Blood transfusion safety; current status and challenges in Nigeria

Directory of Open Access Journals (Sweden)

John C Aneke

2017-01-01

Full Text Available The attainment of blood transfusion safety in Nigeria (and probably the rest of Sub-Saharan Africa remains an uphill task due to a number of factors, ranging from shortage of blood, poor implementation of blood transfusion guidelines, infrastructural deficits to high prevalence of transfusion-transmissible infections (TTIs, particularly hepatitis and human immune deficiency viruses. We reviewed available data on blood transfusion practices and safety in Nigeria using the PubMed, PubMed Central, Google Scholar, and African Index Medicus search engines, through a combination of word and phrases relevant to the subject. The World Health Organization has been in the forefront of efforts to establish safe, available, and affordable blood transfusion services in most parts of Africa through encouraging adequate blood donor recruitment, donor blood testing, and collection as well developing strategies for the rational use of blood. Even though modest improvement has been recorded, particularly with regards to donor blood screening for common TTIs, considerable efforts are needed in the form of robust public enlightenment campaigns (on blood donation and continuous system improvement to drive the current transfusion practices in the country toward safety and self-sustenance.

Status of SPACE Safety Analysis Code Development

International Nuclear Information System (INIS)

Lee, Dong Hyuk; Yang, Chang Keun; Kim, Se Yun; Ha, Sang Jun

2009-01-01

In 2006, the Korean the Korean nuclear industry started developing a thermal-hydraulic analysis code for safety analysis of PWR(Pressurized Water Reactor). The new code is named as SPACE(Safety and Performance Analysis Code for Nuclear Power Plant). The SPACE code can solve two-fluid, three-field governing equations in one dimensional or three dimensional geometry. The SPACE code has many component models required for modeling a PWR, such as reactor coolant pump, safety injection tank, etc. The programming language used in the new code is C++, for new generation of engineers who are more comfortable with C/C++ than old FORTRAN language. This paper describes general characteristics of SPACE code and current status of SPACE code development

Current status and future prospects for thermal-hydraulics and safety research

International Nuclear Information System (INIS)

Park, G.C.

2000-01-01

The present paper is to outline the current activities in Korea for the thermal-hydraulics and safety researches, and furthermore illuminate the future aspect of those field under the umbrella of worldwide nuclear prospect. In Korea, a long-term nuclear research plan has been established since 1992, which was recently funded with a fixed monetary rate of Korean won 1.20 per kWh of electricity produced with nuclear power. 11.5% of the fund is assigned for nuclear safety research in 6 areas. Under this program, 3 axes of research body (KAERI, KINS, University) has been operated with close cooperation. Their role, current activities and long-term plan of each body are introduced in the point of thermal-hydraulics' view. (author)

The current status of exposure-driven approaches for chemical safety assessment: A cross-sector perspective.

Science.gov (United States)

Sewell, Fiona; Aggarwal, Manoj; Bachler, Gerald; Broadmeadow, Alan; Gellatly, Nichola; Moore, Emma; Robinson, Sally; Rooseboom, Martijn; Stevens, Alexander; Terry, Claire; Burden, Natalie

2017-08-15

For the purposes of chemical safety assessment, the value of using non-animal (in silico and in vitro) approaches and generating mechanistic information on toxic effects is being increasingly recognised. For sectors where in vivo toxicity tests continue to be a regulatory requirement, there has been a parallel focus on how to refine studies (i.e. reduce suffering and improve animal welfare) and increase the value that in vivo data adds to the safety assessment process, as well as where to reduce animal numbers where possible. A key element necessary to ensure the transition towards successfully utilising both non-animal and refined safety testing is the better understanding of chemical exposure. This includes approaches such as measuring chemical concentrations within cell-based assays and during in vivo studies, understanding how predicted human exposures relate to levels tested, and using existing information on human exposures to aid in toxicity study design. Such approaches promise to increase the human relevance of safety assessment, and shift the focus from hazard-driven to risk-driven strategies similar to those used in the pharmaceutical sectors. Human exposure-based safety assessment offers scientific and 3Rs benefits across all sectors marketing chemical or medicinal products. The UK's National Centre for the Replacement, Refinement and Reduction of Animals in Research (NC3Rs) convened an expert working group of scientists across the agrochemical, industrial chemical and pharmaceutical industries plus a contract research organisation (CRO) to discuss the current status of the utilisation of exposure-driven approaches, and the challenges and potential next steps for wider uptake and acceptance. This paper summarises these discussions, highlights the challenges - particularly those identified by industry - and proposes initial steps for moving the field forward. Copyright © 2017 The Author(s). Published by Elsevier B.V. All rights reserved.

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

Energy Technology Data Exchange (ETDEWEB)

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

1993-08-01

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

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

International Nuclear Information System (INIS)

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

1993-08-01

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

Environment and safety research status report: 1993

International Nuclear Information System (INIS)

1993-03-01

The 1993 status report discusses ongoing and planned research activities in the GRI Environment and Safety Program. The objectives and goals, accomplishments, and strategy along with the basis for each project area are presented for the supply, end use, and gas operations subprograms. Within the context of these subprograms, contract status summaries under their conceptual titles are given for the following project areas: Gas Supply Environmental and Safety Research, Air Quality Research, End Use Equipment Safety Research, Gas Operations Safety Research, Liquefied Natural Gas, Safety Research, and Gas Operations Environmental Research

Preliminary Integrated Safety Analysis Status Report

International Nuclear Information System (INIS)

Gwyn, D.

2001-01-01

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

Current status of laparoscopic central pancreatectomy

Directory of Open Access Journals (Sweden)

CAO Yang

2017-04-01

Full Text Available Central pancreatectomy is an ideal surgical procedure for the treatment of benign or low-grade malignant tumors in the pancreatic neck or the proximal body of the pancreas, and it can preserve more normal pancreatic tissue in order to reduce the incidence of endocrine and exocrine insufficiency after surgery. Although some clinical studies have demonstrated the feasibility and safety of this procedure, laparoscopic central pancreatectomy was technically challenging with a few number of cases. This article reviews the current status of laparoscopic central pancreatectomy and introduces our clinical experience of laparoscopic central pancreatectomy and pancreaticojejunostomy.

Safety status of Russian research reactors

International Nuclear Information System (INIS)

Morozov, S.I.

2001-01-01

Gosatomnadzor of Russia is conducting the safety regulation and inspection activity related to nuclear and radiation safety at nuclear research facilities, including research reactors, critical assemblies and sub-critical assemblies. It implies implementing three major activities: 1) establishing the laws and safety standards in the field of research reactors nuclear and radiation safety; 2) research reactors licensing; and 3) inspections (or license conditions tracking and inspection). The database on nuclear research facilities has recently been updated based on the actual status of all facilities. It turned out that many facilities have been shutdown, whether temporary or permanently, waiting for the final decision on their decommissioning. Compared to previous years the situation has been inevitably changing. Now we have 99 nuclear research facilities in total under Gosatomnadzor of Russia supervision (compared to 113 in previous years). Their distribution by types and operating organizations is presented. The licensing and conduct of inspection processes are briefly outlined with emphasis being made on specific issues related to major incidents that happened in 2000, spent fuel management, occupational exposure, effluents and emissions, emergency preparedness and physical protection. Finally, a summary of problems at current Russian research facilities is outlined. (author)

CANDU Safety R&D Status, Challenges, and Prospects in Canada

Directory of Open Access Journals (Sweden)

W. Shen

2015-01-01

Full Text Available In Canada, safe operation of CANDU (CANada Deuterium Uranium; it is a registered trademark of Atomic Energy of Canada Limited reactors is supported by a full-scope program of nuclear safety research and development (R&D in key technical areas. Key nuclear R&D programs, facilities, and expertise are maintained in order to address the unique features of the CANDU as well as generic technology areas common to CANDU and LWR (light water reactor. This paper presents an overview of the CANDU safety R&D which includes background, drivers, current status, challenges, and future directions. This overview of the Canadian nuclear safety R&D programs includes those currently conducted by the COG (CANDU Owners Group, AECL (Atomic Energy of Canada Limited, Candu Energy Inc., and the CNSC (Canadian Nuclear Safety Commission and by universities via UNENE (University Network of Excellence in Nuclear Engineering sponsorship. In particular, the nuclear safety R&D program related to the emerging CANDU ageing issues is discussed. The paper concludes by identifying directions for the future nuclear safety R&D.

Status of safety issues at licensed power plants

International Nuclear Information System (INIS)

1991-06-01

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

Safety status system for operating room devices.

Science.gov (United States)

Guédon, Annetje C P; Wauben, Linda S G L; Overvelde, Marlies; Blok, Joleen H; van der Elst, Maarten; Dankelman, Jenny; van den Dobbelsteen, John J

2014-01-01

Since the increase of the number of technological aids in the operating room (OR), equipment-related incidents have come to be a common kind of adverse events. This underlines the importance of adequate equipment management to improve the safety in the OR. A system was developed to monitor the safety status (periodic maintenance and registered malfunctions) of OR devices and to facilitate the notification of malfunctions. The objective was to assess whether the system is suitable for use in an busy OR setting and to analyse its effect on the notification of malfunctions. The system checks automatically the safety status of OR devices through constant communication with the technical facility management system, informs the OR staff real-time and facilitates notification of malfunctions. The system was tested for a pilot period of six months in four ORs of a Dutch teaching hospital and 17 users were interviewed on the usability of the system. The users provided positive feedback on the usability. For 86.6% of total time, the localisation of OR devices was accurate. 62 malfunctions of OR devices were reported, an increase of 12 notifications compared to the previous year. The safety status system was suitable for an OR complex, both from a usability and technical point of view, and an increase of reported malfunctions was observed. The system eases monitoring the safety status of equipment and is a promising tool to improve the safety related to OR devices.

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)

Current status of studies on temperature fluctuation phenomena in LMFRs

International Nuclear Information System (INIS)

Ohshima, H.; Muramatsu, T.; Kobayashi, J.; Yamaguchi, A.

1994-01-01

This paper describes the current status of studies being performed in PNC on temperature fluctuation phenomena occurring in fast reactors. The studies concentrate on four problems: thermal stratification, thermal striping, core-plenum interaction and free surface sloshing. Both experimental and analytical approaches to reveal these phenomena and to establish design and safety evaluation methods are presented together with future works. (author)

Current knowledge of US metal and nonmetal miner health: Current and potential data sources for analysis of miner health status

Science.gov (United States)

Yeoman, K. M.; Halldin, C. N.; Wood, J.; Storey, E.; Johns, D.; Laney, A. S.

2016-01-01

ABSTRACT Little is known about the current health status of US metal and nonmetal (MNM) miners, in part because no health surveillance systems exist for this population. The National Institute for Occupational Safety and Health (NIOSH) is developing a program to characterize burden of disease among MNM miners. This report discusses current knowledge and potential data sources of MNM miner health. Recent national surveys were analyzed, and literature specific to MNM miner health status was reviewed. No robust estimates of disease prevalence were identified, and national surveys did not provide information specific to MNM miners. Because substantial gaps exist in the understanding of MNM miners' current health status, NIOSH plans to develop a health surveillance program for this population to guide intervention efforts to reduce occupational and personal risks for chronic illness. PMID:25658684

Summary of the Current Status of Lessons Learned From Fukushima Accident

International Nuclear Information System (INIS)

Pasamehmetoglu, Kemal

2013-01-01

This presentation introduced the current status of the lessons learned from the Fukushima accident, and in particular, the recommendations released by a NRC Near-term Task Force to enhance reactor safety in the 21. century. The near-term recommendations are focused on emergency power and emergency cooling availability during station blackout accidents

Status of safety issues at licensed power plants

International Nuclear Information System (INIS)

1991-05-01

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

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

International Nuclear Information System (INIS)

1991-12-01

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

Quantification of the safety status of PWR steam generators

International Nuclear Information System (INIS)

Bartonicek, J.; Jonas, O.; Schoeckle, F.

1996-01-01

The operational safety of components is affected during the period of operation (e.g., by loads and environmental effects). Additionally, changes in codes and standards can affect the safety margin of a component. In order to determine a quantitative status of the safety, the existing status of the component and the actual knowledge have to be regarded and evaluated. Differences (deficits) with respect to actual demands must be balanced by use of redundant measure to guarantee safety. The procedure is demonstrated using the steam generators of GKN 1 (German nuclear power plant--in operation since 1975) as an example. The existing status of the component regarding design and construction, material, load history (results of monitoring), the results of nondestructive testing and operational experience is determined and related to the actual regulatory and code compliance and to the state of the art in technics. Non-specified loads were measured in operation. Stress and fatigue analysis computations are performed on the base of realistic load patterns (results from monitoring). Thus the safety status can be quantified. Finally the GKN-concept of measures to guarantee the reliability and the safety of the component in future operation is discussed

Liquefied gaseous fuels safety and environmental control assessment program: third status report

Energy Technology Data Exchange (ETDEWEB)

1982-03-01

This Status Report contains contributions from all contractors currently participating in the DOE Liquefied Gaseous Fuels (LG) Safety and Environmental Control Assessment Program and is presented in two principal sections. Section I is an Executive Summary of work done by all program participants. Section II is a presentation of fourteen individual reports (A through N) on specific LGF Program activities. The emphasis of Section II is on research conducted by Lawrence Livermore National Laboratory (Reports A through M). Report N, an annotated bibliography of literature related to LNG safety and environmental control, was prepared by Pacific Northwest Laboratory (PNL) as part of its LGF Safety Studies Project. Other organizations who contributed to this Status Report are Aerojet Energy Conversion Company; Applied Technology Corporation; Arthur D. Little, Incorporated; C/sub v/ International, Incorporated; Institute of Gas Technology; and Massachusetts Institute of Technology. Separate abstracts have been prepared for Reports A through N for inclusion in the Energy Data Base.

Pediatric post-marketing safety systems in North America: assessment of the current status.

Science.gov (United States)

McMahon, Ann W; Wharton, Gerold T; Bonnel, Renan; DeCelle, Mary; Swank, Kimberley; Testoni, Daniela; Cope, Judith U; Smith, Phillip Brian; Wu, Eileen; Murphy, Mary Dianne

2015-08-01

It is critical to have pediatric post-marketing safety systems that contain enough clinical and epidemiological detail to draw regulatory, public health, and clinical conclusions. The pediatric safety surveillance workshop (PSSW), coordinated by the Food and Drug Administration (FDA), identified these pediatric systems as of 2010. This manuscript aims to update the information from the PSSW and look critically at the systems currently in use. We reviewed North American pediatric post-marketing safety systems such as databases, networks, and research consortiums found in peer-reviewed journals and other online sources. We detail clinical examples from three systems that FDA used to assess pediatric medical product safety. Of the 59 systems reviewed for pediatric content, only nine were pediatric-focused and met the inclusion criteria. Brief descriptions are provided for these nine. The strengths and weaknesses of three systems (two of the nine pediatric-focused and one including both children and adults) are illustrated with clinical examples. Systems reviewed in this manuscript have strengths such as clinical detail, a large enough sample size to capture rare adverse events, and/or a patient denominator internal to the database. Few systems include all of these attributes. Pediatric drug safety would be better informed by utilizing multiple systems to take advantage of their individual characteristics. Copyright © 2015 John Wiley & Sons, Ltd.

Status of the IAEA safety standards programme

International Nuclear Information System (INIS)

2002-01-01

This presentation describes the status of the IAEA safety standards program to May 2002. The safety standards program overcome whole main nuclear implementations as General safety, Nuclear safety, Radiation safety, Radioactive waste safety, and Transport safety. Throughout this report the first column provides the list of published IAEA Safety Standards. The second gives the working identification number (DS) of standards being developed or revised. The bold type indicates standard issued under the authority the Board of Governors, others are issued under authority of the Director General. The last column provides the list of Committees, the first Committee listed has the lead in the preparation and review of the particular standard

Nuclear power for sustainable development. Current status and future prospects

International Nuclear Information System (INIS)

Adamantiades, A.; Kessides, I.

2009-01-01

Interest in nuclear power has been revived as a result of volatile fossil fuel prices, concerns about the security of energy supplies, and global climate change. This paper describes the current status and future plans for expansion of nuclear power, the advances in nuclear reactor technology, and their impacts on the associated risks and performance of nuclear power. Advanced nuclear reactors have been designed to be simpler and safer, and to have lower costs than currently operating reactors. By addressing many of the public health and safety risks that plagued the industry since the accidents at Three Mile Island and Chernobyl, these reactors may help break the current deadlock over nuclear power. In that case, nuclear power could make a significant contribution towards reducing greenhouse gas emissions. However, significant issues persist, fueling reservations among the public and many decision makers. Nuclear safety, disposal of radioactive wastes, and proliferation of nuclear explosives need to be addressed in an effective and credible way if the necessary public support is to be obtained. (author)

Current activities on safety improvement at Ukrainian NPPs

International Nuclear Information System (INIS)

Stovbun, V.V.

2000-01-01

This report describes general development status of the national programs on safety improvement of the Ukrainian NPPs, basic approaches adopted for planning and implementation of safety improvement works, and state of implementation of principal technical activities aimed at safety improvement of Ukrainian NPPs. (author)

Review of current status of LWR safety research in Japan

International Nuclear Information System (INIS)

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

1977-01-01

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

Current safety issues of CANDU licensing

International Nuclear Information System (INIS)

Lee, Y.; Natalizio, A.

1994-01-01

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

Current R and D status on material motion and interactions relevant to core disruptive accidents

Energy Technology Data Exchange (ETDEWEB)

Kondo, Satoru [Safety Engineering Division, O-arai Engineering Center, Power Reactor and Nuclear Fuel Development Corporation, O-arai, Ibaraki (Japan)

1994-07-01

In this paper, the current status of research and development activities are briefly reviewed on evaluation of material-coolant interactions and material movement and relocation relevant to the safety of liquid-metal fast reactors. Since the status of European activities are well summarized in other papers submitted to the present meeting, the activities in Japan and the United States are highlighted in this paper. The review includes: out-of-pile experiments, in-pile experiments and relevant computer code development. It is emphasized that improved understanding on material motion has contributed to establishing more realistic and rational safety evaluation methods, where various mitigation mechanisms are inherently effective. (author)

Current status of international cooperation on nuclear safety research

International Nuclear Information System (INIS)

Katsuragi, Satoru

1984-01-01

JAERI (Japan Atomic Energy Research Institute), as a representative organization in Japan, has been participating in many international cooperations on nuclear safety research. This report reviews the recent achievement and evolution of the international cooperative safety studies. Twelve projects that are based on the agreements between JAERI and foreign organizations are reviewed. As the fuel irradiation studies, the recent achievement of the OECD Halden Reactor Project and the agreement between Pacific Northwest Laboratories, Battelle Memorial Institute, and JAERI are explained. As for the study of reactivity accident, the cooperation of the NSRR (Nuclear Safety Research Reactor) project in Japan with PBF, PNS and PHEBUS projects in the U.S., West Germany and France, respectively, are now in progress. The fuel performance in abnormal transient and the experiment and analysis of severe fuel damage are the new areas of international interest. The OECD/LOFT project and ROSA-4 projects are also explained in connection with the FP source term problem and the analysis codes such as RELAP-5 and TRAC. As the safety studies associated with the downstream of the nuclear fuel cycle, the BEFAST project of IAEA and the ISIRS project of OECD/NEA are shortly reviewed. (Aoki, K.)

LMFBR safety. 6. Review of current issues and bibliography of literature (1977)

International Nuclear Information System (INIS)

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

1978-01-01

This report discusses the current status of liquid-metal fast breeder reactor (LMFBR) development. Selected bibliographic information on LMFBRs relative to the development and safety of the breeder reactor is presented for the year 1977. The bibliography consists of approximately 198 abstracts covering research and development, operating experience, and design practices. Keyword, author, and permuted-title indexes are included for completeness

Nuclear safety in Slovak Republic. Status of safety improvements

International Nuclear Information System (INIS)

Toth, A.

1999-01-01

Status of the safety improvements at Bohunice V-1 units concerning WWER-440/V-230 design upgrading were as follows: supplementing of steam generator super-emergency feed water system; higher capacity of emergency core cooling system; supplementing of automatic links between primary and secondary circuit systems; higher level of secondary system automation. The goal of the modernization program for Bohunice V-1 units WWER-440/V-230 was to increase nuclear safety to the level of the proposals and IAEA recommendations and to reach probability goals of the reactor concerning active zone damage, leak of radioactive materials, failures of safety systems and damage shields. Upgrading program for Mochovce NPP - WWER-440/V-213 is concerned with improving the integrity of the reactor pressure vessel, steam generators 'leak before break' methods applied for the NPP, instrumentation and control of safety systems, diagnostic systems, replacement of in-core monitoring system, emergency analyses, pressurizers safety relief valves, hydrogen removal system, seismic evaluations, non-destructive testing, fire protection. Implementation of quality assurance has a special role in improvement of operational safety activities as well as safety management and safety culture, radiation protection, decommissioning and waste management and training. The Year 2000 problem is mentioned as well

Safety evaluation status report for the prototype license application safety analysis report

International Nuclear Information System (INIS)

1989-07-01

The US Nuclear Regulatory Commission (NRC) staff and consultants reviewed a Prototype License Application Safety Analysis Report (PLASAR) submitted by the US Department of Energy (DOE) for the earth-mounded concrete bunker (EMCB) alternative method of low-level radioactive waste disposal. The NRC reviewers relied extensively on the Standard Review Plan (SRP), Rev.1 (NUREG-1200), to evaluate the acceptability of the information provided in the EMCB PLASAR. The NRC staff selected certain review areas in the PLASAR for development of safety evaluation report input to provide examples of safety assessments that are necessary as part of a licensing review. Because of the fictitious nature of the assumed disposal site, and the decision to limit the review to essentially first-round review status, the NRC staff report is labeled a ''Safety Evaluation Status Report'' (SESR). Appendix A comprises the NRC review comments and questions on the information that DOE submitted in the PLASAR. The NRC concentrated its review on the design and operations-related portions of the EMCB PLASAR

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

International Nuclear Information System (INIS)

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

1977-01-01

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

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

Energy Technology Data Exchange (ETDEWEB)

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

1977-06-08

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

Diagnosis function of safety status in the safety parameter display system (SPDS)

International Nuclear Information System (INIS)

Zhang Yuanfang

1993-04-01

An automatic diagnosis function of safety status for nuclear power plant adopted in the SPDS is introduced. To guarantee diagnosis diversification, two diagnosis criteria of a design basis accident monitoring and a critical safety function monitoring used in plant emergency operation are provided. As an extensive function, a parameter deviation monitoring used in plant normal operation is also provided

Status of safety issues at licensed power plants

International Nuclear Information System (INIS)

1991-03-01

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

Status of High Flux Isotope Reactor (HFIR) post-restart safety analysis and documentation upgrades

International Nuclear Information System (INIS)

Cook, D.H.; Radcliff, T.D.; Rothrock, R.B.; Schreiber, R.E.

1990-01-01

The High Flux Isotope Reactor (HFIR), an experimental reactor located at the Oak Ridge National Laboratory (ORNL) and operated for the US Department of Energy by Martin Marietta Energy Systems, was shut down in November, 1986 after the discovery of unexpected neutron embrittlement of the reactor vessel. The reactor was restarted in April, 1989, following an extensive review by DOE and ORNL of the HFIR design, safety, operation, maintenance and management, and the implementation of several upgrades to HFIR safety-related hardware, analyses, documents and procedures. This included establishing new operating conditions to provide added margin against pressure vessel failure, as well as the addition, or upgrading, of specific safety-related hardware. This paper summarizes the status of some of the follow-on (post-restart) activities which are currently in progress, and which will result in a comprehensive set of safety analyses and documentation for the HFIR, comparable with current practice in commercial nuclear power plants. 8 refs

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

International Nuclear Information System (INIS)

1993-12-01

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

Status report of the US Department of Energy's International Nuclear Safety Program

International Nuclear Information System (INIS)

1994-12-01

The US Department of Energy (DOE) implements the US Government's International Nuclear Safety Program to improve the level of safety at Soviet-designed nuclear power plants in Central and Eastern Europe, Russia, and Unkraine. The program is conducted consistent with guidance and policies established by the US Department of State (DOS) and the Agency for International Development and in close collaboration with the Nuclear Regulatory Commission. Some of the program elements were initiated in 1990 under a bilateral agreement with the former Soviet Union; however, most activities began after the Lisbon Nuclear Safety Initiative was announced by the DOS in 1992. Within DOE, the program is managed by the International Division of the Office of Nuclear Energy. The overall objective of the International Nuclear Safety Program is to make comprehensive improvements in the physical conditions of the power plants, plant operations, infrastructures, and safety cultures of countries operating Soviet-designed reactors. This status report summarizes the Internatioal Nuclear Safety Program's activities that have been completed as of September 1994 and discusses those activities currently in progress

Current collectors for improved safety

Science.gov (United States)

Abdelmalak, Michael Naguib; Allu, Srikanth; Dudney, Nancy J.; Li, Jianlin; Simunovic, Srdjan; Wang, Hsin

2017-12-19

A battery electrode assembly includes a current collector with conduction barrier regions having a conductive state in which electrical conductivity through the conduction barrier region is permitted, and a safety state in which electrical conductivity through the conduction barrier regions is reduced. The conduction barrier regions change from the conductive state to the safety state when the current collector receives a short-threatening event. An electrode material can be connected to the current collector. The conduction barrier regions can define electrical isolation subregions. A battery is also disclosed, and methods for making the electrode assembly, methods for making a battery, and methods for operating a battery.

Formulation of nuclear safety under various induced events. Part 1. Current status and challenges for risk-informed activities in nuclear safety

International Nuclear Information System (INIS)

Itoi, Tatsuya; Hayashi, Kentaro; Yamato, Masaaki

2016-01-01

The Nuclear Safety Subcommittee published in March 2013 a report on 'Seminar on the Fukushima Daiichi Nuclear Power Station accident' (hereinafter referred to as Seminar Report), and has thereafter continued discussions on the challenges that were pointed out in Seminar Report as the target of discussions. This commentary series summarizes the current situation and challenges for the ideal way of nuclear safety against a variety of causal events as one of the above challenges. This paper, as Part 1 of the above theme, firstly summarizes the current state of the challenges of regulatory bodies and business operators who are engaging risk information utilization. It secondly discusses the future risk information utilization of regulations and business operators, realization of integrated decision-making process, timeliness and promptness required in decision-making, and future efforts including incentives. (A.O.)

Probabilistic Safety Goals. Phase 1 Status and Experiences in Sweden and Finland

International Nuclear Information System (INIS)

Holmberg, Jan-Erik; Knochenhauer, Michael

2007-02-01

The outcome of a probabilistic safety assessment (PSA) for a nuclear power plant is a combination of qualitative and quantitative results. Quantitative results are typically presented as the Core Damage Frequency (CDF) and as the frequency of an unacceptable radioactive release. In order to judge the acceptability of PSA results, criteria for the interpretation of results and the assessment of their acceptability need to be defined. Ultimately, the goals are intended to define an acceptable level of risk from the operation of a nuclear facility. However, safety goals usually have a dual function, i.e., they define an acceptable safety level, but they also have a wider and more general use as decision criteria. The exact levels of the safety goals differ between organisations and between different countries. There are also differences in the definition of the safety goal, and in the formal status of the goals, i.e., whether they are mandatory or not. In this first phase of the project, the aim has been on providing a clear description of the issue of probabilistic safety goals for nuclear power plants, to define and describe important concepts related to the definition and application of safety goals, and to describe experiences in Finland and Sweden. Based on a series of interviews and on literature reviews as well as on a limited international over-view, the project has described the history and current status of safety goals in Sweden and Finland, and elaborated on a number of issues, including the following: The status of the safety goals in view of the fact that they have been exceeded for much of the time they have been in use, as well as the possible implications of these exceedances. Safety goals as informal or mandatory limits. Strategies for handling violations of safety goals, including various graded approaches, such as ALARP (As Low As Reasonably Practicable). Relation between safety goals defined on different levels, e.g., for core damage and for

Probabilistic safety goals. Phase 1 - Status and experiences in Sweden and Finland

International Nuclear Information System (INIS)

Holmberg, J.E.; Knochenhauer, M.

2007-03-01

The outcome of a probabilistic safety assessment (PSA) for a nuclear power plant is a combination of qualitative and quantitative results. Quantitative results are typically presented as the Core Damage Frequency (CDF) and as the frequency of an unacceptable radioactive release. In order to judge the acceptability of PSA results, criteria for the interpretation of results and the assessment of their acceptability need to be defined. Ultimately, the goals are intended to define an acceptable level of risk from the operation of a nuclear facility. However, safety goals usually have a dual function, i.e., they define an acceptable safety level, but they also have a wider and more general use as decision criteria. The exact levels of the safety goals differ between organisations and between different countries. There are also differences in the definition of the safety goal, and in the formal status of the goals, i.e., whether they are mandatory or not. In this first phase of the project, the aim has been on providing a clear description of the issue of probabilistic safety goals for nuclear power plants, to define and describe important concepts related to the definition and application of safety goals, and to describe experiences in Finland and Sweden. Based on a series of interviews and on literature reviews as well as on a limited international over-view, the project has described the history and current status of safety goals in Sweden and Finland, and elaborated on a number of issues, including the following: 1) The status of the safety goals in view of the fact that they have been exceeded for much of the time they have been in use, as well as the possible implications of these exceedances. 2) Safety goals as informal or mandatory limits. 3) Strategies for handling violations of safety goals, including various graded approaches, such as ALARP (As Low As Reasonably Practicable). 4) Relation between safety goals defined on different levels, e.g., for core damage

Probabilistic Safety Goals. Phase 1 Status and Experiences in Sweden and Finland

Energy Technology Data Exchange (ETDEWEB)

Holmberg, Jan-Erik (VTT, FI-02044 VTT (Finland)); Knochenhauer, Michael (Relcon Scandpower AB, SE-172 25 Sundbyberg (Sweden))

2007-02-15

The outcome of a probabilistic safety assessment (PSA) for a nuclear power plant is a combination of qualitative and quantitative results. Quantitative results are typically presented as the Core Damage Frequency (CDF) and as the frequency of an unacceptable radioactive release. In order to judge the acceptability of PSA results, criteria for the interpretation of results and the assessment of their acceptability need to be defined. Ultimately, the goals are intended to define an acceptable level of risk from the operation of a nuclear facility. However, safety goals usually have a dual function, i.e., they define an acceptable safety level, but they also have a wider and more general use as decision criteria. The exact levels of the safety goals differ between organisations and between different countries. There are also differences in the definition of the safety goal, and in the formal status of the goals, i.e., whether they are mandatory or not. In this first phase of the project, the aim has been on providing a clear description of the issue of probabilistic safety goals for nuclear power plants, to define and describe important concepts related to the definition and application of safety goals, and to describe experiences in Finland and Sweden. Based on a series of interviews and on literature reviews as well as on a limited international over-view, the project has described the history and current status of safety goals in Sweden and Finland, and elaborated on a number of issues, including the following: The status of the safety goals in view of the fact that they have been exceeded for much of the time they have been in use, as well as the possible implications of these exceedances. Safety goals as informal or mandatory limits. Strategies for handling violations of safety goals, including various graded approaches, such as ALARP (As Low As Reasonably Practicable). Relation between safety goals defined on different levels, e.g., for core damage and for

Probabilistic safety goals. Phase 1 - Status and experiences in Sweden and Finland

Energy Technology Data Exchange (ETDEWEB)

Holmberg, J.E. [VTT (Finland); Knochenhauer, M. [Relcon Scandpower AB (Sweden)

2007-03-15

The outcome of a probabilistic safety assessment (PSA) for a nuclear power plant is a combination of qualitative and quantitative results. Quantitative results are typically presented as the Core Damage Frequency (CDF) and as the frequency of an unacceptable radioactive release. In order to judge the acceptability of PSA results, criteria for the interpretation of results and the assessment of their acceptability need to be defined. Ultimately, the goals are intended to define an acceptable level of risk from the operation of a nuclear facility. However, safety goals usually have a dual function, i.e., they define an acceptable safety level, but they also have a wider and more general use as decision criteria. The exact levels of the safety goals differ between organisations and between different countries. There are also differences in the definition of the safety goal, and in the formal status of the goals, i.e., whether they are mandatory or not. In this first phase of the project, the aim has been on providing a clear description of the issue of probabilistic safety goals for nuclear power plants, to define and describe important concepts related to the definition and application of safety goals, and to describe experiences in Finland and Sweden. Based on a series of interviews and on literature reviews as well as on a limited international over-view, the project has described the history and current status of safety goals in Sweden and Finland, and elaborated on a number of issues, including the following: 1) The status of the safety goals in view of the fact that they have been exceeded for much of the time they have been in use, as well as the possible implications of these exceedances. 2) Safety goals as informal or mandatory limits. 3) Strategies for handling violations of safety goals, including various graded approaches, such as ALARP (As Low As Reasonably Practicable). 4) Relation between safety goals defined on different levels, e.g., for core damage

Operational safety analysis status of Novi Han repository

International Nuclear Information System (INIS)

Boiadjiev, A.

2000-01-01

This article presents the status of the safety studies and activities related to Novi Han repository. The case of this facility is such that no clear boundary exists between post-closure safety assessment and operational safety assessment. The major findings of these activities are given. The Safety Analysis Report (SAR) for Novi Han repository is developed by Risk Engineering Ltd. under a contract with the Committee on the Use of Atomic Energy for Peaceful Purposes. The general structure and main conclusions and recommendations of the SAR are presented. (author)

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

International Nuclear Information System (INIS)

1994-12-01

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

Status of Ignalina's safety analysis reports

International Nuclear Information System (INIS)

Uspuras, E.

1999-01-01

Ignalina NPP is unique among RBMK type reactors in the scope and comprehensiveness of international studies which have been performed to verify its design parameters and analyze risk levels. International assistance took several forms, a very valuable mod of assistance utilized the knowledge of international experts in extensive international studies whose purpose was: collection, systematization and verification of plant design data; analysis of risk levels; recommendations leading to improvements in the safety lave; transfer of state of the art analytical methodology to Lithuanian specialists. The major large scale international studies include: probabilistic risk analysis; extensive international study meant to provide comprehensive overview of plant status with special emphasis on safety aspects; an extensive review of the Safety Analysis Report by an independent group of international experts. In spite of the safety improvements and analyses which have been performed at the Ignalina NPP, much remains to be done in the nearest future

Probabilistic safety analyses. Status and further development of methods and models, applications

International Nuclear Information System (INIS)

Berg, H.P.; Schott, H.

1992-12-01

The report describes the topics of the deterministic and probabilistic approach. The PSA is used in order to investigate event sequences beyond design limits; in particular the expected frequency of core melting is important. The basis of PSA is described including its limits. Moreover, the current state of the art of science and technology in the field of PSA including the so-called 'living PSA' are explained. Some measures which result in order to improve the safety of a nuclear power plant from the German Risk-Study are shown. An overview is given on the status of PSA in periodic safety reviews in German nuclear power plants. Moreover, the main topics of running investigations are presented. (orig.) [de

Seismic proving test of ultimate piping strength (current status of preliminary tests)

International Nuclear Information System (INIS)

Suzuki, K.; Namita, Y.; Abe, H.; Ichihashi, I.; Suzuki, K.; Ishiwata, M.; Fujiwaka, T.; Yokota, H.

2001-01-01

In 1998 Fiscal Year, the 6 year program of piping tests was initiated with the following objectives: i) to clarify the elasto-plastic response and ultimate strength of nuclear piping, ii) to ascertain the seismic safety margin of the current seismic design code for piping, and iii) to assess new allowable stress rules. In order to resolve extensive technical issues before proceeding on to the seismic proving test of a large-scale piping system, a series of preliminary tests of materials, piping components and simplified piping systems is intended. In this paper, the current status of the material tests and the piping component tests is reported. (author)

China's current status and long-term outlook of nuclear power and radioactive waste disposal management

International Nuclear Information System (INIS)

Li, Zhidong

2015-01-01

This study identified the current status and long-term outlook of China's nuclear power development and radioactive waste disposal management after the 3.11 FUKUSHIMA accidents. China strengthened the actions for achieving nuclear power safety and cost efficiency as well as safety management of radioactive waste. It is a hard work to expand the capacity to 58 GW, the governmental target in 2020. The long-term development will strongly depend on the progress in safety management of nuclear power and radioactive waste and economic competitiveness. (author)

EVALUATION OF BRACHYTHERAPY FACILITY SHIELDING STATUS IN KOREA OBTAINED FROM RADIATION SAFETY REPORTS

Directory of Open Access Journals (Sweden)

MI HYUN KEUM

2013-10-01

Full Text Available Thirty-eight radiation safety reports for brachytherapy equipment were evaluated to determine the current status of brachytherapy units in Korea and to assess how radiation oncology departments in Korea complete radiation safety reports. The following data was collected: radiation safety report publication year, brachytherapy unit manufacturer, type and activity of the source that was used, affiliation of the drafter, exposure rate constant, the treatment time used to calculate workload and the HVL values used to calculate shielding design goal values. A significant number of the reports (47.4% included the personal information of the drafter. The treatment time estimates varied widely from 12 to 2,400 min/week. There was acceptable variation in the exposure rate constant values (ranging between 0.469 and 0.592 (R-m2/Ci·hr, as well as in the HVLs of concrete, steel and lead for Iridium-192 sources that were used to calculate shielding design goal values. There is a need for standard guidelines for completing radiation safety reports that realistically reflect the current clinical situation of radiation oncology departments in Korea. The present study may be useful for formulating these guidelines.

Functional Safety Status in Isfahan Private Hospitals in Response to Disasters in 2015

Directory of Open Access Journals (Sweden)

Nahid Tavakoli

2017-04-01

Conclusion: The present study showed that the current status of functional safety in Isfahan private hospitals is not completely satisfactory and the provincial health managers, especially Isfahan University of Medical Sciences, are expected to regularly monitor planning and decision-making about the risks threatening these hospitals, especially in the areas of contingency plans of medical operations and access to medicines as well as equipment and supplies needed in an emergency situation.

International conference on the strengthening of nuclear safety in Eastern Europe. Keynote papers. Regulatory aspects of NPP safety, status of safety improvements, status of safety analysis report

International Nuclear Information System (INIS)

1999-06-01

The Objective of the Conference was to assess the past decade of nuclear safety efforts in countries operating WWER and RBMK nuclear reactors and to address remaining safety issues which require further work. A particular focus of the Conference was on international co-operation and assistance and where such efforts should be focused in the future. All Eastern European countries that operate RBMK or WWER reactors participated in the Conference, and presented papers on three key areas of nuclear safety: Regulatory Aspects of Nuclear Power Plant Safety; Status of Safety Improvements; and Status of Safety Analysis Reports. In addition, representatives from 18 additional countries that provide financial and/or technical assistance and co-operation in the area of WWER and RBMK safety offered the most extensive commentary. Key international (IAEA, World Association of Nuclear Operators, the Nuclear Energy Agency, the G-24 NUSAC, the European Commission, and the EBRD) organizations that provide nuclear safety assistance for WWER and RBMK reactors also made presentations. There is no question that considerable progress on nuclear safety has been made in Eastern Europe. Special mention should be made of successful efforts to strengthen the independence and technical competence of the nuclear regulatory authorities. Efforts should now concentrate on improving the depth and scope of the technical abilities of the regulatory authorities. More attention by governments is needed to ensure that the regulatory authorities have the financial resources and enforcement authority to fully execute their missions. In respect to the operators of the nuclear power plants, they have demonstrated clear progress in operational safety improvements. Significant additional efforts are required to maintain and enhance an effective safety culture. Design safety improvement programmes are in place in all countries. Implementation of these programmes has varied and is particularly affected by

Industrial safety, origins and current situation

International Nuclear Information System (INIS)

Gil Sarralbo, J. F.

2011-01-01

Basic Introduction to Industrial Safety, purpose and expected outcome. Concepts and fundamental principles that support it. Brief overview of its evolution over the course of history. The current legal basis in Spain for Industrial Safety. (Author) 4 refs.

Current status and prospects of HIV treatment.

Science.gov (United States)

Cihlar, Tomas; Fordyce, Marshall

2016-06-01

Current antiviral treatments can reduce HIV-associated morbidity, prolong survival, and prevent HIV transmission. Combination antiretroviral therapy (cART) containing preferably three active drugs from two or more classes is required for durable virologic suppression. Regimen selection is based on virologic efficacy, potential for adverse effects, pill burden and dosing frequency, drug-drug interaction potential, resistance test results, comorbid conditions, social status, and cost. With prolonged virologic suppression, improved clinical outcomes, and longer survival, patients will be exposed to antiretroviral agents for decades. Therefore, maximizing the safety and tolerability of cART is a high priority. Emergence of resistance and/or lack of tolerability in individual patients require availability of a range of treatment options. Development of new drugs is focused on improving safety (e.g. tenofovir alafenamide) and/or resistance profile (e.g. doravirine) within the existing drug classes, combination therapies with improved adherence (e.g. single-tablet regimens), novel mechanisms of action (e.g. attachment inhibitors, maturation inhibitors, broadly neutralizing antibodies), and treatment simplification with infrequent dosing (e.g. long-acting injectables). In parallel with cART innovations, research and development efforts focused on agents that target persistent HIV reservoirs may lead to prolonged drug-free remission and HIV cure. Copyright © 2016 Gilead Sciences, Inc. Published by Elsevier B.V. All rights reserved.

Investigation of status of safety management in radiation handle works

International Nuclear Information System (INIS)

Amauchi, Hiroshi; Nishimura, Kenji; Izumi, Kokichi

2007-01-01

This report describes the investigation in the title concerning the system for safety management and for accident prevention, which was done by a questionnaire in a period of 1.5 months in 2005. The questionnaire including 55 questions for safety management system, 33 for instruments and safety utilization of radiation and 57 for present status of safety management in high-risk radiation works, was performed in 780 hospitals, of which 313 answered. The first 55 questions concerned with the facility, patient identification, information exchange, management of private information, safety management activities, measures to prevent accident, manual preparation, personnel education and safety awareness; the second, with management of instruments, package insert, system for reporting the safety information, management of implants, re-imaging and radiation protection; and the third, with the systems for patients' emergency, in departments of CT/MR, of IVR, of nuclear diagnosis and of radiation therapy. Based on the results obtained, many problems, tasks and advices are presented to various items and further continuation of efforts to improve the present status is mentioned to be necessary. Details are given in the homepage of the Japanese Society of Radiological Technology. (T.I.)

International conference on the strengthening of nuclear safety in Eastern Europe. Keynote papers. Regulatory aspects of NPP safety, status of safety improvements, status of safety analysis report

Energy Technology Data Exchange (ETDEWEB)

NONE

1999-06-01

The Objective of the Conference was to assess the past decade of nuclear safety efforts in countries operating WWER and RBMK nuclear reactors and to address remaining safety issues which require further work. A particular focus of the Conference was on international co-operation and assistance and where such efforts should be focused in the future. All Eastern European countries that operate RBMK or WWER reactors participated in the Conference, and presented papers on three key areas of nuclear safety: Regulatory Aspects of Nuclear Power Plant Safety; Status of Safety Improvements; and Status of Safety Analysis Reports. In addition, representatives from 18 additional countries that provide financial and/or technical assistance and co-operation in the area of WWER and RBMK safety offered the most extensive commentary. Key international (IAEA, World Association of Nuclear Operators, the Nuclear Energy Agency, the G-24 NUSAC, the European Commission, and the EBRD) organizations that provide nuclear safety assistance for WWER and RBMK reactors also made presentations. There is no question that considerable progress on nuclear safety has been made in Eastern Europe. Special mention should be made of successful efforts to strengthen the independence and technical competence of the nuclear regulatory authorities. Efforts should now concentrate on improving the depth and scope of the technical abilities of the regulatory authorities. More attention by governments is needed to ensure that the regulatory authorities have the financial resources and enforcement authority to fully execute their missions. In respect to the operators of the nuclear power plants, they have demonstrated clear progress in operational safety improvements. Significant additional efforts are required to maintain and enhance an effective safety culture. Design safety improvement programmes are in place in all countries. Implementation of these programmes has varied and is particularly affected by

Association between neighborhood safety and overweight status among urban adolescents

Directory of Open Access Journals (Sweden)

Johnson Renee M

2009-08-01

Full Text Available Abstract Background Neighborhood safety may be an important social environmental determinant of overweight. We examined the relationship between perceived neighborhood safety and overweight status, and assessed the validity of reported neighborhood safety among a representative community sample of urban adolescents (who were racially and ethnically diverse. Methods Data come from the 2006 Boston Youth Survey, a cross-sectional study in which public high school students in Boston, MA completed a pencil-and-paper survey. The study used a two-stage, stratified sampling design whereby schools and then 9th–12th grade classrooms within schools were selected (the analytic sample included 1,140 students. Students reported their perceptions of neighborhood safety and several associated dimensions. With self-reported height and weight data, we computed body mass index (BMI, kg/m2 for the adolescents based on CDC growth charts. Chi-square statistics and corresponding p-values were computed to compare perceived neighborhood safety by the several associated dimensions. Prevalence ratios (PRs and 95% confidence intervals (CI were calculated to examine the association between perceived neighborhood safety and the prevalence of overweight status controlling for relevant covariates and school site. Results More than one-third (35.6% of students said they always felt safe in their neighborhood, 43.9% said they sometimes felt safe, 11.6% rarely felt safe, and 8.9% never felt safe. Those students who reported that they rarely or never feel safe in their neighborhoods were more likely than those who said they always or sometimes feel safe to believe that gang violence was a serious problem in their neighborhood or school (68.0% vs. 44.1%, p p = 0.025. In the fully adjusted model (including grade and school stratified by race/ethnicity, we found a statistically significant association between feeling unsafe in one's own neighborhood and overweight status among

Status of safety at Areva group facilities. 2007 annual report

International Nuclear Information System (INIS)

2007-01-01

This report describes the status of nuclear safety and radiation protection in the facilities of the AREVA group and gives information on radiation protection in the service operations, as observed through the inspection programs and analyses carried out by the General Inspectorate in 2007. Having been submitted to the group's Supervisory Board, this report is sent to the bodies representing the personnel. Content: 1 - A look back at 2007 by the AREVA General Inspector: Visible progress in 2007, Implementation of the Nuclear Safety Charter, Notable events; 2 - Status of nuclear safety and radiation protection in the nuclear facilities and service operations: Personnel radiation protection, Event tracking, Service operations, Criticality control, Radioactive waste and effluent management; 3 - Performance improvement actions; 4 - Description of the General Inspectorate; 5 - Glossary

Cancer pain management-current status

Directory of Open Access Journals (Sweden)

Deepak Thapa

2011-01-01

Full Text Available Cancer pain is still one of the most feared entities in cancer and about 75% of these patients require treatment with opioids for severe pain. The cancer pain relief is difficult to manage in patients with episodic or incidental pain, neuropathic pain, substance abuse and with impaired cognitive or communication skills. This non-systematic review article aims to discuss reasons for under treatment, tools of pain assessment, cancer pain and anxiety and possibly carve new approaches for cancer pain management in future. The current status of World Health Organization analgesic ladder has also been reviewed. A thorough literature search was carried out from 1998 to 2010 for current status in cancer pain management in MEDLINE, WHO guidelines and published literature and relevant articles have been included.

