg shares his insights on how to move a bureaucracy to advance worker health and safety and workers' rights.

  10. Advanced I and C systems for nuclear power plants feedback of experience

    International Nuclear Information System (INIS)

    Prehler Heinz Josef

    2001-01-01

    Advanced I and C systems for nuclear power plants have to meet increasing demands for safety and availability. Additionally specific requirements arising from nuclear qualification have to be fulfilled. To meet both subjects adequately in the future, Siemens has developed advanced I and C technology consisting of the two complementary I and C systems TELEPERM XP and TELEPERM XS. TELEPERM XP is primarily oriented to automation of the non safety related part of the power plant process. Such applications involve extensive open and closed loop control systems and encompass all tasks required for process control via the man-machine interface. Therefore the TELEPERM XP system consists of the AS 620 automation system, the OM 690 process control and management system, the ES 680 engineering system, the DS 670 diagnostic system and the SIMATIC NET bus system. Three versions of automation systems are available: for standard automation, for fail safe automation of safety related tasks and for turbine automation. TELEPERM XS is designed to meet all the requirements on I and C important to safety in nuclear power plants. Typical applications include reactor protection (RPS) and Engineered Safety Features Actuation System functions (ESFAS). TELEPERM XS has been rapidly accepted by the market and has accumulated an extensive operational experience. The expected advantages, namely, reduced space requirements, consistent documentation, improved ergonomics, reduced testing effort, less repair have been confirmed by the operation. The new possibilities to apply intelligent diagnostic methods have been only applied in few cases. Very good service records from a broad field of safety application prove that it is right to use digital I and C systems for safety tasks. The expected advantages such as reduced space requirements, less repairs and less effort for periodic tests, have been confirmed by practical experience. For the future, use of digital I and C systems for safety

  11. Advanced neutron source reactor conceptual safety analysis report, three-element-core design: Chapter 15, accident analysis

    International Nuclear Information System (INIS)

    Chen, N.C.J.; Wendel, M.W.; Yoder, G.L.; Harrington, R.M.

    1996-02-01

    In order to utilize reduced enrichment fuel, the three-element-core design for the Advanced Neutron Source has been proposed. The proposed core configuration consists of inner, middle, and outer elements, with the middle element offset axially beneath the inner and outer elements, which are axially aligned. The three-element-core RELAP5 model assumes that the reactor hardware is changed only within the core region, so that the loop piping, heat exchangers, and pumps remain as assumed for the two-element-core configuration. To assess the impact of changes in the core region configuration and the thermal-hydraulic steady-state conditions, the safety analysis has been updated. This report gives the safety margins for the loss-of-off-site power and pressure-boundary fault accidents based on the RELAP5 results. AU margins are greater for the three-element-core simulations than those calculated for the two-element core

  12. Preliminary Safety, Pharmacokinetics, and Efficacy of Regorafenib, Cisplatin, and Pemetrexed in Patients With Advanced Nonsquamous Non-Small-Cell Lung Cancers.

    Science.gov (United States)

    Hellmann, Matthew D; Sturm, Isrid; Trnkova, Zuzana Jirakova; Lettieri, John; Diefenbach, Konstanze; Rizvi, Naiyer A; Gettinger, Scott N

    2015-11-01

    Regorafenib is an oral multitargeted kinase inhibitor with potent antiangiogenic activity. In this phase I trial we evaluated the safety, pharmacokinetics, and efficacy of regorafenib with cisplatin and pemetrexed for patients with advanced nonsquamous non-small-cell lung cancers (nsNSCLCs). Nine patients enrolled before premature termination of the study. Five of 9 (56%) patients had a partial response and the median progression-free survival was 7 months (range, 1.5-15.1 months). Regorafenib had acceptable tolerability and minor pharmacokinetic interactions in combination with standard doses of cisplatin and pemetrexed in patients with advanced nsNSCLCs. The combination of bevacizumab, an antiangiogenesis agent, with cytotoxic chemotherapy improves survival in patients with advanced nonsquamous non-small-cell lung cancers (nsNSCLCs). Regorafenib is an oral multitargeted kinase inhibitor with potent antiangiogenic activity that is approved for patients with advanced colorectal cancer and gastrointestinal stromal tumors. In this phase I trial we evaluated the safety, pharmacokinetics (PK), and efficacy of regorafenib with cisplatin and pemetrexed for patients with advanced nsNSCLCs. Chemotherapy-naive patients with advanced nsNSCLCs were treated with regorafenib 60 mg/d continuously and cisplatin 75 mg/m(2) with pemetrexed 500 mg/m(2) once every 21 days for up to 6 cycles. Thereafter, regorafenib with or without pemetrexed could be continued as maintenance. Nine patients enrolled before premature termination of the study because of slow recruitment and a change in the development strategy of regorafenib by the study sponsor. Five patients experienced at least 1 treatment-related Grade 3 adverse event. No Grade 4 or 5 toxicity occurred. Five of 9 (56%) patients had a partial response and the median progression-free survival was 7 months (range, 1.5-15.1 months). Minor PK interactions between regorafenib and chemotherapy were observed. Regorafenib had acceptable

  13. Development of advanced human-machine system for plant operation and maintenance

    International Nuclear Information System (INIS)

    Wu, Wei; Ohi, Tadashi; Yoshikawa, Hidekazu; Sawaragi, Tetsuo; Kitamura, Masaharu; Furuta, Kazuo; Gofuku, Akio; Ito, Koji

    2004-01-01

    With the worldwide deregulation of the power industry, and the aging of the nuclear power plants (NPPs), concerns are growing over the reliability and safety of the NPPs, because the regulation of man power may lower the current high level of reliability and safety. In this paper, a concept of overall integrated plant management mechanism is proposed, in order to meet the requirements of cutting costs of NPPs and the requirements of maintaining or increasing safety and reliability. The concept is called as satellite operation maintenance center (SOMC). SOMC integrates the operation and maintenance activities of several NPP units by utilizing advanced information technologies to support cooperation activities between workers allocated at SOMC and the field workers. As for the operation activities, a framework called as Advanced Operation System (AOS) is proposed in this paper. AOS consists of three support sub-systems: dynamic operation permission system(DyOPS), supervisor information presentation system using interface agent, and crew performance evaluation system. As for the maintenance activities, a framework called as Ubiquitous-Computing-based Maintenance support System (UCMS) is proposed next. Two case studies are described, in order to show the way of how UCMS support field workers to do maintenance tasks efficiently, safely, and infallibly as well. Finally, a prospect of SOMC is shown in order to explain the way of how the technology elements developed in this project could be integrated as a whole one system to support maintenance activities of NPPs in the future. (author)

  14. Advanced human-system interface design review guidelines

    International Nuclear Information System (INIS)

    O'Hara, J.M.

    1990-01-01

    Advanced, computer-based, human-system interface designs are emerging in nuclear power plant (NPP) control rooms. These developments may have significant implications for plant safety in that they will greatly affect the ways in which operators interact with systems. At present, however, the only guidance available to the US Nuclear Regulatory Commission (NRC) for the review of control room-operator interfaces, NUREG-0700, was written prior to these technological changes and is thus not designed to address them. The objective of the project reported in this paper is to develop an Advanced Control Room Design Review Guideline for use in performing human factors reviews of advanced operator interfaces. This guideline will be implemented, in part, as a portable, computer-based, interactive document for field use. The paper describes the overall guideline development methodology, the present status of the document, and the plans for further guideline testing and development. 21 refs., 3 figs

  15. Introduction of advanced pressurized water reactors in France

    International Nuclear Information System (INIS)

    Millot, J.P.; Nigon, M.; Vitton, M.

    1988-01-01

    Designed >30 yr ago, pressurized water reactors (PWRs) have evolved well to match the current safety, operating, and economic requirements. The first advanced PWR generation, the N4 reactor, is under construction with 1992 as a target date for commercial operation. The N4 may be considered to be a technological outcome of PWR evolution, providing advances in the fields of safety, man/machine interfaces, and load flexibility. As a step beyond N4, a second advanced PWR generation is presently under definition with, as a main objective, a greater ability to cope with the possible deterioration of the natural uranium market. In 1986, Electricite de France (EdF) launched investigations into the possible characteristics of this advanced PWR, called REP-2000 (PWR-2000: the reactor for the next century). Framatome joined EdF in 1987 but had been working on a new tight-lattice reactor. Main options are due by 1988; preliminary studies will begin and, by 1990, detailed design will proceed with the intent of firm commitments for the first unit by 1995. Commissioning is planned in the early years of the next century. This reactor type should be either an improved version of the N4 reactor or a spectral shift convertible reactor (RCVS). Through research and development efforts, Framatome, Commissariat a l'Energie Atomique (CEA), and EdF are investigating the physics of fuel rod tight lattices including neutronics, thermohydraulics, fuel behavior, and reactor mechanics

  16. Reliability Analysis on NPP's Safety-Related Control Module with Field Data

    International Nuclear Information System (INIS)

    Lee, Sang Yong; Jung, Jae Hyun; Kim, Seong Hun

    2006-01-01

    The automatic control systems used in nuclear power plant (NPP) consists of numerous control modules that can be considered to be a network of components various complex ways. The control modules require relatively high reliability than industrial electronic products. Reliability prediction provides the rational basis of system designs and also provides the safety significance of system operations. The aim of this paper is to minimize the deficiencies of the traditional reliability prediction method calculation using the available field return data. This way is possible to do more realistic reliability assessment. SAMCHANG Enterprise Company (SEC) has established database containing high quality data at the module and component level from module maintenance in NPP. On the basis of these, this paper compares results that add failure record (field data) to Telcordia-SR-332 reliability prediction model with MIL-HDBK-217F prediction results

  17. Nuclear Safety Charter; Charte Surete Nucleaire

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2008-07-01

    The AREVA 'Values Charter' reaffirmed the priority that must be given to the requirement for a very high level of safety, which applies in particular to the nuclear field. The purpose of this Nuclear Safety Charter is to set forth the group's commitments in the field of nuclear safety and radiation protection so as to ensure that this requirement is met throughout the life cycle of the facilities. It should enable each of us, in carrying out our duties, to commit to this requirement personally, for the company, and for all stakeholders. These commitments are anchored in organizational and action principles and in complete transparency. They build on a safety culture shared by all personnel and maintained by periodic refresher training. They are implemented through Safety, Health, and Environmental management systems. The purpose of these commitments, beyond strict compliance with the laws and regulations in force in countries in which we operate as a group, is to foster a continuous improvement initiative aimed at continually enhancing our overall performance as a group. Content: 1 - Organization: responsibility of the group's executive management and subsidiaries, prime responsibility of the operator, a system of clearly defined responsibilities that draws on skilled support and on independent control of operating personnel, the general inspectorate: a shared expertise and an independent control of the operating organization, an organization that can be adapted for emergency management. 2 - Action principles: nuclear safety applies to every stage in the plant life cycle, lessons learned are analyzed and capitalized through the continuous improvement initiative, analyzing risks in advance is the basis of Areva's safety culture, employees are empowered to improve nuclear Safety, the group is committed to a voluntary radiation protection initiative And a sustained effort in reducing waste and effluent from facility Operations, employees and

  18. Advanced Infant Car Seat Would Increase Highway Safety

    Science.gov (United States)

    Dabney, Richard; Elrod, Susan

    2004-01-01

    An advanced infant car seat has been proposed to increase highway safety by reducing the incidence of crying, fussy behavior, and other child-related distractions that divert an adult driver s attention from driving. In addition to a conventional infant car seat with safety restraints, the proposed advanced infant car seat would include a number of components and subsystems that would function together as a comprehensive infant-care system that would keep its occupant safe, comfortable, and entertained, and would enable the driver to monitor the baby without having to either stop the car or turn around to face the infant during driving. The system would include a vibrator with bulb switch to operate; the switch would double as a squeeze toy that would make its own specific sound. A music subsystem would include loudspeakers built into the seat plus digital and analog circuitry that would utilize plug-in memory modules to synthesize music or a variety of other sounds. The music subsystem would include a built-in sound generator that could synthesize white noise or a human heartbeat to calm the baby to sleep. A second bulb switch could be used to control the music subsystem and would double as a squeeze toy that would make a distinct sound. An anti-noise sound-suppression system would isolate the baby from potentially disturbing ambient external noises. This subsystem would include small microphones, placed near the baby s ears, to detect ambient noise. The outputs of the microphone would be amplified and fed to the loudspeakers at appropriate amplitude and in a phase opposite that of the detected ambient noise, such that the net ambient sound arriving at the baby s ears would be almost completely cancelled. A video-camera subsystem would enable the driver to monitor the baby visually while continuing to face forward. One or more portable miniature video cameras could be embedded in the side of the infant car seat (see figure) or in a flip-down handle. The outputs of

  19. Intelligent Packaging Systems: Sensors and Nanosensors to Monitor Food Quality and Safety

    Directory of Open Access Journals (Sweden)

    Guillermo Fuertes

    2016-01-01

    Full Text Available The application of nanotechnology in different areas of food packaging is an emerging field that will grow rapidly in the coming years. Advances in food safety have yielded promising results leading to the development of intelligent packaging (IP. By these containers, it is possible to monitor and provide information of the condition of food, packaging, or the environment. This article describes the role of the different concepts of intelligent packaging. It is possible that this new technology could reach enhancing food safety, improving pathogen detection time, and controlling the quality of food and packaging throughout the supply chain.

  20. Nuclear reactors safety issues

    International Nuclear Information System (INIS)

    Barre, Francois; Seiler, Nathalie

    2008-01-01

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

  1. International benchmark study of advanced thermal hydraulic safety analysis codes against measurements on IEA-R1 research reactor

    Energy Technology Data Exchange (ETDEWEB)

    Hainoun, A., E-mail: pscientific2@aec.org.sy [Atomic Energy Commission of Syria (AECS), Nuclear Engineering Department, P.O. Box 6091, Damascus (Syrian Arab Republic); Doval, A. [Nuclear Engineering Department, Av. Cmdt. Luis Piedrabuena 4950, C.P. 8400 S.C de Bariloche, Rio Negro (Argentina); Umbehaun, P. [Centro de Engenharia Nuclear – CEN, IPEN-CNEN/SP, Av. Lineu Prestes 2242-Cidade Universitaria, CEP-05508-000 São Paulo, SP (Brazil); Chatzidakis, S. [School of Nuclear Engineering, Purdue University, West Lafayette, IN 47907 (United States); Ghazi, N. [Atomic Energy Commission of Syria (AECS), Nuclear Engineering Department, P.O. Box 6091, Damascus (Syrian Arab Republic); Park, S. [Research Reactor Design and Engineering Division, Basic Science Project Operation Dept., Korea Atomic Energy Research Institute (Korea, Republic of); Mladin, M. [Institute for Nuclear Research, Campului Street No. 1, P.O. Box 78, 115400 Mioveni, Arges (Romania); Shokr, A. [Division of Nuclear Installation Safety, Research Reactor Safety Section, International Atomic Energy Agency, A-1400 Vienna (Austria)

    2014-12-15

    Highlights: • A set of advanced system thermal hydraulic codes are benchmarked against IFA of IEA-R1. • Comparative safety analysis of IEA-R1 reactor during LOFA by 7 working teams. • This work covers both experimental and calculation effort and presents new out findings on TH of RR that have not been reported before. • LOFA results discrepancies from 7% to 20% for coolant and peak clad temperatures are predicted conservatively. - Abstract: In the framework of the IAEA Coordination Research Project on “Innovative methods in research reactor analysis: Benchmark against experimental data on neutronics and thermal hydraulic computational methods and tools for operation and safety analysis of research reactors” the Brazilian research reactor IEA-R1 has been selected as reference facility to perform benchmark calculations for a set of thermal hydraulic codes being widely used by international teams in the field of research reactor (RR) deterministic safety analysis. The goal of the conducted benchmark is to demonstrate the application of innovative reactor analysis tools in the research reactor community, validation of the applied codes and application of the validated codes to perform comprehensive safety analysis of RR. The IEA-R1 is equipped with an Instrumented Fuel Assembly (IFA) which provided measurements for normal operation and loss of flow transient. The measurements comprised coolant and cladding temperatures, reactor power and flow rate. Temperatures are measured at three different radial and axial positions of IFA summing up to 12 measuring points in addition to the coolant inlet and outlet temperatures. The considered benchmark deals with the loss of reactor flow and the subsequent flow reversal from downward forced to upward natural circulation and presents therefore relevant phenomena for the RR safety analysis. The benchmark calculations were performed independently by the participating teams using different thermal hydraulic and safety

  2. Clinical Outcomes of Patients with Advanced Gastrointestinal Stromal Tumors: Safety and Efficacy in a Worldwide Treatment-use Trial of Sunitinib

    Science.gov (United States)

    Reichardt, Peter; Kang, Yoon-Koo; Rutkowski, Piotr; Schuette, Jochen; Rosen, Lee S; Seddon, Beatrice; Yalcin, Suayib; Gelderblom, Hans; Williams, Charles C; Fumagalli, Elena; Biasco, Guido; Hurwitz, Herbert I; Kaiser, Pamela E; Fly, Kolette; Matczak, Ewa; Chen, Liang; Lechuga, Maria José; Demetri, George D

    2015-01-01

    BACKGROUND To provide sunitinib to patients with gastrointestinal stromal tumor (GIST) who were otherwise unable to obtain sunitinib; to obtain broad safety and efficacy data from a large population of patients with advanced GIST after imatinib failure. METHODS Imatinib-resistant/intolerant patients with advanced GIST received sunitinib on an initial dosing schedule (IDS) of 50 mg/day in 6-week cycles (4 weeks on treatment, 2 weeks off). Tumor assessment frequency was per local practice, with response assessed by investigators per Response Evaluation Criteria in Solid Tumors version 1.0. Overall survival (OS) and safety were assessed regularly. Post-hoc analyses evaluated different patterns of treatment management. RESULTS At final data cutoff, 1124 patients comprised the intent-to-treat population; 15% had a baseline Eastern Cooperative Oncology Group performance status ≥2. Median treatment duration was 7.0 months. Median time to tumor progression was 8.3 months (95% confidence interval [CI], 8.0–9.4), and median OS was 16.6 months (95% CI, 14.9–18.0) with 36% of patients alive at the time of analysis. Patients in whom the IDS was modified exhibited longer median OS (23.5 months) than those treated strictly per the IDS (11.1 months). The most common treatment-related grade 3/4 adverse events (AEs) were hand-foot syndrome (11%), fatigue (9%), neutropenia (8%), hypertension (7%), and thrombocytopenia (6%). Treatment-related AEs associated with cardiac function (eg, congestive heart failure and myocardial infarction) were reported at frequencies of ≤1% each. CONCLUSIONS This treatment-use study confirms the long-term safety and efficacy of sunitinib in a large international population of patients with advanced GIST after imatinib failure. PMID:25641662

  3. Development of digital safety system logic and control

    International Nuclear Information System (INIS)

    Nishikawa, H.; Sakamoto, H.

    1995-01-01

    Advanced-BWR (ABWR) uses total digital control and instrumentation (C and I) system. In particular, ABWR adopts a newly developed safety system using advanced digital technology. In the presentation the digital safety system design, manufacturing and factory validation test method are shortly overviewed. The digital safety system consists of micro-processor based digital controllers, data and information transmission by optical fibers and human-machine interface using color flat displays. This new developed safety system meet the nuclear safety requirements such as high reliability, independence of divisions, operability and maintainability. (2 refs., 4 figs., 1 tab.)

  4. ADVANCED DRIVER SAFETY SUPPORT SYSTEMS FOR THE URBAN TYPE VEHICLE

    Directory of Open Access Journals (Sweden)

    Katarzyna JEZIERSKA-KRUPA

    2015-12-01

    Full Text Available Smart Power Team is currently working on the design of an urban electric vehicle designed to compete in the Shell Eco-marathon. One important aspect of this type of vehicle characteristics is it safety. The project of advanced driver assistance systems has included some proposals of such systems and the concept of their execution. The first concept, BLIS (Blind Spot Information System, is to build a system of informing a driver about vehicles appearing in the blind spot. The system constitutes a second concept, CDIS (Collision Detection and Information System, and it is designed to detect a vehicle collision and inform the team. Further systems are: DPMS (Dew Point Measurement System - a system which does not allow a situation, where the windows are fogged, OHRS (Overtaking Horn Reminder System - a system which checks overtaking and MSS (main supervision system - a supervisory system. These concepts are based on the assumption of the use of laser sensors, photoelectric, humidity and temperature, and other commercially available systems. The article presents a detailed description of driver assistance systems and virtual prototyping methodology for these systems, as well as the numerical results of the verification of one of the systems.

  5. Advances in operational safety and severe accident research

    Energy Technology Data Exchange (ETDEWEB)

    Simola, K. [VTT Automation (Finland)

    2002-02-01

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

  6. 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)

  7. ORNL's NRC-sponsored HTGR safety and licensing analysis activities for Fort St. Vrain and advanced reactors

    International Nuclear Information System (INIS)

    Ball, S.J.; Cleveland, J.C.; Harrington, R.M.

    1985-01-01

    The ORNL safety analysis program for the HTGR was established in 1974 to provide technical assistance to the USNRC on licensing questions for both Fort St. Vrain and advanced plant concepts. The emphasis has been on development of major component and system dynamic simulation codes, and use of these codes to analyze specific licensing-related scenarios. The program has also emphasized code verification, using Fort St. Vrain data where applicable, and comparing results with industry-generated codes. By the use of model and parameter adjustment routines, safety-significant uncertainties have been identified. A major part of the analysis work has been done for the Fort St. Vrain HTGR, and has included analyses of FSAR accident scenario re-evaluations, the core block oscillation problem, core support thermal stress questions, technical specification upgrade review, and TMI action plan applicability studies. The large, 2240-MW(t) cogeneration lead plant design was analyzed in a multi-laboratory cooperative effort to estimate fission product source terms from postulated severe accidents

  8. Efficacy and safety of bevacizumab for the treatment of advanced hepatocellular carcinoma: a systematic review of phase II trials.

    Directory of Open Access Journals (Sweden)

    Ping Fang

    Full Text Available BACKGROUND: Hepatocellular carcinoma (HCC is a common cancer associated with a poor prognosis. Bevacizumab is a monoclonal antibody that binds vascular endothelial growth factor, a mediator of tumor angiogenesis. Bevacizumab is currently under investigation as treatment for HCC. We performed a systematic review of the efficacy and safety of bevacizumab for the treatment of advanced HCC. METHODS: PubMed, the Cochrane Library, and Google Scholar were searched using the terms "bevacizumab AND hepatocellular carcinoma AND (advanced OR unresectable". Phase II trials of bevacizumab for the treatment of advanced HCC were included. Outcomes of interest included progression-free and overall survival (PFS and OS, tumor response, and toxicities. RESULTS: A total of 26 records were identified. Of these, 18 were excluded. Hence, eight trials involving 300 patients were included. Bevacizumab was given as monotherapy (n = 1 trial or in combination with erlotinib (n = 4 trials, capecitabine (n = 1 trial, capecitabine+oxaliplatin (n = 1 trial, or gemcitabine+oxaliplatin (n = 1 trial. Most trials (five of eight reported median PFS and OS between 5.3 months and 9.0 months and 5.9 and 13.7 months, respectively. The disease control rate was consistent in five of eight trials, ranging from 51.1% to 76.9%. The response and partial response rates ranged from 0 to 23.7%, but were around 20% in four trials. Only one patient had a complete response. Frequently reported Grade 3/4 toxicities were increased aspartate transaminase/alanine transaminase (13%, fatigue (12%, hypertension (10%, diarrhea (8%, and neutropenia (5%. Thirty patients experienced gastrointestinal bleeding (grade 1/2 = 18, grade 3/4 = 12, typically due to esophageal varices. CONCLUSIONS: Bevacizumab shows promise as an effective and tolerable treatment for advanced HCC. The reported efficacy of bevacizumab appears to compare favorably with that of sorafenib, the only currently

  9. A Penning trap for advanced studies with particles in extreme laser fields

    International Nuclear Information System (INIS)

    Vogel, M.; Quint, W.; Paulus, G.G.; Stöhlker, Th.

    2012-01-01

    We present a Penning trap as a tool for advanced studies of particles in extreme laser fields. Particularly, trap-specific manipulation techniques allow control over the confined particles’ localization and spatial density by use of trap electrodes as ‘electrostatic tweezers’ and by application of a ‘rotating wall’, respectively. It is thereby possible to select and prepare well-defined ion ensembles and to optimize the laser–particle interaction. Non-destructive detection of reaction educts and products with up to single-ion sensitivity supports advanced studies by maintaining the products for further studies at extended confinement times of minutes and above. The trap features endcaps with conical openings for applications with strongly focused lasers. We show that such a modification of a cylindrical trap is possible while harmonicity and tunability are maintained.

  10. A Penning trap for advanced studies with particles in extreme laser fields

    Science.gov (United States)

    Vogel, M.; Quint, W.; Paulus, G. G.; Stöhlker, Th.

    2012-08-01

    We present a Penning trap as a tool for advanced studies of particles in extreme laser fields. Particularly, trap-specific manipulation techniques allow control over the confined particles' localization and spatial density by use of trap electrodes as 'electrostatic tweezers' and by application of a 'rotating wall', respectively. It is thereby possible to select and prepare well-defined ion ensembles and to optimize the laser-particle interaction. Non-destructive detection of reaction educts and products with up to single-ion sensitivity supports advanced studies by maintaining the products for further studies at extended confinement times of minutes and above. The trap features endcaps with conical openings for applications with strongly focused lasers. We show that such a modification of a cylindrical trap is possible while harmonicity and tunability are maintained.

