75 FR 51525 - Railroad Safety Advisory Committee (RSAC); Working Group Activity Update

Science.gov (United States)

2010-08-20

.... The Working Group continues to work on after arrival orders, and at the September 25-26, 2008, meeting... protecting persons who work on, under, or between rolling equipment and persons applying, removing or.... 63] Railroad Safety Advisory Committee (RSAC); Working Group Activity Update AGENCY: Federal Railroad...

Updating a Strategic Highway Safety Plan : Learning from the Idaho Transportation Department (ITD) - Proceedings from the Federal Highway Administration's (FHWA) Highway Safety Peer-to-Peer Exchange Program

Science.gov (United States)

2009-10-01

On November 4, 2009, ITDs Office of Highway Operations and Safety partnered with the FHWA Office of Safety to host a one-day peer exchange. This event focused on the update of Idahos Strategic Highway Safety Plan (SHSP), entitled Toward Zero...

LANMAS core: Update and current directions

International Nuclear Information System (INIS)

Claborn, J.

1995-01-01

Local Area Network Material Accountability system (LANMAS) core software provides the framework of a material accountability system. It tracks the movement of material throughout a site and generates the required material accountability reports. LANMAS is a net-work- based nuclear material accountability system that runs in a client/server mode. The database of material type and location resides on the server, while the user interface runs on the client. The user interface accesses the data stored on the server via a network. The LANMAS core can be used as the foundation for building required materials control and accountability (MCA) functionality at any site requiring a new MCA system. An individual site will build on the LANMAS core by supplying site-specific software. This paper will provide an update on the current LANMAS development activities and discuss the current direction of the LANMAS project

Safety analysis - current and future regulatory challenges

Energy Technology Data Exchange (ETDEWEB)

Jamieson, T., E-mail: Terry.Jamieson@cnsc-ccsn.gc.ca [Canadian Nuclear Safety Commission, Ottawa, ON (Canada)

2015-07-01

'Full text:' The current and future regulatory challenges associated with deterministic safety analysis are reviewed, including: 1. The CNSC's and safety control areas. 2. Traditional safety analysis approach. 3. Experience gained and impact. 4. Current analysis and regulatory approaches. 5. Current status. 6. Complexity and challenges In particular, the technical, regulatory and strategic aspects of these challenges are discussed. (author)

Safety analysis - current and future regulatory challenges

International Nuclear Information System (INIS)

Jamieson, T.

2015-01-01

'Full text:' The current and future regulatory challenges associated with deterministic safety analysis are reviewed, including: 1. The CNSC's and safety control areas. 2. Traditional safety analysis approach. 3. Experience gained and impact. 4. Current analysis and regulatory approaches. 5. Current status. 6. Complexity and challenges In particular, the technical, regulatory and strategic aspects of these challenges are discussed. (author)

LANMAS core: Update and current directions

International Nuclear Information System (INIS)

Claborn, J.

1994-01-01

Local Area Network Material Accountability System (LANMAS) core software will provide the framework of a material accountability system. LANMAS is a network-based nuclear material accountability system. It tracks the movement of material throughout a site and generates the required reports on material accountability. LANMAS will run in a client/server mode. The database of material type and location will reside on the server, while the user interface runs on the client. The user interface accesses the server via a network. The LANMAS core can be used as the foundation for building required Materials Control and Accountability (MC ampersand A) functionality at any site requiring a new MC ampersand A system. An individual site will build on the LANMAS core by supplying site-specific software. This paper will provide an update on the current LANMAS development activities and discuss the current direction of the LANMAS project

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.

NS [Nuclear Safety] update. Current safety and security activities and developments taking place in the Department of Nuclear Safety and Security. Issue no. 4, June 2007

International Nuclear Information System (INIS)

2007-04-01

allow a broad discussion and to form a consolidated opinion. This should apply to requests for assistance from recipient states as well from donor states/organizations. Participation in the RSTCG is based on competencies and responsibilities. Currently the following divisions/sections within the IAEA's Department of Nuclear Safety and Security with responsibilities related to the control and management of radioactive sources are represented: Division of Radiation, Transport and Waste Safety with responsibilities in radiation safety related to sealed radioactive sources, Division of Nuclear Fuel Cycle and Waste Technology, with responsibilities in recovery, conditioning, storage and/or repatriation and Office of Nuclear Security with responsibilities in the protection against malicious acts (through the whole life cycle of sources)

Current regulatory developments concerning the implementation of probabilistic safety analyses for external hazards in Germany

International Nuclear Information System (INIS)

Krauss, Matias; Berg, Heinz-Peter

2014-01-01

The Federal Ministry for the Environment, Nature Conservation and Nuclear Safety (BMU) initiated in September 2003 a comprehensive program for the revision of the national nuclear safety regulations which has been successfully completed in November 2012. These nuclear regulations take into account the current recommendations of the International Atomic Energy Agency (IAEA) and Western European Nuclear Regulators Association (WENRA). In this context, the recommendations and guidelines of the Nuclear Safety Standards Commission (KTA) and the technical documents elaborated by the respective expert group on Probabilistic Safety Analysis for Nuclear Power Plants (FAK PSA) are being updated or in the final process of completion. A main topic of the revision was the issue external hazards. As part of this process and in the light of the accident at Fukushima and the findings of the related actions resulting in safety reviews of nuclear power plants at national level in Germany and on European level, a revision of all relevant standards and documents has been made, especially the recommendations of KTA and FAK PSA. In that context, not only design issues with respect to events such as earthquakes and floods have been discussed, but also methodological issues regarding the implementation of improved probabilistic safety analyses on this topic. As a result of the revision of the KTA 2201 series 'Design of Nuclear Power Plants against Seismic Events' with their parts 1 to 6, part 1 'Principles' was published as the first standard in November 2011, followed by the revised versions of KTA 2201.2 (soil) and 2201.4 (systems and components) in 2012. The modified the standard KTA 2201.3 (structures) is expected to be issued before the end of 2013. In case of part 5 (seismic instrumentation) and part 6 (post>seismic actions) draft amendments are expected in 2013. The expert group 'Probabilistic Safety Assessments for Nuclear Power Plants' (FAK PSA) is an advisory body of the Federal

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.

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.

An updated status of Department of Energy safety reviews of packages for transporting radioactive material

International Nuclear Information System (INIS)

Kapoor, A.

1995-01-01

The Department of Energy conducts conformance reviews and issues Certificates of Compliance for Type B packaging for radioactive materials. Several offices within DOE perform these reviews which are required by the Department of Transportation to be to the regulations promulgated by the Nuclear Regulatory Commission or their safety equivalent. This paper focuses on one of these offices, the Office of Facility Safety Analysis, EH-32, which is responsible for reviewing and certifying packages other than those used for weapons and weapons component, for Naval Reactors, and for Civilian Radioactive Waste Management. This paper gives the background and organizational history of EH-32, discusses the version of regulations to which the packaging is reviewed, updates the status of these reviews, describes the effectiveness of the reviews, updates the training courses sponsored by EH-32, and mentions the new Quality Assurance Evaluations being started by EH-32

Updated procedure for the safety evaluation of natural flavor complexes used as ingredients in food

NARCIS (Netherlands)

Cohen, Samuel M.; Eisenbrand, Gerhard; Fukushima, Shoji; Gooderham, Nigel J.; Guengerich, F.P.; Hecht, Stephen S.; Rietjens, Ivonne M.C.M.; Davidsen, Jeanne M.; Harman, Christie L.; Taylor, Sean V.

2018-01-01

An effective and thorough approach for the safety evaluation of natural flavor complexes (NFCs) was published in 2005 by the Expert Panel of the Flavor and Extract Manufacturers Association (FEMA). An updated procedure is provided here, which maintains the essential concepts of the use of the

76 FR 10246 - Updating Fire Safety Standards

Science.gov (United States)

2011-02-24

... public noted the importance of requiring facilities to meet up-to-date safety standards. The third... Affairs (VA) regulations concerning community residential care facilities, contract facilities for certain outpatient and residential services, and State home facilities. The final rule will clarify current...

77 FR 41258 - FOIA Fee Schedule Update

Science.gov (United States)

2012-07-13

... DEFENSE NUCLEAR FACILITIES SAFETY BOARD 10 CFR Part 1703 FOIA Fee Schedule Update AGENCY: Defense Nuclear Facilities Safety Board. ACTION: Establishment of FOIA Fee Schedule. SUMMARY: The Defense Nuclear Facilities Safety Board is publishing its Freedom of Information Act (FOIA) Fee Schedule Update pursuant to...

76 FR 43819 - FOIA Fee Schedule Update

Science.gov (United States)

2011-07-22

... DEFENSE NUCLEAR FACILITIES SAFETY BOARD 10 CFR Part 1703 FOIA Fee Schedule Update AGENCY: Defense Nuclear Facilities Safety Board. ACTION: Establishment of FOIA Fee Schedule. SUMMARY: The Defense Nuclear Facilities Safety Board is publishing its Freedom of Information Act (FOIA) Fee Schedule Update pursuant to...

Update on radiation safety and dose reduction in pediatric neuroradiology

International Nuclear Information System (INIS)

Mahesh, Mahadevappa

2015-01-01

The number of medical X-ray imaging procedures is growing exponentially across the globe. Even though the overall benefit from medical X-ray imaging procedures far outweighs any associated risks, it is crucial to take all necessary steps to minimize radiation risks to children without jeopardizing image quality. Among the X-ray imaging studies, except for interventional fluoroscopy procedures, CT studies constitute higher dose and therefore draw considerable scrutiny. A number of technological advances have provided ways for better and safer CT imaging. This article provides an update on the radiation safety of patients and staff and discusses dose optimization in medical X-ray imaging within pediatric neuroradiology. (orig.)

Update on radiation safety and dose reduction in pediatric neuroradiology

Energy Technology Data Exchange (ETDEWEB)

Mahesh, Mahadevappa [Johns Hopkins University School of Medicine, The Russell H. Morgan Department of Radiology and Radiological Science, Baltimore, MD (United States)

2015-09-15

The number of medical X-ray imaging procedures is growing exponentially across the globe. Even though the overall benefit from medical X-ray imaging procedures far outweighs any associated risks, it is crucial to take all necessary steps to minimize radiation risks to children without jeopardizing image quality. Among the X-ray imaging studies, except for interventional fluoroscopy procedures, CT studies constitute higher dose and therefore draw considerable scrutiny. A number of technological advances have provided ways for better and safer CT imaging. This article provides an update on the radiation safety of patients and staff and discusses dose optimization in medical X-ray imaging within pediatric neuroradiology. (orig.)

Safety and efficacy of vernakalant for acute cardioversion of atrial fibrillation: an update

Science.gov (United States)

Tsuji, Yukiomi; Dobrev, Dobromir

2013-01-01

Intravenous vernakalant has recently been approved in Europe as an atrial-selective antiarrhythmic drug for the conversion of recent-onset atrial fibrillation (AF). It inhibits atrial-selective K+ currents (IK,ACh and IKur) and causes rate-dependent atrial-predominant Na+ channel block, with only a small inhibitory effect on the rapid delayed rectifier K+ current (IKr) in the ventricle. Due to its atrial-selective properties, vernakalant prolongs the effective refractory period of the atria with minimal effects on the ventricles, being associated with a low proarrhythmic risk for torsades de pointes arrhythmias. Five pivotal clinical trials consistently demonstrated that vernakalant rapidly terminates AF with stable maintenance of sinus rhythm for up to 24 hours. A head-to-head comparative trial showed that the 90-minute conversion rate of vernakalant was substantially higher than that of amiodarone. Initially, a longer-acting oral formulation of vernakalant was shown to be effective and safe in preventing AF recurrence after cardioversion in a Phase IIb study. However, the clinical studies testing oral vernakalant for maintenance of sinus rhythm after AF cardioversion were prematurely halted for undisclosed reasons. This review article provides an update on the safety and efficacy of intravenous vernakalant for the rapid cardioversion of AF. PMID:23637539

NS [Nuclear Safety] update. Current safety and security activities and developments taking place in the Department of Nuclear Safety and Security, Issue no. 15, February 2011

International Nuclear Information System (INIS)

2011-02-01

The current issue presents information about the following topics: Supporting radiation protection in medicine. Wano's pre-startup support. One stop for incident and emergency communications. Emergency preparedness in IAEA Member States. Sophisticated On-Site Nuclide Identification (RanidSONNI). Over land, sea and air: safe and secure transport of radioactive material. INES at 20: Success from simplicity. IAEA and Ibero-American Forum - strengthening ties. Highlights of the 54th IAEA General Conference, 20-24 September 2010. Highlights of the International conference on Challenges faced by TSOs. Department of Nuclear Safety programme highlights

Tidal current energy resource assessment in Ireland: Current status and future update

International Nuclear Information System (INIS)

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

2010-01-01

Interest in renewable energy in Ireland has increased continually over the past decade. This interest is due primarily to security of supply issues and the effects of climate change. Ireland imports over 90% of its primary energy consumption, mostly in the form of fossil fuels. The exploitation of Ireland's vast indigenous renewable energy resources is required in order to reduce this over-dependence on fossil fuel imports to meet energy demand. Various targets have been set by the Irish government to incorporate renewable energy technologies into Ireland's energy market. As a result of these targets, the development in wind energy has increased substantially over the past decade; however this method of energy extraction is intermittent and unpredictable. Ireland has an excellent tidal current energy resource and the use of this resource will assist in the development of a sustainable energy future. Energy extraction using tidal current energy technologies offers a vast and predictable energy resource. This paper reviews the currently accepted tidal current energy resource assessment for Ireland. This assessment was compiled by Sustainable Energy Ireland in a report in 2004. The assessment employed a 2-dimensional numerical model of the tidal current velocities around Ireland, and from this numerical model the theoretical tidal current energy resource was identified. With the introduction of constraints and limitations, the technical, practical, accessible and viable tidal current energy resources were obtained. The paper discusses why the assessment needs updating including the effect on the assessment of the current stage of development of tidal current turbines and their deployment technology. (author)

2011 NASA Range Safety Annual Report

Science.gov (United States)

Dumont, Alan G.

2012-01-01

Welcome to the 2011 edition of the NASA Range Safety Annual Report. Funded by NASA Headquarters, this report provides a NASA Range Safety overview for current and potential range users. As is typical with odd year editions, this is an abbreviated Range Safety Annual Report providing updates and links to full articles from the previous year's report. It also provides more complete articles covering new subject areas, summaries of various NASA Range Safety Program activities conducted during the past year, and information on several projects that may have a profound impact on the way business will be done in the future. Specific topics discussed and updated in the 2011 NASA Range Safety Annual Report include a program overview and 2011 highlights; Range Safety Training; Range Safety Policy revision; Independent Assessments; Support to Program Operations at all ranges conducting NASA launch/flight operations; a continuing overview of emerging range safety-related technologies; and status reports from all of the NASA Centers that have Range Safety responsibilities. Every effort has been made to include the most current information available. We recommend this report be used only for guidance and that the validity and accuracy of all articles be verified for updates. Once again the web-based format was used to present the annual report. We continually receive positive feedback on the web-based edition and hope you enjoy this year's product as well. As is the case each year, contributors to this report are too numerous to mention, but we thank individuals from the NASA Centers, the Department of Defense, and civilian organizations for their contributions. In conclusion, it has been a busy and productive year. I'd like to extend a personal Thank You to everyone who contributed to make this year a successful one, and I look forward to working with all of you in the upcoming year.

Hepatitis C in Pregnancy: Review of Current Knowledge and Updated Recommendations for Management.

Science.gov (United States)

Page, Charlotte M; Hughes, Brenna L; Rhee, Eleanor H J; Kuller, Jeffrey A

2017-06-01

An estimated 1% to 2.5% of pregnant women in the United States are infected with hepatitis C virus (HCV), which carries approximately a 6% risk of mother-to-infant transmission. The aims of this article are to review the current evidence on HCV in pregnancy and to provide updated recommendations for management. Original research articles, review articles, and guidelines on HCV in general and specifically in pregnancy were reviewed, as were drug safety profiles from the Food and Drug Administration. Pregnancy appears to have a beneficial effect on the course of maternal chronic HCV infection. However, it is associated with an increased risk of adverse fetal outcomes, including fetal growth restriction and low birth weight, and can be transmitted to the infant in utero or during the peripartum period. No perinatal intervention has been shown to reduce the risk of vertical transmission, but some may increase this risk. To date, no treatment regimens for HCV have been approved for use in pregnancy, but the new ribavirin-free, direct-acting antiviral regimens are being used with high efficacy outside pregnancy. Hepatitis C virus infection in pregnancy generally does not adversely affect maternal well-being but is associated with adverse effects on the fetus because of pregnancy complications and vertical transmission. There are currently no approved treatment regimens for HCV in pregnancy; this should be an active area of research in obstetrics.

NS [Nuclear Safety] update. Current safety and security activities and developments taking place in the Department of Nuclear Safety and Security, Issue no. 7, July 2008

International Nuclear Information System (INIS)

2008-09-01

The current issue presents information about the following activities: 1) International Conference on Radioecology and Environmental Radioactivity 15-20 June 2008, Bergen organized by the Norwegian Radiation Protection Authority (NRPA) and the French Institute for Radiation Protection and Nuclear Safety (IRSN) in cooperation with IAEA, WHO, OECD/NEA, the International Union of Radioecology (IUR), the International Commission on Radiological Protection (ICRP) and the Journal of environmental Radioactivity (JER). This conference has evolved from the merging of the series of conferences by ECORAD and of the International Conferences on Radioactivity in the Environment. The primary objective of the conference was to review all scientific themes related to the study of environmental radioactivity and to identify new societal needs and requirements for regulatory bodies and industry. All sources of radiation, from industrial discharges in planned exposure situations through to sources in existing and emergency exposure situations, were included in the scope of the conference. 2) The Ibero American Forum of Nuclear and Radiation Safety and Security Regulatory Agencies (the FORO); 3) Kashiwazaki-Kariwa Nuclear Power Plant in the earthquake on 16 July 2007 - plant's response and effects and lessons learned

Current status of nuclear safety research

International Nuclear Information System (INIS)

Anon.

1977-01-01

Efforts at nuclear safety research have expanded year by year in Japan, in term of money and technical achievement. The Atomic Energy Commission set last year the five year nuclear safety research program, a guideline by which various research institutes will be able to develop their own efforts in a concerted manner. From the results of the nuclear safety research which cover very wide areas ranging from reactor engineering safety, safety of nuclear fuel cycle facilities, prevention of radiation hazards to the adequate treatment and disposal of radioactive wastes, AIJ hereafter focuses of LWR engineering safety and prevents two articles, one introducing the current results of the NSSR program developed by JAERI and the other reporting the LWR reliability demonstration testing projects being promoted by MITI. The outline of these demonstration tests was reported in this report. The tests consist of earthquake resistance reliability test of nuclear power plants, steam generator reliability tests, valve integrity tests, fuel assembly reliability tests, reliability tests of heat affected zones and reliability tests of pumps. (Kobatake, H.)

Current status of safety analysis report for ANPP

International Nuclear Information System (INIS)

Amirjanyan, A.

1999-01-01

Current situation concerning Armenian NPP safety analysis report is considered within the frame of accepted safety practice. Licensing procedure is being developed. Technical support group was established in the Armenian Nuclear Regulatory Authority (ANRA). The task of the group is to study modern methods of NPP in depth safety analysis for technical assistance for the ANRA, and perform independent safety assessments. ANRA will be obliged to demand assistance from various foreign organisations for preparation of different parts of the Safety Analysis Report like determination though certain parts can be prepared in Armenia

NS [Nuclear Safety] update. Current safety and security activities and developments taking place in the Department of Nuclear Safety and Security, Issue no. 9, December 2008

International Nuclear Information System (INIS)

2008-12-01

The current issue presents information about the following activities: 1) IRRS Lessons Learned Workshop held on 3-5 November 2008, Seville. The main purpose of the workshop was to provide information to interested Member States regarding the IRRS, to discuss their experiences and lessons learned from the regulatory review conducted at the CSN and to explore further improvements in the planning and implementation of the IRRS, including the establishment of a network of experts from regulatory authorities. 2) Highlights of the 52 General Conference. 3) The 2008 IAEA General Conference welcomed the endorsement of the new International Nuclear and Radiological Event Scale (INES) User's Manual. 4) Safety and Security Infrastructure for Countries Embarking on Nuclear Power Programmes

Dam safety at Seven Sisters Generating Station

International Nuclear Information System (INIS)

Carson, R. W.; Gupta, R. C.

1996-01-01

A safety surveillance program for all hydraulic structures in Manitoba was first implemented in 1979, and updated in 1988. This contribution describes the current status of the program, and the nature of the issues that the program was designed to address. The Seven Sisters Station's dam on the Winnipeg River, about 90 km northeast of the City of Winnipeg, was used as an example. Extensive reviews of flood risks and downstream inundation potential at Seven Sisters' revealed a number of deficiencies; these findings will be incorporated into a corporate plan of overall remediation. Updating the program will also include efforts to ensure adherence to national dam safety guidelines. 5 figs

Using resources for scientific-driven pharmacovigilance: from many product safety documents to one product safety master file.

Science.gov (United States)

Furlan, Giovanni

2012-08-01

Current regulations require a description of the overall safety profile or the specific risks of a drug in multiple documents such as the Periodic and Development Safety Update Reports, Risk Management Plans (RMPs) and Signal Detection Reports. In a resource-constrained world, the need for preparing multiple documents reporting the same information results in shifting the focus from a thorough scientific and medical evaluation of the available data to maintaining compliance with regulatory timelines. Since the aim of drug safety is to understand and characterize product issues to take adequate risk minimization measures rather than to comply with bureaucratic requirements, there is the need to avoid redundancy. In order to identify core drug safety activities that need to be undertaken to protect patient safety and reduce the number of documents reporting the results of these activities, the author has reviewed the main topics included in the drug safety guidelines and templates. The topics and sources that need to be taken into account in the main regulatory documents have been found to greatly overlap and, in the future, as a result of the new Periodic Safety Update Report structure and requirements, in the author's opinion this overlap is likely to further increase. Many of the identified inter-document differences seemed to be substantially formal. The Development Safety Update Report, for example, requires separate presentation of the safety issues emerging from different sources followed by an overall evaluation of each safety issue. The RMP, instead, requires a detailed description of the safety issues without separate presentation of the evidence derived from each source. To some extent, however, the individual documents require an in-depth analysis of different aspects; the RMP, for example, requires an epidemiological description of the indication for which the drug is used and its risks. At the time of writing this article, this is not specifically

Safety update on the use of recombinant activated factor VII in approved indications.

Science.gov (United States)

Neufeld, Ellis J; Négrier, Claude; Arkhammar, Per; Benchikh el Fegoun, Soraya; Simonsen, Mette Duelund; Rosholm, Anders; Seremetis, Stephanie

2015-06-01

This updated safety review summarises the large body of safety data available on the use of recombinant activated factor VII (rFVIIa) in approved indications: haemophilia with inhibitors, congenital factor VII (FVII) deficiency, acquired haemophilia and Glanzmann's thrombasthenia. Accumulated data up to 31 December 2013 from clinical trials as well as post-marketing data (registries, literature reports and spontaneous reports) were included. Overall, rFVIIa has shown a consistently favourable safety profile, with no unexpected safety concerns, in all approved indications. No confirmed cases of neutralising antibodies against rFVIIa have been reported in patients with congenital haemophilia, acquired haemophilia or Glanzmann's thrombasthenia. The favourable safety profile of rFVIIa can be attributed to the recombinant nature of rFVIIa and its localised mechanism of action at the site of vascular injury. Recombinant FVIIa activates factor X directly on the surface of activated platelets, which are present only at the site of injury, meaning that systemic activation of coagulation is avoided and the risk of thrombotic events (TEs) thus reduced. Nonetheless, close monitoring for signs and symptoms of TE is warranted in all patients treated with any pro-haemostatic agent, including rFVIIa, especially the elderly and any other patients with concomitant conditions and/or predisposing risk factors to thrombosis. Copyright © 2015 Elsevier Ltd. All rights reserved.

75 FR 36773 - Pipeline Safety: Updating Facility Response Plans in Light of the Deepwater Horizon Oil Spill

Science.gov (United States)

2010-06-28

... have been, or are subsequently relocated to the Gulf to respond to the Deepwater Horizon event should.... PHMSA-2010-0175] Pipeline Safety: Updating Facility Response Plans in Light of the Deepwater Horizon Oil... 194. In light of the Deepwater Horizon oil spill in the Gulf of Mexico, which has resulted in the...

Safety during MARS exercise

CERN Multimedia

2015-01-01

It is MARS(1) time again! All employed members of the CERN personnel are currently undergoing the annual MARS evaluations.   This is also a good occasion for supervisors and their supervisees to fill in or update the OHS-0-0-3 form(2) “Identification of occupational hazards”. Filling in the OHS-0-0-3 form is an opportunity to assess any safety issues related to the supervisee's activities.  Each of us should, together with our supervisor, regularly identify and assess the hazards we may be exposed to in the course of our professional activities and reflect on how to control and mitigate them. When filling in the OHS form for the first time, it is important to determine any potential hazards as well as the corresponding preventive measures, in particular training and protective equipment. When updating the form, please review the available information to ensure that it still corresponds to the current activities. The form should be updated w...

Assessment and Management of Ageing of Major Nuclear Power Plant Components Important to Safety: Steam Generators. 2011 Update

International Nuclear Information System (INIS)

2011-11-01

At present there are over four hundred forty operational nuclear power plants (NPPs) in IAEA Member States. Ageing degradation of the systems, structures of components during their operational life must be effectively managed to ensure the availability of design functions throughout the plant service life. From the safety perspective, this means controlling, within acceptable limits, the ageing degradation and wear-out of plant components important to safety so that adequate safety margins remain, i.e. integrity and functional capability in excess of normal operating requirements. This IAEA-TECDOC is one in a series of reports on the assessment and management of ageing of the major NPP components important to safety. The reports are based on experience and practices of NPP operators, regulators, designers, manufacturers, and technical support organizations. The current practices for the assessment of safety margins (fitness for service) and the inspection, monitoring and mitigation of ageing degradation of selected components of Canada deuteriumuranium (CANDU) reactor, boiling water reactor (BWR), pressurized water reactor (PWR), and water moderated, water cooled energy reactor (WWER) plants are documented in the reports. These practices are intended to help all involved directly and indirectly in ensuring the safe operation of NPPs, and also to provide a common technical basis for dialogue between plant operators and regulators when dealing with age related licensing issues. Since the reports are written from a safety perspective, they do not address life or life cycle management of the plant components, which involves the integration of ageing management and economic planning. The target audience of the reports consists of technical experts from NPPs and from regulatory, plant design, manufacturing and technical support organizations dealing with specific plant components addressed in the reports. The component addressed in the present publication is the steam

Safety and efficacy of vernakalant for acute cardioversion of atrial fibrillation: an update

Directory of Open Access Journals (Sweden)

Dobrev D

2013-04-01

Full Text Available Yukiomi Tsuji,1 Dobromir Dobrev1–3 1Institute of Pharmacology, Faculty of Medicine, University Duisburg-Essen, Essen, 2Division of Experimental Cardiology, Medical Faculty Mannheim, Heidelberg University, Mannheim, 3Deutsches Zentrum für Herz-Kreislauf-Forshcung [German Center for Cardiovascular Research], partner site Heidelberg/Mannheim, Mannheim, Germany Abstract: Intravenous vernakalant has recently been approved in Europe as an atrial-selective antiarrhythmic drug for the conversion of recent-onset atrial fibrillation (AF. It inhibits atrial-selective K+ currents (IK,ACh and IKur and causes rate-dependent atrial-predominant Na+ channel block, with only a small inhibitory effect on the rapid delayed rectifier K+ current (IKr in the ventricle. Due to its atrial-selective properties, vernakalant prolongs the effective refractory period of the atria with minimal effects on the ventricles, being associated with a low proarrhythmic risk for torsades de pointes arrhythmias. Five pivotal clinical trials consistently demonstrated that vernakalant rapidly terminates AF with stable maintenance of sinus rhythm for up to 24 hours. A head-to-head comparative trial showed that the 90-minute conversion rate of vernakalant was substantially higher than that of amiodarone. Initially, a longer-acting oral formulation of vernakalant was shown to be effective and safe in preventing AF recurrence after cardioversion in a Phase IIb study. However, the clinical studies testing oral vernakalant for maintenance of sinus rhythm after AF cardioversion were prematurely halted for undisclosed reasons. This review article provides an update on the safety and efficacy of intravenous vernakalant for the rapid cardioversion of AF. Keywords: atrial fibrillation, antiarrhythmic drug, atrial-selective K+ currents, Na+ channel block, ventricles

Playground Safety

Science.gov (United States)

... Prevention Fall Prevention Playground Safety Poisoning Prevention Road Traffic Safety Sports Safety Get Email Updates To receive ... at the Consumer Product Safety Commission’s Playground Safety website . References U.S. Consumer Product Safety Commission. Injuries and ...

2016 Updated American Society of Clinical Oncology/Oncology Nursing Society Chemotherapy Administration Safety Standards, Including Standards for Pediatric Oncology.

Science.gov (United States)

Neuss, Michael N; Gilmore, Terry R; Belderson, Kristin M; Billett, Amy L; Conti-Kalchik, Tara; Harvey, Brittany E; Hendricks, Carolyn; LeFebvre, Kristine B; Mangu, Pamela B; McNiff, Kristen; Olsen, MiKaela; Schulmeister, Lisa; Von Gehr, Ann; Polovich, Martha

2016-12-01

Purpose To update the ASCO/Oncology Nursing Society (ONS) Chemotherapy Administration Safety Standards and to highlight standards for pediatric oncology. Methods The ASCO/ONS Chemotherapy Administration Safety Standards were first published in 2009 and updated in 2011 to include inpatient settings. A subsequent 2013 revision expanded the standards to include the safe administration and management of oral chemotherapy. A joint ASCO/ONS workshop with stakeholder participation, including that of the Association of Pediatric Hematology Oncology Nurses and American Society of Pediatric Hematology/Oncology, was held on May 12, 2015, to review the 2013 standards. An extensive literature search was subsequently conducted, and public comments on the revised draft standards were solicited. Results The updated 2016 standards presented here include clarification and expansion of existing standards to include pediatric oncology and to introduce new standards: most notably, two-person verification of chemotherapy preparation processes, administration of vinca alkaloids via minibags in facilities in which intrathecal medications are administered, and labeling of medications dispensed from the health care setting to be taken by the patient at home. The standards were reordered and renumbered to align with the sequential processes of chemotherapy prescription, preparation, and administration. Several standards were separated into their respective components for clarity and to facilitate measurement of adherence to a standard. Conclusion As oncology practice has changed, so have chemotherapy administration safety standards. Advances in technology, cancer treatment, and education and training have prompted the need for periodic review and revision of the standards. Additional information is available at http://www.asco.org/chemo-standards .

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 impact of safety standards updating for design purposes in nuclear power plants licensing

International Nuclear Information System (INIS)

Alvarenga, Marco Antonio Bayout; Rabello, Sidney Luiz

2009-01-01

The Brazilian experience of nuclear power plants licensing was consolidated by the use of the Brazilian, American, German and IAEA standards. Independently of the set of norms, standards or guides to be used, this set should be in consonance with the state-of-art or the current state of knowledge in science and technology. In the general design criteria of US NRC or German BMI, or in the Brazilian norms (CNEN) or even, in the IAEA standards, this aspect is always emphasized. On the other hand, the international operational experience of nuclear reactors (for example, TMI accident) also contributes to the updating of norms and standards. The use of new technologies (for example, digital technology) impels the norms and standards to adopt new design criteria related to the new technological context. Moreover, we must add the particular vision that each country can have concerning to specific topics in nuclear safety. This work discusses how the norms, standards and guides used in the nuclear licensing are being reviewed to cope with the requirement of the state-of-art. In order to accomplish this aim we took some general design criteria to exemplify how they are fulfilled, mainly those related directly with the protection of the defense-in-depth barriers: primary coolant system, containment vessel and containment systems, including external events and severe accidents. In complement to the deterministic analysis, it is also discussed the design criteria related to the human factors engineering and probabilistic safety analysis, including severe accidents aspects. (author)

Guidance on health effects of toxic chemicals. Safety Analysis Report Update Program

Energy Technology Data Exchange (ETDEWEB)

Foust, C.B.; Griffin, G.D.; Munro, N.B.; Socolof, M.L.

1994-02-01

Martin Marietta Energy Systems, Inc. (MMES), and Martin Marietta Utility Services, Inc. (MMUS), are engaged in phased programs to update the safety documentation for the existing US Department of Energy (DOE)-owned facilities. The safety analysis of potential toxic hazards requires a methodology for evaluating human health effects of predicted toxic exposures. This report provides a consistent set of health effects and documents toxicity estimates corresponding to these health effects for some of the more important chemicals found within MMES and MMUS. The estimates are based on published toxicity information and apply to acute exposures for an ``average`` individual. The health effects (toxicological endpoints) used in this report are (1) the detection threshold; (2) the no-observed adverse effect level; (3) the onset of irritation/reversible effects; (4) the onset of irreversible effects; and (5) a lethal exposure, defined to be the 50% lethal level. An irreversible effect is defined as a significant effect on a person`s quality of life, e.g., serious injury. Predicted consequences are evaluated on the basis of concentration and exposure time.

Safety evaluation in the development of medical devices and combination products

CERN Document Server

Gad, Shayne C

2008-01-01

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

Child Safety: MedlinePlus Health Topic

Science.gov (United States)

... injuries in children (Medical Encyclopedia) Also in Spanish Topic Image MedlinePlus Email Updates Get Child Safety updates ... safety Preventing head injuries in children Related Health Topics Infant and Newborn Care Internet Safety Motor Vehicle ...

Development of safety principles for the design of future nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-06-01

The main purpose of this TECDOC is to propose updates to existing safety principles which could be used as a basis for developing safety principles for the design of future NPPs. Accordingly, this document is intended to be useful to reactor designers, owners, operators, researchers and regulators. It is also expected that this document can contribute to international harmonization of safety approaches, and that it will help ensure that future reactors will be designed worldwide to a high standard of safety. As such, these proposed updates are intended to provide general guidance which, if carefully and properly implemented, will result in reactor designs with enhanced safety characteristics beyond those currently in operation. This enhancement results from the fact that the proposals are derived from the lessons learned from more recent operational experience, R and D, design, testing, and analysis developed over the past decade or so, as well as from attempts to reflect the current trends in reactor design, such as the introduction of new technologies. 8 refs, 3 figs.

Development of safety principles for the design of future nuclear power plants

International Nuclear Information System (INIS)

1995-06-01

The main purpose of this TECDOC is to propose updates to existing safety principles which could be used as a basis for developing safety principles for the design of future NPPs. Accordingly, this document is intended to be useful to reactor designers, owners, operators, researchers and regulators. It is also expected that this document can contribute to international harmonization of safety approaches, and that it will help ensure that future reactors will be designed worldwide to a high standard of safety. As such, these proposed updates are intended to provide general guidance which, if carefully and properly implemented, will result in reactor designs with enhanced safety characteristics beyond those currently in operation. This enhancement results from the fact that the proposals are derived from the lessons learned from more recent operational experience, R and D, design, testing, and analysis developed over the past decade or so, as well as from attempts to reflect the current trends in reactor design, such as the introduction of new technologies. 8 refs, 3 figs

DRY TRANSFER FACILITY CRITICALITY SAFETY CALCULATIONS

International Nuclear Information System (INIS)

C.E. Sanders

2005-01-01

This design calculation updates the previous criticality evaluation for the fuel handling, transfer, and staging operations to be performed in the Dry Transfer Facility (DTF) including the remediation area. The purpose of the calculation is to demonstrate that operations performed in the DTF and RF meet the nuclear criticality safety design criteria specified in the ''Project Design Criteria (PDC) Document'' (BSC 2004 [DIRS 171599], Section 4.9.2.2), the nuclear facility safety requirement in ''Project Requirements Document'' (Canori and Leitner 2003 [DIRS 166275], p. 4-206), the functional/operational nuclear safety requirement in the ''Project Functional and Operational Requirements'' document (Curry 2004 [DIRS 170557], p. 75), and the functional nuclear criticality safety requirements described in the ''Dry Transfer Facility Description Document'' (BSC 2005 [DIRS 173737], p. 3-8). A description of the changes is as follows: (1) Update the supporting calculations for the various Category 1 and 2 event sequences as identified in the ''Categorization of Event Sequences for License Application'' (BSC 2005 [DIRS 171429], Section 7). (2) Update the criticality safety calculations for the DTF staging racks and the remediation pool to reflect the current design. This design calculation focuses on commercial spent nuclear fuel (SNF) assemblies, i.e., pressurized water reactor (PWR) and boiling water reactor (BWR) SNF. U.S. Department of Energy (DOE) Environmental Management (EM) owned SNF is evaluated in depth in the ''Canister Handling Facility Criticality Safety Calculations'' (BSC 2005 [DIRS 173284]) and is also applicable to DTF operations. Further, the design and safety analyses of the naval SNF canisters are the responsibility of the U.S. Department of the Navy (Naval Nuclear Propulsion Program) and will not be included in this document. Also, note that the results for the Monitored Geologic Repository (MGR) Site specific Cask (MSC) calculations are limited to the

USAR managing and updating process

International Nuclear Information System (INIS)

Prah, M.; Spiler, J.