Predictive Toxicology: Current Status and Future Outlook (EBI ...

Science.gov (United States)

Slide presentation at the EBI-EMBL Industry Programme Workshop on Predictive Toxicology and the currently status of Computational Toxicology activities at the US EPA. Slide presentation at the EBI-EMBL Industry Programme Workshop on Predictive Toxicology and the currently status of Computational Toxicology activities at the US EPA.

IAEA occupational radiation protection programme: current status

International Nuclear Information System (INIS)

Deboodt, P.; Mrabit, K.

2006-01-01

As stated in Art.III.A.6 of its Statute, the International Atomic Energy Agency (commonly referred to as the Agency) is authorized to establish or adopt, in consultation and, where appropriate, in collaboration with the competent organs of the United Nations and with the specialized agencies concerned, standards of safety for protection of health and minimization of danger to life and property (including such standards for labour conditions), and to provide for the application of these standards to its own operation as well as to the operations making use of materials, services, equipment, facilities, and information made available by the Agency or at its request or under its control or supervision. The Agency s Occupational Radiation Protection Programme aims at harmonizing infrastructures for the control of radiation exposure of workers and for optimizing radiation protection in situation s of exposures due to external radiation and intakes of radionuclides from both artificial and natural sources of radiation. Under its regular and technical cooperation programmes, the Agency has been assigning high priority to both the establishment of safety standards for labour conditions and for the application of these standards through, Interalia, direct assistance under its technical cooperation (TC) programme, the rendering of services, the promotion of education and training, the fostering of information exchange and the coordination of research and development. The purpose of this paper is to present the current status and future IAEA activities in support of occupational radiation protection. (authors)

International Cooperation in the Area of Nuclear Safety Regulation: Current Status and Way Forward

Energy Technology Data Exchange (ETDEWEB)

Yoo, J. W.; Byeon, M. J.; Lee, J. M.; Lim, J. H. [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

2016-10-15

Global effort and initiatives undertaken after the Fukushima Daiichi accident was the adoption of the Vienna Declaration on Nuclear Safety in February 2015. The Contracting Parties to the Convention on Nuclear Safety (CNS) collaboratively prepared the documentation of the Declaration and unanimously adopted it with the idea to prevent accidents with radiological consequences and to mitigate such consequences should they occur. The OECD/NEA has been working closely with its member and partner countries to identify lessons learnt and follow-up actions at the national and international levels so as to maintain and enhance the level of safety at nuclear facilities following the Fukushima Daiichi nuclear power plant accident. In 2013, the NEA published a report entitled The Fukushima Daiichi Nuclear Power Plant Accident: OECD/NEA Nuclear Safety Response and Lessons Learnt detailing the key immediate responses of the NEA and its member countries. Subsequent to the publish of the report and based on the lessons presented, NEA published a new report entitled Five Years after the Fukushima Daiichi Accident: Nuclear Safety Improvements and Lessons Learnt, focusing on what has been done by the Agency and its member countries to improve safety since the accident in 2011. cooperation based on the needs of technical area would further enhance effectiveness of cooperative activities and would enable to foresee future regulatory needs which can be considered when establishing a strategy. Since the establishment of NSSC in 2011, NSSC has played a major role in concluding agreements with regulatory bodies of other countries. Despite of the change, KINS, yet, is able to pursue technical-specified cooperation as a TSO under the umbrella of agreements between governments or regulatory bodies. establishment of expert pool and systematic mid- and long-term capacity building framework of relevant experts would enhance continuity and expertise. Currently, most of the participants or

Current status of NPP generation IV

International Nuclear Information System (INIS)

Yohanes Dwi Anggoro; Dharu Dewi; Nurlaila; Arief Tris Yuliyanto

2013-01-01

Today development of nuclear technology has reached the stage of research and development of Generation IV nuclear power plants (advanced reactor systems) which is an innovative development from the previous generation of nuclear power plants. There are six types of power generation IV reactors, namely: Very High Temperature Reactor (VHTR), Sodium-cooled Fast Reactor (SFR), Gas-cooled Fast Reactor (GFR), Lead-cooled Fast Reactor (LFR), Molten Salt Reactor (MSR), and Super Critical Water-cooled Reactor (SCWR). The purpose of this study is to know the development of Generation IV nuclear power plants that have been done by the thirteen countries that are members of the Gen IV International Forum (GIF). The method used is review study and refers to various studies related to the current status of research and development of generation IV nuclear power. The result of this study showed that the systems and technology on Generation IV nuclear power plants offer significant advances in sustainability, safety and reliability, economics, and proliferation resistance and physical protection. In addition, based on the research and development experience is estimated that: SFR can be used optimally in 2015, VHTR in 2020, while NPP types GFR, LFR, MSR, and SCWR in 2025. Utilization of NPP generation IV said to be optimal if fulfill the goal of NPP generation IV, such as: capable to generate energy sustainability and promote long-term availability of nuclear fuel, minimize nuclear waste and reduce the long term stewardship burden, has an advantage in the field of safety and reliability compared to the previous generation of NPP and VHTR technology have a good prospects in Indonesia. (author)

Periodic Safety Review in Interim Storage Facilities - Current Regulation and Experiences in Germany

International Nuclear Information System (INIS)

Neles, Julia Mareike; Schmidt, Gerhard

2014-01-01

PSR, to be a comprehensive and systematic review of all safety issues of a facility, based on the current state of science and technology, with a clear description of the safety standards to be applied and a traceable evaluation of the facility's current status against those standards, including identification and evaluation of interdependencies, is currently not completely reached. The current conclusion is that the guideline requires upgrades to improve this implementation process. (authors)

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

International Nuclear Information System (INIS)

1999-01-01

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

Probabilistic safety goals. Phase 3 - Status report

Energy Technology Data Exchange (ETDEWEB)

Holmberg, J.-E. (VTT (Finland)); Knochenhauer, M. (Relcon Scandpower AB, Sundbyberg (Sweden))

2009-07-15

The first phase of the project (2006) described the status, concepts and history of probabilistic safety goals for nuclear power plants. The second and third phases (2007-2008) have provided guidance related to the resolution of some of the problems identified, and resulted in a common understanding regarding the definition of safety goals. The basic aim of phase 3 (2009) has been to increase the scope and level of detail of the project, and to start preparations of a guidance document. Based on the conclusions from the previous project phases, the following issues have been covered: 1) Extension of international overview. Analysis of results from the questionnaire performed within the ongoing OECD/NEA WGRISK activity on probabilistic safety criteria, including participation in the preparation of the working report for OECD/NEA/WGRISK (to be finalised in phase 4). 2) Use of subsidiary criteria and relations between these (to be finalised in phase 4). 3) Numerical criteria when using probabilistic analyses in support of deterministic safety analysis (to be finalised in phase 4). 4) Guidance for the formulation, application and interpretation of probabilistic safety criteria (to be finalised in phase 4). (LN)

Probabilistic safety goals. Phase 3 - Status report

International Nuclear Information System (INIS)

Holmberg, J.-E.; Knochenhauer, M.

2009-07-01

The first phase of the project (2006) described the status, concepts and history of probabilistic safety goals for nuclear power plants. The second and third phases (2007-2008) have provided guidance related to the resolution of some of the problems identified, and resulted in a common understanding regarding the definition of safety goals. The basic aim of phase 3 (2009) has been to increase the scope and level of detail of the project, and to start preparations of a guidance document. Based on the conclusions from the previous project phases, the following issues have been covered: 1) Extension of international overview. Analysis of results from the questionnaire performed within the ongoing OECD/NEA WGRISK activity on probabilistic safety criteria, including participation in the preparation of the working report for OECD/NEA/WGRISK (to be finalised in phase 4). 2) Use of subsidiary criteria and relations between these (to be finalised in phase 4). 3) Numerical criteria when using probabilistic analyses in support of deterministic safety analysis (to be finalised in phase 4). 4) Guidance for the formulation, application and interpretation of probabilistic safety criteria (to be finalised in phase 4). (LN)

Radiation safety status at a bio medical research centre

International Nuclear Information System (INIS)

Mishra, S.K.

1998-01-01

Radioisotopes are being used for biomedical research purpose at School of Life Science, Jawaharlal Nehru University for the last twenty five years. Present paper analyses the overall status of radiation safety at this Centre

Current status of chirality in agrochemicals.

Science.gov (United States)

Jeschke, Peter

2018-04-27

The agrochemical industry is continuously searching for new pesticides to develop products with optimal efficacy, lower application rates in the field, increased selectivity, favorable toxicological and environmental safety, enhanced user friendliness and better economic viability. One strategy to achieve these ambitious goals makes use of the unique properties of molecules containing asymmetric centers. In the past, many natural products and their congeners have been a source of inspiration for designing new active ingredients, and the molecular structure of the resulting molecules have become increasingly complex. 30% contain fragments with asymmetric centers. However, despite the enormous progress that has been made in catalytic asymmetric processes over the last decade, only few agrochemicals are produced in enantiomerically pure or enriched form on an industrial scale. Since 2007, around 43% of the 44 launched products (insecticides, acaricides, fungicides, nematicides, and herbicides) contain one or more asymmetric centers in the molecule (≈ 47 %) and most of them were launched as racemic mixtures of enantiomers or diastereomers. This review gives an overview of the current status of chiral agrochemicals launched over the past 10 years and describes the inherently connected challenges of modern agricultural chemistry by managing important aspects resulting from stereochemistry of these innovative products. This article is protected by copyright. All rights reserved.

LMFBR safety. 3. Review of current issues and bibliography of literature (1972--1974)

International Nuclear Information System (INIS)

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

1977-01-01

The report discusses the current status of liquid-metal fast breeder reactor (LMFBR) development and one of the principal safety issues, a hypothetical core-disruptive accident (HCDA). Bibliographic information on worldwide LMFBRs relative to the development of the breeder reactor as a safe source of nuclear power is presented for the period 1972 through 1974. The bibliography consists of approximately 1380 abstracts covering research and development and operating experiences leading up to the present design practices that are necessary for the licensing of breeder reactors. Key-word, author, and permuted-title indexes are included

LMFBR safety. 3. Review of current issues and bibliography of literature (1972--1974)

Energy Technology Data Exchange (ETDEWEB)

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

1977-02-24

The report discusses the current status of liquid-metal fast breeder reactor (LMFBR) development and one of the principal safety issues, a hypothetical core-disruptive accident (HCDA). Bibliographic information on worldwide LMFBRs relative to the development of the breeder reactor as a safe source of nuclear power is presented for the period 1972 through 1974. The bibliography consists of approximately 1380 abstracts covering research and development and operating experiences leading up to the present design practices that are necessary for the licensing of breeder reactors. Key-word, author, and permuted-title indexes are included.

LMFBR safety. 1. Review of current issues and bibliography of literature, 1960--1969

Energy Technology Data Exchange (ETDEWEB)

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

1976-08-16

This report discusses the current status of liquid-metal fast breeder (LMFBR) development and one of the principal safety issues, a hypothetical core-disruptive accident (HCDA). Bibliographic information on worldwide LMFBRs relative to the development of the breeder reactor as a safe source of nuclear power is presented for the period 1960 through 1969. The bibliography consists of 1560 abstracts covering early research and development and operating experiences leading up to the present design practices that are necessary for the licensing of breeder reactors. Key-word, author, and permuted-title indexes are included for completeness.

LMFBR safety. 1. Review of current issues and bibliography of literature, 1960--1969

International Nuclear Information System (INIS)

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

1976-01-01

This report discusses the current status of liquid-metal fast breeder (LMFBR) development and one of the principal safety issues, a hypothetical core-disruptive accident (HCDA). Bibliographic information on worldwide LMFBRs relative to the development of the breeder reactor as a safe source of nuclear power is presented for the period 1960 through 1969. The bibliography consists of 1560 abstracts covering early research and development and operating experiences leading up to the present design practices that are necessary for the licensing of breeder reactors. Key-word, author, and permuted-title indexes are included for completeness

Panel: Current Status of Knowledge and Recommendations for Further Related Activities

International Nuclear Information System (INIS)

Caldarola, L.; Costa, J.; Fauske, Hans K.; Jakeman, D.; Mizuta, H.; Wright, R.W.; Stadie, K.B.

1976-01-01

This Panel consists of two parts, in the first part the participants attempt to summarise their views on the current status and knowledge of SFI and its importance for the LMFBR safety case and in the second part they try to agree on recommendations for future actions. The first question tackled was: what progress has been made since the Ispra meeting which was a little over two years ago - in answering the question: 'what role does SFI play in LMFBR safety'? The second question approached was: 'Is it possible to identify SFI areas which are not yet covered by the present research and development programme? Finally 4 recommendations were proposed: 1. to have another meeting of the same nature as this one and the previous ones in two years' time; 2. to create a group dealing with the fundamental science with a view to further the safety of the LMFBR. This group would meet more regularly and would not require, and that is the important thing, approval from-CSNI every time it meets; 3. to discontinue the group on calculational models; 4. to publish at least one to two newsletters between this SFI meeting and the next SFI meeting in two years

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

International Nuclear Information System (INIS)

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

1995-05-01

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

Artificial neural network for research reactor safety status monitoring

International Nuclear Information System (INIS)

Varde, P.V.

2001-01-01

During reactor upset/abnormal conditions, emphasis is placed on plant operator's ability to quickly identify the problem and perform diagnosis and initiate recovery action to ensure safety of the plant. However, the reliability of human action is adversely affected at the time of crisis, due to the time stress and psychological factors. Availability of operational aids capable of monitoring the status of the plant and quickly identifying the deviation from normal operation is expected to significantly improve the operator reliability. Artificial Neural Network (based on Back Propagation Algorithm) has been developed and applied for reactor safety status monitoring, as part of an Operator Support System. ANN has been trained for 14 different plant states using 42 input symptom patterns. Recall tests performed on the ANN show that the system was able to identify the plant state with reasonable accuracy. (author)

Status and subjects of thermal-hydraulic analysis for next-generation LWRs with passive safety systems

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-03-01

The present status and subjects on thermal-hydraulic analysis for next-generation light water reactors (LWRs) with passive safety systems were summarized based on survey results and discussion by subcommittee on improvement of reactor thermal-hydraulic analysis codes under nuclear code committee in Japan Atomic Energy Research Institute. This survey was performed to promote the research of improvement of reactor thermal-hydraulic analysis codes in future. In the first part of this report, the status and subjects on system analysis and those on evaluation of passive safety system performance are summarized for various types of reactor proposed before. In the second part, the status and subjects on multidimensional two-phase flow analysis are reviewed, since the multidimensional analysis was recognized as one of most important subjects through the investigation in the first part. Besides, databases for bubbly flow and annular dispersed flow were explored, those are needed to assess and verify each multidimensional analytical method. The contents in this report are the forefront of thermal-hydraulic analysis for LWRs and those include current findings for the development of multidimensional two-phase flow analytical method. Thus, we expect that the contents can offer various useful information against the improvement of reactor thermal-hydraulic analysis codes in future. (author)

Safety culture indicators for NPP: international trends and development status in Korea

International Nuclear Information System (INIS)

Choi, Y. S.; Ko, J. D.; Choi, K. S.; Jung, Y. H.

2004-01-01

Safety culture has been recognized as important to achieve high level of nuclear safety, as several recent events that have occurred in advanced countries were found to have important implications for safety culture. Under the recognition, implementation-focused and practical methods to foster safety culture have become necessary. Development of safety culture indicators for assessing the level of safety culture and identifying some deficiencies is being conducted. This paper examines the regulatory positions of major nuclear power countries on licensee's safety culture, introduces the development status of Korean Safety Culture Indicators and presents its future direction

Commentary: Status of road safety in Asia.

Science.gov (United States)

Wismans, Jac; Skogsmo, Ingrid; Nilsson-Ehle, Anna; Lie, Anders; Thynell, Marie; Lindberg, Gunnar

2016-01-01

The objective of this article is to assess the status of road safety in Asia and present accident and injury prevention strategies based on global road safety improvement experiences and discuss the way forward by indicating opportunities and countermeasures that could be implemented to achieve a new level of safety in Asia. This study provides a review and analyses of data in the literature, including from the World Health Organization (WHO) and World Bank, and a review of lessons learned from best practices in high-income countries. In addition, an estimation of costs due to road transport injuries in Asia and review of future trends in road transport is provided. Data on the global and Asian road safety problem and status of prevention strategies in Asia as well as recommendations for future actions are discussed. The total number of deaths due to road accidents in the 24 Asian countries, encompassing 56% of the total world population, is 750,000 per year (statistics 2010). The total number of injuries is more than 50 million, of which 12% are hospital admissions. The loss to the economy in the 24 Asian countries is estimated to around US$800 billion or 3.6% of the gross domestic product (GDP). This article clearly shows that road safety is causing large problems and high costs in Asia, with an enormous impact on the well-being of people, economy, and productivity. In many Asian low- and middle-income countries, the yearly number of fatalities and injuries is increasing. Vulnerable road users (pedestrians, cyclists, and motorcyclists combined) are particularly at risk. Road safety in Asia should be given rightful attention, including taking powerful, effective actions. This review stresses the need for reliable accident data, because there is considerable underreporting in the official statistics. Reliable accident data are imperative to determine evidence-based intervention strategies and monitor the success of these interventions and analyses. On the other

LMFBR safety. 2. Review of current issues and bibliography of literature, 1970--1972

International Nuclear Information System (INIS)

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

1976-01-01

This report discusses the current status of liquid-metal fast breeder reactor (LMFBR) development and one of the principal safety issues, a hypothetical core-disruptive accident (HCDA). Bibliographic information on worldwide LMFBRs relative to the development of the breeder reactor as a safe source of nuclear power is presented for the period 1970 through 1972. The bibliography consists of approximately 1620 abstracts covering early research and development and operating experiences leading up to the present design practices that are necessary for the licensing of breeder reactors. Key-word, author, and permuted-title indexes are included for completeness

LMFBR safety. 4. Review of current issues and bibliography of literature (1974--1975)

Energy Technology Data Exchange (ETDEWEB)

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

1977-03-21

This report discusses the current status of liquid-metal fast breeder reactor (LMFBR) development and one of the principal safety issues, a hypothetical core-disruptive accident (HCDA). Bibliographic information on worldwide LMFBRs relative to the development of the breeder reactor as a safe source of nuclear power is presented for the period 1974 through 1975. The bibliography consists of approximately 1554 abstracts covering early research and development and operating experiences leading up to the present design practices that are necessary for the licensing of breeder reactors. Key-word, author, and permuted-title indexes are included for completeness.

LMFBR safety. 4. Review of current issues and bibliography of literature (1974--1975)

International Nuclear Information System (INIS)

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

1977-01-01

This report discusses the current status of liquid-metal fast breeder reactor (LMFBR) development and one of the principal safety issues, a hypothetical core-disruptive accident (HCDA). Bibliographic information on worldwide LMFBRs relative to the development of the breeder reactor as a safe source of nuclear power is presented for the period 1974 through 1975. The bibliography consists of approximately 1554 abstracts covering early research and development and operating experiences leading up to the present design practices that are necessary for the licensing of breeder reactors. Key-word, author, and permuted-title indexes are included for completeness

LMFBR safety. 2. Review of current issues and bibliography of literature, 1970--1972

Energy Technology Data Exchange (ETDEWEB)

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

1976-11-22

This report discusses the current status of liquid-metal fast breeder reactor (LMFBR) development and one of the principal safety issues, a hypothetical core-disruptive accident (HCDA). Bibliographic information on worldwide LMFBRs relative to the development of the breeder reactor as a safe source of nuclear power is presented for the period 1970 through 1972. The bibliography consists of approximately 1620 abstracts covering early research and development and operating experiences leading up to the present design practices that are necessary for the licensing of breeder reactors. Key-word, author, and permuted-title indexes are included for completeness.

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

International Nuclear Information System (INIS)

1999-01-01

operation of the units. The plant current safety level analysis has been performed using IAEA analytical methodology according to 50-SG-O12 standard 'Periodic safety review of operational nuclear power plants'. The approach and criteria for acceptable safety level definition, developed by IAEA and presented in INSAG-8 ' was used for analysis performance. Based on this analysis a set of activities was developed, to ensures further plant operation with the necessary safety level. The measures were combined in a program called Complex program for modernization of units 1-4. The implementation of the program is foreseen for a period of four next fuel cycles and started at the beginning of 1998. In respond to the requirements for the content of this paper a detailed description of the current status of resolving of the safety issues, classified by IAEA in TECDOC 640 is presented. The whole process of safety evaluation, short and long term safety improvements presents in a systematical manner the efforts of the Government of Bulgaria, NEK Ltd and KNPP to operate these units with due respect of their nuclear safety responsibility according to Nuclear Safety Convention signed at Vienna in 1994 and ratified by Bulgarian Parliament in 1995

Safety analysis of the present status of the research reactor 'RA' at 'Vinca' Institute

International Nuclear Information System (INIS)

Jovic, V.; Jovic, L.; Zivotic, Z.; Milovanovic, Dj.

1995-01-01

Safety analysis of the nuclear facility which has been out of work for a long time and whose future is not defined at the present moment, can not be connected to the usual, normatively regulated system analysis procedure in both operational and accidental regimes. Therefore, the safety analysis of the present status of the present status of the reactor RA is related to system and components analysis which, in present conditions maintain their nuclear functions operational. In the first place, it refers to components and equipment in which radioactive radiation generation still exists and to installations and equipment maintaining radiation level below permitted limit. in the context of the analysis the following areas are being covered: present status characteristics, accidental events while operating period from 1959. to 1984., nuclear fuels and radioactive waste inventory, basic characteristics and status of safety-related systems and equipment, radiation protection, potential accident analysis at present status of the reactor RA, potential accidental situations due to natural events (earthquakes, water flood) or man-induced events and security. 8 refs

The status of occupational safety among health service providers in ...

African Journals Online (AJOL)

identify and bring under control at workplaces all health risks; provide ... on the status of occupational safety among hospital workers in Tanzania. ..... The assistance from the IPC/IS. National ... tions of the Healthcare Infection Prevention.

Galileo and Ulysses missions safety analysis and launch readiness status

International Nuclear Information System (INIS)

Cork, M.J.; Turi, J.A.

1989-01-01

The Galileo spacecraft will explore the Jupiter system and Ulysses will fly by Jupiter en route to a polar orbit of the sun. Both spacecraft are powered by general purpose heat source radioisotope thermoelectric generators (RTGs). As a result of the Challenger accident and subsequent mission reprogramming, the Galileo and Ulysses missions' safety analysis had to be repeated. In addition to presenting an overview of the safety analysis status for the missions, this paper presents a brief review of the missions' objectives and design approaches, RTG design characteristics and development history, and a description of the safety analysis process. (author)

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

International Nuclear Information System (INIS)

1992-12-01

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

Current status of cerebral glioma surgery in China.

Science.gov (United States)

Wu, Jin-song; Zhang, Jie; Zhuang, Dong-xiao; Yao, Cheng-jun; Qiu, Tian-ming; Lu, Jun-feng; Zhu, Feng-ping; Mao, Ying; Zhou, Liang-fu

2011-09-01

The treatment of gliomas is highly individualized. Surgery for gliomas is essentially for histological diagnosis, to alleviate mass effect, and most importantly, to favor longer survival expectancy. During the past two decades, many surgical techniques and adjuvants have been applied to glioma surgery in China, which lead to a rapid development in the field of cerebral glioma surgery. This article broadly and critically reviewed the existing studies on cerebral glioma surgery and to portrait the current status of glioma surgery in China. A literature search was conducted covering major innovative surgical techniques and adjuvants for glioma surgery in China. The following databases were searched: the Pubmed (January 1995 to date); China Knowledge Resource Integrated Database (January 1995 to date) and VIP Database for Chinese Technical Periodicals (January 1995 to date). A selection criterion was established to exclude duplicates and irrelevant studies. The outcome measures were extracted from included studies. A total of 3307 articles were initially searched. After excluded by abstracts and full texts, 69 studies conducted in the mainland of China were included and went through further analysis. The philosophy of surgical strategies for cerebral gliomas in China is undergoing tremendous change. Nowadays Chinese neurosurgeons pay more attention to the postoperative neurofunctional status of the patients. The aim of the glioma surgery is not only the more extensive tumor resection but also the maximal safety of intervention. The well balance of longer overall survival and higher quality of life should be judged with respect to each individual patient.

Current status of quantum electrical metrology

International Nuclear Information System (INIS)

Urano, Chiharu; Kaneko, Nobuhisa; Kiryu, Shogo

2005-01-01

Physical background, current status of proof systems and researches of the next generation standards of Josephson voltage and Quantized Hall Resistance (QHR) standard system are described. Josephson effect, the principle and theory of quantized hall effect, usual voltage standard system, standard feed of direct current resistance, and researches of voltage standard and direct current resistance standard are explained. The current-voltage of Josephson element in the usual voltage standard proof system and bias method, outline of typical Josephson voltage standard proof system and GaAs/AlGaAs heterostructure used as resistance standard are stated. Cryogenic Current Comparator (CCC) and Direct Current Comparator (DCC) proofread usual resistor. New Quantum Hall Array Resistance Standard (QHARS) is studied by BNM-LNE group in French, and the other new AC Quantized Hall Resistance (AC-QHR) by the European ACQHE Project. (S.Y.)

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

International Nuclear Information System (INIS)

Kirchsteiger, C.; Boeck, H.

2006-01-01

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

Educational status and organizational safety climate: does educational attainment influence workers' perceptions of workplace safety?

OpenAIRE

Gyekye, Seth; Salminen, Simo

2009-01-01

From a practical perspective, understanding the impact of education on perceptions of workplace safety would benefit management’s decisions regarding workers’ adaptability, general work effectiveness, accident frequency, implementation of safety management policies, and handling of education-related accident characteristics. The current study thus examined the relationship between educational attainment and (i) safety perception, (ii) job satisfaction, (iii) compliance with safety management ...

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

Current status and prospects for Chernobyl Ukritiye

International Nuclear Information System (INIS)

Jampsin, B.

1996-01-01

Current status and prospects for Chernobyl Ukritiye (sarcophagus) are described, including the following issues: the accident; the sarcophagus; the radioactive inventory; the design basis criteria; the analysis of the present state; a way forward

Current Status of On-Site Wastewater Management

Science.gov (United States)

Senn, Charles L.

1978-01-01

Wastewater management is becoming an important environmental issue nationally. This article reports the history and current status of wastewater management. Regulatory programs are discussed with specific state examples. Needs assessment is also included. (MA)

Safety and tolerability of transcranial direct current stimulation to stroke patients - A phase I current escalation study.

Science.gov (United States)

Chhatbar, Pratik Y; Chen, Rong; Deardorff, Rachael; Dellenbach, Blair; Kautz, Steven A; George, Mark S; Feng, Wuwei

A prior meta-analysis revealed that higher doses of transcranial direct current stimulation (tDCS) have a better post-stroke upper-extremity motor recovery. While this finding suggests that currents greater than the typically used 2 mA may be more efficacious, the safety and tolerability of higher currents have not been assessed in stroke patients. We aim to assess the safety and tolerability of single session of up to 4 mA in stroke patients. We adapted a traditional 3 + 3 study design with a current escalation schedule of 1»2»2.5»3»3.5»4 mA for this tDCS safety study. We administered one 30-min session of bihemispheric montage tDCS and simultaneous customary occupational therapy to patients with first-ever ischemic stroke. We assessed safety with pre-defined stopping rules and investigated tolerability through a questionnaire. Additionally, we monitored body resistance and skin temperature in real-time at the electrode contact site. Eighteen patients completed the study. The current was escalated to 4 mA without meeting the pre-defined stopping rules or causing any major safety concern. 50% of patients experienced transient skin redness without injury. No rise in temperature (range 26°C-35 °C) was noted and skin barrier function remained intact (i.e. body resistance >1 kΩ). Our phase I safety study supports that single session of bihemispheric tDCS with current up to 4 mA is safe and tolerable in stroke patients. A phase II study to further test the safety and preliminary efficacy with multi-session tDCS at 4 mA (as compared with lower current and sham stimulation) is a logical next step. ClinicalTrials.gov Identifier: NCT02763826. Copyright © 2017 Elsevier Inc. All rights reserved.

The WIMP Paradigm: Current Status

International Nuclear Information System (INIS)

Feng, Jonathan

2011-01-01

The WIMP paradigm is the glue that joins together much of the high energy and cosmic frontiers. It postulates that most of the matter in the Universe is made of weakly-interacting massive particles, with implications for a broad range of experiments and observations. I will review the WIMP paradigm's underlying motivations, its current status in view of rapid experimental progress on several fronts, and recent theoretical variations on the WIMP paradigm theme.

REMPAN at international level: current status

International Nuclear Information System (INIS)

Souchkevitch, Guennadi

1997-01-01

This document describes the current status of the Radiation Emergency medical Preparedness and Assistance Network - REMPAN, for the promotion of radiation emergency medical and public health preparedness and for practical assistance and advising countries, in a case of overexposure from any sources of radiation, by initiative of the World Health Organization - WHO

Current status of ion source development

International Nuclear Information System (INIS)

Ishikawa, Junzo

2001-01-01

In this report, the current status of ion source development will be discussed. In September 2001, the 9th International Conference on Ion Sources (ICIS01) was held in Oakland, U.S.A. Referring the talks presented at ICIS01, recent topics in the ion source research fields will be described. (author)

Improving the safety of LWR power plants. Final report

International Nuclear Information System (INIS)

1980-04-01

This report documents the results of the Study to identify current, potential research issues and efforts for improving the safety of Light Water Reactor (LWR) power plants. This final report describes the work accomplished, the results obtained, the problem areas, and the recommended solutions. Specifically, for each of the issues identified in this report for improving the safety of LWR power plants, a description is provided in detail of the safety significance, the current status (including information sources, status of technical knowledge, problem solution and current activities), and the suggestions for further research and development. Further, the issues are ranked for action into high, medium, and low priority with respect to primarily (a) improved safety (e.g. potential reduction in public risk and occupational exposure), and secondly (b) reduction in safety-related costs

Status of electrical safety in Indira Gandhi Centre for Atomic Research

International Nuclear Information System (INIS)

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

1999-01-01

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

Current status of the AUSTRON project

International Nuclear Information System (INIS)

Rauch, H.; Regler, M.; Lechner, R.E.; Weber, H.

2001-01-01

The current status of the AUSTRON spallation source project is described with reference to the need for neutrons in Europe and - due to a certain West-East imbalance of large research facilities - especially in Central Europe. A short overview about technical aspects of proton accelerator, rapid cycling synchrotron, storage ring, target and instrumentation is presented. (author)

COHERENT Experiment: current status

International Nuclear Information System (INIS)

Akimov, D; Belov, V; Bolozdynya, A; Burenkov, A; Albert, J B; Del Valle Coello, M; D’Onofrio, M; Awe, C; Barbeau, P S; Cervantes, M; Becker, B; Cabrera-Palmer, B; Collar, J I; Cooper, R J; Cooper, R L; Cuesta, C; Detwiler, J; Eberhardt, A; Dean, D; Dolgolenko, A G

2017-01-01

The COHERENT Collaboration is realizing a long term neutrino physics research program. The main goals of the program are to detect and study elastic neutrino-nucleus scattering (CEνNS). This process is predicted by Standard Model but it has never been observed experimentally because of the very low energy of the recoil nucleus. COHERENT is using different detector technologies: CsI[Na] and NaI scintillator crystals, a single-phase liquid Ar and a Ge detectors. The placement of all the detector setups is in the basement of the Spallation Neutron Source (SNS) at Oak Ridge National Laboratory (ORNL). The current status of the COHERENT experimental program is presented. (paper)

CMS Data Analysis: Current Status and Future Strategy

CERN Document Server

Innocente, V

2003-01-01

We present the current status of CMS data analysis architecture and describe work on future Grid-based distributed analysis prototypes. CMS has two main software frameworks related to data analysis: COBRA, the main framework, and IGUANA, the interactive visualisation framework. Software using these frameworks is used today in the world-wide production and analysis of CMS data. We describe their overall design and present examples of their current use with emphasis on interactive analysis. CMS is currently developing remote analysis prototypes, including one based on Clarens, a Grid-enabled client-server tool. Use of the prototypes by CMS physicists will guide us in forming a Grid-enriched analysis strategy. The status of this work is presented, as is an outline of how we plan to leverage the power of our existing frameworks in the migration of CMS software to the Grid.

Health Status of Current National Guard Members

National Research Council Canada - National Science Library

Proctor, Susan P

2005-01-01

.... The objectives are to: 1) describe the current health status of this ARNG cohort, 2) examine to what extent the job strain of ARNG service affects the relationship between Civilian job strain and health and job performance outcomes and, 3...

Current status of fusion-relevant covariance data

International Nuclear Information System (INIS)

Muir, D.W.

1994-01-01

The following review of the current status of formatted data covariance files and their multigroup processing is a contribution to the IAEA Advisory Group Meeting on ''Improved Evaluations and Integral Data Testing for FENDL,'' to be held at the Max-Planck-Institut fuer Plasmaphysik, Garching, Germany, 12--16 September 1994. The draft agenda of this meeting lists as Item 6 the ''assessment of present status and role of uncertainty files, their processing and sensitivity studies related to FENDL.'' We conclude that this is an important and timely topic and recommend needed actions in this field

Review of current status for designing severe accident management support system

Energy Technology Data Exchange (ETDEWEB)

Jeong, Kwang Sub

2000-05-01

The development of operator support system (OSS) is ongoing in many other countries due to the complexity both in design and in operation for nuclear power plant. The computerized operator support system includes monitoring of some critical parameters, early detection of plant transient, monitoring of component status, plant maintenance, and safety parameter display, and the operator support system for these areas are developed and are being used in some plants. Up to now, the most operator support system covers the normal operation, abnormal operation, and emergency operation. Recently, however, the operator support system for severe accident is to be developed in some countries. The study for the phenomena of severe accident is not performed sufficiently, but, based on the result up to now, the operator support system even for severe accident will be developed in this study. To do this, at first, the current status of the operator support system for normal/abnormal/emergency operation is reviewed, and the positive aspects and negative aspects of systems are analyzed by their characteristics. And also, the major items that should be considered in designing the severe accident operator support system are derived from the review. With the survey of domestic and foreign operator support systems, they are reviewed in terms of the safety parameter display system, decision-making support system, and procedure-tracking system. For the severe accident, the severe accident management guideline (SAMG) which is developed by Westinghouse is reviewed; the characteristics, structure, and logical flow of SAMG are studied. In addition, the critical parameters for severe accident, which are the basis for operators decision-making in severe accident management and are supplied to the operators and the technical support center, are reviewed, too.

Review of current status for designing severe accident management support system

International Nuclear Information System (INIS)

Jeong, Kwang Sub

2000-05-01

The development of operator support system (OSS) is ongoing in many other countries due to the complexity both in design and in operation for nuclear power plant. The computerized operator support system includes monitoring of some critical parameters, early detection of plant transient, monitoring of component status, plant maintenance, and safety parameter display, and the operator support system for these areas are developed and are being used in some plants. Up to now, the most operator support system covers the normal operation, abnormal operation, and emergency operation. Recently, however, the operator support system for severe accident is to be developed in some countries. The study for the phenomena of severe accident is not performed sufficiently, but, based on the result up to now, the operator support system even for severe accident will be developed in this study. To do this, at first, the current status of the operator support system for normal/abnormal/emergency operation is reviewed, and the positive aspects and negative aspects of systems are analyzed by their characteristics. And also, the major items that should be considered in designing the severe accident operator support system are derived from the review. With the survey of domestic and foreign operator support systems, they are reviewed in terms of the safety parameter display system, decision-making support system, and procedure-tracking system. For the severe accident, the severe accident management guideline (SAMG) which is developed by Westinghouse is reviewed; the characteristics, structure, and logical flow of SAMG are studied. In addition, the critical parameters for severe accident, which are the basis for operators decision-making in severe accident management and are supplied to the operators and the technical support center, are reviewed, too

Drugs in development for toxoplasmosis: advances, challenges, and current status.

Science.gov (United States)

Alday, P Holland; Doggett, Joseph Stone

2017-01-01

Toxoplasma gondii causes fatal and debilitating brain and eye diseases. Medicines that are currently used to treat toxoplasmosis commonly have toxic side effects and require prolonged courses that range from weeks to more than a year. The need for long treatment durations and the risk of relapsing disease are in part due to the lack of efficacy against T. gondii tissue cysts. The challenges for developing a more effective treatment for toxoplasmosis include decreasing toxicity, achieving therapeutic concentrations in the brain and eye, shortening duration, eliminating tissue cysts from the host, safety in pregnancy, and creating a formulation that is inexpensive and practical for use in resource-poor areas of the world. Over the last decade, significant progress has been made in identifying and developing new compounds for the treatment of toxoplasmosis. Unlike clinically used medicines that were repurposed for toxoplasmosis, these compounds have been optimized for efficacy against toxoplasmosis during preclinical development. Medicines with enhanced efficacy as well as features that address the unique aspects of toxoplasmosis have the potential to greatly improve toxoplasmosis therapy. This review discusses the facets of toxoplasmosis that are pertinent to drug design and the advances, challenges, and current status of preclinical drug research for toxoplasmosis.

Current status of methods for shielding analysis

International Nuclear Information System (INIS)

Engle, W.W.

1980-01-01

Current methods used in shielding analysis and recent improvements in those methods are discussed. The status of methods development is discussed based on needs cited at the 1977 International Conference on Reactor Shielding. Additional areas where methods development is needed are discussed

Nuclear safety review for 1984

International Nuclear Information System (INIS)

1985-08-01

This publication is based on the fourth Nuclear Safety Review prepared by the IAEA Secretariat for presentation to the Board of Governors. It discusses relevant international activities in 1984 and the current status of nuclear safety and radiation protection, and looks ahead to anticipated developments

Current Status of Single-incision Laparoscopic Surgery

DEFF Research Database (Denmark)

Ahmed, Irfan; Ciancio, Fabio; Ferrara, Vincenzo

2012-01-01

Recent advances in minimally invasive surgery have centered on reducing the number of incisions required, which has led to the development of the single-incision laparoscopic technique. A panel of European single-incision laparoscopy experts met to discuss the current status of, and the future...

Current status of Uganda Kob (Kobus Kob Thomasi Neumann) in ...

African Journals Online (AJOL)

Current status of Uganda Kob (Kobus Kob Thomasi Neumann) in Toro Game Reserve, Uganda. ... As part of a biological assessment of Toro Game Reserve, the status of Uganda kob Kobus kob Thomasi ... AJOL African Journals Online.

Status of Safety Precautions in Science Laboratories in Enugu State ...

African Journals Online (AJOL)

This study was conducted to determine the status of safety precautions in science laboratories in Enugu State of Nigeria. Three research questions and two hypotheses guided the study. The research questions include: 1. What are the sources of hazards in school science laboratories? 2. What are the causes of accidents in ...

NPP Krsko periodic safety review. Safety assessment and analyses

International Nuclear Information System (INIS)

Basic, I.; Spiler, J.; Thaulez, F.

2002-01-01

Definition of a PSR (Periodic Safety Review) project is a comprehensive safety review of a plant after ten years of operation. The objective is a verification by means of a comprehensive review using current methods that the plant remains safe when judged against current safety objectives and practices and that adequate arrangements are in place to maintain plant safety. The overall goals of the NEK PSR Program are defined in compliance with the basic role of a PSR and the current practice typical for most of the countries in EU. This practice is described in the related guides and good practice documents issued by international organizations. The overall goals of the NEK PSR are formulated as follows: to demonstrate that the plant is as safe as originally intended; to evaluate the actual plant status with respect to aging and wear-out identifying any structures, systems or components that could limit the life of the plant in the foreseeable future, and to identify appropriate corrective actions, where needed; to compare current level of safety in the light of modern standards and knowledge, and to identify where improvements would be beneficial for minimizing deviations at justifiable costs. The Krsko PSR will address the following safety factors: Operational Experience, Safety Assessment, EQ and Aging Management, Safety Culture, Emergency Planning, Environmental Impact and Radioactive Waste.(author)

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

International Nuclear Information System (INIS)

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

2009-01-01

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

Radiation processing. Current status and future possibilities

International Nuclear Information System (INIS)

Woods, R.J.

2000-01-01

Radiation processing developed following the Second World War and employees gamma- or electron-irradiation to process polymers, cure alkene-based inks and coatings, sterilize medical supplies, irradiate food, and manage wastes. The current status of these applications is described with the probable direction of future developments. (author)

Use of toxicogenomics in drug safety evaluation: Current status and an industry perspective.

Science.gov (United States)

Vahle, John L; Anderson, Ulf; Blomme, Eric A G; Hoflack, Jean-Christophe; Stiehl, Daniel P

2018-04-18

Toxicogenomics held great promise as an approach to enable early detection of toxicities induced by xenobiotics; however, there remain questions regarding the impact of the discipline on pharmaceutical nonclinical safety assessment. To understand the current state of toxicogenomics in the sector, an industry group surveyed companies to determine the frequency of toxicogenomics use in in vivo studies at various stages of drug discovery and development and to assess how toxicogenomics use has evolved over time. Survey data were compiled during 2016 from thirteen pharmaceutical companies. Toxicogenomic analyses were infrequently conducted in the development phase and when performed were done to address specific mechanistic questions. Prior to development, toxicogenomics use was more frequent; however, there were significant differences in approaches among companies. Across all phases, gaining mechanistic insight was the most frequent reason cited for pursing toxicogenomics with few companies using toxicogenomics to predict toxicities. These data were consistent with the commentary submitted in response to survey questions asking companies to describe the evolution of their toxicogenomics strategy. Overall, these survey data indicate that toxicogenomics is not widely used as a predictive tool in the pharmaceutical industry but is used regularly by some companies and serves a broader role in mechanistic investigations and as a complement to other technologies. Copyright © 2018. Published by Elsevier Inc.

Current status of high-T{sub c} wire

Energy Technology Data Exchange (ETDEWEB)

Vase, Per [Nordic Superconductor Technologies A/S, Priorparken 685, DK 2605 Broendby (Denmark); Fluekiger, Rene [Departement de Physique de la Matiere Condensee, Universite de Geneve (Switzerland); Leghissa, Martino [Siemens AG, Corporate Technology, Erlangen (Germany); Glowacki, Bartek [Department of Material Science and Metallurgy, University of Cambridge, Cambridge CB2 3QZ (United Kingdom)

2000-07-01

This paper is the result of the work of a SCENET (The European Network for Superconductivity) material working group's efforts on giving values for present and future expected performance of high-temperature superconducting (HTS) wires and tapes. The purpose of the work is to give input to the design of HTS applications like power cables, motors, current leads, magnets, transformers and generators. The current status performance values are supposed to be used in the design of today's prototypes and the future values for the design of fully commercial HTS applications of the future. We focus on what is expected to be the relevant parameters for HTS application design. The most successful technique by far for making HTS tapes has been on the (Bi, Pb){sub 2}Sr{sub 2}Ca{sub 2}Cu{sub 3}O{sub x} (Bi-2223) material by the powder-in-tube (PIT) technique and this paper therefore focuses on giving the current status and expected future performance for Bi-2223 tapes. (author)

Current Status of HPV Vaccines

Science.gov (United States)

Ma, Barbara; Roden, Richard; Wu, T.C.