  11. Survival, durable tumor remission, and long-term safety in patients with advanced melanoma receiving nivolumab.

    Science.gov (United States)

    Topalian, Suzanne L; Sznol, Mario; McDermott, David F; Kluger, Harriet M; Carvajal, Richard D; Sharfman, William H; Brahmer, Julie R; Lawrence, Donald P; Atkins, Michael B; Powderly, John D; Leming, Philip D; Lipson, Evan J; Puzanov, Igor; Smith, David C; Taube, Janis M; Wigginton, Jon M; Kollia, Georgia D; Gupta, Ashok; Pardoll, Drew M; Sosman, Jeffrey A; Hodi, F Stephen

    2014-04-01

    Programmed cell death 1 (PD-1) is an inhibitory receptor expressed by activated T cells that downmodulates effector functions and limits the generation of immune memory. PD-1 blockade can mediate tumor regression in a substantial proportion of patients with melanoma, but it is not known whether this is associated with extended survival or maintenance of response after treatment is discontinued. Patients with advanced melanoma (N = 107) enrolled between 2008 and 2012 received intravenous nivolumab in an outpatient setting every 2 weeks for up to 96 weeks and were observed for overall survival, long-term safety, and response duration after treatment discontinuation. Median overall survival in nivolumab-treated patients (62% with two to five prior systemic therapies) was 16.8 months, and 1- and 2-year survival rates were 62% and 43%, respectively. Among 33 patients with objective tumor regressions (31%), the Kaplan-Meier estimated median response duration was 2 years. Seventeen patients discontinued therapy for reasons other than disease progression, and 12 (71%) of 17 maintained responses off-therapy for at least 16 weeks (range, 16 to 56+ weeks). Objective response and toxicity rates were similar to those reported previously; in an extended analysis of all 306 patients treated on this trial (including those with other cancer types), exposure-adjusted toxicity rates were not cumulative. Overall survival following nivolumab treatment in patients with advanced treatment-refractory melanoma compares favorably with that in literature studies of similar patient populations. Responses were durable and persisted after drug discontinuation. Long-term safety was acceptable. Ongoing randomized clinical trials will further assess the impact of nivolumab therapy on overall survival in patients with metastatic melanoma.

  12. Nuclear safety approach for PWRs design and operation

    International Nuclear Information System (INIS)

    Vignon, D.

    1988-01-01

    The implementation of France's major nuclear programme - 56 PWR units in service or under construction - has gone hand in hand with the development of an original philosophy in the field of nuclear safety. From an initial core of deterministic safety philosophy current in the seventies, which has been wholly retained and in some instances refined, a range of additions has been made to include consideration of a number of additional situations based on a probabilistic approach. This has resulted in a better coherence for safety and a mitigation of the severe accident probability. Furthermore, the establishment of emergency plans has enabled the Safety Authorities and the operator to adopt a coherent and logical approach to severe accidents with the aim of achieving greater defence in depth, this has resulted in the provision of certain additional measures designed to further reduce the consequences of severe accidents. This paper describes the culmination of this work, as exemplified in the new 1 400MWe - N4 advanced plant series currently under construction, of which the essential elements are also incorporated into all previous units, thereby giving them an equivalent level of safety. This now constitutes the French safety policy with respect to PWR nuclear units

  13. Nuclear safety guide: TID--7016, Revision 2

    International Nuclear Information System (INIS)

    Thomas, J.T.

    1978-01-01

    The Nuclear Safety Guide was first issued in 1956 as classified AEC report LA-2063 and was reprinted the next year, unclassified, as TID-7016. Revision 1, published in 1961, extended the scope and refined the guiding information. Revision 2 of the Guide differs significantly from its predecessor in that the latter was intentionally conservative in its recommendations. Firmly based on experimental evidence of criticality, the original Guide and the first revision were considered to be of most value to organizations whose activities with fissionable materials were not extensive and, secondarily, that it would serve as a point of departure for members of established nuclear safety teams experienced in the field. The advance of calculational capability has permitted validated calculations to extend and substitute for experimental data. The broadened data base has enabled better interpolation, extension, and understanding of available information, especially in areas previously addressed by undefined but adequate factors of safety. The content has been thereby enriched in qualitative guidance. The information inherently contains, and the user can recapture, the quantitative guidance characteristic of the former Guides by employing appropriate safety factors

  14. Twenty sixth DAE safety and occupational health professionals meet: cryogenic safety, electrical safety and ergonomics at work place

    International Nuclear Information System (INIS)

    2009-01-01

    This conference gathered knowledge in safety and occupational health hazards in various fields of nuclear science and technology like radiations, high voltages, ultra-low temperature, ultra-high magnetic fields, electrical breakdown, fire, ergonomics and cryogenic safety at work place. Papers relevant to INIS database are indexed separately

  15. Reliability assurance for regulation of advanced reactors

    International Nuclear Information System (INIS)

    Fullwood, R.; Lofaro, R.; Samanta, P.

    1992-01-01

    The advanced nuclear power plants must achieve higher levels of safety than the first generation of plants. Showing that this is indeed true provides new challenges to reliability and risk assessment methods in the analysis of the designs employing passive and semi-passive protection. Reliability assurance of the advanced reactor systems is important for determining the safety of the design and for determining the plant operability. Safety is the primary concern, but operability is considered indicative of good and safe operation. this paper discusses several concerns for reliability assurance of the advanced design encompassing reliability determination, level of detail required in advanced reactor submittals, data for reliability assurance, systems interactions and common cause effects, passive component reliability, PRA-based configuration control system, and inspection, training, maintenance and test requirements. Suggested approaches are provided for addressing each of these topics

  16. Reliability assurance for regulation of advanced reactors

    International Nuclear Information System (INIS)

    Fullwood, R.; Lofaro, R.; Samanta, P.

    1991-01-01

    The advanced nuclear power plants must achieve higher levels of safety than the first generation of plants. Showing that this is indeed true provides new challenges to reliability and risk assessment methods in the analysis of the designs employing passive and semi-passive protection. Reliability assurance of the advanced reactor systems is important for determining the safety of the design and for determining the plant operability. Safety is the primary concern, but operability is considered indicative of good and safe operation. This paper discusses several concerns for reliability assurance of the advanced design encompassing reliability determination, level of detail required in advanced reactor submittals, data for reliability assurance, systems interactions and common cause effects, passive component reliability, PRA-based configuration control system, and inspection, training, maintenance and test requirements. Suggested approaches are provided for addressing each of these topics

  17. Sandia and General Motors: Advancing Clean Combustion Engines with

    Science.gov (United States)

    , storage, and disposal. Defense Waste Management Programs Advanced Nuclear Energy Nuclear Energy Safety Components and Systems Improving battery performance, economics, and safety for transportation. Batteries Sciences and Engineering Chemical Sciences Geosciences Fusion Energy Sciences Advanced Scientific Computing

  18. Improving safety through an integrated approach for advanced control room development

    International Nuclear Information System (INIS)

    Haugset, K.; Berg, O.; Bologna, S.; Foerdestroemmen, N.T.; Kvalem, J.; Nelson, W.R.; Yamane, N.

    1992-01-01

    With the fast development of computer technology, the potential exists for improving operational safety of nuclear plants by using advanced operator tools in the control room. Specific systems are being introduced, such as systems for alarm handling, failure detection, disturbance diagnosis, procedural advice and others, often based on process modeling techniques or expert system technology. To ensure a maximum benefit from the new technology, a careful integration of the various systems must, however, take place, resulting in a well coordinated interface between the operator and the process. The OECD Halden Reactor Project has started the development of an Integrated Surveillance And Control System (ISACS). The basis for the activity is the experience at Halden in developing specific Computerized Operator Support Systems (COSSs), and the activity around the experimental control room HAMMLAB where detailed validations of operator tools have been performed for a number of years. The first goal in the ISACS project is to have a first, limited prototype in operation at the end of 1990. Validation experiments will follow. (orig.)

  19. Improving safety through an integrated approach for advanced control room development

    International Nuclear Information System (INIS)

    Haugset, K.; Berg, O.; Foerdestroemmen, N.T.; Kvalem, J.; Nelson, W.R.

    1990-01-01

    With the fast development of computer technology, the potential exists for improving operational safety of nuclear plants by using advanced operator tools in the control room. Specific systems are being introduced, such as systems for alarm handling, failure detection, disturbance diagnosis, procedural advice and others, often based on process modeling techniques or expert system technology. To ensure a maximum benefit from the new technology, a careful integration of the various systems must, however, take place, resulting in a well coordinated interface between the operator and the process. The OECD Halden Reactor Project has started the development of an Integrated Surveillance And Control System (ISACS). The basis for the activity is the experience at Halden in developing specific Computerized Operator Support Systems (COSSs), and the activity around the experimental control room HAMMLAB where detailed validations of operator tools have been performed for a number of years. The first goal in the ISACS project is to have a first, limited prototype in operation at the end of 1990. Validation experiments will follow

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

    International Nuclear Information System (INIS)

    1986-04-01

    This list reviews reports from the Federal Republic of Germany, from France, from Japan and from the United States of America concerning single problems in the field of Reactor Safety Research. The list pursues the following order: Country of origin, problem area concerned, according to the Reactor Safety Research Program of the BMFT, reporting organization. The list of reports appears quarterly. (orig./HP) [de

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

    International Nuclear Information System (INIS)

    1986-02-01

    This list reviews reports from the Federal Republic of Germany, from France, from Japan and from the United States of America concerning special problems in the field of reactor safety research. The list pursues the following order: Country of origin, problem area concerned, according to the Reactor Safety Research Programm of the BMFT, reporting organization. The list of reports appears quarterly. (orig./HP) [de

  2. The development of NPP operational safety training courses

    International Nuclear Information System (INIS)

    Lee, Chang Kun; Lee, Duk Sun; Lee, Byung Sun; Lee, Won Koo; Juhn, Heng Run; Moon, Byung Soo; Cho, Min Sik; Lee, Han Young; Moon, Hak Won; Seo, Yeon Ho

    1987-12-01

    The objective of the project is to develop a training course text for the betterment of reactor operation and assurance of its safety in general by providing training materials of the advanced compact nuclear simulator which will become operation in September 1988. Main scope and contents of the project are as follows: - compilation of basic data related to simulator operation and maintenance as well as the comparative analysis with respect to simulator materials in foreign countries - method of training by simulator - review the training status by simulator in foreign countries - development of training course in the field of reactor safety It is expected that the results will be reflected to the actual training and retraining of the reactor operating crew so as to improve and update their capabilities in training fashion. (Author)

  3. Safety, immunogenicity, and early evidence of antitumor response with the use of the vaccine formulation NeuGcGM3 / VSSPs in patients with advanced melanoma

    International Nuclear Information System (INIS)

    Osorio Rodríguez, Marta de la Caridad

    2014-01-01

    Introduction. Melanoma is now considered an epidemic around the world. Its high lethality, constitutes a serious problem despite the continuous pharmacological and technological advances. NeuGcGM3/VSSP is a vaccine formulation containing ganglioside NeuGcGM3 incorporated in the acting of Neisseria meningitidis. It may be a choice therapeutic given this ganglioside in primary melanoma expression and immunogenicity and safety demonstrated by this vaccine in advanced breast cancer. This study evaluated the safety, immunogenicity and the anti-tumor response in patients with advanced melanoma to manage it via IM or SC. Material and methods: The expression of ganglioside in primary melanomas and its metastases was identified by immunohistochemical methods with the AcM 14F7 (anti-NGCGM3). 2 clinical trials Phase Ib/IIa escalation of doses with NeuGcGM3 /VSSP were conducted in patients with melanoma Advanced IM and SC routes. Safety and anti-tumour response were evaluated with the CTC and RECIST criteria. The statistical analysis was performed with the SPSS statistical package. Results: NeuGcGM3 is expressed in primary tumors and the studied lymph nodes metastases. NeuGcGM3/VSSP was safely managed by the SC and IM, roads without limiting toxicity. Immunogenic with IgM and IgG isotype antibody response resulted in 75% patients. There was anti-tumoral response in 38.5% with increase in median SV mainly associated with anti-tumor response. The appearance of vitiligo and the response of antibodies against other not present in the vaccine formulation gangliosides may be considered a manifestation of immune restoration. Conclusions. NeuGcGM3/VSSP managed IM and SC in patients with advanced melanoma was safe, immunogenic and antitumor activity associated with overall survival advantage. (author)

  4. 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

  5. Studying the Safety Impact of Autonomous Vehicles Using Simulation-Based Surrogate Safety Measures

    OpenAIRE

    Morando, Mark Mario; Tian, Qingyun; Truong, Long T.; Vu, Hai L.

    2018-01-01

    Autonomous vehicle (AV) technology has advanced rapidly in recent years with some automated features already available in vehicles on the market. AVs are expected to reduce traffic crashes as the majority of crashes are related to driver errors, fatigue, alcohol, or drugs. However, very little research has been conducted to estimate the safety impact of AVs. This paper aims to investigate the safety impacts of AVs using a simulation-based surrogate safety measure approach. To this end, safety...

  6. Passive Safety Systems in Advanced Water Cooled Reactors (AWCRS). Case Studies. A Report of the International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO)

    International Nuclear Information System (INIS)

    2013-09-01

    This report presents the results from the International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO) collaborative project (CP) on Advanced Water Cooled Reactor Case Studies in Support of Passive Safety Systems (AWCR), undertaken under the INPRO Programme Area C. INPRO was launched in 2000 - on the basis of a resolution of the IAEA General Conference (GC(44)/RES/21) - to ensure that nuclear energy is available in the 21st century in a sustainable manner, and it seeks to bring together all interested Member States to consider actions to achieve innovation. An important objective of nuclear energy system assessments is to identify 'gaps' in the various technologies and corresponding research and development (R and D) needs. This programme area fosters collaboration among INPRO Member States on selected innovative nuclear technologies to bridge technology gaps. Public concern about nuclear reactor safety has increased after the Fukushima Daiichi nuclear power plant accident caused by the loss of power to pump water for removing residual heat in the core. As a consequence, there has been an increasing interest in designing safety systems for new and advanced reactors that are passive in nature. Compared to active systems, passive safety features do not require operator intervention, active controls, or an external energy source. Passive systems rely only on physical phenomena such as natural circulation, thermal convection, gravity and self-pressurization. Passive safety features, therefore, are increasingly recognized as an essential component of the next-generation advanced reactors. A high level of safety and improved competitiveness are common goals for designing advanced nuclear power plants. Many of these systems incorporate several passive design concepts aimed at improving safety and reliability. The advantages of passive safety systems include simplicity, and avoidance of human intervention, external power or signals. For these reasons, most

  7. Proceedings of the third national symposium on advances in control and instrumentation

    International Nuclear Information System (INIS)

    Tiwari, A.P.; Chauhan, Vikas; Wakankar, Amol; Karnani, Urvashi; Saxena, Nikhil; Haridasan, Remya; Mishra, Elina

    2014-01-01

    Control and Instrumentation systems play a vital role in nuclear energy, defence, aerospace, discovery science and transportation sectors. These systems are deployed in safety-critical and mission critical applications as well. Advances in these fields have profound impact on performance, quality, reliability, safety, security and economics of these systems. While the basic theme of the symposium is control and instrumentation, this time the coverage of the symposium has been extended to defence, aerospace, discovery science and transportation sectors besides nuclear energy. This was been motivated by the need for synergy and sharing of experiences among these vital, high technology sectors. Papers relevant to INIS are indexed separately

  8. Probabilistic Durability Analysis in Advanced Engineering Design

    Directory of Open Access Journals (Sweden)

    A. Kudzys

    2000-01-01

    Full Text Available Expedience of probabilistic durability concepts and approaches in advanced engineering design of building materials, structural members and systems is considered. Target margin values of structural safety and serviceability indices are analyzed and their draft values are presented. Analytical methods of the cumulative coefficient of correlation and the limit transient action effect for calculation of reliability indices are given. Analysis can be used for probabilistic durability assessment of carrying and enclosure metal, reinforced concrete, wood, plastic, masonry both homogeneous and sandwich or composite structures and some kinds of equipments. Analysis models can be applied in other engineering fields.

  9. Occurrence of CYP1B1 Mutations in Juvenile Open-Angle Glaucoma With Advanced Visual Field Loss.

    Science.gov (United States)

    Souzeau, Emmanuelle; Hayes, Melanie; Zhou, Tiger; Siggs, Owen M; Ridge, Bronwyn; Awadalla, Mona S; Smith, James E H; Ruddle, Jonathan B; Elder, James E; Mackey, David A; Hewitt, Alex W; Healey, Paul R; Goldberg, Ivan; Morgan, William H; Landers, John; Dubowsky, Andrew; Burdon, Kathryn P; Craig, Jamie E

    2015-07-01

    Juvenile open-angle glaucoma (JOAG) is a severe neurodegenerative eye disorder in which most of the genetic contribution remains unexplained. To assess the prevalence of pathogenic CYP1B1 sequence variants in an Australian cohort of patients with JOAG and severe visual field loss. For this cohort study, we recruited 160 patients with JOAG classified as advanced (n = 118) and nonadvanced (n = 42) through the Australian and New Zealand Registry of Advanced Glaucoma from January 1, 2007, through April 1, 2014. Eighty individuals with no evidence of glaucoma served as a control group. We defined JOAG as diagnosis before age 40 years and advanced JOAG as visual field loss in 2 of the 4 central fixation squares on a reliable visual field test result. We performed direct sequencing of the entire coding region of CYP1B1. Data analysis was performed in October 2014. Identification and characterization of CYP1B1 sequence variants. We identified 7 different pathogenic variants among 8 of 118 patients with advanced JOAG (6.8%) but none among the patients with nonadvanced JOAG. Three patients were homozygous or compound heterozygous for CYP1B1 pathogenic variants, which provided a likely basis for their disease. Five patients were heterozygous. The allele frequency among the patients with advanced JOAG (11 in 236 [4.7%]) was higher than among our controls (1 in 160 [0.6%]; P = .02; odds ratio, 7.8 [95% CI, 0.02-1.0]) or among the control population from the Exome Aggregation Consortium database (2946 of 122 960 [2.4%]; P = .02; odds ratio, 2.0 [95% CI, 0.3-0.9]). Individuals with CYP1B1 pathogenic variants, whether heterozygous or homozygous, had worse mean (SD) deviation on visual fields (-24.5 [5.1] [95% CI, -31.8 to -17.2] vs -15.6 [10.0] [95% CI, -17.1 to -13.6] dB; F1,126 = 5.90; P = .02; partial ηp2 = 0.05) and were younger at diagnosis (mean [SD] age, 23.1 [8.4] [95% CI, 17.2-29.1] vs 31.5 [8.0] [95% CI, 30.1-33.0] years; F1,122 = 7

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

    International Nuclear Information System (INIS)

    Chung, Moon Ki; Park, Chun Kyeong; Yang, Seon Kyu; Chung, Chang Hwan; Chun, Shee Yeong; Song, Cheol Hwa; Chun, Hyeong Gil; Chang, Seok Kyu; Chung, Heung Joon; Won, Soon Yeon; Cho, Yeong Ro; Kim, Bok Deuk; Min, Kyeong Ho

    1994-07-01

    The present research aims at the development of the thermal hydraulic verification test technology for the reactor safety system of the conventional and advanced nuclear power plant and the development of the advanced thermal hydraulic measuring techniques. (Author)

  11. Collaborating with nurse leaders to develop patient safety practices.

    Science.gov (United States)

    Kanerva, Anne; Kivinen, Tuula; Lammintakanen, Johanna

    2017-07-03

    Purpose The organisational level and leadership development are crucial elements in advancing patient safety, because patient safety weaknesses are often caused by system failures. However, little is known about how frontline leader and director teams can be supported to develop patient safety practices. The purpose of this study is to describe the patient safety development process carried out by nursing leaders and directors. The research questions were: how the chosen development areas progressed in six months' time and how nursing leaders view the participatory development process. Design/methodology/approach Participatory action research was used to engage frontline nursing leaders and directors into developing patient safety practices. Semi-structured group interviews ( N = 10) were used in data collection at the end of a six-month action cycle, and data were analysed using content analysis. Findings The participatory development process enhanced collaboration and gave leaders insights into patient safety as a part of the hospital system and their role in advancing it. The chosen development areas advanced to different extents, with the greatest improvements in those areas with simple guidelines to follow and in which the leaders were most participative. The features of high-reliability organisation were moderately identified in the nursing leaders' actions and views. For example, acting as a change agent to implement patient safety practices was challenging. Participatory methods can be used to support leaders into advancing patient safety. However, it is important that the participants are familiar with the method, and there are enough facilitators to steer development processes. Originality/value Research brings more knowledge of how leaders can increase their effectiveness in advancing patient safety and promoting high-reliability organisation features in the healthcare organisation.

  12. Advanced Concepts for Pressure-Channel Reactors: Modularity, Performance and Safety

    Science.gov (United States)

    Duffey, Romney B.; Pioro, Igor L.; Kuran, Sermet

    Based on an analysis of the development of advanced concepts for pressure-tube reactor technology, we adapt and adopt the pressure-tube reactor advantage of modularity, so that the subdivided core has the potential for optimization of the core, safety, fuel cycle and thermal performance independently, while retaining passive safety features. In addition, by adopting supercritical water-cooling, the logical developments from existing supercritical turbine technology and “steam” systems can be utilized. Supercritical and ultra-supercritical boilers and turbines have been operating for some time in coal-fired power plants. Using coolant outlet temperatures of about 625°C achieves operating plant thermal efficiencies in the order of 45-48%, using a direct turbine cycle. In addition, by using reheat channels, the plant has the potential to produce low-cost process heat, in amounts that are customer and market dependent. The use of reheat systems further increases the overall thermal efficiency to 55% and beyond. With the flexibility of a range of plant sizes suitable for both small (400 MWe) and large (1400 MWe) electric grids, and the ability for co-generation of electric power, process heat, and hydrogen, the concept is competitive. The choice of core power, reheat channel number and exit temperature are all set by customer and materials requirements. The pressure channel is a key technology that is needed to make use of supercritical water (SCW) in CANDU®1 reactors feasible. By optimizing the fuel bundle and fuel channel, convection and conduction assure heat removal using passive-moderator cooling. Potential for severe core damage can be almost eliminated, even without the necessity of activating the emergency-cooling systems. The small size of containment structure lends itself to a small footprint, impacts economics and building techniques. Design features related to Canadian concepts are discussed in this paper. The main conclusion is that development of

  13. Present status of education for radiation safety during clinical examinations and the role of the radiological technologist

    International Nuclear Information System (INIS)

    Satou, Yukimitsu

    1988-01-01

    The applications of radiation to the medical field are increasing steadily, along with advances in radiation technology and development of new medical equipment. Medical applications of radiation differ from applications in other fields, because the patient is exposed to radiation during examination and radiotherapy. Consequently, it is important that training courses in radiation safety for radiological technologists, medical doctors and nurses be periodically carried out to ensure a more effective and safe utilization of radiation. Furthermore, it is important that such training be based on a practical education curriculum, including basic knowledge, technical training, and safe habits. In this paper, we discuss the appropriate role and attitudes of the radiological technologist in radiation safety education. (author)

  14. Present status of education for radiation safety during clinical examinations and the role of the radiological technologist

    Energy Technology Data Exchange (ETDEWEB)

    Satou, Yukimitsu

    1988-10-01

    The applications of radiation to the medical field are increasing steadily, along with advances in radiation technology and development of new medical equipment. Medical applications of radiation differ from applications in other fields, because the patient is exposed to radiation during examination and radiotherapy. Consequently, it is important that training courses in radiation safety for radiological technologists, medical doctors and nurses be periodically carried out to ensure a more effective and safe utilization of radiation. Furthermore, it is important that such training be based on a practical education curriculum, including basic knowledge, technical training, and safe habits. In this paper, we discuss the appropriate role and attitudes of the radiological technologist in radiation safety education.

  15. Aligning the 3Rs with new paradigms in the safety assessment of chemicals.

    Science.gov (United States)

    Burden, Natalie; Mahony, Catherine; Müller, Boris P; Terry, Claire; Westmoreland, Carl; Kimber, Ian

    2015-04-01

    There are currently several factors driving a move away from the reliance on in vivo toxicity testing for the purposes of chemical safety assessment. Progress has started to be made in the development and validation of non-animal methods. However, recent advances in the biosciences provide exciting opportunities to accelerate this process and to ensure that the alternative paradigms for hazard identification and risk assessment deliver lasting 3Rs benefits, whilst improving the quality and relevance of safety assessment. The NC3Rs, a UK-based scientific organisation which supports the development and application of novel 3Rs techniques and approaches, held a workshop recently which brought together over 20 international experts in the field of chemical safety assessment. The aim of this workshop was to review the current scientific, technical and regulatory landscapes, and to identify key opportunities towards reaching these goals. Here, we consider areas where further strategic investment will need to be focused if significant impact on 3Rs is to be matched with improved safety science, and why the timing is right for the field to work together towards an environment where we no longer rely on whole animal data for the accurate safety assessment of chemicals.

  16. Assessment of modular construction for safety-related structures at advanced nuclear power plants

    International Nuclear Information System (INIS)

    Braverman, J.; Morante, R.; Hofmayer, C.