1996-01-01

In this paper basis and background of the FSAR (Final Safety Analysis Report) document and its conversion process to the USAR (Updated Safety Analysis Report) document are described. In addition, there are internal and external reviews as approval process presented. The following is included in our new approach to manage USAR changes: initiating the USAR change, technical reviewing, preparing a safety evaluation, KSC (Krsko Safety Committee) and KOC (Krsko Operating Committee) review, ESD Director approval, and the Regulatory Body review or approval. The intensive technological modification activities started in the year 1992 when the NEK Engineering Services Division was established. These activities are one of the most important reason for a very intensive USAR items change. The other reason for its conversation to an electronic format is a possibility for easier and faster searching, updating and changing process and introducing a new systematic USAR managing approach as mentioned above. (author)

AAP Updates Recommendations on Car Seats

Science.gov (United States)

... Size Email Print Share AAP Updates Recommendations on Car Seats Page Content Article Body Children should ride ... of approved car safety seats. Healthy Children Radio: Car Seat Safety Dennis Durbin, MD, FAAP, lead author ...

Dynamic Software Updating with Gosh! Current Status and the Road Ahead

DEFF Research Database (Denmark)

Gregersen, Allan Raundahl; Rasmussen, Michael; Jørgensen, Bo Nørregaard

2013-01-01

Any non-trivial software system has to be upgraded regularly to incorporate bug fixes and security patches or simply to keep up with the inevitable evolution in end-user requirements. Software upgrading is challenging, especially when it comes to online upgrading of running systems. In this paper......, we present the current status of Gosh!, a dynamic-software-updating system for Java, which provides comprehensive support for changing class definitions of live objects, including adding, removing and moving fields, methods, classes and interfaces anywhere in the inheritance hierarchy. Prior...

Reactor safety research program. A description of current and planned reactor safety research sponsored by the Nuclear Regulatory Commission's Division of Reactor Safety Research

International Nuclear Information System (INIS)

1975-06-01

The reactor safety research program, sponsored by the Nuclear Regulatory Commission's Division of Reactor Safety Research, is described in terms of its program objectives, current status, and future plans. Elements of safety research work applicable to water reactors, fast reactors, and gas cooled reactors are presented together with brief descriptions of current and planned test facilities. (U.S.)

Nurses' Perceived Skills and Attitudes About Updated Safety Concepts: Impact on Medication Administration Errors and Practices.

Science.gov (United States)

Armstrong, Gail E; Dietrich, Mary; Norman, Linda; Barnsteiner, Jane; Mion, Lorraine

Approximately a quarter of medication errors in the hospital occur at the administration phase, which is solely under the purview of the bedside nurse. The purpose of this study was to assess bedside nurses' perceived skills and attitudes about updated safety concepts and examine their impact on medication administration errors and adherence to safe medication administration practices. Findings support the premise that medication administration errors result from an interplay among system-, unit-, and nurse-level factors.

NS [Nuclear Safety] update. Current safety and security activities and developments taking place in the Department of Nuclear Safety and Security, Issue no. 8, September 2008

International Nuclear Information System (INIS)

2008-09-01

The current issue presents information about the following activities: 1) International Workshops on Denial of Shipments raise awareness of suppliers, recipients, regulators, carriers/consignors and international organizations of the problems relating to denials of radioactive shipments to determine effective measures to prevent or reduce the instances of shipment denials and delays. 2) Communication and knowledge Management in the Department of Nuclear Safety and Security (NS). 3) Nuclear Security at the Beijing Olympics - an excellent example of the IAEA's work in protecting large scale public events. 4) The Incident and Emergency Centre's Participation in the ConvEx 3 Exercise, 9-10 July 2008, which took place at the Laguna Verde nuclear power plant in Mexico. During the 43 hour long exercise, the Incident and Emergency Centre (IEC) was fully activated. Staff members participating in the exercise represented different departments within the IAEA and the diversity of their knowledge and experience ensured an effective response

Efficacy and safety of biological and targeted-synthetic DMARDs: a systematic literature review informing the 2016 update of the ASAS/EULAR recommendations for the management of axial spondyloarthritis

NARCIS (Netherlands)

Sepriano, Alexandre; Regel, Andrea; van der Heijde, Désirée; Braun, Jürgen; Baraliakos, Xenofon; Landewé, Robert; van den Bosch, Filip; Falzon, Louise; Ramiro, Sofia

2017-01-01

To update the evidence for the efficacy and safety of (b)biological and (ts)targeted-synthetic disease-modifying anti-rheumatic drugs (DMARDs) in patients with axial spondyloarthritis (axSpA) to inform the 2016 update of the Assessment of SpondyloArthritis international Society/European League

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

Role of Ureaplasma Respiratory Tract Colonization in BPD Pathogenesis: Current Concepts and Update

Science.gov (United States)

Viscardi, Rose Marie; Kallapur, Suhas G.

2015-01-01

SYNOPSIS Respiratory tract colonization with the genital mycoplasma species Ureaplasma parvum and U. urealyticum in preterm infants is a significant risk factor for BPD. Recent studies of the ureaplasmal genome, animal infection models, and human infants have provided a better understanding of specific virulence factors, pathogen-host interactions, and variability in genetic susceptibility that contribute to chronic infection, inflammation, and altered lung development. This review will provide an update on the current evidence supporting a causal role of Ureaplasma infection in BPD pathogenesis. The current status of antibiotic trials to prevent BPD in Ureaplasma-infected preterm infants is also reviewed. PMID:26593075

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

DOE interpretations Guide to OSH standards. Update to the Guide

Energy Technology Data Exchange (ETDEWEB)

1994-03-31

Reflecting Secretary O`Leary`s focus on occupational safety and health, the Office of Occupational Safety is pleased to provide you with the latest update to the DOE Interpretations Guide to OSH Standards. This Guide was developed in cooperation with the Occupational Safety and Health Administration, which continued it`s support during this last revision by facilitating access to the interpretations found on the OSHA Computerized Information System (OCIS). This March 31, 1994 update contains 123 formal in letter written by OSHA. As a result of the unique requests received by the 1-800 Response Line, this update also contains 38 interpretations developed by DOE. This new occupational safety and health information adds still more important guidance to the four volume reference set that you presently have in your possession.

DOE interpretations Guide to OSH standards. Update to the Guide

Energy Technology Data Exchange (ETDEWEB)

1994-03-31

Reflecting Secretary O`Leary`s focus on occupational safety and health, the Office of Occupational Safety is pleased to provide you with the latest update to the DOE Interpretations Guide to OSH Standards. This Guide was developed in cooperation with the Occupational Safety and Health Administration, which continued its support during this last revision by facilitating access to the interpretations found on the OSHA Computerized Information System (OCIS). This March 31, 1994 update contains 123 formal interpretation letters written by OSHA. As a result of the unique requests received by the 1-800 Response Line, this update also contains 38 interpretations developed by DOE. This new occupational safety and health information adds still more important guidance to the four volume reference set that you presently have in your possession.

DOE interpretations Guide to OSH standards. Update to the Guide

Energy Technology Data Exchange (ETDEWEB)

1994-03-31

Reflecting Secretary O`Leary`s focus on occupational safety and health, the Office of Occupational Safety is pleased to provide you with the latest update to the DOE Interpretations Guide to OSH Standards. This Guide was developed in cooperation with the Occupational Safety and Health Administration, which continued its support during this last revision by facilitating access to the interpretations found on the OSHA Computerized Information System (OCIS). This March 31, 1994 update contains 123 formal interpretation letters written OSHA. As a result of the unique requests received by the 1-800 Response Line, this update also contains 38 interpretations developed by DOE. This new occupational safety and health information adds still more important guidance to the four volume reference set that you presently have in your possession.

ILK statement about the BMU project of updating nuclear rules and regulations

International Nuclear Information System (INIS)

2007-01-01

In 2003, the German Federal Ministry for the Environment (BMU) started its ''Updating Nuclear Rules and Regulations'' project. Proposals to this effect are currently in revision phase B. They comprise a total of eleven main topics, referred to as modules, under the heading of ''Basic Principles of Safety of Nuclear Power Plants - Safety Requirements in Accordance with the State of the Art.'' The International Nuclear Technology Committee (ILK), in 2005, dealt with the requirements to be met in an up-to-date code of nuclear rules and regulations. Its findings were published in a total of 10 recommendations. The current revision B of the 11 modules contains no discernible incorporation of these recommendations. ILK therefore once more dealt with the BMU project. A summary of its deliberations is available. ILK finds that the safety requirements to be met by nuclear power plants as outlined in the BMU draft are unable to support the implementation of the German Atomic Energy Act. In earlier statements, ILK had written that it deemed updating the code of rules and regulations desirable. The existing draft contains many elements serving this purpose, such as the inclusion of off-power conditions and a more pronounced incorporation of matters of organization and management. The main shortcomings of the present draft are identified and analyzed. (orig.)

Notification: FY 2017 Update of Proposed Key Management Challenges and Internal Control Weaknesses Confronting the U.S. Chemical Safety and Hazard Investigation Board

Science.gov (United States)

Jan 5, 2017. The EPA OIG is beginning work to update for fiscal year 2017 its list of proposed key management challenges and internal control weaknesses confronting the U.S. Chemical Safety and Hazard Investigation Board (CSB).

Project SAFE. Update of the SFR-1 safety assessment. Phase 1. Appendix A4: Far-field

International Nuclear Information System (INIS)

Follin, S.; Andersson, Johan; Holmen, J.; Axelsson, C.L.

1998-01-01

This appendix has identified potential needs for updated hydrogeological modelling of the SFR in connection to the planned update of the performance assessment of the SFR within the framework of the SAFE-project. The objectives of such updated modelling should be to present a credible representation of the hydrogeological system, to explore effects of seals and repository extensions and to provide input to the release and transport calculations of the assessment. The last objective has led to the conclusion that an important focus of the modelling should be to determine the flow through the vaults under different conditions as this flow appear to be a very important quantity in the radionuclide release calculations. The suggested modelling should use relevant data and apply modern modelling tools and techniques, but should be geared towards the objectives. For this reasons it is suggested to apply a set of complementary and sometimes nested approaches, where each model approach is set up in order to address a specific set of questions. Answering these questions would motivate simplifications made in subsequent steps of the modelling. To the extent possible the models should be compared with existing data on flow and Baltic water breakthrough. However, in making such comparisons the accuracy of the measurements and the precision of the models need to be considered. A one-to-one match cannot be expected. It appears that careful geochemical evaluation of the site would only be necessary if more credit is placed on migration in the geosphere. If such an evaluation is considered it should be co-ordinated with the regional groundwater modelling. The issue of gas production should be reconsidered in a scenario and process analysis of SFR. However, given the strong conclusions already made it appears that gas migration in the rock will still remain as a minor issue. The major assumptions going into the analysis of the near-field in the final safety report and the deepened

Revision of the Euratom basic safety standards directive-current status

International Nuclear Information System (INIS)

Mundig, S.

2011-01-01

The European Commission is currently developing a revised Euratom Basic Safety Standards (BSS) Directive covering two major objectives: the consolidation of existing Euratom Radiation Protection legislation and the revision of the Euratom BSS. The consolidation will merge the following five Directives into one single Directive: the BSS Directive, the Medical Exposures Directive, the Public Information Directive, the Outside Workers Directive and the Directive on the Control of high-activity sealed radioactive sources and orphan sources. The revision of the Euratom BSS will take account of the latest recommendations by the International Commission on Radiological Protection and shall improve clarity of the requirements where appropriate. It is planned to introduce more binding requirements on natural radiation sources, on criteria for exemption and clearance, and on the cooperation between Member States for emergency planning and response. The provisions for regulatory control of planned exposure situations foresee a graded approach commensurate to the magnitude and likelihood of exposures from a practice. Finally, the new BSS shall take account of recent scientific developments. One additional goal is to achieve greater harmonisation between the Euratom BSS and the international BSS. While the requirements on the protection of workers, apprentices and students remain nearly unchanged, the revised BSS will clarify the roles and responsibilities of services and experts involved in technical and practical aspects of radiation protection, such as the occupational health services, the dosimetry services, the radiation protection expert and the medical physics expert. The requirements in the BSS on individual monitoring of category A workers remain unchanged, but the existing guidance on individual monitoring was revised and updated-the technical recommendations for monitoring individuals occupationally exposed to external radiation are published by the European

Technical guidelines for the seismic safety re-evaluation at Eastern European NPPs

International Nuclear Information System (INIS)

Godoy, A.R.; Guerpinar, A.

2001-01-01

The paper describes one of the outcomes of the Engineering Safety Review Services (ESRS) that the IAEA provides as an element of the Agency's national, regional and interregional technical assistance and co-operation programmes and other extrabudgetary programmes to assess the safety of nuclear facilities. This refers to the establishment of detailed guidelines for conducting the seismic safety re-evaluation of existing nuclear power plants in Eastern European countries in line with updated criteria and current international practice. (author)

RADWASS update. Radioactive Waste Safety Standards Programme

International Nuclear Information System (INIS)

Delattre, D.

2000-01-01

By the late 1980s, the issue of radioactive wastes and their management was becoming increasingly politically important. The IAEA responded by establishing a high profile family of safety standards, the Radioactive Waste Safety Standards (RADWASS). By this means, the IAEA intended to draw attention to the fact that well-established procedures for the safe management of radioactive wastes already were in place. The programme was intended to establish an ordered structure for safety documents on waste management and to ensure comprehensive coverage of all relevant subject areas. RADWASS documents are categorized under four subject areas - discharges, predisposal, disposal, and environmental restoration. The programme is overseen through a formalized review and approval mechanism that was established in 1996 for all safety standards activities. The Waste Safety Standards Committee (WASSC) is a standing body of senior regulatory officials with technical expertise in radioactive waste safety. To date, three Safety Requirements and seven Safety Guides have been issued

Major update of Safety Analysis Report for Thai Research Reactor-1/Modification 1

Energy Technology Data Exchange (ETDEWEB)

Tippayakul, Chanatip [Thailand Institute of Nuclear Technology, Bangkok (Thailand)

2013-07-01

Thai Research Reactor-1/Modification 1 (TRR-1/M1) was converted from a Material Testing Reactor in 1975 and it had been operated by Office of Atom for Peace (OAP) since 1977 until 2007. During the period, Office of Atom for Peace had two duties for the reactor, that is, to operate and to regulate the reactor. However, in 2007, there was governmental office reformation which resulted in the separation of the reactor operating organization from the regulatory body in order to comply with international standard. The new organization is called Thailand Institute of Nuclear Technology (TINT) which has the mission to promote peaceful utilization of nuclear technology while OAP remains essentially the regulatory body. After the separation, a new ministerial regulation was enforced reflecting a new licensing scheme in which TINT has to apply for a license to operate the reactor. The safety analysis report (SAR) shall be submitted as part of the license application. The ministerial regulation stipulates the outlines of the SAR almost equivalent to IAEA standard 35-G1. Comparing to the IAEA 35-G1 standard, there were several incomplete and missing chapters in the original SAR of TRR1/M1. The major update of the SAR was therefore conducted and took approximately one year. The update work included detail safety evaluation of core configuration which used two fuel element types, the classification of systems, structures and components (SSC), the compilation of detail descriptions of all SSCs and the review and evaluation of radiation protection program, emergency plan and emergency procedure. Additionally, the code of conduct and operating limits and conditions were revised and finalized in this work. A lot of new information was added to the SAR as well, for example, the description of commissioning program, information on environmental impact assessment, decommissioning program, quality assurance program and etc. Due to the complexity of this work, extensive knowledge was

Parametric Criticality Safety Calculations for Arrays of TRU Waste Containers

Energy Technology Data Exchange (ETDEWEB)

Gough, Sean T. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2017-10-26

The Nuclear Criticality Safety Division (NCSD) has performed criticality safety calculations for finite and infinite arrays of transuranic (TRU) waste containers. The results of these analyses may be applied in any technical area onsite (e.g., TA-54, TA-55, etc.), as long as the assumptions herein are met. These calculations are designed to update the existing reference calculations for waste arrays documented in Reference 1, in order to meet current guidance on calculational methodology.

An update on current management of advanced renal cell cancer, biomarkers, and future directions

OpenAIRE

Zhi, Wanqing Iris; Kim, Jenny J.

2014-01-01

In the past decade, metastatic renal cell carcinoma (mRCC) treatment underwent significant advancement that resulted in an unprecedented improvement in the prognosis of this disease. This review will provide an updated review of currently approved treatment options, namely antiangiogenic and immunotherapy, as well as treatment guideline recommended by the National Comprehensive Cancer Network (NCCN). We will summarize studies ongoing in determining prognostic and predictive biomarkers in maxi...

Neurovirulence safety testing of mumps vaccines--historical perspective and current status.

Science.gov (United States)

Rubin, S A; Afzal, M A

2011-04-05

Many live, attenuated viral vaccines are derived from wild type viruses with known neurovirulent properties. To assure the absence of residual neurotoxicity, pre-clinical neurovirulence safety testing of candidate vaccines is performed. For mumps virus, a highly neurotropic virus, neurovirulence safety testing is performed in monkeys. However, laboratory studies suggest an inability of this test to correctly discern among virus strains of varying neurovirulence potential in man, and, further, some vaccines found to be neuroattenuated in monkeys were later found to be neurovirulent in humans when administered in large numbers. Over the past decade, concerted efforts have been made to replace monkey-based neurovirulence safety testing with more informative, alternative methods. This review summarizes the current status of mumps vaccine neurovirulence safety testing and insights into models currently approved and those under development. Published by Elsevier Ltd.

Reliability data update using condition monitoring and prognostics in probabilistic safety assessment

Directory of Open Access Journals (Sweden)

Hyeonmin Kim

2015-03-01

Full Text Available Probabilistic safety assessment (PSA has had a significant role in quantitative decision-making by finding design and operational vulnerabilities and evaluating cost-benefit in improving such weak points. In particular, it has been widely used as the core methodology for risk-informed applications (RIAs. Even though the nature of PSA seeks realistic results, there are still “conservative” aspects. One of the sources for the conservatism is the assumptions of safety analysis and the estimation of failure frequency. Surveillance, diagnosis, and prognosis (SDP, utilizing massive databases and information technology, is worth highlighting in terms of its capability for alleviating the conservatism in conventional PSA. This article provides enabling techniques to solidify a method to provide time- and condition-dependent risks by integrating a conventional PSA model with condition monitoring and prognostics techniques. We will discuss how to integrate the results with frequency of initiating events (IEs and probability of basic events (BEs. Two illustrative examples will be introduced: (1 how the failure probability of a passive system can be evaluated under different plant conditions and (2 how the IE frequency for a steam generator tube rupture (SGTR can be updated in terms of operating time. We expect that the proposed model can take a role of annunciator to show the variation of core damage frequency (CDF depending on operational conditions.

Reliability data update using condition monitoring and prognostics in probabilistic safety assessment

Energy Technology Data Exchange (ETDEWEB)

Kim, Hyeon Min; Lee, Sang Hwan; Park, Jun Seok; Kim, Hyung Dae; Chang, Yoon Suk; Heo, Gyun Young [Dept. of Nuclear Engineering, Kyung Hee University, Yongin (Korea, Republic of)

2015-03-15

Probabilistic safety assessment (PSA) has had a significant role in quantitative decision making by finding design and operational vulnerabilities and evaluating cost-benefit in improving such weak points. In particular, it has been widely used as the core methodology for risk-informed applications (RIAs). Even though the nature of PSA seeks realistic results, there are still 'conservative' aspects. One of the sources for the conservatism is the assumptions of safety analysis and the estimation of failure frequency. Surveillance, diagnosis, and prognosis (SDP), utilizing massive databases and information technology, is worth highlighting in terms of its capability for alleviating the conservatism in conventional PSA. This article provides enabling techniques to solidify a method to provide time and condition-dependent risks by integrating a conventional PSA model with condition monitoring and prognostics techniques. We will discuss how to integrate the results with frequency of initiating events (IEs) and probability of basic events (BEs). Two illustrative examples will be introduced: (1) how the failure probability of a passive system can be evaluated under different plant conditions and (2) how the IE frequency for a steam generator tube rupture (SGTR) can be updated in terms of operating time. We expect that the proposed model can take a role of annunciator to show the variation of core damage frequency (CDF) depending on operational conditions.

Practice Hospital Bed Safety

Science.gov (United States)

... Home For Consumers Consumer Updates Practice Hospital Bed Safety Share Tweet Linkedin Pin it More sharing options ... It depends on the complexity of the bed." Safety Tips CDRH offers the following safety tips for ...

Efficacy and safety of fentanyl buccal for cancer pain management by administration through a soluble film: an update

International Nuclear Information System (INIS)

Delgado-Guay, Marvin Omar

2010-01-01

More than half of patients receiving prescription medicine for cancer pain have been reported to experience inadequate pain relief or breakthrough pain. Buccal administration can deliver lipophilic opioids rapidly to the systemic circulation through the buccal mucosa, limiting gastrointestinal motility and first-pass metabolism. This review updates the safety and efficacy of fentanyl buccal soluble film (FBSF) in patients with cancer pain. Literature was identified through searches of Medline (PubMed). Search terms included combinations of the following: cancer pain, fentanyl, fentanyl buccal soluble film, pharmacology, kinetics, safety, efficacy and toxicity. FBSF is an oral transmucosal form of fentanyl citrate developed as a treatment of breakthrough pain in opioid-tolerant patients with cancer. Studies have shown that it is well tolerated in the oral cavity, with adequate bioavailability and safety in cancer patients. Further studies are warranted to evaluate, in comparison with other short-acting opioids, its efficacy in the management of breakthrough cancer pain, its addictive potential and its economic impact in cancer patients

76 FR 28194 - Proposed FOIA Fee Schedule Update

Science.gov (United States)

2011-05-16

... DEFENSE NUCLEAR FACILITIES SAFETY BOARD 10 CFR Part 1703 Proposed FOIA Fee Schedule Update AGENCY... publishing its proposed Freedom of Information Act (FOIA) Fee Schedule Update and solicits comments from... on the proposed fee schedule should be mailed or delivered to the Office of the General Counsel...

75 FR 27228 - Proposed FOIA Fee Schedule Update

Science.gov (United States)

2010-05-14

... DEFENSE NUCLEAR FACILITIES SAFETY BOARD 10 CFR Part 1703 Proposed FOIA Fee Schedule Update AGENCY... publishing its proposed Freedom of Information Act (FOIA) Fee Schedule Update and solicits comments from... on the proposed fee schedule should be mailed or delivered to the Office of the General Counsel...

NS [Nuclear Safety] update. Current safety and security activities and developments taking place in the Department of Nuclear Safety and Security. Issue no. 2, January 2007

International Nuclear Information System (INIS)

2006-08-01

This newsletter reports on the training of cardiologists in radiation protection, IAEA's safety review services and the operational safety assessment review team (OSART), the international conference on management of spent fuel and the recent INSAG (International Nuclear Safety Group) publications. The IAEA has begun a major international initiative to train interventional cardiologists in radiation protection. Starting with the first course in May 2004, so far 6 regional and 3 national training courses have been conducted with the participation of over 400 health professionals putting the IAEA in a leading role in this area. A programme of two days' training has been developed, covering possible and observed radiation effects among patients and staff, international standards, dose management techniques, examples of good and bad practice and examples indicating prevention of possible injuries as a result of good practice in radiation protection. The training material is freely available on CD and will be placed on the Radiological Protection of Patients website at http://rpop.iaea.org/

Role of Ureaplasma Respiratory Tract Colonization in Bronchopulmonary Dysplasia Pathogenesis: Current Concepts and Update.

Science.gov (United States)

Viscardi, Rose Marie; Kallapur, Suhas G

2015-12-01

Respiratory tract colonization with the genital mycoplasma species Ureaplasma parvum and Ureaplasma urealyticum in preterm infants is a significant risk factor for bronchopulmonary dysplasia (BPD). Recent studies of the ureaplasmal genome, animal infection models, and human infants have provided a better understanding of specific virulence factors, pathogen-host interactions, and variability in genetic susceptibility that contribute to chronic infection, inflammation, and altered lung development. This review provides an update on the current evidence supporting a causal role of ureaplasma infection in BPD pathogenesis. The current status of antibiotic trials to prevent BPD in Ureaplasma-infected preterm infants is also reviewed. Copyright © 2015 Elsevier Inc. All rights reserved.

77 FR 33980 - Proposed FOIA Fee Schedule Update

Science.gov (United States)

2012-06-08

... 1703 Proposed FOIA Fee Schedule Update AGENCY: Defense Nuclear Facilities Safety Board. ACTION: Notice... the Board's proposed FOIA Fee Schedule Update published in the Federal Register of June 1, 2012. The...: The FOIA requires each Federal agency covered by the Act to specify a schedule of fees applicable to...

About the necessity to update the Radiological safety and protection regulations of the National Institute of Nuclear Research (ININ)

International Nuclear Information System (INIS)

Alvarez R, J.T.

1997-01-01

It is argued the necessity to update the Radiological safety and Protection regulations (Review 3) of ININ, with the purpose that it implements the ICRU operative magnitudes system. Such a system used with radiological protection purposes. The objective of this system is to do an estimation of the effective equivalent dose H E and/or the Effective dose E, proposed in the ICRP 26 and ICRU 60 dose limits systems respectively. (Author)

a Bottom-Up Geosptial Data Update Mechanism for Spatial Data Infrastructure Updating

Science.gov (United States)

Tian, W.; Zhu, X.; Liu, Y.

2012-08-01

Currently, the top-down spatial data update mechanism has made a big progress and it is wildly applied in many SDI (spatial data infrastructure). However, this mechanism still has some issues. For example, the update schedule is limited by the professional department's project, usually which is too long for the end-user; the data form collection to public cost too much time and energy for professional department; the details of geospatial information does not provide sufficient attribute, etc. Thus, how to deal with the problems has become the effective shortcut. Emerging Internet technology, 3S technique and geographic information knowledge which is popular in the public promote the booming development of geoscience in volunteered geospatial information. Volunteered geospatial information is the current "hotspot", which attracts many researchers to study its data quality and credibility, accuracy, sustainability, social benefit, application and so on. In addition to this, a few scholars also pay attention to the value of VGI to support the SDI updating. And on that basis, this paper presents a bottom-up update mechanism form VGI to SDI, which includes the processes of match homonymous elements between VGI and SDI vector data , change data detection, SDI spatial database update and new data product publication to end-users. Then, the proposed updating cycle is deeply discussed about the feasibility of which can detect the changed elements in time and shorten the update period, provide more accurate geometry and attribute data for spatial data infrastructure and support update propagation.

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)

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

International Nuclear Information System (INIS)

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

2011-01-01

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

Environmental Regulatory Update Table, January/February 1995

Energy Technology Data Exchange (ETDEWEB)

Houlberg, L.M.; Hawkins, G.T.; Bock, R.E.; Mayer, S.J.; Salk, M.S.

1995-03-01

The Environmental Regulatory Update Table provides information on regulatory initiatives impacting environmental, health, and safety management responsibilities. the table is updated bi-monthly with information from the Federal Register and other sources, including direct contact with regulatory agencies. Each table entry provides a chronological record of the rulemaking process for that initiative with an abstract and a projection of further action.

Environmental Regulatory Update Table, January/February 1995

International Nuclear Information System (INIS)

Houlberg, L.M.; Hawkins, G.T.; Bock, R.E.; Mayer, S.J.; Salk, M.S.

1995-03-01

The Environmental Regulatory Update Table provides information on regulatory initiatives impacting environmental, health, and safety management responsibilities. the table is updated bi-monthly with information from the Federal Register and other sources, including direct contact with regulatory agencies. Each table entry provides a chronological record of the rulemaking process for that initiative with an abstract and a projection of further action

Updating Rhode Island's strategic highway safety plan (SHSP).

Science.gov (United States)

2012-05-01

This report summarizes the peer exchange sponsored by the Rhode Island : Department of Transportation (RIDOT) that focused on Rhode Islands SHSP : update. : Rhode Islands goals for the peer exchange included learning from other States : expe...

Twenty-fifth water reactor safety information meeting: Proceedings. Volume 1: Plenary sessions; Pressure vessel research; BWR strainer blockage and other generic safety issues; Environmentally assisted degradation of LWR components; Update on severe accident code improvements and applications

Energy Technology Data Exchange (ETDEWEB)

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

1998-03-01

This three-volume report contains papers presented at the conference. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included papers presented by researchers from France, Japan, Norway, and Russia. The titles of the papers and the names of the authors have been updated and may differ from those that appeared in the final program of the meeting. This volume contains the following information: (1) plenary sessions; (2) pressure vessel research; (3) BWR strainer blockage and other generic safety issues; (4) environmentally assisted degradation of LWR components; and (5) update on severe accident code improvements and applications. Selected papers have been indexed separately for inclusion in the Energy Science and Technology Database.

Twenty-fifth water reactor safety information meeting: Proceedings. Volume 1: Plenary sessions; Pressure vessel research; BWR strainer blockage and other generic safety issues; Environmentally assisted degradation of LWR components; Update on severe accident code improvements and applications

International Nuclear Information System (INIS)

Monteleone, S.

1998-03-01

This three-volume report contains papers presented at the conference. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included papers presented by researchers from France, Japan, Norway, and Russia. The titles of the papers and the names of the authors have been updated and may differ from those that appeared in the final program of the meeting. This volume contains the following information: (1) plenary sessions; (2) pressure vessel research; (3) BWR strainer blockage and other generic safety issues; (4) environmentally assisted degradation of LWR components; and (5) update on severe accident code improvements and applications. Selected papers have been indexed separately for inclusion in the Energy Science and Technology Database

Technologies and mechanisms for safety control of ready-to-eat muscle foods: an updated review.

Science.gov (United States)

Jiang, Jiang; Xiong, Youling L

2015-01-01

Ready-to-eat (RTE) muscle foods refer to a general category of meat and poultry products that are fully cooked and consumable without reheating. These products, including whole and sliced pork, beef, turkey, chicken, and variety of meats, in the forms of ham, roast, rolls, sausage, and frankfurter, are widely available in the delicatessen section of retail stores or various food service outlets. However, difficulties in avoidance of contamination by foodborne pathogens, notably Listeria monocytogenes, during product postlethality repackaging render RTE meats labile to outbreaks. Accordingly, the USDA-FSIS has established processing guidelines and regulations, which are constantly updated, to minimize foodborne pathogens in RTE products. Technologies that complement good manufacturing practice have been developed to control RTE meat safety. Among them, various antimicrobial product formulations, postpackaging pasteurization (thermal and nonthermal), and antimicrobial packaging are being used. Through these efforts, outbreaks linked to RTE meat consumption have substantially reduced in recent years. However, the pervasive and virulent nature of L. monocytogenes and the possible presence of other cold-tolerant pathogens entail continuing developments of new intervention technologies. This review updates existing and emerging physical and chemical methods and their mode of action to inactivate or inhibit threatening microorganisms in RTE muscle foods.

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)

Second-generation speed limit map updating applications

DEFF Research Database (Denmark)

Tradisauskas, Nerius; Agerholm, Niels; Juhl, Jens

2011-01-01

Intelligent Speed Adaptation is an Intelligent Transport System developed to significantly improve road safety in helping car drivers maintain appropriate driving behaviour. The system works in connection with the speed limits on the road network. It is thus essential to keep the speed limit map...... used in the Intelligent Speed Adaptation scheme updated. The traditional method of updating speed limit maps on the basis of long time interval observations needed to be replaced by a more efficient speed limit updating tool. In a Danish Intelligent Speed Adaptation trial a web-based tool was therefore...... for map updating should preferably be made on the basis of a commercial map provider, 2 such as Google Maps and that the real challenge is to oblige road authorities to carry out updates....

75 FR 76070 - Railroad Safety Advisory Committee (RSAC); Working Group Activity Update

Science.gov (United States)

2010-12-07

... the Passenger Equipment Safety Standards. The Working Group met on September 16, 2010; currently there... ``after arrival mandatory directives,'' among other issues. The Working Group continues to work on after... protecting persons who work on, under, or between rolling equipment and persons applying, removing, or...

National Nuclear Safety Report 2001. Convention on Nuclear Safety

International Nuclear Information System (INIS)

2001-01-01

The First National Nuclear Safety Report was presented at the first review meeting of the Nuclear Safety Convention. At that time it was concluded that Argentina met the obligations of the Convention. This second National Nuclear Safety Report is an updated report which includes all safety aspects of the Argentinian nuclear power plants and the measures taken to enhance the safety of the plants. The present report also takes into account the observations and discussions maintained during the first review meeting. The conclusion made in the first review meeting about the compliance by Argentina of the obligations of the Convention are included as Annex 1. In general, the information contained in this Report has been updated since March 31, 1998 to March 31, 2001. Those aspects that remain unchanged were not addressed in this second report with the objective of avoiding repetitions and in order to carry out a detailed analysis considering article by article. As a result of the above mentioned detailed analysis of all the Articles, it can be stated that the country fulfils all the obligations imposed by the Nuclear Safety Convention

National nuclear safety report 2004. Convention on nuclear safety

International Nuclear Information System (INIS)

2004-01-01

The second National Nuclear Safety Report was presented at the second review meeting of the Nuclear Safety Convention. At that time it was concluded that Argentina met the obligations of the Convention. This third National Nuclear Safety Report is an updated report which includes all safety aspects of the Argentinian nuclear power plants and the measures taken to enhance the safety of the plants. The present report also takes into account the observations and discussions maintained during the second review meeting. The conclusion made in the first review meeting about the compliance by Argentina of the obligations of the Convention are included as Annex I and those belonging to the second review meeting are included as Annex II. In general, the information contained in this Report has been updated since March 31, 2001 to April 30, 2004. Those aspects that remain unchanged were not addressed in this third report. As a result of the detailed analysis of all the Articles, it can be stated that the country fulfils all the obligations imposed by the Nuclear Safety Convention. The questions and answers originated at the Second Review Meeting are included as Annex III

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.

77 FR 32433 - Proposed FOIA Fee Schedule Update

Science.gov (United States)

2012-06-01

... 1703 Proposed FOIA Fee Schedule Update AGENCY: Defense Nuclear Facilities Safety Board. ACTION: Notice... Defense Nuclear Facilities Safety Board is publishing its proposed Freedom of Information Act (FOIA) Fee.... on or before July 2, 2012. ADDRESSES: Comments on the proposed fee schedule should be mailed or...

Cassini Spacecraft Uncertainty Analysis Data and Methodology Review and Update/Volume 1: Updated Parameter Uncertainty Models for the Consequence Analysis

Energy Technology Data Exchange (ETDEWEB)

WHEELER, TIMOTHY A.; WYSS, GREGORY D.; HARPER, FREDERICK T.