2010-01-01

Cervical cancer is the second largest cause of cancer deaths in women worldwide, with ~500,000 diagnoses and 274,000 deaths annually. It remains a significant source of morbidity and mortality despite effective screening tools and treatments for its precursor high-grade cervical intraepithelial neoplasia (CIN). Increased understanding of cervical pathogenesis has led to the identification of human papillomavirus (HPV) as the etiological agent for cervical cancer and the development of preventive and therapeutic vaccines targeting HPV antigens for the control of cervical cancer. Herein, we discuss the current status of HPV vaccines. PMID:20677402

Passive safety features in current and future water cooled reactors

International Nuclear Information System (INIS)

1990-11-01

Better understanding of the passive safety systems and components in current and future water-cooled reactors may enhance the safety of present reactors, to the extend passive features are backfitted. This better understanding should also improve the safety of future reactors, which can incorporate more of these features. Passive safety systems and components may help to prevent accidents, core damage, or release radionuclides to the environment. The Technical Committee Meeting which was hosted by the USSR State Committee for Utilization of Nuclear Energy was attended by about 80 experts from 16 IAEA Member States and the NEA-OECD. A total of 21 papers were presented during the meeting. The objective of the meeting was to review and discuss passive safety systems and features of current and future water cooled reactor designs and to exchange information in this area of activity. A separate abstract was prepared for each of the 21 papers published in this proceedings. Refs, figs and tabs

[Current status and issues in development of occupational physicians in Japan].

Science.gov (United States)

Mori, Koji

2013-10-01

Training systems for occupational physicians (OPs) have existed since the Industrial Safety and Health Act was enacted in 1972. However, it is necessary to enhance them because of changes in the business environment of Japanese corporations and working patterns have brought about new needs of occupational health (OH) activities. In this paper, OPs were classified into three categories; doctors who spend a part of working time on OH activities, i.e. "non-specialist OPs", doctors who engage in OH activities full-time, i.e. "specialists OPs", and doctors who manage corporate-wide occupational health programs or lead programs at OH service institutes, i.e. "lead OPs", and the status and the issues were reviewed. The major concern identified for each of the three categories in training were found to be quality management for non-specialist OPs, short supply for specialists OPs, and development of competencies such as leadership and management skills for lead OPs, respectively. Current efforts and ideas to improve the training systems were discussed.

United States high-level radioactive waste management program: Current status and plans

International Nuclear Information System (INIS)

Williams, J.

1992-01-01

The inventory of spent fuel in storage at reactor sites in the United States is approximately 20,000 metric tons heavy metal (MTHM). It is increasing at a rate of 1700 to 2100 MTHM per year. According to current projections, by the time the last license for the current generation of nuclear reactors expires, there will be an estimated total of 84,000 MTHm. No commercial reprocessing capacity exists or is planned in the US. Therefore, the continued storage of spent fuel is required. The majority of spent fuel remains in the spent fuel pools of the utilities that generated it. Three utilities are presently supplementing pool capacity with on-site dry storage technologies, and four others are planning dry storage. Commercial utilities are responsible for managing their spent fuel until the Federal waste management system, now under development, accepts spent fuel for storage and disposal. Federal legislation charges the Office of Civilian Radioactive Waste Management (OCRWM) within the US Department of Energy (DOE) with responsibility for developing a system to permanently dispose of spent fuel and high level radioactive waste in a manner that protects the health and safety of the public and the quality of the environment. We are developing a waste management system consisting for three components: a mined geologic repository, with a projected start date of 2010; a monitored retrievable storage facility (MRS), scheduled to begin waste acceptance in 1998; and a transportation system to support MRS and repository operations. This paper discusses the background and framework for the program, as well as the current status and plans for management of spent nuclear fuel at commercial utilities; the OCRWM's development of a permanent geologic repository, an MRS, and a transportation system; the OCRWM's safety approach; the OCRWM's program management initiatives; and the OCRWM's external relations activities

Safety of Transcranial Direct Current Stimulation: Evidence Based Update 2016.

Science.gov (United States)

Bikson, Marom; Grossman, Pnina; Thomas, Chris; Zannou, Adantchede Louis; Jiang, Jimmy; Adnan, Tatheer; Mourdoukoutas, Antonios P; Kronberg, Greg; Truong, Dennis; Boggio, Paulo; Brunoni, André R; Charvet, Leigh; Fregni, Felipe; Fritsch, Brita; Gillick, Bernadette; Hamilton, Roy H; Hampstead, Benjamin M; Jankord, Ryan; Kirton, Adam; Knotkova, Helena; Liebetanz, David; Liu, Anli; Loo, Colleen; Nitsche, Michael A; Reis, Janine; Richardson, Jessica D; Rotenberg, Alexander; Turkeltaub, Peter E; Woods, Adam J

2016-01-01

This review updates and consolidates evidence on the safety of transcranial Direct Current Stimulation (tDCS). Safety is here operationally defined by, and limited to, the absence of evidence for a Serious Adverse Effect, the criteria for which are rigorously defined. This review adopts an evidence-based approach, based on an aggregation of experience from human trials, taking care not to confuse speculation on potential hazards or lack of data to refute such speculation with evidence for risk. Safety data from animal tests for tissue damage are reviewed with systematic consideration of translation to humans. Arbitrary safety considerations are avoided. Computational models are used to relate dose to brain exposure in humans and animals. We review relevant dose-response curves and dose metrics (e.g. current, duration, current density, charge, charge density) for meaningful safety standards. Special consideration is given to theoretically vulnerable populations including children and the elderly, subjects with mood disorders, epilepsy, stroke, implants, and home users. Evidence from relevant animal models indicates that brain injury by Direct Current Stimulation (DCS) occurs at predicted brain current densities (6.3-13 A/m(2)) that are over an order of magnitude above those produced by conventional tDCS. To date, the use of conventional tDCS protocols in human trials (≤40 min, ≤4 milliamperes, ≤7.2 Coulombs) has not produced any reports of a Serious Adverse Effect or irreversible injury across over 33,200 sessions and 1000 subjects with repeated sessions. This includes a wide variety of subjects, including persons from potentially vulnerable populations. Copyright © 2016 Elsevier Inc. All rights reserved.

REACH and nanomaterials: current status

International Nuclear Information System (INIS)

Alessandrelli, Maria; Di Prospero Fanghella, Paola; Polci, Maria Letizia; Castelli, Stefano; Pettirossi, Flavio

2015-01-01

New challenges for regulators are emerging about a specific assessment and appropriate management of the potential risks of nanomaterials. In the framework of European legislation on chemicals, Regulation (EC) No. 1907/2006 REACH aims to ensure the safety of human health and the environment through the collection of information on the physico-chemical characteristics of the substances and on their profile (eco) toxicological and the identification of appropriate risk management linked to 'exposure to these substances without impeding scientific progress and the competitiveness of industry. In order to cover the current shortage of information on the safety of nanomaterials and tackle the acknowledged legal vacuum, are being a rich activities, carried out both by regulators both by stake holders, and discussions on the proposals for adapting the European regulatory framework for chemicals . The European Commission is geared to strengthen the REACH Regulation by means of updates of its annexes. The importance of responding to the regulatory requirements has highlighted the need for cooperation between European organizations, scientists and industries to promote and ensure the safe use of nanomaterials. [it

Current status and future trends of medical physics in Mexico

Science.gov (United States)

Azorin Nieto, J.

2015-01-01

Medical Physics is an area that applies the principles of physics to medicine, particularly in the prevention, diagnosis and treatment of diseases using ionizing and nonionizing radiation. The main attractive of medical physics is that it has a direct impact on the quality and safety of medical care in humans; this social component with direct implications for the population is of high value for Mexico. This paper describes the concepts of medical physics, trends and the current status of this discipline as a profession, which is directly related to the efforts of clinical research. It is also described what is, in my opinion, the future of medical physics in Mexico, emphasizing the fact that this field requires a substantial boost from universities and hospitals to recruit highly qualified young medical physicists and the support from government agencies such as Secretaria de Salud, Instituto Mexicano del Seguro Social and Instituto de Seguridad y Servicios Sociales para los Trabajadores del Estado through clinical research projects that allow the necessary evolution of medical physics into the hospital setting.

Current status and future trends of medical physics in Mexico

International Nuclear Information System (INIS)

Nieto, J Azorin

2015-01-01

Medical Physics is an area that applies the principles of physics to medicine, particularly in the prevention, diagnosis and treatment of diseases using ionizing and nonionizing radiation. The main attractive of medical physics is that it has a direct impact on the quality and safety of medical care in humans; this social component with direct implications for the population is of high value for Mexico. This paper describes the concepts of medical physics, trends and the current status of this discipline as a profession, which is directly related to the efforts of clinical research. It is also described what is, in my opinion, the future of medical physics in Mexico, emphasizing the fact that this field requires a substantial boost from universities and hospitals to recruit highly qualified young medical physicists and the support from government agencies such as Secretaria de Salud, Instituto Mexicano del Seguro Social and Instituto de Seguridad y Servicios Sociales para los Trabajadores del Estado through clinical research projects that allow the necessary evolution of medical physics into the hospital setting

Assessment of the current status of playground safety in the midwestern region of Turkey: an effort to provide a safe environment for children.

Science.gov (United States)

Uskun, Ersin; Kişioğlu, Ahmet Nesimi; Altay, Tülin; Cikinlar, Rengül; Kocakaya, Asuman

2008-01-01

This study aimed to identify and evaluate the degree of conformity to the playground standards and the level of compliance with current safety specifications of the playgrounds in the midwestern region of Turkey. An observational technique was used at a total of 57 public playgrounds. A playground safety control form was prepared based on the United States National Program for Playground Safety and the Consumer Product Safety Commission security standards, since there is no national law covering playground equipment and safety in Turkey. The study evaluated the surroundings of the playground, arrangement of equipment in the playground, and characteristics of the equipment. The percentage of playgrounds surveyed with inadequate or hard surfacing was 80.7%. Fifty-two percent of the equipment was found to be inappropriate. Equipment was higher than the recommended heights. The results of our study unfortunately point out that playgrounds for children do not meet many of the safety criteria.

Current status of neutron scattering in Thailand

International Nuclear Information System (INIS)

Kornduangkaeo, Areeratt; Pongkasem, Somchai; Putchar, Suriya; Ampornrat, Pantip; Kajornrith, Varavuth; Chamchang, Jipawat

2006-01-01

The current neutron powder diffractometer at the Thai Research Reactor-1/Modification 1 (TRR-1/M1) has been modified from the obsolete neutron diffractometer which had been used during 1968-1975. The upgraded diffractometer has medium resolution and is appropriate for studying samples with small unit cell dimensions and training university students in the field of neutron scattering. This paper describes the current activities of neutron scattering research in Thailand, the current status of a new research reactor project at Ongkarak for enlarging the perspectives of its utilization in the future as well as the organizational reformation of the Office of Atomic Energy for Peace (OAEP). (author)

Nuclear power: Status report and future prospects

International Nuclear Information System (INIS)

Budnitz, Robert J.

2016-01-01

This article reviews the current status and future prospects of commercial nuclear electric power, with emphasis on issues of safety, physical security, proliferation, and economics. Discussions of these issues are presented separately for the current operating fleet, for new reactor designs similar in size to the current fleet, and for prospective new reactors of substantially smaller size. This article also discusses the issue of expansion of commercial nuclear power into new countries. The article concludes with recommendations, related both to technical issues and policy considerations. The major implications for policy are that although the level of safety and security achieved in today's operating reactor fleet worldwide is considered broadly acceptable, some advanced designs now under development potentially offer demonstrably safer performance, and may offer improved financial performance also. Management and safety culture are vital attributes for achieving adequate safety and security, as are a strong political culture that includes an absence of corruption, an independent regulatory authority, and a separation of nuclear operation from day-to-day politics. In some countries that are now considering a nuclear-power program for the first time, careful attention to these attributes will be essential for success. - Highlights: •Current status of nuclear reactor safety and security is judged to be adequate. •Strong management and safety culture are vital to achieve adequate nuclear safety. •Advanced reactor designs offer important safety advantages. •Maintaining and strengthening international nuclear institutions is important. •Achieving nuclear safety in “newcomer” countries requires a strong political culture.

Safety considerations to avoid current-induced skin burns in MRI

International Nuclear Information System (INIS)

Knopp, M.V.; Metzner, R.; Kaick, G. van; Brix, G.; Bundesamt fuer Strahlenschutz, Oberschleissheim

1998-01-01

The safety aspects of radiological methods continue to evolve. In this paper we report on two cases of skin burns in MRI caused by induced electrical current. A second- and a third-degree skin burn occurred during imaging in a 1.5 T system. The electromagnetic radiofrequency field inadvertently led to electrical currents caused by a conducting loop through the extremities and trunk. Skin burns induced by electrical current may occur in extremely rare cases even with standard MR imaging protocols operating within all current safety guidelines by inadvertently forming a closed conducting loop. By avoiding focal skin to skin contact of the extremities, this extremely rare adverse event can be avoided. (orig.) [de

Dark Matter Detection: Current Status

International Nuclear Information System (INIS)

Akerib, Daniel S.

2011-01-01

Overwhelming observational evidence indicates that most of the matter in the Universe consists of non-baryonic dark matter. One possibility is that the dark matter is Weakly-Interacting Massive Particles (WIMPs) that were produced in the early Universe. These relics could comprise the Milky Way's dark halo and provide evidence for new particle physics, such as Supersymmetry. This talk focuses on the status of current efforts to detect dark matter by testing the hypothesis that WIMPs exist in the galactic halo. WIMP searches have begun to explore the region of parameter space where SUSY particles could provide dark matter candidates.

Safety and regulation in the use of radiation in medicine: status in India and future perspective

International Nuclear Information System (INIS)

Gopalakrishnan, A.; Parthasarathy, K.S.; Ghosh, P.K.

1996-01-01

This paper briefly reviews the history of radiation protection, regulatory aspects and the status of radiation safety in radiotherapy, radiodiagnosis and nuclear medicine in India. The revised basic safety standards and the future developments envisaged in the safety and regulation are also mentioned. (author). 24 refs., 8 tabs

Environmental Health and Safety Status of Schools: Case Study in Paveh City of Kermanshah Province

Directory of Open Access Journals (Sweden)

Seyyed Alireza Mousavi

2017-10-01

Full Text Available Background & Aims of the Study: A most part of children time is spent in a school environment. Important part of the basic mission of schools is promoting the health and safety. So assessing the existing conditions is an important factor in promotion and this study conducted to investigate the environmental health and safety status of Paveh city schools in Kermanshah province. Materials & Methods: This is a descriptive-cross sectional study and has performed in Paveh city of Kermanshah province. The study population consisted of primary, secondary and high schools of Paveh city. Data has been collated by referring to schools, direct observation and completion of environmental health and safety checklist. Schools conditions were determined according to the environmental health and safety checklist in desirable, semi-desirable and undesirable. The collected data were analyzed using Excel software, and data means and frequencies sign in tables and were drawn by charts. Results: From the 28 schools have visited 35.6% of school building is old and 63.7% of school building is new built. In the study of all schools in 8% of schools environmental health status were undesirable and in 21% semi-desirable and in 71% were desirable, also safety status in 4% of all schools were undesirable  and in 21% semi-desirable and in 75% were desirable. Undesirable safety conditions related to adjacent to waste accumulation areas, brick buildings without footing beam, inappropriate distance of  first row bench from the boards, lack of green spaces Conclusion: Given the importance of safety in schools, more attention should be paid to this issue. It is essential to compliance with the principles of health and safety in schools, also any consideration and action in this field can be effective in reducing the risk of many related health problems.

ATM in Europe: analysis of current status

DEFF Research Database (Denmark)

1999-01-01

This deliverable provides an overview of the current status of the European market for ATM services. The offer of ATM services by principal operators in Belgium, Denmark, Finland, France, Germany, Greece, Italy, Norway, Portugal, Spain, Sweden and United Kingdom is described. In addition, a number...... of international providers of ATM in Europe are presented....

Status of School Safety and Security among Elementary Schools in the Fifth Class Municipality

Directory of Open Access Journals (Sweden)

Cresente E. Glariana

2015-12-01

Full Text Available This study attempted to determine the status of school safety and security in terms of the school sites, school playground, school canteen services, water safety, fire safety, campus security, building security, and sanitary facilities situation in eight (8 elementary schools in Libertad town. The descriptive survey was used to find out the status of school safety and security in the elementary schools of Libertad, Misamis Oriental. A checklist on the standards of facilities as implemented by the Department of Education was used to gather the data. Checklist was based from the 2010 Educational Facilities Manual. Evaluation based on the checklist showed that some of standards on 2010 Educational Facilities Manual were not observed. The schools have not complied with the requirements and specifications. The evaluation showed further that most of the schools did not comply within the standards set by the 2010 Educational Facilities Manual. School authorities may review the standards in the 2010 Educational Facilities Manual. The school should try to meet the standard to ensure safety and security of the pupils. Action plan may be prepared to be implemented in case of emergency.

Current status of accreditation for drug testing in hair.

Science.gov (United States)

Cooper, Gail; Moeller, Manfred; Kronstrand, Robert

2008-03-21

At the annual meeting of the Society of Hair Testing in Vadstena, Sweden in 2006, a committee was appointed to address the issue of guidelines for hair testing and to assess the current status of accreditation amongst laboratories offering drug testing in hair. A short questionnaire was circulated amongst the membership and interested parties. Fifty-two responses were received from hair testing laboratories providing details on the amount and type of hair tests they offered and the status of accreditation within their facilities. Although the vast majority of laboratories follow current guidelines (83%), only nine laboratories were accredited to ISO/IEC 17025 for hair testing. A significant number of laboratories reporting that they were in the process of developing quality systems with a view to accrediting their methods within 2-3 years. This study provides an insight into the status of accreditation in hair testing laboratories and supports the need for guidelines to encourage best practice.

Current status of light water reactor and Hitachi's technical improvements for BWR

International Nuclear Information System (INIS)

Miki, Minoru; Ohki, Arahiko.

1984-01-01

Gradual technical improvements in Japan over the years has improved the reliability of light water reactors, and has achieved the highest capacity factor level in the world. Commercial operation of Fukushima 2-2 (1,100 MW) of the Tokyo Electric Power Co. was started in February, 1984, as the first standardized BWR base plant, ushering in a new age of domestic light water reactor technology. The ABWR (1,300 MW class) has been developed as Japan's next generation light water reactor, with construction aimed at the latter half of the 1980's. Hitachi's extensive efforts range from key nuclear equipment to various related robots, directed at improving safety, reliability, and the capacity factor, while reducing radiation exposure. This paper presents an outline of Hitachi's participation in the light water reactor's improvement and standardization, and the current status of our role in the international cooperation plan for the ABWR. (author)

Status of safety in nuclear facilities - 2012. AREVA General Inspectorate Annual report

International Nuclear Information System (INIS)

2013-05-01

After a message from the Areva's Chief Executive Officer and a message from the senior Vice President of safety, health, security, sustainable development, a text by the inspector general comments the key safety results (events, dose levels, radiological impacts), the inspection findings, the areas of vigilance (relationship with the ASN, the management of the criticality risk, and facility compliance), some significant topics after the Fukushima accident. Then this report addresses the status of nuclear safety and radiation protection in the group's facilities and operations. It more specifically addresses the context and findings (lessons learned from the inspections, operating experience from event, employee radiation monitoring, environmental monitoring), crosscutting processes (safety management, controlling facility compliance, subcontractor guidance and management, crisis management), specific risks (criticality risk, fire hazards, transportation safety, radioactive waste management, pollution prevention, liability mitigation and dismantling), and areas for improvement and outlook

International laser-safety regulations: a status update

Science.gov (United States)

Weiner, Robert M.

1990-07-01

There is an increase in international laser safety requirements as part of the emphasis on world-wide standardization of products and regulations. In particular the documents which will evolve from the 1992 consolidation efforts of the European Community (EC) will impact both laser manufacturers and users. This paper provides a discussion of the current status of the various laser radiation standards. NORTH AMERICAN REQUIREMENTS United States Requirements on manufacturers from the Food and Drug Administration (FDA) have been in effect since 1975. The Center for Devices and Radiological Health (CDRH) within that agency ensures that these mandatory requirements [1] are satisfied. The CDRH regulations include the division of products into classes depending on their potential for hazard criteria for power measurement and requirements for product features labels and manuals and records and reports. Manufacturers must test products and certify that they comply with the CDRH requirements. User requirements are found in a standard published by the American National Standards Institute (ANSI) and in requirements from several individual states. Specific ANSI standards have also been published for fiber communications systems [34] and for lasers in medical applications [35]. Please note that the Appendix includes additional information on the standards discussed in this paper including sources for obtaining the documents. Canada In the past Canada has had requirements for two specified product categories (bar code scanners and educational lasers) [26 These will be replaced

Aviation Safety Program: Weather Accident Prevention (WxAP) Project Overview and Status

Science.gov (United States)

Nadell, Shari-Beth

2003-01-01

This paper presents a project overview and status for the Weather Accident Prevention (WxAP) aviation safety program. The topics include: 1) Weather Accident Prevention Project Background/History; 2) Project Modifications; 3) Project Accomplishments; and 4) Project's Next Steps.

Cyclotron facilities in Brazil: Current status and licensing aspects

International Nuclear Information System (INIS)

Facure, A.; Carvalho, S.M.; Di Prinzio, R.; Silveira, C.S.; Gasparian, P.B.R.; Franca, W.F.

2017-01-01

Positron Emission Tomography (PET) is a highly sensitive and accurate nuclear medicine imaging technology but the major problem of this technique is the use of radioisotopes with short half-life, less than two hours. The production and selling of short half-life radioisotopes used to be monopoly of the Brazilian Government. In 2006, a Constitutional Amendment revoked the state monopoly due to the need for the use of short half-life radioisotopes in nuclear medicine centers very far from the government production facilities. The aim of this study is to describe the current status of short half-life radioisotopes production in Brazil and discuss some licensing process. In Brazil, as has been occurring worldwide, the number of nuclear medicine centers is increasing. Currently there are 123 services performing PET scans in Brazil. There are 14 cyclotrons operating in Brazil. The type of licensing process conducted in Brazil does not take into account the population density of each state, with a free competition model being adopted. Because of this there is a lot of equipment concentrated in the Southeast and no cyclotrons operating in the Northern part of the country. One of the biggest obstacles during the licensing process is the designation of qualified personnel as operation workers and radiation safety officers. The number of cyclotron accelerators and PET/CT equipment increased in recent years. However, a number of external factors such as the distance from the nuclear medicine centers, and qualified personnel have proved crucial for the economic viability of this type of facility. (author)

Cyclotron facilities in Brazil: Current status and licensing aspects

Energy Technology Data Exchange (ETDEWEB)

Facure, A.; Carvalho, S.M.; Di Prinzio, R.; Silveira, C.S.; Gasparian, P.B.R.; Franca, W.F., E-mail: facure@cnen.gov.br [Comissao Nacional de Energia Nuclear (CNEN), Rio de Janeiro, RJ (Brazil)

2017-09-01

Positron Emission Tomography (PET) is a highly sensitive and accurate nuclear medicine imaging technology but the major problem of this technique is the use of radioisotopes with short half-life, less than two hours. The production and selling of short half-life radioisotopes used to be monopoly of the Brazilian Government. In 2006, a Constitutional Amendment revoked the state monopoly due to the need for the use of short half-life radioisotopes in nuclear medicine centers very far from the government production facilities. The aim of this study is to describe the current status of short half-life radioisotopes production in Brazil and discuss some licensing process. In Brazil, as has been occurring worldwide, the number of nuclear medicine centers is increasing. Currently there are 123 services performing PET scans in Brazil. There are 14 cyclotrons operating in Brazil. The type of licensing process conducted in Brazil does not take into account the population density of each state, with a free competition model being adopted. Because of this there is a lot of equipment concentrated in the Southeast and no cyclotrons operating in the Northern part of the country. One of the biggest obstacles during the licensing process is the designation of qualified personnel as operation workers and radiation safety officers. The number of cyclotron accelerators and PET/CT equipment increased in recent years. However, a number of external factors such as the distance from the nuclear medicine centers, and qualified personnel have proved crucial for the economic viability of this type of facility. (author)

Discussion about risk-informed regulations on the nuclear safety

International Nuclear Information System (INIS)

Gu Yeyi

2008-01-01

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

Current status of JMTR refurbishment project

International Nuclear Information System (INIS)

Kaminaga, Masanori; Niimi, Motoji; Hori, Naohiko; Takahashi, Kunihiro; Kanno, Masaru; Nakagawa, Tetsuya; Nagao, Yoshiharu; Ishihara, Masahiro; Kawamura, Hiroshi

2010-02-01

The JMTR is a light water moderated and cooled, beryllium reflected tank- type reactor using LUE silicide plate-type fuels. Its thermal power is 50 MW, maximum thermal and fast neutron flux is 4x10 18 m -2 s -1 . First criticality was achieved in March 1968, and its operation was stopped from August, 2006 for the refurbishment. The refurbishment is scheduled from the beginning of FY2007 to the end of FY2010. The renewed and upgraded JMTR will be re-started from FY2011. An investigation on aged components (aged-investigation) was carried out for concrete structures of the JMTR reactor building, exhaust stack, etc., and for tanks in the primary cooling system, heat exchangers, pipes in the secondary cooling system, cooling tower, emergency generators and so on, in order to identify their integrity. The aged-investigation was carried out at the beginning of FY2007. As a result, some components were decided to replace from viewpoints of future maintenance and improvement of reliability, and some components or structures were decided to repair. A visual inspection of inner side of the pressure vessel was carried out using an underwater camera in FY2008, and no serious damage was observed. Up to now, refurbishment works are in progress according to the planned schedule. In FY2009, motors of primary cooling pumps, secondary cooling pumps, motors of drain pumps, pump in the primary water transfer line to the water purification system, beryllium reflector frame, low-voltage motor control centers are to be replaced. A nuclear instrumentation system, process control system, safety protection system and so on are to be replaced in FY2010. In this paper, current status of JMTR refurbishment project is presented. (author)

Computer codes for safety analysis

International Nuclear Information System (INIS)

Holland, D.F.

1986-11-01

Computer codes for fusion safety analysis have been under development in the United States for about a decade. This paper will discuss five codes that are currently under development by the Fusion Safety Program. The purpose and capability of each code will be presented, a sample given, followed by a discussion of the present status and future development plans

Lung cancer: Current status and prospects for the future

International Nuclear Information System (INIS)

Mountain, C.F.; Carr, D.T.

1986-01-01

This book contains 32 papers. Some of the titles are: Activation of cellular ras genes in human neoplasms; The valve of definitive radiation therapy of unresectable squamous cell carcinoma, large cell carcinoma, and adenocarcinoma of the lung; Current concepts of chemotherapy and radiotherapy for small cell lung cancer, and Current status of immunotherapy for lung cancer

Chemical Reaction Engineering: Current Status and Future Directions.

Science.gov (United States)

Dudukovic, M. P.

1987-01-01

Describes Chemical Reaction Engineering (CRE) as the discipline that quantifies the interplay of transport phenomena and kinetics in relating reactor performance to operating conditions and input variables. Addresses the current status of CRE in both academic and industrial settings and outlines future trends. (TW)

The nonparametric bootstrap for the current status model

NARCIS (Netherlands)

Groeneboom, P.; Hendrickx, K.

2017-01-01

It has been proved that direct bootstrapping of the nonparametric maximum likelihood estimator (MLE) of the distribution function in the current status model leads to inconsistent confidence intervals. We show that bootstrapping of functionals of the MLE can however be used to produce valid

Job monitoring on the WLCG scope: Current status and new strategy

International Nuclear Information System (INIS)

Andreeva, Julia; Casey, James; Gaidioz, Benjamin; Karavakis, Edward; Kokoszkiewicz, Lukasz; Lanciotti, Elisa; Maier, Gerhild; Rodrigues, Daniele Filipe Rocha Da Cuhna; Rocha, Ricardo; Saiz, Pablo; Sidorova, Irina; Boehm, Max; Belov, Sergey; Tikhonenko, Elena; Dvorak, Frantisek; Krenek, Ales; Mulac, Milas; Sitera, Jiri; Kodolova, Olga; Vaibhav, Kumar

2010-01-01

Job processing and data transfer are the main computing activities on the WLCG infrastructure. Reliable monitoring of the job processing on the WLCG scope is a complicated task due to the complexity of the infrastructure itself and the diversity of the currently used job submission methods. The paper will describe current status and the new strategy for the job monitoring on the WLCG scope, covering primary information sources, job status changes publishing, transport mechanism and visualization.

Status of generic actions items and safety analysis system of PHWR

Energy Technology Data Exchange (ETDEWEB)

Park, Joo Hwan; Min, Byung Joo

2001-05-01

This report described the review results of a GAIs(Generic Action Item) currently issued on safety analysis of PHWR(Pressurized Heavy Water Reactor) and the research activities and positions to solve the GAIs in each country which possess PHWRs. eviewing the Final Safety Analysis Report for Wolsong-2/3/4 Units, the safety analysis methodology, classification for accident scenarios, safety analysis codes, their interface, etc.. were described. From the present review report, it is intended to establish the CANDU safety analysis system by providing the better understandings and development plans for the safety analysis of PHWR. esults.

Marine current energy devices: Current status and possible future applications in Ireland

International Nuclear Information System (INIS)

Rourke, Fergal O.; Boyle, Fergal; Reynolds, Anthony

2010-01-01

There is a growing demand for the use of renewable energy technologies to generate electricity due to concerns over climate change. The oceans provide a huge potential resource of energy. Energy extraction using marine current energy devices (MCEDs) offers a sustainable alternative to conventional sources and a predictable alternative to other renewable energy technologies. A MCED utilises the kinetic energy of the tides as opposed to the potential energy which is utilised by a tidal barrage. Over the past decade MCEDs have become an increasingly popular method of energy extraction. However, marine current energy technology is still not economically viable on a large scale due to its current stage of development. Ireland has an excellent marine current energy resource as it is an island nation and experiences excellent marine current flows. This paper reviews marine current energy devices, including a detailed up-to-date description of the current status of development. Issues such as network integration, economics, and environmental implications are addressed as well as the application and costs of MCEDs in Ireland. (author)

Biosimilar drugs: Current status.

Science.gov (United States)

Kumar, Rajiv; Singh, Jagjit

2014-07-01

Biologic products are being developed over the past three decades. The expiry of patent protection for many biological medicines has led to the development of biosimilars in UK or follow on biologics in USA. This article reviews the literature on biosimilar drugs that covers the therapeutic status and regulatory guidelines. Appraisal of published articles from peer reviewed journals for English language publications, search from PubMed, and guidelines from European Medicines Agency, US Food Drug Administration (FDA) and India were used to identify data for review. Literature suggest that biosimilars are similar biological products, i.e., comparable but not identical to the reference product, are not generic version of innovator product and do not ensure therapeutic equivalence. Biosimilars present more challenges than conventional generics and marketing approval is also more complicated. To improve access, US Congress passed the Biologics Price Competition and Innovation act 2009 and US FDA allowed "abbreviated pathway" for their approval. U.S law has defined new standards and terms and EMA scientific guidelines have also set detailed approval standards. India being one of the most preferred manufacturing destinations of biosimilars, there is a need for stringent safety and regulatory guidelines. The New India Guidelines "Draft Guidelines on Similar Biologics were announced in June 2012, by Department of Biotechnology at Boston bio and available online.

Structural Learning Theory: Current Status and New Perspectives.

Science.gov (United States)

Scandura, Joseph M.

2001-01-01

Presents the current status and new perspectives on the Structured Learning Theory (SLT), with special consideration given to how SLT has been influenced by recent research in software engineering. Topics include theoretical constructs; content domains; structural analysis; cognition; assessing behavior potential; and teaching and learning issues,…

Education and training in radiation protection in Korea: Current status and improvements

International Nuclear Information System (INIS)

Son, Mi Yeon; Kim; Hyun Kee; Nam, Young Mi; Nam, Jong Soo; Lee, Ki Bog

2012-01-01

Radiation and its various industrial applications have been growing at approximately 10 percent per year for the past decade in Korea. As a result, the importance of the Education and Training (E and T) in radiation protection is of upmost importance. This paper is intended to investigate the present status of the E and T on radiation protection and safety in Korea and to draw up the improvements of the E and T courses required for building the national radiation safety infrastructure. For these purposes, the E and T data from the six major domestic organizations providing radiation protection training courses were investigated and analyzed. Each of the organizations is offering several kinds of E and T courses based on their own specific functions. These organizations have administrative facilities equipped with the latest technology for E and T in radiation protection. The E and T courses mainly cover the training courses for radiation workers, radiological emergency staff, license applicants, license holders, and regulatory staff. In 2010, a total of 58 E and T courses were carried out across six organizations. The conclusions make a number of observations highlighting challenges such as: establishing a formal feedback mechanism, introducing more practical training sessions, developing training courses tailored to the job categories and target audiences, and designing education and training courses in radiation protection that comply with current obligations as well as future requirements.

Education and training in radiation protection in Korea: Current status and improvements

Energy Technology Data Exchange (ETDEWEB)

Son, Mi Yeon; Kim; Hyun Kee; Nam, Young Mi; Nam, Jong Soo; Lee, Ki Bog [Nuclear Training and Education Center, Korea Atomic Energy Research Institute, Daejeon(Korea, Republic of)

2012-10-15

Radiation and its various industrial applications have been growing at approximately 10 percent per year for the past decade in Korea. As a result, the importance of the Education and Training (E and T) in radiation protection is of upmost importance. This paper is intended to investigate the present status of the E and T on radiation protection and safety in Korea and to draw up the improvements of the E and T courses required for building the national radiation safety infrastructure. For these purposes, the E and T data from the six major domestic organizations providing radiation protection training courses were investigated and analyzed. Each of the organizations is offering several kinds of E and T courses based on their own specific functions. These organizations have administrative facilities equipped with the latest technology for E and T in radiation protection. The E and T courses mainly cover the training courses for radiation workers, radiological emergency staff, license applicants, license holders, and regulatory staff. In 2010, a total of 58 E and T courses were carried out across six organizations. The conclusions make a number of observations highlighting challenges such as: establishing a formal feedback mechanism, introducing more practical training sessions, developing training courses tailored to the job categories and target audiences, and designing education and training courses in radiation protection that comply with current obligations as well as future requirements.

Neutrino astronomy current status, future prospects

CERN Document Server

Karle, Albrecht

2017-01-01

This review volume is motivated by the recent discovery of high-energy astrophysical neutrinos by IceCube. The aim of the book is to bring together chapters on the status of current and future neutrino observatories with chapters on the implications and possible interpretations of the present observations and their upper limits. Each chapter is a mini-review of one aspect of the subject by leading experts. Taken together, the chapters constitute an up-to-date review of high-energy astrophysical neutrinos and their potential sources.

Undocumented status as a social determinant of occupational safety and health: The workers' perspective.

Science.gov (United States)

Flynn, Michael A; Eggerth, Donald E; Jacobson, C Jeffrey

2015-11-01

Undocumented immigration to the United States has grown dramatically over the past 25 years. This study explores undocumented status as a social determinant of occupational health by examining its perceived consequences on workplace safety of Latino immigrants. Guided by the Theory of Work Adjustment, qualitative analysis was conducted on transcripts from focus groups and individual interviews conducted with a convenience sample of Latino immigrant workers. Participants reported that unauthorized status negatively impacted their safety at work and resulted in a degree of alienation that exceeded the specific proscriptions of the law. Participants overwhelming used a strategy of disengagement to cope with the challenges they face as undocumented immigrants. This study describes the complex web of consequences resulting from undocumented status and its impact on occupational health. This study presents a framework connecting the daily work experiences of immigrants, the coping strategy of disengagement, and efforts to minimize the impact of structural violence. © 2015 Wiley Periodicals, Inc.

Undocumented Status as a Social Determinant of Occupational Safety and Health: The Workers’ Perspective

Science.gov (United States)

Flynn, Michael A.; Eggerth, Donald E.; Jacobson, C. Jeffrey

2015-01-01

Background Undocumented immigration to the United States has grown dramatically over the past 25 years. This study explores undocumented status as a social determinant of occupational health by examining its perceived consequences on workplace safety of Latino immigrants. Methods Guided by the Theory of Work Adjustment, qualitative analysis was conducted on transcripts from focus groups and individual interviews conducted with a convenience sample of Latino immigrant workers. Results Participants reported that unauthorized status negatively impacted their safety at work and resulted in a degree of alienation that exceeded the specific proscriptions of the law. Participants overwhelming used a strategy of disengagement to cope with the challenges they face as undocumented immigrants. Conclusion This study describes the complex web of consequences resulting from undocumented status and its impact on occupational health. This study presents a framework connecting the daily work experiences of immigrants, the coping strategy of disengagement, and efforts to minimize the impact of structural violence. PMID:26471878

Current status and installation of dental PACS

International Nuclear Information System (INIS)

Park, Chang Seo; Kim, Kee Deog; Park, Hyok; Jeong, Ho Gul

2004-01-01

Picture Archiving and Communication System (PACS) is difficult to implement in the best of situations, but evidence is growing that the benefits are significant. The aims of this study are to analyze the current status of full PACS and establish successful installation standard of dental PACS. Materials and Methods were based on the investigation of current working status and installation standard of PACS, and observation of variable issues to installation of dental PACS. By September 30, 2004, full PACS implementations in their facilities were 88.1% in specialized general hospitals (37 installations out of total 42 hospitals), 59.8% in general hospitals (144 installations out of total 241 hospitals), 12.3% in medical hospitals (116 installations out of total 941 hospitals) and 3.6% in dental hospitals (4 installations out of total 110 hospitals). Only 4 university dental hospitals currently have installed and are operating full PACS. Major obstacle to wide spread of dental PACS is initial high investments. Clinical environments of dental PACS differed from medical situation. Because of characteristic dental practice, the initial investments for dental PACS are generally much greater than those of medical PACS. Also new economic crisis makes users scruple. The best way to overcome these limitations is to establish an economic installation standard for dental PACS. Also the clear technical communication between the customer and the supplier before both sides are committed to the obstacles are critical to its success.

Current status of the PBMR licensing project

International Nuclear Information System (INIS)

Mysen, A.; Clapisson, G.A.; Metcalf, P.E.

2000-01-01

The CNS is currently reviewing the PBMR conceptual design from a licensibility point of view. The PBMR concept is based on a High Temperature Gas Cooled Reactor - pebble bed reactor type. It is anticipated that the PBMR design will rely on inherent safety characteristics to contain fission products within fuel over the full range of design basis events. This feature combined with the high temperature integrity of the fuel and structural graphite, allows the safe use of a high coolant temperature, which allows consideration of the future development of this reactor for non-electrical applications of nuclear heat for industrial use. The CNS licensing approach requires that the licensing and design basis of the plant should respect prevailing international norms and practices and that a quantitative risk assessment should demonstrate compliance with the CNS fundamental safety standards. The first stage of the licensing process is now ongoing; this is a pre-application phase, which will result in a statement on licensibility being issued. Identification of the specific documentation requirements and information needed is required across every step of the licensing process. Top level regulatory requirements have been established for the PBMR. They include the CNS fundamental safety standard and basic licensing criteria, which describes requirements on licensees of nuclear installations regarding risk assessment and compliance with the safety criteria and define classification of licensing basis events. (author)

Status of food safety management activities in fresh produce companies in the European Union and beyond

NARCIS (Netherlands)

Kirezieva, K.; Luning, P.A.; Jacxsens, L.; Uyttendaele, M.

2015-01-01

An increase in food safety incidences linked to fresh produce has been reported in recent years. Imports from the transitional economies have often been blamed for these incidences. However, limited information is available about the status of food safety management activities in companies in

Association between insurance status and patient safety in the lumbar spine fusion population.

Science.gov (United States)

Tanenbaum, Joseph E; Alentado, Vincent J; Miller, Jacob A; Lubelski, Daniel; Benzel, Edward C; Mroz, Thomas E

2017-03-01

Lumbar fusion is a common and costly procedure in the United States. Reimbursement for surgical procedures is increasingly tied to care quality and patient safety as part of value-based reimbursement programs. The incidence of adverse quality events among lumbar fusion patients is unknown using the definition of care quality (patient safety indicators [PSI]) used by the Centers for Medicare and Medicaid Services (CMS). The association between insurance status and the incidence of PSI is similarly unknown in lumbar fusion patients. This study sought to determine the incidence of PSI in patients undergoing inpatient lumbar fusion and to quantify the association between primary payer status and PSI in this population. A retrospective cohort study was carried out. The sample comprised all adult patients aged 18 years and older who were included in the Nationwide Inpatient Sample (NIS) that underwent lumbar fusion from 1998 to 2011. The incidence of one or more PSI, a validated and widely used metric of inpatient health-care quality and patient safety, was the primary outcome variable. The NIS data were examined for all cases of inpatient lumbar fusion from 1998 to 2011. The incidence of adverse patient safety events (PSI) was determined using publicly available lists of the International Classification of Diseases, Ninth Revision, Clinical Modification diagnosis codes. Logistic regression models were used to determine the association between primary payer status (Medicaid and self-pay relative to private insurance) and the incidence of PSI. A total of 539,172 adult lumbar fusion procedures were recorded in the NIS from 1998 to 2011. Patients were excluded from the secondary analysis if "other" or "missing" was listed for primary insurance status. The national incidence of PSI was calculated to be 2,445 per 100,000 patient years of observation, or approximately 2.5%. In a secondary analysis, after adjusting for patient demographics and hospital characteristics, Medicaid

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

International Nuclear Information System (INIS)

2009-06-01

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

Special Education History, Current Status and Future: India

Science.gov (United States)

Antony, Pavan John

2013-01-01

Education of all children in public schools, including those with disabilities, continues to be an unresolved issue in many countries around the globe. While education of all children is mandated by law and considered a basic human right in many countries, the current status of implementation varies. India, for example, is an ancient country that…

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.

Fukushima Daiichi Status Report

International Nuclear Information System (INIS)

2012-01-01

The IAEA issues regular status reports to the public on the current status of the Fukushima Daiichi Nuclear Power Plant, including information on environmental radiation monitoring, the status of workers, and current conditions on-site at the plant. The information cited in this report is compiled from official Japanese sources, including the Ministry of Economy, Trade and Industry (METI), the Nuclear and Industrial Safety Agency (NISA), the Ministry of Education, Culture, Sports, Science and Technology (MEXT), the Ministry of Land, Infrastructure, Transport and Tourism (MLIT), the Ministry of Health, Labour and Welfare (MHLW) and the Ministry of Foreign Affairs (MOFA) through the Japanese Permanent Mission in Vienna and the Cabinet's Office of the Prime Minister. Information is also provided by the Tokyo Electric Power Company (TEPCO), the operator of the Fukushima Daiichi Nuclear Power Plant.

Current safety issues related to research reactor operation

International Nuclear Information System (INIS)

Alcala-Ruiz, F.

2000-01-01

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

Current status of agricultural extension services for market oriented ...

African Journals Online (AJOL)

Current status of agricultural extension services for market oriented agricultural development in Ethiopia: Results from a household baseline ... Log in or Register to get access to full text downloads. ... http://dx.doi.org/10.4314/afrrev.v10i3.1.

The ENIQ pilot study: current status

Energy Technology Data Exchange (ETDEWEB)

Lemaitre, P; Eriksen, B; Crutzen, S [European Commission, DG Joint Research Centre, Petten (Netherlands); Hansch, M [Preussische Elektrizitaets-AG (Preussenelektra), Hannover (Germany); Whittle, J [AEA Technology, Warrington (United Kingdom)

1998-11-01

A pilot study is currently being carried out by ENIQ (European Network for Inspection Qualification) in order to explore the issues involved in inspection qualification applied along the general principles of the European methodology. The components selected for the pilot study are austenitic pipe to pipe and pipe to elbows welds typical of those in BWR recirculation loops. A range of defect parameters has been defined. A suitable inspection procedure designed to find the designated defects will be applied to geometrically representative test pieces. The procedure/equipment will be qualified through open trials and technical justification. The personnel qualification will be done in a blind way. Once all features of the inspection system will have been qualified an in-service inspection will be simulated in order to test the feasibility of the qualification approach followed. In this paper the current status of this pilot study is discussed. (orig.)

Influence of UV Treatment on the Food Safety Status of a Model Aquaponic System

Directory of Open Access Journals (Sweden)

Sai Deepikaa Elumalai

2017-01-01

Full Text Available Few microbial studies in aquaponics, a growing trend in food production, have been conducted to determine food safety status. The aim of this study was to determine the food safety status and the effectiveness of ultraviolet treatment (15 W, luminous flux of 900 lm as a food safety intervention in reducing the microbial loads of the water system in a model aquaponic unit growing lettuce, basil, and barramundi (Australian Sea Bass. Sweet basil, bibb lettuce, water samples, and fish swabs were collected throughout the 118-day production period, and microbial analysis was conducted in triplicate for the presence of E. coli O157:H7, Salmonella spp., and the prevalence of aerobic plate counts (APC, coliforms, and fecal coliforms in these systems. Absence of foodborne pathogens was confirmed using ELISA technology and enumeration through petrifilms (coliform/E. coli. A significant increase was observed in aerobic plate counts over the trial period (1 to 3 log10 CFU·mL−1 in the presence and absence of UV (p > 0.05. Ultraviolet treatment did not significantly reduce the APC or coliform counts when compared to the control system samples. Future work should focus on improving the unit design, the evaluation of bio-solid filtration, and other food safety interventions.

The status of nuclear safety of Ukrainian NPPS and evaluations by ASSET methodology

International Nuclear Information System (INIS)

Koltakov, V.