    1997-03-01

    Modular construction techniques have been successfully used in a number of industries, both domestically and internationally. Recently, the use of structural modules has been proposed for advanced nuclear power plants. The objective in utilizing modular construction is to reduce the construction schedule, reduce construction costs, and improve the quality of construction. This report documents the results of a program which evaluated the proposed use of modular construction for safety-related structures in advanced nuclear power plant designs. The program included review of current modular construction technology, development of licensing review criteria for modular construction, and initial validation of currently available analytical techniques applied to concrete-filled steel structural modules. The program was conducted in three phases. The objective of the first phase was to identify the technical issues and the need for further study in order to support NRC licensing review activities. The two key findings were the need for supplementary review criteria to augment the Standard Review Plan and the need for verified design/analysis methodology for unique types of modules, such as the concrete-filled steel module. In the second phase of this program, Modular Construction Review Criteria were developed to provide guidance for licensing reviews. In the third phase, an analysis effort was conducted to determine if currently available finite element analysis techniques can be used to predict the response of concrete-filled steel modules

  17. The state of art report on advanced reactor development

    International Nuclear Information System (INIS)

    Kim, Keung Koo; Noh, J. M.; Hwang, D. H. and others

    1999-07-01

    Recently, researches on the advanced power reactors are being performed actively, that maximize the economics and enhance the reactor safety by introducing the inherent safety characteristics and passive safety features. In the development of advanced reactor technology, we developed the inherent core design technologies which can form a foundation of indigenous technologies to provide the basic technology for the core design of the domestic advanced reactor. In this report, we examined the neutronics design technologies and core thermal hydraulics design technologies for advanced reactors performed all over the world. Major efforts are focussed on the soluble boron free core design technology and high conversion core design technology. In addition to these, new conceptual core, such as a supercritical core, design technology development was also reviewed. The characteristics of critical heat flux have been investigated for non-square lattice rod bundles, such as triangular lattice and wire wrap lattice. Based on the status of advanced reactor development, the soluble boron free and hexagonal lattice core design technologies are elementary technology for the domestic advanced reactor core. These elementary core technologies would enhance the reactor safety and improve the economics. (author). 71 refs., 31 tabs., 74 figs

  18. Best estimate probabilistic safety assessment results for the Westinghouse Advanced Loop Tester (WALT)

    International Nuclear Information System (INIS)

    Wang, Guoqiang; Xu, Yiban; Oelrich, Robert L. Jr.; Byers, William A.; Young, Michael Y.; Karoutas, Zeses E.

    2011-01-01

    The nuclear industry uses the probabilistic safety assessment (PSA) technique to improve safety decision making and operation. The methodology evaluates the system reliability, which is defined as the probability of system success, and the postulated accident/problematic scenarios of systems for the nuclear power plants or other facilities. The best estimate probabilistic safety assessment (BE-PSA) method of evaluating system reliability and postulated problematic scenarios will produce more detailed results of interest, such as best estimated reliability analysis and detailed thermal hydraulic calculations using a sub-channel or Computational Fluid Dynamics (CFD) code. The methodology is typically applied to reactors, but can also be applied to any system such as a test facility. In this paper, a BE-PSA method is introduced and used for evaluating the Westinghouse Advanced Loop Tester (WALT). The WALT test loop at the George Westinghouse Science and Technology Center (STC), which was completed in October 2005, is designed to be utilized to model the top grid span of a hot rod in a fuel assembly under the Pressurizer Water Reactor (PWR) normal operating conditions. In order to safely and successfully operate the WALT test loop and correctly use the WALT experimental data, it is beneficial to perform a probabilistic safety assessment and analyze the thermal hydraulic results for the WALT loop in detail. Since October 2005, a number of test runs have been performed on the WALT test facility designed and fabricated by Westinghouse Electric Company LLC. This paper briefly describes the BE-PSA method and performs BE-PSA for the WALT loop. Event trees linked with fault trees embedding thermal hydraulic analysis models, such as sub-channel and/or CFD models, were utilized in the analyses. Consequently, some selected useful experimental data and analysis results are presented for future guidance on WALT and/or other similar test facilities. For example, finding and

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

    International Nuclear Information System (INIS)

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

    1998-01-01

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

  20. Advanced fuels with reduced actinide generation. Proceedings of a technical committee meeting

    International Nuclear Information System (INIS)

    1996-11-01

    Nuclear energy can play an important future role in supplying the world population with energy. However, this form of energy will be successful only under certain conditions: it must meet very strict safety requirements, it must be economically competitive, and it must be acceptable to the public. Nuclear power produces radioactive wastes and in several countries the public raises concern about safety. Much development work on advanced nuclear power systems is going on in several countries, with participation of both governmental and private industries to meet these conditions. In the framework of this IAEA activity the Technical Committee Meeting on Advanced Fuels with Reduced Actinide Generation was organized. The aim of the meeting was to highlight current research activities and to identify new research areas and fields of possible co-operation. The scope of the meeting included advanced fuels for all types of nuclear reactors: light water reactors, heavy water reactors, high temperature reactors, fast reactors, molten salt reactors and for accelerator driven systems. Other topics covered a wide range of investigations made, or to be made in the Member States. Refs, figs, tabs

  1. Safety-related subject fields, institutions, associations, inspection boards and authorities

    International Nuclear Information System (INIS)

    Cebulla, E.

    1986-01-01

    The chapter outlines the various branches of industry where safety plays an important role, adapting the scheme applied by the Federal German Labour Office. The various sections of this chapter deal with legal provisions and relevant institutions, with natural and man-made hazards, with industrial systems requiring inspection and surveillance, with agriculture and forestry including animal husbandry, with manufacturing branches, the building industry, traffic and transport, with the services sector, househoulds, leisure and sports, and with establishments and activities where the handling of radioactive substances is a major source of hazards (e.g. in the medical field, for which a particularly extensive literature index is given). Aspects of power supply industries and water pollution prevention are discussed where appropriate. (DG) [de

  2. Identification of improvements of advanced light water reactor concepts

    International Nuclear Information System (INIS)

    Frisch, W.; Liesch, K.; Riegel, B.

    1993-01-01

    The scope of this report is to identify the improvement of reactor developments with respect to reactor safety. This includes the collection of non-proprietary information on the description of the advanced design characteristics, especially summary design descriptions and general publications. This documentation is not intended to include a safety evaluation of the advanced concepts; however, it is structured in such a way that it can serve as a basis for a future safety evaluation. This is taken into account in the structure of the information regarding the distinction of the various concepts with respect to their 'advancement' and the classification of design characteristics according to some basic safety aspects. The overall description concentrates on those features which are relevant to safety. Other aspects, such as economy, operational features, maintenance, the construction period, etc...are not considered explicitly in this report

  3. Reports on the projects in the field of reactor safety sponsored by the Federal Ministry for Research and Technology

    International Nuclear Information System (INIS)

    1977-06-01

    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 energy plants and their systems and the further development of safety technology. The GRS (Reactor Safety Association), Gesellschaft fuer Reaktorsicherheit mbH, by order of the BMFT, informs continuously of the status of these investigations within the series 'GRS-F-Forschrittsberichte' (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

  4. 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

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

    International Nuclear Information System (INIS)

    1977-12-01

    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 energy plants and their systems and the further development of safety technology. The GRS (Reactor Safety Association), Gesellschaft fuer Reaktorsicherheit mbH, by order of the 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

  6. Design on human supervisory control of safety management for advance NPP

    International Nuclear Information System (INIS)

    Nugroho, D.H.; Soentono, S.; Taryo, T.; Wahyon, P.I.

    2006-01-01

    Full text: Full text: Characteristics of an advance NPP related with economic and safety enhancement was represented on capabilities in intelligent control and diagnostic to provide nearly autonomous operation with anticipatory maintenance. An autonomous control system should enable automatic operation while adapting to component faults and system variable upsets. It needs therefore to have many intelligent capabilities, such as modeling, analysis, self-validation, diagnosis and decision. This paper describes a human supervisory control design for nuclear reactor fault management which collaborates between human and autonomous control. The beneficial of collaboration is provided based on belief of information value evaluated from Dempster's rule of evidence. The belief of the collaboration is better compared with single usage. The collaboration was conducted in which agent will autonomously and periodically be conducting surveillance by checking the component abnormalities in the plant if anomalies occur. The anomalies were determined using fault detection module. Thereby the system will be able to conduct preventive maintenance. In the situation of accident happened, hence the system will diagnose to determine the location of component failure autonomously. A human supervisor will then determine the action of decison making based on the prediction result. The decision making will be conducted based on the 4th Sheridan's autonomous level in which the autonomous control will execute the duty autonomously when the plant is in normal condition, or in the predictable accident range. But if the unpredictable accident occurs in the plant, the supervisor will then take over the role to control the plant, and the machine will do what commanded by the supervisor. Sistematically, the system explained before was represented by Traveling Salesman Problem-based surveillance, modified ART-2 artificial neural networks-based fault detection and Bayesian Networks-based fault

  7. Nuclear safety guide TID-7016 Revision 2

    International Nuclear Information System (INIS)

    Thomas, J.T.

    1980-01-01

    The present revision of TID-7016 Nuclear Safety Guide is discussed. This Guide differs significantly from its predecessor in that the latter was intentionally conservative in its recommendations. Firmly based on experimental evidence of criticality, the original Guide and the first revision were considered to be of most value to organizations whose activities with fissionable materials were not extensive and, secondarily, that it would serve as a point of departure for members of established nuclear safety teams, experienced in the field. The reader will find a significant change in the character of information presented in this version. Nuclear Criticality Safety has matured in the past twelve years. The advance of calculational capability has permitted validated calculations to extend and substitute for experimental data. The broadened data base has enabled better interpolation, extension, and understanding of available, information, especially in areas previously addressed by undefined but adequate factors of safety. The content has been thereby enriched in qualitative guidance. The information inherently contains, and the user can recapture, the quantitative guidance characteristic of the former Guides by employing appropriate safety factors. In fact, it becomes incumbent on the Criticality Safety Specialist to necessarily impose safety factors consistent with the possible normal and abnormal credible contingencies of an operation as revealed by his evaluation. In its present form the Guide easily becomes a suitable module in any compendium or handbook tailored for internal use by organizations. It is hoped the Guide will continue to serve immediate needs and will encourage continuing and more comprehensive efforts toward organizing nuclear criticality safety information

  8. Digital Signal Processing for In-Vehicle Systems and Safety

    CERN Document Server

    Boyraz, Pinar; Takeda, Kazuya; Abut, Hüseyin

    2012-01-01

    Compiled from papers of the 4th Biennial Workshop on DSP (Digital Signal Processing) for In-Vehicle Systems and Safety this edited collection features world-class experts from diverse fields focusing on integrating smart in-vehicle systems with human factors to enhance safety in automobiles. Digital Signal Processing for In-Vehicle Systems and Safety presents new approaches on how to reduce driver inattention and prevent road accidents. The material addresses DSP technologies in adaptive automobiles, in-vehicle dialogue systems, human machine interfaces, video and audio processing, and in-vehicle speech systems. The volume also features: Recent advances in Smart-Car technology – vehicles that take into account and conform to the driver Driver-vehicle interfaces that take into account the driving task and cognitive load of the driver Best practices for In-Vehicle Corpus Development and distribution Information on multi-sensor analysis and fusion techniques for robust driver monitoring and driver recognition ...

  9. A single-arm, multicenter, safety-monitoring, phase IV study of icotinib in treating advanced non-small cell lung cancer (NSCLC).

    Science.gov (United States)

    Hu, Xingsheng; Han, Baohui; Gu, Aiqin; Zhang, Yiping; Jiao, Shun Chang; Wang, Chang-Li; He, Jintao; Jia, Xueke; Zhang, Li; Peng, Jiewen; Wu, Meina; Ying, Kejing; Wang, Junye; Ma, Kewei; Zhang, Shucai; You, Changxuan; Tan, Fenlai; Wang, Yinxiang; Ding, Lieming; Sun, Yan

    2014-11-01

    The phase 3 ICOGEN trial established the non-inferiority of icotinib to gefitinib in terms of progression-free survival (PFS) in non-small cell lung cancer (NSCLC) patients, and this led to the approval of icotinib for NSCLC by the China Food and Drug Administration. A phase 4 study was conducted to assess the safety and efficacy of icotinib in a broad range of patients with advanced NSCLC across China. This study retrospectively analyzed data from unresectable, recurrent, and/or advanced NSCLC patients who received oral icotinib 125 mg three times per day. The primary endpoint was safety. The secondary endpoints included objective response rate (ORR) and disease control rate (DCR), which were investigated overall and in subgroups such as patients with an EGFR mutation and elderly patients. Between August, 2011 and August, 2012, a total of 6087 advanced NSCLC patients were registered in this study, of which 5549 were evaluable for safety and tumor response. The median age was 63 years (range 21-95 years), and 1571 (28.3%) patients were over the age of 70. The majority of patients were non-smokers, and had adenocarcinoma and stage IV disease. The overall incidence of adverse drug reactions (ADRs) of any grade was 31.5%. The most common ADRs included rash (17.4%) and diarrhea (8.5%), and three patients experienced interstitial lung disease (ILD). The ORR and DCR were 30.0% and 80.6%, respectively, for the overall population, and 33.4% and 81.2%, 30.3% and 80.3%, and 30.4% and 89.3%, for first-line, second-line, and third-line or multiple line subsets, respectively. In 665 EGFR-mutated patients who were evaluable for tumor response, the ORR and DCR were 49.2% (327/665) and 92.3% (614/665), respectively. The data from over 6000 patients was consistent with the results of the ICOGEN study. Icotinib demonstrated a favorable toxicity profile and efficacy in the routine clinical setting. Copyright © 2014 Elsevier Ireland Ltd. All rights reserved.

  10. Efficacy and safety of benazepril for advanced chronic renal insufficiency.

    Science.gov (United States)

    Hou, Fan Fan; Zhang, Xun; Zhang, Guo Hua; Xie, Di; Chen, Ping Yan; Zhang, Wei Ru; Jiang, Jian Ping; Liang, Min; Wang, Guo Bao; Liu, Zheng Rong; Geng, Ren Wen

    2006-01-12

    Angiotensin-converting-enzyme inhibitors provide renal protection in patients with mild-to-moderate renal insufficiency (serum creatinine level, 3.0 mg per deciliter or less). We assessed the efficacy and safety of benazepril in patients without diabetes who had advanced renal insufficiency. We enrolled 422 patients in a randomized, double-blind study. After an eight-week run-in period, 104 patients with serum creatinine levels of 1.5 to 3.0 mg per deciliter (group 1) received 20 mg of benazepril per day, whereas 224 patients with serum creatinine levels of 3.1 to 5.0 mg per deciliter (group 2) were randomly assigned to receive 20 mg of benazepril per day (112 patients) or placebo (112 patients) and then followed for a mean of 3.4 years. All patients received conventional antihypertensive therapy. The primary outcome was the composite of a doubling of the serum creatinine level, end-stage renal disease, or death. Secondary end points included changes in the level of proteinuria and the rate of progression of renal disease. Of 102 patients in group 1, 22 (22 percent) reached the primary end point, as compared with 44 of 108 patients given benazepril in group 2 (41 percent) and 65 of 107 patients given placebo in group 2 (60 percent). As compared with placebo, benazepril was associated with a 43 percent reduction in the risk of the primary end point in group 2 (P=0.005). This benefit did not appear to be attributable to blood-pressure control. Benazepril therapy was associated with a 52 percent reduction in the level of proteinuria and a reduction of 23 percent in the rate of decline in renal function. The overall incidence of major adverse events in the benazepril and placebo subgroups of group 2 was similar. Benazepril conferred substantial renal benefits in patients without diabetes who had advanced renal insufficiency. (ClinicalTrials.gov number, NCT00270426.) Copyright 2006 Massachusetts Medical Society.

  11. CEC activities in the field of LMFBR safety

    International Nuclear Information System (INIS)

    Balz, W.; Finzi, S.; Klersy, R.

    1976-01-01

    The aim of the ECC is to reach a common LMFBR Safety strategy in Europe. To this end the Commission promotes collaboration between the different fast reactor projects in the Community through working groups and collaborative arrangements and contributes with a research activity executed in its Joint Research Centre Ispra. A short description is given of the activity in the working groups and of the Ispra programme on LMFBR Safety. This programme covers: LMFBR thermohydraulics, fuel coolant interactions, dynamic structure loading and response, safety related material properties and whole core accident code development

  12. Safety regulations for radioisotopes, etc. (interim report)

    International Nuclear Information System (INIS)

    1980-01-01

    An (interim) report by an ad hoc expert committee to the Nuclear Safety Commission, on the safety regulations for radioisotopes, etc., was presented. For the utilization of radioisotopes, etc., there is the Law Concerning Prevention of Radiation Injury Due to Radioisotopes, etc. with the advances in this field and the improvement in international standards, the regulations by the law have been examined. After explaining the basic ideas of the regulations, the problems and countermeasures in the current regulations are described: legal system, rationalization in permission procedures and others, inspection on RI management, the system of the persons in charge of radiation handling, RI transport, low-level radioactive wastes, consumer goods, definitions of RIs, radiation and sealed sources, regulations by group partitioning, RI facilities, system of personnel exposure registration, entrusting of inspection, etc. to private firms, and reduction in the works for permission among governmental offices. (author)

  13. Integration of Active and Passive Safety Technologies--A Method to Study and Estimate Field Capability.

    Science.gov (United States)

    Hu, Jingwen; Flannagan, Carol A; Bao, Shan; McCoy, Robert W; Siasoco, Kevin M; Barbat, Saeed

    2015-11-01

    The objective of this study is to develop a method that uses a combination of field data analysis, naturalistic driving data analysis, and computational simulations to explore the potential injury reduction capabilities of integrating passive and active safety systems in frontal impact conditions. For the purposes of this study, the active safety system is actually a driver assist (DA) feature that has the potential to reduce delta-V prior to a crash, in frontal or other crash scenarios. A field data analysis was first conducted to estimate the delta-V distribution change based on an assumption of 20% crash avoidance resulting from a pre-crash braking DA feature. Analysis of changes in driver head location during 470 hard braking events in a naturalistic driving study found that drivers' head positions were mostly in the center position before the braking onset, while the percentage of time drivers leaning forward or backward increased significantly after the braking onset. Parametric studies with a total of 4800 MADYMO simulations showed that both delta-V and occupant pre-crash posture had pronounced effects on occupant injury risks and on the optimal restraint designs. By combining the results for the delta-V and head position distribution changes, a weighted average of injury risk reduction of 17% and 48% was predicted by the 50th percentile Anthropomorphic Test Device (ATD) model and human body model, respectively, with the assumption that the restraint system can adapt to the specific delta-V and pre-crash posture. This study demonstrated the potential for further reducing occupant injury risk in frontal crashes by the integration of a passive safety system with a DA feature. Future analyses considering more vehicle models, various crash conditions, and variations of occupant characteristics, such as age, gender, weight, and height, are necessary to further investigate the potential capability of integrating passive and DA or active safety systems.

  14. Performance of the visual field index in glaucoma patients with moderately advanced visual field loss.

    Science.gov (United States)

    Lee, Jun Mo; Cirineo, Nila; Ramanathan, Meera; Nouri-Mahdavi, Kouros; Morales, Esteban; Coleman, Anne L; Caprioli, Joseph

    2014-01-01

    To explore the relationship between the visual field index (VFI) and the visual field mean deviation (MD) in glaucoma patients with moderately advanced perimetric damage and to identify the magnitude of the boundary effect of VFI that occurred when the VFI estimation strategy changed from pattern deviation probability value to total deviation probability value as the MD crossed -20 dB in longitudinal visual field (VF) series. A retrospective cohort study of longitudinal data analysis. The MD and VFI values obtained from VF tests conducted on 148 eyes of 148 glaucoma patients having an MD around -20 dB were studied. A total of 1286 VFs with MD values within the range of -16 dB to -24 dB were included. The eyes were divided into 2 groups, with the first having serial MDs all better than or all worse than -20 dB and the second with serial MDs crossing the -20 dB value. Change in MD (ΔMD) was defined as the absolute difference between the MD values of 2 consecutive VFs. Based on the 2 VFI values of the same VFs, the absolute value of change in VFI (ΔVFI) was calculated. The means (± standard deviation) for the ΔVFI were 4.17% (± 3.3%) in the group of eyes with MDs on either side of -20 dB, and were 15.8% (± 8.4%) in the group with MDs crossing -20 dB (P values were 6.8%/dB (± 10.5%) when the range of MD falls on either side of -20 dB, and 7.9%/dB (± 6.2%) when the range of MD crosses the -20 dB values (P = .042). The values of the VFI become highly variable in serial VFs of eyes with MDs crossing -20 dB, in comparison to those VFIs associated with MDs on either side of -20 dB. The likelihood for this effect is the change from use of pattern deviation probability value to total deviation probability value in the points included in the calculation of VFI at -20 dB of MD. The development of indices to measure VF rates that are free from this boundary effect in moderately advanced glaucoma is desirable. Copyright © 2014. Published by Elsevier Inc.

  15. Advances in electron dosimetry of irregular fields; Avances en dosimetria de electrones de campos irregulares

    Energy Technology Data Exchange (ETDEWEB)

    Mendez V, J. [Departamento de Radioterapia, Instituto de Enfermedades Neoplasicas, Avenida Angamos Este 2520, Lima 34 (Peru)

    1998-12-31

    In this work it is presented an advance in Electron dosimetry of irregular fields for beams emitted by linear accelerators. At present diverse methods exist which are coming to apply in the Radiotherapy centers. In this work it is proposed a method for irregular fields dosimetry. It will be allow to calculate the dose rate absorbed required for evaluating the time for the treatment of cancer patients. Utilizing the results obtained by the dosimetric system, it has been possible to prove the validity of the method describe for 12 MeV energy and for square field 7.5 x 7.5 cm{sup 2} with percentile error less than 1 % . (Author)

  16. Modeling of Dipole and Quadrupole Fringe-Field Effects for the Advanced Photon Source Upgrade Lattice

    Energy Technology Data Exchange (ETDEWEB)

    Borland, M.; Lindberg, R.

    2017-06-01

    The proposed upgrade of the Advanced Photon Source (APS) to a multibend-achromat lattice requires shorter and much stronger quadrupole magnets than are present in the existing ring. This results in longitudinal gradient profiles that differ significantly from a hard-edge model. Additionally, the lattice assumes the use of five-segment longitudinal gradient dipoles. Under these circumstances, the effects of fringe fields and detailed field distributions are of interest. We evaluated the effect of soft-edge fringe fields on the linear optics and chromaticity, finding that compensation for these effects is readily accomplished. In addition, we evaluated the reliability of standard methods of simulating hardedge nonlinear fringe effects in quadrupoles.

  17. Advancing CANDU Technology Through R and D

    International Nuclear Information System (INIS)

    Torgerson, David F.

    1993-01-01

    CANDU reactors are evolving to meet future requirements using incremental changes as opposed to revolutionary design changes. The main elements for advancing the technology reducing capital and operating, increasing capacity factors, increasing passive safety, and enhancing fuel/fuel cycle flexibility. These elements are being addressed by carrying out research and development in the areas of safety, plant systems and components, heavy water production, information technology, fuel channels, and fuel/fuel cycle technology. In safety, the focus is on using the inherent features of CANDU to enhance passive or natural safety concepts, such as the use of the moderator as an effective heat sink, and the development of advanced fuels to improve critical heat flux and to reduce source terms. Plant systems and components work includes improvements to plant systems such as steam generators, heat exchangers, pump seals, and advanced control room technology. Heavy water processes are being developed that can be used with existing hydrogen production plants, or that can be used in a stand-alone mode. Information technology is being developed to cover all aspects of CANDU design, construction, and operation. Fuel channel improvements include elucidation and application of basic materials science for life extension, and the development of advanced non-destructive examination methods. Fuel and fuel cycle work is focusing on LWR/CANDU synergy, such as the use of recovered uranium and the direct use of spent PWR fuel in CANDU reactor, advanced fuels to improve burnup and economics (e. g., the joint AECB/KAERI Conflux program), and low void reactivity fuel to enhance passive safety. This paper gives an overview of some of the R and D supporting these activities, with particular emphasis on Alice's vision for advancing CANDU technology over the next 10 years

  18. Institutional and scientific co-operation, networking and capacity building in the field of food safety and quality

    NARCIS (Netherlands)

    Boekel, van M.A.J.S.; Meerdink, G.; Banati, D.; Marvin, H.J.P.; Kuiper, H.A.; Houtman, C.B.

    2002-01-01

    This paper explains the situation in Hungary and The Netherlands regarding scientific co-operation, networking and capacity building in the field of food quality and safety. Specific details are given about institutional co-operation including exchanges between staff and students, collaborative

  19. Laser Induced Breakdown Spectroscopy, advances in resolution and portability

    International Nuclear Information System (INIS)

    Ponce, L.; Flores, T.; Arronte, M.; Moreira, L.; Hernandez, L. C.; Posada, E. de

    2009-01-01

    Laser Induced Breakdown Spectroscopy (LIBS), can be considered as one of the most dynamic and promising technique in the field of analytical spectroscopy. LIBS has turned into a powerful alternative for a wide front of applications, from the geological exploration to the industrial inspection, including the environmental monitoring, the biomedical analysis, the study of patrimonial works, the safety and defense. The advances in LIBS instrumentation have allowed improving gradually the analysis services and quality, on the basis of a better knowledge of the technology principles. Recently, systems of double pulse have facilitated a better dosing of energy, the improvement of the signal-noise relation and the study of the different process stages. Femtosecond lasers offers the possibility of study in detail the ablation and atomic emission processes. New advances like multi-pulse or multi-wavelength systems -in fact stilling without exploring, must offer new information to advance in this knowledge. Finally, which it does to this technology really attractive, is the aptitude to be employed in field conditions, or for the detection of the elementary composition at long distances. In this presentation there are discussed the designs of portable instrumentation, compact and low cost, which can improve substantially the LIBS possibilities. (Author)

  20. Advanced Electron Holography Applied to Electromagnetic Field Study in Materials Science.

    Science.gov (United States)

    Shindo, Daisuke; Tanigaki, Toshiaki; Park, Hyun Soon

    2017-07-01

    Advances and applications of electron holography to the study of electromagnetic fields in various functional materials are presented. In particular, the development of split-illumination electron holography, which introduces a biprism in the illumination system of a holography electron microscope, enables highly accurate observations of electromagnetic fields and the expansion of the observable area. First, the charge distributions on insulating materials were studied by using split-illumination electron holography and including a mask in the illumination system. Second, the three-dimensional spin configurations of skyrmion lattices in a helimagnet were visualized by using a high-voltage holography electron microscope. Third, the pinning of the magnetic flux lines in a high-temperature superconductor YBa 2 Cu 3 O 7-y was analyzed by combining electron holography and scanning ion microscopy. Finally, the dynamic accumulation and collective motions of electrons around insulating biomaterial surfaces were observed by utilizing the amplitude reconstruction processes of electron holography. © 2016 WILEY-VCH Verlag GmbH & Co. KGaA, Weinheim.