2000-11-01

Uncertainty distributions for specific parameters of the Cassini General Purpose Heat Source Radioisotope Thermoelectric Generator (GPHS-RTG) Final Safety Analysis Report consequence risk analysis were revised and updated. The revisions and updates were done for all consequence parameters for which relevant information exists from the joint project on Probabilistic Accident Consequence Uncertainty Analysis by the United States Nuclear Regulatory Commission and the Commission of European Communities.

System Design and the Safety Basis

International Nuclear Information System (INIS)

Ellingson, Darrel

2008-01-01

The objective of this paper is to present the Bechtel Jacobs Company, LLC (BJC) Lessons Learned for system design as it relates to safety basis documentation. BJC has had to reconcile incomplete or outdated system description information with current facility safety basis for a number of situations in recent months. This paper has relevance in multiple topical areas including documented safety analysis, decontamination and decommissioning (D and D), safety basis (SB) implementation, safety and design integration, potential inadequacy of the safety analysis (PISA), technical safety requirements (TSR), and unreviewed safety questions. BJC learned that nuclear safety compliance relies on adequate and well documented system design information. A number of PIS As and TSR violations occurred due to inadequate or erroneous system design information. As a corrective action, BJC assessed the occurrences caused by systems design-safety basis interface problems. Safety systems reviewed included the Molten Salt Reactor Experiment (MSRE) Fluorination System, K-1065 fire alarm system, and the K-25 Radiation Criticality Accident Alarm System. The conclusion was that an inadequate knowledge of system design could result in continuous non-compliance issues relating to nuclear safety. This was especially true with older facilities that lacked current as-built drawings coupled with the loss of 'historical knowledge' as personnel retired or moved on in their careers. Walkdown of systems and the updating of drawings are imperative for nuclear safety compliance. System design integration with safety basis has relevance in the Department of Energy (DOE) complex. This paper presents the BJC Lessons Learned in this area. It will be of benefit to DOE contractors that manage and operate an aging population of nuclear facilities

PSA Update Procedures, an Ultimate Need for Living PSA

International Nuclear Information System (INIS)

Hegedus, D.

1998-01-01

Nuclear facilities by their complex nature, change with time. These changes can be both physical (plant modification, etc.), operational (enhanced procedures, etc.) and organizational. In addition, there are also changes in our understanding of the plant, due to operational experience, data collection, technology enhancements, etc. Therefore, it is imperative that PSA model must be frequently up-dated or modified to reflect these changes. Over the last ten years. these has been a remarkable growth of the use of Probabilistic Safety Assessments (PSAs). The most rapidly growing area of the PSA Applications is their use to support operational decision-making. Many of these applications are characterized by the potential for not only improving the safety level but also for providing guidance on the optimal use of resources and reducing regulatory burden. To enable a wider use of the PSA model as a tool for safety activities it is essential to maintain the model in a controlled state. Moreover, to fulfill requirements for L iving PSA , the PSA model has to be constantly updated and/or monitored to reflect the current plant configuration. It should be noted that the PSA model should not only represent the plant design but should also represent the operational and emergency procedures. To keep the PSA model up-to-date several issues should be clearly defined including: - Responsibility should be divided among the PSA group, - Procedures for implementing changes should be established, and - QA requirements/program should be established to assure documentation and reporting. (author)

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

Efficacy and safety of fentanyl buccal for cancer pain management by administration through a soluble film: an update

Directory of Open Access Journals (Sweden)

Marvin Omar Delgado-Guay

2010-11-01

Full Text Available Marvin Omar Delgado-GuayDivision of Geriatrics and Palliative Medicine, The University of Texas, Medical School at Houston, Houston, TX, USAAbstract: More than half of patients receiving prescription medicine for cancer pain have been reported to experience inadequate pain relief or breakthrough pain. Buccal administration can deliver lipophilic opioids rapidly to the systemic circulation through the buccal mucosa, limiting gastrointestinal motility and first-pass metabolism. This review updates the safety and efficacy of fentanyl buccal soluble film (FBSF in patients with cancer pain. Literature was identified through searches of Medline (PubMed. Search terms included combinations of the following: cancer pain, fentanyl, fentanyl buccal soluble film, pharmacology, kinetics, safety, efficacy and toxicity. FBSF is an oral transmucosal form of fentanyl citrate developed as a treatment of breakthrough pain in opioid-tolerant patients with cancer. Studies have shown that it is well tolerated in the oral cavity, with adequate bioavailability and safety in cancer patients. Further studies are warranted to evaluate, in comparison with other short-acting opioids, its efficacy in the management of breakthrough cancer pain, its addictive potential and its economic impact in cancer patients.Keywords: fentanyl buccal soluble film, cancer pain

National nuclear safety report 2005. Convention on nuclear safety

International Nuclear Information System (INIS)

2006-01-01

This National Nuclear Safety Report was presented at the 3rd. Review meeting. In general the information contained in the report are: Highlights / Themes; Follow-up from 2nd. Review meeting; Challenges, achievements and good practices; Planned measures to improve safety; Updates to National report to 3rd. Review meeting; Questions from peer review of National Report; and Conclusions

Phase 9 update (1987) report for the Energy Economic Data Base Program EEDB-IX

International Nuclear Information System (INIS)

1988-07-01

This document is a review of the 1987 update of detailed reference powerplant cost estimates. This distribution is the latest in a series published since 1978. The overall program purpose is to provide periodically updated, detailed base construction cost estimates for large nuclear electric operating plants. These data, which are representative of current US powerplant construction cost experience, are a useful contribution to program planning by the Office of the Assistant Secretary for Nuclear Energy. The ninth update includes three new models as a basis for projecting future costs of both small and large nuclear power plants and examining the potential for cost reduction by incorporation of improved and advanced design features. The models designated as improved include the advantages of modular construction and standardized approach to design and construction. The advanced model includes many of the features of the improved data models as well as application of passive or near-passive safety systems and design simplification

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

Development and Psychometric Analysis of a Nurses' Attitudes and Skills Safety Scale: Initial Results.

Science.gov (United States)

Armstrong, Gail E; Dietrich, Mary; Norman, Linda; Barnsteiner, Jane; Mion, Lorraine

Health care organizations have incorporated updated safety principles in the analysis of errors and in norms and standards. Yet no research exists that assesses bedside nurses' perceived skills or attitudes toward updated safety concepts. The aims of this study were to develop a scale assessing nurses' perceived skills and attitudes toward updated safety concepts, determine content validity, and examine internal consistency of the scale and subscales. Understanding nurses' perceived skills and attitudes about safety concepts can be used in targeting strategies to enhance their safety practices.

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

Periodic safety reviews in nuclear power plants in Germany have been performed since the end of the 1980's as an indirect follow-up of the accident in Chernobyl and, in the meantime, are formally required by law. During this process the guidelines governing this review were developed in stages and reached their final form in 1996. Interim storage facilities and other nuclear facilities at that time were not included, so the guidelines were solely focused on the specific safety issues of nuclear power plants. Following IAEA's recommendations, the Western European Nuclear Regulator Association (WENRA) introduced PSRs in its safety reference levels for storage facilities (current version in WGWD report 2.1 as of Feb 2011: SRLs 59 - 61). Based on these formulations, Germany improved its regulation in 2010 with a recommendation of the Nuclear Waste Management Commission (Entsorgungskommission, ESK), an expert advisory commission for the federal regulatory body BMU. The ESK formulated these detailed requirements in the 'ESK recommendation for guides to the performance of periodic safety reviews for interim storage facilities for irradiated fuel elements and heat-generating radioactive waste'. Before finalization of the guideline a test phase was introduced, aimed to test the new regulation in practice and to later include the lessons learned in the final formulation of the guideline. The two-year test phase started in October 2011 in which the performance of a PSR will be tested at two selected interim storage facilities. Currently these recommendations are discussed with interested/concerned institutions. The results of the test phase shall be considered for improvements of the draft and during the final preparation of guidelines. Currently the PSR for the first ISF is in an advanced stage, the second facility just started the process. Preliminary conclusions from the test phase show that the implementation of the draft guideline requires interpretation. The aim of a

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/.

Thyroid radiofrequency ablation: Updates on innovative devices and techniques

Energy Technology Data Exchange (ETDEWEB)

Park, Hye Sun; Baek, Jung Hwan; Chung, Sae Rom; Choi, Young Jun; Lee, Jeong Hyun [Dept. of Radiology and Research Institute of Radiology, University of Ulsan College of Medicine, Asan Medical Center, Seoul (Korea, Republic of); Park, Auh Whan [Dept. of Radiology, Vascular and Interventional Radiology Section, University of Virginia Health System, Charlottesville (United States)

2017-08-01

Radiofrequency ablation (RFA) is a well-known, effective, and safe method for treating benign thyroid nodules and recurrent thyroid cancers. Thyroid-dedicated devices and basic techniques for thyroid RFA were introduced by the Korean Society of Thyroid Radiology (KSThR) in 2012. Thyroid RFA has now been adopted worldwide, with subsequent advances in devices and techniques. To optimize the treatment efficacy and patient safety, understanding the basic and advanced RFA techniques and selecting the optimal treatment strategy are critical. The goal of this review is to therefore provide updates and analysis of current devices and advanced techniques for RFA treatment of benign thyroid nodules and recurrent thyroid cancers.

ATHENA simulations of divertor loss of heat sink transient for the GSSR - Final report with updates

Energy Technology Data Exchange (ETDEWEB)

Sponton, L.L

2001-05-01

The ITER-FEAT Generic Site Safety Report includes evaluations of the consequences of various types of conceivable transients that can occur during operation. The transients that have to be considered in this respect are specified in the Accident Analysis Specifications document of the safety report. For the divertor primary heat transport system the ranges of transients include amongst others a loss of heat sink at full fusion power operation. The thermal-hydraulic consequences related to the coolability of the divertor primary heat transport system components for this transient have been evaluated and summarised in the safety report and in the current report an overview of those efforts and associated outcome is provided. The analyses have been made with the ATHENA thermal-hydraulic code using a separately developed ATHENA model of the ITER-FEAT divertor cooling system. In the current report results from calculations with an updated pressurizer model and pressurizer control system are outlined. The results show that the pressurizer safety valve does not open, that the pressurizer level increase is moderate and that no temperature increases jeopardize the structure integrity.

ATHENA simulations of divertor loss of heat sink transient for the GSSR - Final report with updates

International Nuclear Information System (INIS)

Sponton, L.L.

2001-05-01

The ITER-FEAT Generic Site Safety Report includes evaluations of the consequences of various types of conceivable transients that can occur during operation. The transients that have to be considered in this respect are specified in the Accident Analysis Specifications document of the safety report. For the divertor primary heat transport system the ranges of transients include amongst others a loss of heat sink at full fusion power operation. The thermal-hydraulic consequences related to the coolability of the divertor primary heat transport system components for this transient have been evaluated and summarised in the safety report and in the current report an overview of those efforts and associated outcome is provided. The analyses have been made with the ATHENA thermal-hydraulic code using a separately developed ATHENA model of the ITER-FEAT divertor cooling system. In the current report results from calculations with an updated pressurizer model and pressurizer control system are outlined. The results show that the pressurizer safety valve does not open, that the pressurizer level increase is moderate and that no temperature increases jeopardize the structure integrity

Efforts to update firefighter safety zone guidelines

Science.gov (United States)

Bret Butler

2009-01-01

One of the most critical decisions made on wildland fires is the identification of suitable safety zones for firefighters during daily fire management operations. To be effective (timely, repeatable, and accurate), these decisions rely on good training and judgment, but also on clear, concise guidelines. This article is a summary of safety zone guidelines and the...

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)

Development and Psychometric Analysis of a Nurses’ Attitudes and Skills Safety Scale: Initial Results

Science.gov (United States)

Armstrong, Gail E.; Dietrich, Mary; Norman, Linda; Barnsteiner, Jane; Mion, Lorraine

2016-01-01

Health care organizations have incorporated updated safety principles in the analysis of errors and in norms and standards. Yet no research exists that assesses bedside nurses’ perceived skills or attitudes toward updated safety concepts. The aims of this study were to develop a scale assessing nurses’ perceived skills and attitudes toward updated safety concepts, determine content validity, and examine internal consistency of the scale and subscales. Understanding nurses’ perceived skills and attitudes about safety concepts can be used in targeting strategies to enhance their safety practices. PMID:27479518

Skin Wound Healing: An Update on the Current Knowledge and Concepts.

Science.gov (United States)

Sorg, Heiko; Tilkorn, Daniel J; Hager, Stephan; Hauser, Jörg; Mirastschijski, Ursula

2017-01-01

repair have been delineated in part, many underlying pathophysiological processes are still unknown. The purpose of the following update on skin wound healing is to focus on the different phases and to brief the reader on the current knowledge and new insights. Skin wound healing is a complex process, which is dependent on many cell types and mediators interacting in a highly sophisticated temporal sequence. Although some interactions during the healing process are crucial, redundancy is high and other cells or mediators can adopt functions or signaling without major complications. © 2016 S. Karger AG, Basel.

Preliminary safety design analysis of KALIMER

Energy Technology Data Exchange (ETDEWEB)

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

1999-03-01

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

Breast Cancer and Estrogen-Alone Update

Science.gov (United States)

... Current Issue Past Issues Research News From NIH Breast Cancer and Estrogen-Alone Update Past Issues / Summer 2006 ... hormone therapy does not increase the risk of breast cancer in postmenopausal women, according to an updated analysis ...

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

System Safety Program Plan for Project W-314, tank farm restoration and safe operations

International Nuclear Information System (INIS)

Boos, K.A.

1996-01-01

This System Safety Program Plan (SSPP) outlines the safety analysis strategy for project W-314, ''Tank Farm Restoration and Safe Operations.'' Project W-314 will provide capital improvements to Hanford's existing Tank Farm facilities, with particular emphasis on infrastructure systems supporting safe operation of the double-shell activities related to the project's conceptual Design Phase, but is planned to be updated and maintained as a ''living document'' throughout the life of the project to reflect the current safety analysis planning for the Tank Farm Restoration and Safe Operations upgrades. This approved W-314 SSPP provides the basis for preparation/approval of all safety analysis documentation needed to support the project

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 Evolution of Process Safety: Current Status and Future Direction.

Science.gov (United States)

Mannan, M Sam; Reyes-Valdes, Olga; Jain, Prerna; Tamim, Nafiz; Ahammad, Monir

2016-06-07

The advent of the industrial revolution in the nineteenth century increased the volume and variety of manufactured goods and enriched the quality of life for society as a whole. However, industrialization was also accompanied by new manufacturing and complex processes that brought about the use of hazardous chemicals and difficult-to-control operating conditions. Moreover, human-process-equipment interaction plus on-the-job learning resulted in further undesirable outcomes and associated consequences. These problems gave rise to many catastrophic process safety incidents that resulted in thousands of fatalities and injuries, losses of property, and environmental damages. These events led eventually to the necessity for a gradual development of a new multidisciplinary field, referred to as process safety. From its inception in the early 1970s to the current state of the art, process safety has come to represent a wide array of issues, including safety culture, process safety management systems, process safety engineering, loss prevention, risk assessment, risk management, and inherently safer technology. Governments and academic/research organizations have kept pace with regulatory programs and research initiatives, respectively. Understanding how major incidents impact regulations and contribute to industrial and academic technology development provides a firm foundation to address new challenges, and to continue applying science and engineering to develop and implement programs to keep hazardous materials within containment. Here the most significant incidents in terms of their impact on regulations and the overall development of the field of process safety are described.

Aggregate analysis of regulatory authority assessors' comments to improve the quality of periodic safety update reports.

Science.gov (United States)

Jullian, Sandra; Jaskiewicz, Lukasz; Pfannkuche, Hans-Jürgen; Parker, Jeremy; Lalande-Luesink, Isabelle; Lewis, David J; Close, Philippe

2015-09-01

Marketing authorization holders (MAHs) are expected to provide high-quality periodic safety update reports (PSURs) on their pharmaceutical products to health authorities (HAs). We present a novel instrument aiming at improving quality of PSURs based on standardized analysis of PSUR assessment reports (ARs) received from the European Union HAs across products and therapeutic areas. All HA comments were classified into one of three categories: "Request for regulatory actions," "Request for medical and scientific information," or "Data deficiencies." The comments were graded according to their impact on patients' safety, the drug's benefit-risk profile, and the MAH's pharmacovigilance system. A total of 476 comments were identified through the analysis of 63 PSUR HA ARs received in 2013 and 2014; 47 (10%) were classified as "Requests for regulatory actions," 309 (65%) as "Requests for medical and scientific information," and 118 (25%) comments were related to "Data deficiencies." The most frequent comments were requests for labeling changes (35 HA comments in 19 ARs). The aggregate analysis revealed commonly raised issues and prompted changes of the MAH's procedures related to the preparation of PSURs. The authors believe that this novel instrument based on the evaluation of PSUR HA ARs serves as a valuable mechanism to enhance the quality of PSURs and decisions about optimization of the use of the products and, therefore, contributes to improve further the MAH's pharmacovigilance system and patient safety. Copyright © 2015 John Wiley & Sons, Ltd.

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

Development of regulatory guidance on safety reviews of nuclear power plants in Germany. A survey on accomplished and current PSA activities

International Nuclear Information System (INIS)

Berg, H.-P.; Froehmel, T.; Goertz, R.; Rehs, B.

2005-01-01

The paper describes the key points of the accomplished and current regulatory activities in order to revise PSA guide and the corresponding technical documents in Germany. The regulatory German PSA guide covers the fundamental requirements concerning the performance of PSAs in the frame of comprehensive safety reviews. The technical details regarding the performance of PSA are set out in two technical documents (PSA Methods and PSA Data) that have been developed by a working group of PSA experts (FAK PSA). Based on the experiences from the first series of PSRs, international experiences and the fact that PSR is mandatory since April 2002 revisions of all guides are underway. The first guide to be updated is the PSA guide together with the corresponding technical documents. The working programme and the revision process of FAK PSA was finished at the end of 2004 and the technical documents have recently been republished. (author)

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

How update schemes influence crowd simulations

International Nuclear Information System (INIS)

Seitz, Michael J; Köster, Gerta

2014-01-01

Time discretization is a key modeling aspect of dynamic computer simulations. In current pedestrian motion models based on discrete events, e.g. cellular automata and the Optimal Steps Model, fixed-order sequential updates and shuffle updates are prevalent. We propose to use event-driven updates that process events in the order they occur, and thus better match natural movement. In addition, we present a parallel update with collision detection and resolution for situations where computational speed is crucial. Two simulation studies serve to demonstrate the practical impact of the choice of update scheme. Not only do density-speed relations differ, but there is a statistically significant effect on evacuation times. Fixed-order sequential and random shuffle updates with a short update period come close to event-driven updates. The parallel update scheme overestimates evacuation times. All schemes can be employed for arbitrary simulation models with discrete events, such as car traffic or animal behavior. (paper)

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.

SSI and SKI's Review of SKB's Updated Final Safety Report for SFR 1. Review Report

International Nuclear Information System (INIS)

2003-10-01

The Repository for Radioactive Operational Waste (SFR 1) is now the object of a new review by the Swedish Radiation Protection Authority (SSI) and the Swedish Nuclear Power Inspectorate (SKI). One of the stipulations for operating SFR 1 was that a new assessment of the long-term performance and environmental consequences of the repository should be conducted once every 10 years by the licensee, the Swedish Nuclear Fuel and Waste Management Co (SKB). During the time that SFR 1 has been in operation, experience has been gained of operating the facility and new knowledge of long-term performance of SFR 1 has been obtained. New regulations for nuclear facilities have been promulgated since SFR 1 was taken into operation (1988). A review committee comprising employees from SKI and SSI has conducted the review of SSR 2001. This review report has resulted in the committee's evaluation of the safety of SFR 1 and is the basis of the regulatory authorities' decision concerning any amendments to the stipulations for the operation of SFR 1. However, the review has found deficiencies in the follow up of the development of design basis norms since the facility was constructed as well as deficiencies in learning from operating experience. However, the overall evaluation is that the facility is being operated in an acceptable manner from the standpoint of safety. With respect to the long-term performance of the repository, it is a deficiency that SSR 2001 does not describe how compliance with the stipulated radiation protection requirements on optimisation and use of the best available technology (BAT) is achieved during operation. In the opinion of the review committee, issues relating to occupational radiation protection are being handled satisfactorily and the operational releases of radioactive substances are very small. Safety and Radiation Protection after Closure SKB's long-term repository performance assessment contains essential updates and improvements compared with the

Recent developments in the IAEA safety standards: design and operation of nuclear power plants

International Nuclear Information System (INIS)

Saito, Takehiko

2004-01-01

The IAEA has been publishing a wide variety of safety standards for nuclear and radiation related facilities and activities since 1978. In 1996, a more rigorously structured approach for the preparation and review of its safety standards was introduced. Currently, based on the approach, revision of most of the standards is in completion or near completion. The latest versions of the Safety Requirements for ''Design'' and ''Operation'' of nuclear power plants were respectively published in 2000. Currently, along with this revision of the Safety Requirements, many Safety Guides have been revised. In order to clarify the complicated revision procedure, an example of the entire revision process for a Safety Guide is provided. Through actual example of the revision process, enormous amount of work involved in the revision work is clearly indicated. The current status of all of the Safety Standards for Design and that for Operation of nuclear power plants are summarized. Summary of other IAEA safety standards currently revised and available related IAEA publications, together with information on the IAEA Web Site from where these documents can be downloaded, is also provided. The standards are reviewed to determine whether revision (or new issue) is necessary in five years following publication. The IAEA safety standards will continue to be updated through comprehensive and structured approach, collaboration of many experts of the world, and reflecting good practices of the world. The IAEA safety standards will serve to provide high level of safety assurance. (author)

NASA's Software Safety Standard

Science.gov (United States)

Ramsay, Christopher M.

2007-01-01

NASA relies more and more on software to control, monitor, and verify its safety critical systems, facilities and operations. Since the 1960's there has hardly been a spacecraft launched that does not have a computer on board that will provide command and control services. There have been recent incidents where software has played a role in high-profile mission failures and hazardous incidents. For example, the Mars Orbiter, Mars Polar Lander, the DART (Demonstration of Autonomous Rendezvous Technology), and MER (Mars Exploration Rover) Spirit anomalies were all caused or contributed to by software. The Mission Control Centers for the Shuttle, ISS, and unmanned programs are highly dependant on software for data displays, analysis, and mission planning. Despite this growing dependence on software control and monitoring, there has been little to no consistent application of software safety practices and methodology to NASA's projects with safety critical software. Meanwhile, academia and private industry have been stepping forward with procedures and standards for safety critical systems and software, for example Dr. Nancy Leveson's book Safeware: System Safety and Computers. The NASA Software Safety Standard, originally published in 1997, was widely ignored due to its complexity and poor organization. It also focused on concepts rather than definite procedural requirements organized around a software project lifecycle. Led by NASA Headquarters Office of Safety and Mission Assurance, the NASA Software Safety Standard has recently undergone a significant update. This new standard provides the procedures and guidelines for evaluating a project for safety criticality and then lays out the minimum project lifecycle requirements to assure the software is created, operated, and maintained in the safest possible manner. This update of the standard clearly delineates the minimum set of software safety requirements for a project without detailing the implementation for those

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.

Breast-Feeding Analgesia in Infants: An Update on the Current State of Evidence.

Science.gov (United States)

Benoit, Britney; Martin-Misener, Ruth; Latimer, Margot; Campbell-Yeo, Marsha

To provide an updated synthesis of the current state of the evidence for the effectiveness of breast-feeding and expressed breast milk feeding in reducing procedural pain in preterm and full-term born infants. A systematic search of key electronic databases (PubMed, CINAHL, EMBASE) was completed. Of the 1032 abstracts screened, 21 were found eligible for inclusion. Fifteen studies reported on the use of breast-feeding or expressed breast milk in full-term infants and 6 reported on preterm infants. Direct breast-feeding was more effective than maternal holding, maternal skin-to-skin contact, topical anesthetics, and music therapy, and was as or more effective than sweet tasting solutions in full-term infants. Expressed breast milk was not consistently found to reduce pain response in full-term or preterm infants. Studies generally had moderate to high risk of bias. There is sufficient evidence to recommend direct breast-feeding for procedural pain management in full-term infants. Based on current evidence, expressed breast milk alone should not be considered an adequate intervention.

A German perspective on advances in safety standards and regulations

International Nuclear Information System (INIS)

Berg, H.P.; Herttrich, P.M.

1993-01-01

At present, different proposals for evolutionary or innovative reactors are under consideration. Therefore, it is necessary that the regulators give guidance on the required safety characteristics of future designs of nuclear power plants. On the one hand, existing regulations have to be updated according to the current state of science and technology. Best available and adequately approved technology has to be used as a yardstick for the acceptability of future basic design features. On the other hand, potential safety features of innovative or revolutionary designs must be considered as serious competitors and potential technical solutions taking the state of maturity of the concepts, the extent of practical experience and the level of effort needed for realization into due account. On this background, recent developments of the Atomic Energy Act, of safety regulations and investigations of requirements for future designs in the Federal Republic of Germany and current projects of international cooperation are presented. (author)

Atomic Information Technology Safety and Economy of Nuclear Power Plants

CERN Document Server

Woo, Taeho

2012-01-01

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

MO-AB-207-04: ACR Update in Mammography

International Nuclear Information System (INIS)

Berns, E.

2015-01-01

A goal of an imaging accreditation program is to ensure adequate image quality, verify appropriate staff qualifications, and to assure patient and personnel safety. Currently, more than 35,000 facilities in 10 modalities have been accredited by the American College of Radiology (ACR), making the ACR program one of the most prolific accreditation options in the U.S. In addition, ACR is one of the accepted accreditations required by some state laws, CMS/MIPPA insurance and others. Familiarity with the ACR accreditation process is therefore essential to clinical diagnostic medical physicists. Maintaining sufficient knowledge of the ACR program must include keeping up-to-date as the various modality requirements are refined to better serve the goals of the program and to accommodate newer technologies and practices. This session consists of presentations from authorities in four ACR accreditation modality programs, including magnetic resonance imaging, computed tomography, nuclear medicine, and mammography. Each speaker will discuss the general components of the modality program and address any recent changes to the requirements. Learning Objectives: To understand the requirements of the ACR MR Accreditation program. The discussion will include accreditation of whole-body general purpose magnets, dedicated extremity systems well as breast MRI accreditation. Anticipated updates to the ACR MRI Quality Control Manual will also be reviewed. To understand the requirements of the ACR CT accreditation program, including updates to the QC manual as well as updates through the FAQ process. To understand the requirements of the ACR nuclear medicine accreditation program, and the role of the physicist in annual equipment surveys and the set up and supervision of the routine QC program. To understand the current ACR MAP Accreditation requirement and present the concepts and structure of the forthcoming ACR Digital Mammography QC Manual and Program

MO-AB-207-02: ACR Update in MR

International Nuclear Information System (INIS)

Price, R.

2015-01-01

A goal of an imaging accreditation program is to ensure adequate image quality, verify appropriate staff qualifications, and to assure patient and personnel safety. Currently, more than 35,000 facilities in 10 modalities have been accredited by the American College of Radiology (ACR), making the ACR program one of the most prolific accreditation options in the U.S. In addition, ACR is one of the accepted accreditations required by some state laws, CMS/MIPPA insurance and others. Familiarity with the ACR accreditation process is therefore essential to clinical diagnostic medical physicists. Maintaining sufficient knowledge of the ACR program must include keeping up-to-date as the various modality requirements are refined to better serve the goals of the program and to accommodate newer technologies and practices. This session consists of presentations from authorities in four ACR accreditation modality programs, including magnetic resonance imaging, computed tomography, nuclear medicine, and mammography. Each speaker will discuss the general components of the modality program and address any recent changes to the requirements. Learning Objectives: To understand the requirements of the ACR MR Accreditation program. The discussion will include accreditation of whole-body general purpose magnets, dedicated extremity systems well as breast MRI accreditation. Anticipated updates to the ACR MRI Quality Control Manual will also be reviewed. To understand the requirements of the ACR CT accreditation program, including updates to the QC manual as well as updates through the FAQ process. To understand the requirements of the ACR nuclear medicine accreditation program, and the role of the physicist in annual equipment surveys and the set up and supervision of the routine QC program. To understand the current ACR MAP Accreditation requirement and present the concepts and structure of the forthcoming ACR Digital Mammography QC Manual and Program

MO-AB-207-04: ACR Update in Mammography

Energy Technology Data Exchange (ETDEWEB)

Berns, E. [University of Colorado Health Science (United States)

2015-06-15

A goal of an imaging accreditation program is to ensure adequate image quality, verify appropriate staff qualifications, and to assure patient and personnel safety. Currently, more than 35,000 facilities in 10 modalities have been accredited by the American College of Radiology (ACR), making the ACR program one of the most prolific accreditation options in the U.S. In addition, ACR is one of the accepted accreditations required by some state laws, CMS/MIPPA insurance and others. Familiarity with the ACR accreditation process is therefore essential to clinical diagnostic medical physicists. Maintaining sufficient knowledge of the ACR program must include keeping up-to-date as the various modality requirements are refined to better serve the goals of the program and to accommodate newer technologies and practices. This session consists of presentations from authorities in four ACR accreditation modality programs, including magnetic resonance imaging, computed tomography, nuclear medicine, and mammography. Each speaker will discuss the general components of the modality program and address any recent changes to the requirements. Learning Objectives: To understand the requirements of the ACR MR Accreditation program. The discussion will include accreditation of whole-body general purpose magnets, dedicated extremity systems well as breast MRI accreditation. Anticipated updates to the ACR MRI Quality Control Manual will also be reviewed. To understand the requirements of the ACR CT accreditation program, including updates to the QC manual as well as updates through the FAQ process. To understand the requirements of the ACR nuclear medicine accreditation program, and the role of the physicist in annual equipment surveys and the set up and supervision of the routine QC program. To understand the current ACR MAP Accreditation requirement and present the concepts and structure of the forthcoming ACR Digital Mammography QC Manual and Program.

MO-AB-207-02: ACR Update in MR

Energy Technology Data Exchange (ETDEWEB)

Price, R. [Vanderbilt Medical Center (United States)

2015-06-15

A goal of an imaging accreditation program is to ensure adequate image quality, verify appropriate staff qualifications, and to assure patient and personnel safety. Currently, more than 35,000 facilities in 10 modalities have been accredited by the American College of Radiology (ACR), making the ACR program one of the most prolific accreditation options in the U.S. In addition, ACR is one of the accepted accreditations required by some state laws, CMS/MIPPA insurance and others. Familiarity with the ACR accreditation process is therefore essential to clinical diagnostic medical physicists. Maintaining sufficient knowledge of the ACR program must include keeping up-to-date as the various modality requirements are refined to better serve the goals of the program and to accommodate newer technologies and practices. This session consists of presentations from authorities in four ACR accreditation modality programs, including magnetic resonance imaging, computed tomography, nuclear medicine, and mammography. Each speaker will discuss the general components of the modality program and address any recent changes to the requirements. Learning Objectives: To understand the requirements of the ACR MR Accreditation program. The discussion will include accreditation of whole-body general purpose magnets, dedicated extremity systems well as breast MRI accreditation. Anticipated updates to the ACR MRI Quality Control Manual will also be reviewed. To understand the requirements of the ACR CT accreditation program, including updates to the QC manual as well as updates through the FAQ process. To understand the requirements of the ACR nuclear medicine accreditation program, and the role of the physicist in annual equipment surveys and the set up and supervision of the routine QC program. To understand the current ACR MAP Accreditation requirement and present the concepts and structure of the forthcoming ACR Digital Mammography QC Manual and Program.

MO-AB-207-01: ACR Update in CT

Energy Technology Data Exchange (ETDEWEB)

McNitt-Gray, M. [UCLA School of Medicine (United States)

2015-06-15

A goal of an imaging accreditation program is to ensure adequate image quality, verify appropriate staff qualifications, and to assure patient and personnel safety. Currently, more than 35,000 facilities in 10 modalities have been accredited by the American College of Radiology (ACR), making the ACR program one of the most prolific accreditation options in the U.S. In addition, ACR is one of the accepted accreditations required by some state laws, CMS/MIPPA insurance and others. Familiarity with the ACR accreditation process is therefore essential to clinical diagnostic medical physicists. Maintaining sufficient knowledge of the ACR program must include keeping up-to-date as the various modality requirements are refined to better serve the goals of the program and to accommodate newer technologies and practices. This session consists of presentations from authorities in four ACR accreditation modality programs, including magnetic resonance imaging, computed tomography, nuclear medicine, and mammography. Each speaker will discuss the general components of the modality program and address any recent changes to the requirements. Learning Objectives: To understand the requirements of the ACR MR Accreditation program. The discussion will include accreditation of whole-body general purpose magnets, dedicated extremity systems well as breast MRI accreditation. Anticipated updates to the ACR MRI Quality Control Manual will also be reviewed. To understand the requirements of the ACR CT accreditation program, including updates to the QC manual as well as updates through the FAQ process. To understand the requirements of the ACR nuclear medicine accreditation program, and the role of the physicist in annual equipment surveys and the set up and supervision of the routine QC program. To understand the current ACR MAP Accreditation requirement and present the concepts and structure of the forthcoming ACR Digital Mammography QC Manual and Program.

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

Time to rethink: an evidence-based response from pelvic surgeons to the FDA Safety Communication: "UPDATE on Serious Complications Associated with Transvaginal Placement of Surgical Mesh for Pelvic Organ Prolapse".

Science.gov (United States)

Murphy, Miles; Holzberg, Adam; van Raalte, Heather; Kohli, Neeraj; Goldman, Howard B; Lucente, Vincent

2012-01-01

In July of 2011 the U.S. Food and Drug Administration (FDA) released a safety communication entitled "UPDATE on Serious Complications Associated with Transvaginal Placement of Surgical Mesh for Pelvic Organ Prolapse." The stated purpose of this communication is to inform health care providers and patients that serious complications with placement of this mesh are not rare and that it is not clear that these repairs are more effective than nonmesh repair. The comments regarding efficacy are based on a systematic review of the scientific literature from 1996-2011 conducted by the FDA. Our review of the literature during this time yields some different conclusions regarding the safety and efficacy of mesh use in prolapse repair. It may be useful to consider this information prior to making recommendations regarding mesh use in prolapse surgery according to the recent UPDATE.

The nuclear safety case for the replacement research reactor

International Nuclear Information System (INIS)

Willers, A.; Garea, V.

2003-01-01

This paper presents a broad overview of the safety case being used in the licensing of Australia's Replacement Research Reactor. The reactor is a 20 MW pool-type research reactor and is being constructed at the Lucas Heights Science and Technology Centre in Sydney's south. It will be owned and operated by the Australian Nuclear Science and Technology Organisation (ANSTO) and will take over the duties currently performed by HIFAR, a DIDO-type reactor currently operating at the site. The safety case for the RRR considers all aspects of normal operation and anticipated occurrences and will be subject to periodic review and updated in line with evolving methodologies and modifications to plant and procedures. Its scope and degree of detail ensure that the risk posed to members of the public, operators and environment are all adequately low and well in the regulatory limits

NS [Nuclear Safety] update. Current safety and security activities and developments taking place in the Department of Nuclear Safety and Security. Issue no. 3, April 2007

International Nuclear Information System (INIS)

2007-04-01

This newsletter reports on the manual for first responders to a radiological emergency, the IAEA's testing laboratory for radiation measurement, monitoring and protection, which is the first UN laboratory accredited to the international standard ISO17025, and the International Conference on Lessons Learned fro the Decommissioning of Nuclear Facilities and the Safe Termination of Nuclear Activities. The IAEA, in recognition of this critical need, has developed a Manual for First Responders to a Radiological Emergency with the objective to provide practical guidance for those responding within the first few hours of a radiological emergency. This guidance document is co-sponsored by the Comite technique international de prevention et d'extinction du feu (CTIF), the Pan American Health Organization (PAHO) and the World Health Organization (WHO). The Manual for First Responders provides guidance in the form of action guides, instructions, and supporting data that can be easily applied by a State to build a basic capability to respond to a radiological emergency. The guidance also contains practical procedures and tools on the response to a radiological emergency again easily and quickly adaptable by Member States to prepare first responders to respond adequately to a radiological emergency. The Manual can be used for training purposes at the preparedness stage as well as during the response. The Policy and Programme Support Section (PPSS) within the Division of Radiation, Transport and Waste Security (NSRW) has been operating, for many years, a laboratory (the Testing Laboratory) for radiation safety monitoring of individuals and workplaces. The establishment of a quality management system, as required in the International Basic Safety Standards (the BSS), started in 2000 to cover all measurement methods of the laboratory. This system is based on the international standard ISO17025 (General requirements for the competence of testing and calibration laboratories). PPSS

Safety assessment of GM plants: An updated review of the scientific literature.