1997-01-01

The presentation discusses the following issues: nuclear power plants and research reactors; electricity production and operating personnel; status of nuclear safety at NPPs of Ukraine; operation of Ukrainian NPPs; violations of NPPs operation; short review of ASSET missions; experience of feedback process. Figs, tabs

The status of nuclear safety of Ukrainian NPPS and evaluations by ASSET methodology

Energy Technology Data Exchange (ETDEWEB)

Koltakov, V [State Scientific and Technical Center on Nuclear and Radiational Safety, Kiev (Ukraine)

1997-10-01

The presentation discusses the following issues: nuclear power plants and research reactors; electricity production and operating personnel; status of nuclear safety at NPPs of Ukraine; operation of Ukrainian NPPs; violations of NPPs operation; short review of ASSET missions; experience of feedback process. Figs, tabs.

Current status of pediatric minimal access surgery at Sultan Qaboos ...

African Journals Online (AJOL)

Keywords: current status, laparoscopy, minimal access surgery, thoracoscopy. Departments of ... Materials and methods ... procedures, the open technique was used for the creation ... operated for bilateral inguinal herniotomy had recurrence.

Current status of accident analysis for Korean HCCR TBS

Energy Technology Data Exchange (ETDEWEB)

Ahn, Mu-Young, E-mail: myahn74@nfri.re.kr [National Fusion Research Institute, Daejeon (Korea, Republic of); Jin, Hyung Gon [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of); Cho, Seungyon [National Fusion Research Institute, Daejeon (Korea, Republic of); Lee, Dong Won [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of); Ku, Duck Young; Park, Yi-Hyun; Kim, Chang-Shuk; Lee, Youngmin [National Fusion Research Institute, Daejeon (Korea, Republic of)

2014-10-15

Korea has decided to test Helium Cooled Ceramic Reflector (HCCR) Test Blanket Module (TBM) in ITER and design of the TBM with its ancillary systems, i.e. Test Blanket System (TBS), is under progress. Since the TBM is operated at elevated temperature with high heat load, safety consideration is essential in design procedure. In this paper, preliminary accident analysis results for the current HCCR TBS design on selected scenarios are presented as an important part of safety assessments. To simulate transient thermo-hydraulic behavior, GAMMA-FR code which has been developed in Korea for fusion applications was used. The main cooling and tritium extraction circuit systems, as well as the TBM, were simulated and the main components in the TBS were modeled as the associated heat structures. The important accident scenarios were produced and summarized in the paper considering the HCCR TBS design and ITER conditions, which cover in-vessel Loss Of Coolant Accident (LOCA), in-box LOCA, ex-vessel LOCA, Loss Of Flow Accident (LOFA), Loss Of Heat Sink Accident (LOHSA) and purge pipe rupture case. The accident analysis based on the selected scenarios was performed and it was found that the current design of the HCCR TBS meets the thermo-hydraulic safety requirements.

Current status of accident analysis for Korean HCCR TBS

International Nuclear Information System (INIS)

Ahn, Mu-Young; Jin, Hyung Gon; Cho, Seungyon; Lee, Dong Won; Ku, Duck Young; Park, Yi-Hyun; Kim, Chang-Shuk; Lee, Youngmin

2014-01-01

Korea has decided to test Helium Cooled Ceramic Reflector (HCCR) Test Blanket Module (TBM) in ITER and design of the TBM with its ancillary systems, i.e. Test Blanket System (TBS), is under progress. Since the TBM is operated at elevated temperature with high heat load, safety consideration is essential in design procedure. In this paper, preliminary accident analysis results for the current HCCR TBS design on selected scenarios are presented as an important part of safety assessments. To simulate transient thermo-hydraulic behavior, GAMMA-FR code which has been developed in Korea for fusion applications was used. The main cooling and tritium extraction circuit systems, as well as the TBM, were simulated and the main components in the TBS were modeled as the associated heat structures. The important accident scenarios were produced and summarized in the paper considering the HCCR TBS design and ITER conditions, which cover in-vessel Loss Of Coolant Accident (LOCA), in-box LOCA, ex-vessel LOCA, Loss Of Flow Accident (LOFA), Loss Of Heat Sink Accident (LOHSA) and purge pipe rupture case. The accident analysis based on the selected scenarios was performed and it was found that the current design of the HCCR TBS meets the thermo-hydraulic safety requirements

Current status and future prospects on nuclear industry in Korea

International Nuclear Information System (INIS)

Lee, Joongjae

2006-01-01

It is ny great pleasure to have this chance of speaking at twenty-first KAIF/KNS Annual Conference, with the subject of the current status and future prospects of nuclear industry in Korea. As you all know, since the start of operation in Obninsk, the former Soviet Union, on June 26th, 1954, nuclear generation in the world has expanded continuously for the past 50 years. In 1973, when the first oil crisis hit the world, there were 147 nuclear power plants in operation, supplying only 0.8% of the world energy demand. About 30 years later, by the end of last year, 443 plants were in operation in 32 countries, supplying about 16% of the world power demand. Nuclear power generation is greatly contributing to the energy security of many countries and preservation of global environments. Recently, countries all over the world are becoming aware of the values and importance of nuclear energy which can help respond to energy crises caused by a sharp rise in oil prices and protect the earth from global warming. Due to its high energy density and ability to secure fuel supply at a lower cost, in addition to its cleanliness resulting from almost no emission of greenhouse gases, nuclear power generation is the practical alternative for energy security and the prevention of global warming. However, in the rapidly changing 21st century, the nuclear industries of the world, as well as Korea, are facing more challenges than ever before. The political and social disputes on nuclear generation are continuing while we all are facing urgent challenges, including the concerns about the safety of nuclear generation, procuring site to build nuclear power plants, and the improvement of competitiveness. Please allow me to remind you that it is very important for the world's nuclear societies to cooperate together in order to overcome diverse difficulties along our path and to contribute to the development of mankind and preservation of natural environments with nuclear power as a

Current status of low energy EB machine

International Nuclear Information System (INIS)

Toshiro Nishikimi; Shuichi Taniguchi; Kenichi Mizusawa

1999-01-01

Electron beam processing systems have been in use in a variety of applications such as curing of paints and printing inks, crosslinking of PE products, treating of rubber tire and so on. Low energy electron processing systems have become popular as self-shielded machines, which are compact and easy to use and do not require special facility as an irradiation room. This manuscript introduces the status of low energy EB (electron beam) machine through Nissin's products current

Current State of Dental Education: Executive Summary.

Science.gov (United States)

Formicola, Allan J

2017-08-01

This executive summary for Section 1 of the "Advancing Dental Education in the 21 st Century" project provides a composite picture of information from 12 background articles on the current state of dental education in the United States. The summary includes the following topics: the current status of the dental curriculum, the implications of student debt and dental school finances, the expansion of enrollment, student diversity, pre- and postdoctoral education, safety net status of dental school clinics, and trends in faculty.

Regression analysis of informative current status data with the additive hazards model.

Science.gov (United States)

Zhao, Shishun; Hu, Tao; Ma, Ling; Wang, Peijie; Sun, Jianguo

2015-04-01

This paper discusses regression analysis of current status failure time data arising from the additive hazards model in the presence of informative censoring. Many methods have been developed for regression analysis of current status data under various regression models if the censoring is noninformative, and also there exists a large literature on parametric analysis of informative current status data in the context of tumorgenicity experiments. In this paper, a semiparametric maximum likelihood estimation procedure is presented and in the method, the copula model is employed to describe the relationship between the failure time of interest and the censoring time. Furthermore, I-splines are used to approximate the nonparametric functions involved and the asymptotic consistency and normality of the proposed estimators are established. A simulation study is conducted and indicates that the proposed approach works well for practical situations. An illustrative example is also provided.

Helicopter Rotor Noise Prediction: Background, Current Status, and Future Direction

Science.gov (United States)

Brentner, Kenneth S.

1997-01-01

Helicopter noise prediction is increasingly important. The purpose of this viewgraph presentation is to: 1) Put into perspective the recent progress; 2) Outline current prediction capabilities; 3) Forecast direction of future prediction research; 4) Identify rotorcraft noise prediction needs. The presentation includes an historical perspective, a description of governing equations, and the current status of source noise prediction.

Nuclear safety in Slovak Republic. Safety analysis reports for WWER 440 reactors

International Nuclear Information System (INIS)

Rohar, S.

1999-01-01

Implementation of nuclear power program is connected to establishment of regulatory body for safe regulation of siting, construction, operation and decommissioning of nuclear installations. Licensing being one of the most important regulatory surveillance activity is based on independent regulatory review and assessment of information on nuclear safety for particular nuclear facility. Documents required to be submitted to the regulatory body by the licensee in Slovakia for the review and assessment usually named Safety Analysis Report (SAR) are presented in detail in this paper. Current status of Safety Analysis Reports for Bohunice V-1, Bohunice V-2 and Mochovce NPP is shown

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

International Nuclear Information System (INIS)

2009-09-01

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

Current status of radiation treatment of water and wastewater

International Nuclear Information System (INIS)

Pikaev, A.K.

1997-01-01

This is a brief review of the current status of radiation treatment of surface water, groundwater, wastewaters, and sewage sludges. Sources of ionizing radiation, and combination radiation methods for purification are described in some detail. Special attention is paid to pilot and industrial facilities. (author)

Status of the EU test blanket systems safety studies

International Nuclear Information System (INIS)

Panayotov, Dobromir; Poitevin, Yves; Ricapito, Italo; Zmitko, Milan

2015-01-01

Highlights: • TBS safety demonstration files. • Safety functions and related design features – detailed TBS components classifications. • Nuclear analyses, radiation shielding and protection. • TBS radiological waste management strategy and categorization. • Selection and definition of reference accidents scenarios and accidents analyses. - Abstract: The European joint undertaking for ITER and the development of fusion energy (‘Fusion for Energy’ – F4E) provides the European contributions to the ITER international fusion energy research project. Among others it includes also the development, design, technological demonstration and implementation of the European test blanket systems (TBS) in ITER. Currently two EU TBS designs are in the phase of conceptual design – helium-cooled lithium-lead (HCLL) and helium-cooled pebble-bed (HCPB). Safety demonstration is an important part of the work devoted to the achievement of the next key project milestone the conceptual design review. The paper reveals the details of the work on EU TBS safety performed in the last couple of years: update of the TBS safety demonstration files; safety functions and related design features; detailed TBS components classifications; nuclear analyses, radiation shielding and protection; TBS radiological waste management strategy and categorization; selection and definition of reference accidents scenarios, and accidents analyses. Finally the authors share the information on on-going and planned future EU TBS safety activities.

Status of the EU test blanket systems safety studies

Energy Technology Data Exchange (ETDEWEB)

Panayotov, Dobromir, E-mail: dobromir.panayotov@f4e.europa.eu; Poitevin, Yves; Ricapito, Italo; Zmitko, Milan

2015-10-15

Highlights: • TBS safety demonstration files. • Safety functions and related design features – detailed TBS components classifications. • Nuclear analyses, radiation shielding and protection. • TBS radiological waste management strategy and categorization. • Selection and definition of reference accidents scenarios and accidents analyses. - Abstract: The European joint undertaking for ITER and the development of fusion energy (‘Fusion for Energy’ – F4E) provides the European contributions to the ITER international fusion energy research project. Among others it includes also the development, design, technological demonstration and implementation of the European test blanket systems (TBS) in ITER. Currently two EU TBS designs are in the phase of conceptual design – helium-cooled lithium-lead (HCLL) and helium-cooled pebble-bed (HCPB). Safety demonstration is an important part of the work devoted to the achievement of the next key project milestone the conceptual design review. The paper reveals the details of the work on EU TBS safety performed in the last couple of years: update of the TBS safety demonstration files; safety functions and related design features; detailed TBS components classifications; nuclear analyses, radiation shielding and protection; TBS radiological waste management strategy and categorization; selection and definition of reference accidents scenarios, and accidents analyses. Finally the authors share the information on on-going and planned future EU TBS safety activities.

Safety and pharmacokinetics of intravenous levetiracetam infusion as add-on in status epilepticus

NARCIS (Netherlands)

Uges, Joris W F; van Huizen, Marc D; Engelsman, Jeroen; Wilms, Erik B; Touw, Daniel J; Peeters, Els; Vecht, Charles J

PURPOSE: To evaluate the feasibility and safety of intravenous (iv) levetiracetam (LEV) added to the standard therapeutic regimen in adults with status epilepticus (SE), and as secondary objective to assess a population pharmacokinetic (PK) model for ivLEV in patients with SE. METHODS: In 12 adults

[Current status and prospects of gene doping detection].

Science.gov (United States)

Wang, Wenjun; Zhang, Sichun; Xu, Jingjuan; Xia, Xinghua; Tian, Yaping; Zhang, Xinrong; Chen, Hong-Yuan

2008-07-01

The fast development of biotechnology promotes the development of doping. From recombinant protein to gene doping, there is a great challenge to their detection. The improvement of gene therapy and potential to enhance athletic performance open the door for gene doping. After a brief introduction of the concept of gene doping, the current status and prospects of gene doping detection are reviewed.

Current status of radiation safety of disposal facility in the Republic of Moldova and measures of its improvement

International Nuclear Information System (INIS)

Zaharia, G.

2000-01-01

The infrastructure and waste management safety in the Republic of Moldova is presented. The current situation in the waste disposal facility is described. The radioactive waste inventory shows a total activity of 16.4 TBq. The radiological survey of soils at the CRWDF show a significant increase of the contamination by 226 Ra and 90 Sr at depths 3 - 5.5 m, considered as an accidental situation provoked by the disintegration of the facility protective walls. Measures for the prevention of further contamination and ground water are discussed. Construction of a new radioactive waste shallow land disposal facility on the site combined with some engineering improvements of the site is considered the best solution. Some problems of the waste management in the country are presented

Distal protection in cardiovascular medicine: current status.

Science.gov (United States)

Ali, Onn Akbar; Bhindi, Ravinay; McMahon, Aisling C; Brieger, David; Kritharides, Leonard; Lowe, Harry C

2006-08-01

Iatrogenic and spontaneous downstream microembolization of atheromatous material is increasingly recognized as a source of cardiovascular morbidity and mortality. Devising ways of reducing this distal embolization using a variety of mechanical means--distal protection--is currently under intense and diverse investigation. This review therefore summarizes the present status of distal protection. It examines the problem of distal embolization, describes the available distal protection devices, reviews those areas of cardiovascular medicine where distal protection devices are being investigated, and discusses potential future developments.

Safety first. Status reports on the IAEA's safety standards

International Nuclear Information System (INIS)

Webb, G.; Karbassioun, A.; Linsley, G.; Rawl, R.

1998-01-01

Documents in the IAEA's Safety Standards Series known as RASS (Radiation Safety Standards) are produced to develop an internally consistent set of regulatory-style publications that reflects an international consensus on the principles of radiation protection and safety and their application through regulation. In this article are briefly presented the Agency's programmes on Nuclear Safety Standards (NUSS), Radioactive Waste Safety Standards (RADWASS), and Safe Transport of Radioactive Materials

Regulatory assessment of safety culture in nuclear organisations - current trends and challenges

International Nuclear Information System (INIS)

Tronea, M.

2010-01-01

The paper gives an overview of the current practices in the area of regulatory assessment of safety culture in nuclear organisations and of the associated challenges. While the assessment and inspection procedures currently in use by regulatory authorities worldwide are directed primarily at verifying compliance with the licensing basis, there is a recognised need for a more systematic approach to the identification, collection and review of data relevant to the safety culture in licensees' organisations. The paper presents a proposal for using the existing regulatory inspection practices for gathering information relevant to safety culture and for assessing it in an integrated manner. The proposal is based on the latest requirements and guidance issued by the International Atomic Energy Agency (IAEA) on management systems for nuclear facilities and activities, particularly as regards the attributes needed for a strong nuclear safety culture. (author)

Virtual reality simulation for construction safety promotion.

Science.gov (United States)

Zhao, Dong; Lucas, Jason

2015-01-01

Safety is a critical issue for the construction industry. Literature argues that human error contributes to more than half of occupational incidents and could be directly impacted by effective training programs. This paper reviews the current safety training status in the US construction industry. Results from the review evidence the gap between the status and industry expectation on safety. To narrow this gap, this paper demonstrates the development and utilisation of a training program that is based on virtual reality (VR) simulation. The VR-based safety training program can offer a safe working environment where users can effectively rehearse tasks with electrical hazards and ultimately promote their abilities for electrical hazard cognition and intervention. Its visualisation and simulation can also remove the training barriers caused by electricity's features of invisibility and dangerousness.

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

International Nuclear Information System (INIS)

2009-03-01

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

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

International Nuclear Information System (INIS)

2008-03-01

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

A safety concern related to CANDU moderator subcooling and status of KAERI moderator circulation test (MCT) experiments

International Nuclear Information System (INIS)

Rhee, Bo W.; Kim, Hyoung T.; Kim, Tongbeum; Im, Sunghyuk

2015-01-01

The flow inside the moderator tank of a CANDU-6 reactor during full power steady state operation has been suspected to be operating in the buoyancy/inertial driven mixed convection regime as illustrated in the middle figure. At some regions of the moderator tank where the buoyancy driven upward flow and the inertial momentum driven downward flows interface counter-currently, there exist some interface regions between these two flows like the middle one, and the local temperatures at these interface regions are known to oscillate with different amplitude at various fluctuation frequencies as shown. According to a numerical simulation of the moderator flow and temperature distribution at full power steady state carried out by previous researches showed that any small disturbances in the flow or temperature may initiate the system unstable and aggravate the asymmetric flow and temperature patterns. The tests at the 3-D Moderator Test Facility (MTF) that is a representative scaled-down of CANDU reactors, reproduced the expected and observed moderator behavior in the reactor as well as the local temperature fluctuations arising from the delicate balance of forced and buoyancy induced flow. This observation raised a safety concern as the local moderator temperature at some regions showed fluctuations with an amplitude that may jeopardize the safety margin, i.e. the difference between the available subcooling and the subcooling requirement. The scope of this paper is to review the basis of the safety concern related to this moderator subcooling and local temperature fluctuation and describe the current status of MCT erection and some of the experiments carried so far

The current status of wind energy in Turkey and in the world

International Nuclear Information System (INIS)

Ilkilic, Cumali; Aydin, Hueseyin; Behcet, Rasim

2011-01-01

The rapid increase in world energy demand, the depletion of conventional energy sources and the pollution caused by conventional fuels have increased the importance of developing new and renewable energy sources. Additionally, technological developments have resulted in increased energy demand for the entire world, including Turkey, especially for electrical energy. At present, wind energy is receiving considerable attention. This report focuses on the current status of wind energy in Turkey and in the world. An overview of wind energy in Turkey is presented, and its current status, application, support mechanisms and associated legislation in Turkey are described. Wind energy and its status in the world are also addressed. It can be concluded from this analysis that wind energy utilization in Turkey and throughout world has sharply increased. Turkey has an abundance of wind energy sources. - Research highlights: →The importance of wind energy utilization. →Wind energy status, potential, applications, legislations and supports in Turkey. →An overview of wind energy the world.

Current safety practices in nano-research laboratories in China.

Science.gov (United States)

Zhang, Can; Zhang, Jing; Wang, Guoyu

2014-06-01

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

Current status of neutron scattering in Thailand

International Nuclear Information System (INIS)

Ampornrat, Pantip

2000-01-01

The neutron scattering experiments in Thailand have been done continuously since the start up of the reactor. In 1977, Thai research reactor was modified into TRIGA MARK III core. After that, the neutron spectrometer was installed again under a development program. Installation of upgrading spectrometer was delayed because of some problems involving the neutron intensity and instruments. However, these problems were solved and the setup is almost completed. The paper reports the current status of neutron spectrometer, the problems and plans for the experiments. (author)

FRM-II project status and safety of its compact fuel element

International Nuclear Information System (INIS)

Nuding, M.; Rottmann, M.; Axmann, A.; Boening, K.

2000-01-01

The construction of the new research reactor FRM-II is close to completion and the nuclear start-up is scheduled to begin in January 2001. This contribution provides an overview on the concept of the facility and the safety features of the reactor. It also describes some of the tests performed during the licensing procedure of the compact fuel element and their results. At the end a short status report is given. (author)

FRM-II project status and safety of its compact fuel element

Energy Technology Data Exchange (ETDEWEB)

Nuding, M.; Rottmann, M.; Axmann, A.; Boening, K. [Technical University of Munich, D-85747 Garching (Germany)

2000-07-01

The construction of the new research reactor FRM-II is close to completion and the nuclear start-up is scheduled to begin in January 2001. This contribution provides an overview on the concept of the facility and the safety features of the reactor. It also describes some of the tests performed during the licensing procedure of the compact fuel element and their results. At the end a short status report is given. (author)

The Status of Road Safety in Iran during 2001 – 2006

Directory of Open Access Journals (Sweden)

M. J. Jafari

2013-08-01

.Result: The results revealed that during the period of 6 years, death toll has been increased by 9 deaths per 100000 person of the population. Moreover, application of seat belt and safety helmet has been increased by 20% and 18%, respectively. It also indicated that the number of motorists and the length of paved roads have been increased by 20%, and 10%, respectively. The net income per capita has also grown from 5884 US$ to 7968 US$ and the life expectancy has gone up from 68.9 years to 70.9 years, the percentage of the literate population has grown by 2% (from 76% to 78% and the human development index has increased from 0.721 to 0.759. The results of the present study showed that the increased level of death toll per 10000 vehicles and the increased level (% of seat belt as well as helmet application, paved roads, urbanization, the net income per capita, life expectancy, literacy and human development index were statistically significant and R2 coefficient for this factors was 0.84, 0.9, 0.994, 0.9, 0.97, 0.82, 0.69 and 0.84 respectively. .Conclusion: According to result of the present study, roads safety were not in an appropriate level. The roads safety status can be determined using road safety indicators to be applied for road safety promotion.

Assessment of Safety Culture in Isfahan Hospitals (2010)

OpenAIRE

Raeisi, Ahmed Reza; Nazari, Maryam; Bahmanziari, Najme

2013-01-01

Introduction: Many internal and external risk factors in health care organizations make safety important and it has caused the management to consider safety in their mission statement. One of the most important tools is to establish the appropriate organizational structure and safety culture. The goal: The goal of this research is to inform managers and staff about current safety culture status in hospitals in order to improve the efficiency and effectiveness of health services. Methods: This...

IVS: Current Status and Future Plans

Science.gov (United States)

Behrend, D.; Nothnagel, A.; Petrachenko, W. T.; Tuccari, G.

2016-12-01

The International VLBI Service for Geodesy and Astrometry (IVS) is a globally operating service that coordinates and performs Very Long Baseline Interferometry (VLBI) activities through its constituent components. The VLBI activities are associated with the creation, provision, dissemination, and archiving of relevant VLBI data and products. The products mostly pertain to the determination of the celestial and terrestrial reference frames, the Earth orientation parameters (EOP), atmospheric parameters as well as other ancillary parameters. The IVS observational network currently consists of about 40 radio telescopes worldwide. Subsets of these telescopes (8-12 stations) participate in 24-hour observing sessions that are run several times per week and in 1-hour intensive sessions for UT1 determination every day. The current VLBI network was developed mainly in the 1970s and 1980s. A number of factors, including aging infrastructure and demanding new scientific requirements, started to challenge its future sustainability and relevance. In response, the IVS and other groups developed and started implementing the next generation VLBI system, called VGOS (VLBI Global Observing System), at existing and new sites. The VGOS network is expected to reach maturity in the early 2020s. We describe the current status, progress, and anticipated prospects of geodetic/astrometric VLBI and the IVS.

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

Energy Technology Data Exchange (ETDEWEB)

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

1995-09-01

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

Improving the safety of Ukrainian NPP to reach an internationally accepted level

International Nuclear Information System (INIS)

Bozhko, S.; Helske, J.; Janke, R.; Mayoral, C.

2013-01-01

This paper summarizes the safety status and the modernization progress of Ukrainian NPPs towards an internationally accepted level of safety. After a brief discussion of the concept of what is called an 'international accepted level' for new and operating NPPs, the status of Russian type WWER and in particular the Ukrainian NPPs is presented. Then, the performed investigations of the gaps between international accepted level and the original status of Ukrainian NPPs are presented. The safety objectives of the modernization programs, some examples of defence in depth improvements, and an overall view of the modernization programs of Ukrainian NPPs are produced. Then, few important safety improvements implemented at the oldest Ukrainian WWER-1000 South Ukraine-1 are given in more detail. Finally, a conclusion presents the current status on the way to fulfill the national safety targets and to reach an internationally accepted level for all the Ukrainian NPPs. The paper is followed by the slides of the presentation. (authors)

Status of conceptual safety design study of Japanese sodium-cooled fast reactor

International Nuclear Information System (INIS)

Kubo, Shigenobu; Kurisaka, Kenichi; Niwa, Hajime; Shimakawa, Yoshio

2005-01-01

In this paper, the current conceptual safety design and related evaluation of Japanese Sodium-cooled Fast Reactor which is studied in the framework of the Feasibility Study (FS) on commercialized Fast Reactor Cycle Systems in Japan are described. The purpose of the safety design is to establish a feasible safety concept of FBR which aims at a sustainable energy source of the next generations. The safety targets and the safety design principle are set aiming at realizing worldwide acceptability of the safety level. The basic safety design concept, which can meet the safety targets, was formulated taking along with the defense-in-depth philosophy as the basic safety design principle. In order to cope with wide range of energy and resource demands, there are some various designs both of oxide and metal fuel for JSFR. Some analytical results of typical design basis events, design extension conditions and core damage frequency estimation show the feasibility of the safety design concept for them. (author)

Current status of RCA projects and strategies for future implementation

International Nuclear Information System (INIS)

Kim, Kyoung Pyo; Lee, Jeong Kong

1998-12-01

This report is intended to provide basic overall information about ways to promote technical cooperation within the framework of RCA to accelerate and coordinate cooperative activities in nuclear science and technology in Asia and the Pacific region through a thorough review on the current status and through suggesting future implementation strategies. The contents of this report include an overall introduction of RCA, guidelines and operating rules for RCA programmes, current status and future plans for RCA projects as well as the RCA vision for the next 25 years. By reviewing the current status and future implementation strategies for RCA projects, it will help to set up a national nuclear policy aimed at seeking maximum benefits from participation in RCA projects and to implement programmes for nuclear cooperation with Asian-Pacific countries. It is expected that as a lead country for the energy sector, which is one of five thematic areas for the year 1999 - 2000 cycle programmes, Korea will continue to make significant contributions towards the implementation of RCA programmes in the future. With this report, we plan to keep up with future developments as well as implement an effective cooperation with the countries in the region so that the opinion of Korea, one of the nuclear advanced countries in the region, can be fully reflected in the establishment of future plans for RCA programmes. (author). 3 refs., 5 tabs., 1 fig

Five years later: the current status of the use of proteomics and transcriptomics in EMF research.

Science.gov (United States)

Leszczynski, Dariusz; de Pomerai, David; Koczan, Dirk; Stoll, Dieter; Franke, Helmut; Albar, Juan Pablo

2012-08-01

The World Health Organization's and Radiation and Nuclear Safety Authority's "Workshop on Application of Proteomics and Transcriptomics in Electromagnetic Fields Research" was held in Helsinki in the October/November 2005. As a consequence of this meeting, Proteomics journal published in 2006 a special issue "Application of Proteomics and Transcriptomics in EMF Research" (Vol. 6 No. 17; Guest Editor: D. Leszczynski). This Proteomics issue presented the status of research, of the effects of electromagnetic fields (EMF) using proteomics and transcriptomics methods, present in 2005. The current overview/opinion article presents the status of research in this area by reviewing all studies that were published by the end of 2010. The review work was a part of the European Cooperation in the Field of Scientific and Technical Research (COST) Action BM0704 that created a structure in which researchers in the field of EMF and health shared knowledge and information. The review was prepared by the members of the COST Action BM0704 task group on the high-throughput screening techniques and electromagnetic fields (TG-HTST-EMF). © 2012 WILEY-VCH Verlag GmbH & Co. KGaA, Weinheim.

Tooth bleaching using peroxide-containing agents: current status of safety issues.

Science.gov (United States)

Li, Y

1998-08-01

During the last 10 years, at-home tooth bleaching using peroxide-containing agents has quickly become well accepted. It is one of the most popular cosmetic dental procedures for whitening teeth. Although there are few disputes regarding their efficacy, concerns and debates have continued regarding the safety of peroxide-containing tooth bleaching agents. Potential carcinogenicity and genotoxicity of the peroxides used in bleaching agents are the two most persistent and controversial issues. This article reviews and discusses available information on carcinogenicity and genotoxicity of hydrogen peroxide and the potential risks associated with the use of peroxide-containing bleaching agents. Clinical studies reported after the 1996 international symposium on responses of oral tissues to peroxide-containing bleaching agents are also reviewed. Overall evidence supports the conclusion that the proper use of peroxide-containing at-home tooth bleaching agents is safe. However, potential adverse effects may occur in inappropriate applications, abuses, or the use of inappropriate products. At-home tooth bleaching should be monitored by dental professionals to maximize the benefits while minimizing potential risks.

Current Status of Yongbyon Nuclear Complex

Energy Technology Data Exchange (ETDEWEB)

Hwang, Yong Soo [Korea Institute of Nuclear Non-proliferation and Control, Daejeon (Korea, Republic of)

2016-05-15

The DPRK has developed Yongbyon Nuclear Complex in Figure 1 since 1960's. Currently it is composed of the reactor facility, fuel fabrication facility including the enrichment center, and the radiochemistry center. Even though many facilities are not modern and economic in the western standards, Yongbyon Nuclear Complex is fully equipped with the entire life cycle of the nuclear installation. The key facilities have been added step by step. For example, the DPRK's nuclear reactor fleet started with the 2 MW IRT-2000 reactor in the middle of 80's. It started with a small scale radioactive isotope separation center nearby. But nowadays the DPRK is constructing a much more larger isotope separation center in the vicinity of its enrichment center along with a potential new UF6 conversion center. The general description over Yongbyon Nuclear Complex is given in this paper. More detailed context of the current status of the center will be discussed in the main symposium purely based on the open source information study.

Current status and future direction of the MONK software package

International Nuclear Information System (INIS)

Smith, Nigel; Armishaw, Malcolm; Cooper, Andrew

2003-01-01

The current status of the MONK criticality software package is summarized in terms of recent and current developments and envisaged directions for the future. The areas of the discussion are physics modeling, geometry modeling, source modeling, nuclear data, validation, supporting tools and customer services. In future development plan, MONK continues to be focused on meeting the short and long-term needs of the code user community. (J.P.N.)

Current status of education and training in medical physics in developing and developed countries

International Nuclear Information System (INIS)

Kulkarni, N.S.

2008-01-01

Significant resources are allocated for applying Medical Physics to health care. State-of-the-art technological developments have made this discipline valuable in early diagnosis and treatment of many diseases, particularly cancer. The current challenge is the dire need of harmonizing the standards of practice, including equipment, quality assurance, safety, education and training in Medical Physics across various countries. With experiences gained from the successes and failures in this field, standards of practice have evolved in the developed as well as the developing countries, but at different rates. Considerations of cost-benefit and priorities have led to increased gap in these standards of practice. In this presentation, the status of the education and training component of selected countries representing the two domains will be discussed. Possible causes, as well as the means adopted by the national and international organisations to bridge the gaps, will also be a part of the discussion. Suggestions for future improvements will be offered for consideration

Operational validation - current status and opportunities for improvement

International Nuclear Information System (INIS)

Davey, E.

2002-01-01

The design of nuclear plant systems and operational practices is based on the application of multiple defenses to minimize the risk of occurrence of safety and production challenges and upsets. With such an approach, the effectiveness of individual or combinations of design and operational features in preventing upset challenges should be known. A longstanding industry concern is the adverse impact errors in human performance can have on plant safety and production. To minimize the risk of error occurrence, designers and operations staff routinely employ multiple design and operational defenses. However, the effectiveness of individual or combinations of defensive features in minimizing error occurrence are generally only known in a qualitative sense. More importantly, the margins to error or upset occurrence provided by combinations of design or operational features are generally not characterized during design or operational validation. This paper provides some observations and comments on current validation practice as it relates to operational human performance concerns. The paper also discusses opportunities for future improvement in validation practice in terms of the resilience of validation results to operating changes and characterization of margins to safety or production challenge. (author)

Radiological safety status and quality assurance audit of medical X-ray diagnostic installations in India.

Science.gov (United States)

Sonawane, A U; Singh, Meghraj; Sunil Kumar, J V K; Kulkarni, Arti; Shirva, V K; Pradhan, A S

2010-10-01

We conducted a radiological safety and quality assurance (QA) audit of 118 medical X-ray diagnostic machines installed in 45 major hospitals in India. The main objective of the audit was to verify compliance with the regulatory requirements stipulated by the national regulatory body. The audit mainly covered accuracy check of accelerating potential (kVp), linearity of tube current (mA station) and timer, congruence of radiation and optical field, and total filtration; in addition, we also reviewed medical X-ray diagnostic installations with reference to room layout of X-ray machines and conduct of radiological protection survey. A QA kit consisting of a kVp Test-O-Meter (ToM) (Model RAD/FLU-9001), dose Test-O-Meter (ToM) (Model 6001), ionization chamber-based radiation survey meter model Gun Monitor and other standard accessories were used for the required measurements. The important areas where there was noncompliance with the national safety code were: inaccuracy of kVp calibration (23%), lack of congruence of radiation and optical field (23%), nonlinearity of mA station (16%) and timer (9%), improper collimator/diaphragm (19.6%), faulty adjustor knob for alignment of field size (4%), nonavailability of warning light (red light) at the entrance of the X-ray room (29%), and use of mobile protective barriers without lead glass viewing window (14%). The present study on the radiological safety status of diagnostic X-ray installations may be a reasonably good representation of the situation in the country as a whole. The study contributes significantly to the improvement of radiological safety by the way of the steps already taken and by providing a vital feed back to the national regulatory body.

Radiological safety status and quality assurance audit of medical X-ray diagnostic installations in India

International Nuclear Information System (INIS)

Sonawane, A.U.; Singh, Meghraj; Sunil Kumar, J.V.K.; Kulkarni, Arti; Shirva, V.K.; Pradhan, A.S.

2010-01-01

We conducted a radiological safety and quality assurance (QA) audit of 118 medical X-ray diagnostic machines installed in 45 major hospitals in India. The main objective of the audit was to verify compliance with the regulatory requirements stipulated by the national regulatory body. The audit mainly covered accuracy check of accelerating potential (kVp), linearity of tube current (mA station) and timer, congruence of radiation and optical field, and total filtration; in addition, we also reviewed medical X-ray diagnostic installations with reference to room layout of X-ray machines and conduct of radiological protection survey. A QA kit consisting of a kVp Test-O-Meter (ToM) (Model RAD/FLU-9001), dose Test-O-Meter (ToM) (Model 6001), ionization chamber-based radiation survey meter model Gun Monitor and other standard accessories were used for the required measurements. The important areas where there was noncompliance with the national safety code were: inaccuracy of kVp calibration (23%), lack of congruence of radiation and optical field (23%), nonlinearity of mA station (16%) and timer (9%), improper collimator/diaphragm (19.6%), faulty adjustor knob for alignment of field size (4%), nonavailability of warning light (red light) at the entrance of the X-ray room (29%), and use of mobile protective barriers without lead glass viewing window (14%). The present study on the radiological safety status of diagnostic X-ray installations may be a reasonably good representation of the situation in the country as a whole. The study contributes significantly to the improvement of radiological safety by the way of the steps already taken and by providing a vital feed back to the national regulatory body. (author)

Cost Estimating in DoD: Current Status, Trends, and What the Future Holds

National Research Council Canada - National Science Library

Nussbaum, Daniel A

2005-01-01

(1) Current Status: Baseline analysis of current cost estimating community, including which organizations are responsible for developing and reviewing cost estimates, how many personnel there are, what...

Nuclear Safety in Central and Eastern Europe

International Nuclear Information System (INIS)

2001-04-01

Nuclear safety is one of the critical issues with respect to the enlargement of the European Union towards the countries of Central and Eastern Europe. In the context of the enlargement process, the European Commission overall strategy on nuclear safety matters has been to bring the general standard of nuclear safety in the pre-accession countries up to a level that would be comparable to the safety levels in the countries of the European Union. In this context, the primary objective of the project was to develop a common format and general guidance for the evaluation of the current nuclear safety status in countries that operate commercial nuclear power plants. Therefore, one of the project team first undertakings was to develop an approach that would allow for a consistent and comprehensive overview of the nuclear safety status in the CEEC, enabling an equal treatment of the countries to be evaluated. Such an approach, which did not exist, should also ensure identification of the most important safety issues of the individual nuclear power plants. The efforts resulted in the development of the ''Performance Evaluation Guide'', which focuses on important nuclear safety issues such as plant design and operation, the practice of performing safety assessments, and nuclear legislation and regulation, in particular the role of the national regulatory body. Another important aspect of the project was the validation of the Performance Evaluation Guide (PEG) by performing a preliminary evaluation of nuclear safety in the CEEC, namely in Bulgaria, Czech Republic, Hungary, Lithuania, Romania, Slovak Republic, and Slovenia. The nuclear safety evaluation of each country was performed as a desktop exercise, using solely available documents that had been prepared by various Western institutions and the countries themselves. Therefore, the evaluation is only of a preliminary nature. The project did not intend to re-assess nuclear safety, but to focus on a comprehensive summary

Hardwood lumber supply chain: current status and market opportunities

Science.gov (United States)

Urs Buehlmann; Matthew Bumgardner; Al Schuler; Mark Barford

2007-01-01

The membership of the Appalachian Hardwood Manufacturers Association was surveyed in 2005 to determine the current status of large Appalachian sawmills. The primary focus was to assess the impacts of globalization on primary manufacturing, but attention was also paid to general issues affecting the hardwood lumber supply chain-from concerns over forest health and log...

Improving operational safety management through probabilistic safety assessment on personal computers

International Nuclear Information System (INIS)

1988-10-01

The Technical Committee Meeting considered the current effort in the implementation and use of PSA information for day-to-day operational safety management on Personal Computers. Due to the very recent development of the necessary hardware and software for Personal Computers, the application of PSA information for day-to-day operational safety management on PCs is essentially still in a pioneering stage. There is at present only one such system for end users existing, the PRISIM (Plant Risk Status Information Management) program for which a limited practical application experience is available. Others are still in the development stage. The main aim of the Technical Committee Meeting was to discuss the present status of PSA based systems for operational safety management support on small computers, to consider practical aspects when implementing these systems into a nuclear installation and to address problems related to the further work in the area. A separate abstract was prepared for the summary of the Technical Committee Meeting and for the 8 papers presented by the participants. Refs, figs and tabs

The Safety and Tritium Applied Research (STAR) Facility: Status-2004

International Nuclear Information System (INIS)

Anderl, R.A.; Longhurst, G.R.; Pawelko, R.J.; Sharpe, J.P.; Schuetz, S.T.; Petti, D.A.

2005-01-01

The Safety and Tritium Applied Research (STAR) Facility, a US DOE National User Facility at the Idaho National Engineering and Environmental Laboratory (INEEL), comprises capabilities and infrastructure to support both tritium and non-tritium research activities important to the development of safe and environmentally friendly fusion energy. Research thrusts include (1) interactions of tritium and deuterium with plasma-facing-component (PFC) materials, (2) fusion safety issues [PFC material chemical reactivity and dust/debris generation, activation product mobilization, tritium behavior in fusion systems], and (3) molten salts and fusion liquids for tritium breeder and coolant applications. This paper updates the status of STAR and the capabilities for ongoing research activities, with an emphasis on the development, testing and integration of the infrastructure to support tritium research activities. Key elements of this infrastructure include a tritium storage and assay system, a tritium cleanup system to process glovebox and experiment tritiated effluent gases, and facility tritium monitoring systems

Smart wearable systems: current status and future challenges.

Science.gov (United States)

Chan, Marie; Estève, Daniel; Fourniols, Jean-Yves; Escriba, Christophe; Campo, Eric

2012-11-01

Extensive efforts have been made in both academia and industry in the research and development of smart wearable systems (SWS) for health monitoring (HM). Primarily influenced by skyrocketing healthcare costs and supported by recent technological advances in micro- and nanotechnologies, miniaturisation of sensors, and smart fabrics, the continuous advances in SWS will progressively change the landscape of healthcare by allowing individual management and continuous monitoring of a patient's health status. Consisting of various components and devices, ranging from sensors and actuators to multimedia devices, these systems support complex healthcare applications and enable low-cost wearable, non-invasive alternatives for continuous 24-h monitoring of health, activity, mobility, and mental status, both indoors and outdoors. Our objective has been to examine the current research in wearable to serve as references for researchers and provide perspectives for future research. Herein, we review the current research and development of and the challenges facing SWS for HM, focusing on multi-parameter physiological sensor systems and activity and mobility measurement system designs that reliably measure mobility or vital signs and integrate real-time decision support processing for disease prevention, symptom detection, and diagnosis. For this literature review, we have chosen specific selection criteria to include papers in which wearable systems or devices are covered. We describe the state of the art in SWS and provide a survey of recent implementations of wearable health-care systems. We describe current issues, challenges, and prospects of SWS. We conclude by identifying the future challenges facing SWS for HM. Copyright © 2012 Elsevier B.V. All rights reserved.

Nuclear power systems: Their safety. Current issue review

International Nuclear Information System (INIS)

Myers, L.C.

1994-04-01

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

Counseling in Malaysia: History, Current Status, and Future Trends

Science.gov (United States)

See, Ching Mey; Ng, Kok-Mun

2010-01-01

This article presents an overview of the history of counseling in Malaysia, provides an update of its current status, and discusses some anticipated future trends for the profession in light of recent developments in the country. Counseling in Malaysia began with school guidance in the 1960s and has now achieved recognition as a profession in…

Modeling the critical safety functions status tree of a NPP using FPGA

International Nuclear Information System (INIS)

Farias, Marcos Santana; Oliveira, Mauro Vitor de; Jaime, Guilherme Dutra Gonzaga; Almeida, Jose Carlos Soares de; Augusto, Silas Cordeiro

2013-01-01

Field Programmable Gate Arrays (FPGAs) based systems and equipment are beginning to appear in new plants I and C applications, as well as in retrofits for operating plants, in particular for safety applications due to their capability to face the systems obsolescence since they are circuit independent. The circuits implemented can be portable to different FPGAs architectures. Moreover, they reduce complexity for regulatory approval as compared to conventional microprocessor-based systems. Critical safety function (CSF) is the most significant design concept for prioritize operator actions for NPP based on the potential threat to the three barriers (fuel cladding, primary coolant system boundary, and containment) and allows the operator to respond to these threats prior to event diagnosis. CSF has a hierarchical information structure that organizes the system variables affecting the plant safety in terms of goal-means relations. This paper describes the application of FPGA in the implementation of the CSFs status tree logic for a Westinghouse 3-loops NPP simulator. (author)

Finite element transport methods for criticality calculations - current status and potential applications

International Nuclear Information System (INIS)

Oliveira, C.R.E. de; Goddard, A.

1991-01-01

In this paper we review the current status of the finite element method applied to the solution of the neutron transport equation and we discuss its potential role in the field of criticality safety. We show that the method's ability in handling complex, irregular geometry in two- and three-dimensions coupled with its accurate solutions potentially renders it an attractive alternative to the longer-established Monte Carlo method. Details of the most favoured form of the method - that which combines finite elements in space and spherical harmonics in angle - are presented. This form of the method, which has been extensively investigated over the last decade by research groups at the University of London, has been numerically implemented in the finite element code EVENT. The code has among its main features the capability of solving fixed source eigenvalue and time-dependent complex geometry problems in two- and three-dimensions. Other features of the code include anisotropic up- and down-scatter, direct and/or adjoint solutions and access to standard data libraries. Numerical examples, ranging from simple criticality benchmark studies to the analysis of idealised three-dimensional reactor cores, are presented to demonstrate the potential of the method. (author)

DNA Analyses in Food Safety and Quality: Current Status and Expectations

Science.gov (United States)

Marchelli, Rosangela; Tedeschi, Tullia; Tonelli, Alessandro

Food safety and quality are very important issues receiving a lot of attention in most countries by producers, consumers and regulatory and control authorities. In particular, DNA analysis in food is becoming popular not only in relation to genetically modified products (GMOs), in which DNA modification is the "clue" of the novelty, but also in other fields like microbiology and pathogen detection, which require long times for the cultivation and specially in cases in which the microorganisms are not cultivable like some viruses, as well as for authenticity and allergen detection. A new topic concerning "nutrigenetics and nutrigenomics" has also been mentioned, very important but still in its infancy, which could lead in the future to a personalized diet. In this chapter we have described the main areas of food research and fields of application where DNA analysis is being performed and the relative methods of detection, which are generally based on PCR. The possibility/opportunity to detect DNA without previous amplification (PCR-free) will be discussed. We have examined the following areas: (1) genetically modified foods (GMOs); (2) food allergens; (3) microbiological contaminations; (4) food authenticity; (5) nutrigenetics/nutrigenomics.