  1. AGNES - safety reassessment of Paks NPP

    International Nuclear Information System (INIS)

    Gado, J.

    1995-01-01

    The main goal of the AGNES (Advanced General and New Evaluation of Safety) project for the reassessment of the safety of Paks Nuclear Power Plant, Hungary, was to improve the safety culture of the technology at Paks. A report was prepared on the reassessment of the Paks NPP safety. The analysis was divided into four groups: systems analysis, analysis of design basis accidents, severe accident analysis, and level 1 probabilistic safety analysis. Proposed safety enhancement measures are discussed. (N.T.)

  2. Advanced nuclear systems. Review study; Fortgeschrittene Nuklearsysteme. Review Study

    Energy Technology Data Exchange (ETDEWEB)

    Liebert, Wolfgang; Glaser, Alexander; Pistner, Christoph [Interdisziplinaere Arbeitsgruppe Naturwissenschaft, Technik und Sicherheit (IANUS), Darmstadt University of Technology, Hochschulstrasse 10, D-64289 Darmstadt (Germany); Baehr, Roland; Hahn, Lothar [Institute for applied ecology (Oeko-Institut), Elisabethenstrasse 55-57, D-64283 Darmstadt (Germany)

    1999-04-01

    The task of this review study is to from provide an overview of the developments in the field of the various advanced nuclear systems, and to create the basis for more comprehensive studies of technology assessment. In an overview the concepts for advanced nuclear systems pursued worldwide are subdivided into eight subgroups. A coarse examination raster (set pattern) is developed to enable a detailed examination of the selected systems. In addition to a focus on enhanced safety features, further aspects are also taken into consideration, like the lowering of the proliferation risk, the enhancement of the economic competitiveness of the facilities and new usage possibilities (for instance concerning the relaxation of the waste disposal problem or the usage of alternative fuels to uranium). The question about the expected time span for realization and the discussion about the obstacles on the way to a commercially usable reactor also play a substantial role as well as disposal requirements as far as they can be presently recognized. In the central chapter of this study, the documentation of the representatively selected concepts is evaluated as well as existing technology assessment studies and expert opinions. In a few cases where this appears to be necessary, according technical literature, further policy advisory reports, expert statements as well as other relevant sources are taken into account. Contradictions, different assessments and dissents in the literature as well as a few unsettled questions are thus indicated. The potential of advanced nuclear systems with respect to economical and societal as well as environmental objectives cannot exclusively be measured by the corresponding intrinsic or in comparison remarkable technical improvements. The acceptability of novel or improved systems in nuclear technology will have to be judged by their convincing solutions for the crucial questions of safety, nuclear waste and risk of proliferation of nuclear weapons

  3. Status of researches in the field of safety of pressurized water reactors

    International Nuclear Information System (INIS)

    Couturier, Jean; Schwarz, Michel

    2017-01-01

    This collective publication proposes a synthesis of the status of researches performed in the field of safety of pressurized water reactors. They may discuss past, current and projected research works, involved actors, or lessons learned from these works. The authors propose a presentation of some research tools privileged by the IRSN for these researches: the CABRI and PHEBUS reactors, the GALAXIE experimental platform, and some other installations. Then they address researches related to loss-of-coolant accidents (two-phase thermohydraulics, fuel rod behaviour), to reactivity accidents, to accidents related to dewatering of irradiated fuel storage pools, to fires, to extreme aggressions of natural origin (earthquake, extreme flooding), to core fusion accidents (core heating and fusion within the vessel, vessel failure and apron erosion by corium, containment enclosure dynamic loading, release of radioactive products), to the behaviour of nuclear plant important metallic or civil works components and notably to their ageing, to organisational and human factors or more generally to social and human sciences (design of control rooms, safety organisation and management in EDF nuclear plants), and to other issues and research perspectives

  4. Safety and efficacy results of the advanced renal cell carcinoma sorafenib expanded access program in North America.

    Science.gov (United States)

    Stadler, Walter M; Figlin, Robert A; McDermott, David F; Dutcher, Janice P; Knox, Jennifer J; Miller, Wilson H; Hainsworth, John D; Henderson, Charles A; George, Jeffrey R; Hajdenberg, Julio; Kindwall-Keller, Tamila L; Ernstoff, Marc S; Drabkin, Harry A; Curti, Brendan D; Chu, Luis; Ryan, Christopher W; Hotte, Sebastien J; Xia, Chenghua; Cupit, Lisa; Bukowski, Ronald M

    2010-03-01

    The Advanced Renal Cell Carcinoma Sorafenib (ARCCS) program made sorafenib available to patients with advanced renal cell carcinoma (RCC) before regulatory approval. In this nonrandomized, open-label expanded access program, 2504 patients from the United States and Canada were treated with oral sorafenib 400 mg twice daily. Safety and efficacy were explored overall and in subgroups of patients including those with no prior therapy, nonclear cell (nonclear cell) RCC, brain metastases, prior bevacizumab treatment, and elderly patients. Sorafenib was approved for RCC 6 months after study initiation, at which time patients with no prior therapy or with nonclear cell RCC could enroll in an extension protocol for continued assessment for a period of 6 months. The most common grade > or =2 drug-related adverse events were hand-foot skin reaction (18%), rash (14%), hypertension (12%), and fatigue (11%). In the 1891 patients evaluable for response, complete response was observed in 1 patient, partial response in 67 patients (4%), and stable disease for at least 8 weeks in 1511 patients (80%). Median progression-free survival in the extension population was 36 weeks (95% confidence interval [CI], 33-45 weeks; censorship rate, 56%); median overall survival in the entire population was 50 weeks (95% CI, 46-52 weeks; censorship rate, 63%). The efficacy and safety results were similar across the subgroups. Sorafenib 400 mg twice daily demonstrated activity and a clinically acceptable toxicity profile in all patient subsets enrolled in the ARCCS expanded access program (clinicaltrials.gov identifier: NCT00111020).

  5. Efficacy and safety of everolimus in combination with trastuzumab and paclitaxel in Asian patients with HER2+ advanced breast cancer in BOLERO-1.

    Science.gov (United States)

    Toi, Masakazu; Shao, Zhimin; Hurvitz, Sara; Tseng, Ling-Ming; Zhang, Qingyuan; Shen, Kunwei; Liu, Donggeng; Feng, Jifeng; Xu, Binghe; Wang, Xiaojia; Lee, Keun Seok; Ng, Ting Ying; Ridolfi, Antonia; Noel-Baron, Florence; Ringeisen, Francois; Jiang, Zefei

    2017-04-11

    The current exploratory analysis was performed to evaluate the efficacy and safety of everolimus for treatment of human epidermal growth factor receptor 2-positive (HER2+) advanced breast cancer in the Asian subset of patients in the BOLERO-1 trial. Postmenopausal women with HER2+ advanced breast cancer, who had not received systemic therapy for advanced disease, were randomized 2:1 to receive everolimus or placebo, plus trastuzumab and paclitaxel. The two primary end points were investigator-assessed progression-free survival (PFS) in the full population and in the hormone receptor-negative (HR-) subpopulation. Secondary end points included assessment of the objective response rate, the clinical benefit rate, and safety. In the Asian subset, median PFS was similar in the everolimus (n = 198) and placebo (n = 105) arms in the full analysis set (hazard ratio = 0.82 (95% CI 0.61-1.11)). In the HR- subpopulation, everolimus prolonged median PFS by 10.97 months vs placebo (25.46 vs 14.49 months; hazard ratio = 0.48 (95% CI 0.29-0.79)). In the everolimus arm of the Asian subset, the most common adverse events of any grade were stomatitis (62.2%), diarrhea (48.0%), rash (43.4%) and neutropenia (42.3%). Neutropenia (grade 3: 27.6%; grade 4: 4.6%) and decreased neutrophil count (grade 3: 11.2%; grade 4: 3.6%) were the most frequent grade 3/4 adverse events. Serious adverse events included pneumonia (5.1%), pneumonitis (3.1%), and interstitial lung disease (3.1%). There were three deaths (1.5%) during treatment in the everolimus arm vs none in the placebo arm. The efficacy and safety of everolimus plus trastuzumab and paclitaxel as first-line treatment for HER2+ advanced breast cancer in the Asian subset was consistent with that reported previously in the overall population. ClinicalTrials.gov, NCT00876395 . Registered on 2 April 2009.

  6. FY1994 annual report on the advanced combustion science in microgravity field

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-03-01

    Researches were implemented continuously from the previous year on combustion equipment which enables advanced combustion technologies by studying combustion in a microgravity field, for the purpose of preventing environmental pollution caused by diversification of energy sources and exhaust gasses. In joint studies with NASA, research was conducted at both ends concerning the interaction of fuel droplets in a microgravity field; namely, high pressure combustion of binary fuel sprays at NASA against interaction in high pressure spray combustion of binary fuel at Japan side, and ignition and flame spread in microgravity field at NASA against combustion characteristics of organic solid fuels at Japan side. In fiscal 1994, in addition to the test equipment built in the previous year, a fuel droplet combustion test device was manufactured, as were a gas sampling and analyzing device, particle speed measuring device, and laser induced fluorescence measuring device. The tests using these measuring devices and microgravity test equipment were carried out 112 times, thereby establishing the measuring method of flame structure which was an objective of the present year. (NEDO)

  7. Safety Culture Enhancement Project. Final Report. A Field Study on Approaches to Enhancement of Safety Culture

    Energy Technology Data Exchange (ETDEWEB)

    Lowe, Andrew; Hayward, Brent (Dedale Asia Pacific, Albert Park VIC 3206 (Australia))

    2006-08-15

    This report documents a study with the objective of enhancing safety culture in the Swedish nuclear power industry. A primary objective of this study was to ensure that the latest thinking on human factors principles was being recognised and applied by nuclear power operators as a means of ensuring optimal safety performance. The initial phase of the project was conducted as a pilot study, involving the senior management group at one Swedish nuclear power-producing site. The pilot study enabled the project methodology to be validated after which it was repeated at other Swedish nuclear power industry sites, providing a broad-ranging analysis of opportunities across the industry to enhance safety culture. The introduction to this report contains an overview of safety culture, explains the background to the project and sets out the project rationale and objectives. The methodology used for understanding and analysing the important safety culture issues at each nuclear power site is then described. This section begins with a summary of the processes used in the information gathering and data analysis stage. The six components of the Management Workshops conducted at each site are then described. These workshops used a series of presentations, interactive events and group exercises to: (a) provide feedback to site managers on the safety culture and safety leadership issues identified at their site, and (b) stimulate further safety thinking and provide 'take-away' information and leadership strategies that could be applied to promote safety culture improvements. Section 3, project Findings, contains the main observations and output from the project. These include: - a brief overview of aspects of the local industry operating context that impinge on safety culture; - a summary of strengths or positive attributes observed within the safety culture of the Swedish nuclear industry; - a set of identified opportunities for further improvement; - the aggregated

  8. Safety requirements applicable to the SMART design

    International Nuclear Information System (INIS)

    Seul, Kwang Won; Kim, Wee Kyong; Kim, Hho Jung

    1999-01-01

    The 330 MW thermal power of integral reactor, named SMART (System integrated Modular Advanced ReacTor), is under development at KAERI for seawater desalination application and electricity generation. The final product of nuclear desalination plant (NDP) is electricity and fresh water. Thus, in addition to the protection of the public around the plant facility from the possible release of radioactive materials, the fresh water should be prevented from radioactivity contamination. In this study, to ensure the safety of SMART reactor in the early stage of design development, the safety requirements applicable to the SMART design were investigated, based on the current regulatory requirements for the existing NPPs and the advanced light water reactor (LWR) designs. The interface requirements related to the desalination facility were also investigated, based on the recent IAEA research activities pertaining to the NDP. As a result, it was found that the current regulatory requirements and guidance for the existing NPPs and advanced LWR designs are applicable to the SMART design and its safety evaluation. However, the safety requirements related to the SMART-specific design and the desalination plant are needed to develop in the future to assure the safety of the SMART reactor

  9. Electromagnetic Field Modeling of Transcranial Electric and Magnetic Stimulation: Targeting, Individualization, and Safety of Convulsive and Subconvulsive Applications

    Science.gov (United States)

    Deng, Zhi-De

    The proliferation of noninvasive transcranial electric and magnetic brain stimulation techniques and applications in recent years has led to important insights into brain function and pathophysiology of brain-based disorders. Transcranial electric and magnetic stimulation encompasses a wide spectrum of methods that have developed into therapeutic interventions for a variety of neurological and psychiatric disorders. Although these methods are at different stages of development, the physical principle underlying these techniques is the similar. Namely, an electromagnetic field is induced in the brain either via current injection through scalp electrodes or via electromagnetic induction. The induced electric field modulates the neuronal transmembrane potentials and, thereby, neuronal excitability or activity. Therefore, knowledge of the induced electric field distribution is key in the design and interpretation of basic research and clinical studies. This work aims to delineate the fundamental physical limitations, tradeoffs, and technological feasibility constraints associated with transcranial electric and magnetic stimulation, in order to inform the development of technologies that deliver safer, and more spatially, temporally, and patient specific stimulation. Part I of this dissertation expounds on the issue of spatial targeting of the electric field. Contrasting electroconvulsive therapy (ECT) and magnetic seizure therapy (MST) configurations that differ markedly in efficacy, side effects, and seizure induction efficiency could advance our understanding of the principles linking treatment parameters and therapeutic outcome and could provide a means of testing hypotheses of the mechanisms of therapeutic action. Using the finite element method, we systematically compare the electric field characteristics of existing forms of ECT and MST. We introduce a method of incorporating a modality-specific neural activation threshold in the electric field models that can

  10. Safety Culture Enhancement Project. Final Report. A Field Study on Approaches to Enhancement of Safety Culture

    International Nuclear Information System (INIS)

    Lowe, Andrew; Hayward, Brent

    2006-08-01

    This report documents a study with the objective of enhancing safety culture in the Swedish nuclear power industry. A primary objective of this study was to ensure that the latest thinking on human factors principles was being recognised and applied by nuclear power operators as a means of ensuring optimal safety performance. The initial phase of the project was conducted as a pilot study, involving the senior management group at one Swedish nuclear power-producing site. The pilot study enabled the project methodology to be validated after which it was repeated at other Swedish nuclear power industry sites, providing a broad-ranging analysis of opportunities across the industry to enhance safety culture. The introduction to this report contains an overview of safety culture, explains the background to the project and sets out the project rationale and objectives. The methodology used for understanding and analysing the important safety culture issues at each nuclear power site is then described. This section begins with a summary of the processes used in the information gathering and data analysis stage. The six components of the Management Workshops conducted at each site are then described. These workshops used a series of presentations, interactive events and group exercises to: (a) provide feedback to site managers on the safety culture and safety leadership issues identified at their site, and (b) stimulate further safety thinking and provide 'take-away' information and leadership strategies that could be applied to promote safety culture improvements. Section 3, project Findings, contains the main observations and output from the project. These include: - a brief overview of aspects of the local industry operating context that impinge on safety culture; - a summary of strengths or positive attributes observed within the safety culture of the Swedish nuclear industry; - a set of identified opportunities for further improvement; - the aggregated results of the

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

    International Nuclear Information System (INIS)

    2000-09-01

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

  12. Active gated imaging for automotive safety applications

    Science.gov (United States)

    Grauer, Yoav; Sonn, Ezri

    2015-03-01

    The paper presents the Active Gated Imaging System (AGIS), in relation to the automotive field. AGIS is based on a fast gated-camera equipped with a unique Gated-CMOS sensor, and a pulsed Illuminator, synchronized in the time domain to record images of a certain range of interest which are then processed by computer vision real-time algorithms. In recent years we have learned the system parameters which are most beneficial to night-time driving in terms of; field of view, illumination profile, resolution and processing power. AGIS provides also day-time imaging with additional capabilities, which enhances computer vision safety applications. AGIS provides an excellent candidate for camera-based Advanced Driver Assistance Systems (ADAS) and the path for autonomous driving, in the future, based on its outstanding low/high light-level, harsh weather conditions capabilities and 3D potential growth capabilities.

  13. Pilot study of psilocybin treatment for anxiety in patients with advanced-stage cancer.

    Science.gov (United States)

    Grob, Charles S; Danforth, Alicia L; Chopra, Gurpreet S; Hagerty, Marycie; McKay, Charles R; Halberstadt, Adam L; Greer, George R

    2011-01-01

    Researchers conducted extensive investigations of hallucinogens in the 1950s and 1960s. By the early 1970s, however, political and cultural pressures forced the cessation of all projects. This investigation reexamines a potentially promising clinical application of hallucinogens in the treatment of anxiety reactive to advanced-stage cancer. To explore the safety and efficacy of psilocybin in patients with advanced-stage cancer and reactive anxiety. A double-blind, placebo-controlled study of patients with advanced-stage cancer and anxiety, with subjects acting as their own control, using a moderate dose (0.2 mg/kg) of psilocybin. A clinical research unit within a large public sector academic medical center. Twelve adults with advanced-stage cancer and anxiety. In addition to monitoring safety and subjective experience before and during experimental treatment sessions, follow-up data including results from the Beck Depression Inventory, Profile of Mood States, and State-Trait Anxiety Inventory were collected unblinded for 6 months after treatment. Safe physiological and psychological responses were documented during treatment sessions. There were no clinically significant adverse events with psilocybin. The State-Trait Anxiety Inventory trait anxiety subscale demonstrated a significant reduction in anxiety at 1 and 3 months after treatment. The Beck Depression Inventory revealed an improvement of mood that reached significance at 6 months; the Profile of Mood States identified mood improvement after treatment with psilocybin that approached but did not reach significance. This study established the feasibility and safety of administering moderate doses of psilocybin to patients with advanced-stage cancer and anxiety. Some of the data revealed a positive trend toward improved mood and anxiety. These results support the need for more research in this long-neglected field. clinicaltrials.gov Identifier: NCT00302744.

  14. [The therapeutic value and safety of icotinib as first-line therapy for advanced non-small cell lung cancer patients].

    Science.gov (United States)

    Chen, H; Wang, H P; Zhang, L; Si, X Y

    2017-01-01

    Objective: To evaluate the safety and efficacy of icotinib as first-line therapy in Chinese non-small cell lung cancer (NSCLC) patients harboring epidermal growth factor receptor (EGFR) sensitive mutations. Methods: Patients with stage ⅢB/Ⅳ NSCLC who had EGFR sensitive mutation and had no previous treatment were enrolled into this study. The response rates, progress free survival (PFS), overall survival (OS), and the safety were analyzed. Results: Ninety advanced adenocarcinoma patients were enrolled in this study, 44 patients had partial response (PR), 42 patients had stable disease (SD), 4 patients had progressive disease (PD), with an overall response rate (ORR) of 48.9%, and a disease control rate (DCR) of 95.6%. The median PFS was 14.9 months (95% CI 13.5-16.3) and the OS was 37.0 weeks (95% CI 27.9-46.1). Patients with brain metastases showed higher ORR( P =0.049). Patients with stage ⅢB had longer PFS than those with stage Ⅳ( P =0.007). The most common adverse events were grade 1-2 skin rash (38 patients, 40.9%). Other adverse events included dry skin, oral mucositis, diarrhea and liver function injury. Three patients withdrew because of severe liver injury or skin rash. No treatment related mortality occurred. Conclusions: Icotinib is effective and safe as first-line treatment for Chinese advanced NSCLC patients with EGFR sensitive mutation.

  15. Comparisons among different development ways of advanced reactors in China

    International Nuclear Information System (INIS)

    Guo Xingqu; Lin Jianwen; Wang Ruoli

    1992-03-01

    For the development of nuclear energy in the 21st century, China will select a new type reactor to develop, which will have higher fuel efficiency, high safety and better economics. The selection is among the types of FBR (fast breeder reactor), HTGR (high temperature gas-cooled reactor) and FFHR (fusion-fission hybrid reactor). Since the evaluation of advanced reactors involves many uncertain factors and the difficulty of quantization, both the AHP (analytic hierarchy process) method and expert consultation are adopted. Four aspects are taken in the norm system of AHP, i.e. safety, maturity of technology, economy and appropriateness. By using questionnaire method to experts and studying related documents, five types of advanced reactor are selected, i.e. oxide fueled FBR, metal fueled FBR, uranium fueled HTGR, U-Th fueled HTGR and FFBR. Their evaluation parameters are a comprehensively assessed and sorted. About 130 experts and professors who have been working in the research institutes and government agencies of nuclear field are asked to give their comments on the development of advanced reactors. The response rate of questionnaires is 86%, and the data collected are processed by computers. From the evaluation result of AHP method and expert consultation of the fast breeder reactor, especially, the metal fueled FBR, should have the priority in nuclear energy development in the 21st century in China

  16. Advances in the study of far-field phenomena affecting repository performance

    International Nuclear Information System (INIS)

    Tsang, C.F.

    1991-01-01

    Studies of far-field phenomena affecting repository performance have focussed on the role of fractures and other heterogeneities in the potential transport of radioactive solutes from the repository to the biosphere. The present paper summarizes two recent advances in the subject: the channeling model for the understanding and analysis tracer transport in variable-aperture fractures and the modeling of coupled thermo-hydro-mechanical processes in geologic formation around a repository. The paper concludes with remarks on the need for duality in the approach to performance assessment. One line of the duality is fundamental studies and the other, goal-oriented assessment to satisfy regulatory requirements. 15 refs., 10 figs., 1 tab

  17. Study on advanced systematic function of the JNC geological disposal technical information integration system. Research document

    International Nuclear Information System (INIS)

    Ishihara, Yoshinao; Fukui, Hiroshi; Sagawa, Hiroshi; Matsunaga, Kenichi; Ito Takaya

    2004-02-01

    In this study, while attaining systematization about the technical know-how mutually utilized between geology environmental field, disposal technology (design) field and safety assessment field, the share function of general information in which the formation of an information share and the use promotion between the technical information management databases built for every field were aimed at as an advancement of the function of JNC Geological Disposal Technical Information Integration System considered, and the system function for realizing considered in integration of technical information. (1) Since the concrete information about geology environment which is gradually updated with progress of stratum disposal research, or increases in reflected suitable for research of design and safety assessment. After arranging the form suitable for systematizing technical information, while arranging the technical information in both the fields of design and safety assessment with the form of two classes based on tasks/works, it systematized planning adjustment about delivery of technical information with geology environmental field. (2) In order to aim at integration of 3-fields technical information of geological disposal, based on the examination result of systematization of technical information, the function of mutual use of the information managed in two or more databases was considered. Moreover, while considering system functions, such as management of the use history of technical information, connection of information use, and a notice of common information, the system operation windows in consideration of the ease of operation was examined. (author)

  18. Challenge problem and milestones for : Nuclear Energy Advanced Modeling and Simulation (NEAMS) waste Integrated Performance and Safety Codes (IPSC).

    Energy Technology Data Exchange (ETDEWEB)

    Freeze, Geoffrey A.; Wang, Yifeng; Howard, Robert; McNeish, Jerry A.; Schultz, Peter Andrew; Arguello, Jose Guadalupe, Jr.

    2010-09-01

    This report describes the specification of a challenge problem and associated challenge milestones for the Waste Integrated Performance and Safety Codes (IPSC) supporting the U.S. Department of Energy (DOE) Office of Nuclear Energy Advanced Modeling and Simulation (NEAMS) Campaign. The NEAMS challenge problems are designed to demonstrate proof of concept and progress towards IPSC goals. The goal of the Waste IPSC is to develop an integrated suite of modeling and simulation capabilities to quantitatively assess the long-term performance of waste forms in the engineered and geologic environments of a radioactive waste storage or disposal system. The Waste IPSC will provide this simulation capability (1) for a range of disposal concepts, waste form types, engineered repository designs, and geologic settings, (2) for a range of time scales and distances, (3) with appropriate consideration of the inherent uncertainties, and (4) in accordance with robust verification, validation, and software quality requirements. To demonstrate proof of concept and progress towards these goals and requirements, a Waste IPSC challenge problem is specified that includes coupled thermal-hydrologic-chemical-mechanical (THCM) processes that describe (1) the degradation of a borosilicate glass waste form and the corresponding mobilization of radionuclides (i.e., the processes that produce the radionuclide source term), (2) the associated near-field physical and chemical environment for waste emplacement within a salt formation, and (3) radionuclide transport in the near field (i.e., through the engineered components - waste form, waste package, and backfill - and the immediately adjacent salt). The initial details of a set of challenge milestones that collectively comprise the full challenge problem are also specified.

  19. Challenge problem and milestones for: Nuclear Energy Advanced Modeling and Simulation (NEAMS) waste Integrated Performance and Safety Codes (IPSC)

    International Nuclear Information System (INIS)

    Freeze, Geoffrey A.; Wang, Yifeng; Howard, Robert; McNeish, Jerry A.; Schultz, Peter Andrew; Arguello, Jose Guadalupe Jr.