Science.gov (United States)

Domingo, José L

2016-09-01

In a wide revision of the literature conducted in 2000, I noted that the information in scientific journals on the safety of genetically modified (GM) foods in general, and GM plants in particular, was scarce. Of course, it was not sufficient to guarantee that the consumption of these products should not mean risks for the health of the consumers. Because of the scientific interest in GM organisms (GMOs), as well as the great concern that the consumption of GM foods/plants has raised in a number of countries, I conducted two subsequent revisions (2007 and 2011) on the adverse/toxic effects of GM plants. In the present review, I have updated the information on the potential adverse health effects of GM plants consumed as food and/or feed. With only a few exceptions, the reported studies in the last six years show rather similar conclusions; that is to say, the assessed GM soybeans, rice, corn/maize and wheat would be as safe as the parental species of these plants. However, in spite of the notable increase in the available information, studies on the long-term health effects of GM plants, including tests of mutagenicity, teratogenicity and carcinogenicity seem to be still clearly necessary. Copyright © 2016 Elsevier Ltd. All rights reserved.

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.

New Safety rules

CERN Multimedia

Safety Commission

2008-01-01

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

Safety design analyses of Korea Advanced Liquid Metal Reactor

International Nuclear Information System (INIS)

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

2000-01-01

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

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

FY2017 Updates to the SAS4A/SASSYS-1 Safety Analysis Code

Energy Technology Data Exchange (ETDEWEB)

Fanning, T. H. [Argonne National Lab. (ANL), Argonne, IL (United States)

2017-09-30

The SAS4A/SASSYS-1 safety analysis software is used to perform deterministic analysis of anticipated events as well as design-basis and beyond-design-basis accidents for advanced fast reactors. It plays a central role in the analysis of U.S. DOE conceptual designs, proposed test and demonstration reactors, and in domestic and international collaborations. This report summarizes the code development activities that have taken place during FY2017. Extensions to the void and cladding reactivity feedback models have been implemented, and Control System capabilities have been improved through a new virtual data acquisition system for plant state variables and an additional Block Signal for a variable lag compensator to represent reactivity feedback for novel shutdown devices. Current code development and maintenance needs are also summarized in three key areas: software quality assurance, modeling improvements, and maintenance of related tools. With ongoing support, SAS4A/SASSYS-1 can continue to fulfill its growing role in fast reactor safety analysis and help solidify DOE’s leadership role in fast reactor safety both domestically and in international collaborations.

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.

MO-AB-207-03: ACR Update in Nuclear Medicine

International Nuclear Information System (INIS)

Harkness, B.

2015-01-01

A goal of an imaging accreditation program is to ensure adequate image quality, verify appropriate staff qualifications, and to assure patient and personnel safety. Currently, more than 35,000 facilities in 10 modalities have been accredited by the American College of Radiology (ACR), making the ACR program one of the most prolific accreditation options in the U.S. In addition, ACR is one of the accepted accreditations required by some state laws, CMS/MIPPA insurance and others. Familiarity with the ACR accreditation process is therefore essential to clinical diagnostic medical physicists. Maintaining sufficient knowledge of the ACR program must include keeping up-to-date as the various modality requirements are refined to better serve the goals of the program and to accommodate newer technologies and practices. This session consists of presentations from authorities in four ACR accreditation modality programs, including magnetic resonance imaging, computed tomography, nuclear medicine, and mammography. Each speaker will discuss the general components of the modality program and address any recent changes to the requirements. Learning Objectives: To understand the requirements of the ACR MR Accreditation program. The discussion will include accreditation of whole-body general purpose magnets, dedicated extremity systems well as breast MRI accreditation. Anticipated updates to the ACR MRI Quality Control Manual will also be reviewed. To understand the requirements of the ACR CT accreditation program, including updates to the QC manual as well as updates through the FAQ process. To understand the requirements of the ACR nuclear medicine accreditation program, and the role of the physicist in annual equipment surveys and the set up and supervision of the routine QC program. To understand the current ACR MAP Accreditation requirement and present the concepts and structure of the forthcoming ACR Digital Mammography QC Manual and Program

MO-AB-207-03: ACR Update in Nuclear Medicine

Energy Technology Data Exchange (ETDEWEB)

Harkness, B. [Henry Ford Hospital System (United States)

2015-06-15

A goal of an imaging accreditation program is to ensure adequate image quality, verify appropriate staff qualifications, and to assure patient and personnel safety. Currently, more than 35,000 facilities in 10 modalities have been accredited by the American College of Radiology (ACR), making the ACR program one of the most prolific accreditation options in the U.S. In addition, ACR is one of the accepted accreditations required by some state laws, CMS/MIPPA insurance and others. Familiarity with the ACR accreditation process is therefore essential to clinical diagnostic medical physicists. Maintaining sufficient knowledge of the ACR program must include keeping up-to-date as the various modality requirements are refined to better serve the goals of the program and to accommodate newer technologies and practices. This session consists of presentations from authorities in four ACR accreditation modality programs, including magnetic resonance imaging, computed tomography, nuclear medicine, and mammography. Each speaker will discuss the general components of the modality program and address any recent changes to the requirements. Learning Objectives: To understand the requirements of the ACR MR Accreditation program. The discussion will include accreditation of whole-body general purpose magnets, dedicated extremity systems well as breast MRI accreditation. Anticipated updates to the ACR MRI Quality Control Manual will also be reviewed. To understand the requirements of the ACR CT accreditation program, including updates to the QC manual as well as updates through the FAQ process. To understand the requirements of the ACR nuclear medicine accreditation program, and the role of the physicist in annual equipment surveys and the set up and supervision of the routine QC program. To understand the current ACR MAP Accreditation requirement and present the concepts and structure of the forthcoming ACR Digital Mammography QC Manual and Program.

Safety training: places available in September 2014

CERN Multimedia

HSE Unit

2014-01-01

There are places available in the forthcoming Safety courses. For updates and registrations, please refer to the Safety Training Catalogue (see here).   Please note that there are 7 places left on the “Territorial Safety Officer (TSO) – Initial” course on September 23-25, 2014 (in French).

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

Expert panel on weight loss surgery: executive report update.

Science.gov (United States)

Blackburn, George L; Hutter, Matthew M; Harvey, Alan M; Apovian, Caroline M; Boulton, Hannah R W; Cummings, Susan; Fallon, John A; Greenberg, Isaac; Jiser, Michael E; Jones, Daniel B; Jones, Stephanie B; Kaplan, Lee M; Kelly, John J; Kruger, Rayford S; Lautz, David B; Lenders, Carine M; Lonigro, Robert; Luce, Helen; McNamara, Anne; Mulligan, Ann T; Paasche-Orlow, Michael K; Perna, Frank M; Pratt, Janey S A; Riley, Stancel M; Robinson, Malcolm K; Romanelli, John R; Saltzman, Edward; Schumann, Roman; Shikora, Scott A; Snow, Roger L; Sogg, Stephanie; Sullivan, Mary A; Tarnoff, Michael; Thompson, Christopher C; Wee, Christina C; Ridley, Nancy; Auerbach, John; Hu, Frank B; Kirle, Leslie; Buckley, Rita B; Annas, Catherine L

2009-05-01

Rapid shifts in the demographics and techniques of weight loss surgery (WLS) have led to new issues, new data, new concerns, and new challenges. In 2004, this journal published comprehensive evidence-based guidelines on WLS. In this issue, we've updated those guidelines to assure patient safety in this fast-changing field. WLS involves a uniquely vulnerable population in need of specialized resources and ongoing multidisciplinary care. Timely best-practice updates are required to identify new risks, develop strategies to address them, and optimize treatment. Findings in these reports are based on a comprehensive review of the most current literature on WLS; they directly link patient safety to methods for setting evidence-based guidelines developed from peer-reviewed scientific publications. Among other outcomes, these reports show that WLS reduces chronic disease risk factors, improves health, and confers a survival benefit on those who undergo it. The literature also shows that laparoscopy has displaced open surgery as the predominant approach; that government agencies and insurers only reimburse procedures performed at accredited WLS centers; that best practice care requires close collaboration between members of a multidisciplinary team; and that new and existing facilities require wide-ranging changes to accommodate growing numbers of severely obese patients. More than 100 specialists from across the state of Massachusetts and across the many disciplines involved in WLS came together to develop these new standards. We expect them to have far-reaching effects of the development of health care policy and the practice of WLS.

Conceptual safety design analysis of Korea advanced liquid metal reactor

International Nuclear Information System (INIS)

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

1999-01-01

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

An Online Risk Monitor System (ORMS) to Increase Safety and Security Levels in Industry

International Nuclear Information System (INIS)

Zubair, M; Ur Rahman, Khalil; Ul Hassan, Mehmood

2013-01-01

The main idea of this research is to develop an Online Risk Monitor System (ORMS) based on Living Probabilistic Safety Assessment (LPSA). The article highlights the essential features and functions of ORMS. The basic models and modules such as, Reliability Data Update Model (RDUM), running time update, redundant system unavailability update, Engineered Safety Features (ESF) unavailability update and general system update have been described in this study. ORMS not only provides quantitative analysis but also highlights qualitative aspects of risk measures. ORMS is capable of automatically updating the online risk models and reliability parameters of equipment. ORMS can support in the decision making process of operators and managers in Nuclear Power Plants

An Online Risk Monitor System (ORMS) to Increase Safety and Security Levels in Industry

Science.gov (United States)

Zubair, M.; Rahman, Khalil Ur; Hassan, Mehmood Ul

2013-12-01

The main idea of this research is to develop an Online Risk Monitor System (ORMS) based on Living Probabilistic Safety Assessment (LPSA). The article highlights the essential features and functions of ORMS. The basic models and modules such as, Reliability Data Update Model (RDUM), running time update, redundant system unavailability update, Engineered Safety Features (ESF) unavailability update and general system update have been described in this study. ORMS not only provides quantitative analysis but also highlights qualitative aspects of risk measures. ORMS is capable of automatically updating the online risk models and reliability parameters of equipment. ORMS can support in the decision making process of operators and managers in Nuclear Power Plants.

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)

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

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

Science.gov (United States)

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

2015-06-01

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

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...

Final Report of the NASA Office of Safety and Mission Assurance Agile Benchmarking Team

Science.gov (United States)

Wetherholt, Martha

2016-01-01

To ensure that the NASA Safety and Mission Assurance (SMA) community remains in a position to perform reliable Software Assurance (SA) on NASAs critical software (SW) systems with the software industry rapidly transitioning from waterfall to Agile processes, Terry Wilcutt, Chief, Safety and Mission Assurance, Office of Safety and Mission Assurance (OSMA) established the Agile Benchmarking Team (ABT). The Team's tasks were: 1. Research background literature on current Agile processes, 2. Perform benchmark activities with other organizations that are involved in software Agile processes to determine best practices, 3. Collect information on Agile-developed systems to enable improvements to the current NASA standards and processes to enhance their ability to perform reliable software assurance on NASA Agile-developed systems, 4. Suggest additional guidance and recommendations for updates to those standards and processes, as needed. The ABT's findings and recommendations for software management, engineering and software assurance are addressed herein.

New uses of sulfur - update

Energy Technology Data Exchange (ETDEWEB)

Almond, K.P.

1995-07-01

An update to an extensive bibliography on alternate uses of sulfur was presented. Alberta Sulphur Research Ltd., previously compiled a bibliography in volume 24 of this quarterly bulletin. This update provides an additional 44 new publications. The information regarding current research focusses on topics regarding the use of sulfur in oil and gas applications, mining and metallurgy, concretes and other structural materials, waste management, rubber and textile products, asphalts and other paving and highway applications.

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

Waste Isolation Pilot Plant Safety Analysis Report

International Nuclear Information System (INIS)

1995-11-01

The following provides a summary of the specific issues addressed in this FY-95 Annual Update as they relate to the CH TRU safety bases: Executive Summary; Site Characteristics; Principal Design and Safety Criteria; Facility Design and Operation; Hazards and Accident Analysis; Derivation of Technical Safety Requirements; Radiological and Hazardous Material Protection; Institutional Programs; Quality Assurance; and Decontamination and Decommissioning. The System Design Descriptions'' (SDDS) for the WIPP were reviewed and incorporated into Chapter 3, Principal Design and Safety Criteria and Chapter 4, Facility Design and Operation. This provides the most currently available final engineering design information on waste emplacement operations throughout the disposal phase up to the point of permanent closure. Also, the criteria which define the TRU waste to be accepted for disposal at the WIPP facility were summarized in Chapter 3 based on the WAC for the Waste Isolation Pilot Plant.'' This Safety Analysis Report (SAR) documents the safety analyses that develop and evaluate the adequacy of the Waste Isolation Pilot Plant Contact-Handled Transuranic Wastes (WIPP CH TRU) safety bases necessary to ensure the safety of workers, the public and the environment from the hazards posed by WIPP waste handling and emplacement operations during the disposal phase and hazards associated with the decommissioning and decontamination phase. The analyses of the hazards associated with the long-term (10,000 year) disposal of TRU and TRU mixed waste, and demonstration of compliance with the requirements of 40 CFR 191, Subpart B and 40 CFR 268.6 will be addressed in detail in the WIPP Final Certification Application scheduled for submittal in October 1996 (40 CFR 191) and the No-Migration Variance Petition (40 CFR 268.6) scheduled for submittal in June 1996. Section 5.4, Long-Term Waste Isolation Assessment summarizes the current status of the assessment

Waste Isolation Pilot Plant Safety Analysis Report

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-11-01

The following provides a summary of the specific issues addressed in this FY-95 Annual Update as they relate to the CH TRU safety bases: Executive Summary; Site Characteristics; Principal Design and Safety Criteria; Facility Design and Operation; Hazards and Accident Analysis; Derivation of Technical Safety Requirements; Radiological and Hazardous Material Protection; Institutional Programs; Quality Assurance; and Decontamination and Decommissioning. The System Design Descriptions`` (SDDS) for the WIPP were reviewed and incorporated into Chapter 3, Principal Design and Safety Criteria and Chapter 4, Facility Design and Operation. This provides the most currently available final engineering design information on waste emplacement operations throughout the disposal phase up to the point of permanent closure. Also, the criteria which define the TRU waste to be accepted for disposal at the WIPP facility were summarized in Chapter 3 based on the WAC for the Waste Isolation Pilot Plant.`` This Safety Analysis Report (SAR) documents the safety analyses that develop and evaluate the adequacy of the Waste Isolation Pilot Plant Contact-Handled Transuranic Wastes (WIPP CH TRU) safety bases necessary to ensure the safety of workers, the public and the environment from the hazards posed by WIPP waste handling and emplacement operations during the disposal phase and hazards associated with the decommissioning and decontamination phase. The analyses of the hazards associated with the long-term (10,000 year) disposal of TRU and TRU mixed waste, and demonstration of compliance with the requirements of 40 CFR 191, Subpart B and 40 CFR 268.6 will be addressed in detail in the WIPP Final Certification Application scheduled for submittal in October 1996 (40 CFR 191) and the No-Migration Variance Petition (40 CFR 268.6) scheduled for submittal in June 1996. Section 5.4, Long-Term Waste Isolation Assessment summarizes the current status of the assessment.

Blood safety in the world updated

Institute of Scientific and Technical Information of China (English)

Silvano Wandel

2010-01-01

@@ Blood safety is of paramount importance in any medical context, given that it represents one of the most impor-tant supportive procedures in medicine. Nearly all medical fields that lead with very critical patients will depend on blood products as part of supporting medical strategies (both clinical and surgical). Thus, it is im-portant that every country in the world relies on a well established national blood program.

Probabilistic risk assessment (PRA) update in light of the accident at Fukushima Daiichi Nuclear Power Station - 15461

International Nuclear Information System (INIS)

Maeda, K.; Abe, H.; Hirokawa, N.; Satou, C.

2015-01-01

We have performed internal and external event probabilistic risk assessments (PRA) for boiling water reactor power nuclear plants to identify the important accident sequence groups and to evaluate the effectiveness of the additional severe accident measures, regarding to the new regulatory requirements implemented after the accident at Fukushima Daiichi Nuclear Power Station in Japan in 2011. In addition, we will further update our PRA by extracting problems and improvements from the current PRA, by catching up the state-of-the-art knowledge, modern PRA methodologies in order to contribute voluntarily to safety improvement as well as to comply with regulations. In this document, prior to the extensive PRA updates, we would describe technical contents and qualitative results about PRA updates that have been performed preliminary so far, especially about the external event (seismic) PRA and how to model the additionally deployed severe accident measures (e.g. power supply car, fire engine) so that they can be function external hazards, such as component failure rate of equipment, human reliability 'out of control room', and mission time extension. (authors)

Control of Interference during Working Memory Updating

Science.gov (United States)

Szmalec, Arnaud; Verbruggen, Frederick; Vandierendonck, Andre; Kemps, Eva

2011-01-01

The current study examined the nature of the processes underlying working memory updating. In 4 experiments using the n-back paradigm, the authors demonstrate that continuous updating of items in working memory prevents strong binding of those items to their contexts in working memory, and hence leads to an increased susceptibility to proactive…

The safety of osmotically acting cathartics in colonic cleansing

DEFF Research Database (Denmark)

Nyberg, Caroline; Hendel, J.; Nielsen, O.H.

2010-01-01

Efficient cleansing of the colon before a colonoscopy or a radiological examination is essential. The osmotically acting cathartics (those given the Anatomical Therapeutic Chemical code A06AD) currently used for this purpose comprise products based on three main substances: sodium phosphate...... hyperphosphatemia and irreversible kidney damage owing to acute phosphate nephropathy, have been reported after use of sodium-phosphate-based products. The aim of this Review is to provide an update on the potential safety issues related to the use of osmotically acting cathartics, especially disturbances of renal...

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

A Web-based Alternative Non-animal Method Database for Safety Cosmetic Evaluations.

Science.gov (United States)

Kim, Seung Won; Kim, Bae-Hwan

2016-07-01

Animal testing was used traditionally in the cosmetics industry to confirm product safety, but has begun to be banned; alternative methods to replace animal experiments are either in development, or are being validated, worldwide. Research data related to test substances are critical for developing novel alternative tests. Moreover, safety information on cosmetic materials has neither been collected in a database nor shared among researchers. Therefore, it is imperative to build and share a database of safety information on toxicological mechanisms and pathways collected through in vivo, in vitro, and in silico methods. We developed the CAMSEC database (named after the research team; the Consortium of Alternative Methods for Safety Evaluation of Cosmetics) to fulfill this purpose. On the same website, our aim is to provide updates on current alternative research methods in Korea. The database will not be used directly to conduct safety evaluations, but researchers or regulatory individuals can use it to facilitate their work in formulating safety evaluations for cosmetic materials. We hope this database will help establish new alternative research methods to conduct efficient safety evaluations of cosmetic materials.

Cost update: Technology, safety, and costs of decommissioning reference independent spent fuel storage installations

International Nuclear Information System (INIS)

Miles, T.L.

1994-07-01

The cost estimates originally developed in NUREG/CR-2210 for decommissioning five conceptual Independent Spent Fuel Storage Installations (ISFSIs) and their supporting ancillaries (hot cell and transporter) are updated from 1981 to 1993 dollars. The costs for labor and materials increased approximately at the rate of inflation, the cost of energy increased more slowly than the rate of inflation, and the cost of low-level radioactive waste disposal increased much more rapidly than the rate of inflation. A methodology and a formula are presented for estimating the cost of decommissioning the ISFSIs at some future time, based on these current cost estimates. The formula contains essentially the same elements as the formula given in 10 CFR 50.75 for escalating the decommissioning costs for nuclear power reactors to some future time

MO-AB-201-00: Radiation Safety Officer Update

Energy Technology Data Exchange (ETDEWEB)

NONE

2015-06-15

The role of the Radiation Safety Officer at a medical facility can be complicated. The complexity of the position is based on the breadth of services provided at the institution and the nature of the radioactive materials license. Medical practices are constantly changing and the use of ionizing radiation continues to rise in this area. Some of the newer medical applications involving radiation have unique regulatory and safety issues that must be addressed. Oversight of the uses of radiation start at the local level (radiation safety officer, radiation safety committee) and are heavily impacted by outside agencies (i.e. Nuclear Regulatory Commission, State Radiologic Health, The Joint Commission (TJC), etc). This session will provide both an overview of regulatory oversight and essential compliance practices as well as practical ways to assess and introduce some of the new applications utilizing radioactive materials into your medical facility. Learning Objectives: Regulatory Compliance and Safety with New Radiotherapies: Spheres and Ra-223 (Lance Phillips) Understand the radioactive materials license amendment process to add new radiotherapies (i.e., SIR-Spheres, Therasphere, Xofigo). Understand the AU approval process for microspheres and Xofigo. Examine the training and handling requirements for new procedures. Understand the process involved with protocol development, SOP in order to define roles and responsibilities. The RSO and The RSC: Challenges and Opportunities (Colin Dimock) Understand how to form an effective Committee. Examine what the Committee does for the Program and the RSO. Understand the importance of Committee engagement. Discuss the balance of the complimentary roles of the RSO and the Committee. The Alphabet Soup of Regulatory Compliance: Being Prepared for Inspections (Linda Kroger) Recognize the various regulatory bodies and organizations with oversight or impact in Nuclear Medicine, Radiology and Radiation Oncology. Examine 10CFR35

MO-AB-201-00: Radiation Safety Officer Update

International Nuclear Information System (INIS)

2015-01-01

The role of the Radiation Safety Officer at a medical facility can be complicated. The complexity of the position is based on the breadth of services provided at the institution and the nature of the radioactive materials license. Medical practices are constantly changing and the use of ionizing radiation continues to rise in this area. Some of the newer medical applications involving radiation have unique regulatory and safety issues that must be addressed. Oversight of the uses of radiation start at the local level (radiation safety officer, radiation safety committee) and are heavily impacted by outside agencies (i.e. Nuclear Regulatory Commission, State Radiologic Health, The Joint Commission (TJC), etc). This session will provide both an overview of regulatory oversight and essential compliance practices as well as practical ways to assess and introduce some of the new applications utilizing radioactive materials into your medical facility. Learning Objectives: Regulatory Compliance and Safety with New Radiotherapies: Spheres and Ra-223 (Lance Phillips) Understand the radioactive materials license amendment process to add new radiotherapies (i.e., SIR-Spheres, Therasphere, Xofigo). Understand the AU approval process for microspheres and Xofigo. Examine the training and handling requirements for new procedures. Understand the process involved with protocol development, SOP in order to define roles and responsibilities. The RSO and The RSC: Challenges and Opportunities (Colin Dimock) Understand how to form an effective Committee. Examine what the Committee does for the Program and the RSO. Understand the importance of Committee engagement. Discuss the balance of the complimentary roles of the RSO and the Committee. The Alphabet Soup of Regulatory Compliance: Being Prepared for Inspections (Linda Kroger) Recognize the various regulatory bodies and organizations with oversight or impact in Nuclear Medicine, Radiology and Radiation Oncology. Examine 10CFR35

75 FR 13807 - Pipeline Safety: Information Collection Activities

Science.gov (United States)

2010-03-23

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

Supplementary safety system 1/4 scale testing

Energy Technology Data Exchange (ETDEWEB)

Garrett, R.L.; Paik, I.K.

1993-09-01

During the course of updating the K-Reactor Safety Analysis Report Chapter 15 in 1990, it was identified that the current Supplementary Safety System (SSS) may not be adequate in protecting the reactor during the process water pump coastdown initiated by a loss of AC power when the safety rods are assumed to fail. A SSS modification project was initiated to add an additional ink injection pathway near the pump suction. In addition, the Department of Energy raised a question on the thermal buoyancy effects on moderator flow pattern and ink dispersion in the moderator space. The development and documentation of a two-dimensional code called MODFLOW was undertaken to describe the problem. This report discusses the results of the moderator flow and ink (Gadolinium Poison Solution - GPS) dispersion tests designed to provide qualified data for validation and benchmarking of the MODFLOW computer code with the secondary objectives being the development of concentration profiles and video footage of simulated GPS dispersion under steady-state and transient flow conditions.

Performance of dynamic safety barriers-Structuring, modelling and visualization

OpenAIRE

Wikdahl, Olga

2014-01-01

The main objective of this master thesis is to discuss performance of dynamic safety barriers. A comprehensive literature review is performed in order to get understanding what dynamic safety barrier is. Three different concepts of dynamic safety barriers based on various meanings of dynamic were derived from the literature review: - dynamic safety barriers related to motion or physical force - dynamic safety barriers as updated barriers from dynamic risk analysis - dynamic safety ...

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)

IAEA safety glossary. Terminology used in nuclear safety and radiation protection, multilingual 2007 edition, including the IAEA safety fundamentals [no. SF-1

International Nuclear Information System (INIS)

2008-10-01

The IAEA Safety Glossary defines and explains technical terms used in the IAEA Safety Standards and other safety related IAEA publications, and provides information on their usage.The publication is multilingual and covers the six official IAEA languages,, Arabic, Chinese, English, French, Russian and Spanish. It has been in use since April 2000. The 2007 Edition is a revised and updated version. The primary purpose of the publication is to harmonize terminology and usage in the IAEA Safety Standards. It is a source of information for users of the IAEA Safety Standards and other safety related IAEA publications and provides guidance for the drafters and reviewers of publications, including IAEA technical officers and consultants, and members of technical committees, advisory groups, working groups and bodies for the endorsement of safety standards

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.

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

76 FR 70885 - Updating Fire Safety Standards

Science.gov (United States)

2011-11-16

... effect on the economy of $100 million or more or adversely affect in a material way the economy, a sector of the economy, productivity, competition, jobs, the environment, public health or safety, or State...; 64.018, Sharing Specialized Medical Resources; 64.019, Veterans Rehabilitation Alcohol and Drug...

OVERVIEW OF MODULAR HTGR SAFETY CHARACTERIZATION AND POSTULATED ACCIDENT BEHAVIOR LICENSING STRATEGY

Energy Technology Data Exchange (ETDEWEB)

Ball, Sydney J [ORNL

2014-06-01

This report provides an update on modular high-temperature gas-cooled reactor (HTGR) accident analyses and risk assessments. One objective of this report is to improve the characterization of the safety case to better meet current regulatory practice, which is commonly geared to address features of today s light water reactors (LWRs). The approach makes use of surrogates for accident prevention and mitigation to make comparisons with LWRs. The safety related design features of modular HTGRs are described, along with the means for rigorously characterizing accident selection and progression methodologies. Approaches commonly used in the United States and elsewhere are described, along with detailed descriptions and comments on design basis (and beyond) postulated accident sequences.

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.

IEA-NEA Nuclear Technology Road-map Update - Asia Stakeholder Engagement Workshop

International Nuclear Information System (INIS)

Tam, Cecilia; ); Paillere, Henri; ); Guoxing, Gu; Tianmin, Xin; Autebert, Remy; Murphy, Paul; Barkatullah, Nadira; Nkong-Njock, Vincent; Dubinsky, Melissa; Cordero, Didier

2014-01-01

In 2010, the International Energy Agency (IEA) and the Nuclear Energy Agency (NEA) released a Nuclear Energy Technology Road-map which outlined the steps needed to accelerate the development of nuclear power and its role in achieve deep greenhouse-gas emissions reduction. Both the global energy sector and the outlook for nuclear have changed significantly since then and an update of this Road-map is currently underway. The IEA and NEA held a stakeholder dialogue meeting focused on nuclear develop in Asia on 25 February 2014 in Hong Kong. The meeting brought together key stakeholders from industry, government, finance and other relevant organisations from Asia and beyond to help define and prioritise key items to be discussed in the IEA/NEA's Nuclear Road-map Update. One of the expected outcomes of this intensive brainstorming and Road-map development session was to discus key targets, milestones, policy measures and other actions needed to support the development and deployment of nuclear power. The workshop was organized in 3 sessions dealing with: Session 1 - Technology development needs for nuclear (Reactor technology, Fuel cycle and decommissioning); Session 2 - Breakout Discussion: - Group I: Financing nuclear. This session focussed on today's reality for financing nuclear and the current economics of nuclear. Mechanisms such as government loan guarantees, vendor financing and role of export credit agencies were discussed. Participants were asked to share lessons learnt and current practices on financing nuclear as well as recommendations (if needed) for additional policy support or changes in technology development (e.g. SMR) which would facilitate greater deployment of nuclear technologies. - Group II: Nuclear regulation and safety. This session focussed on regulatory needs for enhanced security and regulation for new build programmes, institutional development requirements for new nuclear countries. Safety research following the Fukushima Daiichi accident

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

Psychometrics of the AAN Caregiver Driving Safety Questionnaire and contributors to caregiver concern about driving safety in older adults.

Science.gov (United States)

Carvalho, Janessa O; Springate, Beth; Bernier, Rachel A; Davis, Jennifer

2018-03-01

ABSTRACTBackground:The American Academy of Neurology (AAN) updated their practice parameters in the evaluation of driving risk in dementia and developed a Caregiver Driving Safety Questionnaire, detailed in their original manuscript (Iverson Gronseth, Reger, Classen, Dubinsky, & Rizzo, 2010). They described four factors associated with decreased driving ability in dementia patients: history of crashes or citations, informant-reported concerns, reduced mileage, and aggressive driving. An informant-reported AAN Caregiver Driving Safety Questionnaire was designed with these elements, and the current study was the first to explore the factor structure of this questionnaire. Additionally, we examined associations between these factors and cognitive and behavioral measures in patients with mild cognitive impairment or early Alzheimer's disease and their informants. Exploratory factor analysis revealed a four-component structure, consistent with the theory behind the AAN scale composition. These four factor scores also were significantly associated with performance on cognitive screening instruments and informant reported behavioral dysfunction. Regressions revealed that behavioral dysfunction predicted caregiver concerns about driving safety beyond objective patient cognitive dysfunction. In this first known quantitative exploration of the scale, our results support continued use of this scale in office driving safety assessments. Additionally, patient behavioral changes predicted caregiver concerns about driving safety over and above cognitive status, which suggests that caregivers may benefit from psychoeducation about cognitive factors that may negatively impact driving safety.

An update on the safety of nutraceuticals and effects on lipid parameters.

Science.gov (United States)

Cicero, Arrigo F G; Colletti, Alessandro

2018-03-01

Cardiovascular diseases (CVDs) are the leading cause of mortality and disability in developed countries, whereas a large portion of patients in primary prevention have uncontrolled level of CVD risk factors. Dietary supplementation with bioactive natural compounds with demonstrated lipid-lowering effects is currently supported by the international guidelines for CVD prevention and some international expert panels. Areas covered: This review provides insights on issues concerning the tolerability and safety of the most commonly used nutraceuticals with demonstrated lipid-lowering effect in humans. They will be then divided into three main categories according to their mechanism of action (cholesterol synthesis inhibitors, intestinal cholesterol absorption inhibitors, and LDL-C excretion stimulants) and their pharmacological profile will be discussed. Expert opinion: A growing body of preclinical, epidemiological and clinical evidence has defined the tolerability and safety profile of the most commonly used lipid-lowering nutraceuticals. In the most part of cases, the side effects are mild and reversible. However, detailed knowledge of specific health risks and pharmacological interactions for each individual compound is needed for the management of frail patients, such as children, elderly, patients with liver or renal failure, and patients consuming numerous drugs.

Animal Cloning and Food Safety

Science.gov (United States)

... Products For Consumers Home For Consumers Consumer Updates Animal Cloning and Food Safety Share Tweet Linkedin Pin ... safe to eat as food from conventionally bred animals. This conclusion stems from an extensive study of ...

New Brunswick Power Nuclear Corporation update 2005

International Nuclear Information System (INIS)

White, R.M.; Eagles, E.R.; Pilkington, W.S.

2005-01-01

A brief presentation will be made on the operations and business activities over the previous year with a discussion of the current status of the NB Power group of companies. The New Brunswick Government has implemented the new 'Electricity Act' which has resulted restructuring of NB Power, opening of the electricity market to wholesale completion and the separation of the transmission system operation from NB Power. On October 1, 2005 the restructuring of NB Power was implemented to change NB Power from a single integrated utility into NB Power Holding Corporation with four subsidiary operating companies including NB Power Nuclear Corporation, NB Power Distribution and Customer Service Corporation, NB Power Transmission Corporation and NB Power Generation Corporation. As part of the Electricity Act, the transmission system reliability, operation and market control functions have been moved into a separate company, the NB System Operator, outside of the NB Power group of companies. A review of Point Lepreau's operational activities will include presentation of the capacity factor, availability and safety results with a summary of significant issues, planned outages and unplanned outages. An update on the current status of Power Reactor Operating License renewal and the strategies for renewal timing will be presented. Planning for refurbishment has continued with a major focus on addressing the recommendations made by Dr. Robin Jeffrey in his report to the Province of New Brunswick. These recommendations included three options for replacement of the Point Lepreau capacity and energy; 1) improve refurbishment contract arrangements with AECL, 2) solicit external investment in refurbishment and the station and 3) update the case for fossil fuel alternatives. The NB Power Holding Corporation Board of Directors have provided the appropriate information on the options to the owner (Province of New Brunswick) for consideration. A decision on the future of the Point Lepreau

Safety stock placement in supply chains with demand forecast updates

Directory of Open Access Journals (Sweden)

Youssef Boulaksil

2016-01-01

Full Text Available Supply chains are exposed to many types of risks and it may not be obvious where to keep safety stocks in the supply chain to hedge against those risks, while maintaining a high customer service level. In this paper, we develop an approach to determine the safety stock levels in supply chain systems that face demand uncertainty. We model customer demand following the Martingale Model of Forecast Evolution (MMFE. An extensive body of literature discusses the safety stock placement problem in supply chains, but most studies assume independent and identically distributed demand. Our approach is based on a simulation study in which mathematical models are solved in a rolling horizon setting. It allows determining the safety stock levels at each stage of the supply chain. Based on a numerical study, we find that a big portion of the safety stocks should be placed downstream in the supply chain to achieve a high customer service level.

Using Multi-Viewpoint Contracts for Negotiation of Embedded Software Updates

Directory of Open Access Journals (Sweden)

Sönke Holthusen

2016-05-01

Full Text Available In this paper we address the issue of change after deployment in safety-critical embedded system applications. Our goal is to substitute lab-based verification with in-field formal analysis to determine whether an update may be safely applied. This is challenging because it requires an automated process able to handle multiple viewpoints such as functional correctness, timing, etc. For this purpose, we propose an original methodology for contract-based negotiation of software updates. The use of contracts allows us to cleanly split the verification effort between the lab and the field. In addition, we show how to rely on existing viewpoint-specific methods for update negotiation. We illustrate our approach on a concrete example inspired by the automotive domain.

Updated concepts on the pathophysiology and the clinical management of trauma hemorrhage and coagulopathy

Directory of Open Access Journals (Sweden)

Marc Maegele

2017-06-01

Full Text Available Uncontrolled hemorrhage and subsequent trauma-induced coagulopathy (TIC are still the principle causes for preventable death after trauma and early detection and aggressive management have been associated with reduced mortality. Despite increasing knowledge about trauma resuscitation, best practice to treat this newly defined entity is still under debate. A synopsis of best current knowledge with reference to the updated European trauma guideline on the management of severe trauma hemorrhage and TIC is presented. The implementation of evidence-based local protocols and algorithms including clinical quality and safety management systems together with parameters to assess key measures of bleeding control and outcome is advocated.