Current status of Pohang Neutron Facility

Energy Technology Data Exchange (ETDEWEB)

Kim, G.N.; Lee, Y.S.; Cho, M.H. [Pohang Accelerator Laboratory, POSTECH, Pohang (KR)] [and others

2000-03-01

We present the current status of Pohang Neutron Facility, which is the pulsed neutron facility, based on the 70-MeV electron linear accelerator completed on Dec.1997. We have prepared the 15-m time-of-flight path, a Ta-target system, and the Data Acquisition System. Meanwhile we have measured the total cross-sections of Dy and Hf samples at the Research Reactor Institute, Kyoto University and the neutron capture cross-sections of {sup 164}Dy isotope at Research Laboratory for Nuclear Reactors, Tokyo Institute of Technology both in Japan. We also were participated the experiment at the 122-m flight path of the IBR-30 pulsed neutron source of Joint Institute of Nuclear Research in Dubna, Russia. (author)

Instantaneous Project Controls: Current Status, State of the Art, Benefits, and Strategies

Science.gov (United States)

Abbaszadegan, Amin

2016-01-01

Despite advancements in construction and construction-related technology, capital project performance deviations, typically overruns, remain endemic within the capital projects industry. Currently, management is generally unaware of the current status of their projects, and thus monitoring and control of projects are not achieved effectively. In…

Current Status of Mycotoxin Analysis: A Critical Review.

Science.gov (United States)

Shephard, Gordon S

2016-07-01

It is over 50 years since the discovery of aflatoxins focused the attention of food safety specialists on fungal toxins in the feed and food supply. Since then, analysis of this important group of natural contaminants has advanced in parallel with general developments in analytical science, and current MS methods are capable of simultaneously analyzing hundreds of compounds, including mycotoxins, pesticides, and drugs. This profusion of data may advance our understanding of human exposure, yet constitutes an interpretive challenge to toxicologists and food safety regulators. Despite these advances in analytical science, the basic problem of the extreme heterogeneity of mycotoxin contamination, although now well understood, cannot be circumvented. The real health challenges posed by mycotoxin exposure occur in the developing world, especially among small-scale and subsistence farmers. Addressing these problems requires innovative approaches in which analytical science must also play a role in providing suitable out-of-laboratory analytical techniques.

Review on the current status of molten chloride reactor and its future prospect

Energy Technology Data Exchange (ETDEWEB)

Seo, Seok Bin; Shin, Yukyung; Bang, In Cheol [UNIST, Ulsan (Korea, Republic of)

2016-10-15

This paper has summarized and reviewed the current status of MCR as an online pyroprocessing reactor, and introduced the related works in UNIST. As the developments of the next generation nuclear energy systems require the fuel sustainability, passive operation safety, nuclear proliferation, and reduction of highly radioactive waste, only several types of nuclear reactor systems survive to the last. Among these, molten salt reactor (MSR) is one of the most promising concepts of next generation nuclear reactor system that deliver on these requirements. MSR have great advantages in the fuel cycle and reduction of nuclear waste, since MSR can serve the online reprocessing system for the reprocessing of spent fuel. Especially, MSR utilizing chloride-based fuel, called molten chloride reactor (MCR) has been recently highlighted in USA under the DOE’s Gateway for Accelerated Innovation in Nuclear (GAIN) program. Recently, the interests in the molten chloride salt have arisen. The use of chloride-based salt gives great advantages to the reactor operating in a fast spectrum. Then MCR can serve waste management functions or fuel cycle sustainability functions, which can solve the current issues in nuclear field. Thus, research plan was established in UNIST which includes the investigation of thermal-hydraulic characteristics of chloride salt and optimization of heat transport system of MCR, using both numerical method and experimental method.

Review on the current status of molten chloride reactor and its future prospect

International Nuclear Information System (INIS)

Seo, Seok Bin; Shin, Yukyung; Bang, In Cheol

2016-01-01

This paper has summarized and reviewed the current status of MCR as an online pyroprocessing reactor, and introduced the related works in UNIST. As the developments of the next generation nuclear energy systems require the fuel sustainability, passive operation safety, nuclear proliferation, and reduction of highly radioactive waste, only several types of nuclear reactor systems survive to the last. Among these, molten salt reactor (MSR) is one of the most promising concepts of next generation nuclear reactor system that deliver on these requirements. MSR have great advantages in the fuel cycle and reduction of nuclear waste, since MSR can serve the online reprocessing system for the reprocessing of spent fuel. Especially, MSR utilizing chloride-based fuel, called molten chloride reactor (MCR) has been recently highlighted in USA under the DOE’s Gateway for Accelerated Innovation in Nuclear (GAIN) program. Recently, the interests in the molten chloride salt have arisen. The use of chloride-based salt gives great advantages to the reactor operating in a fast spectrum. Then MCR can serve waste management functions or fuel cycle sustainability functions, which can solve the current issues in nuclear field. Thus, research plan was established in UNIST which includes the investigation of thermal-hydraulic characteristics of chloride salt and optimization of heat transport system of MCR, using both numerical method and experimental method

Providing current radiation safety according to new version of 'Ukrytie' object regulation

International Nuclear Information System (INIS)

Borovoj, A.A.; Vysotskij, E.D.; Krinitsyn, A.P.; Bogatov, S.A.

1999-01-01

Main provisions are given of the 'Ukryttia' object's Regulation related to provision of radiation safety during the object's operation. The safety is provided due to the realization by the object's personnel of functions of global monitoring of current radiation conditions, as well as of the measures of operative or preventive suppression of radiation abnormalities sources

The current status of radiological protection infraestructures in Tanzania

International Nuclear Information System (INIS)

Ngalie, J.E.; Mompome, W.K.; Meza, L.H.

2008-01-01

Without adequate and sustainable radiation protection infrastructure, the benefits associated with safe use of nuclear technology and atomic energy might be jeopardized. In the United Republic of Tanzania, the Atomic Energy Act No. 7 of 2003 established the Tanzania Atomic Energy Commission as sole regulatory body responsible for regulating and controlling the safe and peaceful utilization of nuclear technology in the country. The Atomic Energy (Protection from ionizing radiation) Regulations, 2004 further specifies practices designed to ensure that unnecessary exposure of persons to ionizing radiation is avoided, that all exposures are kept as low as reasonably achievable and that all the dose limits specified in the radiation protection standards are not exceeded. This is achieved through the systems of notification, authorizations through registration and licensing, safety and security of radiation sources as well as regulatory inspections and enforcements. These activities are performed by the Commission with operational funds allocated by the Government of Tanzania. The Commission further provides other services namely individual monitoring; calibration services; education and training to radiation workers, public as well as law enforcers; and safe management of radioactive waste. Despite such achievement, still there are a lot to be done in order to strengthen the radiation protection infrastructure in Tanzania. These include issues such as gaps in our legislations, regulations and guidance, security of sources, enforcement of laws, etc. This paper describes and discusses the current status of the regulatory control activities and radiation protection services provided by the Commission and suggestions for further improvement of radiological protection infrastructure in Tanzania. (author)

The Canadian Nuclear Safety Commission's financial guarantee requirements

International Nuclear Information System (INIS)

Ferch, R.

2006-01-01

The Nuclear Safety and Control Act gives the Canadian Nuclear Safety Commission (CNSC) the legal authority to require licensees to provide financial guarantees in order to meet the purposes of the Act. CNSC policy and guidance with regard to financial guarantees is outlined, and the current status of financial guarantee requirements as applied to various CNSC licensees is described. (author)

CT colonography: current status in Europe and future perspectives

International Nuclear Information System (INIS)

Lefere, P.; Gryspeerdt, S.; Yoshida, H.

2007-01-01

In this article, we review the current status of CT colonography (CTC) in Europe and future perspectives of CTC including fecal tagging and CAD. There are several large multi-centre studies that have been initiated. Fecal tagging has gradually become a prerequisite to perform state-of-the-art CTC. However, CAD for fecal-tagging CTC remains a subject for future research. (orig.)

Current status of application of Moessbauer effect in geology and mineralogy

International Nuclear Information System (INIS)

Xu Binfu

1995-01-01

The paper briefly introduces the current status of the application of Moessbauer effect in geology and mineralogy. It shows that geology and mineralogy are very active fields in the application of Moessbauer effect

The current status of biomarkers for predicting toxicity

Science.gov (United States)

Campion, Sarah; Aubrecht, Jiri; Boekelheide, Kim; Brewster, David W; Vaidya, Vishal S; Anderson, Linnea; Burt, Deborah; Dere, Edward; Hwang, Kathleen; Pacheco, Sara; Saikumar, Janani; Schomaker, Shelli; Sigman, Mark; Goodsaid, Federico

2013-01-01

Introduction There are significant rates of attrition in drug development. A number of compounds fail to progress past preclinical development due to limited tools that accurately monitor toxicity in preclinical studies and in the clinic. Research has focused on improving tools for the detection of organ-specific toxicity through the identification and characterization of biomarkers of toxicity. Areas covered This article reviews what we know about emerging biomarkers in toxicology, with a focus on the 2012 Northeast Society of Toxicology meeting titled ‘Translational Biomarkers in Toxicology.’ The areas covered in this meeting are summarized and include biomarkers of testicular injury and dysfunction, emerging biomarkers of kidney injury and translation of emerging biomarkers from preclinical species to human populations. The authors also provide a discussion about the biomarker qualification process and possible improvements to this process. Expert opinion There is currently a gap between the scientific work in the development and qualification of novel biomarkers for nonclinical drug safety assessment and how these biomarkers are actually used in drug safety assessment. A clear and efficient path to regulatory acceptance is needed so that breakthroughs in the biomarker toolkit for nonclinical drug safety assessment can be utilized to aid in the drug development process. PMID:23961847

Is it time to reassess current safety standards for glyphosate-based herbicides?

Science.gov (United States)

Vandenberg, Laura N; Blumberg, Bruce; Antoniou, Michael N; Benbrook, Charles M; Carroll, Lynn; Colborn, Theo; Everett, Lorne G; Hansen, Michael; Landrigan, Philip J; Lanphear, Bruce P; Mesnage, Robin; Vom Saal, Frederick S; Welshons, Wade V; Myers, John Peterson

2017-06-01

Use of glyphosate-based herbicides (GBHs) increased ∼100-fold from 1974 to 2014. Additional increases are expected due to widespread emergence of glyphosate-resistant weeds, increased application of GBHs, and preharvest uses of GBHs as desiccants. Current safety assessments rely heavily on studies conducted over 30 years ago. We have considered information on GBH use, exposures, mechanisms of action, toxicity and epidemiology. Human exposures to glyphosate are rising, and a number of in vitro and in vivo studies challenge the basis for the current safety assessment of glyphosate and GBHs. We conclude that current safety standards for GBHs are outdated and may fail to protect public health or the environment. To improve safety standards, the following are urgently needed: (1) human biomonitoring for glyphosate and its metabolites; (2) prioritisation of glyphosate and GBHs for hazard assessments, including toxicological studies that use state-of-the-art approaches; (3) epidemiological studies, especially of occupationally exposed agricultural workers, pregnant women and their children and (4) evaluations of GBHs in commercially used formulations, recognising that herbicide mixtures likely have effects that are not predicted by studying glyphosate alone. Published by the BMJ Publishing Group Limited. For permission to use (where not already granted under a licence) please go to http://www.bmj.com/company/products-services/rights-and-licensing/.

Ethiopia's emerging domestic biogas sector : Current status, bottlenecks and drivers

NARCIS (Netherlands)

Kamp, L.M.; Bermúdez Forn, Esteban

2016-01-01

Ethiopia experiences an energy and environmental crisis due to the sustained reliance on woody biomass to satisfy its energy needs. This situation could be improved by using biogas. This paper analyses the current status of the domestic biogas sector in Ethiopia and identifies barriers and

Edible vaccines: Current status and future

Directory of Open Access Journals (Sweden)

Lal P

2007-01-01

Full Text Available Edible vaccines hold great promise as a cost-effective, easy-to-administer, easy-to-store, fail-safe and socioculturally readily acceptable vaccine delivery system, especially for the poor developing countries. It involves introduction of selected desired genes into plants and then inducing these altered plants to manufacture the encoded proteins. Introduced as a concept about a decade ago, it has become a reality today. A variety of delivery systems have been developed. Initially thought to be useful only for preventing infectious diseases, it has also found application in prevention of autoimmune diseases, birth control, cancer therapy, etc. Edible vaccines are currently being developed for a number of human and animal diseases. There is growing acceptance of transgenic crops in both industrial and developing countries. Resistance to genetically modified foods may affect the future of edible vaccines. They have passed the major hurdles in the path of an emerging vaccine technology. Various technical obstacles, regulatory and non-scientific challenges, though all seem surmountable, need to be overcome. This review attempts to discuss the current status and future of this new preventive modality.

Current status of Paragonimus and paragonimiasis in Ecuador

Directory of Open Access Journals (Sweden)

Manuel Calvopiña

2014-11-01

Full Text Available A review of national and international publications on paragonimiasis in Ecuador, epidemiological records from the Ministry of Public Health and unpublished research data was conducted to summarise the current status of the parasite/disease. The purpose of the review is to educate physicians, policy-makers and health providers on the status of the disease and to stimulate scientific investigators to conduct further research. Paragonimiasis was first diagnosed in Ecuador 94 years ago and it is endemic to both tropical and subtropical regions in 19 of 24 provinces in the Pacific Coast and Amazon regions. Paragonimus mexicanus is the only known species in the country, with the mollusc Aroapyrgus colombiensis and the crabs Moreirocarcinus emarginatus, Hypolobocera chilensis and Hypolobocera aequatorialis being the primary and secondary intermediate hosts, respectively. Recent studies found P. mexicanus metacercariae in Trichodactylus faxoni crabs of the northern Amazon. Chronic pulmonary paragonimiasis is commonly misdiagnosed and treated as tuberculosis and although studies have demonstrated the efficacy of praziquantel and triclabendazole for the treatment of human infections, neither drug is available in Ecuador. Official data recorded from 1978-2007 indicate an annual incidence of 85.5 cases throughout the 19 provinces, with an estimated 17.2% of the population at risk of infection. There are no current data on the incidence/prevalence of infection, nor is there a national control programme.

Parametric overdispersed frailty models for current status data.

Science.gov (United States)

Abrams, Steven; Aerts, Marc; Molenberghs, Geert; Hens, Niel

2017-12-01

Frailty models have a prominent place in survival analysis to model univariate and multivariate time-to-event data, often complicated by the presence of different types of censoring. In recent years, frailty modeling gained popularity in infectious disease epidemiology to quantify unobserved heterogeneity using Type I interval-censored serological data or current status data. In a multivariate setting, frailty models prove useful to assess the association between infection times related to multiple distinct infections acquired by the same individual. In addition to dependence among individual infection times, overdispersion can arise when the observed variability in the data exceeds the one implied by the model. In this article, we discuss parametric overdispersed frailty models for time-to-event data under Type I interval-censoring, building upon the work by Molenberghs et al. (2010) and Hens et al. (2009). The proposed methodology is illustrated using bivariate serological data on hepatitis A and B from Flanders, Belgium anno 1993-1994. Furthermore, the relationship between individual heterogeneity and overdispersion at a stratum-specific level is studied through simulations. Although it is important to account for overdispersion, one should be cautious when modeling both individual heterogeneity and overdispersion based on current status data as model selection is hampered by the loss of information due to censoring. © 2017, The International Biometric Society.

Current status of JAERI Tokai hot cell facilities

International Nuclear Information System (INIS)

Itami, Hiroharu; Morozumi, Minoru; Yamahara, Takeshi

1992-01-01

JAERI has 4 hot cell facilities in order to examine high radioactive materials. Three of them, the Research Hot Laboratory, the Reactor Fuel Examination Facility and the Waste Safety Testing Facility are located in the JAERI Tokai site, and the rest is the JMTR Hot Laboratory in the Oarai site. The Research Hot Laboratory (RHL) was constructed for post-irradiation examination (PIE), especially nuclear related basic research experiment, such as metallurgical, chemical and mechanical examination on fuels and materials irradiated in research and test reactors. This facility has 10 large dimension concrete and 38 lead cells. At present the RHL is used for various kinds of examinations of high radioactive samples such as fuels of research and test reactors, power reactors and high temperature testing reactor (HTTR), and structural materials. The Reactor Fuel Examination Facility (RFEF) was designed and constructed for carrying out PIE of irradiated full-size fuel assemblies of light water reactors (LWRs). This facility has a storage pool, 8 concrete and 5 lead cells. They are currently used for safety evaluation on high burnup and advanced lWR fuels as part of the national program. The Waste Safety Testing Facility (WASTEF) was designed and constructed for safety research on long-term storage and disposal of high level radioactive wastes, generated by fuel reprocessing. The WASTEF has 5 concrete cells and 1 lead cell. Examinations on the behavior of various long-lived fission products in a glass form and in a canister and, releasing behavior of them out of a canister are carrying out under the condition at storage. (author)

Radiological safety status and quality assurance audit of medical X-ray diagnostic installations in India

Directory of Open Access Journals (Sweden)

Sonawane A

2010-01-01

Full Text Available We conducted a radiological safety and quality assurance (QA audit of 118 medical X-ray diagnostic machines installed in 45 major hospitals in India. The main objective of the audit was to verify compliance with the regulatory requirements stipulated by the national regulatory body. The audit mainly covered accuracy check of accelerating potential (kVp, linearity of tube current (mA station and timer, congruence of radiation and optical field, and total filtration; in addition, we also reviewed medical X-ray diagnostic installations with reference to room layout of X-ray machines and conduct of radiological protection survey. A QA kit consisting of a kVp Test-O-Meter (ToM (Model RAD/FLU-9001, dose Test-O-Meter (ToM (Model 6001, ionization chamber-based radiation survey meter model Gun Monitor and other standard accessories were used for the required measurements. The important areas where there was noncompliance with the national safety code were: inaccuracy of kVp calibration (23%, lack of congruence of radiation and optical field (23%, nonlinearity of mA station (16% and timer (9%, improper collimator/diaphragm (19.6%, faulty adjustor knob for alignment of field size (4%, nonavailability of warning light (red light at the entrance of the X-ray room (29%, and use of mobile protective barriers without lead glass viewing window (14%. The present study on the radiological safety status of diagnostic X-ray installations may be a reasonably good representation of the situation in the country as a whole. The study contributes significantly to the improvement of radiological safety by the way of the steps already taken and by providing a vital feed back to the national regulatory body.

Current status of SFR development in Japan

Energy Technology Data Exchange (ETDEWEB)

Ieda, Yoshiaki; Chikazawa, Yoshitaka [Japan Atomic Energy Agency, Tokyo (Japan). Project Promotion Office; Kotake, Shoji [Japan Atomic Power Company, Tokyo (Japan)

2012-03-15

Fast Reactor development experiences and status in Japan are summarized. Even though international SFR circumstances were against in 1980s and 1990s, e.g. CRBRP, SNR-300 and Superphenix terminations, we kept on with our R and D activities steadily aiming at positive development targets in Japan. As results of our efforts, it has shown that our commercialized SFR concept, Japan Sodium-cooled Fast Reactor (JSFR) could meet the targets in the Feasibility Study on Commercialized Fast Reactor Cycle Systems (FS) and the Fast Reactor Cycle Technology Development (FaCT) project. Further, Monju has finally achieved restart in May 2010 after having been shut for almost 15 years. A future plan of Monju is to be determined based on a direction of the national nuclear and energy policies that will be established in 2012. The undergoing FaCT project is pursuing commercialization of fast reactor cycle system around 2050 under cooperation of MEXT (Ministry of Education, Culture, Sports, Science and Technology), METI (Ministry of Economy, Trade and Industry), utilities, venders and JAEA (Japan Atomic Energy Agency). As results of the FaCT Phase I, feasibility of the key technologies for JSFR has been evaluated and the project is waiting for launching the phase II due to the Tohoku large earthquake. It is considered that the nuclear development policy might be affected by the Tohoku large Earthquake/Tsunami in Japan. Nevertheless the significance of nuclear energy will not be changed and thus we will focus on the issues learnt from Fukushima accidents and reflect into the improvement of the safety of Monju and the safety design criteria for the next generation Fast Reactor systems. (orig.)

Current status of SFR development in Japan

International Nuclear Information System (INIS)

Ieda, Yoshiaki; Chikazawa, Yoshitaka

2012-01-01

Fast Reactor development experiences and status in Japan are summarized. Even though international SFR circumstances were against in 1980s and 1990s, e.g. CRBRP, SNR-300 and Superphenix terminations, we kept on with our R and D activities steadily aiming at positive development targets in Japan. As results of our efforts, it has shown that our commercialized SFR concept, Japan Sodium-cooled Fast Reactor (JSFR) could meet the targets in the Feasibility Study on Commercialized Fast Reactor Cycle Systems (FS) and the Fast Reactor Cycle Technology Development (FaCT) project. Further, Monju has finally achieved restart in May 2010 after having been shut for almost 15 years. A future plan of Monju is to be determined based on a direction of the national nuclear and energy policies that will be established in 2012. The undergoing FaCT project is pursuing commercialization of fast reactor cycle system around 2050 under cooperation of MEXT (Ministry of Education, Culture, Sports, Science and Technology), METI (Ministry of Economy, Trade and Industry), utilities, venders and JAEA (Japan Atomic Energy Agency). As results of the FaCT Phase I, feasibility of the key technologies for JSFR has been evaluated and the project is waiting for launching the phase II due to the Tohoku large earthquake. It is considered that the nuclear development policy might be affected by the Tohoku large Earthquake/Tsunami in Japan. Nevertheless the significance of nuclear energy will not be changed and thus we will focus on the issues learnt from Fukushima accidents and reflect into the improvement of the safety of Monju and the safety design criteria for the next generation Fast Reactor systems. (orig.)

Draft pilot report - Approaches to the resolution of safety issues

International Nuclear Information System (INIS)

2006-01-01

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

The current implementation status of the integration of sports and physical activity into Dutch rehabilitation care

NARCIS (Netherlands)

Hoekstra, Femke; Hettinga, Florentina J; Alingh, Rolinde A; Duijf, Marjo; Dekker, Rienk; van der Woude, Lucas H V; van der Schans, Cees P

PURPOSE: To describe the current status of the nationwide implementation process of a sports and physical activity stimulation programme to gain insight into how sports and physical activity were integrated into Dutch rehabilitation care. METHODS: The current implementation status of a sports and

ICNC2003: Proceedings of the seventh international conference on nuclear criticality safety. Challenges in the pursuit of global nuclear criticality safety

International Nuclear Information System (INIS)

2003-10-01

This proceedings contain (technical, oral and poster papers) presented papers at the Seventh International Conference on Nuclear Criticality Safety ICNC2003 held on 20-24 October 2003, in Tokai, Ibaraki, Japan, following ICNC'99 in Versailles, France. The theme of this conference is 'Challenges in the Pursuit of Global Nuclear Criticality Safety'. This proceedings represent the current status of nuclear criticality safety research throughout the world. The 81 of the presented papers are indexed individually. (J.P.N.)

ICNC2003: Proceedings of the seventh international conference on nuclear criticality safety. Challenges in the pursuit of global nuclear criticality safety

International Nuclear Information System (INIS)

2003-10-01

This proceedings contain (technical, oral and poster papers) presented papers at the Seventh International Conference on Nuclear Criticality Safety ICNC2003 held on 20-24 October 2003, in Tokai, Ibaraki, Japan, following ICNC'99 in Versailles, France. The theme of this conference is 'Challenges in the Pursuit of Global Nuclear Criticality Safety'. This proceedings represent the current status of nuclear criticality safety research throughout the world. The 79 of the presented papers are indexed individually. (J.P.N.)

Indirect dark matter searches: current status and perspectives

CERN Multimedia

CERN. Geneva

2016-01-01

Many theoretical ideas for the particle nature of dark matter exist. The  most popular models often predict that dark matter particles self-annihilate or decay, giving rise to potentially detectable signatures in astronomical observations.  I will summarize the current status of searches for such signatures and critically reassess recent claims for dark matter signals.  I will further provide an outlook on anticipated developments in the next 10 years, and discuss new methods to facilitate strategy development.

ZnO growth technologies: current status and perspectives

International Nuclear Information System (INIS)

Lupan, Oleg

2011-01-01

Development of new technologies for ZnO nano materials and thin films is of critical importance for further fundamental investigations and practical applications. We discuss on the main technical control of the synthesis of zinc oxide and its properties, which are of significance in understanding the growth mechanism and further developing ZnO-based devices. Next, we present a brief summary of recent research activities, current status and progress in developing improved control of technological processes for zinc oxide as advanced material.

Criticality safety research on nuclear fuel cycle facility

Energy Technology Data Exchange (ETDEWEB)

Miyoshi, Yoshinori [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

2004-07-01

This paper present d s current status and future program of the criticality safety research on nuclear fuel cycle made by Japan Atomic Energy Research Institute. Experimental research on solution fuel treated in reprocessing plant has been performed using two critical facilities, STACY and TRACY. Fundamental data of static and transient characteristics are accumulated for validation of criticality safety codes. Subcritical measurements are also made for developing a monitoring system for criticality safety. Criticality safety codes system for solution and power system, and evaluation method related to burnup credit are developed. (author)

Investigation on Current Status of World Nuclear Education and Training

International Nuclear Information System (INIS)

Shin, J. Y.; Min, M. J.; Noh, B. C.

2010-04-01

All over the world, the interest of nuclear energy is increasing and the expectations of it are getting more as one of the most practical alternative energy resources. However, since 1990s, as a lot of nuclear specialists are being retired, now the problem of manpower shortage is taken into consideration for all of us and will be continued until 2011. In this point of view, the good quality of the professional nuclear training and education systems and the nuclear education centers are requested in order to breed and supply the next generation nuclear scientists and engineers. Thus, the objective of this study is to explore the current status of world nuclear education for both of nuclear power countries and potential nuclear power utilization countries in the near future. This report introduces the importance of nuclear energy, the current status of world nuclear power plants operation and the contribution of nuclear energy. Besides, it also includes the nuclear energy development plan of potential nuclear developing countries in the near future. In addition, this study also explores the nuclear training and education systems of the nuclear development countries and the current status of nuclear education in various fields such as government, industries, nuclear power plants ect. Especially, as considering the status of nuclear education classified such as Asia, the Americas, East and West Europe, the Middle East and Africa, it shows the different characteristics of nuclear education systems in each regions aimed to identify the good practices on the nuclear education systems. Finally, through observation of international cooperation and networks of the various nuclear organizations, this will be contributed to the development of nuclear education for member states and be suggested the various of the direction of development for nuclear education in Korea. The report presents in the basis of the recent status data of the world nuclear education systems collected

Current status of quantitative rotational spectroscopy for atmospheric research

Science.gov (United States)

Drouin, Brian J.; Wlodarczak, Georges; Colmont, Jean-Marcel; Rohart, Francois

2004-01-01

Remote sensing of rotational transitions in the Earth's atmosphere has become an important method for the retrieval of geophysical temperatures, pressures and chemical composition profiles that requires accurate spectral information. This paper highlights the current status of rotational data that are useful for atmospheric measurements, with a discussion of the types the rotational lineshape measurements that are not generally available in either online repository.

Review of the current status of radiation risk estimates

International Nuclear Information System (INIS)

Charles, M.W.; Little, M.P.

1988-10-01

This report reviews the current status of radiation risk estimation for low linear energy transfer radiation. Recent statements by various national and international organisations regarding risk estimates are critically discussed. The recently published revised population risk estimates from the study of Japanese bomb survivors are also reviewed and used with some unpublished data from Japan to calculate risk figures for a general work force. (author)

Present status and improvement approach of atomic energy laws and safety standards

International Nuclear Information System (INIS)

Oh, B. J.; An, H. J.; Kim, S. W.; Kim, C. B.; Kang, S. C.; Lee, J. I.

2000-01-01

Major revision to the atomic energy act, which is currently undergoing are introduced: increase of members of nuclear safety commission, adoption of standard design certification, periodic safety review, production license system of radioactive isotope facilities, preparation for implementation of IAEA convention. Improvement of the notice of ministry of science and technology are discussed in accordance with the new atomic energy act, enforcement detect, and enforcement regulations, whose revision were completed in May 2000. Allocation of the code number to the notice, development procedures for the safety and regulatory guides are also introduced

Current Diagnosis, Treatment and Etiology of Status Epilepticus

Directory of Open Access Journals (Sweden)

Çetin Kürşad Akpınar

2014-03-01

Full Text Available Status Epilepticus (SE is a medical emergency that causes significant morbidity and mortality and requires prompt diagnosis and treatment. Although SE can be divided into two subgroups as convulsive and nonconvulsive, treatment principles are generally similar. Treatment should be prompt and underlying cause should be corrected. Although intravenous lorazepam is the first-line treatment due to a lower risk of relapse, diazepam becomes the first choice since loeazepan is not available in our country. Even though intravenous benzodiazepine stops seizures, intravenous antiepileptic drug (phenytoin, etc. should be administered at a loading dose. Patients with refractory status epilepticus should be supported with respect to vital, respiratory, metabolic and hemodynamic aspects and followed up in an intensive care unit to monitor cerebral electrical activity. The most common cause in the etiology is the cessation of antiepileptic drugs. The aim of SE treatment is to stop seizures and prevent complications and recurrence. In this paper, current diagnosis, treatment and etiology of SE are reviewed.

Current Status of Mycotoxin Contamination of Food Commodities in Zimbabwe

Directory of Open Access Journals (Sweden)

Nancy Nleya

2018-05-01

Full Text Available Agricultural products, especially cereal grains, serve as staple foods in sub-Saharan Africa. However, climatic conditions in this region can lead to contamination of these commodities by moulds, with subsequent production of mycotoxins posing health risks to both humans and animals. There is limited documentation on the occurrence of mycotoxins in sub-Saharan African countries, leading to the exposure of their populations to a wide variety of mycotoxins through consumption of contaminated foods. This review aims at highlighting the current status of mycotoxin contamination of food products in Zimbabwe and recommended strategies of reducing this problem. Zimbabwe is one of the African countries with very little information with regards to mycotoxin contamination of its food commodities, both on the market and at household levels. Even though evidence of multitoxin occurrence in some food commodities such as maize and other staple foods exist, available published research focuses only on Aspergillus and Fusarium mycotoxins, namely aflatoxins, deoxynivalenol (DON, trichothecenes, fumonisins, and zearalenone (ZEA. Occurrence of mycotoxins in the food chain has been mainly associated with poor agricultural practices. Analysis of mycotoxins has been done mainly using chromatographic and immunological methods. Zimbabwe has adopted European standards, but the legislation is quite flexible, with testing for mycotoxin contamination in food commodities being done voluntarily or upon request. Therefore, the country needs to tighten its legislation as well as adopt stricter standards that will improve the food safety and security of the masses.

Current Status of Mycotoxin Contamination of Food Commodities in Zimbabwe.

Science.gov (United States)

Nleya, Nancy; Adetunji, Modupeade Christianah; Mwanza, Mulunda

2018-05-03

Agricultural products, especially cereal grains, serve as staple foods in sub-Saharan Africa. However, climatic conditions in this region can lead to contamination of these commodities by moulds, with subsequent production of mycotoxins posing health risks to both humans and animals. There is limited documentation on the occurrence of mycotoxins in sub-Saharan African countries, leading to the exposure of their populations to a wide variety of mycotoxins through consumption of contaminated foods. This review aims at highlighting the current status of mycotoxin contamination of food products in Zimbabwe and recommended strategies of reducing this problem. Zimbabwe is one of the African countries with very little information with regards to mycotoxin contamination of its food commodities, both on the market and at household levels. Even though evidence of multitoxin occurrence in some food commodities such as maize and other staple foods exist, available published research focuses only on Aspergillus and Fusarium mycotoxins, namely aflatoxins, deoxynivalenol (DON), trichothecenes, fumonisins, and zearalenone (ZEA). Occurrence of mycotoxins in the food chain has been mainly associated with poor agricultural practices. Analysis of mycotoxins has been done mainly using chromatographic and immunological methods. Zimbabwe has adopted European standards, but the legislation is quite flexible, with testing for mycotoxin contamination in food commodities being done voluntarily or upon request. Therefore, the country needs to tighten its legislation as well as adopt stricter standards that will improve the food safety and security of the masses.

Recent and current activities of the OECD/NEA Working Group on Fuel Safety (NEA/CSNI). Recent and Current Activities of the Working Group on Fuel Safety (NEA/CSNI)

International Nuclear Information System (INIS)

Petit, Marc

2013-01-01

The Working Group on Fuel Safety (WGFS) is part of the Committee on the Safety of Nuclear Installations (CSNI) of the Nuclear Energy Agency and has the main mission of advancing the current understanding and addressing fuel safety issues. Recent and current activities of the working group have addressed mainly the loss of coolant accident (LOCA), the reactivity initiated accident (RIA), the fuel safety criteria and leaking fuel issues, as well as Fukushima-related fuel topics. In the area of LOCA, the group issued different documents, the most notable being a very comprehensive state of the art report [NEA/CSNI/R (2009)15]. Regarding RIA, some documents were finalised and issued in the recent years, as well as a state of the art report [NEA/CSNI/R (2010)1]. The question of leaking fuel and how it is handled in the reactors is an activity that is just starting. Of particular interest to people developing new fuel concepts is the Nuclear Fuel Safety Criteria Technical Review - Second Edition [NEA/CSNI/R (2012)3]. This document provides a broad overview of the numerous criteria used in the NEA member countries to demonstrate to safe use of fuel in light water reactors. The WGFS has started discussions about fuel related issues raised by the Fukushima accident, in particular, hydrogen production. New concepts have been proposed to solve these issues but it appears that these concepts will need to go through a long qualification process to assess their adequacy for the different situations considered in the evaluation of fuel safety, from normal operation to accident conditions

Safety of research reactors (Design and Operation)

International Nuclear Information System (INIS)

Dirar, H. M.

2012-06-01

The primary objective of this thesis is to conduct a comprehensive up-to-date literature review on the current status of safety of research reactor both in design and operation providing the future trends in safety of research reactors. Data and technical information of variety selected historical research reactors were thoroughly reviewed and evaluated, furthermore illustrations of the material of fuel, control rods, shielding, moderators and coolants used were discussed. Insight study of some historical research reactors was carried with considering sample cases such as Chicago Pile-1, F-1 reactor, Chalk River Laboratories,. The National Research Experimental Reactor and others. The current status of research reactors and their geographical distribution, reactor category and utilization is also covered. Examples of some recent advanced reactors were studied like safety barriers of HANARO of Korea including safety doors of the hall and building entrance and finger print identification which prevent the reactor from sabotage. On the basis of the results of this research, it is apparent that a high quality of safety of nuclear reactors can be attained by achieving enough robust construction, designing components of high levels of efficiency, replacing the compounds of the reactor in order to avoid corrosion and degradation with age, coupled with experienced scientists and technical staffs to operate nuclear research facilities.(Author)

Current Methods Applied to Biomaterials - Characterization Approaches, Safety Assessment and Biological International Standards.

Science.gov (United States)

Oliveira, Justine P R; Ortiz, H Ivan Melendez; Bucio, Emilio; Alves, Patricia Terra; Lima, Mayara Ingrid Sousa; Goulart, Luiz Ricardo; Mathor, Monica B; Varca, Gustavo H C; Lugao, Ademar B

2018-04-10

Safety and biocompatibility assessment of biomaterials are themes of constant concern as advanced materials enter the market as well as products manufactured by new techniques emerge. Within this context, this review provides an up-to-date approach on current methods for the characterization and safety assessment of biomaterials and biomedical devices from a physicalchemical to a biological perspective, including a description of the alternative methods in accordance with current and established international standards. Copyright© Bentham Science Publishers; For any queries, please email at epub@benthamscience.org.

The Current Status of Teachers and the Teaching Profession in ...

African Journals Online (AJOL)

This paper examines the current status of teachers and the teaching sector in Tanzania. It draws on experiences of teachers, parents, and students in Dar es Salaam, Iringa and Mbeya regions. Informed by the qualitative inquiry, the paper is largely empirical in character. Data was sought through interviews and document ...

Safety Parameter Considerations of Anodal Transcranial Direct Current Stimulation in Rats

Science.gov (United States)

2017-10-01

Richardson, J.D., Baker, J.M., Rorden, C., 2011. Transcranial direct current stimulation improves naming reaction time in fluent aphasia: a...AFRL-RH-WP-TR-2017-0069 Safety parameter considerations of anodal transcranial Direct Current Stimulation in rats R. Andy McKinley...response, including the time for reviewing instructions, searching existing data sources, searching existing data sources, gathering and maintaining the

Small modular reactors: current status, economic aspects and licensing

International Nuclear Information System (INIS)

Zimbron E, E.; Puente E, F.

2014-10-01

Interest for nuclear energy had resurgence since the beginning of the new century. This was a consequence of the new world conditions and needs: increasing energy demands (mainly from developing countries), awareness of the importance of energetic security and the necessity of limiting carbon emissions. In this nuclear boom, Small Modular Reactors (SMRs) develop and start to consolidate as a viable option for the present energy market. Their modular characteristics, lower initial capital cost, passive safety features and their niche applications, situate them as a technology with various advantages. The following study will present and analysis that will help to comprehend the SMRs present status. Information will show planned reactors, reactors in construction and in operation, advantages and challenges of their implementation, relevant economic aspects and important licensing factors that need to be highlighted. The analysis showed that the SMR technology is still in an initial stage that could reach and important development point in the next ten years. In this period, many of the reactors that are in design stage or that are through their licensing process might be constructed and could be getting ready for a commercial status. On the other hand, it has been observed that there are two main economic factors that need to be considered for any SMRs implementation project. First, the costs (initial, operation, maintenance, fuel and decommissioning) and second their possible niche market applications. Additionally, it has been noted that the licensing process is one of the greatest challenges for SMR general development. Licensing is mainly related to topic such as Emergency Planning Zone, first-of-a-kind engineering, passive safety features, proliferation resistance, multiple module designs and staffing. Previous information will serve as a base for carrying out a feasibility assessment analysis for SMR in Mexico. This part will be the last section of the project

Small modular reactors: current status, economic aspects and licensing

Energy Technology Data Exchange (ETDEWEB)

Zimbron E, E. [Instituto Tecnologico de Estudios Superiores de Monterrey, Campus Santa Fe, Av. Carlos Lazo No. 100, Santa Fe, 01389 Mexico D. F. (Mexico); Puente E, F., E-mail: erick.zimbron@gmail.com [ININ, Direccion de Investigacion Cientifica, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

2014-10-15

Interest for nuclear energy had resurgence since the beginning of the new century. This was a consequence of the new world conditions and needs: increasing energy demands (mainly from developing countries), awareness of the importance of energetic security and the necessity of limiting carbon emissions. In this nuclear boom, Small Modular Reactors (SMRs) develop and start to consolidate as a viable option for the present energy market. Their modular characteristics, lower initial capital cost, passive safety features and their niche applications, situate them as a technology with various advantages. The following study will present and analysis that will help to comprehend the SMRs present status. Information will show planned reactors, reactors in construction and in operation, advantages and challenges of their implementation, relevant economic aspects and important licensing factors that need to be highlighted. The analysis showed that the SMR technology is still in an initial stage that could reach and important development point in the next ten years. In this period, many of the reactors that are in design stage or that are through their licensing process might be constructed and could be getting ready for a commercial status. On the other hand, it has been observed that there are two main economic factors that need to be considered for any SMRs implementation project. First, the costs (initial, operation, maintenance, fuel and decommissioning) and second their possible niche market applications. Additionally, it has been noted that the licensing process is one of the greatest challenges for SMR general development. Licensing is mainly related to topic such as Emergency Planning Zone, first-of-a-kind engineering, passive safety features, proliferation resistance, multiple module designs and staffing. Previous information will serve as a base for carrying out a feasibility assessment analysis for SMR in Mexico. This part will be the last section of the project

Status of nuclear safety research - 2000

International Nuclear Information System (INIS)

Sobajima, Makoto; Sasajima, Hideo; Umemoto, Michitaka; Yamamoto, Toshihiro; Tanaka, Tadao; Togashi, Yoshihiro; Nakata, Masahito

2000-11-01

The nuclear safety research at JAERI is performed in accordance with the long term plan on nuclear research, development and use and the safety research yearly plan determined by the government and under close relationship to the related departments in and around the Nuclear Safety Research Center. The criticality accident having occurred in Tokai-mura in 1999 has been the highest level nuclear accident in Japan and ensuring safety in whole nuclear cycle is severely questioned. The causes of such an accident have to be clarified not only technical points but also organizational points, and it is extremely important to make efforts in preventing recurrence, to fulfill emergency plan and to improve the safety of whole nuclear fuel cycle for restoring the reliability by the people to nuclear energy system. The fields of conducting safety research are engineering safety research on reactor facilities and nuclear fuel cycle facilities including research on radioactive waste processing and disposal and research and development on future technology for safety improvement. Also, multinational cooperation and bilateral cooperation are promoted in international research organizations in the center to internationally share the recognition of world-common issues of nuclear safety and to attain efficient promotion of research and effective utilization of research resources. (author)

The Current Status of Sport Sociology within American and Canadian Colleges and Universities.

Science.gov (United States)

Brooks, Dana D.

The purpose of this study was to investigate the current status of sport sociology within American and Canadian Colleges and Universities. The study investigated: (1) the number of graduate and undergraduate courses offered in sport sociology; (2) current research area(s) of interest within sport sociology; (3) current text used as reference and…

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

International Nuclear Information System (INIS)

David Trickett

1998-01-01

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

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

Energy Technology Data Exchange (ETDEWEB)

Trickett, D.

1998-12-15

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

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.

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

Corporate Blended Learning in Portugal: Current Status and Future Directions

Science.gov (United States)

Marcal, Julia; Caetano, Antonio

2010-01-01

The aim of this study is to characterize the current status of blended learning in Portugal, given that b-learning has grown exponentially in the Portuguese market over recent years. 38 organizations (representing 68% of all institutions certified to provide distance training by the Government Labour Office--DGERT-) participated in this study. The…

The current status of mango farming business in Ghana: A case ...

African Journals Online (AJOL)

The current status of mango farming business in Ghana: A case study of mango farming in the Dangme West District. ... Mango (Mangifera indica L.) is a crop which is assuming great economic importance in Ghana. ... HOW TO USE AJOL.

Current status, questions and challenges of transcatheter uterine artery embolization for the treatment of uterine fibroids

International Nuclear Information System (INIS)

Chen Xiaoming; Luo Pengfei

2006-01-01

Current status, questions and challenges of transcatheter uterine artery embolization (UAE) in the treatment of uterine fibroids were summarized and analysed. It has been proved that UAE presents a good effectiveness in controlling the symptoms and shrinkage of fibroid and uterine volumes during follow-up of 4 to 6.9 years domestically and abroad, but relapse of the fibroid may however occur in 2 years or longer after UAE. Generally speaking, UAE is safe in the treatment of uterine fibroids but has a possibility of serious complications. UAE has no damage on normal uterine tissues but may affect pregnancy and delivery of patients significantly later on the cause of hypoxia and inertia of uterus. UAE may cause amenorrhea in the minority of women with ovarian failure and endometrium atrophy. The current questions are how to improve long-term efficiency to reduce relapse of tumor and to insure the safety of UAE. It is our further task to exploit more new effective and safe embolic agents by using animal and clinical study on the basic knowledge of pathology, pharmacology, biochemistry, endocrinology and molecular biology. (authors)

Current status of nuclear engineering education

International Nuclear Information System (INIS)

Palladino, N.J.

1975-01-01

The 65 colleges and universities offering undergraduate degrees in nuclear engineering and the 15 schools offering strong nuclear engineering options are, in general, doing a good job to meet the current spectrum of job opportunities. But, nuclear engineering programs are not producing enough graduates to meet growing demands. They currently receive little aid and support from their customers --industry and government--in the form of scholarships, grants, faculty research support, student thesis and project support, or student summer jobs. There is not enough interaction between industry and universities. Most nuclear engineering programs are geared too closely to the technology of the present family of reactors and too little to the future breeder reactors and controlled thermonuclear reactors. In addition, nuclear engineering programs attract too few women and members of minority ethnic groups. Further study of the reasons for this fact is needed so that effective corrective action can be taken. Faculty in nuclear engineering programs should assume greater initiative to provide attractive and objective nuclear energy electives for technical and nontechnical students in other disciplines to improve their technical understanding of the safety and environmental issues involved. More aggressive and persistent efforts must be made by nuclear engineering schools to obtain industry support and involvement in their programs

The status of safety in the public high school chemistry laboratories in Mississippi

Science.gov (United States)

Lacy, Sarah Louise Trotman

Since laboratory-based science courses have become an essential element of any science curriculum and are required by the Mississippi Department of Education for graduation, the chemistry laboratories in the public high schools in Mississippi must be safe. The purpose of this study was to determine: the safety characteristics of a high school chemistry laboratory; the perceived safety characteristics of the chemistry laboratories in public high schools in Mississippi; the basic safety knowledge of chemistry teachers in public high schools in Mississippi, where chemistry teachers in Mississippi gain knowledge about laboratory safety and instruction; if public high school chemistry laboratories in Mississippi adhere to recommended class size, laboratory floor space per student, safety education, safety equipment, and chemical storage; and the relationship between teacher knowledge of chemistry laboratory safety and the safety status of the laboratory in which they teach. The survey instrument was composed of three parts. Part I Teacher Knowledge consisted of 23 questions concerning high school chemistry laboratory safety. Part II Chemistry Laboratory Safety Information consisted of 40 items divided into four areas of interest concerning safety in high school chemistry laboratories. Part III Demographics consisted of 11 questions relating to teacher certification, experience, education, and safety training. The survey was mailed to a designated chemistry teacher in every public high school in Mississippi. The responses to Part I of the survey indicated that the majority of the teachers have a good understanding of knowledge about chemistry laboratory safety but need more instruction on the requirements for a safe high school chemistry laboratory. Less than 50% of the responding teachers thought they had received adequate preparation from their college classes to conduct a safe chemistry laboratory. According to the responses of the teachers, most of their high school

Investigation of assumptions underlying current safety guidelines on EM-induced nerve stimulation

Science.gov (United States)

Neufeld, Esra; Vogiatzis Oikonomidis, Ioannis; Iacono, Maria Ida; Angelone, Leonardo M.; Kainz, Wolfgang; Kuster, Niels

2016-06-01

An intricate network of a variety of nerves is embedded within the complex anatomy of the human body. Although nerves are shielded from unwanted excitation, they can still be stimulated by external electromagnetic sources that induce strongly non-uniform field distributions. Current exposure safety standards designed to limit unwanted nerve stimulation are based on a series of explicit and implicit assumptions and simplifications. This paper demonstrates the applicability of functionalized anatomical phantoms with integrated coupled electromagnetic and neuronal dynamics solvers for investigating the impact of magnetic resonance exposure on nerve excitation within the full complexity of the human anatomy. The impact of neuronal dynamics models, temperature and local hot-spots, nerve trajectory and potential smoothing, anatomical inhomogeneity, and pulse duration on nerve stimulation was evaluated. As a result, multiple assumptions underlying current safety standards are questioned. It is demonstrated that coupled EM-neuronal dynamics modeling involving realistic anatomies is valuable to establish conservative safety criteria.