    2010-01-01

    This report describes the specification of a challenge problem and associated challenge milestones for the Waste Integrated Performance and Safety Codes (IPSC) supporting the U.S. Department of Energy (DOE) Office of Nuclear Energy Advanced Modeling and Simulation (NEAMS) Campaign. The NEAMS challenge problems are designed to demonstrate proof of concept and progress towards IPSC goals. The goal of the Waste IPSC is to develop an integrated suite of modeling and simulation capabilities to quantitatively assess the long-term performance of waste forms in the engineered and geologic environments of a radioactive waste storage or disposal system. The Waste IPSC will provide this simulation capability (1) for a range of disposal concepts, waste form types, engineered repository designs, and geologic settings, (2) for a range of time scales and distances, (3) with appropriate consideration of the inherent uncertainties, and (4) in accordance with robust verification, validation, and software quality requirements. To demonstrate proof of concept and progress towards these goals and requirements, a Waste IPSC challenge problem is specified that includes coupled thermal-hydrologic-chemical-mechanical (THCM) processes that describe (1) the degradation of a borosilicate glass waste form and the corresponding mobilization of radionuclides (i.e., the processes that produce the radionuclide source term), (2) the associated near-field physical and chemical environment for waste emplacement within a salt formation, and (3) radionuclide transport in the near field (i.e., through the engineered components - waste form, waste package, and backfill - and the immediately adjacent salt). The initial details of a set of challenge milestones that collectively comprise the full challenge problem are also specified.

  20. Nursing leaders' accountability to narrow the safety chasm: insights and implications from the collective evidence base on healthcare safety.

    Science.gov (United States)

    Jeffs, Lianne; Macmillan, Kathleen; McKey, Colleen; Ferris, Ella

    2009-01-01

    Challenges continue to exist in bridging the safety gap to ensure that consistent, high-quality nursing care is provided based on the best scientific knowledge available. This paper examines findings from nursing research presented at the symposium Advancing Nursing Leadership for a Safer Healthcare System, held in Toronto, Ontario in 2007. Four central themes emerged: (1) place the patient in safety; (2) generate a broader knowledge base on safety across the continuum of care; (3) create a safe culture and healthy work environment to mitigate current threats to patient safety; and (4) advance translation of evidence to practice at the organizational and clinical levels. The aim of this exchange of knowledge was to equip nursing leaders and their decision partners with evidence that can become a catalyst for mobilizing change in practice to address the safety chasm.

  1. Yanqing solar field: Dynamic optical model and operational safety analysis

    International Nuclear Information System (INIS)

    Zhao, Dongming; Wang, Zhifeng; Xu, Ershu; Zhu, Lingzhi; Lei, Dongqiang; Xu, Li; Yuan, Guofeng

    2017-01-01

    Highlights: • A dynamic optical model of the Yanqing solar field was built. • Tracking angle characteristics were studied with different SCA layouts and time. • The average energy flux was simulated across four clear days. • Influences of defocus angles for energy flux were analyzed. - Abstract: A dynamic optical model was established for the Yanqing solar field at the parabolic trough solar thermal power plant and a simulation was conducted on four separate days of clear weather (March 3rd, June 2nd, September 25th, December 17th). The solar collector assembly (SCA) was comprised of a North-South and East-West layout. The model consisted of the following modules: DNI, SCA operational, and SCA optical. The tracking angle characteristics were analyzed and the results showed that the East-West layout of the tracking system was the most viable. The average energy flux was simulated for a given time period and different SCA layouts, yielding an average flux of 6 kW/m 2 , which was then used as the design and operational standards of the Yanqing parabolic trough plant. The mass flow of North-South layout was relatively stable. The influences of the defocus angles on both the average energy flux and the circumferential flux distribution were also studied. The results provided a theoretical basis for the following components: solar field design, mass flow control of the heat transfer fluid, design and operation of the tracking system, operational safety of SCAs, and power production prediction in the Yanqing 1 MW parabolic trough plant.

  2. Survival, Durable Response, and Long-Term Safety in Patients With Previously Treated Advanced Renal Cell Carcinoma Receiving Nivolumab.

    Science.gov (United States)

    McDermott, David F; Drake, Charles G; Sznol, Mario; Choueiri, Toni K; Powderly, John D; Smith, David C; Brahmer, Julie R; Carvajal, Richard D; Hammers, Hans J; Puzanov, Igor; Hodi, F Stephen; Kluger, Harriet M; Topalian, Suzanne L; Pardoll, Drew M; Wigginton, Jon M; Kollia, Georgia D; Gupta, Ashok; McDonald, Dan; Sankar, Vindira; Sosman, Jeffrey A; Atkins, Michael B

    2015-06-20

    Blockade of the programmed death-1 inhibitory cell-surface molecule on immune cells using the fully human immunoglobulin G4 antibody nivolumab mediates tumor regression in a portion of patients with advanced treatment-refractory solid tumors. We report clinical activity, survival, and long-term safety in patients with advanced renal cell carcinoma (RCC) treated with nivolumab in a phase I study with expansion cohorts. A total of 34 patients with previously treated advanced RCC, enrolled between 2008 and 2012, received intravenous nivolumab (1 or 10 mg/kg) in an outpatient setting once every two weeks for up to 96 weeks and were observed for survival and duration of response after treatment discontinuation. Ten patients (29%) achieved objective responses (according to RECIST [version 1.0]), with median response duration of 12.9 months; nine additional patients (27%) demonstrated stable disease lasting > 24 weeks. Three of five patients who stopped treatment while in response continued to respond for ≥ 45 weeks. Median overall survival in all patients (71% with two to five prior systemic therapies) was 22.4 months; 1-, 2-, and 3-year survival rates were 71%, 48%, and 44%, respectively. Grade 3 to 4 treatment-related adverse events occurred in 18% of patients; all were reversible. Patients with advanced treatment-refractory RCC treated with nivolumab demonstrated durable responses that in some responders persisted after drug discontinuation. Overall survival is encouraging, and toxicities were generally manageable. Ongoing randomized clinical trials will further assess the impact of nivolumab on overall survival in patients with advanced RCC. © 2015 by American Society of Clinical Oncology.

  3. Efficacy and safety of pharmacological interventions in second- or later-line treatment of patients with advanced soft tissue sarcoma: a systematic review

    International Nuclear Information System (INIS)

    Sharma, Sheetal; Takyar, Shweta; Manson, Stephanie C; Powell, Sarah; Penel, Nicolas

    2013-01-01

    Current guidelines recommend anthracycline-based chemotherapy primarily with doxorubicin either as monotherapy or in combination with ifosfamide as the first-line treatment for most advanced STS subtypes. Therapeutic options after failure of doxorubicin and/or ifosfamide are limited. This study aimed to comprehensively review available data on the activity and safety of interventions in second- or later-line treatment of advanced STS. Electronic literature databases (Embase ® , MEDLINE ® , MEDLINE ® In-Process, Cochrane Central Register of Controlled Trials, and Cochrane Database of Systematic Reviews) were searched from 1980 to 01 March 2012 to identify randomised controlled trials (RCTs) and non-randomised studies (both prospective and retrospective) evaluating pharmacological interventions in patients with advanced STS pre-treated with anthracycline- and/or ifosfamide-based therapy. The review identified six RCTs (one phase III and five phase II trials) and 94 non-randomised studies. Based on the primary trial endpoints, RCTs demonstrated favourable efficacy for pazopanib over placebo (PFS: 4.6 months vs. 1.6 months), gemcitabine plus dacarbazine over dacarbazine monotherapy (3-month PFS rate: 54.2% vs. 35.2%), and trabectedin 3-weekly schedule over weekly schedule (TTP: 3.7 months vs. 2.3 months. The non-randomised studies demonstrated heterogeneity in efficacy and safety results. Across the RCTs, pazopanib over placebo, gemcitabine-dacarbazine over dacarbazine, and trabectedin 3-weekly over weekly regimen clearly demonstrated a PFS advantage in the second- and later-line treatment of advanced STS. With only one phase III trial in this setting, there is a clear need for additional comparative trials to better understand the risk: benefit ratios of available agents and combinations

  4. Utility requirements for safety in the passive advanced light-water reactor

    International Nuclear Information System (INIS)

    Marston, T.U.; Layman, W.H.; Bockhold, G. Jr.

    1993-01-01

    The objective of the passive plant design is to use passive systems to replace all the active engineered safety systems presently used in light-water reactors. The benefits derived from such an approach to safety design are multiple. First, it is expected that a passive design approach will significantly simplify the overall plant design, including a reduction in the number of components, and reduce the operation and maintenance burden. Second, it is expected that the overall safety and reliability of the passive systems will be improved over active systems, which will result in extremely low risk to public health and safety. Third, challenges to the operating staff will be minimized during transient and emergency conditions, which will reduce the uncertainty associated with human behavior. Finally, it is expected that reliance on passive safety features will lead to a better understanding by the general public and recognition that a major improvement in public safety has been achieved

  5. New and recently finalised activities within the NKS Programmes for Nordic cooperation on nuclear reactor safety and emergency preparedness

    DEFF Research Database (Denmark)

    Andgren, Karin; Andersson, Kasper Grann; Magnússon, Sigurður M.

    2015-01-01

    Over the years, NKS has provided funding for hundreds of research activities in fields comprising reactor safety, decommissioning, nuclear and radiological emergency preparedness, and management of radioactive waste. Advanced technologies and methods developed under the NKS framework have been used...... within the Nordic countries as well as internationally. Two programme areas are defined under the NKS platform: The NKS-R programme on nuclear reactor safety and the NKS-B programme on emergency preparedness. Three articles, giving an introduction to NKS and its two programmes, were published...

  6. On the road to new nuclear safety

    International Nuclear Information System (INIS)

    Kovacs, Zoltan; Novakova, Helena; Spenlinger, Robert

    2013-01-01

    The article describes the issue of nuclear safety of nuclear power plants and major factors affecting nuclear safety, discusses the consequences of the Fukushima-Daiichi accident, and outlines the advanced concept of nuclear safety which extends the current regulatory requirements for plant safety. This new concept should be adopted globally to prevent occurrences having similar consequences worldwide. The tasks of this new nuclear safety concept are discussed. (orig.)

  7. Advanced Materials in Support of EERE Needs to Advance Clean Energy Technologies Program Implementation

    Energy Technology Data Exchange (ETDEWEB)

    Liby, Alan L [ORNL; Rogers, Hiram [ORNL

    2013-10-01

    The goal of this activity was to carry out program implementation and technical projects in support of the ARRA-funded Advanced Materials in Support of EERE Needs to Advance Clean Energy Technologies Program of the DOE Advanced Manufacturing Office (AMO) (formerly the Industrial Technologies Program (ITP)). The work was organized into eight projects in four materials areas: strategic materials, structural materials, energy storage and production materials, and advanced/field/transient processing. Strategic materials included work on titanium, magnesium and carbon fiber. Structural materials included work on alumina forming austentic (AFA) and CF8C-Plus steels. The advanced batteries and production materials projects included work on advanced batteries and photovoltaic devices. Advanced/field/transient processing included work on magnetic field processing. Details of the work in the eight projects are available in the project final reports which have been previously submitted.

  8. Problems of nuclear reactor safety. Vol. 2

    International Nuclear Information System (INIS)

    Goncharov, L.A.

    1995-01-01

    Theses of proceedings of the 9 Topical Meeting on problems of nuclear power plant safety are presented. Reports include results of neutron-physical experiments carried out for reactor safety justification. Concepts of advanced reactors with improved safety are considered. Results of researches on fuel cycles are given too

  9. The Efficacy and Safety of Icotinib in Patients with Advanced Non-Small Cell Lung Cancer Previously Treated with Chemotherapy: A Single-Arm, Multi-Center, Prospective Study.

    Directory of Open Access Journals (Sweden)

    Xingsheng Hu

    Full Text Available Icotinib is a small molecule targeting epidermal growth factor receptor tyrosine kinase, which shows non-inferior efficacy and better safety comparing to gefitinib in previous phase III trial. The present study was designed to further evaluate the efficacy and safety of icotinib in patients with advanced non-small-cell lung cancer (NSCLC previously treated with platinum-based chemotherapy.Patients with NSCLC progressing after one or two lines of chemotherapy were enrolled to receive oral icotinib (125 mg tablet, three times per day. The primary endpoint was progression-free survival. The secondary endpoints included overall survival, objective response rate, time to progression, quality of life and safety.From March 16, 2010 to October 9, 2011, 128 patients from 15 centers nationwide were enrolled, in which 124 patients were available for efficacy evaluation and 127 patients were evaluable for safety. The median progression-free survival and time to progression were 5.0 months (95%CI 2.9-6.6 m and 5.4 months (95%CI 3.1-7.9 m, respectively. The objective response rate and disease control rate were 25.8% and 67.7% respectively. Median overall survival exceeded 17.6 months (95%CI 14.2 m-NA according to censored data. Further follow-up of overall survival is ongoing. The most frequent treatment-related adverse events were rash (26%, 33/127, diarrhea (12.6%, 16/127 and elevation of transaminase (15.7%, 20/127.In general, this study showed similar efficacy and numerically better safety when compared with that in ICOGEN trial, further confirming the efficacy and safety of icotinib in treating patients with advanced NSCLC previously treated with chemotherapy.ClinicalTrials.gov NCT02486354.

  10. The Efficacy and Safety of Icotinib in Patients with Advanced Non-Small Cell Lung Cancer Previously Treated with Chemotherapy: A Single-Arm, Multi-Center, Prospective Study.

    Science.gov (United States)

    Hu, Xingsheng; Zhang, Li; Shi, Yuankai; Zhou, Caicun; Liu, Xiaoqing; Wang, Dong; Song, Yong; Li, Qiang; Feng, Jifeng; Qin, Shukui; Xv, Nong; Zhou, Jianying; Zhang, Li; Hu, Chunhong; Zhang, Shucai; Luo, Rongcheng; Wang, Jie; Tan, Fenlai; Wang, Yinxiang; Ding, Lieming; Sun, Yan

    2015-01-01

    Icotinib is a small molecule targeting epidermal growth factor receptor tyrosine kinase, which shows non-inferior efficacy and better safety comparing to gefitinib in previous phase III trial. The present study was designed to further evaluate the efficacy and safety of icotinib in patients with advanced non-small-cell lung cancer (NSCLC) previously treated with platinum-based chemotherapy. Patients with NSCLC progressing after one or two lines of chemotherapy were enrolled to receive oral icotinib (125 mg tablet, three times per day). The primary endpoint was progression-free survival. The secondary endpoints included overall survival, objective response rate, time to progression, quality of life and safety. From March 16, 2010 to October 9, 2011, 128 patients from 15 centers nationwide were enrolled, in which 124 patients were available for efficacy evaluation and 127 patients were evaluable for safety. The median progression-free survival and time to progression were 5.0 months (95%CI 2.9-6.6 m) and 5.4 months (95%CI 3.1-7.9 m), respectively. The objective response rate and disease control rate were 25.8% and 67.7% respectively. Median overall survival exceeded 17.6 months (95%CI 14.2 m-NA) according to censored data. Further follow-up of overall survival is ongoing. The most frequent treatment-related adverse events were rash (26%, 33/127), diarrhea (12.6%, 16/127) and elevation of transaminase (15.7%, 20/127). In general, this study showed similar efficacy and numerically better safety when compared with that in ICOGEN trial, further confirming the efficacy and safety of icotinib in treating patients with advanced NSCLC previously treated with chemotherapy. ClinicalTrials.gov NCT02486354.

  11. Performance of an iPad Application to Detect Moderate and Advanced Visual Field Loss in Nepal.

    Science.gov (United States)

    Johnson, Chris A; Thapa, Suman; George Kong, Yu Xiang; Robin, Alan L

    2017-10-01

    To evaluate the accuracy and efficiency of Visual Fields Easy (VFE), a free iPad app, for performing suprathreshold perimetric screening. Prospective, cross-sectional validation study. We performed screening visual fields using a calibrated iPad 2 with the VFE application on 206 subjects (411 eyes): 210 normal (NL), 183 glaucoma (GL), and 18 diabetic retinopathy (DR) at Tilganga Institute of Ophthalmology, Kathmandu, Nepal. We correlated the results with a Humphrey Field Analyzer using 24-2 SITA Standard tests on 373 of these eyes (198 NL, 160 GL, 15 DR). The number of missed locations on the VFE correlated with mean deviation (MD, r = 0.79), pattern standard deviation (PSD, r = 0.60), and number of locations that were worse than the 95% confidence limits for total deviation (r = 0.51) and pattern deviation (r = 0.68) using SITA Standard. iPad suprathreshold perimetry was able to detect most visual field deficits with moderate (MD of -6 to -12 dB) and advanced (MD worse than -12 dB) loss, but had greater difficulty in detecting early (MD better than -6 dB) loss, primarily owing to an elevated false-positive response rate. The average time to perform the Visual Fields Easy test was 3 minutes, 18 seconds (standard deviation = 16.88 seconds). The Visual Fields Easy test procedure is a portable, fast, effective procedure for detecting moderate and advanced visual field loss. Improvements are currently underway to monitor eye and head tracking during testing, reduce testing time, improve performance, and eliminate the need to touch the video screen surface. Copyright © 2017 Elsevier Inc. All rights reserved.

  12. Analysis of an Advanced Test Reactor Small-Break Loss-of-Coolant Accident with an Engineered Safety Feature to Automatically Trip the Primary Coolant Pumps

    International Nuclear Information System (INIS)

    Polkinghorne, Steven T.; Davis, Cliff B.; McCracken, Richard T.

    2000-01-01

    A new engineered safety feature that automatically trips the primary coolant pumps following a low-pressure reactor scram was recently installed in the Advanced Test Reactor (ATR). The purpose of this engineered safety feature is to prevent the ATR's surge tank, which contains compressed air, from emptying during a small-break loss-of-coolant accident (SBLOCA). If the surge tank were to empty, the air introduced into the primary coolant loop could potentially cause the performance of the primary and/or emergency coolant pumps to degrade, thereby reducing core thermal margins. Safety analysis performed with the RELAP5 thermal-hydraulic code and the SINDA thermal analyzer shows that adequate thermal margins are maintained during an SBLOCA with the new engineered safety feature installed. The analysis also shows that the surge tank will not empty during an SBLOCA even if one of the primary coolant pumps fails to trip

  13. Progress of nuclear safety research. 2001

    Energy Technology Data Exchange (ETDEWEB)

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

    2001-10-01

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

  14. Safety and efficacy of first-line bevacizumab with chemotherapy in Asian patients with advanced nonsquamous NSCLC: results from the phase IV MO19390 (SAiL) study.

    Science.gov (United States)

    Tsai, Chun-Ming; Au, Joseph Siu-kie; Chang, Gee-Chen; Cheng, Ashley Chi-kin; Zhou, Caicun; Wu, Yi-long

    2011-06-01

    First-line treatment with bevacizumab combined with chemotherapy has been shown to improve outcomes in patients with advanced, nonsquamous non-small cell lung cancer (NSNSCLC) in phase III clinical trials. SAiL (MO19390), an open-label, multicenter, single-arm study, evaluated the safety and efficacy of first-line bevacizumab-based treatment in clinical practice. This report presents the results of a preplanned subanalysis of Asian patients enrolled in SAiL. Patients with untreated, locally advanced, metastatic or recurrent NSNSCLC received bevacizumab 7.5 or 15 mg/kg every 3 weeks plus chemotherapy for up to six cycles, followed by single-agent bevacizumab until disease progression. Eligibility criteria for SAiL permitted enrolment of a broad patient population. The primary end point was safety; secondary end points included time to disease progression and overall survival. The Asian intent-to-treat population comprised 314 of the 2212 patients enrolled in the SAiL trial. In the Asian subanalysis, patients received a median of nine cycles of bevacizumab, and the median follow-up was 16.4 months. The incidence of clinically significant adverse events (grade ≥3) of special interest was relatively low in this population (15.6% overall); proteinuria (7.6%), hypertension (4.8%), and bleeding (2.5%) were the most common. A total of five adverse events related to bevacizumab were reported as grade 5. Disease control rate was 94.1%, median time to disease progression was 8.3 months, and median overall survival was 18.9 months. The safety and efficacy of first-line bevacizumab-based treatment in Asian patients with advanced NSNSCLC is consistent with that demonstrated in phase III studies and in the overall SAiL population. There were no new safety signals.

  15. Probabilistic safety and risk assessments in the field of nuclear technology - Mode of operation, possibilities and limits

    International Nuclear Information System (INIS)

    Mertens, J.

    1993-01-01

    In this study probabilistic safety and risk assessments in the field of nuclear energy are explained. Mainly qualitative results and conclusions are presented. Explanations for often discussed aspects of such analysis reveal the procedure and reasonable limits of application. The mentioned literature contains detailed results. (orig./DG) [de

  16. A phase I open-label trial evaluating the cardiovascular safety of regorafenib in patients with advanced cancer.

    Science.gov (United States)

    Jones, Robin L; Bendell, Johanna C; Smith, David C; Diefenbach, Konstanze; Lettieri, John; Boix, Oliver; Lockhart, A Craig; O'Bryant, Cindy; Moore, Kathleen N

    2015-10-01

    To characterize the cardiovascular safety profile of regorafenib in patients with advanced cancer. Patients received regorafenib 160 mg/day for 21 days followed by a 7-day break. The primary endpoint was the change from baseline in QTcF at the regorafenib t(max) (Day 21, Cycle 1 or 2) and changes in left ventricular ejection fraction (LVEF) from baseline on Cycle 2, Day 21. Secondary objectives were pharmacokinetics, safety, anti-tumor activity and effects on electrocardiogram intervals. QT intervals were corrected using the methods of Fridericia (QTcF) and Bazett (QTcB). LVEF was assessed by multigated acquisition scanning. Fifty-three patients were enrolled, and all received at least one dose of regorafenib 160 mg. Twenty-five patients received regorafenib for 21 days without dose reduction. The mean change from baseline in QTcF at t(max) was (-)2 ms (90 % CI -8, 3). No patient experienced a change from baseline in QTcF > 60 ms, and two had QTcF changes between 30 and 60 ms. No patient had a QTcF or QTcB > 480 ms. In 27 patients who received at least 80 mg of regorafenib, the mean change from baseline in LVEF% ± SD was 1.7 ± 7.8. In 14 patients without a dose reduction, the mean change from baseline in LVEF% was (-)0.1 ± 8.6 at Cycle 2, Day 21. Four patients experienced a LVEF decrease between 10 and 20 %. The effects of regorafenib on the QT/QTc interval and LVEF were modest and unlikely to be of clinical significance in the setting of advanced cancer therapy.

  17. Effects of magnetic geometry, fluctuations, and electric fields on confinement in the Advanced Toroidal Facility

    International Nuclear Information System (INIS)

    Isler, R.C.; Aceto, S.; Baylor, L.R.; Bigelow, T.S.; Bell, G.L.; Bell, J.D.; Carreras, B.A.; Colchin, R.J.; Crume, E.C.; Dominguez, N.; Dory, R.A.; Dunlap, J.L.; Dyer, G.R.; England, A.C.; Gandy, R.F.; Glowienka, J.C.; Hanson, G.R.; Harris, J.H.; Hiroe, S.; Horton, L.D.; Jernigan, T.C.; Ji, H.; Langley, R.A.; Lee, D.K.; Likin, K.M.; Lyon, J.F.; Ma, C.H.; Morimoto, S.; Murakami, M.; Okada, H.; Qualls, A.L.; Rasmussen, D.A.; Rome, J.A.; Sato, M.; Schwelberger, J.G.; Shats, M.G.; Simpkins, J.E.; Thomas, C.E.; Uckan, T.; Wade, M.R.; Wilgen, J.B.; Wing, W.R.; Yamada, H.; Zielinski, J.J.

    1992-01-01

    Recent experiments in the Advanced Toroidal Facility (ATF) [Fusion Technol. 10, 179 (1986)] have been directed toward investigations of the basic physics mechanisms that control confinement in this device. Measurements of the density fluctuations throughout the plasma volume have provided indications for the existence of theoretically predicted dissipative trapped electron and resistive interchange instabilities. These identifications are supported by results of dynamic configuration scans of the magnetic fields during which the magnetic well volume, shear, and fraction of confined trapped particles are changed continuously. The influence of magnetic islands on the global confinement has been studied by deliberately applying error fields which strongly perturb the nested flux-surface geometry, and the effects of electric fields have been investigated by means of biased limiter experiments

  18. MRI Evaluation and Safety in the Developing Brain

    Science.gov (United States)

    Tocchio, Shannon; Kline-Fath, Beth; Kanal, Emanuel; Schmithorst, Vincent J.; Panigrahy, Ashok

    2015-01-01

    Magnetic resonance imaging (MRI) evaluation of the developing brain has dramatically increased over the last decade. Faster acquisitions and the development of advanced MRI sequences such as magnetic resonance spectroscopy (MRS), diffusion tensor imaging (DTI), perfusion imaging, functional MR imaging (fMRI), and susceptibility weighted imaging (SWI), as well as the use of higher magnetic field strengths has made MRI an invaluable tool for detailed evaluation of the developing brain. This article will provide an overview of the use and challenges associated with 1.5T and 3T static magnetic fields for evaluation of the developing brain. This review will also summarize the advantages, clinical challenges and safety concerns specifically related to MRI in the fetus and newborn, including the implications of increased magnetic field strength, logistics related to transporting and monitoring of neonates during scanning, sedation considerations and a discussion of current technologies such as MRI-conditional neonatal incubators and dedicated small-foot print neonatal intensive care unit (NICU) scanners. PMID:25743582

  19. The US Advanced Liquid Metal Reactor and the Fast Flux Test Facility Phase IIA passive safety tests

    International Nuclear Information System (INIS)

    Shen, P.K.; Harris, R.A.; Campbell, L.R.; Dautel, W.A.; Dubberley, A.E.; Gluekler, E.L.