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

Science.gov (United States)

Becker, Robert E

2016-01-11

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

Safety Awareness & Communications Internship

Science.gov (United States)

Jefferson, Zanani

2015-01-01

The projects that I have worked on during my internships were updating the JSC Safety & Health Action Team JSAT Employee Guidebook, conducting a JSC mishap case study, preparing for JSC Today Close Call success stories, and assisting with event planning and awareness.

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.)

Cardiovascular Update: Risk, Guidelines, and Recommendations.

Science.gov (United States)

Pearson, Tamera

2015-09-01

This article provides an update of the current status of cardiovascular disease (CVD) in the United States, including a brief review of the underlying pathophysiology and epidemiology. This article presents a discussion of the latest American Heart Association guidelines that introduce the concept of promoting ideal cardiovascular health, defined by seven identified metrics. Specific CVD risk factors and utilization of the 10-year CVD event prediction calculator are discussed. In addition, current management recommendations of health-related conditions that increase risk for CVD, such as hypertension and hypercholesterolemia, are provided. Finally, a discussion of detailed evidence-based lifestyle recommendations to promote cardiovascular health and reduce CVD risks concludes the update. © 2015 The Author(s).

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)

77 FR 71089 - Pilot Loading of Aeronautical Database Updates

Science.gov (United States)

2012-11-29

...) card, rather than in resident memory. The database update was accomplished by removing the SD card with... frequency distance measuring equipment (DME), and any updates that affect system operating software--that... developed with attention to data integrity. Current technology uses databases which are developed in...

Setting the standard: The IAEA safety standards set the global reference

International Nuclear Information System (INIS)

Williams, L.

2003-01-01

For the IAEA, setting and promoting standards for nuclear radiation, waste, and transport safety have been priorities from the start, rooted in the Agency's 1957 Statute. Today, a corpus of international standards are in place that national regulators and industries in many countries are applying, and more are being encouraged and assisted to follow them. Considerable work is done to keep safety standards updated and authoritative. They cover five main areas: the safety of nuclear facilities; radiation protection and safety of radiation sources; safe management of radioactive waste; safe transport of radioactive material; and thematic safety areas, such as emergency preparedness or legal infrastructures. Overall, the safety standards reflect an international consensus on what constitutes a high level of safety for protecting people and the environment. All IAEA Member States can nominate experts for the Agency standards committees and provide comments on draft standards. Through this ongoing cycle of review and feedback, the standards are refined, updated, and extended where needed

Current Activities on Nuclear Safety Culture in Korea. How to meet the challenges for Safety and Safety Culture?

Energy Technology Data Exchange (ETDEWEB)

Oh, Chaewoon [International Policy Department Policy and Standard Division, Korea Institute of Nuclear Safety, 19 Gusung-Dong Yuseong-Ku, 305-338 DAEJEON (Korea, Republic of)

2008-07-01

'Statement of Nuclear Safety Policy' declared by the Korean Government elucidates adherence to the principle of 'priority to safety'. The 3. Comprehensive Nuclear Energy Promotion Plan (2007-2011) more specifically addressed the necessity to develop and apply 'safety culture evaluation criteria' and to strengthen safety management of concerned organizations in an autonomous way. Putting these policies as a backdrop, Korean Government has taken diverse safety culture initiatives and has encouraged the relevant organizations to develop safety culture practices of their own accord. Accordingly, KHNP, the operating organization in Korea, developed a 'safety culture performance indicator', which has been used to evaluate safety mind of employees and the evaluation results have been continuously reflected in operational management and training programs. Furthermore, KHNP inserted 'nuclear safety culture subject' into every course of more than two week length, and provided employees with special lectures on safety culture. KINS, the regulatory organization, developed indicators for the safety culture evaluation based on the IAEA Guidelines. Also, KINS has hosted an annual Nuclear Safety Technology Information Meeting to share information between regulatory organizations and industries. Furthermore, KINS provided a nuclear safety culture class to the new employees and they are given a chance to participate in performance of a role-reversal socio-drama. Additionally, KINS developed a safety culture training program, published training materials and conducted a 'Nuclear Safety Culture Basic Course' in October 2007, 4 times of which are planed this year. In conclusion, from Government to relevant organizations, 'nuclear safety culture' concept is embraced as important and has been put into practice on a variety of forms. Specifically, 'education and training' is a starting line and sharing

Domestic Regulation for Periodic Safety Review of Nuclear Power Plants

International Nuclear Information System (INIS)

Kim, Daesik; Ahn, Seunghoon; Auh, Geunsun; Lee, Jonghyeok

2015-01-01

The so-called Periodic Safety Review (PSR) has been carried out such safety assessment throughout its life, on a periodic basis. In January 2001, the Atomic Energy Act and related regulations were amended to adopt the PSR institutional scheme from IAEA Nuclear Safety Guide 50-SG-O12. At that time the safety assessment was made to review the plant safety on 10 safety factors, such as aging management and emergency planning, where the safety factor indicates the important aspects of safety of an operating NPP to be addressed in the PSR. According to this legislation, the domestic utility, the KHNP has conducted the PSR for the operating NPP of 10 years coming up from operating license date, starting since May 2000. Some revisions in the PSR rule were made to include the additional safety factors last year. This paper introduces the current status of the PSR review and regulation, in particular new safety factors and updated technical regulation. Comprehensive safety assessment for Korea Nuclear Power Plants have performed a reflecting design and procedure changes and considering the latest technology every 10 years. This paper also examined the PSR system changes in Korea. As of July 2015, reviews for PSR of 18 units have been completed, with 229 nuclear safety improvement items. And implementation have been completed for 165 of them. PSR system has been confirmed that it has contributed to improvement of plant safety. In addition, this paper examined the PSR system change in Korea

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

Safety analysis reports. Current status (third key report)

International Nuclear Information System (INIS)

1999-01-01

A review of Ukrainian regulations and laws concerned with Nuclear power and radiation safety is presented with an overview of the requirements for the Safety Analysis Report Contents. Status of Safety Analysis Reports (SAR) is listed for each particular Ukrainian NPP including SAR development schedules. Organisational scheme of SAR development works includes: general technical co-ordination on Safety Analysis Report development; list of leading organisations and utilization of technical support within international projects

Cataract surgery in patients with pseudoexfoliation syndrome: current updates

Directory of Open Access Journals (Sweden)

Fontana L

2017-07-01

Full Text Available Luigi Fontana, Marco Coassin, Alfonso Iovieno, Antonio Moramarco, Luca Cimino Ophthalmology Unit, Arcispedale Santa Maria Nuova – IRCCS, Reggio Emilia, Italy Abstract: Pseudoexfoliation is a ubiquitous syndrome of multifactorial origin affecting elderly people by increasing the risk of cataract and secondary glaucoma development. Despite modern techniques and technologies for cataract surgery, pseudoexfoliation syndrome represents a challenge for surgeons because of the increased weakness of the zonular apparatus and limited pupil dilation. Due to the inherent difficulties during surgery, the risk of vitreous loss in these patients is several times higher than in cataract patients without pseudoexfoliation. Using currently available surgical devices (ophthalmic viscosurgical device, iris retractors and ring dilators, capsular tension ring, etc., the risk of intraoperative complications may be much reduced, allowing the surgeon to handle difficult cases with greater confidence and safety. This review analyzes the methodologic approach to the patient with zonular laxity with the aim of providing useful advices to limit the risks of intraoperative and postoperative complications. From the preoperative planning, to the intraoperative management of the small pupil and phacodonesis, and to the postoperative correction of capsule phimosis and intraocular lens dislocation, a step approach to the surgical management of pseudoexfoliation patients is illustrated. Keywords: pseudoexfoliation syndrome, cataract surgery, zonular laxity, intraocular lens implant, complications

Development of a safety case for the use of current limiting devices to manage short circuit currents on electrical distribution networks. Final report

Energy Technology Data Exchange (ETDEWEB)

NONE

2004-07-01

The original objective of this study was to review the safety issues associated with the use of current limiting devices and to write a risk assessment in accordance with good practice. But, when legislative procedures became apparent, the scope was changed to include involvement with the HSE, the DTI and Ofgem. It turned out that it would have been very difficult to write a safety case that would satisfy all of the agencies, or a risk assessment that would cover all applications. The scope of the study was therefore changed to focus on how the existing barriers should be tackled and the implications of the existing legislation. The approach to the study is described; it included reviews of background information and literature, questionnaires to manufacturers, a review of the reliability and hazards of the devices, and a review of UK safety legislation. The Final Report describes all this and includes discussion on the consequences of failure of fault current limiting devices, control measures which could be used to minimise risk, and recommendations for a way forward.

Quality assurance for software important to safety

International Nuclear Information System (INIS)

2000-01-01

Software applications play an increasingly relevant role in nuclear power plant systems. This is particularly true of software important to safety used in both: calculations for the design, testing and analysis of nuclear reactor systems (design, engineering and analysis software); and monitoring, control and safety functions as an integral part of the reactor systems (monitoring, control and safety system software). Computer technology is advancing at a fast pace, offering new possibilities in nuclear reactor design, construction, commissioning, operation, maintenance and decommissioning. These advances also present new issues which must be considered both by the utility and by the regulatory organization. Refurbishment of ageing instrumentation and control systems in nuclear power plants and new safety related application areas have emerged, with direct (e.g. interfaces with safety systems) and indirect (e.g. operator intervention) implications for safety. Currently, there exist several international standards and guides on quality assurance for software important to safety. However, none of the existing documents provides comprehensive guidance to the developer, manager and regulator during all phases of the software life-cycle. The present publication was developed taking into account the large amount of available documentation, the rapid development of software systems and the need for updated guidance on h ow to do it . It provides information and guidance for defining and implementing quality assurance programmes covering the entire life-cycle of software important to safety. Expected users are managers, performers and assessors from nuclear utilities, regulatory bodies, suppliers and technical support organizations involved with the development and use of software applied in nuclear power plants

Updating systematic reviews: an international survey.

Directory of Open Access Journals (Sweden)

Chantelle Garritty

Full Text Available BACKGROUND: Systematic reviews (SRs should be up to date to maintain their importance in informing healthcare policy and practice. However, little guidance is available about when and how to update SRs. Moreover, the updating policies and practices of organizations that commission or produce SRs are unclear. METHODOLOGY/PRINCIPAL FINDINGS: The objective was to describe the updating practices and policies of agencies that sponsor or conduct SRs. An Internet-based survey was administered to a purposive non-random sample of 195 healthcare organizations within the international SR community. Survey results were analyzed using descriptive statistics. The completed response rate was 58% (n = 114 from across 26 countries with 70% (75/107 of participants identified as producers of SRs. Among responders, 79% (84/107 characterized the importance of updating as high or very-high and 57% (60/106 of organizations reported to have a formal policy for updating. However, only 29% (35/106 of organizations made reference to a written policy document. Several groups (62/105; 59% reported updating practices as irregular, and over half (53/103 of organizational respondents estimated that more than 50% of their respective SRs were likely out of date. Authors of the original SR (42/106; 40% were most often deemed responsible for ensuring SRs were current. Barriers to updating included resource constraints, reviewer motivation, lack of academic credit, and limited publishing formats. Most respondents (70/100; 70% indicated that they supported centralization of updating efforts across institutions or agencies. Furthermore, 84% (83/99 of respondents indicated they favoured the development of a central registry of SRs, analogous to efforts within the clinical trials community. CONCLUSIONS/SIGNIFICANCE: Most organizations that sponsor and/or carry out SRs consider updating important. Despite this recognition, updating practices are not regular, and many organizations lack

Application of the Dragon reactor experiment to the safety evaluation of current HTR systems

International Nuclear Information System (INIS)

Ashworth, F.P.O.; Faircloth, R.L.

1976-01-01

An important component of the confidence required for the safety assessment of high-temperature reactors is the experimental proof of phenomena such as fission product release or core corrosion. The most convincing experiments are those carried out in a reactor. This paper outlines the scope of experiments relevant to safety which can be done in the Dragon Reactor Experiment and describes as an example the experimental campaign and the current outcome of the work on validating the predictions of caesium release and migration. (author)

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

Comparative analysis of safety related site characteristics

International Nuclear Information System (INIS)

Andersson, Johan

2010-12-01

This document presents a comparative analysis of site characteristics related to long-term safety for the two candidate sites for a final repository for spent nuclear fuel in Forsmark (municipality of Oesthammar) and in Laxemar (municipality of Oskarshamn) from the point of view of site selection. The analyses are based on the updated site descriptions of Forsmark /SKB 2008a/ and Laxemar /SKB 2009a/, together with associated updated repository layouts and designs /SKB 2008b and SKB 2009b/. The basis for the comparison is thus two equally and thoroughly assessed sites. However, the analyses presented here are focussed on differences between the sites rather than evaluating them in absolute terms. The document serves as a basis for the site selection, from the perspective of long-term safety, in SKB's application for a final repository. A full evaluation of safety is made for a repository at the selected site in the safety assessment SR-Site /SKB 2011/, referred to as SR-Site main report in the following

Comparative analysis of safety related site characteristics

Energy Technology Data Exchange (ETDEWEB)

Andersson, Johan (ed.)

2010-12-15

This document presents a comparative analysis of site characteristics related to long-term safety for the two candidate sites for a final repository for spent nuclear fuel in Forsmark (municipality of Oesthammar) and in Laxemar (municipality of Oskarshamn) from the point of view of site selection. The analyses are based on the updated site descriptions of Forsmark /SKB 2008a/ and Laxemar /SKB 2009a/, together with associated updated repository layouts and designs /SKB 2008b and SKB 2009b/. The basis for the comparison is thus two equally and thoroughly assessed sites. However, the analyses presented here are focussed on differences between the sites rather than evaluating them in absolute terms. The document serves as a basis for the site selection, from the perspective of long-term safety, in SKB's application for a final repository. A full evaluation of safety is made for a repository at the selected site in the safety assessment SR-Site /SKB 2011/, referred to as SR-Site main report in the following

An updated checklist of the Culicidae (Diptera) of Morocco, with notes on species of historical and current medical importance.

Science.gov (United States)

Trari, Bouchra; Dakki, Mohamed; Harbach, Ralph E

2017-06-01

An updated checklist of the mosquito species (Diptera: Culicidae) recorded in Morocco from 1916 to 2016 is provided, including synonyms and synonymous usage for each species. Forty-three species belonging to seven genera are recorded so far: Anopheles (9), Aedes (12) Coquillettidia (2), Culex (12), Culiseta (5), Orthopodomyia (1) and Uranotaenia (2). Traditional and equivalent names in the polyphyletic concept of Aedes are provided for the aedine species. The historical importance and current potential threat of mosquitoes to human health in Morocco is reviewed. © 2017 The Society for Vector Ecology.

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.

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)

Energy Storage System Safety: Plan Review and Inspection Checklist

Energy Technology Data Exchange (ETDEWEB)

Cole, Pam C (PNNL); Conover, David R (PNNL)

2017-03-01

Codes, standards, and regulations (CSR) governing the design, construction, installation, commissioning, and operation of the built environment are intended to protect the public health, safety, and welfare. While these documents change over time to address new technology and new safety challenges, there is generally some lag time between the introduction of a technology into the market and the time it is specifically covered in model codes and standards developed in the voluntary sector. After their development, there is also a timeframe of at least a year or two until the codes and standards are adopted. Until existing model codes and standards are updated or new ones are developed and then adopted, one seeking to deploy energy storage technologies or needing to verify the safety of an installation may be challenged in trying to apply currently implemented CSRs to an energy storage system (ESS). The Energy Storage System Guide for Compliance with Safety Codes and Standards1 (CG), developed in June 2016, is intended to help address the acceptability of the design and construction of stationary ESSs, their component parts, and the siting, installation, commissioning, operations, maintenance, and repair/renovation of ESS within the built environment.

Los Alamos Climatology 2016 Update

Energy Technology Data Exchange (ETDEWEB)

Bruggeman, David Alan [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2017-02-10

The Los Alamos National Laboratory (LANL or the Laboratory) operates a meteorology monitoring network to support LANL emergency response, engineering designs, environmental compliance, environmental assessments, safety evaluations, weather forecasting, environmental monitoring, research programs, and environmental restoration. Weather data has been collected in Los Alamos since 1910. Bowen (1990) provided climate statistics (temperature and precipitation) for the 1961– 1990 averaging period, and included other analyses (e.g., wind and relative humidity) based on the available station locations and time periods. This report provides an update to the 1990 publication Los Alamos Climatology (Bowen 1990).

Safety inspections to TRIGA reactors

International Nuclear Information System (INIS)

Byszewski, W.

1988-01-01

The operational safety advisory programme was created to provide useful assistance and advice from an international perspective to research reactor operators and regulators on how to enhance operational safety and radiation protection on their reactors. Safety missions cover not only the operational safety of reactors themselves, but also the safety of associated experimental loops, isotope laboratories and other experimental facilities. Safety missions are also performed on request in other Member States which are interested in receiving impartial advice and assistance in order to enhance the safety of research reactors. The results of the inspections have shown that in some countries there are problems with radiation protection practices and nuclear safety. Very often the Safety Analysis Report is not updated, regulatory supervision needs clarification and improvement, maintenance procedures should be more formalised and records and reports are not maintained properly. In many cases population density around the facility has increased affecting the validity of the original safety analysis

Training Presentation for NASA Civil Helicopter Safety Website

Science.gov (United States)

Iseler, Laura

2002-01-01

NASA civil helicopter safety News & Updates include the following: Mar. 2002. The Air Medical Operations Survey has been completed! Check it out! Also accessible via the Mission pages under Air Medical Mission. Air Medical and Law Enforcement Mission pages have been added. They are accessible via the Mission pages. The Public Use, Personal, Offshore, Law Enforcement, External Load, Business and Gyro accident pages (accessable via the Mission page) have been updated. Feb. 2002. A Words of Wisdom section has been added. You can access it by clicking the Library button. A link to a Corporate Accident Response Plan has been added to the Accident page. The AMs, Aerial Application and Instruction accident pages (accessable via the Mission page) have been updated. Jan. 2002. A new searchable safety article database has been added. You can access it by clicking the Library button. The 2001 accident summaries have been updated and the statistics have been compiled - check it out by clicking the accident tab to the left. Dec. 2001. Please read the FAA Administrator's memo regarding the latest FBI warning. 3ee the FAA column - Fall 2001 Read it now!

Food Safety: MedlinePlus Health Topic

Science.gov (United States)

... Food and Drug Administration) Also in Spanish Animal Cloning and Food Safety (Food and Drug Administration) Chemicals ... Bethesda, MD 20894 U.S. Department of Health and Human Services National Institutes of Health Page last updated ...

Updating radiation protection regulations in Egypt

International Nuclear Information System (INIS)

Gomaa, M.A.; El-Naggar, A.M.

1996-01-01

The aim of this treatise is to present -the rational steps taken in the process of updating the Radiation Protection Regulations in Egypt. The contents of the review will include a historical synopsis, and the current state of art regarding competent authorities. Furthermore, the various committees formed with responsibilities for specific issues are indicated, including the role of the Ministry of Health (MOH), and that of the Atomic Energy Authority (AEA). Finally, the efforts made towards updating the radiation Protection Regulations in Egypt are highlighted. (author)

CANISTER HANDLING FACILITY CRITICALITY SAFETY CALCULATIONS

International Nuclear Information System (INIS)

C.E. Sanders

2005-01-01

This design calculation revises and updates the previous criticality evaluation for the canister handling, transfer and staging operations to be performed in the Canister Handling Facility (CHF) documented in BSC [Bechtel SAIC Company] 2004 [DIRS 167614]. The purpose of the calculation is to demonstrate that the handling operations of canisters performed in the CHF meet the nuclear criticality safety design criteria specified in the ''Project Design Criteria (PDC) Document'' (BSC 2004 [DIRS 171599], Section 4.9.2.2), the nuclear facility safety requirement in ''Project Requirements Document'' (Canori and Leitner 2003 [DIRS 166275], p. 4-206), the functional/operational nuclear safety requirement in the ''Project Functional and Operational Requirements'' document (Curry 2004 [DIRS 170557], p. 75), and the functional nuclear criticality safety requirements described in the ''Canister Handling Facility Description Document'' (BSC 2004 [DIRS 168992], Sections 3.1.1.3.4.13 and 3.2.3). Specific scope of work contained in this activity consists of updating the Category 1 and 2 event sequence evaluations as identified in the ''Categorization of Event Sequences for License Application'' (BSC 2004 [DIRS 167268], Section 7). The CHF is limited in throughput capacity to handling sealed U.S. Department of Energy (DOE) spent nuclear fuel (SNF) and high-level radioactive waste (HLW) canisters, defense high-level radioactive waste (DHLW), naval canisters, multicanister overpacks (MCOs), vertical dual-purpose canisters (DPCs), and multipurpose canisters (MPCs) (if and when they become available) (BSC 2004 [DIRS 168992], p. 1-1). It should be noted that the design and safety analyses of the naval canisters are the responsibility of the U.S. Department of the Navy (Naval Nuclear Propulsion Program) and will not be included in this document. In addition, this calculation is valid for the current design of the CHF and may not reflect the ongoing design evolution of the facility

Current Situation in Occupational Health and Safety Education in Higher Education Institutions of Turkey

Directory of Open Access Journals (Sweden)

Osman SİVRİKAYA

2016-10-01

Full Text Available During recent years, “the occupational health and safety” topic, which has gained importance in different countries in the world, has got attention in Turkey as well. The importance of human life and health is being increased in the world especially in the developed countries. As a result of this, in order to prevent the work accidents involving death or personal injury in the work life, the importance of the “occupational health and safety” is increasing gradually. In Turkey, the regulation studies are being carried out on this topic with the successive regulations especially during recent years. The application aspect of the topic, which is related to employers on the occasion of legal liabilities in accordance with the regulations, and for the graduates who are seeking for a job and especially want to be occupational safety specialists, it is popular from the point of view to be hope for a job. However, due to the difficulties to follow the rapidly changing developments, efficient awareness about the topic is not possible. It is possible that to get true and current information about the topic is possible by showing necessary sensitivity about occupational health and safety education. The graduates from different departments wonder the topics such as what is “occupational health and safety” education and “what kind of an education is necessary to become an occupational safety specialist”. Hence, in this article, by giving current information about occupational health and safety education and their content in the higher education institutions in Turkey, the points, which have had improvements compared to the past, are considered, and certain suggestions are presented to have better occupational health and safety education.

Eighth ITER technical meeting on safety and environment

International Nuclear Information System (INIS)

Gordon, C.; Raeder, J.

2000-01-01

From November 27 to 30, 2000 the Eighth ITER Technical Meeting on Safety and Environment was held by the ITER Joint Central Team (JCT) at the Garching Joint Work Site, which also hosts the ITER Safety, Environment and Health Group (SEHG). At this meeting, safety experts from the Home Teams (HT) worked together with the SEHG members towards the following main objectives: review of Generic Site Safety Report (GSSR) results and drafts; review of the Plant Design Description (PDD) summary of safety; update on the status of the R and D tasks contributing to GSSR

Current status and applications of intergrated safety assessment and simulation code system for ISA

Energy Technology Data Exchange (ETDEWEB)

Izquierdo, J. M.; Hortal, J.; Perea, M. Sanchez; Melendez, E. [Modeling and Simulation Area (MOSI), Nuclear Safety Council (CSN), Madrid (Spain); Queral, E.; Rivas-Lewicky, J. [Energy and Fuels Department, Technical University of Madrid (UPM), Madrid (Spain)

2017-03-15

This paper reviews current status of the unified approach known as integrated safety assessment (ISA), as well as the associated SCAIS (simulation codes system for ISA) computer platform. These constitute a proposal, which is the result of collaborative action among the Nuclear Safety Council (CSN), University of Madrid (UPM), and NFQ Solutions S.L, aiming to allow independent regulatory verification of industry quantitative risk assessments. The content elaborates on discussions of the classical treatment of time in conventional probabilistic safety assessment (PSA) sequences and states important conclusions that can be used to avoid systematic and unacceptable underestimation of the failure exceedance frequencies. The unified ISA method meets this challenge by coupling deterministic and probabilistic mutual influences. The feasibility of the approach is illustrated with some examples of its application to a real size plant.

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

Science.gov (United States)

Daniels, Stijn; Risser, Ralf

2014-01-01

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

Current Trends in Radiation Protection Recommendations

International Nuclear Information System (INIS)

Gomaa, M.A.

2008-01-01

The third generation of the ICRP recommendations was adopted in April 2007. The recommendations rely on situations (planned, emergency and existing), individual (occupational, public and patient) and radiation protection system (justification, optimization and dose limits). In the present work attention is paid to discuss the new recommendations and role of IAEA in updating its Basic Safety Standards for protection against ionizing radiation and safety of radiation sources and its impact for the national regulations

An approach to handling timescales in post-closure safety assessment

International Nuclear Information System (INIS)

Bailey, L.; Littleboy, A.

2002-01-01

Previous Nirex post-closure assessments of deep geological disposal have been based on the use of probabilistic safety analysis covering many millions of years. However, Nirex has also published an assessment methodology in which the assessment timescale is divided into a number of discrete periods of time (time frames). Nirex is currently at the stage of planning the next update to its generic post-closure performance assessment and is considering the merits of using an assessment methodology based on time frames, in order to improve links with operational assessments and the provision of advice on the packaging of wastes, and to encourage stakeholder dialogue. This paper has been prepared as part of Nirex's aim, wherever possible, to 'preview', or seek input from others on, its ideas for new work to generate discussion and feedback. It describes an evolution of Nirex's published assessment methodology and outlines how it could be applied in an updated post-closure performance assessment of the Nirex generic phased disposal concept. (authors)

Repository Safety Strategy: Strategy for Protecting Public Health and Safety after Closure of a Yucca Mountain Repository, Rev. 1

Energy Technology Data Exchange (ETDEWEB)

DOE

1998-01-01

The updated Strategy to Protect Public Health and Safety explains the roles that the natural and engineered systems are expected to play in achieving the objectives of a potential repository system at Yucca Mountain. These objectives are to contain the radionuclides within the waste packages for thousands of years, and to ensure that annual doses to a person living near the site will be acceptably low. This strategy maintains the key assumption of the Site Characterization Plan (DOE 1988) strategy that the potential repository level (horizon) will remain unsaturated. Thus, the strategy continues to rely on the natural attributes of the unsaturated zone for primary protection by providing a setting where waste packages assisted by other engineered barriers are expected to contain wastes for thousands of years. As in the Site Characterization Plan (DOE 1988) strategy, the natural system from the walls of the underground openings (drifts) to the human environment is expected to provide additional defense by reducing the concentrations of any radionuclides released from the waste packages. The updated Strategy to Protect Public Health and Safety is the framework for the integration of site information, repository design and assessment of postclosure performance to develop a safety case for the viability assessment and a subsequent license application. Current site information and a reference design are used to develop a quantitative assessment of performance to be compared with a performance measure. Four key attributes of an unsaturated repository system that are critical to meeting the objectives: (1) Limited water contacting the waste packages; (2) Long waste package lifetime; (3) Slow rate of release of radionuclides from the waste form; and (4) Concentration reduction during transport through engineered and natural barriers.

MO-AB-207-00: ACR Update in MR, CT, Nuclear Medicine, and Mammography

International Nuclear Information System (INIS)

2015-01-01

A goal of an imaging accreditation program is to ensure adequate image quality, verify appropriate staff qualifications, and to assure patient and personnel safety. Currently, more than 35,000 facilities in 10 modalities have been accredited by the American College of Radiology (ACR), making the ACR program one of the most prolific accreditation options in the U.S. In addition, ACR is one of the accepted accreditations required by some state laws, CMS/MIPPA insurance and others. Familiarity with the ACR accreditation process is therefore essential to clinical diagnostic medical physicists. Maintaining sufficient knowledge of the ACR program must include keeping up-to-date as the various modality requirements are refined to better serve the goals of the program and to accommodate newer technologies and practices. This session consists of presentations from authorities in four ACR accreditation modality programs, including magnetic resonance imaging, computed tomography, nuclear medicine, and mammography. Each speaker will discuss the general components of the modality program and address any recent changes to the requirements. Learning Objectives: To understand the requirements of the ACR MR Accreditation program. The discussion will include accreditation of whole-body general purpose magnets, dedicated extremity systems well as breast MRI accreditation. Anticipated updates to the ACR MRI Quality Control Manual will also be reviewed. To understand the requirements of the ACR CT accreditation program, including updates to the QC manual as well as updates through the FAQ process. To understand the requirements of the ACR nuclear medicine accreditation program, and the role of the physicist in annual equipment surveys and the set up and supervision of the routine QC program. To understand the current ACR MAP Accreditation requirement and present the concepts and structure of the forthcoming ACR Digital Mammography QC Manual and Program

MO-AB-207-00: ACR Update in MR, CT, Nuclear Medicine, and Mammography

Energy Technology Data Exchange (ETDEWEB)

NONE

2015-06-15

A goal of an imaging accreditation program is to ensure adequate image quality, verify appropriate staff qualifications, and to assure patient and personnel safety. Currently, more than 35,000 facilities in 10 modalities have been accredited by the American College of Radiology (ACR), making the ACR program one of the most prolific accreditation options in the U.S. In addition, ACR is one of the accepted accreditations required by some state laws, CMS/MIPPA insurance and others. Familiarity with the ACR accreditation process is therefore essential to clinical diagnostic medical physicists. Maintaining sufficient knowledge of the ACR program must include keeping up-to-date as the various modality requirements are refined to better serve the goals of the program and to accommodate newer technologies and practices. This session consists of presentations from authorities in four ACR accreditation modality programs, including magnetic resonance imaging, computed tomography, nuclear medicine, and mammography. Each speaker will discuss the general components of the modality program and address any recent changes to the requirements. Learning Objectives: To understand the requirements of the ACR MR Accreditation program. The discussion will include accreditation of whole-body general purpose magnets, dedicated extremity systems well as breast MRI accreditation. Anticipated updates to the ACR MRI Quality Control Manual will also be reviewed. To understand the requirements of the ACR CT accreditation program, including updates to the QC manual as well as updates through the FAQ process. To understand the requirements of the ACR nuclear medicine accreditation program, and the role of the physicist in annual equipment surveys and the set up and supervision of the routine QC program. To understand the current ACR MAP Accreditation requirement and present the concepts and structure of the forthcoming ACR Digital Mammography QC Manual and Program.

ELFR: The European Lead Fast Reactor. Design, Safety Approach and Safety Characteristics

International Nuclear Information System (INIS)

Alemberti, Alessandro

2012-01-01

• In the framework of the LEADER project, the safety approach for a Lead cooled fast reactor has been defined and, in particular, all the possible challenges to the main safety functions and their mechanisms have been specified, in order to better define the needed provisions. • On the basis of the above and taking into account the results of the safety analyses performed during previous project (ELSY), a reference configuration of the ELFR plant has been consolidated, by improving and updating the plant design features. In particular, the emerged safety concerns have been analyzed in the LEADER project and a new set of design options and safety provisions have been proposed. • The combination of favourable Lead coolant inherent characteristics and plant design features, specifically developed to face identified challenges, resulted in a very robust and forgiving design, even in very extreme conditions, as a Fukushima-like scenario

Automatic Barometric Updates from Ground-Based Navigational Aids

Science.gov (United States)

1990-03-12

ro fAutomatic Barometric Updates US Department from of Transportation Ground-Based Federal Aviation Administration Navigational Aids Office of Safety...tighter vertical spacing controls , particularly for operations near Terminal Control Areas (TCAs), Airport Radar Service Areas (ARSAs), military climb and...E.F., Ruth, J.C., and Williges, B.H. (1987). Speech Controls and Displays. In Salvendy, G., E. Handbook of Human Factors/Ergonomics, New York, John

NASA ESTO Lidar Technologies Investment Strategy: 2016 Decadal Update

Science.gov (United States)

Valinia, Azita; Komar, George J.; Tratt, David M.; Lotshaw, William T.; Gaab, Kevin M.

2017-01-01

The NASA Earth Science Technology Office (ESTO) recently updated its investment strategy in the area of lidar technologies as it pertains to NASA's Earth Science measurement goals in the next decade. The last ESTO lidar strategy was documented in 2006. The current (2016) report assesses the state-of-the-art in lidar technologies a decade later. Lidar technology maturation in the past decade has been evaluated, and the ESTO investment strategy is updated and laid out in this report according to current NASA Earth science measurement needs and new emerging technologies.

Updates to building-code maps for the 2015 NEHRP recommended seismic provisions

Science.gov (United States)

Luco, Nicolas; Bachman, Robert; Crouse, C.B; Harris, James R.; Hooper, John D.; Kircher, Charles A.; Caldwell, Phillp; Rukstales, Kenneth S.

2015-01-01

With the 2014 update of the U.S. Geological Survey (USGS) National Seismic Hazard Model (NSHM) as a basis, the Building Seismic Safety Council (BSSC) has updated the earthquake ground motion maps in the National Earthquake Hazards Reduction Program (NEHRP) Recommended Seismic Provisions for New Buildings and Other Structures, with partial funding from the Federal Emergency Management Agency. Anticipated adoption of the updated maps into the American Society of Civil Engineers Minimum Design Loads for Building and Other Structures and the International Building and Residential Codes is underway. Relative to the ground motions in the prior edition of each of these documents, most of the updated values are within a ±20% change. The larger changes are, in most cases, due to the USGS NSHM updates, reasons for which are given in companion publications. In some cases, the larger changes are partly due to a BSSC update of the slope of the fragility curve that is used to calculate the risk-targeted ground motions, and/or the introduction by BSSC of a quantitative definition of “active faults” used to calculate deterministic ground motions.

Belief update as social choice

NARCIS (Netherlands)

van Benthem, J.; Girard, P.; Roy, O.; Marion, M.

2011-01-01

Dynamic epistemic-doxastic logics describe the new knowledge or new beliefs indexBelief of agents after some informational event has happened. Technically, this requires an update rule that turns a doxastic-epistemic modelM(recording the current information state of the agents) and a dynamic ‘event

Hazardous properties and toxicological update of mercury: From fish food to human health safety perspective.

Science.gov (United States)

Okpala, Charles Odilichukwu R; Sardo, Giacomo; Vitale, Sergio; Bono, Gioacchino; Arukwe, Augustine

2017-04-10

The mercury (Hg) poisoning of Minamata Bay of Japan widely activated a global attention to Hg toxicity and its potential consequences to the aquatic ecosystem and human health. This has resulted to an increased need for a dynamic assembly, contextualization, and quantification of both the current state-of-the-art and approaches for understanding the cause-and-effect relationships of Hg exposure. Thus, the objective of this present review is to provide both hazardous toxic properties and toxicological update of Hg, focusing on how it ultimately affects the aquatic biota to potentially produce human health effects. Primarily, we discussed processes that relate to Hg exposure, including immunological aspects and risk assessment, vulnerability, toxicokinetics, and toxicodynamics, using edible fish, swordfish (Xiphias gladius), as a model. In addition, we summarized available information about Hg concentration limits set by different governmental agencies, as recognized by national and international standardization authorities.