Research for enhancing reactor safety

International Nuclear Information System (INIS)

1989-05-01

Recent research for enhanced reactor safety covers extensive and numerous experiments and computed modelling activities designed to verify and to improve existing design requirements. The lectures presented at the meeting report GRS research results and the current status of reactor safety research in France. The GRS experts present results concerning expert systems and their perspectives in safety engineering, large-scale experiments and their significance in the development and verification of computer codes for thermohydraulic modelling of safety-related incidents, the advanced system code ATHLET for analysis of thermohydraulic processes of incidents, the analysis simulator which is a tool for fast evaluation of accident management measures, and investigations into event sequences and the required preventive emergency measures within the German Risk Study. (DG) [de

Current and past menstrual status is an important determinant of femoral neck geometry in exercising women.

Science.gov (United States)

Mallinson, Rebecca J; Williams, Nancy I; Gibbs, Jenna C; Koehler, Karsten; Allaway, Heather C M; Southmayd, Emily; De Souza, Mary Jane

2016-07-01

Menstrual status, both past and current, has been established as an important determinant of bone mineral density (BMD) in young exercising women. However, little is known regarding the association between the cumulative effect of menstrual status and indices of bone health beyond BMD, such as bone geometry and estimated bone strength. This study explores the association between cumulative menstrual status and indices of bone health assessed using dual-energy x-ray absorptiometry (DXA), including femoral neck geometry and strength and areal BMD (aBMD), in exercising women. 101 exercising women (22.0±0.4years, BMI 21.0±0.2kg/m(2), 520±40min/week of self-reported exercise) participated in this cross-sectional study. Women were divided into three groups as follows based on their self-reported current and past menstrual status: 1) current and past regular menstrual cycles (C+P-R) (n=23), 2) current and past irregular menstrual cycles (C+P-IR) (n=56), 3) and current or past irregular cycles (C/P-RIR) (n=22). Current menstrual status was confirmed using daily urinary metabolites of reproductive hormones. DXA was used to assess estimates of femoral neck geometry and strength from hip strength analysis (HSA), aBMD, and body composition. Cross-sectional moment of inertia (CSMI), cross-sectional area (CSA), strength index (SI), diameter, and section modulus (Z) were calculated at the femoral neck. Low CSMI, CSA, SI, diameter, and Z were operationally defined as values below the median. Areal BMD (g/cm(2)) and Z-scores were determined at the lumbar spine, femoral neck, and total hip. Low BMD was defined as a Z-score0.05). However, after controlling for confounding variables, cumulative menstrual status was not a significant predictor of low aBMD. In exercising women, the cumulative effect of current and past menstrual irregularity appears to be an important predictor of lower estimates of femoral neck geometry, as observed by smaller CSMI and CSA, which may serve as an

Thermoelectric microgenerators. Current status and prospects of application

Directory of Open Access Journals (Sweden)

Strutynska L. T.

2008-08-01

Full Text Available Analysis of current status and prospects of using thermoelectric microgenerators, including organic-fueled ones, is performed. Developments of thermoelectric microgenerators presented in this review demonstrate that their increasingly wide use forms a separate, very important line of thermoelectricity – micropower generation with growing potential of practical applications for charging batteries, mobile phones, digital cameras and photocameras, power supply to small radio stations, other portable devices, including medical. The ways of increasing the efficiency of such devices and relevant lines of their wide use in practice are determined.

Current status of the nuclear medicine in Japan

International Nuclear Information System (INIS)

Torizuka, K.

1974-01-01

A brief survey of the current status of Japan nuclear medicine is given. The following data are described (from the material of the 11th Japan Conference of Radioisotopes): 1. the increase of the number of nuclear instruments between 1971 and 1973; 2. the total amount of the cobalt radiation apparatur (inclusive of the cesium apparatus) in the hospitals in 1971- and 1972; 3. the radioactive medicines and nuclids used in Japan; 4. the radioactive isotopes used generally in the therapeutics in 1971 and 1972; 5. the question of labour. (K.A.)

Efficacy of Web-Based Instruction to Provide Training on Federal Motor Carrier Safety Regulations

Science.gov (United States)

2011-05-01

This report presents an evaluation of the current state-of-the-art Web-based instruction (WBI), reviews the current computer platforms of potential users of WBI, reviews the current status of WBI applications for Federal Motor Carrier Safety Administ...

Safety pharmacology — Current and emerging concepts

International Nuclear Information System (INIS)

Hamdam, Junnat; Sethu, Swaminathan; Smith, Trevor; Alfirevic, Ana; Alhaidari, Mohammad; Atkinson, Jeffrey; Ayala, Mimieveshiofuo; Box, Helen; Cross, Michael; Delaunois, Annie; Dermody, Ailsa; Govindappa, Karthik; Guillon, Jean-Michel; Jenkins, Rosalind; Kenna, Gerry; Lemmer, Björn; Meecham, Ken; Olayanju, Adedamola; Pestel, Sabine; Rothfuss, Andreas

2013-01-01

Safety pharmacology (SP) is an essential part of the drug development process that aims to identify and predict adverse effects prior to clinical trials. SP studies are described in the International Conference on Harmonisation (ICH) S7A and S7B guidelines. The core battery and supplemental SP studies evaluate effects of a new chemical entity (NCE) at both anticipated therapeutic and supra-therapeutic exposures on major organ systems, including cardiovascular, central nervous, respiratory, renal and gastrointestinal. This review outlines the current practices and emerging concepts in SP studies including frontloading, parallel assessment of core battery studies, use of non-standard species, biomarkers, and combining toxicology and SP assessments. Integration of the newer approaches to routine SP studies may significantly enhance the scope of SP by refining and providing mechanistic insight to potential adverse effects associated with test compounds. - Highlights: • SP — mandatory non-clinical risk assessments performed during drug development. • SP organ system studies ensure the safety of clinical participants in FiH trials. • Frontloading in SP facilitates lead candidate drug selection. • Emerging trends: integrating SP-Toxicological endpoints; combined core battery tests

Safety pharmacology — Current and emerging concepts

Energy Technology Data Exchange (ETDEWEB)

Hamdam, Junnat; Sethu, Swaminathan; Smith, Trevor; Alfirevic, Ana; Alhaidari, Mohammad [MRC Centre for Drug Safety Science, University of Liverpool (United Kingdom); Atkinson, Jeffrey [Lorraine University Pharmacolor Consultants Nancy PCN (France); Ayala, Mimieveshiofuo; Box, Helen; Cross, Michael [MRC Centre for Drug Safety Science, University of Liverpool (United Kingdom); Delaunois, Annie [UCB Pharma (Belgium); Dermody, Ailsa; Govindappa, Karthik [MRC Centre for Drug Safety Science, University of Liverpool (United Kingdom); Guillon, Jean-Michel [Sanofi-aventis (France); Jenkins, Rosalind [MRC Centre for Drug Safety Science, University of Liverpool (United Kingdom); Kenna, Gerry [Astra-Zeneca (United Kingdom); Lemmer, Björn [Ruprecht-Karls-Universität Heidelberg (Germany); Meecham, Ken [Huntingdon Life Sciences (United Kingdom); Olayanju, Adedamola [MRC Centre for Drug Safety Science, University of Liverpool (United Kingdom); Pestel, Sabine [Boehringer-Ingelheim (Germany); Rothfuss, Andreas [Roche (Switzerland); and others

2013-12-01

Safety pharmacology (SP) is an essential part of the drug development process that aims to identify and predict adverse effects prior to clinical trials. SP studies are described in the International Conference on Harmonisation (ICH) S7A and S7B guidelines. The core battery and supplemental SP studies evaluate effects of a new chemical entity (NCE) at both anticipated therapeutic and supra-therapeutic exposures on major organ systems, including cardiovascular, central nervous, respiratory, renal and gastrointestinal. This review outlines the current practices and emerging concepts in SP studies including frontloading, parallel assessment of core battery studies, use of non-standard species, biomarkers, and combining toxicology and SP assessments. Integration of the newer approaches to routine SP studies may significantly enhance the scope of SP by refining and providing mechanistic insight to potential adverse effects associated with test compounds. - Highlights: • SP — mandatory non-clinical risk assessments performed during drug development. • SP organ system studies ensure the safety of clinical participants in FiH trials. • Frontloading in SP facilitates lead candidate drug selection. • Emerging trends: integrating SP-Toxicological endpoints; combined core battery tests.

The Use and Development of Probabilistic Safety Assessment in NEA Member Countries

International Nuclear Information System (INIS)

2002-01-01

The mission of the CSNI is to assist Member countries in maintaining and further developing the scientific and technical knowledge base required to assess the safety of nuclear reactors and fuel cycle facilities. The mission of the Working Group on Risk Assessment (WGRisk) is to advance the understanding and utilisation of Probabilistic Safety Assessment (PSA) in ensuring continued safety of nuclear installations in Member countries. In pursuing this goal, the Working Group shall recognize the different methodologies for identifying contributors to risk and assessing their importance. While the Working Group shall continue to focus on the more mature PSA methodologies for Level 1, Level 2, internal, external, shutdown, etc. It shall also consider the applicability and maturity of PSA methods for considering evolving issues such as human reliability, software reliability, ageing issues, etc., as appropriate. This report provides descriptions of the current status of PSA programmes in Member countries including basic background information, guidelines, various PSA applications, major results in recent studies, PSA based plant modifications and research and development topics. While the compilation is a not complete compilation it provides a 'snapshot' of the current situation in the Member countries and hence it provides reference information and various insights to both the PSA practician and others involved in the nuclear industry. The terms PSA (Probabilistic Safety Assessment) and PRA (Probabilistic Risk Assessment) are utilised to denote this subject. In each of the chapters the objective is to present a 'snapshot' of the current status. The main issues considered in the different chapters are Background Information, Quantitative Safety Guidelines, Status of PSA Programmes, PSA Applications, PSA Related Research and Development and PSA Based Plant Modifications. It is important to note that the information contained in this report represents current practices in

Controlling the HIV/AIDS epidemic: current status and global challenges

Directory of Open Access Journals (Sweden)

Thorsten eDemberg

2012-08-01

Full Text Available This review provides an overview of the current status of the global HIV pandemic and strategies to bring it under control. It updates numerous preventive approaches including behavioral interventions, male circumcision, pre- and post-exposure prophylaxis, vaccines, and microbicides. The manuscript summarizes current anti-retroviral treatment options, their impact in the western world, and difficulties faced by emerging and resource-limited nations in providing and maintaining appropriate treatment regimens. Current clinical and pre-clinical approaches towards a cure for HIV are described, including new drug compounds that target viral reservoirs and gene therapy approaches aimed at altering susceptibility to HIV infection. Recent progress in vaccine development is summarized, including novel approaches and new discoveries.

The Current Status of Classroom Inclusion Activities of Secondary Agriculture Teachers

Science.gov (United States)

Hoerst, Caryn M.; Whittington, M. Susie

2009-01-01

The current status of classroom inclusion activities among agriculture teachers in comprehensive secondary agricultural education programs in Ohio is reported. The researchers describe secondary agriculture teachers' needs related to teaching learners with special needs in inclusion classes, given legislative mandates. Specifically, the…

Patient safety in external beam radiotherapy, results of the ACCIRAD project: Current status of proactive risk assessment, reactive analysis of events, and reporting and learning systems in Europe.

Science.gov (United States)

Malicki, Julian; Bly, Ritva; Bulot, Mireille; Godet, Jean-Luc; Jahnen, Andreas; Krengli, Marco; Maingon, Philippe; Prieto Martin, Carlos; Przybylska, Kamila; Skrobała, Agnieszka; Valero, Marc; Jarvinen, Hannu

2017-04-01

To describe the current status of implementation of European directives for risk management in radiotherapy and to assess variability in risk management in the following areas: 1) in-country regulatory framework; 2) proactive risk assessment; (3) reactive analysis of events; and (4) reporting and learning systems. The original data were collected as part of the ACCIRAD project through two online surveys. Risk assessment criteria are closely associated with quality assurance programs. Only 9/32 responding countries (28%) with national regulations reported clear "requirements" for proactive risk assessment and/or reactive risk analysis, with wide variability in assessment methods. Reporting of adverse error events is mandatory in most (70%) but not all surveyed countries. Most European countries have taken steps to implement European directives designed to reduce the probability and magnitude of accidents in radiotherapy. Variability between countries is substantial in terms of legal frameworks, tools used to conduct proactive risk assessment and reactive analysis of events, and in the reporting and learning systems utilized. These findings underscore the need for greater harmonisation in common terminology, classification and reporting practices across Europe to improve patient safety and to enable more reliable inter-country comparisons. Copyright © 2017 Elsevier B.V. All rights reserved.

Study of Grants, new Mexico, uranium miners: current status

International Nuclear Information System (INIS)

Samet, J.M.; Morgan, M.V.; Buechley, R.W.; Key, C.R.; Valdivia, A.A.

1981-01-01

The Uranium Epidemiology Study at the University of New Mexico was initiated in 1977 with the objective of assessing health effects of uranium mining in the Grants, New Mexico, area. The planned approach was a cohort study of mortality that would capitalize on the availability of health records at the Grants Clinic. The first year's work confirmed the study's feasibility (Buechley, 1979). Subsequent efforts have focused on the health and exposure data base and comprehensive follow-up. A retrospective cohort study of early miners is in progress; a prospective cohort study of miners who began working under the current federal standard is planned. This report will summarize the current status of the Uranium Epidemiology Study

Curriculum leadership in the postgraduate: Gap between current and optimal status.

Science.gov (United States)

Avizhgan, Maryam; Jafari, Ebrahim Mirshah; Nasr, Ahmad Reza; Changiz, Tahereh

2015-04-01

Identifying the strengths and weakness points is one of the effective methods to analyze current status, and prioritizing actions based on the gap between current and optimal status is necessary for short-term and long-term planning in departments and colleges. The aim of this study was to determine the gap between current and optimal status of curriculum leadership in the postgraduate courses in two Iranian universities. In this cross-sectional study, a sample of 212 faculty members from the two Iranian universities (one medical and one nonmedical) was randomly selected through stratified random sampling method. Data were collected by using a researcher-made questionnaire, with 55 items categorized in four areas of main dimensions in curriculum leadership. The validity of the questionnaire was determined by curriculum studies scholars, and the reliability was confirmed as the Cronbach's alpha calculated 0.969. Data were analyzed using descriptive and inferential statistics according to the variables. There was a gap in all dimensions and roles. The maximum gap (-1.70) with the highest frequency (98%) were related to "improving the educational atmosphere" dimension. As for items, the maximum gap (-2.41) was related to "society needs and expectations and the labor market" in "curriculum development and revision" dimension. The negative gap between all dimensions of curriculum leadership implies faculty members' dissatisfaction. Curriculum leadership at universities, colleges and departments of the study in all aspects need to be improved. Hence, it is necessary for managers to make use of the viewpoints of the faculty members to decrease the gap.

Alternative (non-animal) methods for cosmetics testing: current status and future prospects-2010.

Science.gov (United States)

Adler, Sarah; Basketter, David; Creton, Stuart; Pelkonen, Olavi; van Benthem, Jan; Zuang, Valérie; Andersen, Klaus Ejner; Angers-Loustau, Alexandre; Aptula, Aynur; Bal-Price, Anna; Benfenati, Emilio; Bernauer, Ulrike; Bessems, Jos; Bois, Frederic Y; Boobis, Alan; Brandon, Esther; Bremer, Susanne; Broschard, Thomas; Casati, Silvia; Coecke, Sandra; Corvi, Raffaella; Cronin, Mark; Daston, George; Dekant, Wolfgang; Felter, Susan; Grignard, Elise; Gundert-Remy, Ursula; Heinonen, Tuula; Kimber, Ian; Kleinjans, Jos; Komulainen, Hannu; Kreiling, Reinhard; Kreysa, Joachim; Leite, Sofia Batista; Loizou, George; Maxwell, Gavin; Mazzatorta, Paolo; Munn, Sharon; Pfuhler, Stefan; Phrakonkham, Pascal; Piersma, Aldert; Poth, Albrecht; Prieto, Pilar; Repetto, Guillermo; Rogiers, Vera; Schoeters, Greet; Schwarz, Michael; Serafimova, Rositsa; Tähti, Hanna; Testai, Emanuela; van Delft, Joost; van Loveren, Henk; Vinken, Mathieu; Worth, Andrew; Zaldivar, José-Manuel

2011-05-01

The 7th amendment to the EU Cosmetics Directive prohibits to put animal-tested cosmetics on the market in Europe after 2013. In that context, the European Commission invited stakeholder bodies (industry, non-governmental organisations, EU Member States, and the Commission's Scientific Committee on Consumer Safety) to identify scientific experts in five toxicological areas, i.e. toxicokinetics, repeated dose toxicity, carcinogenicity, skin sensitisation, and reproductive toxicity for which the Directive foresees that the 2013 deadline could be further extended in case alternative and validated methods would not be available in time. The selected experts were asked to analyse the status and prospects of alternative methods and to provide a scientifically sound estimate of the time necessary to achieve full replacement of animal testing. In summary, the experts confirmed that it will take at least another 7-9 years for the replacement of the current in vivo animal tests used for the safety assessment of cosmetic ingredients for skin sensitisation. However, the experts were also of the opinion that alternative methods may be able to give hazard information, i.e. to differentiate between sensitisers and non-sensitisers, ahead of 2017. This would, however, not provide the complete picture of what is a safe exposure because the relative potency of a sensitiser would not be known. For toxicokinetics, the timeframe was 5-7 years to develop the models still lacking to predict lung absorption and renal/biliary excretion, and even longer to integrate the methods to fully replace the animal toxicokinetic models. For the systemic toxicological endpoints of repeated dose toxicity, carcinogenicity and reproductive toxicity, the time horizon for full replacement could not be estimated.

Status of safety at Areva group facilities. 2007 annual report; Areva, etat de surete des installations nucleaires. Rapport annuel 2007

Energy Technology Data Exchange (ETDEWEB)

NONE

2007-07-01

This report describes the status of nuclear safety and radiation protection in the facilities of the AREVA group and gives information on radiation protection in the service operations, as observed through the inspection programs and analyses carried out by the General Inspectorate in 2007. Having been submitted to the group's Supervisory Board, this report is sent to the bodies representing the personnel. Content: 1 - A look back at 2007 by the AREVA General Inspector: Visible progress in 2007, Implementation of the Nuclear Safety Charter, Notable events; 2 - Status of nuclear safety and radiation protection in the nuclear facilities and service operations: Personnel radiation protection, Event tracking, Service operations, Criticality control, Radioactive waste and effluent management; 3 - Performance improvement actions; 4 - Description of the General Inspectorate; 5 - Glossary.

Prognostics and Health Management of Wind Turbines: Current Status and Future Opportunities

Energy Technology Data Exchange (ETDEWEB)

Sheng, Shuangwen

2016-10-04

This presentation was given at the 2016 Annual Conference of the Prognostics and Health Management Society. It covers the current status and challenges and opportunities of prognostics and health management of wind turbines.

Nanobody Technology for Mycotoxin Detection in the Field of Food Safety: Current Status and Prospects.

Science.gov (United States)

He, Ting; Zhu, Jiang; Nie, Yao; Hu, Rui; Wang, Ting; Li, Peiwu; Zhang, Qi; Yang, Yunhuang

2018-04-29

Mycotoxins, which are toxic, carcinogenic, and/or teratogenic, have posed a threat to food safety and public health. Sensitive and effective determination technologies for mycotoxin surveillance are required. Immunoassays have been regarded as useful supplements to chromatographic techniques. However, conventional antibodies involved in immunoassays are difficult to be expressed recombinantly and are susceptible to harsh environments. Nanobodies (or VHH antibodies) are antigen-binding sites of the heavy-chain antibodies produced from Camelidae. They are found to be expressed easily in prokaryotic or eukaryotic expression systems, more robust in extreme conditions, and facile to be used as surrogates for artificial antigens. These properties make them the promising and environmentally friendly immunoreagents in the next generation of immunoassays. This review briefly describes the latest developments in the area of nanobodies used in mycotoxin detection. Moreover, by integrating the introduction of the principle of nanobodies production and the critical assessment of their performance, this paper also proposes the prospect of nanobodies in the field of food safety in the foreseeable future.

Safety is paramount; Sicherheit ist das oberste Gebot

Energy Technology Data Exchange (ETDEWEB)

NONE

2013-11-15

Since 20 years nuclear power plants provider a contribution to the power supply in Germany. In this long period the safety concept has been approved and was completed ever more. Aim of the safety concept is the operational personnel and the population from ionizing (radioactive) radiation, which arises in the nuclear fission itself or is emitted by the radionuclides produced in the nuclear fission. Base of the safety concept is the concerted action of facility safety, safety management, qualification of co-workers, and living safety culture. German nuclear power plants belong concidedly to the worldwide safest. They were and are currently fitted to the progressing status of technology and offer the guarantee that they also during the remaining operational time are operated on the highest safety level.

Current status and perspectives of cysticercosis and taeniasis in Japan.

Science.gov (United States)

Yamasaki, Hiroshi

2013-02-01

This mini-review describes recent epidemiological trends in cysticercosis and taeniasis in Japan. Some of the topics discussed herein were presented at the first symposium on "Current perspectives of Taenia asiatica researches", that was held in Osong in Chungbuk Province, South Korea, in October 2011 and organized by Prof. K. S. Eom, Chungbuk National University School of Medicine. To better understand the trends in the occurrence of cysticercosis and taeniasis in Japan, clinical cases reported in 2005 have been updated. In addition, the current status of Taenia asiatica infections successively occurring in Japan since 2010 is also discussed.

MONK and MCBEND: Current status and recent developments

International Nuclear Information System (INIS)

Richards, Simon D.; Baker, Chris M.J.; Bird, Adam J.; Cowan, Pat; Davies, Nigel; Dobson, Geoff P.; Fry, Tim C.; Kyrieleis, Albrecht; Smith, Paul N.

2015-01-01

Highlights: • We describe recent developments to the Monte Carlo codes MONK and MCBEND. • MONK is a Monte Carlo code for nuclear criticality and reactor physics analyses. • MCBEND is a Monte Carlo code for radiation shielding and dosimetry analyses. • Improvements include input; physics; scoring; variance reduction; and visualisation. • Parallelisation of MONK and multi-physics coupling are described. - Abstract: MONK® and MCBEND are Monte Carlo software packages for: nuclear criticality and reactor physics; and radiation shielding and dosimetry applications, respectively. The codes are actively developed, maintained and supported by AMEC’s ANSWERS® Software Service in line with the ANSWERS vision of providing easy-to-use software that meets the current and emerging needs of the user community. This paper summarises the current status of MONK and MCBEND and the recent developments which have been carried out to the codes, and their supporting nuclear data libraries and visualisation package

Polycystic ovary syndrome: current status and future perspective

Science.gov (United States)

Barthelmess, Erin K.; Naz, Rajesh K.

2015-01-01

Polycystic ovary syndrome (PCOS) is a widespread reproductive disorder that encompasses many associated health conditions and has an impact on various metabolic processes. PCOS is depicted by hyperandrogenism, polycystic ovaries, and anovulation. It increases the risk of insulin resistance (IR), type 2 diabetes, obesity, and cardiovascular disease. The etiology of the disease remains unclear, and the subjective phenotype makes a united diagnosis difficult among physicians. It seems to be a familial genetic syndrome caused by a combination of environmental and genetic factors. It can be linked with metabolic disorders in first-degree family members. PCOS is the cause of up to 30% of infertility in couples seeking treatment. Currently, there is no cure for PCOS. Despite the growing incidence of this syndrome, limited research has been done that encompasses the entirety of PCOS spectrum. In this review, the current status and possible future perspective will be discussed. PMID:24389146

Current status and future expectation concerning probabilistic risk assessment of NPPs. 1. Features and issues of probabilistic risk assessment methodology

International Nuclear Information System (INIS)

Yamashita, Masahiro

2012-01-01

Probabilistic risk assessment (PRA) of Nuclear Power Plants (NPPs) could play an important role in assuring safety of NPPs. However PRA had not always effectively used, which was indicated in Japanese government's report on Fukushima Daiichi NPP accident. At the Risk Technical Committee (RTC) of Standards Committee of Atomic Energy Society of Japan, preparation of standards (implementing criteria) focusing on PRA methodology and investigation on basic philosophy for use of PRA had been in progress. Based on activities of RTC, a serial in three articles including this described current status and future expectation concerning probabilistic risk assessment of NPPs. This article introduced features and issues of PRA methodology related to the use of PRA. Features of PRA methodology could be shown as (1) systematic and comprehensive understanding of risk, (2) support of grading approach, (3) identification of effective safety upgrade measures and (4) quantitative understanding of effects of uncertainty. Issues of PRA methodology were (1) extension of PRA application area, (2) upgrade of PRA methodology, (3) quality assurance of PRA, (4) treatment of uncertainty and (5) quantitative evaluation criteria. (T. Tanaka)

Status of safety analysis reports

Energy Technology Data Exchange (ETDEWEB)

Cserhati, A

1999-06-01

The safety regulation connected to both of the Atomic Acts from 1980 and 1996 requires preparation of the Preliminary Safety Analysis Report (PSAR) as well as Final SAR (FSAR). In this respect the licensing procedure for the construction and commissioning of Paks NPP did not formally deviate from the standards applied in developed countries; this is particularly true if comparison is made with the standards applied for commissioning NPPs in the second half of the seventies. By the time the overall development of internationally accepted safety standards and some existing deficiencies of earlier SAR made necessary a general reassessment of the plant safety (AGNES project). The carried out PSR for Paks-1 and 2 also added a valuable contribution to the SAR content, however a formal update of SAR is not made yet. A Hungarian nuclear authority decree from 1997 obligates the licensee to prepare and submit a major upgrade of FSAR until the mid of 2000, after finishing the PSR for Paks-3 and 4. From this date a periodic update of FSAR is required every year. The operational license renewal affects only the PSR but not the FSAR updating. The new Nuclear Safety Code outlines the contents of PSAR and FSAR, based on US NRC Reg. Guide 1. 70. Rev. 3. Hungary by now can fulfill the upgrading of SAR without major external technical or financial help. The AGNES project covered the safety analysis chapters of SAR. It was financed mainly by the country. In the project there have been involved in limited cases as performers the VTT (Finland), Belgatom (Belgium), GRS (Germany), etc., the IVO (Finland) fulfilled tasks of an independent reviewer for safety analysis. The AGNES had certain interconnection with the similar IAEA RER safety reassessment project for WWER-440/213. The PSR for Paks-1 and 2 have been carried out by the Paks staff from the resources of the plant. During the evaluation of several parts of Paks-3 and 4 PSR documentation the authority intends to use certain

Status of safety analysis reports

International Nuclear Information System (INIS)

Cserhati, A.

1999-01-01

The safety regulation connected to both of the Atomic Acts from 1980 and 1996 requires preparation of the Preliminary Safety Analysis Report (PSAR) as well as Final SAR (FSAR). In this respect the licensing procedure for the construction and commissioning of Paks NPP did not formally deviate from the standards applied in developed countries; this is particularly true if comparison is made with the standards applied for commissioning NPPs in the second half of the seventies. By the time the overall development of internationally accepted safety standards and some existing deficiencies of earlier SAR made necessary a general reassessment of the plant safety (AGNES project). The carried out PSR for Paks-1 and 2 also added a valuable contribution to the SAR content, however a formal update of SAR is not made yet. A Hungarian nuclear authority decree from 1997 obligates the licensee to prepare and submit a major upgrade of FSAR until the mid of 2000, after finishing the PSR for Paks-3 and 4. From this date a periodic update of FSAR is required every year. The operational license renewal affects only the PSR but not the FSAR updating. The new Nuclear Safety Code outlines the contents of PSAR and FSAR, based on US NRC Reg. Guide 1. 70. Rev. 3. Hungary by now can fulfill the upgrading of SAR without major external technical or financial help. The AGNES project covered the safety analysis chapters of SAR. It was financed mainly by the country. In the project there have been involved in limited cases as performers the VTT (Finland), Belgatom (Belgium), GRS (Germany), etc., the IVO (Finland) fulfilled tasks of an independent reviewer for safety analysis. The AGNES had certain interconnection with the similar IAEA RER safety reassessment project for WWER-440/213. The PSR for Paks-1 and 2 have been carried out by the Paks staff from the resources of the plant. During the evaluation of several parts of Paks-3 and 4 PSR documentation the authority intends to use certain

Current status of endoscopic simulation in gastroenterology fellowship training programs.

Science.gov (United States)

Jirapinyo, Pichamol; Thompson, Christopher C

2015-07-01

Recent guidelines have encouraged gastroenterology and surgical training programs to integrate simulation into their core endoscopic curricula. However, the role that simulation currently has within training programs is unknown. This study aims to assess the current status of simulation among gastroenterology fellowship programs. This questionnaire study consisted of 38 fields divided into two sections. The first section queried program directors' experience on simulation and assessed the current status of simulation at their institution. The second portion surveyed their opinion on the potential role of simulation on the training curriculum. The study was conducted at the 2013 American Gastroenterological Association Training Directors' Workshop in Phoenix, Arizona. The participants were program directors from Accreditation Council for Graduate Medical Education accredited gastroenterology training programs, who attended the workshop. The questionnaire was returned by 69 of 97 program directors (response rate of 71%). 42% of programs had an endoscopic simulator. Computerized simulators (61.5%) were the most common, followed by mechanical (30.8%) and animal tissue (7.7%) simulators, respectively. Eleven programs (15%) required fellows to use simulation prior to clinical cases. Only one program has a minimum number of hours fellows have to participate in simulation training. Current simulators are deemed as easy to use (76%) and good educational tools (65%). Problems are cost (72%) and accessibility (69%). The majority of program directors believe that there is a need for endoscopic simulator training, with only 8% disagreeing. Additionally, a majority believe there is a role for simulation prior to initiation of clinical cases with 15% disagreeing. Gastroenterology fellowship program directors widely recognize the importance of simulation. Nevertheless, simulation is used by only 42% of programs and only 15% of programs require that trainees use simulation prior to

Current status in Japan related to LMNPP

International Nuclear Information System (INIS)

Otsuka, Takehiro

1998-01-01

Current status of nuclear power plants in Japan is presented with the basic concepts against ageing of LWR plants which are considered to continue growing into the 21st century. Life management for aged NPPs is recognized to be important for the safe and reliable operation. In April 1996 MITI published the first report regarding the measures to cope with the aged NPPs. Two BWRs and one PWR were evaluated as aged NPPs in Phase-I Technical evaluation, which concluded that safe operation is possible with correct and adequate maintenance despite operation exceeded 30 years. The technology development items towards attaining further highly reliable management were indicated including the inspection/monitoring technology, the preventive maintenance/repair technology and ageing evaluation technology

Research oil guidelines for safety review of category 2 waste disposal

Energy Technology Data Exchange (ETDEWEB)

NONE

2013-08-15

Safety confirmation items and monitoring items for engineered barriers were compiled, considering the current technical status and monitoring plan for the simulated subsurface disposal and its test facilities. In order to develop the guidelines of the safety review for the disposal of LLW generated from RI facilities and research facilities, technical issues relating toxic substances were surveyed. (author)

The present status of iodine chemistry research in Canada and its application to reactor safety analysis

Energy Technology Data Exchange (ETDEWEB)

Weaver, K R [Ontario Hydro Nuclear, Toronto (Canada); Kupferschmid, W C.H.; Wren, J C; Ball, J M [Atomic Energy of Canada Ltd., Pinawa, MB (Canada). Whiteshell Labs.

1996-12-01

The current need to understand iodine chemistry in a reactor safety context has become more sharply focussed as the level of that understanding has advanced. At the same time, the situations of most concern within containment, from an iodine perspective, are also being redefined in the light of that understanding. The present paper summarises these developments. Over the past five years, considerable advances have occurred in our understanding of iodine chemistry under conditions of interest in reactor accidents. A number of key experiments have yielded important results in the areas of solution chemistry, the role of surfaces, the importance of organics and the effects of impurities. This understanding supplements the already substantial gains made in characterising the key roles of pH and the effects of radiation. All these factors underline the now evident fact that the kinetics of iodine are the controlling factor when radiation is involved, and that a number of reactive species, not present in thermal reactions, effectively control the observed volatility of iodine. In this paper, recent advances are summarised and the present status of our understanding of iodine chemistry is reviewed. Specifically, an attempt is made to identify those areas where our understanding appears to be relatively complete, and to flag the remaining critical areas where our attention is currently focussed. The state of our modelling capability is reviewed, as is the significance or related areas such as the role of mass transfer. Finally, an overview is presented of the significance of this work for reactor safety, and our expectations for its application over the near term future. (author) 2 figs., 12 refs.

The present status of iodine chemistry research in Canada and its application to reactor safety analysis

International Nuclear Information System (INIS)

Weaver, K.R.; Kupferschmid, W.C.H.; Wren, J.C.; Ball, J.M.

1996-01-01

The current need to understand iodine chemistry in a reactor safety context has become more sharply focussed as the level of that understanding has advanced. At the same time, the situations of most concern within containment, from an iodine perspective, are also being redefined in the light of that understanding. The present paper summarises these developments. Over the past five years, considerable advances have occurred in our understanding of iodine chemistry under conditions of interest in reactor accidents. A number of key experiments have yielded important results in the areas of solution chemistry, the role of surfaces, the importance of organics and the effects of impurities. This understanding supplements the already substantial gains made in characterising the key roles of pH and the effects of radiation. All these factors underline the now evident fact that the kinetics of iodine are the controlling factor when radiation is involved, and that a number of reactive species, not present in thermal reactions, effectively control the observed volatility of iodine. In this paper, recent advances are summarised and the present status of our understanding of iodine chemistry is reviewed. Specifically, an attempt is made to identify those areas where our understanding appears to be relatively complete, and to flag the remaining critical areas where our attention is currently focussed. The state of our modelling capability is reviewed, as is the significance or related areas such as the role of mass transfer. Finally, an overview is presented of the significance of this work for reactor safety, and our expectations for its application over the near term future. (author) 2 figs., 12 refs

Current status and technology development tendency of research reactors in china

International Nuclear Information System (INIS)

Ke Guotu; Shen Feng; Zhao Shouzhi; Zhang Weiguo; Yuan Luzheng

2009-01-01

The current status and development history of domestic and abroad research reactors (RRs) are mentioned. The representative RRs and their respective technology characteristics are introduced. The utilizations of China's RRs, mainly included as nuclear engineering technology, basic research applications of nuclear technology, teaching and personnel training, are explained. (authors)

Research on international cooperation for nuclear and radiation safety

International Nuclear Information System (INIS)

Cheng Jianxiu

2013-01-01

This paper describes the importance and related requirements of international cooperation on nuclear and radiation safety, analyzes the current status, situation and challenges faced, as well as the existing weakness and needs for improvement, and gives some proposals for reference. (author)

The association between alcohol exposure and self-reported health status: the effect of separating former and current drinkers.

Directory of Open Access Journals (Sweden)

Wenbin Liang

Full Text Available To investigate the direction and degree of potential bias introducedto analyses of drinking and health status which exclude former drinkers from exposure groups.Pooled analysis of 14 waves (1997-2010 of the U.S. National Health Interview Survey (NHIS.General population-based study.404,462 participants, from 14 waves of the NHIS, who had knownself-reported health status and alcohol consumption status.Self-reported health status was used as the indicatorof health. Two approaches were used to classify alcohol consumption: (i separation of former drinkers and current drinkers, and (ii combined former and current drinkers. The prevalence of fair/poor health by alcohol use, gender and age with 95% confidence intervals was estimated. The difference in prevalence of fair/poor health status for lifetime abstainers, former drinkers, current drinkers and drinkers (former drinkers and current drinkers combined were compared using Poisson regression with robust estimations of variance.Excluding former drinkers from drinker groups exaggerates the difference in health status between abstainers and drinkers, especially for males.In cohort study analyses, former drinkers should be assigned to a drinking category based on their previous alcohol consumption patterns and not treated as a discrete exposure group.

National HTGR safety program

International Nuclear Information System (INIS)

Davis, D.E.; Kelley, A.P. Jr.

1982-01-01

This paper presents an overview of the National HTGR Program in the US with emphasis on the safety and licensing strategy being pursued. This strategy centers upon the development of an integrated approach to organizing and classifying the functions needed to produce safe and economical nuclear power production. At the highest level, four plant goals are defined - Normal Operation, Core and Plant Protection, Containment Integrity and Emergency Preparedness. The HTGR features which support the attainment of each goal are described and finally a brief summary is provided of the current status of the principal safety development program supporting the validation of the four plant goals

Marine renewable energy in China: Current status and perspectives

OpenAIRE

Yong-liang Zhang; Zheng Lin; Qiu-lin Liu

2014-01-01

Based on a general review of marine renewable energy in China, an assessment of the development status and amount of various marine renewable energy resources, including tidal energy, tidal current energy, wave energy, ocean thermal energy, and salinity gradient energy in China's coastal seas, such as the Bohai Sea, the Yellow Sea, the East China Sea, and the South China Sea, is presented. We have found that these kinds of marine renewable energy resources will play an important role in meeti...

Current status of quality assurance of treatment planning systems

International Nuclear Information System (INIS)

Mijnheer, B.J.

1997-01-01

A review is given of the current status of quality assurance of treatment planning systems. At this moment only one comprehensive report is available. In order to review national activities a questionnaire has been distributed amongst national societies of medical physicists. From the 23 responding countries, 8 indicated that only limited efforts are underway, 8 answered that a working group is evaluating their specific national requirements while in 5 countries a document is drafted. The highlights of these reports have been summarized. (author)

Current status of environmental, health, and safety issues of lithium polymer electric vehicle batteries

Energy Technology Data Exchange (ETDEWEB)

Corbus, D; Hammel, C J

1995-02-01

Lithium solid polymer electrolyte (SPE) batteries are being investigated by researchers worldwide as a possible energy source for future electric vehicles (EVs). One of the main reasons for interest in lithium SPE battery systems is the potential safety features they offer as compared to lithium battery systems using inorganic and organic liquid electrolytes. However, the development of lithium SPE batteries is still in its infancy, and the technology is not envisioned to be ready for commercialization for several years. Because the research and development (R&D) of lithium SPE battery technology is of a highly competitive nature, with many companies both in the United States and abroad pursuing R&D efforts, much of the information concerning specific developments of lithium SPE battery technology is proprietary. This report is based on information available only through the open literature (i.e., information available through library searches). Furthermore, whereas R&D activities for lithium SPE cells have focused on a number of different chemistries, for both electrodes and electrolytes, this report examines the general environmental, health, and safety (EH&S) issues common to many lithium SPE chemistries. However, EH&S issues for specific lithium SPE cell chemistries are discussed when sufficient information exists. Although lithium batteries that do not have a SPE are also being considered for EV applications, this report focuses only on those lithium battery technologies that utilize the SPE technology. The lithium SPE battery technologies considered in this report may contain metallic lithium or nonmetallic lithium compounds (e.g., lithium intercalated carbons) in the negative electrode.

Nuclear liability legislation in Russia - current status and expected developments

International Nuclear Information System (INIS)

Karpov, A. E.; Borisov, D. G.

2000-01-01

Present report is provided by the experts of the Russian insurance business, a company member of the Russian Nuclear Pool, and not the experts of the Ministry of Atomic Energy of Russian Federation (RF Minatom). Considering the above, the following document will outline the current status of nuclear liability legislation and insurance in Russia from a viewpoint of the insurance companies and not RF Minatom. (author)

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

Energy Technology Data Exchange (ETDEWEB)

NONE

2000-09-01

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

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

International Nuclear Information System (INIS)

2000-09-01

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

Safety assessment and detection methods of genetically modified organisms.

Science.gov (United States)

Xu, Rong; Zheng, Zhe; Jiao, Guanglian

2014-01-01

Genetically modified organisms (GMOs), are gaining importance in agriculture as well as the production of food and feed. Along with the development of GMOs, health and food safety concerns have been raised. These concerns for these new GMOs make it necessary to set up strict system on food safety assessment of GMOs. The food safety assessment of GMOs, current development status of safety and precise transgenic technologies and GMOs detection have been discussed in this review. The recent patents about GMOs and their detection methods are also reviewed. This review can provide elementary introduction on how to assess and detect GMOs.

RSAS: a Reactor Safety Assessment System

International Nuclear Information System (INIS)

Sebo, D.E.; Dixon, B.W.; Bray, M.A.

1985-01-01

The Reactor Safety Assessment System (RSAS) is an expert system under development for the United States Nuclear Regulatory Commission (NRC). RSAS is being developed for use at the NRC's Operations Center in the event of a serious incident at a licensed nuclear power plant. The system generates situation assessments for the NRC Reactor Safety Team based on a limited number of plant parameters, known operator actions, and plant status data. The RSAS rule base currently covers one reactor type. The extension of the rule base to other reactor types is also discussed

Safety pharmacology--current and emerging concepts.

Science.gov (United States)

Hamdam, Junnat; Sethu, Swaminathan; Smith, Trevor; Alfirevic, Ana; Alhaidari, Mohammad; Atkinson, Jeffrey; Ayala, Mimieveshiofuo; Box, Helen; Cross, Michael; Delaunois, Annie; Dermody, Ailsa; Govindappa, Karthik; Guillon, Jean-Michel; Jenkins, Rosalind; Kenna, Gerry; Lemmer, Björn; Meecham, Ken; Olayanju, Adedamola; Pestel, Sabine; Rothfuss, Andreas; Sidaway, James; Sison-Young, Rowena; Smith, Emma; Stebbings, Richard; Tingle, Yulia; Valentin, Jean-Pierre; Williams, Awel; Williams, Dominic; Park, Kevin; Goldring, Christopher

2013-12-01

Safety pharmacology (SP) is an essential part of the drug development process that aims to identify and predict adverse effects prior to clinical trials. SP studies are described in the International Conference on Harmonisation (ICH) S7A and S7B guidelines. The core battery and supplemental SP studies evaluate effects of a new chemical entity (NCE) at both anticipated therapeutic and supra-therapeutic exposures on major organ systems, including cardiovascular, central nervous, respiratory, renal and gastrointestinal. This review outlines the current practices and emerging concepts in SP studies including frontloading, parallel assessment of core battery studies, use of non-standard species, biomarkers, and combining toxicology and SP assessments. Integration of the newer approaches to routine SP studies may significantly enhance the scope of SP by refining and providing mechanistic insight to potential adverse effects associated with test compounds. Copyright © 2013 Elsevier Inc. All rights reserved.

Status of Nuclear Safety evaluation in China

International Nuclear Information System (INIS)

Tian Jiashu

1999-01-01

Chinese nuclear safety management and control follows international practice, the regulations are mainly from IAEA with the Chinese condition. The regulatory body is National Nuclear Safety Administration (NNSA). The nuclear safety management, surveillance, safety review and evaluation are guided by NNSA with technical support by several units. Beijing Review Center of Nuclear Safety is one of these units, which was founded in 1987 within Beijing Institute of nuclear Engineering (BINE), co-directed by NNSA and BINE, it is the first technical support team to NNSA. Most of the safety reviews and evaluations of Chinese nuclear installations has been finished by this unit. It is described briefly in this paper that the NNSA's main function and organization, regulations on the nuclear safety, procedure of application and issuing of license, the main activities performed by Beijing Review Center of Nuclear Safety, the situation of severe accident analyses in China, etc. (author)

Elementary particle physics and cosmology: current status and prospects

International Nuclear Information System (INIS)

Rubakov, Valerii A

1999-01-01

The current status of elementary particle physics can be briefly summarized as follows: the Standard Model of elementary particles is perfectly (at the level of radiation effects!) adequate in describing all the available experimental data except for the recent indications of neutrino oscillations. At the same time, much (and possibly most) of today's cosmology is not encompassed by the Standard Model - a fact which, together with intrinsic theoretical difficulties and the neutrino oscillation challenge, strongly indicates that the Standard Model is incomplete. It is expected that in the current decade a 'new physics', i.e. particles and interactions beyond the Standard Model, will emerge. Major advances in cosmology, both in terms of qualitatively improved observations and theoretical analysis of the structure and evolution of the Universe, are expected as well. (special issue)

Current issues and perspectives in food safety and risk assessment.