    1992-07-01

    This report discusses the safety approach of the Advanced Liquid Metal reactor program, sponsored by the US Department of Energy, which relies upon passive reactor responses to off-normal condition to limit power and temperature excursions to levels that allow safety margins. Gas expansion modules (GEM) have included in the design to provide negative reactivity to enhance these margins in the extremely unlikely event that pumping power is lost and the highly reliable scram system fails to operate. The feasibility and beneficial features of these devices were first demonstrated in the core of the Fast Flux Test Facility (FFTF) in 1986. Preapplication safety evaluations by the US Nuclear Regulatory Commission have identified areas that must be addressed if these devices are to be relied on. One of these areas is the response of the reactor when it is critical and the pumps are turned on, resulting in positive reactivity being added to the core. Tests to examine such transients have been performed as part of the continuing FFTF program to confirm the passive safety characteristics of liquid metal reactors (LMR). The primary tests consisted of starting the main coolant pumps, which forced sodium coolant into the GEMS, decreasing neutron leakage and adding positive reactivity. The resulting transients were shown to be benign and easily mitigated by the reactivity feedbacks inherent in the FFTF and all LMRs. Steady-state auxiliary tests of the GEM and feedback reactivity worths accurately predicted the transient results. The auxiliary GEM worth tests also demonstrated that the worth can be determined at a subcritical state, which allows for a verification of the GEM's availability prior to ascending to power

  20. Advanced reactor systems: safety and regulatory aspects

    International Nuclear Information System (INIS)

    Gopalakrishnan, A.

    1994-01-01

    Safety features which are desirable in futuristic reactor systems have been the subject of several studies over the past decade by different expert groups. When one discusses this subject, therefore, in a somewhat non-specific and qualitative manner, it is best to make use of the already available collective wisdom and literature on the matter. (author). 3 refs

  1. 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

  2. A 100 MWe Advanced Sodium-cooled Fast Reactor (AFR-100)

    International Nuclear Information System (INIS)

    Grandy, C.; Kim, T.K.; Jin, E.

    2013-01-01

    • AFR-100 Design development is continuing in the U.S.; • Various innovations are included in the design to understand their feasibility; • Engineering and safety analyses have been performed that demonstrate the inherent safety characteristics of the AFR-100 design during severe accidents; • R&D is being performed on a number of the innovations such as advanced materials, compact fuel handing system, advanced energy conversion system, advanced core design, etc

  3. Simulation of advanced accumulator and its application in CPR1000 LBLOCA analysis

    International Nuclear Information System (INIS)

    Hu, Hongwei; Shan, Jianqiang; Gou, Junli; Cao, Jianhua; Shen, Yonggang; Fu, Xiangang

    2014-01-01

    Highlights: • The analysis model was developed for advanced accumulator. • The sensitivity analysis of each key parameter was performed. • The LBLOCA was analyzed for the CPR1000 with advanced accumulator. • The analysis shows that advanced accumulator can improve CPR1000 safety performance. - Abstract: The advanced accumulator is designed to improve the safety and reliability of CPR1000 by providing a small injection flow to keep the reactor core in flooded condition. Thus, the core still stays in a cooling state without the intervention of low pressure safety injection and the startup grace time of the low pressure safety injection pump can be greatly extended. A new model for the advanced accumulator, which is based on the basic conservation equations, is developed and incorporated into RELAP5/MOD 3.3. The simulation of the advanced accumulator can be carried out and results show that the behavior of the advanced accumulator satisfied its primary design target. There is a large flow in the advanced accumulator at the initial stage. When the accumulator water level is lower than the stand pipe, a vortex appears in the damper, which results in a large pressure drop and a small flow. And then the sensitivity analysis is performed and the major factors which affected the flow rate of the advanced accumulator were obtained, including the damper diameter, the initial volume ratio of the water and the nitrogen and the diameter ratio of the standpipe and the small pipe. Additionally, the primary coolant loop cold leg double-ended guillotine break LBLOCA in CPR1000 with advanced accumulator is analyzed. The results show that the criterion for maximum cladding temperature limit (1477 K) (NRC, 1992) can be met ever with 200 s after the startup of the low pressure safety injection. From this point of view, passive advanced accumulator can strive a longer grace time for LPSI. Thus the reliability, safety and economy of the reactor system can be improved

  4. A tool to diagnose context riskiness in view of food safety activities and microbiological safety output

    NARCIS (Netherlands)

    Luning, P.A.; Marcelis, W.J.; Boekel, van M.A.J.S.; Rovira, J.; Uyttendaele, M.; Jacxsens, L.

    2011-01-01

    Stakeholders entail increasing demands on food safety management systems (FSMS) stimulating ongoing efforts of companies to progress to more advanced systems. However, the actual microbiological food safety (FS) output is not only a result of the performance of an FSMS, but it also depends on the

  5. Safety significance of ATR passive safety response attributes

    International Nuclear Information System (INIS)

    Atkinson, S.A.

    1990-01-01

    The Advanced Test Reactor (ATR) at the Idaho National Engineering Laboratory was designed with some passive safety response attributes which contribute to the safety of the facility. The three passive safety attributes being evaluated in the paper are: 1) In-core and in-vessel natural convection cooling, 2) a passive heat sink capability of the ATR primary coolant system (PCS) for the transfer of decay power from the uninsulated piping to the confinement, and 3) gravity feed of emergency coolant makeup. The safety significance of the ATR passive safety response attributes is that the reactor can passively respond to most transients, given a reactor scram, to provide adequate decay power removal and a significant time for operator action should the normal active heat removal systems and their backup systems both fail. The ATR Interim Level 1 Probabilistic Risk Assessment (PRA) models and results were used to evaluate the significance to ATR fuel damage frequency (or probability) of the above three passive response attributes. The results of the evaluation indicate that the first attribute is a major safety characteristic of the ATR. The second attribute has a noticeable but only minor safety significance. The third attribute has no significant influence on the ATR firewater injection system (emergency coolant system)

  6. Integral fast reactor safety features

    International Nuclear Information System (INIS)

    Cahalan, J.E.; Kramer, J.M.; Marchaterre, J.F.; Mueller, C.J.; Pedersen, D.R.; Sevy, R.H.; Wade, D.C.; Wei, T.Y.C.

    1988-01-01

    The integral fast reactor (IFR) is an advanced liquid-metal-cooled reactor concept being developed at Argonne National Laboratory. The two major goals of the IFR development effort are improved economics and enhanced safety. In addition to liquid metal cooling, the principal design features that distinguish the IFR are: a pool-type primary system, and advanced ternary alloy metallic fuel, and an integral fuel cycle with on-site fuel reprocessing and fabrication. This paper focuses on the technical aspects of the improved safety margins available in the IFR concept. This increased level of safety is made possible by the liquid metal (sodium) coolant and pool-type primary system layout, which together facilitate passive decay heat removal, and a sodium-bonded metallic fuel pin design with thermal and neutronic properties that provide passive core responses which control and mitigate the consequences of reactor accidents

  7. Advanced thermal-hydraulic and neutronic codes: current and future applications. Summary and conclusions

    International Nuclear Information System (INIS)

    2001-05-01

    An OECD Workshop on Advanced Thermal-Hydraulic and Neutronic Codes Applications was held from 10 to 13 April 2000, in Barcelona, Spain, sponsored by the Committee on the Safety of Nuclear Installations (CSNI) of the OECD Nuclear Energy Agency (NEA). It was organised in collaboration with the Spanish Nuclear Safety Council (CSN) and hosted by CSN and the Polytechnic University of Catalonia (UPC) in collaboration with the Spanish Electricity Association (UNESA). The objectives of the Workshop were to review the developments since the previous CSNI Workshop held in Annapolis [NEA/CSNI/ R(97)4; NUREG/CP-0159], to analyse the present status of maturity and remnant needs of thermal-hydraulic (TH) and neutronic system codes and methods, and finally to evaluate the role of these tools in the evolving regulatory environment. The Technical Sessions and Discussion Sessions covered the following topics: - Regulatory requirements for Best-Estimate (BE) code assessment; - Application of TH and neutronic codes for current safety issues; - Uncertainty analysis; - Needs for integral plant transient and accident analysis; - Simulators and fast running codes; - Advances in next generation TH and neutronic codes; - Future trends in physical modeling; - Long term plans for development of advanced codes. The focus of the Workshop was on system codes. An incursion was made, however, in the new field of applying Computational Fluid Dynamic (CFD) codes to nuclear safety analysis. As a general conclusion, the Barcelona Workshop can be considered representative of the progress towards the targets marked at Annapolis almost four years ago. The Annapolis Workshop had identified areas where further development and specific improvements were needed, among them: multi-field models, transport of interfacial area, 2D and 3D thermal-hydraulics, 3-D neutronics consistent with level of details of thermal-hydraulics. Recommendations issued at Annapolis included: developing small pilot/test codes for

  8. Discussion on safety analysis approach for sodium fast reactors

    International Nuclear Information System (INIS)

    Hong, Soon Joon; Choo, Yeon Joon; Suh, Nam Duk; Shin, Ahn Dong; Bae, Moo Hoon

    2012-01-01

    Utilization of nuclear energy is increasingly necessary not only because of the increasing energy consumption but also because of the controls on greenhouse emissions against global warming. To keep step with such demands, advanced reactors are now world widely under development with the aims of highly economical advances, and enhanced safety. Recently, further elaborating is encouraged on the research and development program for Generation IV (GEN IV) reactors, and in collaboration with other interested countries through the Generation IV International Forum (GIF). Sodium cooled Fast Reactor (SFR) is a strong contender amongst the GEN IV reactor concepts. Korea also takes part in that program and plans to construct demonstration reactor of SFR. SFR is under the development for a candidate of small modular reactors, for example, PRISM (Power Reactor Innovative Small Module). Understanding of safety analysis approach has also advanced by the demand of increasing comprehensive safety requirement. Reviewing the past development of the licensing and safety basis in the advanced reactors, such approaches seemed primarily not so satisfactory because the reference framework of licensing and safety analysis approach in the advanced reactors was always the one in water reactors. And, the framework is very plant specific one and thereby the advanced reactors and their frameworks don't look like a well assorted couple. Recently as a result of considerable advances in probabilistic safety assessment (PSA), risk informed approaches are increasingly applied together with some of the deterministic approaches like as the ones in water reactors. Technology neutral framework (TNF) can be said to be the utmost works of such risk informed approaches, even though an intensive assessment of the applicability has not been sufficiently accomplished. This study discusses the viable safety analysis approaches for the urgent application to the construction of pool type SFR. As discussed in

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

    Science.gov (United States)

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

    2015-09-01

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

  10. Criticality safety evaluation for the Advanced Test Reactor enhanced low enriched uranium fuel elements

    Energy Technology Data Exchange (ETDEWEB)

    Montierth, Leland M. [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2016-07-19

    The Global Threat Reduction Initiative (GTRI) convert program is developing a high uranium density fuel based on a low enriched uranium (LEU) uranium-molybdenum alloy. Testing of prototypic GTRI fuel elements is necessary to demonstrate integrated fuel performance behavior and scale-up of fabrication techniques. GTRI Enhanced LEU Fuel (ELF) elements based on the ATR-Standard Size elements (all plates fueled) are to be fabricated for testing in the Advanced Test Reactor (ATR). While a specific ELF element design will eventually be provided for detailed analyses and in-core testing, this criticality safety evaluation (CSE) is intended to evaluate a hypothetical ELF element design for criticality safety purposes. Existing criticality analyses have analyzed Standard (HEU) ATR elements from which controls have been derived. This CSE documents analysis that determines the reactivity of the hypothetical ELF fuel elements relative to HEU ATR elements and whether the existing HEU ATR element controls bound the ELF element. The initial calculations presented in this CSE analyzed the original ELF design, now referred to as Mod 0.1. In addition, as part of a fuel meat thickness optimization effort for reactor performance, other designs have been evaluated. As of early 2014 the most current conceptual designs are Mk1A and Mk1B, that were previously referred to as conceptual designs Mod 0.10 and Mod 0.11, respectively. Revision 1 evaluates the reactivity of the ATR HEU Mark IV elements for a comparison with the Mark VII elements.

  11. Criticality safety evaluation for the Advanced Test Reactor enhanced low enriched uranium fuel elements

    International Nuclear Information System (INIS)

    Montierth, Leland M.

    2016-01-01

    The Global Threat Reduction Initiative (GTRI) convert program is developing a high uranium density fuel based on a low enriched uranium (LEU) uranium-molybdenum alloy. Testing of prototypic GTRI fuel elements is necessary to demonstrate integrated fuel performance behavior and scale-up of fabrication techniques. GTRI Enhanced LEU Fuel (ELF) elements based on the ATR-Standard Size elements (all plates fueled) are to be fabricated for testing in the Advanced Test Reactor (ATR). While a specific ELF element design will eventually be provided for detailed analyses and in-core testing, this criticality safety evaluation (CSE) is intended to evaluate a hypothetical ELF element design for criticality safety purposes. Existing criticality analyses have analyzed Standard (HEU) ATR elements from which controls have been derived. This CSE documents analysis that determines the reactivity of the hypothetical ELF fuel elements relative to HEU ATR elements and whether the existing HEU ATR element controls bound the ELF element. The initial calculations presented in this CSE analyzed the original ELF design, now referred to as Mod 0.1. In addition, as part of a fuel meat thickness optimization effort for reactor performance, other designs have been evaluated. As of early 2014 the most current conceptual designs are Mk1A and Mk1B, that were previously referred to as conceptual designs Mod 0.10 and Mod 0.11, respectively. Revision 1 evaluates the reactivity of the ATR HEU Mark IV elements for a comparison with the Mark VII elements.

  12. Recent advances in aptasensors based on graphene and graphene-like nanomaterials.

    Science.gov (United States)

    Ping, Jianfeng; Zhou, Yubin; Wu, Yuanyuan; Papper, Vladislav; Boujday, Souhir; Marks, Robert S; Steele, Terry W J

    2015-02-15

    Graphene and graphene-like two-dimensional nanomaterials have aroused tremendous research interest in recent years due to their unique electronic, optical, and mechanical properties associated with their planar structure. Aptamers have exhibited many advantages as molecular recognition elements for sensing devices compared to traditional antibodies. The marriage of two-dimensional nanomaterials and aptamers has emerged many ingenious aptasensing strategies for applications in the fields of clinical diagnosis and food safety. This review highlights current advances in the development and application of two-dimensional nanomaterials-based aptasensors with the focus on two main signal-transducing mechanisms, i.e. electrochemical and optical. A special attention is paid to graphene, a one-atom thick layer of graphite with exceptional properties, representing a fastgrowing field of research. In view of the unique properties of two-dimensional nanostructures and their inherent advantages of synthetic aptamers, we expect that high-performance two-dimensional nanomaterials-based aptasensing devices will find extensive applications in environmental monitoring, biomedical diagnostics, and food safety. Copyright © 2014 Elsevier B.V. All rights reserved.

  13. Advances in imaging for oncology guidance

    International Nuclear Information System (INIS)

    Amies, Christopher J.

    2008-01-01

    Over the last 30 years major improvements in medical imaging have played a significant role to help advance the management of oncology diseases. These advances have covered the continuum of care from screening, diagnosis, staging, treatment planning and intervention. More recently image guided radiation therapy (IGRT) has placed sophisticated imaging closer to the treatment event. The opportunity to improve care seems obvious; however the clinical benefits of IGRT are at present not easily proven and yet contribute to the complexity of treatment and the rising costs of care. It is proposed that this is in part due to the present immaturity of IGRT technology development, which is predominantly determined by the challenge of achieving precise delivery of radiation in one or many episodes (fractions) for very different diseases. There is no single type or mode of imaging that will be suitable to address all radiotherapy guidance challenges whether defined by the general criteria identified for a specific disease or the unique characteristics encountered with an individual patient. Finally the wide adoption of this or any medical technology general requires the attainment of a sufficient degree of safety and efficiency. I present the challenges faced by industry as well as select interesting technology based solutions and concepts that may help advance the field of oncology guidance

  14. Nuclear safety guide. TID-7016, Revision 2

    International Nuclear Information System (INIS)

    Thomas, J.T.

    1978-01-01

    The Nuclear Safety Guide was first issued in 1956 as classified AEC report LA-2063 and was reprinted the next year, unclassified, as TID-7016. Revision 1, published in 1961, extended the scope and refined the guiding information. The present revision of the Guide differs significantly from its predecessor in that the latter was intentionally conservative in its recommendations. Firmly based on experimental evidence of criticality, the original Guide and the first revision were considered to be of most value to organizations whose activities with fissionable materials were not extensive and, secondarily, that it would serve as a point of departure for members of established nuclear safety teams, experienced in the field. The reader will find a significant change in the character of information presented in this version. Nuclear Criticality Safety has matured in the past twelve years. The advance of calculational capability has permitted validated calculations to extend and substitute for experimental data. The broadened data base has enabled better interpolation, extension, and understanding of available information, especially in areas previously addressed by undefined but adequate factors of safety. The content has been thereby enriched in qualitative guidance. The information inherently contains, and the user can recapture, the quantitative guidance characteristic of the formerGuides by employing appropriate safety factors. In fact, it becomes incumbent on the Criticality Safety Specialist to necessarily impose safety factors consistent with the possible normal and abnormal credible contingencies of an operation as revealed by his evaluation. In its present form the Guide easily becomes a suitable module in any compendium or handbook tailored for internal use by organizations. It is hoped the Guide will continue to serve immediate needs and will encourage continuing and more comprehensive efforts toward organizing nuclear criticality safety information

  15. Nuclear safety guide. TID-7016, Revision 2

    Energy Technology Data Exchange (ETDEWEB)

    Thomas, J T [ed.

    1978-05-01

    The Nuclear Safety Guide was first issued in 1956 as classified AEC report LA-2063 and was reprinted the next year, unclassified, as TID-7016. Revision 1, published in 1961, extended the scope and refined the guiding information. The present revision of the Guide differs significantly from its predecessor in that the latter was intentionally conservative in its recommendations. Firmly based on experimental evidence of criticality, the original Guide and the first revision were considered to be of most value to organizations whose activities with fissionable materials were not extensive and, secondarily, that it would serve as a point of departure for members of established nuclear safety teams, experienced in the field. The reader will find a significant change in the character of information presented in this version. Nuclear Criticality Safety has matured in the past twelve years. The advance of calculational capability has permitted validated calculations to extend and substitute for experimental data. The broadened data base has enabled better interpolation, extension, and understanding of available information, especially in areas previously addressed by undefined but adequate factors of safety. The content has been thereby enriched in qualitative guidance. The information inherently contains, and the user can recapture, the quantitative guidance characteristic of the formerGuides by employing appropriate safety factors. In fact, it becomes incumbent on the Criticality Safety Specialist to necessarily impose safety factors consistent with the possible normal and abnormal credible contingencies of an operation as revealed by his evaluation. In its present form the Guide easily becomes a suitable module in any compendium or handbook tailored for internal use by organizations. It is hoped the Guide will continue to serve immediate needs and will encourage continuing and more comprehensive efforts toward organizing nuclear criticality safety information.

  16. Radiation safety of Takasaki ion accelerators for advanced radiation in JAERI

    International Nuclear Information System (INIS)

    Watanabe, Hiromasa; Tanaka, Susumu; Anazawa, Yutaka

    1991-01-01

    Building layout of Takasaki ion accelerator facility has been started since 1987, with the propulsion of research development of (1) cosmetic environment materials, (2) nuclear fusion reactors, (3) biotechnology, and (4) new functional materials. This paper deals with an AVF cyclotron and a tandem type accelerator, focusing on safety design, radiation safety management, and radioactive waste management. Safety design is discussed in view of radiation shielding and activation countermeasures. Radiation safety management covers radiation monitoring in the workplace, exhaust radioactivity, environment outside the facility, and the other equipments; personal monitoring; and protective management of exposure. For radiation waste management, basic concept and management methods are commented on. (N.K.)

  17. The Advanced Glaucoma Intervention Study (AGIS): 14. Distinguishing progression of glaucoma from visual field fluctuations.

    Science.gov (United States)

    Kim, Jonghyeon; Dally, Leonard G; Ederer, Fred; Gaasterland, Douglas E; VanVeldhuisen, Paul C; Blackwell, Beth; Sullivan, E Kenneth; Prum, Bruce; Shafranov, George; Beck, Allen; Spaeth, George L

    2004-11-01

    To determine the least worsening of a visual field (VF) and the least number of confirming tests needed to identify progression of glaucomatous VF defects. Cohort study of participants in a clinical trial. Seven hundred fifty-two eyes of 565 patients with advanced glaucoma. Visual field tests were quantified with the Advanced Glaucoma Intervention Study (AGIS) VF defect score and the Humphrey Field Analyzer mean deviation (MD). Follow-up was 8 to 13 years. Two measures based on the AGIS VF defect score: (1) sustained decrease of VF (SDVF), a worsening from baseline by 2 (alternatively, 3 or 4) or more units and sustained for 2 (alternatively, 3) consecutive 6-month visits and (2) after the occurrence of SDVF, the average percent of eyes with worsening by 2 (alternatively, 3 or 4) or more units from baseline. Two similar measures based on MD. Based on the original AGIS criteria for SDVF (a worsening of 4 units in the AGIS score sustained during 3 consecutive 6-month visits), 31% of eyes had an SDVF. The percent of eyes with a sustained event increases by approximately 10% when either the minimum number of units of field loss or the minimum number of 6-month visits during which the loss is sustained decreases by 1. During 3 years of follow-up after a sustained event, a worsening of at least 2 units was found in 72% of eyes that had a 2-visit sustained event. The same worsening was found in 84% of eyes that had a 3-visit sustained event. Through the next 10 years after a sustained event, based on worsening of 2, 3, or 4 units at 2 or 3 consecutive tests, the loss reoccurred, on average, in >/=75% of study eyes. Results for MD are similar. In patients with advanced glaucoma, a single confirmatory test 6 months after a VF worsening indicates with at least 72% probability a persistent defect when the worsening is defined by at least 2 units of AGIS score or by at least 2 decibels of MD. When the number of confirmatory tests is increased from 1 to 2, the percentage of

  18. Advanced Neutron Source: The designer's perspective

    International Nuclear Information System (INIS)

    Peretz, F.J.

    1990-01-01

    The Advanced Neutron Source (ANS) is a research facility based on a 350 MW beam reactor, to be brought into service at the Oak Ridge National Laboratory at the end of the century. The primary objective is to provide high-flux neutron beams and guides, with cold, thermal, hot, and ultra-cold neutrons, for research in many fields of science. Secondary objectives include isotopes production, materials irradiation and activation analysis. The design of the ANS is strongly influenced by the historical development of research and power reactor concepts, and of the regulatory infrastructure of the Department of Energy (DOE) and the Nuclear Regulatory Commission (NRC). Current trends in reactor safety also impact the climate for the design of such a reactor

  19. A Quantum Field Approach for Advancing Optical Coherence Tomography Part I: First Order Correlations, Single Photon Interference, and Quantum Noise.

    Science.gov (United States)

    Brezinski, M E

    2018-01-01

    Optical coherence tomography has become an important imaging technology in cardiology and ophthalmology, with other applications under investigations. Major advances in optical coherence tomography (OCT) imaging are likely to occur through a quantum field approach to the technology. In this paper, which is the first part in a series on the topic, the quantum basis of OCT first order correlations is expressed in terms of full field quantization. Specifically first order correlations are treated as the linear sum of single photon interferences along indistinguishable paths. Photons and the electromagnetic (EM) field are described in terms of quantum harmonic oscillators. While the author feels the study of quantum second order correlations will lead to greater paradigm shifts in the field, addressed in part II, advances from the study of quantum first order correlations are given. In particular, ranging errors are discussed (with remedies) from vacuum fluctuations through the detector port, photon counting errors, and position probability amplitude uncertainty. In addition, the principles of quantum field theory and first order correlations are needed for studying second order correlations in part II.

  20. A Quantum Field Approach for Advancing Optical Coherence Tomography Part I: First Order Correlations, Single Photon Interference, and Quantum Noise

    Science.gov (United States)

    Brezinski, ME

    2018-01-01

    Optical coherence tomography has become an important imaging technology in cardiology and ophthalmology, with other applications under investigations. Major advances in optical coherence tomography (OCT) imaging are likely to occur through a quantum field approach to the technology. In this paper, which is the first part in a series on the topic, the quantum basis of OCT first order correlations is expressed in terms of full field quantization. Specifically first order correlations are treated as the linear sum of single photon interferences along indistinguishable paths. Photons and the electromagnetic (EM) field are described in terms of quantum harmonic oscillators. While the author feels the study of quantum second order correlations will lead to greater paradigm shifts in the field, addressed in part II, advances from the study of quantum first order correlations are given. In particular, ranging errors are discussed (with remedies) from vacuum fluctuations through the detector port, photon counting errors, and position probability amplitude uncertainty. In addition, the principles of quantum field theory and first order correlations are needed for studying second order correlations in part II.

  1. State of development progress of advanced boiling water reactors

    International Nuclear Information System (INIS)

    Tomono, Katsuya

    1982-01-01

    Advanced BWRs being developed at present are those aiming at the improvement of reliability and safety, the reduction of radiation exposure, the improvement of operation performance and capacity ratio of plants, and the heightening of economical efficiency by concentrating the experience and excellent technology of BWR manufacturers in the world. Now in Japan, the independence with Japanese technology is possible in almost all fields of nuclear power generation, and the improvement and standardization project is in progress to obtain the steady results. However, in order to pursue the most desirable BWRs conceivable at present, five BWR manufacturers in the world organized the Advanced Engineering Team in July, 1978, and performed the feasibility study of advanced BWRs for more than one year. Tokyo Electric Power Co., Inc., evaluated the report on the results, and judged that it is desirable to advance into the next stage aiming at the practical use of advanced BWRs. For the purpose, the electric power common research on advanced BWRs has been in progress, and the A-BWR project is to be examined in the third improvement and standardization project of MITI. The main technical features such as the coolant recirculation system of internal pump type, reinforced concrete containment vessels, fine motion control rod drive, improved core and fuel and others are explained. (Kako, I.)