NS [Nuclear Safety] update. Current safety and security activities and developments taking place in the Department of Nuclear Safety and Security, Issue no. 14, March 2010

International Nuclear Information System (INIS)

2010-03-01

The current issue presents information about the following topics: Highlights of the 2nd International Conference on Effective Nuclear Regulatory Systems, Cape Town, 14 December 2009. Denial of Shipment of Radioactive Material. Emergency Preparedness Review (EPREV)

Radiation Protection and Safety of Radiation Sources: International Basic Safety Standards. General Safety Requirements. Pt. 3 (Chinese Edition)

International Nuclear Information System (INIS)

2014-01-01

This publication is the new edition of the International Basic Safety Standards. The edition is co-sponsored by seven other international organizations — European Commission (EC/Euratom), FAO, ILO, OECD/NEA, PAHO, UNEP and WHO. It replaces the interim edition that was published in November 2011 and the previous edition of the International Basic Safety Standards which was published in 1996. It has been extensively revised and updated to take account of the latest finding of the United Nations Scientific Committee on the Effects of Atomic Radiation, and the latest recommendations of the International Commission on Radiological Protection. The publication details the requirements for the protection of people and the environment from harmful effects of ionizing radiation and for the safety of radiation sources. All circumstances of radiation exposure are considered

Radiation protection and safety of radiation sources: International basic safety standards. General safety requirements. Pt. 3 (French Edition)

International Nuclear Information System (INIS)

2016-01-01

This publication is the new edition of the International Basic Safety Standards. The edition is co-sponsored by seven other international organizations — European Commission (EC/Euratom), FAO, ILO, OECD/NEA, PAHO, UNEP and WHO. It replaces the interim edition that was published in November 2011 and the previous edition of the International Basic Safety Standards which was published in 1996. It has been extensively revised and updated to take account of the latest finding of the United Nations Scientific Committee on the Effects of Atomic Radiation, and the latest recommendations of the International Commission on Radiological Protection. The publication details the requirements for the protection of people and the environment from harmful effects of ionizing radiation and for the safety of radiation sources. All circumstances of radiation exposure are considered

Radiation Protection and Safety of Radiation Sources: International Basic Safety Standards. General Safety Requirements. Pt. 3 (Arabic Edition)

International Nuclear Information System (INIS)

2015-01-01

This publication is the new edition of the International Basic Safety Standards. The edition is co-sponsored by seven other international organizations — European Commission (EC/Euratom), FAO, ILO, OECD/NEA, PAHO, UNEP and WHO. It replaces the interim edition that was published in November 2011 and the previous edition of the International Basic Safety Standards which was published in 1996. It has been extensively revised and updated to take account of the latest finding of the United Nations Scientific Committee on the Effects of Atomic Radiation, and the latest recommendations of the International Commission on Radiological Protection. The publication details the requirements for the protection of people and the environment from harmful effects of ionizing radiation and for the safety of radiation sources. All circumstances of radiation exposure are considered

Current status and new trends in the methodology of safety assessment for near surface disposal facilities

International Nuclear Information System (INIS)

Ilie, Petre; Didita, Liana; Danchiv, Alexandru

2008-01-01

The main goal of this paper is to present the status of the safety assessment methodology at the end of IAEA CRP 'Application of Safety Assessment Methodology for Near-Surface Radioactive Waste Disposal Facilities (ASAM)', and the new trends outlined at the launch of the follow-up project 'Practical Implementation of Safety Assessment Methodologies in a Context of Safety Case of Near-Surface Facilities (PRISM)'. Over the duration of the ASAM project, the ISAM methodology was confirmed as providing a good framework for conducting safety assessment calculations. In contrast, ASAM project identified the limitations of the ISAM methodology as currently formulated. The major limitations are situated in the area of the use of safety assessment for informing practical decisions about alternative waste and risk management strategies for real disposal sites. As a result of the limitation of the ISAM methodology, the PRISM project is established as an extension of the ISAM and ASAM projects. Based on the outcomes of the ASAM project, the main objective of the PRISM project are: 1 - to develop an overview of what constitutes an adequate safety case and safety assessment with a view to supporting decision making processes; 2 - to provide practical illustrations of how the safety assessment methodology could be used for addressing some specific issues arising from the ASAM project and national cases; 3 - to support harmonization with the IAEA's international safety standards. (authors)

Four Medication Safety Tips for Older Adults

Science.gov (United States)

... Products For Consumers Home For Consumers Consumer Updates 4 Medication Safety Tips for Older Adults Share Tweet ... you are experiencing could be due to medications. 4. Review Medications with Your Health Care Provider Ideally, ...

International Symposium on Nuclear Safety

International Nuclear Information System (INIS)

2013-03-01

Nuclear Regulatory Authority of the Slovak Republic and the Embassy of Japan in the Slovak Republic, under the auspices of the Deputy Prime Minister and Minister of Foreign and European Affairs Mr Lajcak organized International Symposium on Nuclear Safety on 14 and 15 March 2013. The symposium took place almost exactly two years after the occurrence of accidents at the Japanese nuclear power plant Fukushima Daichi. The main mission of the symposium was an attempt to contribute to the improvement of nuclear safety by sharing information and lessons presented by Japanese experts with experts from the region, the International Atomic Energy Agency (IAEA) and the European Commission. The aim of the symposium, unlike many other events organized in connection with the events in Fukushima Daichi NPP, was a summary of the results of stress tests and measures update adopted by the international community, especially within Europe. Panel discussion was included to the program of the symposium for this aim was, mainly focused on the current state of implementation of the National Action Plan of the Slovak Republic, the Czech Republic, Poland, Ukraine and Switzerland and the IAEA Action Plan.

Specialized meeting on 'Current topics of reactor safety research in Germany'

International Nuclear Information System (INIS)

Kruessenberg, Anne

2013-01-01

On October 11 and 12, 2012, the 2-day specialized meeting organized by the Thermodynamics and Fluid Dynamics Group together with the Dresden-Rossendorf Helmholtz Center and TUeV NORD SysTec GmbH and Co.KG was held at the Dresden-Rossendorf Helmholtz Center within the series of events on 'Current Topics of Safety Research in Germany.' The program of lectures was supplemented by poster presentations and exhibitions by the members of the joint research groups and companies working in the fields. The meeting again was very well attended by over 100 persons. (orig.)

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 trends in radiation protection in Egypt. Vol. 1

International Nuclear Information System (INIS)

Gomma, M.A.

1996-01-01

The treatise presents the development of radiation protection in egypt over the past four decades. The contents will include a historical synopsis, and the current state of art regarding competent authorities, the hierarchy involved, and the respective responsibilities. The recent publications of the international trends in radiation protection are also mentioned. The efforts made towards the implementation of the new recommendations on radiation protection, and updating of the radiation protection legislations are also discussed. The 1994 international safety standards, and the collective opinion of the committee on radiation protection and public health (CRPPH) of the organization for economic Co-operation and development of the Nuclear energy agency OECD/NEA are also summarized

Current trends in radiation protection in Egypt. Vol. 1

Energy Technology Data Exchange (ETDEWEB)

Gomma, M A [Atomic Energy Authority, Cairo (Egypt)

1996-03-01

The treatise presents the development of radiation protection in egypt over the past four decades. The contents will include a historical synopsis, and the current state of art regarding competent authorities, the hierarchy involved, and the respective responsibilities. The recent publications of the international trends in radiation protection are also mentioned. The efforts made towards the implementation of the new recommendations on radiation protection, and updating of the radiation protection legislations are also discussed. The 1994 international safety standards, and the collective opinion of the committee on radiation protection and public health (CRPPH) of the organization for economic Co-operation and development of the Nuclear energy agency OECD/NEA are also summarized.

Safety analysis for research reactors

International Nuclear Information System (INIS)

2008-01-01

The aim of safety analysis for research reactors is to establish and confirm the design basis for items important to safety using appropriate analytical tools. The design, manufacture, construction and commissioning should be integrated with the safety analysis to ensure that the design intent has been incorporated into the as-built reactor. Safety analysis assesses the performance of the reactor against a broad range of operating conditions, postulated initiating events and other circumstances, in order to obtain a complete understanding of how the reactor is expected to perform in these situations. Safety analysis demonstrates that the reactor can be kept within the safety operating regimes established by the designer and approved by the regulatory body. This analysis can also be used as appropriate in the development of operating procedures, periodic testing and inspection programmes, proposals for modifications and experiments and emergency planning. The IAEA Safety Requirements publication on the Safety of Research Reactors states that the scope of safety analysis is required to include analysis of event sequences and evaluation of the consequences of the postulated initiating events and comparison of the results of the analysis with radiological acceptance criteria and design limits. This Safety Report elaborates on the requirements established in IAEA Safety Standards Series No. NS-R-4 on the Safety of Research Reactors, and the guidance given in IAEA Safety Series No. 35-G1, Safety Assessment of Research Reactors and Preparation of the Safety Analysis Report, providing detailed discussion and examples of related topics. Guidance is given in this report for carrying out safety analyses of research reactors, based on current international good practices. The report covers all the various steps required for a safety analysis; that is, selection of initiating events and acceptance criteria, rules and conventions, types of safety analysis, selection of

The current CEA/DRN safety approach for the design and the assessment of future nuclear installations

International Nuclear Information System (INIS)

Fiorini, G.L.; Pinto, P.L.; Costa, M.

1999-01-01

The purpose of the document is to present the basis of the safety approach currently implemented by the CEA/DRN, both for the design and the assessment of innovative systems and future nuclear installations. This approach is the result of the experience maturated, within the context of the CEA/DRN Innovative Programme through practical applications over several future concepts, both for fission and fusion reactors, as well as for waste disposal. The background of this experience is structured coherently with the European Safety Authorities recommendations and the European Utilities Requirements (EUR). The Defence In Depth principle and its application, by means, among others, of the barrier concept, remains the basis of the safety design process of future nuclear installations. Its adequacy is checked through the safety assessment. The methodology for Lines Of Defence (LOD) implementation as well as the one for the LOD architecture assessment is shown and motivated. The document shows that the clear and unambiguous definition of the safety approach provides an essential base for the organisation of the design tasks, being sure that the safety aspects are correctly taken into account and implemented, and for an adequate safety assessment of the final design, both from qualitative point of view as well as for the quantitative safety analysis. (author)

BE-2004: International meeting on updates in best estimate methods in nuclear installation safety analysis. Proceedings

International Nuclear Information System (INIS)

2004-01-01

BE-2004 is the second in a series of embedded conferences that focus on generating and sustaining the dialogue regarding the use of best estimate plus uncertainty tools to license operational and advanced nuclear systems. The first conference in the series was held during the 2000 American Nuclear Society Winter Meeting in Washington. BE-2004 is international in scope, as evidenced by the multinational sources of the papers, and is intended to serve as an opportunity for information exchange between research scientists, practicing engineers, and regulators. However, as appropriate to a follow-on conference, the primary theme of BE-2004 is to provide updates reflecting the progress in best estimate methodologies in the last four years. Examples include research activities that evolved from the current Generation-IV initiative and other new designs [Nuclear Energy Research Initiative (NERI), etc.], core design and neutronic calculations that support best estimate analysis, use of advanced methodologies to produce plant licensing procedures competitive with best estimate methods, and of course current philosophical and technical issues that need to be considered in implementing best estimate codes as an established part of the international licensing framework

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

Science.gov (United States)

2014-08-01

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

78 FR 65932 - Updating OSHA Standards Based on National Consensus Standards; Signage

Science.gov (United States)

2013-11-04

...; Signage AGENCY: Occupational Safety and Health Administration (OSHA), Department of Labor. ACTION... accompanied its direct final rule revising its signage standards for general industry and construction. DATES... proposed rule (NPRM) along with the direct final rule (DFR) (see 78 FR 35585) updating its signage...

Neuro-oncology update: radiation safety and nursing care during interstitial brachytherapy

International Nuclear Information System (INIS)

Randall, T.M.; Drake, D.K.; Sewchand, W.

1987-01-01

Radiation control and safety are major considerations for nursing personnel during the care of patients receiving brachytherapy. Since the theory and practice of radiation applications are not part of the routine curriculum of nursing programs, the education of nurses and other health care professionals in radiation safety procedures is important. Regulatory agencies recommend that an annual safety course be given to all persons frequenting, using, or associated with patients containing radioactive materials. This article presents pertinent aspects of the principles and procedures of radiation safety, the role of personnel dose-monitoring devices, and the value of additional radiation control features, such as a lead cubicle, during interstitial brain implants. One institution's protocol and procedures for the care of high-intensity iridium-192 brain implants are discussed. Preoperative teaching guidelines and nursing interventions included in the protocol focus on radiation control principles

Study of Updating Initiating Event Frequency using Prognostics

Energy Technology Data Exchange (ETDEWEB)

Kim, Hyeonmin; Lee, Sang-Hwan; Park, Jun-seok; Kim, Hyungdae; Chang, Yoon-Suk; Heo, Gyunyoung [Kyung Hee Univ., Yongin (Korea, Republic of)

2014-10-15

The Probabilistic Safety Assessment (PSA) model enables to find the relative priority of accident scenarios, weak points in achieving accident prevention or mitigation, and insights to improve those vulnerabilities. Thus, PSA consider realistic calculation for precise and confidence results. However, PSA model still 'conservative' aspects in the procedures of developing a PSA model. One of the sources for the conservatism is caused by the assumption of safety analysis and the estimation of failure frequency. Recently, Surveillance, Diagnosis, and Prognosis (SDP) is a growing trend in applying space and aviation systems in particular. Furthermore, a study dealing with the applicable areas and state-of-the-art status of the SDP in nuclear industry was published. SDP utilizing massive database and information technology among such enabling techniques is worthwhile to be highlighted in terms of the capability of alleviating the conservatism in the conventional PSA. This paper review the concept of integrating PSA and SDP and suggest the updated methodology of Initiating Event (IE) using prognostics. For more detailed, we focus on IE of the Steam Generator Tube Rupture (SGTR) considering tube degradation. This paper is additional research of previous our suggested the research. In this paper, the concept of integrating PSA and SDP are suggested. Prognostics algorithms in SDP are applied at IE, Bes in the Level 1 PSA. As an example, updating SGTR IE and its ageing were considered. Tube ageing were analyzed by using PASTA and Monte Carlo method. After analyzing the tube ageing, conventional SGTR IE were updated by using Bayesian approach. The studied method can help to cover the static and conservatism in PSA.

Study of Updating Initiating Event Frequency using Prognostics

International Nuclear Information System (INIS)

Kim, Hyeonmin; Lee, Sang-Hwan; Park, Jun-seok; Kim, Hyungdae; Chang, Yoon-Suk; Heo, Gyunyoung

2014-01-01

The Probabilistic Safety Assessment (PSA) model enables to find the relative priority of accident scenarios, weak points in achieving accident prevention or mitigation, and insights to improve those vulnerabilities. Thus, PSA consider realistic calculation for precise and confidence results. However, PSA model still 'conservative' aspects in the procedures of developing a PSA model. One of the sources for the conservatism is caused by the assumption of safety analysis and the estimation of failure frequency. Recently, Surveillance, Diagnosis, and Prognosis (SDP) is a growing trend in applying space and aviation systems in particular. Furthermore, a study dealing with the applicable areas and state-of-the-art status of the SDP in nuclear industry was published. SDP utilizing massive database and information technology among such enabling techniques is worthwhile to be highlighted in terms of the capability of alleviating the conservatism in the conventional PSA. This paper review the concept of integrating PSA and SDP and suggest the updated methodology of Initiating Event (IE) using prognostics. For more detailed, we focus on IE of the Steam Generator Tube Rupture (SGTR) considering tube degradation. This paper is additional research of previous our suggested the research. In this paper, the concept of integrating PSA and SDP are suggested. Prognostics algorithms in SDP are applied at IE, Bes in the Level 1 PSA. As an example, updating SGTR IE and its ageing were considered. Tube ageing were analyzed by using PASTA and Monte Carlo method. After analyzing the tube ageing, conventional SGTR IE were updated by using Bayesian approach. The studied method can help to cover the static and conservatism in PSA

Transcranial direct current stimulation for depression in Alzheimer's disease: study protocol for a randomized controlled trial.

Science.gov (United States)

Narita, Zui; Yokoi, Yuma

2017-06-19

Patients with Alzheimer's disease frequently elicit neuropsychiatric symptoms as well as cognitive deficits. Above all, depression is one of the most common neuropsychiatric symptoms in Alzheimer's disease but antidepressant drugs have not shown significant beneficial effects on it. Moreover, electroconvulsive therapy has not ensured its safety for potential severe adverse events although it does show beneficial clinical effect. Transcranial direct current stimulation can be the safe alternative of neuromodulation, which applies weak direct electrical current to the brain. Although transcranial direct current stimulation has plausible evidence for its effect on depression in young adult patients, no study has explored it in older subjects with depression in Alzheimer's disease. Therefore, we present a study protocol designed to evaluate the safety and clinical effect of transcranial direct current stimulation on depression in Alzheimer's disease in subjects aged over 65 years. This is a two-arm, parallel-design, randomized controlled trial, in which patients and assessors will be blinded. Subjects will be randomized to either an active or a sham transcranial direct current stimulation group. Participants in both groups will be evaluated at baseline, immediately, and 2 weeks after the intervention. This study investigates the safety and effect of transcranial direct current stimulation that may bring a significant impact on both depression and cognition in patients with Alzheimer's disease, and may be useful to enhance their quality of life. ClinicalTrials.gov, NCT02351388 . Registered on 27 January 2015. Last updated on 30 May 2016.

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

Safety Training: places available in October 2014

CERN Multimedia

2014-01-01

There are places available in the forthcoming Safety courses. For updates and registrations, please refer to the Safety Training Catalogue. Safety Training, HSE Unit safety-training@cern.ch Title of the course EN Title of the course FR Date Hours Language Chemical Safety ATEX Habilitation - Level 2 Habilitation ATEX - Niveau 2 16-Oct-14 to 17-Oct-14 9:00 - 17:30 French Cryogenic Safety Cryogenic Safety - Fundamentals Sécurité Cryogénie - Fondamentaux 23-Oct-14 10:00 - 12:00 English Cryogenic Safety - Helium Transfer Sécurité Cryogénie - Transfert d'hélium 30-Oct-14 9:30 - 12:00 English Electrical Safety Habilitation Electrique - Electrician Low Voltage - Initial Habilitation électrique - Électricien basse tension - Initial 02-Oct-14 to 06-Oct-14 9:00 - 17:30 English 20-Oct-14 to 22-Oct-14 9:00 -...

Early Limits on the Verbal Updating of an Object's Location

Science.gov (United States)

Ganea, Patricia A.; Harris, Paul L.

2013-01-01

Recent research has shown that by 30 months of age, children can successfully update their representation of an absent object's location on the basis of new verbal information, whereas 23-month-olds often return to the object's prior location. The current results show that this updating failure persisted even when (a) toddlers received visual and…

DARHT: INTEGRATION OF AUTHORIZATION BASIS REQUIREMENTS AND WORKER SAFETY

International Nuclear Information System (INIS)

MC CLURE, D. A.; NELSON, C. A.; BOUDRIE, R. L.

2001-01-01

This document describes the results of consensus agreements reached by the DARHT Safety Planning Team during the development of the update of the DARHT Safety Analysis Document (SAD). The SAD is one of the Authorization Basis (AB) Documents required by the Department prior to granting approval to operate the DARHT Facility. The DARHT Safety Planning Team is lead by Mr. Joel A. Baca of the Department of Energy Albuquerque Operations Office (DOE/AL). Team membership is drawn from the Department of Energy Albuquerque Operations Office, the Department of Energy Los Alamos Area Office (DOE/LAAO), and several divisions of the Los Alamos National Laboratory. Revision 1 of the DARHT SAD had been written as part of the process for gaining approval to operate the Phase 1 (First Axis) Accelerator. Early in the planning stage for the required update of the SAD for the approval to operate both Phase 1 and Phase 2 (First Axis and Second Axis) DARHT Accelerator, it was discovered that a conflict existed between the Laboratory approach to describing the management of facility and worker safety

Evaluation of Hazardous Material Management Safety in the Chemical Laboratory in BATAN

International Nuclear Information System (INIS)

Nur-Rahmah-Hidayati

2005-01-01

The management safety of the hazardous material (B3) in the chemical laboratory of BATAN was evaluated. The evaluation is necessary to be done because B3 is often used together with radioactive materials in the laboratory, but the attention to the safety aspect of B3 is not paid sufficiently in spite of its big potential hazard. The potential hazard generated from the nature of B3 could be flammable, explosive, oxidative, corrosive and poisonous. The handling of B3 could be conducted by enforcing the labelling and classification in the usage and disposal processes. Some observations of the chemical laboratory of BATAN show that the management safety of hazardous material in compliance with the government regulation no. 74 year 2001 has not been dully conducted. The management safety of B3 could be improved by, designating one who has adequate skill in hazardous material safety specially as the B3 safety officer, providing the Material Safety Data Sheet that is updated periodically to use in the laboratory and storage room, updating periodically the inventory of B3, performing training in work safety periodically, and monitoring the ventilation system intensively in laboratory and storage room. (author)

LBTool: A stochastic toolkit for leave-based key updates

DEFF Research Database (Denmark)

Yuksel, Ender; Nielson, Hanne Riis; Nielson, Flemming

2012-01-01

Quantitative techniques have been successfully employed in verification of information and communication systems. However, the use of such techniques are still rare in the area of security. In this paper, we present a toolkit that implements transient analysis on a key update method for wireless...... sensor networks. The analysis aims to find out the probability of a network key being compromised at a specific time point, which result in fluctuations over time for a specific key update method called Leave-based key update. For such a problem, the use of current tools is limited in many ways...

Building America Expert Meeting. Combustion Safety

Energy Technology Data Exchange (ETDEWEB)

Brand, Larry [Partnership for Advanced Residential Retrofit (PARR), Des Plaines, IL (United States)

2013-03-01

This is an overview of "The Best Approach to Combustion Safety in a Direct Vent World," held June 28, 2012, in San Antonio, TX. The objective of this Expert Meeting was to identify gaps and barriers that need to be addressed by future research, and to develop data-driven technical recommendations for code updates so that a common approach for combustion safety can be adopted by all members of the building energy efficiency and code communities.

Building America Expert Meeting: Combustion Safety

Energy Technology Data Exchange (ETDEWEB)

Brand, L.

2013-03-01

This is a meeting overview of 'The Best Approach to Combustion Safety in a Direct Vent World', held June 28, 2012, in San Antonio, Texas. The objective of this Expert Meeting was to identify gaps and barriers that need to be addressed by future research, and to develop data-driven technical recommendations for code updates so that a common approach for combustion safety can be adopted by all members of the building energy efficiency and code communities.

76 FR 17808 - Final Vehicle Safety Rulemaking and Research Priority Plan 2011-2013

Science.gov (United States)

2011-03-31

... [Docket No. NHTSA-2009-0108] Final Vehicle Safety Rulemaking and Research Priority Plan 2011- 2013 AGENCY... availability. SUMMARY: This document announces the availability of the Final NHTSA Vehicle Safety and Fuel.... This Priority Plan is an update to the Final Vehicle Safety Rulemaking and Research Priority Plan 2009...

Impaired Working Memory Updating for Emotional Stimuli in Depressed Patients.

Science.gov (United States)

Zhang, Dandan; Xie, Hui; He, Zhenhong; Wei, Zhaoguo; Gu, Ruolei

2018-01-01

Although two previous studies have demonstrated that depressed individuals showed deficits in working memory (WM) updating of both negative and positive contents, the effects were confounded by shifting dysfunctions and the detailed neural mechanism associated with the failure in N-back task is not clear. Using a 2-back task, the current study examined the WM updating of positive, negative and neutral contents in depressed patients. It is found that depressed patients performed poorer than healthy controls only when updating positive material. Using event-related potential (ERP) technique, the current study also investigated the neural correlates of updating deficits in depression. According to previous studies, the n-back task was divided into three sub-processes, i.e., encoding, matching and maintaining. Our ERP results showed that depressed patients had smaller occipital P1 for positive material compared to healthy controls, indicating their insensitivity to positive items on early encoding stage. Besides, depressed patients had larger frontal P2 and parietal late positive potential (LPP) than healthy controls irrespective of the valence of the words, reflecting that patients are inefficient during matching (P2) and maintaining (LPP) processes. These two mechanisms (insufficient attention to positive stimuli and low efficiency in matching and maintaining) together lead to the deficits of WM updating in depression.

Current Status of Periodic Safety Review of HANARO Research Reactor

Energy Technology Data Exchange (ETDEWEB)

Kim, Minjin; Ahn, Guk-Hoon; Lee, Choong Sung [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2016-10-15

A PSR for a research reactor became a legal requirement as the Nuclear Safety Act was amended and came into effect in 2014. This paper describes the current status and methodology of the first Periodic Safety Review (PSR) of HANARO that is being performed. The legal requirements, work plan, and process of implementing a PSR are described. Because this is the first PSR for a research reactor, it is our understating that the operating organization and regulatory body should communicate well with each other to complete the PSR in a timely manner. The first PSR of HANARO is under way. In order to achieve a successful result, activities of the operation organization such as scheduling, maintaining consistency in input data for review, and reviewing the PSR reports that will require intensive resources should be well planned. This means the operating organization needs to incorporate appropriate measures to ensure the transfer of knowledge and expertise arising from the PSR via a contractor to the operation organization. It is desirable for the Regulatory Body to be involved in all stage of the PSR to prevent any waste of resources and minimize the potential for a reworking of the PSR and the need for an additional assessment and review as recommended by foreign experts.

Update of GRASP/Ada reverse engineering tools for Ada

Science.gov (United States)

Cross, James H., II

1993-01-01

The GRASP/Ada project (Graphical Representations of Algorithms, Structures, and Processes for Ada) successfully created and prototyped a new algorithmic level graphical representation for Ada software, the Control Structure Diagram (CSD). The primary impetus for creation of the CSD was to improve the comprehension efficiency of Ada software and, as a result, improve reliability and reduce costs. The emphasis was on the automatic generation of the CSD from Ada PDL or source code to support reverse engineering and maintenance. The CSD has the potential to replace traditional pretty printed Ada source code. In Phase 1 of the GRASP/Ada project, the CSD graphical constructs were created and applied manually to several small Ada programs. A prototype CSD generator (Version 1) was designed and implemented using FLEX and BISON running under VMS on a VAX 11-780. In Phase 2, the prototype was improved and ported to the Sun 4 platform under UNIX. A user interface was designed and partially implemented using the HP widget toolkit and the X Windows System. In Phase 3, the user interface was extensively reworked using the Athena widget toolkit and X Windows. The prototype was applied successfully to numerous Ada programs ranging in size from several hundred to several thousand lines of source code. Following Phase 3,e two update phases were completed. Update'92 focused on the initial analysis of evaluation data collected from software engineering students at Auburn University and the addition of significant enhancements to the user interface. Update'93 (the current update) focused on the statistical analysis of the data collected in the previous update and preparation of Version 3.4 of the prototype for limited distribution to facilitate further evaluation. The current prototype provides the capability for the user to generate CSD's from Ada PDL or source code in a reverse engineering as well as forward engineering mode with a level of flexibility suitable for practical

The use of remote sensing for updating extensive forest inventories

Science.gov (United States)

John F. Kelly

1990-01-01

The Forest Inventory and Analysis unit of the USDA Forest Service Southern Forest Experiment Station (SO-FIA) has the research task of devising an inventory updating system that can be used to provide reliable estimates of forest area, volume, growth, and removals at the State level. These updated inventories must be accomplished within current budgetary restraints....

Current activities and future trends in reliability analysis and probabilistic safety assessment in Hungary

International Nuclear Information System (INIS)

Hollo, E.; Toth, J.

1986-01-01

In Hungary reliability analysis (RA) and probabilistic safety assessment (PSA) of nuclear power plants was initiated 3 years ago. First, computer codes for automatic fault tree analysis (CAT, PREP) and numerical evaluation (REMO, KITT1,2) were adapted. Two main case studies - detailed availability/reliability calculation of diesel sets and analysis of safety systems influencing event sequences induced by large LOCA - were performed. Input failure data were taken from publications, a need for failure and reliability data bank was revealed. Current and future activities involves: setup of national data bank for WWER-440 units; full-scope level-I PSA of PAKS NPP in Hungary; operational safety assessment of particular problems at PAKS NPP. In the present article the state of RA and PSA activities in Hungary, as well as the main objectives of ongoing work are described. A need for international cooperation (for unified data collection of WWER-440 units) and for IAEA support (within Interregional Program INT/9/063) is emphasized. (author)

Qualified Presumption of Safety (QPS) is a generic risk assessment approach applied by the European Food Safety Authority (EFSA)

DEFF Research Database (Denmark)

Leuschner, R. G. K.; Robinson, T. P.; Hugas, M.

2010-01-01

Qualified Presumption of Safety (QPS) is a generic risk assessment approach applied by the European Food Safety Authority (EFSA) to notified biological agents aiming at simplifying risk assessments across different scientific Panels and Units. The aim of this review is to outline the implementation...... and value of the QPS assessment for EFSA and to explain its principles such as the unambiguous identity of a taxonomic unit, the body of knowledge including potential safety concerns and how these considerations lead to a list of biological agents recommended for QPS which EFSA keeps updated through...

CANISTER HANDLING FACILITY CRITICALITY SAFETY CALCULATIONS

Energy Technology Data Exchange (ETDEWEB)

C.E. Sanders

2005-04-07

This design calculation revises and updates the previous criticality evaluation for the canister handling, transfer and staging operations to be performed in the Canister Handling Facility (CHF) documented in BSC [Bechtel SAIC Company] 2004 [DIRS 167614]. The purpose of the calculation is to demonstrate that the handling operations of canisters performed in the CHF meet the nuclear criticality safety design criteria specified in the ''Project Design Criteria (PDC) Document'' (BSC 2004 [DIRS 171599], Section 4.9.2.2), the nuclear facility safety requirement in ''Project Requirements Document'' (Canori and Leitner 2003 [DIRS 166275], p. 4-206), the functional/operational nuclear safety requirement in the ''Project Functional and Operational Requirements'' document (Curry 2004 [DIRS 170557], p. 75), and the functional nuclear criticality safety requirements described in the ''Canister Handling Facility Description Document'' (BSC 2004 [DIRS 168992], Sections 3.1.1.3.4.13 and 3.2.3). Specific scope of work contained in this activity consists of updating the Category 1 and 2 event sequence evaluations as identified in the ''Categorization of Event Sequences for License Application'' (BSC 2004 [DIRS 167268], Section 7). The CHF is limited in throughput capacity to handling sealed U.S. Department of Energy (DOE) spent nuclear fuel (SNF) and high-level radioactive waste (HLW) canisters, defense high-level radioactive waste (DHLW), naval canisters, multicanister overpacks (MCOs), vertical dual-purpose canisters (DPCs), and multipurpose canisters (MPCs) (if and when they become available) (BSC 2004 [DIRS 168992], p. 1-1). It should be noted that the design and safety analyses of the naval canisters are the responsibility of the U.S. Department of the Navy (Naval Nuclear Propulsion Program) and will not be included in this document. In addition, this calculation is valid for

Ontario Hydro's DSP update

International Nuclear Information System (INIS)

Anon.

1992-01-01

Ontario Hydro's Demand/Supply Plan (DSP), the 25 year plan which was submitted in December 1989, is currently being reviewed by the Environmental Assessment Board (EAB). Since 1989 there have been several changes which have led Ontario Hydro to update the original Demand/Supply Plan. This information sheet gives a quick overview of what has changed and how Ontario Hydro is adapting to that change

DATMAN: A reliability data analysis program using Bayesian updating

International Nuclear Information System (INIS)

Becker, M.; Feltus, M.A.

1996-01-01

Preventive maintenance (PM) techniques focus on the prevention of failures, in particular, system components that are important to plant functions. Reliability-centered maintenance (RCM) improves on the PM techniques by introducing a set of guidelines by which to evaluate the system functions. It also minimizes intrusive maintenance, labor, and equipment downtime without sacrificing system performance when its function is essential for plant safety. Both the PM and RCM approaches require that system reliability data be updated as more component failures and operation time are acquired. Systems reliability and the likelihood of component failures can be calculated by Bayesian statistical methods, which can update these data. The DATMAN computer code has been developed at Penn State to simplify the Bayesian analysis by performing tedious calculations needed for RCM reliability analysis. DATMAN reads data for updating, fits a distribution that best fits the data, and calculates component reliability. DATMAN provides a user-friendly interface menu that allows the user to choose from several common prior and posterior distributions, insert new failure data, and visually select the distribution that matches the data most accurately

Robot Visual Tracking via Incremental Self-Updating of Appearance Model

Directory of Open Access Journals (Sweden)

Danpei Zhao

2013-09-01

Full Text Available This paper proposes a target tracking method called Incremental Self-Updating Visual Tracking for robot platforms. Our tracker treats the tracking problem as a binary classification: the target and the background. The greyscale, HOG and LBP features are used in this work to represent the target and are integrated into a particle filter framework. To track the target over long time sequences, the tracker has to update its model to follow the most recent target. In order to deal with the problems of calculation waste and lack of model-updating strategy with the traditional methods, an intelligent and effective online self-updating strategy is devised to choose the optimal update opportunity. The strategy of updating the appearance model can be achieved based on the change in the discriminative capability between the current frame and the previous updated frame. By adjusting the update step adaptively, severe waste of calculation time for needless updates can be avoided while keeping the stability of the model. Moreover, the appearance model can be kept away from serious drift problems when the target undergoes temporary occlusion. The experimental results show that the proposed tracker can achieve robust and efficient performance in several benchmark-challenging video sequences with various complex environment changes in posture, scale, illumination and occlusion.

Updating Geospatial Data from Large Scale Data Sources

Science.gov (United States)

Zhao, R.; Chen, J.; Wang, D.; Shang, Y.; Wang, Z.; Li, X.; Ai, T.

2011-08-01

In the past decades, many geospatial databases have been established at national, regional and municipal levels over the world. Nowadays, it has been widely recognized that how to update these established geo-spatial database and keep them up to date is most critical for the value of geo-spatial database. So, more and more efforts have been devoted to the continuous updating of these geospatial databases. Currently, there exist two main types of methods for Geo-spatial database updating: directly updating with remote sensing images or field surveying materials, and indirectly updating with other updated data result such as larger scale newly updated data. The former method is the basis because the update data sources in the two methods finally root from field surveying and remote sensing. The later method is often more economical and faster than the former. Therefore, after the larger scale database is updated, the smaller scale database should be updated correspondingly in order to keep the consistency of multi-scale geo-spatial database. In this situation, it is very reasonable to apply map generalization technology into the process of geo-spatial database updating. The latter is recognized as one of most promising methods of geo-spatial database updating, especially in collaborative updating environment in terms of map scale, i.e , different scale database are produced and maintained separately by different level organizations such as in China. This paper is focused on applying digital map generalization into the updating of geo-spatial database from large scale in the collaborative updating environment for SDI. The requirements of the application of map generalization into spatial database updating are analyzed firstly. A brief review on geospatial data updating based digital map generalization is then given. Based on the requirements analysis and review, we analyze the key factors for implementing updating geospatial data from large scale including technical

Safety equipment list for the 241-SY-101 RAPID mitigation project

Energy Technology Data Exchange (ETDEWEB)

MORRIS, K.L.

1999-06-29

This document provides the safety classification for the safety (safety class and safety RAPID Mitigation Project. This document is being issued as the project SEL until the supporting authorization basis documentation, this document will be superseded by the TWRS SEL (LMHC 1999), documentation istlralized. Upon implementation of the authorization basis significant) structures, systems, and components (SSCS) associated with the 241-SY-1O1 which will be updated to include the information contained herein.

Safety equipment list for the 241-SY-101 RAPID mitigation project

International Nuclear Information System (INIS)

Morris, K.L.

1999-01-01

This document provides the safety classification for the safety (safety class and safety RAPID Mitigation Project. This document is being issued as the project SEL until the supporting authorization basis documentation, this document will be superseded by the TWRS SEL (LMHC 1999), documentation istlralized. Upon implementation of the authorization basis significant) structures, systems, and components (SSCS) associated with the 241-SY-1O1 which will be updated to include the information contained herein

New risks and trends in the safety and health of women at work

OpenAIRE

Flaspöler, E; Hauke, A; Koppisch, D; Reinert, D; Koukoulaki, T; Vilkevicius, G; Žemės, L; Águila Martínez-Casariego, M; Baquero Martínez, M; González Lozar, L; Vega Martínez, S; López Riera, S; Carter, L; Leah, C; Gervais, R

2013-01-01

In 2009 and 2010, the Agency commissioned an update to its previous research on gender issues at\\ud work (EU-OSHA, 2003), which found that inequality both within and outside the workplace can have\\ud an effect on the health and safety of women at work. This report provides that update and the first\\ud figures on the effects of the recent economic downturn on women at work. It aims to fulfil the task\\ud outlined by the European strategy on health and safety at work (EC, 2002) for EU-OSHA’s Eur...

Omics and biotechnology of arsenic stress and detoxification in plants: current updates and prospective.