Science.gov (United States)

Eisenbrand, G

2015-12-01

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

Water reactor safety research program. A description of current and planned research

International Nuclear Information System (INIS)

1978-07-01

The U.S. Nuclear Regulatory Commission (NRC) sponsors confirmatory safety research on lightwater reactors in support of the NRC regulatory program. The principal responsibility of the NRC, as implemented through its regulatory program is to ensure that public health, public safety, and the environment are adequately protected. The NRC performs this function by defining conditions for the use of nuclear power and by ensuring through technical review, audit, and follow-up that these conditions are met. The NRC research program provides technical information, independent of the nuclear industry, to aid in discharging these regulatory responsibilities. The objectives of NRC's research program are the following: (1) to maintain a confirmatory research program that supports assurance of public health and safety, and public confidence in the regulatory program, (2) to provide objectively evaluated safety data and analytical methods that meet the needs of regulatory activities, (3) to provide better quantified estimates of the margins of safety for reactor systems, fuel cycle facilities, and transportation systems, (4) to establish a broad and coherent exchange of safety research information with other Federal agencies, industry, and foreign organization. Current and planned research toward these goals is described

Differences in emergency colorectal surgery in Medicaid and uninsured patients by hospital safety net status.

Science.gov (United States)

Bradley, Cathy J; Dahman, Bassam; Sabik, Lindsay M

2015-02-01

We examined whether safety net hospitals reduce the likelihood of emergency colorectal cancer (CRC) surgery in uninsured and Medicaid-insured patients. If these patients have better access to care through safety net providers, they should be less likely to undergo emergency resection relative to similar patients at non- safety net hospitals. Using population-based data, we estimated the relationship between safety net hospitals, patient insurance status, and emergency CRC surgery. We extracted inpatient admission data from the Virginia Health Information discharge database and matched them to the Virginia Cancer Registry for patients aged 21 to 64 years who underwent a CRC resection between January 1, 1999, and December 31, 2005 (n = 5488). We differentiated between medically defined emergencies and those that originated in the emergency department (ED). For each definition of emergency surgery, we estimated the linear probability models of the effects of being treated at a safety net hospital on the probability of having an emergency resection. Safety net hospitals reduce emergency surgeries among uninsured and Medicaid CRC patients. When defining an emergency resection as those that involved an ED visit, these patients were 15 to 20 percentage points less likely to have an emergency resection when treated in a safety net hospital. Our results suggest that these hospitals provide a benefit, most likely through the access they afford to timely and appropriate care, to uninsured and Medicaid-insured patients relative to hospitals without a safety net mission.

NPP Temelin. Status of safety improvements

International Nuclear Information System (INIS)

1999-01-01

The WWER-1000 Temelin NPP under construction has been subjected as other NPPs of the same type to numerous project reviews resulting in quite a number of recommendations for design changes. Results of the IAEA mission to review the resolution of WWER-1000 safety issues at Temelin NPP are cited in this paper. The main conclusions emphasize that a combination of eastern and western technology and practices led to safety improvements in comparison with the international practices. Plant managers are clearly committed to implementation of operational programs which are consistent with effective western operational safety practices. Considerable effort remains to bring planned programs to successful implementation, in particular in meeting the need to foster strong safety culture among all personnel

Nonclinical safety biomarkers of drug-induced vascular injury: current status and blueprint for the future.

Science.gov (United States)

Mikaelian, Igor; Cameron, Mark; Dalmas, Deidre A; Enerson, Bradley E; Gonzalez, Raymond J; Guionaud, Silvia; Hoffmann, Peter K; King, Nicholas M P; Lawton, Michael P; Scicchitano, Marshall S; Smith, Holly W; Thomas, Roberta A; Weaver, James L; Zabka, Tanja S

2014-06-01

Better biomarkers are needed to identify, characterize, and/or monitor drug-induced vascular injury (DIVI) in nonclinical species and patients. The Predictive Safety Testing Consortium (PSTC), a precompetitive collaboration of pharmaceutical companies and the U.S. Food and Drug Administration (FDA), formed the Vascular Injury Working Group (VIWG) to develop and qualify translatable biomarkers of DIVI. The VIWG focused its research on acute DIVI because early detection for clinical and nonclinical safety monitoring is desirable. The VIWG developed a strategy based on the premise that biomarkers of DIVI in rat would be translatable to humans due to the morphologic similarity of vascular injury between species regardless of mechanism. The histomorphologic lexicon for DIVI in rat defines degenerative and adaptive findings of the vascular endothelium and smooth muscles, and characterizes inflammatory components. We describe the mechanisms of these changes and their associations with candidate biomarkers for which advanced analytical method validation was completed. Further development is recommended for circulating microRNAs, endothelial microparticles, and imaging techniques. Recommendations for sample collection and processing, analytical methods, and confirmation of target localization using immunohistochemistry and in situ hybridization are described. The methods described are anticipated to aid in the identification and qualification of translational biomarkers for DIVI. © 2014 by The Author(s).

History, Current Status, and Future Prospects of Counseling in South Korea

Science.gov (United States)

Lee, Sang Min; Suh, Suhyun; Yang, Eunjoo; Jang, Yoo Jin

2012-01-01

Although the counseling profession was introduced to South Korea in the 1950s by American delegates of education, counseling has been only lately recognized as a specialized field that requires distinctive knowledge and skills. In this article, the authors describe the history and the current status of counseling in South Korea and then discuss…

Online-coupled meteorology and chemistry models: history, current status, and outlook

Directory of Open Access Journals (Sweden)

Y. Zhang

2008-06-01

Full Text Available The climate-chemistry-aerosol-cloud-radiation feedbacks are important processes occurring in the atmosphere. Accurately simulating those feedbacks requires fully-coupled meteorology, climate, and chemistry models and presents significant challenges in terms of both scientific understanding and computational demand. This paper reviews the history and current status of the development and application of online-coupled meteorology and chemistry models, with a focus on five representative models developed in the US including GATOR-GCMOM, WRF/Chem, CAM3, MIRAGE, and Caltech unified GCM. These models represent the current status and/or the state-of-the science treatments of online-coupled models worldwide. Their major model features, typical applications, and physical/chemical treatments are compared with a focus on model treatments of aerosol and cloud microphysics and aerosol-cloud interactions. Aerosol feedbacks to planetary boundary layer meteorology and aerosol indirect effects are illustrated with case studies for some of these models. Future research needs for model development, improvement, application, as well as major challenges for online-coupled models are discussed.

CKM Phenomenology and B-mesons physics-present status and current issues

International Nuclear Information System (INIS)

Ali, A.

2004-01-01

We review the status of the Cabibbo-Kobayashi-Maskawa (CKM) matrix elements and the CP-violating phases in the CKM-unitarity triangle. The emphasis in these lecture notes is on B-meson physics, through we also review the current status and issues in the light quark sector of this matrix. Selected applications of theoretical methods in QCD used in the interpretation of data are given and some of the issues restricting the theoretical precision on the CKM matrix elements discussed. The overall consistency of the CKM theory with the available data in flavour physics is impressive and we quantify this consistency. Current data also show some anomalies which, however, are not yet statistically significant. They are discussed briefly. some benchmark measurements that remain to be done in experiments at the B-factories and hadron colliders are listed. Together with the already achieved results, they will provide unprecedented test of the CKM theory and by the same token may lead to the discovery of new physics. (Author) 284 refs

Physics and safety of transmutation systems. A status report

International Nuclear Information System (INIS)

2006-01-01

The safe and efficient management of spent fuel from the operation of commercial nuclear power plants is an important issue. Worldwide, more than 250 000 tons of spent fuel from currently operating reactors will require disposal. These numbers account for only high-level radioactive waste generated by present-day power reactors. Nearly all issues related to risks to future generations arising from the long-term disposal of such spent nuclear fuel is attributable to only about 1% of its content. This 1% is made up primarily of plutonium, neptunium, americium and curium (called transuranic elements) and the long-lived isotopes of iodine and technetium.When transuranics are removed from discharged fuel destined for disposal, the toxic nature of the spent fuel drops below that of natural uranium ore (that which was originally mined for the nuclear fuel) within a period of several hundred to a thousand years. This significantly reduces the burden on geological repositories and the problem of addressing the remaining long-term residues can thus de done in controlled environments having timescales of centuries rather than millennia stretching beyond 10 000 years. Transmutation is one of the means being explored to address the disposal of transuranic elements. To achieve this, advanced reactors systems, appropriate fuels, separation techniques and associated fuel cycle strategies are required. This status report begins by providing a clear definition of partitioning and transmutation (P and T), and then describes the state of the art concerning the challenges facing the implementation of P and T, scenario studies and specific issues related to accelerator-driven systems (ADS) dynamics and safety, long-lived fission product transmutation and the impact of nuclear data uncertainty on transmutation system design. The report will be of particular interest to nuclear scientists working on P and T issues as well as advanced fuel cycles in general. (author)

HSI for monitoring the critical safety functions status tree of a NPP

International Nuclear Information System (INIS)

Oliveira, Mauro Vitor de; Almeida, Jose Carlos Soares de; Augusto, Silas Cordeiro; Jaime, Guilherme Dutra Gonzaga

2013-01-01

Critical safety function (CSF) is the most significant design concept for prioritize operator actions based on the potential threat to the three barriers (fuel cladding, primary coolant system boundary, and containment) and allows the operator to respond to these threats prior to event diagnosis. CSF has a hierarchical information structure that organizes the system variables affecting the plant safety in terms of goal-means relations. It is important that the operator should be aware of various success paths associated with each CSF in order to respond to unanticipated system failures quickly. When an emergency occurs in NPPs, the operator should monitor CSFs periodically and identify possible success paths as necessary, and try to stabilize or safely shut down the plant using emergency operating procedure (EOP) that includes steps to check the CSFs. This implies that safety function status check may become a cognitively burdensome task that needs to be supported by proper information display. The advanced human-system interface (HSI) in nuclear power plants provides an information environment that supports the operators' burdensome cognitive tasks. This paper describes a CSFs interface design for supporting the operator's tasks to monitor and identify the associated success path for Westinghouse 3-loops NPP. (author)

Applications of computer based safety systems in Korea nuclear power plants

International Nuclear Information System (INIS)

Won Young Yun

1998-01-01

With the progress of computer technology, the applications of computer based safety systems in Korea nuclear power plants have increased rapidly in recent decades. The main purpose of this movement is to take advantage of modern computer technology so as to improve the operability and maintainability of the plants. However, in fact there have been a lot of controversies on computer based systems' safety between the regulatory body and nuclear utility in Korea. The Korea Institute of Nuclear Safety (KINS), technical support organization for nuclear plant licensing, is currently confronted with the pressure to set up well defined domestic regulatory requirements from this aspect. This paper presents the current status and the regulatory activities related to the applications of computer based safety systems in Korea. (author)

SCALE Graphical Developments for Improved Criticality Safety Analyses

International Nuclear Information System (INIS)

Barnett, D.L.; Bowman, S.M.; Horwedel, J.E.; Petrie, L.M.

1999-01-01

New computer graphic developments at Oak Ridge National Ridge National Laboratory (ORNL) are being used to provide visualization of criticality safety models and calculational results as well as tools for criticality safety analysis input preparation. The purpose of this paper is to present the status of current development efforts to continue to enhance the SCALE (Standardized Computer Analyses for Licensing Evaluations) computer software system. Applications for criticality safety analysis in the areas of 3-D model visualization, input preparation and execution via a graphical user interface (GUI), and two-dimensional (2-D) plotting of results are discussed

Low-dose antibiotics: current status and outlook for the future

DEFF Research Database (Denmark)

Antimicrobial therapy is a key factor in our success against pathogens poised to ravage at risk or infected individuals. However, we are currently at a watershed point as we face a growing crisis of antibiotic resistance among diverse pathogens. One area of intense interest is the impact of the a......Antimicrobial therapy is a key factor in our success against pathogens poised to ravage at risk or infected individuals. However, we are currently at a watershed point as we face a growing crisis of antibiotic resistance among diverse pathogens. One area of intense interest is the impact...... of the application of antibiotics for uses other than the treatment of patients and the association with such utilization with emerging drug resistance. This Research Topic “Low- dose antibiotics: current status and outlook for the future” in Frontiers in Microbiology: Antimicrobials, Resistance and Chemotherapy...

FLIGHT SAFETY MANAGEMENT PROBLEMS AND EVALUATION OF FLIGHT SAFETY LEVEL OF AN AVIATION ENTERPRISE

Directory of Open Access Journals (Sweden)

B. V. Zubkov

2017-01-01

Full Text Available This article is devoted to studying the problem of safety management system (SMS and evaluating safety level of an aviation enterprise.This article discusses the problems of SMS, presented at the 41st meeting of the Russian Aviation Production Commanders Club in June 2014 in St. Petersburg in connection with the verification of the status of the CA of the Russian Federation by the International Civil Aviation Organization (ICAO in the same year, a set of urgent measures to eliminate the deficiencies identified in the current safety management system by participants of this meeting were proposed.In addition, the problems of evaluating flight safety level based on operation data of an aviation enterprise were analyzed. This analysis made it possible to take into account the problems listed in this article as a tool for a comprehensive study of SMS parameters and allows to analyze the quantitative indicators of the flights safety level.The concepts of Acceptable Safety Level (ASL indicators are interpreted differently depending on the available/applicable methods of their evaluation and how to implement them in SMS. However, the indicators for assessing ASL under operational condition at the aviation enterprise should become universal. Currently, defined safety levels and safety indicators are not yet established functionally and often with distorted underrepresented models describing their contextual contents, as well as ways of integrating them into SMS aviation enterprise.The results obtained can be used for better implementation of SMS and solving problems determining the aviation enterprise technical level of flight safety.

Microbiological food safety: a dilemma of developing societies.

Science.gov (United States)

Akhtar, Saeed; Sarker, Mahfuzur R; Hossain, Ashfaque

2014-11-01

Current food safety issues are deleteriously reshaping the life style of the population in the developing world. Socioeconomic status of the population in poorer economies is one of the major determinants to delineate the availability of safe food to the vulnerable population. Assessment of the prevalence of foodborne illness in developing world is the most neglected area to control disease. Botulism, Shigellosis, Campylobacteriosis, Escherichia coli infection, Staphylococcus aureus infection, Salmonellosis, Listeriosis and Cholerae are extensively prevalent and pose a major threat to human health in underdeveloped communities. The existing food safety status of many African, South Asian, Central, and South American developing countries is distressing therefore; it seems much timely to highlight the areas for the improvement to ensure the supply of safe food to the population in these regions. Extensive literature search at PubMed, Science Direct and Medline was carried out during the current year to catch on relevant data from 1976 to date, using selective terms like food safety, South East Asia, Africa, Central and South America, and foodborne illness etc. Efforts were made to restrict the search to low income countries of these regions with reference to specific foodborne pathogens. This report briefly discusses the present food safety situation in these developing countries and associated consequences as prime issues, suggesting foodborne illness to be the most distressing threat for human health and economic growth.

Status and trends in IAEA safety standards

International Nuclear Information System (INIS)

Lipar, M.

2004-01-01

While safety is a national responsibility, international standards and approaches to safety promote consistency and facilitate international technical co-operation and trade, and help to provide assurance that nuclear and radiation related technologies are used safely. The standards also provide support for States in meeting their international obligations. One general international obligation is that a State must not pursue activities that cause damage in another State. More specific obligations on Contracting States are set out in international safety related conventions. The internationally agreed IAEA safety standards provide the basis for States to demonstrate that they are meeting these obligations. These standards are founded in the IAEA's Statute, which authorizes the Agency to establish standards of safety for nuclear and radiation related facilities and activities and to provide for their application. The safety standards reflect an international consensus on what constitutes a high level of safety for protecting people and the environment. (orig.) [de

NS [Nuclear Safety] update. Current safety and security activities and developments taking place in the Department of Nuclear Safety and Security, Issue no. 13, December 2009

International Nuclear Information System (INIS)

2009-12-01

The current issue presents information about the following activities: Highlights of the 53rd IAEA General Conference, 14-18 September 2009. Current status of the Building, Testing and Using the Response Assistance Network (RANET). 10th Meeting of the ANSN Steering Committee. The document also gives an overview on International Physical Protection Advisory Service (IPPAS)

Current status of multi-detector row helical CT in imaging of adult ...

African Journals Online (AJOL)

Current status of multi-detector row helical CT in imaging of adult acquired pancreatic diseases and assessing surgical neoplastic resectability. ... The presence of inflammation, masses, and vascular invasion was evaluated and interpreted images were obtained during each phase. Results were compared with surgery, ...

Elements of a nuclear criticality safety program

International Nuclear Information System (INIS)

Hopper, C.M.

1995-01-01

Nuclear criticality safety programs throughout the United States are quite successful, as compared with other safety disciplines, at protecting life and property, especially when regarded as a developing safety function with no historical perspective for the cause and effect of process nuclear criticality accidents before 1943. The programs evolved through self-imposed and regulatory-imposed incentives. They are the products of conscientious individuals, supportive corporations, obliged regulators, and intervenors (political, public, and private). The maturing of nuclear criticality safety programs throughout the United States has been spasmodic, with stability provided by the volunteer standards efforts within the American Nuclear Society. This presentation provides the status, relative to current needs, for nuclear criticality safety program elements that address organization of and assignments for nuclear criticality safety program responsibilities; personnel qualifications; and analytical capabilities for the technical definition of critical, subcritical, safety and operating limits, and program quality assurance

Optimizing Quality of Care and Patient Safety in Malaysia: The Current Global Initiatives, Gaps and Suggested Solutions.

Science.gov (United States)

Jarrar, Mu'taman; Abdul Rahman, Hamzah; Don, Mohammad Sobri

2015-10-20

Demand for health care service has significantly increased, while the quality of healthcare and patient safety has become national and international priorities. This paper aims to identify the gaps and the current initiatives for optimizing the quality of care and patient safety in Malaysia. Review of the current literature. Highly cited articles were used as the basis to retrieve and review the current initiatives for optimizing the quality of care and patient safety. The country health plan of Ministry of Health (MOH) Malaysia and the MOH Malaysia Annual Reports were reviewed. The MOH has set four strategies for optimizing quality and sustaining quality of life. The 10th Malaysia Health Plan promotes the theme "1 Care for 1 Malaysia" in order to sustain the quality of care. Despite of these efforts, the total number of complaints received by the medico-legal section of the MOH Malaysia is increasing. The current global initiatives indicted that quality performance generally belong to three main categories: patient; staffing; and working environment related factors. There is no single intervention for optimizing quality of care to maintain patient safety. Multidimensional efforts and interventions are recommended in order to optimize the quality of care and patient safety in Malaysia.

Optimizing Quality of Care and Patient Safety in Malaysia: The Current Global Initiatives, Gaps and Suggested Solutions

Science.gov (United States)

Jarrar, Mu’taman; Rahman, Hamzah Abdul; Don, Mohammad Sobri

2016-01-01

Background and Objective: Demand for health care service has significantly increased, while the quality of healthcare and patient safety has become national and international priorities. This paper aims to identify the gaps and the current initiatives for optimizing the quality of care and patient safety in Malaysia. Design: Review of the current literature. Highly cited articles were used as the basis to retrieve and review the current initiatives for optimizing the quality of care and patient safety. The country health plan of Ministry of Health (MOH) Malaysia and the MOH Malaysia Annual Reports were reviewed. Results: The MOH has set four strategies for optimizing quality and sustaining quality of life. The 10th Malaysia Health Plan promotes the theme “1 Care for 1 Malaysia” in order to sustain the quality of care. Despite of these efforts, the total number of complaints received by the medico-legal section of the MOH Malaysia is increasing. The current global initiatives indicted that quality performance generally belong to three main categories: patient; staffing; and working environment related factors. Conclusions: There is no single intervention for optimizing quality of care to maintain patient safety. Multidimensional efforts and interventions are recommended in order to optimize the quality of care and patient safety in Malaysia. PMID:26755459

Virtual reality training in neurosurgery: Review of current status and future applications

Science.gov (United States)

Alaraj, Ali; Lemole, Michael G.; Finkle, Joshua H.; Yudkowsky, Rachel; Wallace, Adam; Luciano, Cristian; Banerjee, P. Pat; Rizzi, Silvio H.; Charbel, Fady T.

2011-01-01

Background: Over years, surgical training is changing and years of tradition are being challenged by legal and ethical concerns for patient safety, work hour restrictions, and the cost of operating room time. Surgical simulation and skill training offer an opportunity to teach and practice advanced techniques before attempting them on patients. Simulation training can be as straightforward as using real instruments and video equipment to manipulate simulated “tissue” in a box trainer. More advanced virtual reality (VR) simulators are now available and ready for widespread use. Early systems have demonstrated their effectiveness and discriminative ability. Newer systems enable the development of comprehensive curricula and full procedural simulations. Methods: A PubMed review of the literature was performed for the MESH words “Virtual reality, “Augmented Reality”, “Simulation”, “Training”, and “Neurosurgery”. Relevant articles were retrieved and reviewed. A review of the literature was performed for the history, current status of VR simulation in neurosurgery. Results: Surgical organizations are calling for methods to ensure the maintenance of skills, advance surgical training, and credential surgeons as technically competent. The number of published literature discussing the application of VR simulation in neurosurgery training has evolved over the last decade from data visualization, including stereoscopic evaluation to more complex augmented reality models. With the revolution of computational analysis abilities, fully immersive VR models are currently available in neurosurgery training. Ventriculostomy catheters insertion, endoscopic and endovascular simulations are used in neurosurgical residency training centers across the world. Recent studies have shown the coloration of proficiency with those simulators and levels of experience in the real world. Conclusion: Fully immersive technology is starting to be applied to the practice of

Virtual reality training in neurosurgery: Review of current status and future applications.

Science.gov (United States)

Alaraj, Ali; Lemole, Michael G; Finkle, Joshua H; Yudkowsky, Rachel; Wallace, Adam; Luciano, Cristian; Banerjee, P Pat; Rizzi, Silvio H; Charbel, Fady T

2011-01-01

Over years, surgical training is changing and years of tradition are being challenged by legal and ethical concerns for patient safety, work hour restrictions, and the cost of operating room time. Surgical simulation and skill training offer an opportunity to teach and practice advanced techniques before attempting them on patients. Simulation training can be as straightforward as using real instruments and video equipment to manipulate simulated "tissue" in a box trainer. More advanced virtual reality (VR) simulators are now available and ready for widespread use. Early systems have demonstrated their effectiveness and discriminative ability. Newer systems enable the development of comprehensive curricula and full procedural simulations. A PubMed review of the literature was performed for the MESH words "Virtual reality, "Augmented Reality", "Simulation", "Training", and "Neurosurgery". Relevant articles were retrieved and reviewed. A review of the literature was performed for the history, current status of VR simulation in neurosurgery. Surgical organizations are calling for methods to ensure the maintenance of skills, advance surgical training, and credential surgeons as technically competent. The number of published literature discussing the application of VR simulation in neurosurgery training has evolved over the last decade from data visualization, including stereoscopic evaluation to more complex augmented reality models. With the revolution of computational analysis abilities, fully immersive VR models are currently available in neurosurgery training. Ventriculostomy catheters insertion, endoscopic and endovascular simulations are used in neurosurgical residency training centers across the world. Recent studies have shown the coloration of proficiency with those simulators and levels of experience in the real world. Fully immersive technology is starting to be applied to the practice of neurosurgery. In the near future, detailed VR neurosurgical modules

Australian shellfish ecosystems: Past distribution, current status and future direction.

Directory of Open Access Journals (Sweden)

Chris L Gillies

Full Text Available We review the status of marine shellfish ecosystems formed primarily by bivalves in Australia, including: identifying ecosystem-forming species, assessing their historical and current extent, causes for decline and past and present management. Fourteen species of bivalves were identified as developing complex, three-dimensional reef or bed ecosystems in intertidal and subtidal areas across tropical, subtropical and temperate Australia. A dramatic decline in the extent and condition of Australia's two most common shellfish ecosystems, developed by Saccostrea glomerata and Ostrea angasi oysters, occurred during the mid-1800s to early 1900s in concurrence with extensive harvesting for food and lime production, ecosystem modification, disease outbreaks and a decline in water quality. Out of 118 historical locations containing O. angasi-developed ecosystems, only one location still contains the ecosystem whilst only six locations are known to still contain S. glomerata-developed ecosystems out of 60 historical locations. Ecosystems developed by the introduced oyster Crasostrea gigas are likely to be increasing in extent, whilst data on the remaining 11 ecosystem-forming species are limited, preventing a detailed assessment of their current ecosystem-forming status. Our analysis identifies that current knowledge on extent, physical characteristics, biodiversity and ecosystem services of Australian shellfish ecosystems is extremely limited. Despite the limited information on shellfish ecosystems, a number of restoration projects have recently been initiated across Australia and we propose a number of existing government policies and conservation mechanisms, if enacted, would readily serve to support the future conservation and recovery of Australia's shellfish ecosystems.

Australian shellfish ecosystems: Past distribution, current status and future direction

Science.gov (United States)

Gillies, Chris L.; McLeod, Ian M.; Alleway, Heidi K.; Cook, Peter; Crawford, Christine; Creighton, Colin; Diggles, Ben; Ford, John; Hamer, Paul; Heller-Wagner, Gideon; Lebrault, Emma; Le Port, Agnès; Russell, Kylie; Sheaves, Marcus; Warnock, Bryn

2018-01-01

We review the status of marine shellfish ecosystems formed primarily by bivalves in Australia, including: identifying ecosystem-forming species, assessing their historical and current extent, causes for decline and past and present management. Fourteen species of bivalves were identified as developing complex, three-dimensional reef or bed ecosystems in intertidal and subtidal areas across tropical, subtropical and temperate Australia. A dramatic decline in the extent and condition of Australia’s two most common shellfish ecosystems, developed by Saccostrea glomerata and Ostrea angasi oysters, occurred during the mid-1800s to early 1900s in concurrence with extensive harvesting for food and lime production, ecosystem modification, disease outbreaks and a decline in water quality. Out of 118 historical locations containing O. angasi-developed ecosystems, only one location still contains the ecosystem whilst only six locations are known to still contain S. glomerata-developed ecosystems out of 60 historical locations. Ecosystems developed by the introduced oyster Crasostrea gigas are likely to be increasing in extent, whilst data on the remaining 11 ecosystem-forming species are limited, preventing a detailed assessment of their current ecosystem-forming status. Our analysis identifies that current knowledge on extent, physical characteristics, biodiversity and ecosystem services of Australian shellfish ecosystems is extremely limited. Despite the limited information on shellfish ecosystems, a number of restoration projects have recently been initiated across Australia and we propose a number of existing government policies and conservation mechanisms, if enacted, would readily serve to support the future conservation and recovery of Australia’s shellfish ecosystems. PMID:29444143

Review of the current status of linear hybrid reactor concepts

International Nuclear Information System (INIS)

Schultz, K.R.

1977-07-01

A review was made of the current status of linear fusion-fission hybrid reactor design studies in the USA. The linear hybrid reactor concepts reviewed include the linear theta-pinch hybrid reactor being studied at Los Alamos Scientific Laboratory, the electron beam-heated solenoid hybrid reactor under development at Physics International Co., the laser-heated solenoid hybrid reactor being investigated at Mathematical Sciences Northwest, Inc., and the linear fusion waste burning reactor being studied at General Atomic Company. The discussion addresses confinement and heating mechanisms for each concept, as well as the hybrid blanket designs. The current state of the four reactor designs is summarized and the performance of the various concepts compared

Yellow fever vaccination status and safety in hemodialysis patients.

Science.gov (United States)

Facincani, Tila; Guimarães, Maia Nogueira Crown; De Sousa Dos Santos, Sigrid

2016-07-01

The adverse effects of yellow fever (YF) vaccine in dialysis patients are not well known. There is concern about the risks and benefits of the vaccine in immunocompromised patients living in endemic areas, particularly given the risk of resurgence of urban YF with the spread of Aedes aegypti mosquitoes. The purpose of this study was to assess the coverage and safety of YF vaccine in chronic dialysis patients. A cross-sectional study of 130 chronic dialysis patients was performed. Data were collected on clinical characteristics and YF vaccine status. Patients not vaccinated against YF or without a booster vaccination within the last 10 years were referred to receive the vaccine, and adverse effects were monitored. Previous vaccination was verified in 44 patients within the last 10 years and in 26 patients at more than 10 years ago, with no mention of adverse effects. Thirty-six patients had never been vaccinated and 24 had an unknown vaccination status. Of the total 86 patients referred for immunization, 45 actually received the YF vaccine, with 24.4% experiencing mild local adverse effects and 4.4% experiencing fever. No serious adverse effects attributable to YF vaccine were observed (anaphylaxis, neurological or viscerotropic disease). YF vaccine coverage among hemodialysis patients is low, and the vaccine appeared to be safe in this population with a small sample size. Copyright © 2016 The Authors. Published by Elsevier Ltd.. All rights reserved.

Income Inequality and Health Status in the United States: Evidence from the Current Population Survey.

Science.gov (United States)

Mellor, Jennifer M.; Milyo, Jeffrey

2002-01-01

Current Population Survey data on self-reported health status and income for the general population and those in poverty were analyzed. No consistent association was found between income inequality and individual health status. Previous findings of such an association were attributed to ecological fallacy or failure to control for individual…

Current status of ground motions evaluation in seismic design guide for nuclear power facilities. Investigation on IAEA and US.NRC

International Nuclear Information System (INIS)

Nakajima, Masato; Ito, Hiroshi; Hirata, Kazuta

2009-01-01

Recently, IAEA (International Atomic Energy Agency) and US.NRC (US. Nuclear Regulatory Commission) published several standards and technical reports on seismic design and safety evaluation for nuclear power facilities. This report summarizes the current status of the international guidelines on seismic design and safety evaluation for nuclear power facilities in order to explore the future research topics. The main results obtained are as follows: 1 IAEA: (1) In the safety standard series, two levels are defined as seismic design levels, and design earthquake ground motion is determined corresponding to each seismic design level. (2) A new framework on seismic design which consists of conventional deterministic method and risk-based method is discussed in the technical report although the framework is not adopted in the safety guidelines. 2 USA: (1) US.NRC discusses a performance-based seismic design framework which has been originally developed by the private organization (American Society of Civil Engineers). (2) Design earthquakes and earthquake ground motion are mainly evaluated and determined based on probabilistic seismic hazard evaluations. 3 Future works: It should be emphasized that IAEA and US.NRC have investigated the implementation of risk-based concept into seismic design. The implementation of risk-based concept into regulation and seismic design makes it possible to consider various uncertainties and to improve accountability. Therefore, we need to develop the methods for evaluating seismic risk of structures, and to correlate seismic margin and seismic risk quantitatively. Moreover, the probabilistic method of earthquake ground motions, that is required in the risk-based design, should be applied to sites in Japan. (author)

Current status of the Fastbus Micro-Vax

International Nuclear Information System (INIS)

Siskind, E.J.

1985-01-01

The present hardware, firmware, and software design and status of the Fastbus Micro-VAX, a two board Fastbus module packaging of the DEC Micro-VAX II computing system, is described. The hardware currently features an Intel 80186, equipped with 64 kB of ROM, 32 kB of RAM, and an 82586/82501 Ethernet port, as a front end I/O processor, plus a high bandwidth Fastbus interface implemented in semi-custom ECL 100K VLSI with the Motorola MCA2500ECL macrocell array. Standard 80186 firmware implements multiple Fastbus segment drivers and interrupt receivers software compatible with the UPI, a limited Fastbus interprocessor network, and emulations of the DEC DEQNA Ethernet interface and an MSCP disk interface. Software includes device drivers for the non-DEC devices, plus appropriate standard access subroutines for the Fastbus and network devices

The biosphere: current status

International Nuclear Information System (INIS)

Thorne, M.C.

1988-06-01

This paper outlines the biosphere models and data required to assess the post-closure radiological impact of deep geological repositories for low and intermediate level radioactive wastes. It then goes on to show how these requirements are being met either within the Nirex Safety Assessment Research Programme or from other research programmes. (Author)

Current status of the IREN project

International Nuclear Information System (INIS)

Furman, W.I.

1997-01-01

A current status and a corrected time-schedule of the project of the new Intense Resonance Neutron pulsed source (IREN) realized in JINR (Dubna) for experiments dealing with fundamental and applied nuclear physics studies are discussed. This source is the upgraded variant of the existing IBR-30 pulsed booster. It consists of the 200 MeV electron linac and supplying by an electron beam the photo-neutron converter placed in the center of the very fast multiplying subcritical core. The existing buildings and beam infrastructure are planned to adopt for the new IREN source. The aim of the project is to improve essentially an energy resolution of the time-of-flight spectrometer and to increase twice (up to 10 15 n/sec) an integral neutron yield. An implementation of the IREN project has started in June 1994 with the planned end in December 1997. But due to mainly insufficient financing the approved time-schedule is shifted. Now most optimistic time of start-up of the neutron source is the end of 1999

AREVA General Inspectorate Annual Report 2013 - Status of safety in nuclear facilities

International Nuclear Information System (INIS)

Oursel, Luc; Riou, Jean

2014-06-01

This annual report by AREVA's General Inspectorate deals with the status of nuclear safety and radiation protection in the group's facilities and operations over the course of 2013. Based on the findings made during implementation of the annual inspection program, this annual report also includes the results of the analysis of significant events and the observations and assessments of specialists in the Safety Health Security Sustainable Development Department (SHSSDD), supplemented by regular interaction with the safety regulators, different government agencies, stakeholders and other nuclear operators. Additionally, this report presents the action plans put into motion and the directions taken for continuous improvement in risk prevention for operations conducted in France and internationally. In 2013, the level of safety in the group's nuclear facilities and operations remained satisfactory, although improvements are necessary in some domains. This report is based on established indicators, analyses of reported events, responses to commitments made to the regulators, and the results of different improvement actions reported on in the inspected and supported entities. In 2013, no level 2 event on the International Nuclear and Radiological Event Scale (INES) was reported, the bottom-up reporting of weak signals was confirmed, dose levels were low and there were no radiological impacts on the environment. The General Inspectorate conducted 45 inspections in 30 of the group's entities in 2013. Of these, 10 concerned sites outside France and 7 were conducted following events or particular situations. These inspections gave rise to 176 recommendations, which the inspected entities have translated into action plans. Verification of these different action plans according to planned procedures and announced schedules gave rise to 16 follow-up inspections. The major lessons learned from these inspections relate to project management, facility compliance and operational

Current Status of Family Medicine Faculty Development in Sub-Saharan Africa.

Science.gov (United States)

Larson, Paul R; Chege, Patrick; Dahlman, Bruce; Gibson, Christine; Evensen, Ann; Colon-Gonzalez, Maria C; Onguka, Stephanie; Lamptey, Roberta; Cayley, William E; Nguyen, Bich-May; Johnson, Brian; Getnet, Sawra; Hasnain, Memoona

2017-03-01

Reducing the shortage of primary care physicians in sub-Saharan Africa requires expansion of training programs in family medicine. Challenges remain in preparing, recruiting, and retaining faculty qualified to teach in these pioneering programs. Little is known about the unique faculty development needs of family medicine faculty within the sub-Saharan African context. The purpose of this study was to assess the current status and future needs for developing robust family medicine faculty in sub-Saharan Africa. The results are reported in two companion articles. A cross-sectional study design was used to conduct a qualitative needs assessment comprising 37 in-depth, semi-structured interviews of individual faculty trainers from postgraduate family medicine training programs in eight sub-Saharan African countries. Data were analyzed according to qualitative description. While faculty development opportunities in sub-Saharan Africa were identified, current faculty note many barriers to faculty development and limited participation in available programs. Faculty value teaching competency, but institutional structures do not provide adequate support. Sub-Saharan African family physicians and postgraduate trainee physicians value good teachers and recognize that clinical training alone does not provide all of the skills needed by educators. The current status of limited resources of institutions and individuals constrain faculty development efforts. Where faculty development opportunities do exist, they are too infrequent or otherwise inaccessible to provide trainers the necessary skills to help them succeed as educators.

Optimizing Quality of Care and Patient Safety in Malaysia: The Current Global Initiatives, Gaps and Suggested Solutions

OpenAIRE

Jarrar, Mu?taman; Rahman, Hamzah Abdul; Don, Mohammad Sobri

2015-01-01

Background and Objective: Demand for health care service has significantly increased, while the quality of healthcare and patient safety has become national and international priorities. This paper aims to identify the gaps and the current initiatives for optimizing the quality of care and patient safety in Malaysia. Design: Review of the current literature. Highly cited articles were used as the basis to retrieve and review the current initiatives for optimizing the quality of care and patie...

[Analysis of the current situation the oral medical interns' awareness on occupation safety behavior in college].

Science.gov (United States)

Hongyan, Song; Yu, Wang; Rongrong, He; Ying, Xu

2015-04-01

This study aims to determine the awareness oral medical interns about occupation safety protection of knowledge and to present a scientific basis for perfecting the occupation safety education system and standard protection behavior. A self-designed questionnaire that used a retrospective questionnaire survey on 425 stomatological interns, scoring, and statistical analysis of the survey were performed. The questionnaire included occupation safety prevention knowledge, behavior cognitive, and protective behavior, among others. The questionnaire recovery rate was 100%, and the average scores of the prevention knowledge and behavior cognitive were 4.55 ± 0.91 and 4.40 ± 1.05, respectively. More than 90% interns can conduct the conventional protection, and less than 40% can perform special protection. For the item "occupation safety protection knowledge", the scores of three grade III hospitals were higher than that of stomatological hospitals and second level of first-class hospitals; the difference was statistically significant (P safety protection knowledge, behavioral cognitive, and protection behavior. The average score was higher for than for boys in the three contents, and the average score of interns accepting pre-job training was higher than those rejected; the difference was statistically significant (P safety knowledge of oral medical interns is not sufficient, and the protective behavior is poor. Schools and hospitals should strengthen the intern occupation safety and protection education and improve the status of occupation safety behavior.

Current Status of HbA1c Biosensors

Science.gov (United States)

Lin, Hua; Yi, Jun

2017-01-01

Glycated hemoglobin (HbA1c) is formed via non-enzymatic glycosylation reactions at the α–amino group of βVal1 residues in the tetrameric Hb, and it can reflect the ambient glycemic level over the past two to three months. A variety of HbA1c detection methods, including chromatography, immunoassay, enzymatic measurement, electrochemical sensor and capillary electrophoresis have been developed and used in research laboratories and in clinics as well. In this review, we summarize the current status of HbA1c biosensors based on the recognition of the sugar moiety on the protein and also their applications in the whole blood sample measurements. PMID:28777351

Effect of Occupational Health and Safety Management System on Work-Related Accident Rate and Differences of Occupational Health and Safety Management System Awareness between Managers in South Korea's Construction Industry

OpenAIRE

Yoon, Seok J.; Lin, Hsing K.; Chen, Gang; Yi, Shinjea; Choi, Jeawook; Rui, Zhenhua

2013-01-01

Background: The study was conducted to investigate the current status of the occupational health and safety management system (OHSMS) in the construction industry and the effect of OHSMS on accident rates. Differences of awareness levels on safety issues among site general managers and occupational health and safety (OHS) managers are identified through surveys. Methods: The accident rates for the OHSMS-certified construction companies from 2006 to 2011, when the construction OHSMS became ...

Safety evaluation by living probabilistic safety assessment. Procedures and applications for planning of operational activities and analysis of operating experience

International Nuclear Information System (INIS)

Johanson, Gunnar; Holmberg, J.

1994-01-01

Living Probabilistic Safety Assessment (PSA) is a daily safety management system and it is based on a plant-specific PSA and supporting information systems. In the living use of PSA, plant status knowledge is used to represent actual plant safety status in monitoring or follow-up perspective. The PSA model must be able to express the risk at a given time and plant configuration. The process, to update the PSA model to represent the current or planned configuration and to use the model to evaluate and direct the changes in the configuration, is called living PSA programme. The main purposes to develop and increase the usefulness of living PSA are: Long term safety planning: To continue the risk assessment process started with the basic PSA by extending and improving the basic models and data to provide a general risk evaluation tool for analyzing the safety effects of changes in plant design and procedures. Risk planning of operational activities: To support the operational management by providing means for searching optimal operational maintenance and testing strategies from the safety point of view. The results provide support for risk decision making in the short term or in a planning mode. The operational limits and conditions given by technical specifications can be analyzed by evaluating the risk effects of alternative requirements in order to balance the requirements with respect to operational flexibility and plant economy. Risk analysis of operating experience: To provide a general risk evaluation tool for analyzing the safety effects of incidents and plant status changes. The analyses are used to: identify possible high risk situations, rank the occurred events from safety point of view, and get feedback from operational events for the identification of risk contributors. This report describes the methods, models and applications required to continue the process towards a living use of PSA. 19 tabs, 20 figs

Analysis of international approaches which are used at development of theoperational safety performance indicators

International Nuclear Information System (INIS)

Lyigots'kij, O.Yi.; Nosovs'kij, A.V.; Chemeris, Yi.O.

2009-01-01

Description of international approaches and experience of the use of theoperational safety performance indicators system is provided for estimationof current status and making a decision on corrections in the operationpractice. The state of development of the operational safety performanceindicators system by the operating organization is overviewed. Thepossibility of application of international approaches during development ofthe integral safety performance indicators system is analyzed. Aims and tasksof future researches are formulated in relation to development of theintegral safety performance indicators system.

Hepatitis B Virus Infection in Tanzania: Current Status and Challenges

OpenAIRE

Kilonzo, Semvua B.; Gunda, Daniel W.; Mpondo, Bonaventura C. T.; Bakshi, Fatma A.; Jaka, Hyasinta

2018-01-01

Hepatitis B is one of the most common infectious diseases in the world with high prevalence in most of sub-Saharan Africa countries. The complexity in its diagnosis and treatment poses a significant management challenge in the resource-limited settings including Tanzania, where most of the tests and drugs are either unavailable or unaffordable. This mini review aims at demonstrating the current status of the disease in the country and discussing the concomitant challenges in diagnosis, treatm...

SRP reactor safety evolution

International Nuclear Information System (INIS)

Rankin, D.B.

1984-01-01

The Savannah River Plant reactors have operated for over 100 reactor years without an incident of significant consequence to on or off-site personnel. The reactor safety posture incorporates a conservative, failure-tolerant design; extensive administrative controls carried out through detailed operating and emergency written procedures; and multiple engineered safety systems backed by comprehensive safety analyses, adapting through the years as operating experience, changes in reactor operational modes, equipment modernization, and experience in the nuclear power industry suggested. Independent technical reviews and audits as well as a strong organizational structure also contribute to the defense-in-depth safety posture. A complete review of safety history would discuss all of the above contributors and the interplay of roles. This report, however, is limited to evolution of the engineered safety features and some of the supporting analyses. The discussion of safety history is divided into finite periods of operating history for preservation of historical perspective and ease of understanding by the reader. Programs in progress are also included. The accident at Three Mile Island was assessed for its safety implications to SRP operation. Resulting recommendations and their current status are discussed separately at the end of the report. 16 refs., 3 figs

Study on European Nuclear Safety Practices during Planned Outages at Nuclear Power Plants

International Nuclear Information System (INIS)

2001-12-01

The present project was aimed at providing: a description of the current status of nuclear safety practices during planned outages at nuclear power plants followed in Europe; the criteria for the safety analysis of future reactors at the design stage; proposing a set of recommendations on good practices and criteria leading to the improvement of nuclear safety during those conditions. The work was organised in 3 phases: Collecting data on current practices; Analysis of questionnaire answers and drawing up of safety good practices references and recommendations; Collecting relevant ideas related to the future reactors at design stage (European Pressurised Water Reactor, European Passive Plant project, European Utilities Requirements and Utilities Requirement Document project). The key element of the performed work was the detailed questionnaire, based on bibliographical review, expert experience and outage practices available in the working team. Different safety areas and activities were covered: outage context; nuclear safety; outage strategy, organisation and control; operating feedback; use of Probabilistic Safety Assessment. The questionnaire was answered by 12 European nuclear power plants, representing 9 different European countries and three different types of reactors (Pressurised Water Reactor, Boiling Water Reactor and Water Water Energy Reactor). Conclusions were drawn under the following headers: Organisational survey and generalities Organisational effectiveness Quality of maintenance Quality of operation Engineering support, management of modification Specific aspects Each analysed subject includes the following topics: Questions background with a summary and the aim of the questions. Current status, that describes common practices, as derived from the answers to the questionnaire, and some examples of good specific practices. Identified good practices. (author)

Current status of nuclear power

International Nuclear Information System (INIS)

Behnke, W.B.

1984-01-01

The decision to devote the 1984 conference to nuclear power is timely and appropriate. Illinois has a long, and distinguished history in the development of civilian nuclear power. The concept was born at the University of Chicago, developed at Argonne National Laboratory and demonstrated on the Commonwealth Edison system at our pioneer Dresden Nuclear Station. Today, Illinois ranks number one in the nation in nuclear generation. With over a quarter century of commercial operating experience, nuclear power has proven its worth and become a significant and growing component of electric power supply domestically and throughout the world. Despite its initial acceptance, however, the nuclear power industry in the U.S. is now in the midst of a difficult period of readjustment stemming largely from the economic and regulatory problems of the past decade. As a result, the costs of plants under construction have increased dramatically, causing serious financial difficulties for several projects and their owners. At the same time, the U.S. is facing hard choices concerning its future energy supplies. Conferences such as this have an important role in clarifying the issues and helping to find solutions to today's pressing energy problems. This paper summarizes the status of nuclear power both here and abroad, discussing the implications of current events in the context of national energy policy and economic development here in Illinois

[Molecular imaging; current status and future prospects in USA].