  2. Safety and efficacy of first-line bevacizumab-based therapy in advanced non-squamous non-small-cell lung cancer (SAiL, MO19390): a phase 4 study.

    Science.gov (United States)

    Crinò, Lucio; Dansin, Eric; Garrido, Pilar; Griesinger, Frank; Laskin, Janessa; Pavlakis, Nick; Stroiakovski, Daniel; Thatcher, Nick; Tsai, Chun-Ming; Wu, Yi-long; Zhou, Caicun

    2010-08-01

    Results of two phase 3 trials have shown first-line bevacizumab in combination with chemotherapy improves clinical outcomes in patients with advanced or recurrent non-squamous non-small-cell lung cancer (NSCLC). The SAiL (MO19390) study was undertaken to assess the safety and efficacy of first-line bevacizumab combined with standard chemotherapy regimens in clinical practice. Between August, 2006, and June, 2008, patients with untreated locally advanced, metastatic, or recurrent non-squamous NSCLC were recruited to this open-label, single group, phase 4 study from centres in 40 countries. Eligible patients had histologically or cytologically documented inoperable, locally advanced, metastatic, or recurrent disease (stage IIIB-IV); an Eastern Cooperative Oncology Group performance status of 0-2; and adequate haematological, hepatic, and renal function. Patients received bevacizumab (7.5 or 15 mg/kg every 3 weeks) plus standard chemotherapy for up to six cycles, followed by single-agent bevacizumab until disease progression. The primary endpoint was safety; analysis was by intention to treat (ITT). This study is registered with ClinicalTrials.gov, number NCT00451906. At the final data cutoff (July 24, 2009), an ITT population of 2212 patients was assessed. The incidence of clinically significant (grade > or = 3) adverse events of special interest was generally low; thromboembolism occurred in 172 (8%) patients, hypertension in 125 (6%), bleeding in 80 (4%), proteinuria in 67 (3%), and pulmonary haemorrhage in 15 (1%). 57 (3%) patients died because of these adverse events, with thromboembolism (26 patients, 1%) and bleeding (17, 1%) as the most common causes. The most common grade 3 or higher serious adverse events deemed by investigators to be associated with bevacizumab were pulmonary embolism (28 patients; 1%) and epistaxis, neutropenia, febrile neutropenia, and deep vein thrombosis (all of which occurred in 13 patients [1%]). Bevacizumab was temporarily

  3. Occupational Safety and Health Curriculum Manual.

    Science.gov (United States)

    Gourley, Frank A., Jr., Comp.

    With the enactment of the Occupational Safety and Health Act of 1970, the need for manpower development in the field of industrial safety and hygiene has resulted in the development of a broad based program in Occupational Safety and Health. The manual provides information to administrators and instructors on a program of study in this field for…

  4. 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.

  5. Some Thoughts on Regulating Food Safety in China

    Institute of Scientific and Technical Information of China (English)

    Wang Lei

    2006-01-01

    The article analyses the current situation of food safety supervision in China, summarizes the deep reason behind the food safety and puts forward some suggestions to strengthen the supervision by using foreign references and advance operations from the legislation, the food safety supervision system and other aspects.

  6. Advanced technologies available for future solid propellant grains

    Energy Technology Data Exchange (ETDEWEB)

    Thepenier, J. [SNPE Propulsion, St Medard en Jalles (France); Fonblanc, G. [SNPE Propulsion, Vert le Petit (France). Centre de Recherche de Bouchet

    2001-06-01

    Significant advances have been made during the last decade in several fields of solid propulsion: the advances have enabled new savings in the motor development phase and in recurring costs, because they help limit the number of prototypes and tests. The purpose of the paper is to describe the improvements achieved by SNPE in solid grain technologies, making these technologies available for new developments in more efficient and reliable future SRMs: new energetic molecules, new solid propellants, new processes for grain manufacturing, quick response grain design tools associated with advanced models for grain performance predictions. Using its expertise in chemical synthesis, SNPE develops new molecules to fit new energetic material requirements. Tests based on new propellant formulations have produced good results in the propellant performance/safety behavior ratio. New processes have been developed simultaneously to reduce the manufacturing costs of the new propellants. In addition, the grain design has been optimized by using the latest generation of predictive theoretical tools supported by a large data bank of experimental parameters resulting from over 30 years' experience in solid propulsion: computer-aided method for the preliminary grain design; advanced models for SRM operating and performance predictions. All these technologies are available for industrial applications in future developments of solid propellant grains. (author)

  7. A content analysis of dissemination and implementation science resource initiatives: what types of resources do they offer to advance the field?

    Science.gov (United States)

    Darnell, Doyanne; Dorsey, Caitlin N; Melvin, Abigail; Chi, Jonathan; Lyon, Aaron R; Lewis, Cara C

    2017-11-21

    The recent growth in organized efforts to advance dissemination and implementation (D & I) science suggests a rapidly expanding community focused on the adoption and sustainment of evidence-based practices (EBPs). Although promising for the D & I of EBPs, the proliferation of initiatives is difficult for any one individual to navigate and summarize. Such proliferation may also result in redundant efforts or missed opportunities for participation and advancement. A review of existing D & I science resource initiatives and their unique merits would be a significant step for the field. The present study aimed to describe the global landscape of these organized efforts to advance D & I science. We conducted a content analysis between October 2015 and March 2016 to examine resources and characteristics of D & I science resource initiatives using public, web-based information. Included resource initiatives must have engaged in multiple efforts to advance D & I science beyond conferences, offered D & I science resources, and provided content in English. The sampling method included an Internet search using D & I terms and inquiry among internationally representative D & I science experts. Using a coding scheme based on a priori and grounded approaches, two authors consensus coded website information including interactive and non-interactive resources and information regarding accessibility (membership, cost, competitive application, and location). The vast majority (83%) of resource initiatives offered at least one of seven interactive resources (consultation/technical assistance, mentorship, workshops, workgroups, networking, conferences, and social media) and one of six non-interactive resources (resource library, news and updates from the field, archived talks or slides, links pages, grant writing resources, and funding opportunities). Non-interactive resources were most common, with some appearing frequently across resource initiatives (e.g., news and updates from the

  8. The comparative analysis of safety and economic competitiveness of the advanced high-power reactor projects of NPP

    International Nuclear Information System (INIS)

    Batyrbekov, G.A.; Makhanov, U.M.; Philimonova, R.A.; Kichutkina, E.G.

    2002-01-01

    The comparative analysis results of the safety and economic competitiveness of the seven advanced large sized reactors projects (900 MW and more) are submitted in that report: EPR, Frameatome France, Siemens Germany; EP-1000 Westinghouse, USA and Genesi Italy; Candu 9, Atomic Energy of Canada Ltd; System 80 +, ABB, USA; KNGR, group NSSS Engineering and Development, Korea Power Engineering Company, Inc; APWR, Electric Power company, Japan Atomic Power Company, Mitsubishi Heavy Industries, Westinghouse Electric; and WWER-1000 (V-392), Atomenergoproject/Gidropress Russian Federation. According to the economic competitiveness of listed compared power reactors the 14 criteria of safety have been accepted. These criteria: 1. Features of the barrier system of 'defence-in-depth'. 2. The self-security of a reactor under increase of power and reactivity of a reactor, decrease of the expense and phase transformations of the reactor core coolant (presence of negative feedbacks). 3. Presence of the reactor shutdown systems responding principles of a variety, independence and reservation. Presence of the passive means of initiation and operation of the emergency protection. 4. The emergency cooling of the core of reactor. A presence of the passive means of cooling. Presence of the water reservation for the water supply of the different safety systems. 5. The emergency electrical supply, its reliability and degree of reservation. 6. The prevention measures of the heavy accident with the melt core. The decrease of the heavy accident probability. 7. The account of the heavy accident under development of the levels of protection. 8. The protection levels of NPP, the technological criteria of efficiency of the each safety barriers and the limiting radiation criteria for the each level of protection , in particular for the design-basis and beyond-design-basis accidents. 9. The measures for reduction of the heavy accident consequences. The management by the beyond

  9. NS [Nuclear Safety] update. Current safety and security activities and developments taking place in the Department of Nuclear Safety and Security. Issue no. 4, June 2007

    International Nuclear Information System (INIS)

    2007-04-01

    This newsletter contains information on the Centre for Advanced Safety Assessment Tools (CASAT), the new strategy for the recovery of radioactive sources, the Technical Support Organization Conference and a message form the Director of the Division of Nuclear Installation Safety. To improve the efficiency of safety assessment methods, ensure transparency in their validation and application and establish an excellent knowledge base and training programmes, the IAEA's Centre for Advanced Safety Assessment Tools (CASAT) has therefore been formed. The Centre addresses the need for continuous technical support mechanisms for safety assessment methods. It provides support to Member States to enhance their safety assessment capabilities for present and future generations of nuclear systems, with a special focus on countries with a developing nuclear technology and nuclear safety infrastructure. It serves as a consolidated repository of relevant safety analysis knowledge, provides for focused training including advanced analytical simulations, and supports collaboration on safety assessment projects among Member States. The resources provided through CASAT include codes, models, databases, verification and validation information, analytical procedures and guides. The main purpose of the recently established Radioactive Source Technical Coordination Group (RSTCG) is to facilitate the technical coordination of activities of the IAEA related to the control and management of radioactive sources through the development of common approaches in technical matters and to advise the management of the relevant Divisions. It is the task of the RSTCG to provide the programme managers of the participating divisions/sections with a common opinion/advice on technical issues related to the control and management of radioactive sources. The RSTCG members obtain, inter alia from programme managers, information on all relevant project proposals, and share relevant materials in due time to

  10. Statistical assessment of fire safety in multi-residential buildings in Slovenia

    Directory of Open Access Journals (Sweden)

    Domen Kušar

    2009-01-01

    Full Text Available Nearly a third of residential units in Slovenia are located in multi-residential buildings. The majority of such buildings were built after WW2, when the need for suitable accommodation buildings was at its peak. They were built using the construction possibilities and requirements of the time. Every year there are over 200 fires in these buildings, resulting in fatalities and vast material damage. Due to the great efforts over the past centuries, which were all mainly aimed at replacing combustible construction materials with non-combustible ones, and with advancements in fire service equipment and techniques, the number of fires and their scope has decreased significantly but they were not entirely put out. New and greater advances in the field of fire safety of multi-residential buildings became obvious within the last few years, when stricter regulations regarding the construction of such objects came into force. Developments in science and within the industry itself brought about several new solutions in improving the situation in this field, which has been confirmed by experiences from abroad. Unfortunately in Slovenia, the establishment of safety principles still depends mainly on an occupants’ perception, financial means, and at the same time, certain implementation procedures that are much more complicated due to new property ownership. With the aid of the statistical results from the 2002 Census and contemporary fire safety requirements, this article attempts to show the present-day situation of the problem at both the state and municipality level and will propose solutions to improve this situation. The authors established that not even one single older, multi-residential building meets complies with modern requirements. Fortunately, the situation is improved by the fact that most buildings in Slovenia are built from non-combustible materials (concrete, brick, which limit the spread of fire.

  11. Indian advanced nuclear reactors

    International Nuclear Information System (INIS)

    Saha, D.; Sinha, R.K.

    2005-01-01

    For sustainable development of nuclear energy, a number of important issues like safety, waste management, economics etc. are to be addressed. To do this, a number of advanced reactor designs as well as fuel cycle technologies are being pursued worldwide. The advanced reactors being developed in India are the AHWR and the CHTR. Both the reactors use thorium based fuel and have many passive features. This paper describes the Indian advanced reactors and gives a brief account of the international initiatives for the sustainable development of nuclear energy. (author)

  12. Traceability technique of isotopic application in food safety

    International Nuclear Information System (INIS)

    Guo Boli; Wei Yimin; Pan Jiarong

    2006-01-01

    Epidemics such as BSE, mouth and foot disease, avian influenza have brought new pressure to food safety management, constituted a extreme threat to people health, and caused serious economic loss and social scare to countries with outbreaks of above diseases. Isotopic tracing technology is an effect tool for tracing food origin and implementing the preservation of production premise in the world at present, and it is promising in the field of food safety traceability, so some developed countries have put a lot of effort on establishment of isotopic technology for food traceability. In this paper, the basic principles of isotopic tracing technology and the recent research advancement were be expounded, and the differentiate and connection was be compared between isotopic tracing technology and others. Furthermore, the suggestion about study of isotopic tracing technology in China was put forward. The aim of the paper is to promote the establishment and improvement of food traceability system, and ensure the consumer health. (authors)

  13. RISMC Advanced Safety Analysis Project Plan – FY 2015 - FY 2019

    Energy Technology Data Exchange (ETDEWEB)

    Szilard, Ronaldo H. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Smith, Curtis L. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Youngblood, Robert [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2014-09-01

    In this report, a project plan is developed, focused on industry applications, using Risk-Informed Safety Margin Characterization (RISMC) tools and methods applied to realistic, relevant, and current interest issues to the operating nuclear fleet. RISMC focuses on modernization of nuclear power safety analysis (tools, methods and data); implementing state-of-the-art modeling techniques (which include, for example, enabling incorporation of more detailed physics as they become available); taking advantage of modern computing hardware; and combining probabilistic and mechanistic analyses to enable a risk informed safety analysis process. The modernized tools will maintain the current high level of safety in our nuclear power plant fleet, while providing an improved understanding of safety margins and the critical parameters that affect them. Thus, the set of tools will provide information to inform decisions on plant modifications, refurbishments, and surveillance programs, while improving economics. This set of tools will also benefit the design of new reactors, enhancing safety per unit cost of a nuclear plant. The proposed plan will focus on application of the RISMC toolkit, in particular, solving realistic problems of important current issues to the nuclear industry, in collaboration with plant owners and operators to demonstrate the usefulness of these tools in decision making.

  14. Feasibility of a Video-Based Advance Care Planning Website to Facilitate Group Visits among Diverse Adults from a Safety-Net Health System.

    Science.gov (United States)

    Zapata, Carly; Lum, Hillary D; Wistar, Emily; Horton, Claire; Sudore, Rebecca L

    2018-02-20

    Primary care providers in safety-net settings often do not have time to discuss advance care planning (ACP). Group visits (GV) may be an efficient means to provide ACP education. To assess the feasibility and impact of a video-based website to facilitate GVs to engage diverse adults in ACP. Feasibility pilot among patients who were ≥55 years of age from two primary care clinics in a Northern California safety-net setting. Participants attended two 90-minute GVs and viewed the five steps of the movie version of the PREPARE website ( www.prepareforyourcare.org ) concerning surrogates, values, and discussing wishes in video format. Two clinician facilitators were available to encourage participation. We assessed pre-to-post ACP knowledge, whether participants designated a surrogate or completed an advance directive (AD), and acceptability of GVs and PREPARE materials. We conducted two GVs with 22 participants. Mean age was 64 years (±7), 55% were women, 73% nonwhite, and 55% had limited literacy. Knowledge improved about surrogate designation (46% correct pre vs. 85% post, p = 0.01) and discussing decisions with others (59% vs. 90%, p = 0.01). Surrogate designation increased (48% vs. 85%, p = 0.01) and there was a trend toward AD completion (9% vs. 24%, p = 0.21). Participants rated the GVs and PREPARE materials a mean of 8 (±3.1) on a 10-point acceptability scale. Using the PREPARE movie to facilitate ACP GVs for diverse adults in safety net, primary care settings is feasible and shows potential for increasing ACP engagement.

  15. 75 FR 68224 - Safety Management Systems for Part 121 Certificate Holders

    Science.gov (United States)

    2010-11-05

    ... safety audit (LOSA), and an advanced qualification program (AQP) as part of the SMS. The FAA must issue a... the SMS safety assurance process, periodic audits of flight crew performance, such as Line Operations... programs: ASAPs, flight operational quality assurance systems (FOQAs), LOSAs, and advanced qualification...

  16. Integral fast reactor safety features

    International Nuclear Information System (INIS)

    Cahalan, J.E.; Kramer, J.M.; Marchaterre, J.F.; Mueller, C.J.; Pedersen, D.R.; Sevy, R.H.; Wade, D.C.; Wei, T.Y.C.

    1988-01-01

    The Integral Fast Reactor (IFR) is an advanced liquid-metal-cooled reactor concept being developed at Argonne National Laboratory. The two major goals of the IFR development effort are improved economics and enhanced safety. In addition to liquid metal cooling, the principal design features that distinguish the IFR are: (1) a pool-type primary system, (2) an advanced ternary alloy metallic fuel, and (3) an integral fuel cycle with on-site fuel reprocessing and fabrication. This paper focuses on the technical aspects of the improved safety margins available in the IFR concept. This increased level of safety is made possible by (1) the liquid metal (sodium) coolant and pool-type primary system layout, which together facilitate passive decay heat removal, and (2) a sodium-bonded metallic fuel pin design with thermal and neutronic properties that provide passive core responses which control and mitigate the consequences of reactor accidents

  17. Analysis of rainfall-induced slope instability using a field of local factor of safety

    Science.gov (United States)

    Lu, Ning; Şener-Kaya, Başak; Wayllace, Alexandra; Godt, Jonathan W.

    2012-01-01

    Slope-stability analyses are mostly conducted by identifying or assuming a potential failure surface and assessing the factor of safety (FS) of that surface. This approach of assigning a single FS to a potentially unstable slope provides little insight on where the failure initiates or the ultimate geometry and location of a landslide rupture surface. We describe a method to quantify a scalar field of FS based on the concept of the Coulomb stress and the shift in the state of stress toward failure that results from rainfall infiltration. The FS at each point within a hillslope is called the local factor of safety (LFS) and is defined as the ratio of the Coulomb stress at the current state of stress to the Coulomb stress of the potential failure state under the Mohr-Coulomb criterion. Comparative assessment with limit-equilibrium and hybrid finite element limit-equilibrium methods show that the proposed LFS is consistent with these approaches and yields additional insight into the geometry and location of the potential failure surface and how instability may initiate and evolve with changes in pore water conditions. Quantitative assessments applying the new LFS field method to slopes under infiltration conditions demonstrate that the LFS has the potential to overcome several major limitations in the classical FS methodologies such as the shape of the failure surface and the inherent underestimation of slope instability. Comparison with infinite-slope methods, including a recent extension to variably saturated conditions, shows further enhancement in assessing shallow landslide occurrence using the LFS methodology. Although we use only a linear elastic solution for the state of stress with no post-failure analysis that require more sophisticated elastoplastic or other theories, the LFS provides a new means to quantify the potential instability zones in hillslopes under variably saturated conditions using stress-field based methods.

  18. Electrical safety guidelines

    Energy Technology Data Exchange (ETDEWEB)

    1993-09-01

    The Electrical Safety Guidelines prescribes the DOE safety standards for DOE field offices or facilities involved in the use of electrical energy. It has been prepared to provide a uniform set of electrical safety standards and guidance for DOE installations in order to affect a reduction or elimination of risks associated with the use of electrical energy. The objectives of these guidelines are to enhance electrical safety awareness and mitigate electrical hazards to employees, the public, and the environment.

  19. Recent advances in head-mounted light field displays for virtual and augmented reality (Conference Presentation)

    Science.gov (United States)

    Hua, Hong

    2017-02-01

    Head-mounted light field displays render a true 3D scene by sampling either the projections of the 3D scene at different depths or the directions of the light rays apparently emitted by the 3D scene and viewed from different eye positions. They are capable of rendering correct or nearly correct focus cues and addressing the very well-known vergence-accommodation mismatch problem in conventional virtual and augmented reality displays. In this talk, I will focus on reviewing recent advancements of head-mounted light field displays for VR and AR applications. I will demonstrate examples of HMD systems developed in my group.

  20. The ARIES-AT advanced tokamak, Advanced technology fusion power plant

    International Nuclear Information System (INIS)

    Najmabadi, Farrokh; Abdou, A.; Bromberg, L.

    2006-01-01

    The ARIES-AT study was initiated to assess the potential of high-performance tokamak plasmas together with advanced technology in a fusion power plant and to identifying physics and technology areas with the highest leverage for achieving attractive and competitive fusion power in order to guide fusion R and D. The 1000-MWe ARIES-AT design has a major radius of 5.2 m, a minor radius of 1.3 m, a toroidal β of 9.2% (β N = 5.4) and an on-axis field of 5.6 T. The plasma current is 13 MA and the current-drive power is 35 MW. The ARIES-AT design uses the same physics basis as ARIES-RS, a reversed-shear plasma. A distinct difference between ARIES-RS and ARIES-AT plasmas is the higher plasma elongation of ARIES-AT (κ x = 2.2) which is the result of a 'thinner' blanket leading to a large increase in plasma β to 9.2% (compared to 5% for ARIES-RS) with only a slightly higher β N . ARIES-AT blanket is a simple, low-pressure design consisting of SiC composite boxes with a SiC insert for flow distribution that does not carry any structural load. The breeding coolant (Pb-17Li) enters the fusion core from the bottom, and cools the first wall while traveling in the poloidal direction to the top of the blanket module. The coolant then returns through the blanket channel at a low speed and is superheated to ∼1100 deg. C. As most of the fusion power is deposited directly into the breeding coolant, this method leads to a high coolant outlet temperature while keeping the temperature of the SiC structure as well as interface between SiC structure and Pb-17Li to about 1000 deg. C. This blanket is well matched to an advanced Brayton power cycle, leading to an overall thermal efficiency of ∼59%. The very low afterheat in SiC composites results in exceptional safety and waste disposal characteristics. All of the fusion core components qualify for shallow land burial under U.S. regulations (furthermore, ∼90% of components qualify as Class-A waste, the lowest level). The ARIES

  1. Transport safety and struggle against malevolent acts: a synergy to be developed - Protecting transports against malevolent acts, Synergies between security and safety: lessons learned from the IAEA international conference, Role of the IRSN transport operational level in the field of safety, Transparency and secret in the field of nuclear material transport

    International Nuclear Information System (INIS)

    Riac, Christian; Flory, Denis; Loiseau, Olivier; Mermaz, Frederic; Demolins, Laurent

    2012-01-01

    The first article proposes an interview with the chief of the security department within the French ministry of Ecology, Sustainable Development, Transports and Housing who comments his missions and his relationships with the ASN and the French Home Office for the protection and control of nuclear materials. A second article discusses the lessons learned from an IAEA international conference about the relationship between the approaches to security and to safety. The third article briefly describes the role of the IRSN transport operational level in the field of safety. The last article discusses how opposite notions like transparency and secret are managed in the case of nuclear material transport

  2. Defence-in-depth and development of safety requirements for advanced nuclear reactors

    International Nuclear Information System (INIS)

    Carnino, A.; Gasparini, M.

    2002-01-01

    The paper addresses a general approach for the preparation of the design safety requirements using the IAEA Safety Objectives and the strategy of defence-in-depth. It proposes a general method (top-down approach) to prepare safety requirements for a given kind of reactor using the IAEA requirements for nuclear power plants as a starting point through a critical interpretation and application of the strategy of defence-in-depth. The IAEA has recently developed a general methodology for screening the defence-in-depth of nuclear power plants starting from the fundamental safety objectives as proposed in the IAEA Safety Fundamentals. This methodology may provide a useful tool for the preparation of safety requirements for the design and operation of any kind of reactor. Currently the IAEA is preparing the technical basis for the development of safety requirements for Modular High Temperature Gas Reactors, with the aim of showing the viability of the method. A draft TECDOC has been prepared and circulated among several experts for comments. This paper is largely based on the content of the draft TECDOC. (authors)

  3. Prospects for nuclear safety research

    Energy Technology Data Exchange (ETDEWEB)

    Beckjord, E.S.

    1995-04-01

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

  4. Deep Borehole Disposal Safety Analysis.

    Energy Technology Data Exchange (ETDEWEB)

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

    2016-10-01

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

  5. Advanced reactor development for non-electric applications

    International Nuclear Information System (INIS)

    Chang, M.H.; Kim, S.H.

    1996-01-01

    Advance in the nuclear reactor technology achieved through nuclear power programs carried out in the world has led nuclear communities to direct its attention to a better and peaceful utilization of nuclear energy in addition to that for power generation. The efforts for non-electric application of nuclear energy has been pursued in a limited number of countries in the world for their special needs. However, those needs and the associated efforts contributed largely to the development and practical realization of advanced reactors characterized by highly improved reactor safety and reliability by deploying the most up-to-date safety technologies. Due mainly to the special purpose of utilization, economic reasons and ease in implementation of new advanced technologies, small and medium reactors have become a major stream in the reactor developments for non-electric applications. The purpose of this paper is to provide, to the interested nuclear society, the overview of the development status and design characteristics of selected advanced nuclear reactors previously developed and/or currently under development specially for non-electric applications. Major design technologies employed in those reactors to enhance the reactor safety and reliability are reviewed to present the underlying principles of the design. Along with the overview, this paper also introduces a development program and major design characteristics of an advanced integral reactor (SMART) for co-generation purpose currently under conceptual development in Korea. (author)

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

    International Nuclear Information System (INIS)

    2012-03-01

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

  7. RiskSOAP: Introducing and applying a methodology of risk self-awareness in road tunnel safety.

    Science.gov (United States)

    Chatzimichailidou, Maria Mikela; Dokas, Ioannis M

    2016-05-01

    Complex socio-technical systems, such as road tunnels, can be designed and developed with more or less elements that can either positively or negatively affect the capability of their agents to recognise imminent threats or vulnerabilities that possibly lead to accidents. This capability is called risk Situation Awareness (SA) provision. Having as a motive the introduction of better tools for designing and developing systems that are self-aware of their vulnerabilities and react to prevent accidents and losses, this paper introduces the Risk Situation Awareness Provision (RiskSOAP) methodology to the field of road tunnel safety, as a means to measure this capability in this kind of systems. The main objective is to test the soundness and the applicability of RiskSOAP to infrastructure, which is advanced in terms of technology, human integration, and minimum number of safety requirements imposed by international bodies. RiskSOAP is applied to a specific road tunnel in Greece and the accompanying indicator is calculated twice, once for the tunnel design as defined by updated European safety standards and once for the 'as-is' tunnel composition, which complies with the necessary safety requirements, but calls for enhancing safety according to what EU and PIARC further suggest. The derived values indicate the extent to which each tunnel version is capable of comprehending its threats and vulnerabilities based on its elements. The former tunnel version seems to be more enhanced both in terms of it risk awareness capability and safety as well. Another interesting finding is that despite the advanced tunnel safety specifications, there is still room for enriching the safe design and maintenance of the road tunnel. Copyright © 2016 Elsevier Ltd. All rights reserved.