Science.gov (United States)

Kumar, Smita; Dubey, Rama Shanker; Tripathi, Rudra Deo; Chakrabarty, Debasis; Trivedi, Prabodh Kumar

2015-01-01

Arsenic (As), a naturally occurring metallic element, is a dreadful health hazard to millions of people across the globe. Arsenic is present in low amount in the environment and originates from anthropogenic impact and geogenic sources. The presence of As in groundwater used for irrigation is a worldwide problem as it affects crop productivity, accumulates to different tissues and contaminates food chain. The consumption of As contaminated water or food products leads to several diseases and even death. Recently, studies have been carried out to explore the biochemical and molecular mechanisms which contribute to As toxicity, accumulation, detoxification and tolerance acquisition in plants. This information has led to the development of the biotechnological tools for developing plants with modulated As tolerance and detoxification to safeguard cellular and genetic integrity as well as to minimize food chain contamination. This review aims to provide current updates about the biochemical and molecular networks involved in As uptake by plants and the recent developments in the area of functional genomics in terms of developing As tolerant and low As accumulating plants. Copyright © 2014 Elsevier Ltd. All rights reserved.

Regulatory aspects of oncology drug safety evaluation: Past practice, current issues, and the challenge of new drugs

International Nuclear Information System (INIS)

Rosenfeldt, Hans; Kropp, Timothy; Benson, Kimberly; Ricci, M. Stacey; McGuinn, W. David; Verbois, S. Leigh

2010-01-01

The drug development of new anti-cancer agents is streamlined in response to the urgency of bringing effective drugs to market for patients with limited life expectancy. FDA's regulation of oncology drugs has evolved from the practices set forth in Arnold Lehman's seminal work published in the 1950s through the current drafting of a new International Conference on Harmonization of Technical Requirements for Registration of Pharmaceuticals for Human Use (ICH) safety guidance for anti-cancer drug nonclinical evaluations. The ICH combines the efforts of the regulatory authorities of Europe, Japan, and the United States and the pharmaceutical industry from these three regions to streamline the scientific and technical aspects of drug development. The recent development of new oncology drug classes with novel mechanisms of action has improved survival rates for some cancers but also brings new challenges for safety evaluation. Here we present the legacy of Lehman and colleagues in the context of past and present oncology drug development practices and focus on some of the current issues at the center of an evolving harmonization process that will generate a new safety guidance for oncology drugs, ICH S9. The purpose of this new guidance will be to facilitate oncology drug development on a global scale by standardizing regional safety requirements.

78 FR 35585 - Updating OSHA Standards Based on National Consensus Standards; Signage

Science.gov (United States)

2013-06-13

...; Signage AGENCY: Occupational Safety and Health Administration (OSHA), Department of Labor. ACTION: Notice... Administration (``OSHA'' or ``the Agency'') proposes to update its general industry and construction signage... standards, ANSI Z53.1-1967, Z35.1-1968, and Z35.2-1968, in its signage standards, thereby providing...

77 FR 2126 - Pipeline Safety: Implementation of the National Registry of Pipeline and Liquefied Natural Gas...

Science.gov (United States)

2012-01-13

... Natural Gas Operators AGENCY: Pipeline and Hazardous Materials Safety Administration (PHMSA), DOT. ACTION... DEPARTMENT OF TRANSPORTATION Pipeline and Hazardous Materials Safety Administration [Docket No...: ``Pipeline Safety: Updates to Pipeline and Liquefied Natural Gas Reporting Requirements.'' The final rule...

Safety analysis SFR 1. Long-term safety

Energy Technology Data Exchange (ETDEWEB)

2008-12-15

An updated assessment of the long-term safety of SKB's final repository for radioactive operational waste, SFR 1, is presented in this report. The report is included in the safety analysis report for SFR 1. The most recent account of long-term safety was submitted to the regulatory authorities in 2001. The present report has been compiled on SKB's initiative to address the regulatory authorities' viewpoints regarding the preceding account of long-term safety. Besides the new mode of working with safety functions there is another important difference between the 2001 safety assessment and the current assessment: The time horizon in the current assessment has been extended to 100,000 years in order to include the effect of future climate changes. The purpose of this renewed assessment of the long-term safety of SFR 1 is to show with improved data that the repository is capable of protecting human health and the environment against ionizing radiation in a long-term perspective. This is done by showing that calculated risks lie below the risk criteria stipulated by the regulatory authorities. SFR 1 is built to receive, and after closure serve as a passive repository for, low. and intermediate-level radioactive waste. The disposal chambers are situated in rock beneath the sea floor, covered by about 60 metres of rock. The underground part of the facility is reached via two tunnels whose entrances are near the harbour. The repository has been designed so that it can be abandoned after closure without further measures needing to be taken to maintain its function. The waste in SFR 1 is short-lived low- and intermediate-level waste. After 100 years the activity is less than half, and after 1,000 years only about 2% of the original activity remains. The report on long-term safety comprises eleven chapters. Chapter 1 Introduction. The chapter describes the purpose, background, format and contents of SAR-08, applicable regulations and injunctions, and the regulatory

Safety analysis SFR 1. Long-term safety

International Nuclear Information System (INIS)

2008-12-01

An updated assessment of the long-term safety of SKB's final repository for radioactive operational waste, SFR 1, is presented in this report. The report is included in the safety analysis report for SFR 1. The most recent account of long-term safety was submitted to the regulatory authorities in 2001. The present report has been compiled on SKB's initiative to address the regulatory authorities' viewpoints regarding the preceding account of long-term safety. Besides the new mode of working with safety functions there is another important difference between the 2001 safety assessment and the current assessment: The time horizon in the current assessment has been extended to 100,000 years in order to include the effect of future climate changes. The purpose of this renewed assessment of the long-term safety of SFR 1 is to show with improved data that the repository is capable of protecting human health and the environment against ionizing radiation in a long-term perspective. This is done by showing that calculated risks lie below the risk criteria stipulated by the regulatory authorities. SFR 1 is built to receive, and after closure serve as a passive repository for, low. and intermediate-level radioactive waste. The disposal chambers are situated in rock beneath the sea floor, covered by about 60 metres of rock. The underground part of the facility is reached via two tunnels whose entrances are near the harbour. The repository has been designed so that it can be abandoned after closure without further measures needing to be taken to maintain its function. The waste in SFR 1 is short-lived low- and intermediate-level waste. After 100 years the activity is less than half, and after 1,000 years only about 2% of the original activity remains. The report on long-term safety comprises eleven chapters. Chapter 1 Introduction. The chapter describes the purpose, background, format and contents of SAR-08, applicable regulations and injunctions, and the regulatory

Safety analysis SFR 1. Long-term safety

Energy Technology Data Exchange (ETDEWEB)

2008-12-15

An updated assessment of the long-term safety of SKB's final repository for radioactive operational waste, SFR 1, is presented in this report. The report is included in the safety analysis report for SFR 1. The most recent account of long-term safety was submitted to the regulatory authorities in 2001. The present report has been compiled on SKB's initiative to address the regulatory authorities' viewpoints regarding the preceding account of long-term safety. Besides the new mode of working with safety functions there is another important difference between the 2001 safety assessment and the current assessment: The time horizon in the current assessment has been extended to 100,000 years in order to include the effect of future climate changes. The purpose of this renewed assessment of the long-term safety of SFR 1 is to show with improved data that the repository is capable of protecting human health and the environment against ionizing radiation in a long-term perspective. This is done by showing that calculated risks lie below the risk criteria stipulated by the regulatory authorities. SFR 1 is built to receive, and after closure serve as a passive repository for, low. and intermediate-level radioactive waste. The disposal chambers are situated in rock beneath the sea floor, covered by about 60 metres of rock. The underground part of the facility is reached via two tunnels whose entrances are near the harbour. The repository has been designed so that it can be abandoned after closure without further measures needing to be taken to maintain its function. The waste in SFR 1 is short-lived low- and intermediate-level waste. After 100 years the activity is less than half, and after 1,000 years only about 2% of the original activity remains. The report on long-term safety comprises eleven chapters. Chapter 1 Introduction. The chapter describes the purpose, background, format and contents of SAR-08, applicable regulations and injunctions, and the

[Preoperative fasting guidelines: an update].

Science.gov (United States)

López Muñoz, A C; Busto Aguirreurreta, N; Tomás Braulio, J

2015-03-01

Anesthesiology societies have issued various guidelines on preoperative fasting since 1990, not only to decrease the incidence of lung aspiration and anesthetic morbidity, but also to increase patient comfort prior to anesthesia. Some of these societies have been updating their guidelines, as such that, since 2010, we now have 2 evidence-based preoperative fasting guidelines available. In this article, an attempt is made to review these updated guidelines, as well as the current instructions for more controversial patients such as infants, the obese, and a particular type of ophthalmic surgery. Copyright © 2014 Sociedad Española de Anestesiología, Reanimación y Terapéutica del Dolor. Publicado por Elsevier España, S.L.U. All rights reserved.

Internet Journal of Medical Update - EJOURNAL

African Journals Online (AJOL)

Internet Journal of Medical Update (IJMU) is an international e-journal which provides a multidisciplinary forum for the exchange of current ideas in form of review articles, original research work, interesting case reports, etc. among medical professionals. Editorial policy: The Editor receives manuscripts with the ...

77 FR 68717 - Updating OSHA Standards Based on National Consensus Standards; Head Protection

Science.gov (United States)

2012-11-16

..., 1918, and 1926 [Docket No. OSH-2011-0184] RIN 1218-AC65 Updating OSHA Standards Based on National Consensus Standards; Head Protection AGENCY: Occupational Safety and Health Administration (OSHA), Labor. ACTION: Proposed rule; withdrawal. SUMMARY: With this notice, OSHA is withdrawing the proposed rule that...

Long-term follow-up of MCL patients treated with single-agent ibrutinib: updated safety and efficacy results.

Science.gov (United States)

Wang, Michael L; Blum, Kristie A; Martin, Peter; Goy, Andre; Auer, Rebecca; Kahl, Brad S; Jurczak, Wojciech; Advani, Ranjana H; Romaguera, Jorge E; Williams, Michael E; Barrientos, Jacqueline C; Chmielowska, Ewa; Radford, John; Stilgenbauer, Stephan; Dreyling, Martin; Jedrzejczak, Wieslaw Wiktor; Johnson, Peter; Spurgeon, Stephen E; Zhang, Liang; Baher, Linda; Cheng, Mei; Lee, Dana; Beaupre, Darrin M; Rule, Simon

2015-08-06

Ibrutinib, an oral inhibitor of Bruton tyrosine kinase, is approved for patients with mantle cell lymphoma (MCL) who have received one prior therapy. We report the updated safety and efficacy results from the multicenter, open-label phase 2 registration trial of ibrutinib (median 26.7-month follow-up). Patients (N = 111) received oral ibrutinib 560 mg once daily, and those with stable disease or better could enter a long-term extension study. The primary end point was overall response rate (ORR). The median patient age was 68 years (range, 40-84), with a median of 3 prior therapies (range, 1-5). The median treatment duration was 8.3 months; 46% of patients were treated for >12 months, and 22% were treated for ≥2 years. The ORR was 67% (23% complete response), with a median duration of response of 17.5 months. The 24-month progression-free survival and overall survival rates were 31% (95% confidence interval [CI], 22.3-40.4) and 47% (95% CI, 37.1-56.9), respectively. The most common adverse events (AEs) in >30% of patients included diarrhea (54%), fatigue (50%), nausea (33%), and dyspnea (32%). The most frequent grade ≥3 infections included pneumonia (8%), urinary tract infection (4%), and cellulitis (3%). Grade ≥3 bleeding events in ≥2% of patients were hematuria (2%) and subdural hematoma (2%). Common all-grade hematologic AEs were thrombocytopenia (22%), neutropenia (19%), and anemia (18%). The prevalence of infection, diarrhea, and bleeding was highest for the first 6 months of therapy and less thereafter. With longer follow-up, ibrutinib continues to demonstrate durable responses and favorable safety in relapsed/refractory MCL. The trial is registered to www.ClinicalTrials.gov as #NCT01236391. © 2015 by The American Society of Hematology.

75 FR 80517 - HUD Multifamily Rental Project Closing Documents-Revisions and Updates Notice of Information...

Science.gov (United States)

2010-12-22

... familiar with the updated closing documents, the existing closing documents, which these updated closing... assures the industry and the public that sufficient staff will be available and thoroughly familiar with... documents that are updated for current commercial legal standards, balanced with the public policy role that...

It’s all about safety signs!

CERN Multimedia

2013-01-01

Their first occurrence may date back to the Egyptian hieroglyphs, but today they can be found everywhere: on our clothes labels as care labels, in train stations and airports to guide us, during the Olympics to identify various sports, on our dashboards, etc.   Safety wise, they are used to indicate a danger, a prohibition, an obligation, a safety exit, firefighting equipment, etc. The HSE Unit has decided to update the 150 safety signs used on the CERN site and, to correspond with this, recently published a Safety Guideline GS-1-0-1, available on the Safety Unit website. The Guideline contains more than 150 safety signs as well as diverse information regarding the meaning of the signs, their location and how to use them. The Guideline will shortly be completed with a new Safety Rule that will replace the former Security Code A3, “Safety colours and safety signs”. Please be informed that you also have the option to create new safety signs, provided that you first g...

Sixth national report of Brazil for the nuclear safety convention

International Nuclear Information System (INIS)

2013-01-01

Brazil has presented periodically its National Report prepared by a group composed of representatives of the various Brazilian organizations with responsibilities related to nuclear safety. Due to the implications of the Fukushima nuclear accident in 2011, an Extraordinary National Report was presented in 2012. This Sixth National Report is an update of the Fifth National Report in relation to the Convention on Nuclear Safety articles and also an update of the Extraordinary Report with respect to the action taken related to lesson learned from the Fukushima accident. It includes relevant information for the period of 2010/2012. This document represents the national report prepared as a fulfillment of the brazilian obligations related to the Convention on Nuclear Safety. In chapter 2 some details are given about the existing nuclear installations. Chapter 3 provides details about the legislation and regulations, including the regulatory framework and the regulatory body. Chapter 4 covers general safety considerations as described in articles 10 to 16 of the Convention. Chapter 5 addresses to the safety of the installations during siting, design, construction and operation. Chapter 6 describes planned activities to further enhance nuclear safety. Chapter 7 presents the final remarks related to the degree of compliance with the Convention obligations

Sixth national report of Brazil for the nuclear safety convention

Energy Technology Data Exchange (ETDEWEB)

NONE

2013-07-01

Brazil has presented periodically its National Report prepared by a group composed of representatives of the various Brazilian organizations with responsibilities related to nuclear safety. Due to the implications of the Fukushima nuclear accident in 2011, an Extraordinary National Report was presented in 2012. This Sixth National Report is an update of the Fifth National Report in relation to the Convention on Nuclear Safety articles and also an update of the Extraordinary Report with respect to the action taken related to lesson learned from the Fukushima accident. It includes relevant information for the period of 2010/2012. This document represents the national report prepared as a fulfillment of the brazilian obligations related to the Convention on Nuclear Safety. In chapter 2 some details are given about the existing nuclear installations. Chapter 3 provides details about the legislation and regulations, including the regulatory framework and the regulatory body. Chapter 4 covers general safety considerations as described in articles 10 to 16 of the Convention. Chapter 5 addresses to the safety of the installations during siting, design, construction and operation. Chapter 6 describes planned activities to further enhance nuclear safety. Chapter 7 presents the final remarks related to the degree of compliance with the Convention obligations.

Engineering and Safety Partnership Enhances Safety of the Space Shuttle Program (SSP)

Science.gov (United States)

Duarte, Alberto

2007-01-01

Project Management must use the risk assessment documents (RADs) as tools to support their decision making process. Therefore, these documents have to be initiated, developed, and evolved parallel to the life of the project. Technical preparation and safety compliance of these documents require a great deal of resources. Updating these documents after-the-fact not only requires substantial increase in resources - Project Cost -, but this task is also not useful and perhaps an unnecessary expense. Hazard Reports (HRs), Failure Modes and Effects Analysis (FMEAs), Critical Item Lists (CILs), Risk Management process are, among others, within this category. A positive action resulting from a strong partnership between interested parties is one way to get these documents and related processes and requirements, released and updated in useful time. The Space Shuttle Program (SSP) at the Marshall Space Flight Center has implemented a process which is having positive results and gaining acceptance within the Agency. A hybrid Panel, with equal interest and responsibilities for the two larger organizations, Safety and Engineering, is the focal point of this process. Called the Marshall Safety and Engineering Review Panel (MSERP), its charter (Space Shuttle Program Directive 110 F, April 15, 2005), and its Operating Control Plan emphasizes the technical and safety responsibilities over the program risk documents: HRs; FMEA/CILs; Engineering Changes; anomalies/problem resolutions and corrective action implementations, and trend analysis. The MSERP has undertaken its responsibilities with objectivity, assertiveness, dedication, has operated with focus, and has shown significant results and promising perspectives. The MSERP has been deeply involved in propulsion systems and integration, real time technical issues and other relevant reviews, since its conception. These activities have transformed the propulsion MSERP in a truly participative and value added panel, making a

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

77 FR 16471 - Pipeline Safety: Implementation of the National Registry of Pipeline and Liquefied Natural Gas...

Science.gov (United States)

2012-03-21

... Registry of Pipeline and Liquefied Natural Gas Operators AGENCY: Pipeline and Hazardous Materials Safety... DEPARTMENT OF TRANSPORTATION Pipeline and Hazardous Materials Safety Administration 49 CFR Parts... Register (75 FR 72878) titled: ``Pipeline Safety: Updates to Pipeline and Liquefied Natural Gas Reporting...

Updated requirements for control room annunciation: an operations perspective

International Nuclear Information System (INIS)

Davey, E.; Lane, L.

2001-01-01

The purpose of this paper is to describe the results of updating and aligning requirements for annunciation functionality and performance with current expectations for operational excellence. This redefinition of annunciation requirements was undertaken as one component of a project to characterize improvement priorities, establish the operational and economic basis for improvement, and identify preferred implementation options for Ontario Power Generation plants. The updated requirements express the kinds of information support annunciation should provide to Operations staff to support the detection, recognition and response to changes in plant conditions. The updated requirements were developed using several types of information: management and industry expectations for operations excellence, previous definitions of user needs for annunciation, and operational and ergonomic principles. Operations and engineering staff at several stations have helped refine and complete the initial requirements definition. Application of these updated requirements is expected to lead to more effective and task relevant annunciation system improvements that better serve plant operation needs. The paper outlines the project rationale, reviews development objectives, discusses the approaches applied for requirements definition and organization, describes key requirements findings in relation to current operations experience, and discusses the proposed application of these requirements for guiding future annunciation system improvements. (author)

Extraglottic airway devices: technology update

Directory of Open Access Journals (Sweden)

Sharma B

2017-08-01

Full Text Available Bimla Sharma, Chand Sahai, Jayashree Sood Department of Anaesthesiology, Pain and Perioperative Medicine, Sir Ganga Ram Hospital, New Delhi, India Abstract: Extraglottic airway devices (EADs have revolutionized the field of airway management. The invention of the laryngeal mask airway was a game changer, and since then, there have been several innovations to improve the EADs in design, functionality, safety and construction material. These have ranged from changes in the shape of the mask, number of cuffs and material used, like rubber, polyvinylchloride and latex. Phthalates, which were added to the construction material in order to increase device flexibility, were later omitted when this chemical was found to have serious adverse reproductive outcomes. The various designs brought out by numerous companies manufacturing EADs resulted in the addition of several devices to the airway market. These airway devices were put to use, many of them with inadequate or no evidence base regarding their efficacy and safety. To reduce the possibility of compromising the safety of the patient, the Difficult Airway Society (DAS formed the Airway Device Evaluation Project Team (ADEPT to strengthen the evidence base for airway equipment and vet the new extraglottic devices. A preuse careful analysis of the design and structure may help in better understanding of the functionality of a particular device. In the meantime, the search for the ideal EAD continues. Keywords: extraglottic airway devices, laryngeal mask airway, other extraglottic airway devices, safety, technology update

Safety Improvements on Wood Chippers Currently in Use: A Study on Feasibility in the Italian Context

Directory of Open Access Journals (Sweden)

Giorgia Bagagiolo

2017-12-01

Full Text Available Following formal opposition by France, the harmonized safety standards regarding manually-loaded wood chippers (EN 13525:2005+A2:2009 which presumed compliance with the Essential Health and Safety Requirements (EHSR required by the Machine Directive (Directive 2006/42/EC, have recently been withdrawn, and a new draft of the standard is currently under revision. In order to assess the potential impact of the expected future harmonized standards within the Italian context, this study has examined the main issues in implementing EHSRs on wood chippers already being used. Safety issues regarding wood chippers already in use were identified in an analysis of the draft standard, through the observation of a number of case studies, and qualitative analysis of the essential technical interventions. A number of agricultural and forestry operators and companies participated in the study, pointing out the technical and economic obstacle facing the safety features requested by the pending new standard. It emerged that the main safety issues concerned the implementation of the reverse function, the stop bar, and the protective devices, the infeed chute dimension, the emergency stop function, and the designated feeding area. The possibility of adopting such solutions mainly depends on technical feasibility and costs, but an important role is also played by the attitude towards safety and a lack of adequate information regarding safety obligations and procedures among users.

Update on phototherapy in jaundiced neonates

DEFF Research Database (Denmark)

Ebbesen, Finn; Hansen, Thor Willy Ruud; Maisels, M Jeffrey

2017-01-01

is the current treatment of choice. OBJECTIVE: To present an update on the most important issues involved in phototherapy for jaundiced infants. RESULTS: Light absorption by bilirubin in the skin transforms the native Z,Z-bilirubin to conformational photoisomers Z,E-bilirubin and E,Z-bilirubin and structural...

Excipients and their role in approved injectable products: current usage and future directions.

Science.gov (United States)

Nema, Sandeep; Brendel, Ronald J

2011-01-01

This review article is a current survey of excipients used in approved injectable products. Information provided includes concentration ranges, function, frequency of use, and role in dosage form. This article is an update of a paper published more than a decade ago (reference 11). Since then many new products have been approved. Safety concerning excipients has evolved as the scientific community continues to learn about their usage. New excipients are being used in early phases of clinical trials to support novel therapeutic entities like RNAi, aptamers, anti-sense, fusion proteins, monoclonal antibodies, and variant scaffolds. Because these excipients are not inert, various pharmacopoeias are responding with monographs or informational chapters addressing excipient functionality. The final sections of this article discuss new excipients, serving specific needs that traditional excipients are unable to provide and for which safety studies are necessary to support a novel excipient for marketing applications. Excipients are added to parenteral dosage forms to serve a variety of functions including stabilization and as vehicles. This review article is a survey of excipients used in approved injectable products. Information provided includes excipient concentrations, functional roles, and frequency of use. This article is an update of an article originally published over a decade ago. Since then new products have been approved and safety concerns have evolved as the scientific community has learned about the usage of excipients. In addition, new excipients are being used in early phases of clinical trials to support novel therapeutic entities such as RNAi, aptamers, anti-sense, fusion proteins, monoclonal antibodies, and variant scaffolds. Because these excipients are not inert, various pharmacopoeias are responding with monographs or informational chapters addressing excipient functionality. The final sections of this article discuss new excipients, serving

77 FR 68684 - Updating OSHA Standards Based on National Consensus Standards; Head Protection

Science.gov (United States)

2012-11-16

..., 1918, and 1926 [Docket No. OSHA-2011-0184] RIN 1218-AC65 Updating OSHA Standards Based on National Consensus Standards; Head Protection AGENCY: Occupational Safety and Health Administration (OSHA), Labor. ACTION: Final rule; confirmation of effective date. SUMMARY: OSHA is confirming the effective date of its...

IAEA safety glossary. Terminology used in nuclear safety and radiation protection. 2007 ed

International Nuclear Information System (INIS)

2007-01-01

legislation, should be aware that the terms included have been chosen and the definitions and explanations given have been drafted for the purpose mentioned above. Terminology and usage may differ in other contexts, such as in binding international legal instruments and in the publications of other organizations. It is recognized that the Safety Glossary will be of wider interest, and it is therefore now issued as an IAEA publication. It is intended to issue a CD-ROM that will include this Safety Glossary (2007 Edition) and versions of the publication in the other five official languages of the IAEA: Arabic, Chinese, French, Russian and Spanish. These other five versions will also be made available for downloading from the Safety Glossary web site. It is intended to revise and update the Safety Glossary periodically in the light of changes in terminology and usage in the safety standards due to developments in technology and changes in regulatory approaches in Member States. The IAEA Secretariat invites the submission of feedback concerning the definitions of technical terms and the explanations of their usage given in the Safety Glossary from users of the IAEA safety standards (in English and in translation) and other safety related publications. A change form is provided on the Safety Glossary web site - http://www-ns.iaea.org/standards/safetyglossary.htm - for the submission of information or suggestions for consideration in a revision of the Safety Glossary. The first version of the Safety Glossary was compiled and issued in 2000. The Safety Glossary, 2007 Edition, is a revised and updated version. In revising the Safety Glossary, account has been taken of safety standards issued since 2000 and of the comments and suggestions submitted in the revision process and in the course of its translation

IAEA safety glossary. Terminology used in nuclear safety and radiation protection. 2007 ed

International Nuclear Information System (INIS)

2007-06-01

legislation, should be aware that the terms included have been chosen and the definitions and explanations given have been drafted for the purpose mentioned above. Terminology and usage may differ in other contexts, such as in binding international legal instruments and in the publications of other organizations. It is recognized that the Safety Glossary will be of wider interest, and it is therefore now issued as an IAEA publication. It is intended to issue a CD-ROM that will include this Safety Glossary (2007 Edition) and versions of the publication in the other five official languages of the IAEA: Arabic, Chinese, French, Russian and Spanish. These other five versions will also be made available for downloading from the Safety Glossary web site. It is intended to revise and update the Safety Glossary periodically in the light of changes in terminology and usage in the safety standards due to developments in technology and changes in regulatory approaches in Member States. The IAEA Secretariat invites the submission of feedback concerning the definitions of technical terms and the explanations of their usage given in the Safety Glossary from users of the IAEA safety standards (in English and in translation) and other safety related publications. A change form is provided on the Safety Glossary web site - http://www-ns.iaea.org/standards/safetyglossary.htm - for the submission of information or suggestions for consideration in a revision of the Safety Glossary. The first version of the Safety Glossary was compiled and issued in 2000. The Safety Glossary, 2007 Edition, is a revised and updated version. In revising the Safety Glossary, account has been taken of safety standards issued since 2000 and of the comments and suggestions submitted in the revision process and in the course of its translation

IAEA safety glossary. Terminology used in nuclear safety and radiation protection. 2007 ed

International Nuclear Information System (INIS)

2007-01-01

legislation, should be aware that the terms included have been chosen and the definitions and explanations given have been drafted for the purpose mentioned above. Terminology and usage may differ in other contexts, such as in binding international legal instruments and in the publications of other organizations. It is recognized that the Safety Glossary will be of wider interest, and it is therefore now issued as an IAEA publication. It is intended to issue a CD-ROM that will include this Safety Glossary (2007 Edition) and versions of the publication in the other five official languages of the IAEA: Arabic, Chinese, French, Russian and Spanish. These other five versions will also be made available for downloading from the Safety Glossary web site. It is intended to revise and update the Safety Glossary periodically in the light of changes in terminology and usage in the safety standards due to developments in technology and changes in regulatory approaches in Member States. The IAEA Secretariat invites the submission of feedback concerning the definitions of technical terms and the explanations of their usage given in the Safety Glossary from users of the IAEA safety standards (in English and in translation) and other safety related publications. A change form is provided on the Safety Glossary web site - http://www-ns.iaea.org/standards/safetyglossary.htm - for the submission of information or suggestions for consideration in a revision of the Safety Glossary. The first version of the Safety Glossary was compiled and issued in 2000. The Safety Glossary, 2007 Edition, is a revised and updated version. In revising the Safety Glossary, account has been taken of safety standards issued since 2000 and of the comments and suggestions submitted in the revision process and in the course of its translation

Periodic Safety Review of Nuclear Power Plants: Experience of Member States

International Nuclear Information System (INIS)

2010-04-01

Routine reviews of nuclear power plant operation (including modifications to hardware and procedures, operating experience, plant management and personnel competence) and special reviews following major events of safety significance are the primary means of safety verification. In addition, many Member States of the IAEA have initiated systematic safety reassessments, termed periodic safety reviews, of nuclear power plants, to assess the cumulative effects of plant ageing and plant modifications, operating experience, technical developments and siting aspects. The reviews include an assessment of plant design and operation against current safety standards and practices, and they have the objective of ensuring a high level of safety throughout the plant's operating lifetime. They are complementary to the routine and special safety reviews and do not replace them. Periodic safety reviews of nuclear power plants are considered an effective way to obtain an overall view of actual plant safety, and to determine reasonable and practical modifications that should be made in order to maintain a high level of safety. They can be used as a means of identifying time limiting features of the plant in order to determine nuclear power plant operation beyond the designed lifetime. The periodic safety review process can be used to support the decision making process for long term operation or licence renewal. Since 1994, the use of periodic safety reviews by Member States has substantially broadened and confirmed its benefits. Periodic safety review results have, for example, been used by some Member States to help provide a basis for continued operation beyond the current licence term, to communicate more effectively with stakeholders regarding nuclear power plant safety, and to help identify changes to plant operation that enhance safety. This IAEA-TECDOC is intended to assist Member States in the implementation of a periodic safety review. This publication complements the

Methods and strategies for future reactor safety goals

Science.gov (United States)

Arndt, Steven Andrew

-informed analyses and discussions. This dissertation examines potential approaches to updating the safety goals that include the establishment of new quantitative safety goal associated with the comparative risk of generating electricity by viable competing technologies and modifications of the goals to account for multi-plant reactor sites, and issues associated with the use of safety goals in both initial licensing and operational decision making. This research develops a new quantitative health objective that uses a comparable benefit risk metric based on the life-cycle risk of the construction, operation and decommissioning of a comparable non-nuclear electric generation facility, as well as the risks associated with mining and transportation. This dissertation also evaluates the effects of using various methods for aggregating site risk as a safety metric, as opposed to using single plant safety goals. Additionally, a number of important assumptions inherent in the current safety goals, including the effect of other potential negative societal effects such as the generation of greenhouse gases (e.g., carbon dioxide) have on the risk of electric power production and their effects on the setting of safety goals, is explored. Finally, the role risk perception should play in establishing safety goals has been explored. To complete this evaluation, a new method to analytically compare alternative technologies of generating electricity was developed, including development of a new way to evaluate risk perception, and a new method was developed for evaluating the risk at multiple units on a single site. To test these modifications to the safety goals a number of possible reactor designs and configurations were evaluated using these new proposed safety goals to determine the goals' usefulness and utility. The results of the analysis showed that the modifications provide measures that more closely evaluate the potential risk to the public from the operation of nuclear power plants than

Construction safety and waste management an economic analysis

CERN Document Server

Li, Rita Yi Man

2015-01-01

This monograph presents an analysis of construction safety problems and on-site safety measures from an economist’s point of view. The book includes examples from both emerging countries, e.g. China and India, and developed countries, e.g. Australia and Hong Kong. Moreover, the author covers an analysis on construction safety knowledge sharing by means of updatable mobile technology such as apps in Androids and iOS platform mobile devices. The target audience comprises primarily researchers and experts in the field but the book may also be beneficial for graduate students.

Using Addenda in Documented Safety Analysis Reports

International Nuclear Information System (INIS)

Swanson, D.S.; Thieme, M.A.

2003-01-01

This paper discusses the use of addenda to the Radioactive Waste Management Complex (RWMC) Documented Safety Analysis (DSA) located at the Idaho National Engineering and Environmental Laboratory (INEEL). Addenda were prepared for several systems and processes at the facility that lacked adequate descriptive information and hazard analysis in the DSA. They were also prepared for several new activities involving unreviewed safety questions (USQs). Ten addenda to the RWMC DSA have been prepared since the last annual update

Summary Analysis: Hanford Site Composite Analysis Update

Energy Technology Data Exchange (ETDEWEB)

Nichols, W. E. [CH2M HILL Plateau Remediation Company, Richland, WA (United States); Lehman, L. L. [CH2M HILL Plateau Remediation Company, Richland, WA (United States)

2017-06-05

The Hanford Site’s currently maintained Composite Analysis, originally completed in 1998, requires an update. A previous update effort was undertaken by the U.S. Department of Energy (DOE) in 2001-2005, but was ended before completion to allow the Tank Closure & Waste Management Environmental Impact Statement (TC&WM EIS) (DOE/EIS-0391) to be prepared without potential for conflicting sitewide models. This EIS was issued in 2012, and the deferral was ended with guidance in memorandum “Modeling to Support Regulatory Decision Making at Hanford” (Williams, 2012) provided with the aim of ensuring subsequent modeling is consistent with the EIS.

Safety for all: The new INSAG

International Nuclear Information System (INIS)

Meserve, Richard; Brockman, Kenneth

2004-01-01

In 1985, the IAEA Director General identified the need for an advisory committee to the IAEA in the area of nuclear safety. The group that was subsequently chartered was called the International Nuclear Safety Advisory Group (INSAG). The nuclear community knew it over the years for the sage counsel and advice that it provided to, and through, the Agency. Between 1985 and 2002, INSAG membership ranged from 13 to 15 experts from around the world. Individuals whose names are synonymous with a commitment to nuclear safety led the group during these years. Over these 17 years, INSAG produced numerous studies that provided the foundation for advances in nuclear safety. These studies included evaluations of design and operational safety at nuclear power plants, consideration of the impacts of radiological exposures, and the examination of how best to develop and maintain a proper safety culture. While INSAG publications were recognized throughout the nuclear community as authoritative and insightful reflections on topics relating to nuclear safety, some believed the Group was limited by its charter obligation to provide advice solely to the IAEA. Other international groups of experts, most notably the International Commission on Radiological Protection (ICRP), evolved with much broader responsibilities. As result, the organization and Terms of Reference for the ICRP were seen to provide a model to emulate if one wanted to have an expert group that could serve all concerned stake holders. It was in response to this desire that the current INSAG was chartered. The IAEA has issued a collection of reports on nuclear safety under the INSAG framework. They include the world's fi rst authoritative account of the 1986 nuclear accident at Chernobyl, and an update issued in 1993. Other reports have focused on topics including basic safety principles; safety culture; regulatory decision-making; knowledge management; safe management of radioactive sources; and the defence

System safety program plan for the Isotope Brayton Ground Demonstration System (phase I)

International Nuclear Information System (INIS)

1976-01-01

The safety engineering effort to be undertaken in achieving an acceptable level of safety in the Brayton Isotope Power System (BIPS) development program is discussed. The safety organizational relationships, the methods to be used, the tasks to be completed, and the documentation to be published are described. The plan will be updated periodically as the need arises

Update in clinical allergy and immunology.

Science.gov (United States)

von Gunten, S; Marsland, B J; von Garnier, C; Simon, D

2012-12-01

In the recent years, a tremendous body of studies has addressed a broad variety of distinct topics in clinical allergy and immunology. In this update, we discuss selected recent data that provide clinically and pathogenetically relevant insights or identify potential novel targets and strategies for therapy. The role of the microbiome in shaping allergic immune responses and molecular, as well as cellular mechanisms of disease, is discussed separately and in the context of atopic dermatitis, as an allergic model disease. Besides summarizing novel evidence, this update highlights current areas of uncertainties and debates that, as we hope, shall stimulate scientific discussions and research activities in the field. © 2012 John Wiley & Sons A/S.

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)

Cost update technology, safety, and costs of decommissioning a reference uranium hexafluoride conversion plant

International Nuclear Information System (INIS)

Miles, T.L.; Liu, Y.