Science.gov (United States)

Kobayashi, Hisataka

2007-02-01

The goal of this review is to introduce the definition, current status, and future prospects of the molecular imaging, which has recently been a hot topic in medicine and the biological science in USA. In vivo imaging methods to visualize the molecular events and functions in organs or animals/humans are overviewed and discussed especially in combinations of imaging modalities (machines) and contrast agents(chemicals) used in the molecular imaging. Next, the close relationship between the molecular imaging and the nanotechnology, an important part of nanomedicine, is stressed from the aspect of united multidisciplinary sciences such as physics, chemistry, biology, and medicine.

Interventional Radiology of Male Varicocele: Current Status

International Nuclear Information System (INIS)

Iaccarino, Vittorio; Venetucci, Pietro

2012-01-01

Varicocele is a fairly common condition in male individuals. Although a minor disease, it may cause infertility and testicular pain. Consequently, it has high health and social impact. Here we review the current status of interventional radiology of male varicocele. We describe the radiological anatomy of gonadal veins and the clinical aspects of male varicocele, particularly the physical examination, which includes a new clinical and ultrasound Doppler maneuver. The surgical and radiological treatment options are also described with the focus on retrograde and antegrade sclerotherapy, together with our long experience with these procedures. Last, we compare the outcomes, recurrence and persistence rates, complications, procedure time and cost-effectiveness of each method. It clearly emerges from this analysis that there is a need for randomized multicentre trials designed to compare the various surgical and percutaneous techniques, all of which are aimed at occlusion of the anterior pampiniform plexus.

Current Status of Concentrator Photovoltaic (CPV) Technology

Energy Technology Data Exchange (ETDEWEB)

Philipps, Simon P. [Fraunhofer Inst. for Solar Energy Systems ISE, Freiburg (Germany); Bett, Andreas W. [Fraunhofer Inst. for Solar Energy Systems ISE, Freiburg (Germany); Horowitz, Kelsey [National Renewable Energy Lab. (NREL), Golden, CO (United States); Kurtz, Sarah [National Renewable Energy Lab. (NREL), Golden, CO (United States)

2015-12-01

This report summarizes the status of the concentrator photovoltaic (CPV) market and industry as well as current trends in research and technology. This report is intended to guide research agendas for Fraunhofer ISE, the National Renewable Energy Laboratory (NREL), and other R&D organizations. Version 1.1 of this report includes recent progress in CPV. The recent record module efficiency of 38.9% at Concentrator Standard Test Conditions (CSTC) is an impressive result, demonstrating the continuing opportunity for CPV technology to improve. 38.9% at Concentrator Standard Test Conditions (CSTC) is an impressive result, demonstrating the continuing opportunity for CPV technology to improve. 38.9% at Concentrator Standard Test Conditions (CSTC) is an impressive result, demonstrating the continuing opportunity for CPV technology to improve. 38.9% at Concentrator Standard Test Conditions (CSTC) is an impressive result, demonstrating the continuing opportunity for CPV technology to improve.

Interventional Radiology of Male Varicocele: Current Status

Energy Technology Data Exchange (ETDEWEB)

Iaccarino, Vittorio, E-mail: vittorio.iaccarino@unina.it; Venetucci, Pietro [University of Naples ' Federico II' , Diagnostic Imaging Department-Cardiovascular and Interventional Radiology, School of Medicine (Italy)

2012-12-15

Varicocele is a fairly common condition in male individuals. Although a minor disease, it may cause infertility and testicular pain. Consequently, it has high health and social impact. Here we review the current status of interventional radiology of male varicocele. We describe the radiological anatomy of gonadal veins and the clinical aspects of male varicocele, particularly the physical examination, which includes a new clinical and ultrasound Doppler maneuver. The surgical and radiological treatment options are also described with the focus on retrograde and antegrade sclerotherapy, together with our long experience with these procedures. Last, we compare the outcomes, recurrence and persistence rates, complications, procedure time and cost-effectiveness of each method. It clearly emerges from this analysis that there is a need for randomized multicentre trials designed to compare the various surgical and percutaneous techniques, all of which are aimed at occlusion of the anterior pampiniform plexus.

Robotic technology in surgery: current status in 2008.

Science.gov (United States)

Murphy, Declan G; Hall, Rohan; Tong, Raymond; Goel, Rajiv; Costello, Anthony J

2008-12-01

There is increasing patient and surgeon interest in robotic-assisted surgery, particularly with the proliferation of da Vinci surgical systems (Intuitive Surgical, Sunnyvale, CA, USA) throughout the world. There is much debate over the usefulness and cost-effectiveness of these systems. The currently available robotic surgical technology is described. Published data relating to the da Vinci system are reviewed and the current status of surgical robotics within Australia and New Zealand is assessed. The first da Vinci system in Australia and New Zealand was installed in 2003. Four systems had been installed by 2006 and seven systems are currently in use. Most of these are based in private hospitals. Technical advantages of this system include 3-D vision, enhanced dexterity and improved ergonomics when compared with standard laparoscopic surgery. Most procedures currently carried out are urological, with cardiac, gynaecological and general surgeons also using this system. The number of patients undergoing robotic-assisted surgery in Australia and New Zealand has increased fivefold in the past 4 years. The most common procedure carried out is robotic-assisted laparoscopic radical prostatectomy. Published data suggest that robotic-assisted surgery is feasible and safe although the installation and recurring costs remain high. There is increasing acceptance of robotic-assisted surgery, especially for urological procedures. The da Vinci surgical system is becoming more widely available in Australia and New Zealand. Other surgical specialties will probably use this technology. Significant costs are associated with robotic technology and it is not yet widely available to public patients.

Current statistical tools, systems and bodies concerned with safety and accident statistics.

NARCIS (Netherlands)

Koornstra, M.J.

1996-01-01

There are a wide range of differences in the methods used nationally to classify and record road accidents. The current use of road safety information systems and the few systems available for international use are discussed. Recommendations are made for a more efficient, less costly, and improved

Current Status and Application of Hazard Definition Technology

Science.gov (United States)

Greene, George C.

1997-01-01

A research is performed: to define wake non-encounter & hazard, to provide requirements for sensors, and to obtain input from the user community. This research includes: validating wake encounter simulation models, establishing a metric to quantify the upset potential of a wake encounter, applying hazard metric and simulation models to the commercial fleet for development of candidate acceptable encounter limits, and applying technology to near term problems to evaluate current status of technology. The following lessons are learned from this project: technology is not adequate to determine absolute spacing requirements; time, not distance, determines the duration of the wake hazard; Optimum standards depend on the traffic; Wing span is an important parameter for characterizing both generator and follower; and Short span "biz jets" are easily rolled.

Safety research on fusion DEMO in Japan: Toward development of safety strategy of a water-cooled DEMO

Energy Technology Data Exchange (ETDEWEB)

Nakamura, Makoto, E-mail: nakamura.makoto@jaea.go.jp [Japan Atomic Energy Agency, Rokkasho 039-3212, Aomori (Japan); Tobita, Kenji; Someya, Youji; Utoh, Hiroyasu; Sakamoto, Yoshiteru [Japan Atomic Energy Agency, Rokkasho 039-3212, Aomori (Japan); Gulden, Werner [Fusion for Energy, Garching D-85748 (Germany)

2016-11-01

Highlights: • This paper reports the current status of a safety research on water-cooled fusion DEMO in Japan. • We report analyses of two transients: (i) complete loss of decay heat removal and (ii) major ex-VV LOCA. • The MELCOR analysis has clarified the temperature histories of the DEMO components in complete loss of decay heat removal. • A strategy to reduce the pressure load to the final barrier confining radioactive materials is proposed against the major ex-VV LOCA. - Abstract: This paper reports the current status of a safety research on water-cooled fusion DEMO in Japan. A basic strategy of development of the safety guidelines is described for DEMO based on a water-cooled solid pebble bed blanket. Clarification of safety features of the DEMO in accident situations is a key issue to develop the guidelines. Recent achievements in understanding of the safety features of the water-cooled DEMO are reported. The MELCOR analysis has clarified the temperature histories of the DEMO components in a complete loss of decay heat removal event. The transient behavior of the first wall temperature is found to be essentially different from that of ITER. The pressure load to the tokamak cooling water system vault (TCWSV) is analyzed based on a simple model equation of the energy conservation. If the amount of the primary coolant is the same as that of Slim-CS, the previous small Japanese DEMO, the discharged water does not damage the TCWSV with the volume and pressure-tightness similar to those of pressurized light water reactors. It is shown that implementation of a pressure suppression system to the small TCWSV is effective to suppress the pressure load to the second confinement barrier.

Hepatitis B Virus Infection in Tanzania: Current Status and Challenges

Science.gov (United States)

Bakshi, Fatma A.; Jaka, Hyasinta

2018-01-01

Hepatitis B is one of the most common infectious diseases in the world with high prevalence in most of sub-Saharan Africa countries. The complexity in its diagnosis and treatment poses a significant management challenge in the resource-limited settings including Tanzania, where most of the tests and drugs are either unavailable or unaffordable. This mini review aims at demonstrating the current status of the disease in the country and discussing the concomitant challenges in diagnosis, treatment, and prevention. PMID:29666656

Hepatitis B Virus Infection in Tanzania: Current Status and Challenges

Directory of Open Access Journals (Sweden)

Semvua B. Kilonzo

2018-01-01

Full Text Available Hepatitis B is one of the most common infectious diseases in the world with high prevalence in most of sub-Saharan Africa countries. The complexity in its diagnosis and treatment poses a significant management challenge in the resource-limited settings including Tanzania, where most of the tests and drugs are either unavailable or unaffordable. This mini review aims at demonstrating the current status of the disease in the country and discussing the concomitant challenges in diagnosis, treatment, and prevention.

77 FR 25179 - Patient Safety Organizations: Voluntary Relinquishment From Surgical Safety Institute

Science.gov (United States)

2012-04-27

... DEPARTMENT OF HEALTH AND HUMAN SERVICES Agency for Healthcare Research and Quality Patient Safety... voluntary relinquishment from the Surgical Safety Institute of its status as a Patient Safety Organization (PSO). The Patient Safety and Quality Improvement Act of 2005 (Patient Safety Act) authorizes the...

Development of safety performance indicators in Japan

International Nuclear Information System (INIS)

Ohashi, H.; Tamao, S.; Tanaka, J.; Sawayama, T.

2001-01-01

For the purpose of safety regulations of operating nuclear power stations in Japan, the regulatory authorities utilize two types of regulations. One is the direct regulation, such as periodical inspection to inspect the function and performance of equipment important to safety, and the other is the audit type regulation such as preservation inspection to audit the compliance with the safety preservation rules. As performance indicators are expected to be an effective tool to evaluate the activities by audit type regulations, NUPEC is studying a comprehensive set of operational performance indicators to meet the effective evaluation method for the safety preservation activities in the audit type regulations under the frame of current safety regulation system. The study includes the establishment of comprehensive operational performance indicators applicable in Japan, the effective application of performance indicators to the current Japanese regulation, the clarification of the applicable scope of utilization, the possibility of applying the performance indicators. This report describes the present status of our performance indicator studies. After the completion of these studies the regulatory authorities will evaluate if and how the new set of comprehensive performance indicators could be introduced to Japanese regulatory scheme. (author)

Investigation on regulatory requirements for radiation safety management

International Nuclear Information System (INIS)

Han, Eun Ok; Choi, Yoon Seok; Cho, Dae Hyung

2013-01-01

NRC recognizes that efficient management of radiation safety plan is an important factor to achieve radiation safety service. In case of Korea, the contents to perform the actual radiation safety management are legally contained in radiation safety management reports based on the Nuclear Safety Act. It is to prioritize the importance of safety regulations in each sector in accordance with the current situation of radiation and radioactive isotopes-used industry and to provide a basis for deriving safety requirements and safety regulations system maintenance by the priority of radiation safety management regulations. It would be helpful to achieve regulations to conform to reality based on international standards if consistent safety requirements is developed for domestic users, national standards and international standards on the basis of the results of questions answered by radiation safety managers, who lead on-site radiation safety management, about the priority of important factors in radioactive sources use, sales, production, moving user companies, to check whether derived configuration requirements for radiation safety management are suitable for domestic status

Fast reactor test facilities in the US safety program

International Nuclear Information System (INIS)

Avery, R.; Dickerman, C.E.; Lennox, D.H.; Rose, D.

1979-01-01

The needs for safety information derivable from in-pile programs are reviewed, and the correlation made with existing and planned capability. In view of the current status of the U.S. breeder program, emphasis is given in the review to the impact of different fast breeder options on the required program and facilities. It is concluded that facility needs are somewhat independent of specific fast breeder concept, even though the relative emphasis on the various safety issues will differ. 8 refs

Civilian Power Program. Part 1, Summary, Current status of reactor concepts

Energy Technology Data Exchange (ETDEWEB)

Author, Not Given

1959-09-01

This study group covered the following: delineation of the specific objectives of the overall US AEC civilian power reactor program, technical objectives of each reactor concept, preparation of a chronological development program for each reactor concept, evaluation of the economic potential of each reactor type, a program to encourage the the development, and yardsticks for measuring the development. Results were used for policy review by AEC, program direction, authorization and appropriation requests, etc. This evaluation encompassed civilian power reactors rated at 25 MW(e) or larger and related experimental facilities and R&D. This Part I summarizes the significant results of the comprehensive effort to determine the current technical and economic status for each reactor concept; it is based on the 8 individual technical status reports (Part III).

Current status of ITER EC design

International Nuclear Information System (INIS)

Bosia, G.

2003-01-01

The ITER-FEAT Electron Cyclotron System employs one equatorial launcher and three upper port launchers to inject 20 + 20 MW of mm-wave power at 170 GHz through slots in the plasma-facing neutron and radiation shield. The equatorial launcher includes 3 sets of toroidally steer-able mirrors, each collecting 8 RF beams from 24 circular cross-section corrugated wave-guides. In the upper-port launcher, eight beams, reflected in pairs by four toroidally angled (∼30 angle) and poloidally steer-able (∼ 10 angle) mirrors focus of the RF power on the plasma m = 2 and m = 3/2 plasma flux rational surfaces, for neo-classical tearing mode(s) (NTM) control. Conceptual studies of remote steering that would possibly allow removing the beam- steering equipment from the vacuum vessel and locating them in more protected positions have been carried out. All EC wave transmission is based on low losses circular cross section corrugated and evacuated wave guides each connected to a 170 GHz, 1 MW CW Gyrotron tube oscillator featuring an overall efficiency of ∼ 50%, obtained by depressed-collector energy recovery. In the paper, requirements, issues and the current status of the design is reviewed. (authors)

Current status of cadmium as an environmental health problem

International Nuclear Information System (INIS)

Jaerup, Lars; Akesson, Agneta

2009-01-01

Cadmium is a toxic metal occurring in the environment naturally and as a pollutant emanating from industrial and agricultural sources. Food is the main source of cadmium intake in the non-smoking population. The bioavailability, retention and toxicity are affected by several factors including nutritional status such as low iron status. Cadmium is efficiently retained in the kidney (half-time 10-30 years) and the concentration is proportional to that in urine (U-Cd). Cadmium is nephrotoxic, initially causing kidney tubular damage. Cadmium can also cause bone damage, either via a direct effect on bone tissue or indirectly as a result of renal dysfunction. After prolonged and/or high exposure the tubular injury may progress to glomerular damage with decreased glomerular filtration rate, and eventually to renal failure. Furthermore, recent data also suggest increased cancer risks and increased mortality in environmentally exposed populations. Dose-response assessment using a variety of early markers of kidney damage has identified U-Cd points of departure for early kidney effects between 0.5 and 3 μg Cd/g creatinine, similar to the points of departure for effects on bone. It can be anticipated that a considerable proportion of the non-smoking adult population has urinary cadmium concentrations of 0.5 μg/g creatinine or higher in non-exposed areas. For smokers this proportion is considerably higher. This implies no margin of safety between the point of departure and the exposure levels in the general population. Therefore, measures should be put in place to reduce exposure to a minimum, and the tolerably daily intake should be set in accordance with recent findings.

Study of In-Pile test facility for fast reactor safety research: performance requirements and design features

Energy Technology Data Exchange (ETDEWEB)

Nonaka, N.; Kawatta, N.; Niwa, H.; Kondo, S.; Maeda, K

1996-12-31

This paper describes a program and the main design features of a new in-pile safety facility SERAPH planned for future fast reactor safety research. The current status of R and D on technical developments in relation to the research objectives and performance requirements to the facility design is given.

Tele-yoga for Chronic Pain: Current Status and Future Directions.

Science.gov (United States)

Mathersul, Danielle C; Mahoney, Louise A; Bayley, Peter J

2018-01-01

Pain is a pervasive, debilitating disorder that is resistant to long-term pharmacological interventions. Although psychological therapies such as cognitive behavior therapy demonstrate moderate efficacy, many individuals continue to have ongoing difficulties following treatment. There is a current trend to establish complementary and integrative health interventions for chronic pain, for which yoga has been found to have exciting potential. Nevertheless, an important consideration within the field is accessibility to adequate care. Telehealth can be used to provide real-time interactive video conferencing leading to increased access to health care for individuals located remotely or who otherwise have difficulty accessing services, perhaps through issues of mobility or proximity of adequate services. This article assesses the current status and feasibility of implementing tele-yoga for chronic pain. Methodological limitations and recommendations for future research are discussed.

The Japanese artificial organs scene: current status.

Science.gov (United States)

Mitamura, Yoshinori; Murabayashi, Shun

2005-08-01

Artificial organs and regenerative medicine are the subjects of very active research and development (R&D) in Japan and various artificial organs are widely used in patients. Results of the R&D are presented at the annual conference of the Japanese Society for Artificial Organs (JSAO). Progress in the fields of artificial organs and regenerative medicine are reviewed annually in the Japanese Journal of Artificial Organs. The official English-language journal of JSAO, Journal of Artificial Organs, also publishes many original articles by Japanese researchers. Although the annual conference and the publications of JSAO provide the world with update information on artificial organs and regenerative medicine in Japan, the information is not always understood appropriately in the rest of the world, mainly due to language problems. This article therefore introduces the current status of artificial organs and regenerative medicine in Japan. Artificial hearts and metabolic support systems are reviewed here and other interesting areas such as regenerative medicine can be found elsewhere.

Current status of GALS setup in JINR

Energy Technology Data Exchange (ETDEWEB)

Zemlyanoy, S., E-mail: zemlya@jinr.ru; Avvakumov, K., E-mail: kavvakumov@jinr.ru [Joint Institute for Nuclear Research, Flerov Laboratory of Nuclear Reactions (Russian Federation); Fedosseev, V. [CERN (Switzerland); Bark, R. [Nat. Research Foundation, iThemba LABS (South Africa); Blazczak, Z. [A. Mickiewicz University, Faculty of Physics (Poland); Janas, Z. [University of Warsaw, Faculty of Physics (Poland)

2017-11-15

This is a brief report on the current status of the new GAs cell based Laser ionization Setup (GALS) at the Flerov Laboratory for Nuclear Reactions (FLNR) of the Joint Institute for Nuclear Research (JINR) in Dubna. GALS will exploit available beams from the U-400M cyclotron in low energy multi-nucleon transfer reactions to study exotic neutron-rich nuclei located in the “north-east” region of nuclear map. Products from 4.5 to 9 MeV/nucleon heavy-ion collisions, such as {sup 136}Xe on {sup 208}Pb, are thermalized and neutralized in a high pressure gas cell and subsequently selectively laser re-ionized. In order to choose the best scheme of ion extraction the results of computer simulations of two different systems are presented. The first off- and online experiment will be performed on osmium atoms that is regarded as a most convenient element for producing isotopes with neutron number in the vicinity of the magic N = 126.

NPP Temelin safety analysis reports and PSA status

International Nuclear Information System (INIS)

Mlady, O.

1999-01-01

To enhance the safety level of Temelin NPP, recommendations of the international reviews were implemented into the design as well as into organization of the plant construction and preparation for operation. The safety assessment of these design changes has been integrated and reflected in the Safety Analysis Reports, which follow the internationally accepted guidelines. All safety analyses within Safety Analysis Reports were repeated carefully considering technical improvements and replacements to complement preliminary safety documentation. These analyses were performed by advanced western computer codes to the depth and in the structure required by western standards. The Temelin NPP followed a systematic approach in the functional design of the Reactor Protection System and related safety analyses. Modifications of reactor protection system increase defense in depth and facilitate demonstrating that LOCA and radiological limits are met for non-LOCA events. The rigorous safety analysis methodology provides assurance that LOCA and radiological limits are met. Established and accepted safety analysis methodology and accepted criteria were applied to Temelin NPP meeting US NRC and Czech Republic requirements. IAEA guidelines and recommendations

Pediatric regional anesthesia: what is the current safety record?

Science.gov (United States)

Polaner, David M; Drescher, Jessica

2011-07-01

The use of regional anesthetics, whether as adjuncts, primary anesthetics or postoperative analgesia, is increasingly common in pediatric practice. Data on safety remain limited because of the paucity of very large-scale prospective studies that are necessary to detect low incidence events, although several studies either have been published or have reported preliminary results. This paper will review the data on complications and risk in pediatric regional anesthesia. Information currently available suggests that regional blockade, when performed properly, carries a very low risk of morbidity and mortality in appropriately selected infants and children. © 2010 Blackwell Publishing Ltd.

Reactor safety in Eastern Europe. Proceedings

International Nuclear Information System (INIS)

1995-02-01

The papers presented to the GRS colloquium refer to the cooperative activities for reactor accident analysis and modification of the GRS computer codes for their application to reactors of the Russian design types of WWER or RBMK. Another topic is the safety of RBMK reactors in particular, and the current status of investigations and studies addressing the containment of unit 4 of the Chernobyl reactor station. (HP) [de

Current status of large-scale cryogenic gravitational wave telescope

International Nuclear Information System (INIS)

Kuroda, K; Ohashi, M; Miyoki, S; Uchiyama, T; Ishitsuka, H; Yamamoto, K; Kasahara, K; Fujimoto, M-K; Kawamura, S; Takahashi, R; Yamazaki, T; Arai, K; Tatsumi, D; Ueda, A; Fukushima, M; Sato, S; Nagano, S; Tsunesada, Y; Zhu, Zong-Hong; Shintomi, T; Yamamoto, A; Suzuki, T; Saito, Y; Haruyama, T; Sato, N; Higashi, Y; Tomaru, T; Tsubono, K; Ando, M; Takamori, A; Numata, K; Aso, Y; Ueda, K-I; Yoneda, H; Nakagawa, K; Musha, M; Mio, N; Moriwaki, S; Somiya, K; Araya, A; Kanda, N; Telada, S; Tagoshi, H; Nakamura, T; Sasaki, M; Tanaka, T; Oohara, K; Takahashi, H; Miyakawa, O; Tobar, M E

2003-01-01

The large-scale cryogenic gravitational wave telescope (LCGT) project is the proposed advancement of TAMA, which will be able to detect the coalescences of binary neutron stars occurring in our galaxy. LCGT intends to detect the coalescence events within about 240 Mpc, the rate of which is expected to be from 0.1 to several events in a year. LCGT has Fabry-Perot cavities of 3 km baseline and the mirrors are cooled down to a cryogenic temperature of 20 K. It is planned to be built in the underground of Kamioka mine. This paper overviews the revision of the design and the current status of the R and D

CT myocardial perfusion imaging: current status and future perspectives.

Science.gov (United States)

Yang, Dong Hyun; Kim, Young-Hak

2017-07-01

Computed tomography myocardial perfusion (CTP) combined with coronary computed tomography angiography (CCTA) may constitute a "1-stop shop" for the noninvasive diagnosis of hemodynamically significant coronary stenosis during a single CT examination. CTP shows high diagnostic performance and provides incremental value over CCTA for the detection of hemodynamically significant coronary stenosis in patients with a high Agatston calcium score or coronary artery stents. Future studies should determine the optimal protocol and clinical value of CTP for guiding revascularization strategy and prognostication. In this article, we review the current status and future perspectives of CTP, focusing on technical considerations, clinical applications, and future research topics.

History and current status of nuclear fuel reprocessing technology

International Nuclear Information System (INIS)

Funasaka, Hideyuki; Nagai, Toshihisa; Washiya, Tadahiro

2008-01-01

History and present state of fast breeder reactor was reviewed in series. As a history and current status of nuclear fuel reprocessing technology, this ninth lecture presented the progress of the FBR fuel reprocessing technology and advanced reprocessing processes. FBR fuel reprocessing technology had been developed to construct the reprocessing equipment test facilities (RETF) based on PUREX process technologies. With economics, reduction of environmental burdens and proliferation resistance taken into consideration, advanced aqueous method for nuclear fuel cycle activities has been promoted as the government's basic policy. Innovative technologies on mechanical disassembly, continuous rotary dissolver, crystallizer, solvent extraction and actinides recovery have been mainly studied. (T. Tanaka)

Community-based dental education: history, current status, and future.

Science.gov (United States)

Formicola, Allan J; Bailit, Howard L

2012-01-01

This article examines the history, current status, and future direction of community-based dental education (CBDE). The key issues addressed include the reasons that dentistry developed a different clinical education model than the other health professions; how government programs, private medical foundations, and early adopter schools influenced the development of CBDE; the societal and financial factors that are leading more schools to increase the time that senior dental students spend in community programs; the impact of CBDE on school finances and faculty and student perceptions; and the reasons that CBDE is likely to become a core part of the clinical education of all dental graduates.

Early Childhood Inclusion in the United States: Goals, Current Status, and Future Directions

Science.gov (United States)

Guralnick, Michael J.; Bruder, Mary Beth

2016-01-01

The current status and future directions of early childhood inclusion in the United States are discussed from the perspective of 4 key goals: access, accommodations and feasibility, developmental progress, and social integration. Recommendations are put forward to promote inclusion goals emphasizing administrative structures, personnel…

[Current approaches to evaluating the anatomic and functional status of the cornea].

Science.gov (United States)

Avetisov, S E; Borodina, N V; Kobzova, M V; Musaeva, G M

2010-01-01

The review provides data on current methods for evaluating the anatomic and functional status of the cornea (light refraction, light transmission, and biomechanical properties, in particular). It analyzes the main advantages and disadvantages of basic (biomicroscopy, endothelial microscopy, ophthalmometry, topography, and pachymetry) and special (confocal microscopy, optical coherence tomography, ultrasound biomicroscopy, aberrometry, bidirectional corneal applanation, and keratoesthesiometry) studies.

Probabilistic safety criteria at the safety function/system level

International Nuclear Information System (INIS)

1989-09-01

A Technical Committee Meeting was held in Vienna, Austria, from 26-30 January 1987. The objectives of the meeting were: to review the national developments of PSC at the level of safety functions/systems including future trends; to analyse basic principles, assumptions, and objectives; to compare numerical values and the rationale for choosing them; to compile the experience with use of such PSC; to analyse the role of uncertainties in particular regarding procedures for showing compliance. The general objective of establishing PSC at the level of safety functions/systems is to provide a pragmatic tool to evaluate plant safety which is placing emphasis on the prevention principle. Such criteria could thus lead to a better understanding of the importance to safety of the various functions which have to be performed to ensure the safety of the plant, and the engineering means of performing these functions. They would reflect the state-of-the-art in modern PSAs and could contribute to a balance in system design. This report, prepared by the participants of the meeting, reviews the current status and future trends in the field and should assist Member States in developing their national approaches. The draft of this document was also submitted to INSAG to be considered in its work to prepare a document on safety principles for nuclear power plants. Five papers presented at the meeting are also included in this publication. A separate abstract was prepared for each of these papers. Refs, figs and tabs

76 FR 71345 - Patient Safety Organizations: Voluntary Relinquishment From Child Health Patient Safety...

Science.gov (United States)

2011-11-17

... Organizations: Voluntary Relinquishment From Child Health Patient Safety Organization, Inc. AGENCY: Agency for... notification of voluntary relinquishment from Child Health Patient Safety Organization, Inc. of its status as a Patient Safety Organization (PSO). The Patient Safety and Quality Improvement Act of 2005 (Patient Safety...

76 FR 79192 - Patient Safety Organizations: Voluntary Relinquishment From HSMS Patient Safety Organization

Science.gov (United States)

2011-12-21

... Organizations: Voluntary Relinquishment From HSMS Patient Safety Organization AGENCY: Agency for Healthcare... voluntary relinquishment from the HSMS Patient Safety Organization of its status as a Patient Safety Organization (PSO). The Patient Safety and Quality Improvement Act of 2005 (Patient Safety Act), Public Law 109...

Reactor safety in Eastern Europe

International Nuclear Information System (INIS)

1995-02-01

The papers presented to the GRS colloquium refer to the cooperative activities for reactor accident analysis and modification of the GRS computer codes for their application to reactors of the Russian design types of WWER or RBMK. Another topic is the safety of RBMK reactors in particular, and the current status of investigations and studies addressing the containment of unit 4 of the Chernobyl reactor station. All papers are indexed separately in report GRS--117. (HP)

Fuel Cell Buses in U.S. Transit Fleets: Current Status 2011

Energy Technology Data Exchange (ETDEWEB)

Eudy, L.; Chandler, K.; Gikakis, C.

2011-11-01

This status report, fifth in a series of annual status reports from the U.S. Department of Energy's National Renewable Energy Laboratory (NREL), discusses the achievements and challenges of fuel cell propulsion for transit and summarizes the introduction of fuel cell transit buses in the United States. Progress this year includes an increase in the number of fuel cell electric buses (FCEBs), from 15 to 25, operating at eight transit agencies, as well as increased diversity of the fuel cell design options for transit buses. The report also provides an analysis of the combined results from fuel cell transit bus demonstrations evaluated by NREL with a focus on the most recent data through July 2011 including fuel cell power system reliability and durability; fuel economy; roadcall; and hydrogen fueling results. These evaluations cover 22 of the 25 FCEBs currently operating.

Current status on techniques for determining paleo-temperature using geothermometer

International Nuclear Information System (INIS)

Kanazawa, Sunao; Oikawa, Teruki; Umeda, Koji; Tomiyama, Shingo

2005-01-01

Development of the research technologies for geotectonic events has been carried out to evaluate the long-term stability of geological environment. In terms of the effects of geothermal activity, it is necessary to estimate the geothermal regime and thermal history on any given site. This paper describes the current status on techniques for determining paleo-temperature using geothermometer, and presents a concept of the systematic research techniques. The application of geothermometer, especially thermochronology, has been effective in the studies on the cooling history of geological body and the paleo-geothermal structure at depth. (author)

CANDU safety management in Pakistan. A status report

Energy Technology Data Exchange (ETDEWEB)

Mazhar Hasan, S; Badshah Hussain, S; Mirza, K F; Siddiqui, Z H [Karachi Nuclear Power Plant (KANUPP) (Pakistan)

1997-12-01

The overall safety performance of KANUPP against these requirements has been quite good over the past 25 years. But the phenomena of equipment aging, equipment absolescence and evolution of nuclear safety standards, faced by all older NPPs, were aggravated for KANUPP by complete technological isolation from the vendor country for more than 14 years, When it became possible following international attention in 1990, an IAEA sponsored project titled `Safe Operation of KANUPP (SOK)` was started to assess and ensure compliance to the contemporary internationally acceptable level of safety, leading to a prioritized and Integrated Safety Review Master Plan (ISARMAP) implemented under the supervision of an international Steering Committee. Fortunately, the work done so far has indicated good overall equipment condition, effective obsolescence measures, adequate operational safety practices, and adequate design safety using up-to-date analytical methods. Further detailed analyses and improvements are continuing, to avoid the future potential for an unacceptable level of safety. Difficulties in applying modern safety design standards to backfits are common to older NPPs. 13 refs.

CANDU safety management in Pakistan. A status report

International Nuclear Information System (INIS)

Mazhar Hasan, S.; Badshah Hussain, S.; Mirza, K.F.; Siddiqui, Z.H.

1997-01-01

The overall safety performance of KANUPP against these requirements has been quite good over the past 25 years. But the phenomena of equipment aging, equipment absolescence and evolution of nuclear safety standards, faced by all older NPPs, were aggravated for KANUPP by complete technological isolation from the vendor country for more than 14 years, When it became possible following international attention in 1990, an IAEA sponsored project titled 'Safe Operation of KANUPP (SOK)' was started to assess and ensure compliance to the contemporary internationally acceptable level of safety, leading to a prioritized and Integrated Safety Review Master Plan (ISARMAP) implemented under the supervision of an international Steering Committee. Fortunately, the work done so far has indicated good overall equipment condition, effective obsolescence measures, adequate operational safety practices, and adequate design safety using up-to-date analytical methods. Further detailed analyses and improvements are continuing, to avoid the future potential for an unacceptable level of safety. Difficulties in applying modern safety design standards to backfits are common to older NPPs. 13 refs

WISM - A Wideband Instrument for Snow Measurement: Past Accomplishments, Current Status, and Path Forward

Science.gov (United States)

Bonds, Quenton; Racette, Paul; Durham, Tim (Principal Investigator)

2016-01-01

Presented are the prior accomplishments, current status and path forward for GSFC's Wideband Instrument for Snow Measurement (WISM). This work is a high level overview of the project, presented via Webinar to the IEEE young professionals.

Psychological Therapies for Auditory Hallucinations (Voices): Current Status and Key Directions for Future Research

NARCIS (Netherlands)

Thomas, N.; Hayward, M.; Peters, E; van der Gaag, M.; Bentall, R.P.; Jenner, J.; Strauss, C.; Sommer, I.E.; Johns, L.C.; Varese, F.; Gracia-Montes, J.M.; Waters, F.; Dodgson, G.; McCarthy-Jones, S.

2014-01-01

This report from the International Consortium on Hallucinations Research considers the current status and future directions in research on psychological therapies targeting auditory hallucinations (hearing voices). Therapy approaches have evolved from behavioral and coping-focused interventions,

Status and prospects of safety research about fuel cycle facilities in France

International Nuclear Information System (INIS)

Auchere, H.; Mercier, J.P.

1996-01-01

Although there is a good knowledge of the risks and no major accident occurred in France, as in other OECD countries, it remains useful to complete basic knowledge and to allow the quality of fuel cycle plants safety assessments to be improved further, particularly in countries equipped with a 'complete' nuclear fuel cycle (France, Japan and U.K.). The scope of the current and future IPSN ('Institut de Protection et de Surete Nucleaire': institute for protection and nuclear safety) research deals with the whole fuel cycle. The overview presented here in NUCEF'95 symposium contains a number of specific themes, some of which have already been started. Successful conclusion of the safety researches will allow the IPSN to have a more precise understanding about specific phenomena and notably to replace 'engineer judgements', though they may be based on a lot of experience and competence, by more scientifically established basic data. (J.P.N.)

MDSplus integration at TCABR tokamak: Current status

International Nuclear Information System (INIS)

Sá, W.P. de; Ronchi, G.

2016-01-01

Highlights: • The implementation of MDSplus in TCABR tokamak, current status. • Interfaces between the system already installed and the MDSplus. • Web MDSplus interface. - Abstract: Experimental data for the TCABR tokamak is currently stored in MDSplus (Model Driven System Plus) database. The access to the data recorded during the experiments is performed using tools and libraries available by MDSplus system. The MDSplus system is widely used in different physics experiments, especially in plasmas physics and nuclear fusion. This standardized environment enables easy interaction among scientists of different experiments in different countries without the need to understand the particular characteristics of control, data acquisition and analysis, and remote access (CODAS) customized in each laboratory. In the first phase of implementation, intermediate interfaces had been developed between the legacy proprietary system and the MDSplus. In a second phase, the new diagnostic systems had been directly included in the created MDSplus system in the laboratory. After three years of use, the system installed on TCABR proved extremely efficient and significantly increased productivity in data analysis by involved scientists, regardless of whether they are locally at the TCABR, or accessing the system remotely from their home laboratories. The third phase, and subject of this article, are the development and implementation of the following systems: (i) web tools for the visualization of data, integrated with the experiment logbook, (ii) integration of MDSplus with applications (LabVIEW + MDSplus) and newer data acquisition hardware.

MDSplus integration at TCABR tokamak: Current status

Energy Technology Data Exchange (ETDEWEB)

Sá, W.P. de, E-mail: pires@if.usp.br; Ronchi, G., E-mail: gronchi@if.usp.br

2016-11-15

Highlights: • The implementation of MDSplus in TCABR tokamak, current status. • Interfaces between the system already installed and the MDSplus. • Web MDSplus interface. - Abstract: Experimental data for the TCABR tokamak is currently stored in MDSplus (Model Driven System Plus) database. The access to the data recorded during the experiments is performed using tools and libraries available by MDSplus system. The MDSplus system is widely used in different physics experiments, especially in plasmas physics and nuclear fusion. This standardized environment enables easy interaction among scientists of different experiments in different countries without the need to understand the particular characteristics of control, data acquisition and analysis, and remote access (CODAS) customized in each laboratory. In the first phase of implementation, intermediate interfaces had been developed between the legacy proprietary system and the MDSplus. In a second phase, the new diagnostic systems had been directly included in the created MDSplus system in the laboratory. After three years of use, the system installed on TCABR proved extremely efficient and significantly increased productivity in data analysis by involved scientists, regardless of whether they are locally at the TCABR, or accessing the system remotely from their home laboratories. The third phase, and subject of this article, are the development and implementation of the following systems: (i) web tools for the visualization of data, integrated with the experiment logbook, (ii) integration of MDSplus with applications (LabVIEW + MDSplus) and newer data acquisition hardware.

Patient Safety Culture Status From The Perspective Medical Staff Of Yasuj Hospitals In 2015

Directory of Open Access Journals (Sweden)

M Rezaean

2016-01-01

Full Text Available Background & aim: One of the most important problems in the health sector, particularly in clinical centers, is the quality of healthcare. Patient safety is one of the most important elements in creating health care quality due to the fact that it is a critical component to the quality of health care and many errors are present in patient care and treatment practices..                                                               Thus, the aim of the present study was to determine the status of the patient safety culture and its relationship with events reported in Yasuj hospitals. Methods: The present descriptive cross-sectional study was conducted on 361 medical staff of Yasuj hospitals. The data were collected through a hospital survey on patient safety culture. The collected data were analyzed by using SPSS statistics soft ware version 21, using Descriptive methods, Pearson Coefficient, ANOVA, and T-Test. Results: The results of the present study revealed that the teamwork among hospital units (71/89percent, with expectations and management measures (66/38% in the case of safety obtained the most score and non-punitive response to errors (48/79% and manager support (55/88 percent obtained the least score. 73/7% of employees of three hospitals in the past 12 months did not report any event. In addition, there was a meaningful statistical relationship between the total score of safety culture and reporting the events. In this study, 15.5 % of respondents assess their safety culture in work as good, 44.3 % as acceptable and 30.5 percent reported poor. The overall safety culture among the three studied hospitals was 61.81 %. Results confirmed that the culture safety of patient in studied hospitals was average. Conclusions: The hospitals may rely on their strong points in terms of patient safety culture and try to remove their weak points to form a safe environment and appropriate

The status of safety of radiation sources and security of radioactive materials in Ethiopia

International Nuclear Information System (INIS)

Gebeyehu Wolde, G.

2001-01-01

Since 1993, the National Radiation Protection Authority (NRPA) has been empowered by the 'Radiation Protection Proclamation no. 79/1993' to authorize and inspect regulated activities, issue guidelines and standards and enforce the legislation and regulations. The report describes the status of the safety of radiation sources and the security of radioactive materials in Ethiopia and the progress made towards building a sound and effective national regulatory infrastructure. Also, the report highlights the challenges and difficulties encountered and concludes by indicating the way forward towards the strategic goals. (author)

Reflections on current nuclear safety problems

International Nuclear Information System (INIS)

Teillac, J.

1981-01-01

After operations totalling more than 2000 reactor-years, the safety balance is undeniably positive: no nuclear power plant in the world has so far caused significant damage to populations or to the environment. The paper reviews the darker and brighter aspects of recent analyses, in particular since the Harrisburg accident, and suggests three general lines of action: maintenance of a high level of technical competence in safety, systematic analysis of operational incidents and, finally, increased attention to the ''human factor'' as regards both the man/machine relationship and the training of personnel. With regard to the last-mentioned point, it is suggested that the greatest possible profit should be drawn from the tests carried out at the time of plant commissioning. International collaboration is particularly necessary both to ensure progress in the technical aspects of safety and to place the credibility of specialists on a firmer foundation. Finally, it is essential to assist countries which are embarking on nuclear power programmes. Nuclear safety is not always correctly perceived by public opinion, which will not definitively accept this new source of energy without having complete confidence in those who are promoting it. A clear and firm position on the part of those in positions of political responsibility is an important element in gaining public confidence. (author)

Current status of low power/shutdown PSA and accident sequence analysis for loss of RHR during mid-loop operation

International Nuclear Information System (INIS)

Park, Chang Kyu; Choi, Young; Kim, Tae Woon; Jin, Young Ho

1994-07-01

Probabilistic safety assessment (PSA) has been applied to only full-power operation of nuclear power plant (NPP), but some events which were recently occurred could reach severe plant damage state. Thus, various countries around the world have focused their interests on the evaluation for low power/shutdown (LP/S) operation. This report covers the main stream of LP/S PSA methodology, current status of LP/S PSA practices and results, and accident sequence analysis for loss of RHR during mid-loop operation. Therefore this report would be helpful for us to practice LP/S PSA for YGN 5,6 NPP which will be built in the near future. Also the results of accident sequence analysis show that operator's mis-diagnosis and failure of recovery action would initiate core damage during LP/S operation. In summary, overall environmental improvements (equipments, procedures, Tech Spec, etc, ...) and operating support system will be very useful to reduce risk during LP/S operation. (Author) 5 figs., 9 tabs

Convention on nuclear safety. Signature, ratification, acceptance, approval or accession. Status as of 17 March 1997

International Nuclear Information System (INIS)

1997-01-01

The document presents the status as of 17 March 1997 of signature, ratification, acceptance, approval or accession by Member States of the Convention on Nuclear Safety adopted on 17 June 1994 by the Diplomatic Conference convened by the IAEA at its Headquarters between 14-17 June 1994. The Convention entered into force on 24 October 1996. There are 65 signatories and 35 parties. Reservations/declarations deposited upon signature are also included

Operational Safety Performance Indicators and Balanced Scorecard in HANARO

International Nuclear Information System (INIS)

Wu, Jong-Sup; Jung, Hoan-Sung; Ahn, Guk-Hoon; Lee, Kye-Hong; Lim, In-Cheol; Kim, Hark-Rho

2007-01-01

Research reactors need an extensive basis for ensuring their safety. The importance of a safety management in nuclear facilities and activities has been emphasized. The safety activities in HANARO have been continuously conducted to enhance its safe operation. Last year, HANARO prepared two indicator sets to measure and assess the safety status of the reactor's operation and utilization. One is Safety Performance Indicators (SPI) and the other is Balanced Scorecard (BSC). Through reviewing these indicators, we can obtain the following information; - Plant safety status - Safety parameter trends - Safety information, for example, reactor operation status and radiation safety HANARO will continuously pursue the trends of SPI and BSC

Current Status and Future Agenda for the Theory, Research, and Practice of Childhood Career Development

Science.gov (United States)

Schultheiss, Donna E. Palladino

2008-01-01

This article reviews the current status and a future agenda for childhood career development theory, research, and practice. The fragmented nature of the current state of the literature is noted, and a call is made for a reexamination and reconsideration of the childhood developmental pathways of life's work. It is suggested that the study of…

Status of high temperature superconductor cable and fault current limiter projects at American Superconductor

International Nuclear Information System (INIS)

Maguire, J.F.; Yuan, J.

2009-01-01

This paper will describe the status of three key programs currently underway at American Superconductor Corp. The first program is the LIPA project which is a transmission voltage high temperature superconducting cable program, with funding support from the US Department of Energy. The 600 m cable, capable of carrying 574 MVA, was successfully installed and commissioned in LIPA grid on April 22, 2008. An overview of the project, system level design details and operational data will be provided. In addition, the status of the newly awarded LIPA II project will be described. The second program is Project Hydra, with funding support from the US Department of Homeland Security, to design, develop and demonstrate an HTS cable with fault current limiting functionality. The cable is 300 m long and is being designed to carry 96 MVA at a distribution level voltage of 13.8 kV. The cable will be permanently installed and energized in Manhattan, New York in 2010. The initial status of Project Hydra will be presented. The final program to be discussed is a transmission voltage, high temperature superconducting fault current limiter funded by the US DOE. The project encompasses the design, construction and test of a 115 kV FCL for power transmission within a time frame of 4-5 years. Installation and testing are planned for a Southern California Edison substation. A project overview and progress under the first phase will be reported.

Status of high temperature superconductor cable and fault current limiter projects at American Superconductor

Energy Technology Data Exchange (ETDEWEB)

Maguire, J.F., E-mail: jmaguire@amsc.co [American Superconductor Co., 64 Jackson Road, Devens, MA 01434 (United States); Yuan, J. [American Superconductor Co., 64 Jackson Road, Devens, MA 01434 (United States)

2009-10-15