  8. Recent development of nuclear power in Japan and instrumentation and control system and control room equipment for advanced light water reactors

    International Nuclear Information System (INIS)

    Wakayama, N.

    1992-01-01

    This paper was provided for the 13th IAEA/IWG-NPPCI Meeting and aims to introduce an outline of recent development of nuclear power in Japan and some topics in the field of nuclear power plant control and instrumentation. Forty units of nuclear power plants are in operation in Japan and five units of BWRs and six PWRs are under construction. Construction of prototype FBR Monju have almost completed an construction of High-Temperature Engineering Test Reactor, HTTR, started in March 1991. In parallel of those, extensive effort has been carried out to develop the third generation LWRs which are called Advanced BWR (ABWR) and Advanced PWR (APWR). Two Advanced BWRs are under safety review for construction. Instrumentation and control system of these Advanced LWRs adopts integrated digital I and C system, optical multiplexing signal transmission, fault tolerant control systems and software logic for reactor protection and safety systems and enhances plant control performance and provides human-friendly operation and maintenance environments. Main control room of these Advanced LWRs, comprised with large display panels and advanced console, has special futures such as one-man sit-down operation, human friendly man-machine interface, high level automation in operation and maintenance. (author). 7 refs, 9 figs, 1 tab

  9. A brief review of advances in complex networks of nuclear science and technology field

    International Nuclear Information System (INIS)

    Fang Jinqing

    2010-01-01

    A brief review of advances in complex networks of nuclear science and technology field at home and is given and summarized. These complex networks include: nuclear energy weapon network, network centric warfare, beam transport networks, continuum percolation evolving network associated with nuclear reactions, global nuclear power station network, (nuclear) chemistry reaction networks, radiological monitoring and anti-nuclear terror networks, and so on. Some challenge issues and development prospects of network science are pointed out finally. (authors)

  10. Analysis of exposure to electromagnetic fields in a healthcare environment: simulation and experimental study.

    Science.gov (United States)

    de Miguel-Bilbao, Silvia; Martín, Miguel Angel; Del Pozo, Alejandro; Febles, Victor; Hernández, José A; de Aldecoa, José C Fernández; Ramos, Victoria

    2013-11-01

    Recent advances in wireless technologies have lead to an increase in wireless instrumentation present in healthcare centers. This paper presents an analytical method for characterizing electric field (E-field) exposure within these environments. The E-field levels of the different wireless communications systems have been measured in two floors of the Canary University Hospital Consortium (CUHC). The electromagnetic (EM) conditions detected with the experimental measures have been estimated using the software EFC-400-Telecommunications (Narda Safety Test Solutions, Sandwiesenstrasse 7, 72793 Pfullingen, Germany). The experimental and simulated results are represented through 2D contour maps, and have been compared with the recommended safety and exposure thresholds. The maximum value obtained is much lower than the 3 V m(-1) that is established in the International Electrotechnical Commission Standard of Electromedical Devices. Results show a high correlation in terms of E-field cumulative distribution function (CDF) between the experimental and simulation results. In general, the CDFs of each pair of experimental and simulated samples follow a lognormal distribution with the same mean.

  11. Third Advances in Solar Physics Euroconference: Magnetic Fields and Oscillations

    Science.gov (United States)

    Schmieder, B.; Hofmann, A.; Staude, J.

    The third Advances in Solar Physics Euroconference (ASPE) "Magnetic Fields and Oscillations"concluded a series of three Euroconferences sponsored by the European Union. The meeting took place in Caputh near Potsdam, Germany, on September 22-25, 1998, followed by the JOSO (Joint Organization for Solar Observations) 30th Annual Board Meeting on September 26, 1998. The ASPE formula is attractive and compares well with other meetings with "show-and-tell" character. This meeting had 122 participants coming from 26 countries; 36 participants came from countries formerly behind the Iron Curtain; a "politically incorrect" estimate says that 48 participants were below 35 years of age, with an unusually large female-to-male ratio. This characteristic of youngness is the more striking since solar physics is a perhaps overly established field exhibiting an overly senior age profile. It was a good opportunity to train this young generation in Solar Physics. The conference topic "Magnetic Fields and Oscillations" obviously was wide enough to cater to many an interest. These proceedings are organized according to the structure of the meeting. They include the topics 'High resolution spectropolarimetry and magnetometry', 'Flux-tube dynamics', 'Modelling of the 3-D magnetic field structure', 'Mass motions and magnetic fields in sunspot penumbral structures', 'Sunspot oscillations', 'Oscillations in active regions - diagnostics and seismology', 'Network and intranetwork structure and dynamics', and 'Waves in magnetic structures'. These topics covered the first 2.5 days of the conference. The reviews, oral contributions, and poster presentations were by no means all of the meeting. The ASPE formula also adds extensive plenary sessions of JOSO Working groups on topics that involve planning of Europe-wide collaboration. At this meeting these concerned solar observing techniques, solar data bases, coordination between SOHO and ground-based observing, and preparations for August 11, 1999

  12. Annual report 90. Institute for advanced materials

    International Nuclear Information System (INIS)

    1991-01-01

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

  13. Cookbooks in U.S. history: How do they reflect food safety from 1896 to 2014?

    Science.gov (United States)

    Almanza, Barbara A; Byrd, Karen S; Behnke, Carl; Ma, Jing; Ge, Li

    2017-09-01

    Historical cookbooks as a source of recipes and food preparation information would be expected to document advancements in food safety related to kitchen equipment, cleaning, foodborne illness knowledge, and consumer education materials. In turn, this food safety information might be expected to contribute to consumers' food safety behaviors. Using both quantitative and qualitative research methodology, this study assessed how food safety information in cookbooks changed and how quickly advancements were incorporated. Faster assimilation into cookbooks was associated with kitchen equipment, educational resources (hotlines and websites), and foodborne illness outbreaks. The rate of incorporation of education materials was moderate. Cleaning advances were the slowest to be incorporated. Modern cookbooks published after the 1980's rapidly evolved with advances in food safety knowledge. Copyright © 2017 Elsevier Ltd. All rights reserved.

  14. The IAEA Activities in the Field of Fast Reactors Technology Development

    International Nuclear Information System (INIS)

    Monti, Stefano

    2011-01-01

    Main activities of the IAEA Programme on Fast Reactor: Carry out Collaborative Research Projects (CRPs) of common interest to the TWG-FR Member States in the field of FRs and ADS; Secure Training and Education in the field of fast neutron system physics, technology and applications; Support Fast Reactor data retrieval and knowledge preservation activities in MSs; Provide support to IAEA Nuclear Safety and Security Department for preparation of fast reactor Safety standards / requirements / guides. IAEA TWG-FR Functions: Provide advice and guidance, and marshal support in their countries for implementation of IAEA’s programmatic activities in the area of advanced technologies and R&D for fast reactors and sub-critical hybrid systems for energy production and for utilization/transmutation of long-lived nuclides; Provide a forum for information and knowledge sharing on national and international development programs; Act as a link between IAEA’s activities in the specific area of the TWG-FR and national scientific communities, delivering information from and to national communities

  15. Safety design requirements for safety systems and components of JSFR

    International Nuclear Information System (INIS)

    Kubo, Shigenobu; Shimakawa, Yoshio; Yamano, Hidemasa; Kotake, Shoji

    2011-01-01

    Safety design requirements for JSFR were summarized taking the development targets of the FaCT project and design feature of JSFR into account. The related safety principle and requirements for Monju, CRBRP, PRISM, SPX, LWRs, IAEA standards, goals of GIF, basic principle of INPRO etc. were also taken into account so that the safety design requirements can be a next-generation global standard. The development targets for safety and reliability are set based on those of FaCT, namely, ensuring safety and reliability equal to future LWR and related fuel cycle facilities. In order to achieve these targets, the defence-in-depth concept is used as the basic safety design principle. General features of the safety design requirements are 1) Achievement of higher reliability, 2) Achievement of higher inspectability and maintainability, 3) Introduction of passive safety features, 4) Reduction of operator action needs, 5) Design consideration against Beyond Design Basis Events, 6) In-Vessel Retention of degraded core materials, 7) Prevention and mitigation against sodium chemical reactions, and 8) Design against external events. The current specific requirements for each system and component are summarized taking the basic design concept of JSFR into account, which is an advanced loop-type large-output power plant with a mixed-oxide-fuelled core. (author)

  16. Advanced gadolinia core and Toshiba advanced reactor management system

    International Nuclear Information System (INIS)

    Miyamoto, Toshiki; Yoshioka, Ritsuo; Ebisuya, Mitsuo

    1988-01-01

    At the Hamaoka Nuclear Power Station, Unit No. 3, advanced core design and core management technology have been adopted, significantly improving plant availability, operability and reliability. The outstanding technologies are the advanced gadolinia core (AGC) which utilizes gadolinium for the axial power distribution control, and Toshiba advanced reactor management system (TARMS) which uses a three-dimensional core physics simulator to calculate the power distribution. Presented here are the effects of these advanced technologies as observed during field testing. (author)

  17. Virtual sensors for advanced vehicle stability control

    NARCIS (Netherlands)

    Leenen, R.; Schouten, H.

    2010-01-01

    Advanced vehicle control technologies provide a great potential to further improve vehicle handling, ride and safety. The goal of this research is to demonstrate the added value of the TNO Vehicle State Estimation module to integrated active safety. State-of-the-art Electronic Stability Control

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

    International Nuclear Information System (INIS)

    1990-05-01

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

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

    International Nuclear Information System (INIS)

    1991-08-01

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

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

    International Nuclear Information System (INIS)

    1990-02-01

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

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

    International Nuclear Information System (INIS)

    1989-05-01

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

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

    International Nuclear Information System (INIS)

    1989-11-01

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

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

    International Nuclear Information System (INIS)

    1985-04-01

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

  4. Development of quantitative goals for inherent safety feature design and licensing

    International Nuclear Information System (INIS)

    Kastenberg, W.E.; Apostolakis, G.; Dhir, V.K.; Okrent, D.

    1987-01-01

    There is now considerable interest in the development of advanced fast reactors whose major focus is inherent safety. The achievement of inherent safety can be viewed from several aspects. In the Integral Fast Reactor Concept the approach is to utilize the intrinsic characteristics of pool-type liquid metal fast breeder reactors (LMFBRs) and the properties of metal fuels to integrate a high degree of inherent safety into the design. The PRISM and SAFR concepts focus on other inherent safety features. The reactors discussed above represent a radical departure from existing LWR designs as well as previous LMFBR designs (e.g., CRBRP) which are based, for the most part, on the General Design Criteria found in 10CFR50 Appendix. In view of these parallel developments (advanced reactors exploiting inherent safety and the use of quantitative goals to augment licensing), there appears to be a need to perform research on the development of methods for designing, assessing, and licensing inherent safety features in advanced reactors. The objectives of such research are outlined

  5. The safety of domestic robotics: A survey of various safety-related publications

    OpenAIRE

    Tadele, T.S.; de Vries, Theodorus J.A.; Stramigioli, Stefano

    2014-01-01

    Different branches of technology are striving to come up with new advancements that will enhance civilization and ultimately improve the quality of life. In the robotics community, strides have been made to bring the use of personal robots in office and home environments on the horizon. Safety is one of the critical issues that must be guaranteed for the successful acceptance, deployment, and utilization of domestic robots. Unlike the barrier-based operational safety guarantee that is widely ...

  6. Lack of a safety culture destroyed the reactor

    International Nuclear Information System (INIS)

    Vuori, A.

    1996-01-01

    The importance of good safety culture in the operation of nuclear power plants is discussed. The modern safety culture emphasizes responsibility and preventive maintenance that can eliminate or minimize faults in advance. In the article the accident of Chernobyl is used as an example of the lack of safety culture. (1 fig.)

  7. Probabilistic Analysis of Passive Safety System Reliability in Advanced Small Modular Reactors: Methodologies and Lessons Learned

    Energy Technology Data Exchange (ETDEWEB)

    Grabaskas, David; Bucknor, Matthew; Brunett, Acacia; Grelle, Austin

    2015-06-28

    Many advanced small modular reactor designs rely on passive systems to fulfill safety functions during accident sequences. These systems depend heavily on boundary conditions to induce a motive force, meaning the system can fail to operate as intended due to deviations in boundary conditions, rather than as the result of physical failures. Furthermore, passive systems may operate in intermediate or degraded modes. These factors make passive system operation difficult to characterize with a traditional probabilistic framework that only recognizes discrete operating modes and does not allow for the explicit consideration of time-dependent boundary conditions. Argonne National Laboratory has been examining various methodologies for assessing passive system reliability within a probabilistic risk assessment for a station blackout event at an advanced small modular reactor. This paper describes the most promising options: mechanistic techniques, which share qualities with conventional probabilistic methods, and simulation-based techniques, which explicitly account for time-dependent processes. The primary intention of this paper is to describe the strengths and weaknesses of each methodology and highlight the lessons learned while applying the two techniques while providing high-level results. This includes the global benefits and deficiencies of the methods and practical problems encountered during the implementation of each technique.

  8. FY1996 annual report on the advanced combustion science in microgravity field

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-03-01

    Research was implemented continuously from the previous year on combustion equipment enabling advanced combustion technologies, by studying combustion in a microgravity field, for the purpose of preventing environmental pollution caused by diversification of energy sources and exhaust gasses. In joint studies with NASA, the themes of the previous year were continued, for which tests were conducted 37 times using Japanese drop test equipment and 131 times using NASA's. The evaluation and analysis of the experiments and test data by the microgravity test equipment were, in addition to the themes of the previous year, such that micro observation for ignition/combustion mechanism of fuel spray droplets was made, as well as studies on fuel droplets combustion by a laser diagnostic device, concerning combustion of fuel droplets and vaporization process, that flame spread on solid substances was researched in relation to combustion characteristics of high density fuels, and that mixed gas combustion on a solid surface was studied in connection with the research on flammability limits. Furthermore, a study on combustion technology for gas turbines was added for the purpose of studying an advanced combustor. (NEDO)

  9. Integrated Safety Culture Model and Application

    Institute of Scientific and Technical Information of China (English)

    汪磊; 孙瑞山; 刘汉辉

    2009-01-01

    A new safety culture model is constructed and is applied to analyze the correlations between safety culture and SMS. On the basis of previous typical definitions, models and theories of safety culture, an in-depth analysis on safety culture's structure, composing elements and their correlations was conducted. A new definition of safety culture was proposed from the perspective of sub-cuhure. 7 types of safety sub-culture, which are safety priority culture, standardizing culture, flexible culture, learning culture, teamwork culture, reporting culture and justice culture were defined later. Then integrated safety culture model (ISCM) was put forward based on the definition. The model divided safety culture into intrinsic latency level and extrinsic indication level and explained the potential relationship between safety sub-culture and all safety culture dimensions. Finally in the analyzing of safety culture and SMS, it concluded that positive safety culture is the basis of im-plementing SMS effectively and an advanced SMS will improve safety culture from all around.

  10. China's Work Safety Report

    Institute of Scientific and Technical Information of China (English)

    Liang Jiakun

    2005-01-01

    @@ General Situation of China's Work Safety in 2004 In 2004, the national work safety situation remained stable as a whole and gained momentum to improve. The totality of accidents held the line and began to drop. The safety conditions in industrial,mining, and commercial/trading enterprises improved. Progress was made in ensuring work safety in the relevant industries and fields. The safety situation in most provinces (autonomous regions, municipalities directly under the Central Government) kept stable.

  11. Progress in high energy physics and nuclear safety : Proceedings of the NATO Advanced Research Workshop on Safe Nuclear Energy

    CERN Document Server

    Polański, Aleksander; Begun, Viktor

    2009-01-01

    The book contains recent results on the progress in high-energy physics, accelerator, detection and nuclear technologies, as well as nuclear safety in high-energy experimentation and in nuclear industry, covered by leading experts in the field. The forthcoming experiments at the Large Hadron Collider (LHC) at CERN and cosmic-ray experiments are highlighted. Most of the current high-energy experiments and their physical motivation are analyzed. Various nuclear energy safety aspects, including progress in the production of new radiation-resistant materials, new and safe nuclear reactor designs, such as the slowly-burning reactor, as well as the use of coal-nuclear symbiotic methods of energy production can be found in the book.

  12. Analysis, fabrication, and field test of an advanced embedded throwing electromechanical sensing system

    Energy Technology Data Exchange (ETDEWEB)

    Gao, Zhen; Zhang, Dan [Beijing JiaoTong University, Beijing (China)

    2014-01-15

    Scientific measuring equipment is important in maintaining and further improving the daily training quality of professional athletes. In throwing sports, only kinematic information is usually recorded by several high-speed cameras, whereas the dynamic data are lacking. An advanced embedded throwing system is analyzed, fabricated, and field tested. This throwing system can be used to substitute the normal shot-put that obtains acceleration information from the upper limb when force is applied onto the device. This device has four main parts, namely, a mechanical shell, an embedded sensor, a signal processing circuit, and interface ports. The detailed design, simulation, and prototyping process are introduced in this work. The practical results obtained from the field test and feedback from users prove that the proposed throwing system is efficient for technical training and monitoring. This design provides a unique solution for the modeling and development of non-traditional, electro-mechanical sensing devices.

  13. Prospects for the development of advanced reactors. [Advanced Reactors

    Energy Technology Data Exchange (ETDEWEB)

    Semenov, B. A.; Kupitz, J.; Cleveland, J. [International Atomic Energy Agency Vienna (Austria). Dept. of Nuclear Energy and Safety

    1992-01-01

    Energy supply is an important prerequisite for further socio-economic development, especially in developing countries where the per capita energy use is only a very small fraction of that in industrialized countries. Nuclear energy is an essentially unlimited energy resource with the potential to provide this energy in the form of electricity, district heat and process heat under environmentally acceptable conditions. However, this potential will be realized only if nuclear power plants can meet the challenges of increasingly demanding safety requirements, economic competitiveness and public acceptance. Worldwide a tremendous amount of experience has been accumulated during development, licensing, construction and operation of nuclear power reactors. The experience forms a sound basis for further improvements. Nuclear programmes in many countries are addressing the development of advanced reactors which are intended to have better economics, higher reliability and improved safety in order to overcome the current concerns of nuclear power. Advanced reactors now being developed could help to meet the demand for new plants in developed and developing countries, not only for electricity generation, but also for district heating, desalination and for process heat. The IAEA, as the only global international governmental organization dealing with nuclear power, promotes international information exchange and international co-operation between all countries with their own advanced nuclear power programmes and offers assistance to countries with an interest in exploratory or research programmes.

  14. Advances by the Integral Fast Reactor Program

    International Nuclear Information System (INIS)

    Lineberry, M.J.; Pedersen, D.R.; Walters, L.C.; Cahalan, J.E.

    1991-01-01

    The advances by the Integral Fast Reactor Program at Argonne National Laboratory are the subject of this paper. The Integral Fast Reactor (IFR) is an advanced liquid-metal-cooled reactor concept being developed at Argonne National Laboratory. The advances stressed in the paper include fuel irradiation performance, improved passive safety, and the development of a prototype fuel cycle facility. 14 refs

  15. Safety and Efficacy of Advanced Bipolar Vessel Sealing in Vaginal Hysterectomy: 1000 Cases.

    Science.gov (United States)

    Clavé, Henri; Clavé, Arnaud

    2017-02-01

    To determine the safety and efficacy of advanced electrothermal bipolar vessel sealing (EBVS) during vaginal hysterectomy by evaluating urinary complications, overall complications, and reoperation rate. A retrospective cohort (Canadian Task Force classification III). High-volume gynecologic surgeon practice, private hospital. One thousand consecutive patients who have undergone vaginal hysterectomy for benign conditions carried out with EBVS between January 2002 and December 2012. Vaginal hysterectomy performed using an EBVS device. One thousand consecutive patients underwent vaginal hysterectomy with advanced EBVS between January 2002 and December 2012 with an average age of 51.4 ± 8.9 years (range, 31-88) and mean weight and body mass index of 57.4 ± 7.2 kg (range, 42-105) and 25.8 ± 4.2 kg/m 2 (range, 19.1-38.9), respectively. Eighty-five percent of patients (852/1000) were healthy without any severe systemic disease. A single experienced surgeon performed all vaginal hysterectomies with EBVS, specifically by not applying traction during thermofusion to avoid hemorrhage, amputating the cervix to transform the uterus to an apple shape to facilitate a vaginal approach and rotation of the uterus, and placing bi-clamp forceps on the edge of the uterus and not at a 45- or 90-degree angle. Wound closure was completed with a continuous suture. Eleven urinary complications (1.1%) were recorded (10 bladder mechanical injuries and 1 vesicovaginal fistula). This was not statistically different from the rate of .64% previously reported in the FINHYST study (p = .15). The overall rate of complications was 5.3%, and 20 patients (2.0%) required reoperation. The presence of uterine scar tissue (odds ratio, 5.5; 95% confidence interval, 1.6-19.2) and larger uterus size (odds ratio, 2.5; 95% confidence interval, 1.01-19.2) were associated with a higher risk of urinary complications. The use of EBVS during vaginal hysterectomy results in urinary and overall

  16. Safety culture: modern slogan or effective contribution to safety?

    International Nuclear Information System (INIS)

    Salm, M.

    1994-01-01

    Safety culture is defined and its impact on nuclear power plants is documented using the words of the INSAG of IAEA. Two examples from the field of aviation and space flight testify, that the upper management, by its sheer image, may considerably influence actions of the lower levels of the hierarchy. Management therefore can do a lot more for safety than is commonly assumed. Two examples, although separated by 57 years, show that the mentioned influence remains unchanged inspire of progress in management- and organisation-methods as well as in safety-engineering. Safety culture is an overriding element of safety, acting at all levels of a hierarchy. Its action is most important on those levels, for which precise reglementation is hardly possible. The chain of technical and organisational measures guarantees safety only under the condition, that it is embedded in 'safety culture'. Safety culture therefore merits our full attention. (author) 1 fig

  17. The basic discussion on nuclear power safety improvement based on nuclear equipment design

    International Nuclear Information System (INIS)

    Zhao Feiyun; Yao Yangui; Yu Hao; He Yinbiao; Gao Lei; Yao Weida

    2013-01-01

    The safety of strengthening nuclear power design was described based on nuclear equipment design after Fukushima nuclear accident. From these aspects, such as advanced standard system, advanced design method, suitable test means, consideration of beyond design basis event, and nuclear safety culture construction, the importance of nuclear safety improvement was emphatically presented. The enlightenment was given to nuclear power designer. (authors)

  18. Nuclear Safety

    Energy Technology Data Exchange (ETDEWEB)

    Silver, E G [ed.

    1989-01-01

    This document is a review journal that covers significant developments in the field of nuclear safety. Its scope includes the analysis and control of hazards associated with nuclear energy, operations involving fissionable materials, and the products of nuclear fission and their effects on the environment. Primary emphasis is on safety in reactor design, construction, and operation; however, the safety aspects of the entire fuel cycle, including fuel fabrication, spent-fuel processing, nuclear waste disposal, handling of radioisotopes, and environmental effects of these operations, are also treated.

  19. Risk-informed decision making a keystone in advanced safety assessment

    International Nuclear Information System (INIS)

    Reinhart, M.

    2007-01-01

    Probabilistic Safety Assessment (PSA) has provided extremely valuable complementary insight, perspective, comprehension, and balance to deterministic nuclear reactor safety assessment. This integrated approach of risk-informed management and decision making has been called Risk-Informed Decision Making (RIDM). RIDM provides enhanced safety, reliability, operational flexibility, reduced radiological exposure, and improved fiscal economy. Applications of RIDM continuously increase. Current applications are in the areas of design, construction, licensing, operations, and security. Operational phase safety applications include the following: technical specifications improvement, risk-monitors and configuration control, maintenance planning, outage planning and management, in-service inspection, inservice testing, graded quality assurance, reactor oversight and inspection, inspection finding significance determination, operational events assessment, and rulemaking. Interestingly there is a significant spectrum of approaches, methods, programs, controls, data bases, and standards. The quest of many is to assimilate the full compliment of PSA and RIDM information and to achieve a balanced international harmony. The goal is to focus the best of the best, so to speak, for the benefit of all. Accordingly, this presentation will address the principles, benefits, and applications of RIDM. It will also address some of the challenges and areas to improve. Finally it will highlight efforts by the IAEA and others to capture the international thinking, experience, successes, challenges, and lessons in RIDM. (authors)

  20. Radiation protection medicine - a special field of health care and industrial safety

    International Nuclear Information System (INIS)

    Arndt, D.

    1988-01-01

    The definition of the term radiation protection medicine is followed by a brief account of the pathophysiology of radiation effects. Developments in the special field of general and occupational health are also described together with relevant GDR regulations. Information is provided on what is done at present at various levels in the GDR, in the context of peaceful use of nuclear energy, to provide adequate services in radiation protection medicine for all radiation workers and the population, with reference to the scope of activities of the Institute of Medicine attached to the National Board for Atomic Safety and Radiation Protection, the network of works medical officers in charge of radiation protection and the system for clinical treatment of acute radiation damage. (author)