1995-08-01

The purpose of this study is to update the cost estimates developed in a previous report, NUREG/CR-1757 (Elder 1980) for decommissioning a reference uranium hexafluoride conversion plant from the original mid-1981 dollars to values representative of January 1993. The cost updates were performed by using escalation factors derived from cost index trends over the past 11.5 years. Contemporary price quotes wee used for costs that have increased drastically or for which is is difficult to find a cost trend. No changes were made in the decommissioning procedures or cost element requirements assumed in NUREG/CR-1757. This report includes only information that was changed from NUREG/CR-1757. Thus, for those interested in detailed descriptions and associated information for the reference uranium hexafluoride conversion plant, a copy of NUREG/CR-1757 will be needed

Hepatic veno-occlusive disease after hematopoietic stem cell transplantation: update on defibrotide and other current investigational therapies.

Science.gov (United States)

Ho, V T; Revta, C; Richardson, P G

2008-02-01

Hepatic veno-occlusive disease (VOD), also known as sinusoidal obstruction syndrome (SOS), remains one of the most serious and common complications after myeloablative hematopoietic stem cell transplantation (HSCT). Clinical diagnosis of hepatic VOD is based on the clinical triad of (1) painful hepatomegaly, (2) hyperbilirubinemia and (3) unexplained fluid retention. While milder cases usually resolve spontaneously, severe VOD is associated with a grim prognosis. Defibrotide (DF), a polydisperse mixture of single-stranded oligonucleotide with antithrombotic and fibrinolytic effects on microvascular endothelium, has emerged as an effective and safe therapy for patients with severe VOD. Multiple studies, including a recent large international multicenter phase II clinical trial, have demonstrated 30-60% complete remission rates with DF, even among patients with severe VOD and multiorgan failure. This article will review our current understanding of hepatic VOD, and update the clinical trial experience with DF and other potential therapies for this feared transplant complication.

Update on the state of play of Animal Health and Welfare and Environmental Impact of Animals derived from SCNT Cloning and their Offspring, and Food Safety of Products Obtained from those Animals

OpenAIRE

European Food Safety Authority

2012-01-01

The European Food Safety Authority (EFSA) received in December 2011, a request from the European Commission for an update on the possible scientific developments for cloning of farmed animals for food production purposes. The present Statement follows the EFSA 2009 and 2010 Statements and the EFSA 2008 Scientific Opinion, and is based on peer reviewed scientific literature published since the EFSA 2010 Statement, information made available to EFSA following a call for data, and discu...

About the necessity to update the Radiological safety and protection regulations of the National Institute of Nuclear Research (ININ); Sobre la necesidad de actualizar el reglamento de proteccion y seguridad radiologica del ININ

Energy Technology Data Exchange (ETDEWEB)

Alvarez R, J.T. [Instituto Nacional de Investigaciones Nucleares, Salazar (Mexico). Dept. de Metrologia

1997-07-01

It is argued the necessity to update the Radiological safety and Protection regulations (Review 3) of ININ, with the purpose that it implements the ICRU operative magnitudes system. Such a system used with radiological protection purposes. The objective of this system is to do an estimation of the effective equivalent dose H{sub E} and/or the Effective dose E, proposed in the ICRP 26 and ICRU 60 dose limits systems respectively. (Author)

Monitoring product safety in the postmarketing environment.

Science.gov (United States)

Sharrar, Robert G; Dieck, Gretchen S

2013-10-01

The safety profile of a medicinal product may change in the postmarketing environment. Safety issues not identified in clinical development may be seen and need to be evaluated. Methods of evaluating spontaneous adverse experience reports and identifying new safety risks include a review of individual reports, a review of a frequency distribution of a list of the adverse experiences, the development and analysis of a case series, and various ways of examining the database for signals of disproportionality, which may suggest a possible association. Regulatory agencies monitor product safety through a variety of mechanisms including signal detection of the adverse experience safety reports in databases and by requiring and monitoring risk management plans, periodic safety update reports and postauthorization safety studies. The United States Food and Drug Administration is working with public, academic and private entities to develop methods for using large electronic databases to actively monitor product safety. Important identified risks will have to be evaluated through observational studies and registries.

Fuel-coolant interaction (FCI) phenomena in reactor safety. Current understanding and future research needs

Energy Technology Data Exchange (ETDEWEB)

Speis, T.P. [Maryland Univ., College Park, MD (United States); Basu, S.

1998-01-01

This paper gives an account of the current understanding of fuel-coolant interaction (FCI) phenomena in the context of reactor safety. With increased emphasis on accident management and with emerging in-vessel core melt retention strategies for advanced light water reactor (ALWR) designs, recent interest in FCI has broadened to include an evaluation of potential threats to the integrity of reactor vessel lower head and ex-vessel structural support, as well as the role of FCI in debris quenching and coolability. The current understanding of FCI with regard to these issues is discussed, and future research needs to address the issues from a risk perspective are identified. (author)

Safety culture in the nuclear field

International Nuclear Information System (INIS)

2005-09-01

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

Safety design guides for seismic requirements for CANDU 9

International Nuclear Information System (INIS)

Lee, Duk Su; Chang, Woo Hyun; Lee, Nam Young; A. C. D. Wright

1996-03-01

This safety design guide for seismic requirements for CANDU 9 describes the seismic design philosophy, defines the applicable earthquakes and identifies the structures and systems requiring seismic qualification to ensure that the essential safety function can be adequately satisfied following earthquake. The detailed requirements for structures, systems and components which must be seismically qualified are specified in the Appendix. The change status of the regulatory requirements, code and standards should be traced and this safety design guide shall be updated accordingly. 1 fig., (Author) .new

Questionnaire responses concerning safety issues in MR examination

International Nuclear Information System (INIS)

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

2011-01-01

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

Updated embrittlement trend curve for reactor pressure vessel steels

International Nuclear Information System (INIS)

Kirk, M.; Santos, C.; Eason, E.; Wright, J.; Odette, G.R.

2003-01-01

The reactor pressure vessels of commercial nuclear power plants are subject to embrittlement due to exposure to high energy neutrons from the core. Irradiation embrittlement of RPV belt-line materials is currently evaluated using US Regulatory Guide 1.99 Revision 2 (RG 1.99 Rev 2), which presents methods for estimating the Charpy transition temperature shift (ΔT30) at 30 ft-lb (41 J) and the drop in Charpy upper shelf energy (ΔUSE). A more recent embrittlement model, based on a broader database and more recent research results, is presented in NUREG/CR-6551. The objective of this paper is to describe the most recent update to the embrittlement model in NUREG/CR-6551, based upon additional data and increased understanding of embrittlement mechanisms. The updated ΔT30 and USE models include fluence, copper, nickel, phosphorous content, and product form; the ΔT30 model also includes coolant temperature, irradiation time (or flux), and a long-time term. The models were developed using multi-variable surface fitting techniques, understanding of the ΔT30 mechanisms, and engineering judgment. The updated ΔT30 model reduces scatter significantly relative to RG 1.99 Rev 2 on the currently available database for plates, forgings, and welds. This updated embrittlement trend curve will form the basis of revision 3 to Regulatory Guide 1.99. (author)

Assessment of current safety evaluation analysis on reflood behavior during PWR-LOCA by using CCTF data

International Nuclear Information System (INIS)

Iguchi, Tadashi; Murao, Yoshio; Akimoto, Hajime; Okubo, Tsutomu; Sugimoto, Jun; Hojo, Tsuneyuki.

1987-01-01

This paper describes an assessment result on conservatism of current safety analysis concerning reflood behavior during a LOCA in a PWR by using the experimental data with cylindrical core test facility (CCTF) performed at Japan Atomic Energy Research Institute (JAERI). WREM code is selected for a representative of current safety analyses. The predicted peak clad temperature with the WREM code was higher than the data, and it was confirmed that the WREM code had the overall conservatism against CCTF data. The WREM code predicted the reasonable core boundary conditions and it was found that the conservatism of the code came mainly from the calculations on the incore thermal hydraulics and clad temperature. In addition, it was found that the conservatism of the WREM code against the CCTF data could be attributed to the neglection of horizontal fluid mixing between subchannels, the neglection of the heat transfer enhancement due to the radial core power profile, and the usage of the heat transfer correlations conservative against CCTF data. (author)

IRIS project update: status of the design and licensing activities

International Nuclear Information System (INIS)

Petrovic, B.; Carelli, M.

2004-01-01

This paper presents an overview of the current status of the IRIS (International Reactor Innovative and Secure) project, focusing on the design and licensing activities. An update relative to the previous presentation at the 4th HND Conference is provided, highlighting some of the main accomplishments over the past two years. After successfully completing the conceptual design phase, IRIS is now finalizing the preliminary design as well. The pre-application licensing review with the U.S. NRC has been initiated in October of 2002. The safety-by-design approach and PRA-guided design open the possibility to aim for licensing not requiring off-site emergency response planning. Multiple single-unit and twin-unit site layouts have been developed within the ESP (Early Site Permit) program currently pursued by three U.S. power utilities. Desalination and district heating options have recently been added to the base design. Staggered construction schedules of multiple units may be applied to optimize cash-flow and minimize the required investment, making IRIS a financially attractive option, even for economies with limited investment capabilities. Because of its modularity, compatibility with smaller/medium grids, and enabling gradual build of new generating capacity matching the needs, IRIS has a large potential in the worldwide market.(author)

A systematic review of the safety information contained within the Summaries of Product Characteristics of medications licensed in the United Kingdom for Attention Deficit Hyperactivity Disorder. how does the safety prescribing advice compare with national guidance?

Directory of Open Access Journals (Sweden)

Savill Nicola

2012-01-01

Full Text Available Abstract Background The safety of paediatric medications is paramount and contraindications provide clear pragmatic advice. Further advice may be accessed through Summaries of Product Characteristics (SPCs and relevant national guidelines. The SPC can be considered the ultimate independent guideline and is regularly updated. In 2008, the authors undertook a systematic review of the SPC contraindications of medications licensed in the United Kingdom (UK for the treatment of Attention Deficit Hyperactivity Disorder (ADHD. At that time, there were fewer contraindications reported in the SPC for atomoxetine than methylphenidate and the specific contraindications varied considerably amongst methylphenidate formulations. In 2009, the European Medicines Agency (EMA mandated harmonisation of methylphenidate SPCs. Between September and November 2011, there were three changes to the atomoxetine SPC that resulted in revised prescribing information. In addition, Clinical Guidance has also been produced by the National Institute for Health and Clinical Excellence (NICE (2008, the Scottish Intercollegiate Guidelines Network (SIGN (2009 and the British National Formulary for Children (BNFC. Methods An updated systematic review of the Contraindications sections of the SPCs of all medications currently licensed for treatment of ADHD in the UK was undertaken and independent statements regarding contraindications and relevant warnings and precautions were then compared with UK national guidance with the aim of assessing any disparity and potential areas of confusion for prescribers. Results As of November 2011, there were seven medications available in the UK for the treatment of ADHD. There are 15 contraindications for most formulations of methylphenidate, 14 for dexamfetamine and 5 for atomoxetine. Significant differences exist between the SPCs and national guidance part due to the ongoing reactive process of amending the former as new information becomes known

Endobronchial Ultrasound (EBUS) - Update 2017.

Science.gov (United States)

Darwiche, Kaid; Özkan, Filiz; Wolters, Celina; Eisenmann, Stephan

2018-02-01

Endobronchial ultrasound (EBUS) has revolutionized the diagnosis of lung cancer over the last decade. This minimally invasive diagnostic method has also become increasingly important in the case of other diseases such as sarcoidosis, thereby helping to avoid unnecessary diagnostic interventions. This review article provides an update regarding EBUS and discusses current and future developments of this method. © Georg Thieme Verlag KG Stuttgart · New York.

MEMS Stirling Cooler Development Update

Science.gov (United States)

Moran, Matthew E.; Wesolek, Danielle

2003-01-01

This presentation provides an update on the effort to build and test a prototype unit of the patented MEMS Stirling cooler concept. A micro-scale regenerator has been fabricated by Polar Thermal Technologies and is currently being integrated into a Stirling cycle simulator at Johns Hopkins University Applied Physics Laboratory. A discussion of the analysis, design, assembly, and test plans for the prototype will be presented.

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.)

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

International Nuclear Information System (INIS)

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

2014-01-01

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

Hazard screening application guide. Safety Analysis Report Update Program

Energy Technology Data Exchange (ETDEWEB)

None

1992-06-01

The basic purpose of hazard screening is to group precesses, facilities, and proposed modifications according to the magnitude of their hazards so as to determine the need for and extent of follow on safety analysis. A hazard is defined as a material, energy source, or operation that has the potential to cause injury or illness in human beings. The purpose of this document is to give guidance and provide standard methods for performing hazard screening. Hazard screening is applied to new and existing facilities and processes as well as to proposed modifications to existing facilities and processes. The hazard screening process evaluates an identified hazards in terms of the effects on people, both on-site and off-site. The process uses bounding analyses with no credit given for mitigation of an accident with the exception of certain containers meeting DOT specifications. The process is restricted to human safety issues only. Environmental effects are addressed by the environmental program. Interfaces with environmental organizations will be established in order to share information.

Forklift safety a practical guide to preventing powered industrial truck incidents and injuries

CERN Document Server

Swartz, George

1999-01-01

Written for the more than 1.5 million powered industrial truck operators and supervisors in general industry, as well as those in the construction and marine industries, this Second Edition provides an updated guide to training operators in safety and complying with OSHA's 1999 forklift standard. This edition of Forklift Safety includes a new chapter devoted to the new OSHA 1910.178 standard and new information regarding dock safety, narrow aisle trucks, off-dock incidents, tip-over safety, pallet safety, and carbon monoxide.

Los Alamos National Laboratory SAVY-4000 Field Surveillance Plan Update for 2016

International Nuclear Information System (INIS)

Kelly, Elizabeth J.; Stone, Timothy Amos; Smith, Paul Herrick; Prochnow, David Adrian; Weis, Eric M.

2016-01-01

The Packaging Surveillance Program section of the Department of Energy (DOE) Manual 441.1-1, Nuclear Material Packaging Manual (DOE 2008), requires DOE contractors to ''ensure that a surveillance program is established and implemented to ensure the nuclear material storage package continues to meet its design criteria.'' The Los Alamos National Laboratory (LANL) SAVY-4000 Field Surveillance Plan was first issued in FY 2013 (Kelly et al. 2013). The surveillance plan is reviewed annually and updated as necessary based on SAVY-4000 surveillance and other surveillance findings, as well as results of the lifetime extension studies (Blair et al. 2012, Weis et al. 2015a). The LANL SAVY-4000 Field Surveillance Plan Update was issued in 2014 (Kelly et al. 2014). This 2016 update reflects changes to the surveillance plan resulting from restrictions on handling residue materials greater than 500 g, the addition of specific engineering judgment containers, and 2015 surveillance findings. The SAVY-4000 container has a design life of five years, which was chosen as a conservative estimate of the functional properties of the materials used in the construction of the SAVY 4000 when exposed to the potential insults including temperature, corrosive materials and gases, and radiation. The SAVY-4000 container design basis is described in a safety analysis report (Anderson et al. 2013). In the National Nuclear Security Administration's (NNSA's) approval of the safety analysis report, it was recommended that the design life clock begin on March 2014 (Nez et al. 2014). However, it is expected that a technical basis can be developed to extend the design life of the SAVY-4000 containers to approximately 40 years (Blair et al. 2012, Weis et al. 2015a). This surveillance plan update covers five years (2015-2019) and is developed to ensure SAVY-4000 containers meet their design criteria over the current five-year design life and to gather data that can be used in

Safety critical systems handbook a straightforward guide to functional safety : IEC 61508 (2010 edition) and related standards

CERN Document Server

Smith, David J

2010-01-01

Electrical, electronic and programmable electronic systems increasingly carry out safety functions to guard workers and the public against injury or death and the environment against pollution. The international functional safety standard IEC 61508 was revised in 2010, and this is the first comprehensive guide available to the revised standard. As functional safety is applicable to many industries, this book will have a wide readership beyond the chemical and process sector, including oil and gas, power generation, nuclear, aircraft, and automotive industries, plus project, instrumentation, design, and control engineers. * The only comprehensive guide to IEC 61508, updated to cover the 2010 amendments, that will ensure engineers are compliant with the latest process safety systems design and operation standards* Helps readers understand the process required to apply safety critical systems standards* Real-world approach helps users to interpret the standard, with case studies and best practice design examples...

Who's Who? Memory updating and character reference in children's narratives.

Science.gov (United States)

Whitely, Cristy; Colozzo, Paola

2013-10-01

The capacity to update and monitor the contents of working memory is an executive function presumed to play a critical role in language processing. The current study used an individual differences approach to consider the relationship between memory updating and accurate reference to story characters in the narratives of typically developing children. English-speaking children from kindergarten to grade 2 ( N = 63; M age = 7.0 years) completed updating tasks, short-term memory tasks, and narrative productions. The authors used multiple regression to test whether updating accounted for independent variability in referential adequacy. The capacity to update working memory was related to adequate character reference beyond the effects of age and of short-term memory capacity, with the strongest relationship emerging for maintaining reference over multiple utterances. This individual differences study is the first to show a link between updating and performance in a discourse production task for young school-age children. The findings contribute to the growing body of research investigating the role of working memory in shaping language production. This study invites extension to children of different ages and language abilities as well as to other language production tasks.

SCALE 5: Powerful new criticality safety analysis tools

International Nuclear Information System (INIS)

Bowman, Stephen M.; Hollenbach, Daniel F.; Dehart, Mark D.; Rearden, Bradley T.; Gauld, Ian C.; Goluoglu, Sedat

2003-01-01

Version 5 of the SCALE computer software system developed at Oak Ridge National Laboratory, scheduled for release in December 2003, contains several significant new modules and sequences for criticality safety analysis and marks the most important update to SCALE in more than a decade. This paper highlights the capabilities of these new modules and sequences, including continuous energy flux spectra for processing multigroup problem-dependent cross sections; one- and three-dimensional sensitivity and uncertainty analyses for criticality safety evaluations; two-dimensional flexible mesh discrete ordinates code; automated burnup-credit analysis sequence; and one-dimensional material distribution optimization for criticality safety. (author)

Contrast media safety-an update

DEFF Research Database (Denmark)

Thomsen, Henrik S

2011-01-01

The value of contrast agents has for long been documented by their common daily use in imaging departments worldwide. In principle, they should be injected and leave the body immediately after use in the same condition or undergo natural metabolism without making any harm to the patient. However......, this is not the case. It is of utmost importance to reduce the prevalence to as close as possible to zero. This can be done by identifying the patients at risk before administration of contrast agents. For acute non-renal adverse reactions, it is also important to be prepared for treating them instantly. The current...... review is a short state of the art regarding adverse reactions to contrast agents....

Safety Training: Basic Safety and Access Courses

CERN Multimedia

Antonella Vignes

2005-01-01

Objective The purpose of the basic safety courses is to increase awareness for everyone working on the CERN site (CERN staff, associates, outside companies, students and apprentices) of the various existing on-site hazards, and how to recognize and avoid them. Safety course changes The current organization for basic safety courses is changing. There will be two main modifications: the organization of the courses and the implementation of a specific new training course for the LHC machine during the LHC tests and hardware commissioning phase. Organizational changes This concerns the existing basic safety training, currently called level1, level2 and level3. Under the new procedure, a video will be projected in registration building 55 and will run every day at 14.00 and 15.00 in English. The duration of the video will be 50 minutes. The course contents will be the same as the slides currently used, plus a video showing real situations. With this new organization, attendees will systematically follow the...

Safety Training: basic safety and access courses

CERN Multimedia

2005-01-01

Objective The purpose of the basic safety courses is to increase awareness for everyone working on the CERN site (CERN staff, associates, outside companies, students and apprentices) of the various hazards existing on site, and how to recognise and avoid them. Safety course changes The current organisation of basic safety courses is changing. There will be two main modifications: the organisation of the courses and the implementation of a specific new training course for the LHC machine during the LHC tests and hardware commissioning phase. Organisational changes This concerns the existing basic safety training, currently called level 1, level 2 and level 3. Under the new procedure, a video will be projected in registration building 55 and will run every day at 14.00 and 15.00 in English. The duration of the video will be 50 minutes. The course contents will be the same as the slides currently used, plus a video showing real situations. With this new organization, participants will systematically follow...

Development and Presentation of the Drigg Post-Closure Safety Case

International Nuclear Information System (INIS)

Kelly, Eugene; Watts, Len; Grimwood, Paul

2001-01-01

Drigg is an operational facility for the near-surface disposal of solid low level radioactive waste (LLW). The disposal facility is located in Cumbria, north-west England, near the Sellafield nuclear site, and is owned and operated by British Nuclear Fuels plc (BNFL). Disposals at Drigg are carried out under the terms of an authorisation granted by the UK Environment Agency. Periodically the Drigg authorisation is subject to formal regulatory review. The current regulatory guidance, 'Disposal Facilities on Land for Low and Intermediate Level Radioactive Wastes: Guidance on Requirements for Authorisation' (the GRA) was published in 1997 and contains guidance on the principles and requirements against which the Environment Agency will consider applications for disposal authorisation. BNFL has undertaken to produce an updated Drigg postclosure safety case (PCSC) in September 2002 to support the next authorisation review. In preparation for this, BNFL published a 'Status Report on the Development of the 2002 Drigg PCSC' in March 2000. This paper discusses the main components of the Drigg PCSC and how they relate to each other. Central to the safety case will be a systematic, post-closure radiological safety assessment (PCRSA). However the main focus of this paper is on the other main components of the PCSC which are presented in conjunction with the PCRSA to make a complete and integrated safety case. In addition other confidence building activities which are key to developing and presenting the safety case are discussed, in particular communications with the stakeholders

Safety evaluation report related to the operation of Millstone Nuclear Power Station, Unit No. 3 (Docket No. 50-423)

International Nuclear Information System (INIS)

1985-09-01

The Safety Evaluation Report issued in August 1984 provided the results of the NRC staff review of Northeast Nuclear Energy Company's application for a license to operate the Millstone Nuclear Power Station, Unit No. 3. Supplement No. 1 to that report, issued in March 1985 updated the information contained in the Safety Evaluation Report and addressed the ACRS Report issued on September 10, 1984. The Report, Supplement No. 2 updates the information contained in the Safety Evaluation Report and Supplement No. 1 and addresses prior unresolved items. The facility is located in Waterford Township, New London, Connecticut. 11 refs., 9 tabs

Update on Intra-Arterial Chemotherapy for Retinoblastoma

Directory of Open Access Journals (Sweden)

Mario Zanaty

2014-01-01

Full Text Available The tools for managing retinoblastoma have been increasing in the past decade. While globe-salvage still relies heavily on intravenous chemotherapy, tumors in advanced stage that failed chemotherapy are now referred for intra-arterial chemotherapy (IAC to avoid enucleation. However, IAC still has many obstacles to overcome. We present an update on the indications, complications, limitations, success, and technical aspects of IAC. Given its safety and high efficacy, it is expected that IAC will replace conventional strategies and will become a first-line option even for tumors that are amenable for other strategies.

Occurrence of lead-related symptoms below the current occupational safety and health act allowable blood lead levels.

Science.gov (United States)

Rosenman, Kenneth D; Sims, Amy; Luo, Zhehui; Gardiner, Joseph

2003-05-01

To determine the occurrence of symptoms of lead toxicity at levels below the current allowable Occupational Safety and Health Act blood lead level of 50 micrograms/dL, standardized telephone interviews were conducted of individuals reported to a statewide laboratory-based surveillance system. Four hundred and ninety-seven, or 75%, of the eligible participants were interviewed. Gastrointestinal, musculoskeletal, and nervous system symptoms increased with increasing blood lead levels. Nervous, gastrointestinal, and musculoskeletal symptoms all began to be increased in individuals with blood leads between 30-39 micrograms/dL and possibly at levels as low as 25-30 micrograms/dL for nervous system symptoms. The results of this study of increased symptoms are consistent with and provide added weight to previous results showing subclinical changes in the neurologic and renal systems and sperm counts at blood lead levels currently allowed by the Occupational Safety and Health Act.

Updates of the fire protection system of the Juzbado Nuclear Fuel Fabrication Plant; Actualizaciones del Sistema de Proteccion Contra Incendios de la Fabrica de Combustible Nuclear de Juzbado

Energy Technology Data Exchange (ETDEWEB)

Dorado, P.; Palomo, J. J.; Romano, A.

2015-07-01

The Juzbado Nuclear Fuel Fabrication Plant fire protection system is one of the most important safety system of the plant. Every year, a large part of the annual investment is employed to improve this system, to update its technology, in order to improve detection and extinction capability to minimize fire risk. Over the last few years, several improvement projects have been carried out that focused on fire detection technology update and on optimization of local detectors integration with a centralized control system, as well as on an advanced public address system, which used clear and unambiguous messages improving personnel response to a plant evacuation. Planned projects and those, which are currently under development, focus on improving passive fire protection means as well as fire protection of key emergency response equipment s such as emergency diesel generators and fire extinguishing bombs. (Author)

Technology Road-map Update for Generation IV Nuclear Energy Systems

International Nuclear Information System (INIS)

2014-01-01

This Technology Road-map Update provides an assessment of progress made by the Generation IV International Forum (GIF) in the development of the six systems selected when the original Technology Road-map was published in 2002. More importantly, it provides an overview of the major R and D objectives and milestones for the coming decade, aiming to achieve the Generation IV goals of sustainability, safety and reliability, economic competitiveness, proliferation resistance and physical protection. Lessons learnt from the Fukushima Daiichi nuclear power plant accident are taken into account to ensure that Generation IV systems attain the highest levels of safety, with the development of specific safety design criteria that are applicable across the six systems. Accomplishing the ten-year R and D objectives set out in this new Road-map should allow the more advanced Generation IV systems to move towards the demonstration phase. (authors)

Diagnosis of current state of the radiological safety system in the radiotherapy services of CCSS

International Nuclear Information System (INIS)

Calvo, Carolina Masis

2013-01-01

This article presents an analysis of evaluation reports issued by the Area of Control of Quality and Radiation Protection (ACCPR) of the Caja Costarricense de Seguro Social (CCSS, unit responsible for monitoring and auditing the System of Institutional Radiation Safety of the Costa Rica. In addition, were conducted a series of interviews to the radiotherapy services and authorities of the services to determine the internal perception on the performance and suitability of these programs.The results of this research have allowed identifying an improvement in the level of compliments of the current legislation on protection and radiation safety in these services through the previous five years; and how internally there is a positive perception of the officials, confirming the suitability of Radiological Protection and Quality Control Programs local. As a result of the analysis of the information gathered, we propose a series of actions and recommendations, that will allow improvements in the System of Institutional Radiation Safety, as the implementation of evaluations type QUATRO and the improvement of the local training programs

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

The nuclear law: safety. 2006-2010

International Nuclear Information System (INIS)

Bringuier, P.

2010-01-01

The author discusses the legal evolutions related to nuclear safety between 2006 and 2010. He identifies three main topics of unequal importance. Firstly, he comments the implementation of an international reference framework which has been completed at the European level and which aims at the harmonization of safety and security rules. Secondly, he comments the creation of the French Nuclear Safety Authority (ASN, Autorite de Surete Nucleaire). Thirdly, he comments the recast of the standard framework in order to update the French law with respect to the international reference framework. This leaded to a new distribution of power and authority, to more complete and constraining procedures, and to the definition of procedures for each step of an installation life cycle

242-A evaporator safety analysis report

International Nuclear Information System (INIS)

Campbell, T.A.

1998-01-01

In compliance with DOE Orders, an update of the 242-A SAR has been prepared, as documented in the referenced ECN. Several categories of changes were identified for inclusion in this revision of the SAR. These categories will be utilized to simplify the discussion of the changes for this USQ document. However, it is important to note that no new tests or experiments were included in this revision of the SAR. Editorial changes and/or informational updates to Chapters 9 and 11 were included as part of this revision. However, no changes to Operational Safety Requirements (OSRs) contained in Chapter 11 were required. General categories of changes included in this revision are listed

Fusion Energy Update

International Nuclear Information System (INIS)

Whitson, M.O.

1982-01-01

Fusion Energy Update (CFU) provides monthly abstracting and indexing coverage of current scientific and technical reports, journal articles, conference papers and proceedings, books, patents, theses, and monographs for all sources on fusion energy. All information announced in CFU, plus additional backup information, is included in the energy information data base of the Department of Energy's Technical Information Center. The subject matter covered by CFU includes plasma physics, the physics and engineering of blankets, magnet coils and fields, power supplies and circuitry, cooling systems, fuel systems, radiation hazards, power conversion systems, inertial confinement systems, and component development and testing

Active transportation: do current traffic safety policies protect non-motorists?

Science.gov (United States)

Mader, Emily M; Zick, Cathleen D

2014-06-01

This study investigated the impact that state traffic safety regulations have on non-motorist fatality rates. Data obtained from the National Highway Traffic Safety Administration (NHTSA), the Federal Highway Administration (FHWA), and the National Institute on Alcohol Abuse and Alcoholism (NIAAA) were analyzed through a pooled time series cross-sectional model using fixed effects regression for all 50 states from 1999 to 2009. Two dependent variables were used in separate models measuring annual state non-motorist fatalities per million population, and the natural log of state non-motorist fatalities. Independent variables measuring traffic policies included state expenditures for highway law enforcement and safety per capita; driver cell phone use regulations; graduated driver license regulations; driver blood alcohol concentration regulations; bike helmet regulations; and seat belt regulations. Other control variables included percent of all vehicle miles driven that are urban and mean per capita alcohol consumption per year. Non-motorist traffic safety was positively impacted by state highway law enforcement and safety expenditures per capita, with a decrease in non-motorist fatalities occurring with increased spending. Per capita consumption of alcohol also influenced non-motorist fatalities, with higher non-motorist fatalities occurring with higher per capita consumption of alcohol. Other traffic safety covariates did not appear to have a significant impact on non-motorist fatality rates in the models. Our research suggests that increased expenditures on state highway and traffic safety and the initiation/expansion of programs targeted at curbing both driver and non-motorist intoxication are a starting point for the implementation of traffic safety policies that reduce risks for non-motorists. Copyright © 2014 Elsevier Ltd. All rights reserved.

UPDATE: Nuclear Power Program information and data, July-September 1984

International Nuclear Information System (INIS)

1985-02-01

UPDATE is published by the Office of Converter Reactor Deployment, Office of Nuclear Energy, to provide a quick reference source on the current status of nuclear powerplant construction and operation in the United States and for information on the fuel cycle, economics, and performance of nuclear generating units. Similar information on other means of electric generation as related to nuclear power is included when appropriate. The subject matter of the reports and analyses presented in UPDATE will vary from issue to issue, reflecting changes in foci of interest and new developments in the field of commercial nuclear power generation. UPDATE is intended to provide a timely source of current statistics, results of analyses, and programmatic information proceeding from the activities of the Office of Nuclear Energy and other components of the Department of Energy, as well as condensations of topical articles from other sources of interest to the nuclear community. It also facilitates quick responses to requests for data and information of the type often solicited from this office

Update: nuclear power program information and data, April-June 1982

International Nuclear Information System (INIS)

1982-01-01

UPDATE is published by the Office of Coordination and Special Projects, Office of Nuclear Reactor Programs, to provide a quick reference source on the current status of nuclear powerplant construction and operation in the United States and for information on the fuel cycle, economics, and performance of nuclear generating units. Similar information on other means of electric generation as related to nuclear power is included when appropriate. The subject matter of the reports and analyses presented in UPDATE will vary from issue to issue, reflecting changes in foci of interest and new developments in the field of commercial nuclear power generation. UPDATE is intended to provide a timely source of current statistics, results of analyses, and programmatic information proceeding from the activities of the Office of Nuclear Reactor Programs and other components of the Department of Energy, as well as condensations of topical articles from other sources of interst to the nuclear community. It also facilitates quick responses to requests for data and information of the type often solicited from this office

Update: nuclear power program information and data, March-April 1981

International Nuclear Information System (INIS)

1981-01-01

UPDATE is published by the Office of Coordination and Special Projects, Office of Nuclear Reactor Programs, to provide a quick reference source on the current status of nuclear powerplant construction and operation in the United States and for information on the fuel cycle, economics, and performance of nuclear generating units. Similar information on other means of electric generation as related to nuclear power is included when appropriate. The subject matter of the reports and analyses presented in UPDATE will vary from issue to issue, reflecting changes in foci of interest and new developments in the field of commercial nuclear power generation. UPDATE is intended to provide a timely source of current statistics, results of analyses, and programmatic information proceeding from the activities of the Office of Nuclear Reactor Programs and other components of the Department of Energy, as well as condensations of topical articles from other sources of interest to the nuclear community. It also facilitates quick responses to requests for data and information of the type often solicited from this office

Update: nuclear power program information and data, October-December 1981

International Nuclear Information System (INIS)

1981-01-01

UPDATE is published by the Office of Coordination and Special Projects, Office of Nuclear Reactor Programs, to provide a quick reference source on the current status of nuclear powerplant construction and operation in the United States and for information on the fuel cycle, economics, and performance of nuclear generating units. Similar information on other means of electric generation as related to nuclear power is included when appropriate. The subject matter of the reports and analyses presented in UPDATE will vary from issue to issue, reflecting changes in foci of interest and new developments in the field of commercial nuclear power generation. UPDATE is intended to provide a timely source of current statistics, results of analyses, and programmatic information proceeding from the activities of the Office of Nuclear Reactor Programs and other components of the Department of Energy, as well as condensations of topical articles from other sources of interest to the nuclear community. It also facilitates quick responses to requests for data and information of the type often solicited from this office

UPDATE: nuclear power program information and data, May-June 1981

International Nuclear Information System (INIS)

1981-01-01

UPDATE is published by the Office of Coordination and Special Projects, Office of Nuclear Reactor Programs, to provide a quick reference source on the current of nuclear status powerplant construction and operation in the United States and for information on the fuel cycle, economics, and performance of nuclear generating units. Similar information on other means of electric generation as related to nuclear power is included when appropriate. The subject matter of the reports and analyses presented in UPDATE will vary from issue to issue, reflecting changes in foci of interest and new development in the field of commercial nuclear power generation. UPDATE is intended to provide a timely source of current statistics, results of analyses, and programmatic information proceeding from the activities of the Office of Nuclear Reactor Programs and other components of the Department of Energy, as well as condensations of topical articles from other sources of interest to the nuclear community. It also facilities quick response for data and information of the type often solicited from this office

Update: nuclear power program information and data, October-December 1981

Energy Technology Data Exchange (ETDEWEB)

1981-01-01

UPDATE is published by the Office of Coordination and Special Projects, Office of Nuclear Reactor Programs, to provide a quick reference source on the current status of nuclear powerplant construction and operation in the United States and for information on the fuel cycle, economics, and performance of nuclear generating units. Similar information on other means of electric generation as related to nuclear power is included when appropriate. The subject matter of the reports and analyses presented in UPDATE will vary from issue to issue, reflecting changes in foci of interest and new developments in the field of commercial nuclear power generation. UPDATE is intended to provide a timely source of current statistics, results of analyses, and programmatic information proceeding from the activities of the Office of Nuclear Reactor Programs and other components of the Department of Energy, as well as condensations of topical articles from other sources of interest to the nuclear community. It also facilitates quick responses to requests for data and information of the type often solicited from this office.

Low edge safety factor operation and passive disruption avoidance in current carrying plasmas by the addition of stellarator rotational transform

Science.gov (United States)

Pandya, M. D.; ArchMiller, M. C.; Cianciosa, M. R.; Ennis, D. A.; Hanson, J. D.; Hartwell, G. J.; Hebert, J. D.; Herfindal, J. L.; Knowlton, S. F.; Ma, X.; Massidda, S.; Maurer, D. A.; Roberds, N. A.; Traverso, P. J.

2015-11-01

Low edge safety factor operation at a value less than two ( q (a )=1 /ι̷tot(a )routine on the Compact Toroidal Hybrid device with the addition of sufficient external rotational transform. Presently, the operational space of this current carrying stellarator extends down to q (a )=1.2 without significant n = 1 kink mode activity after the initial plasma current rise phase of the discharge. The disruption dynamics of these low edge safety factor plasmas depend upon the fraction of helical field rotational transform from external stellarator coils to that generated by the plasma current. We observe that with approximately 10% of the total rotational transform supplied by the stellarator coils, low edge q disruptions are passively suppressed and avoided even though q(a) disrupt, the instability precursors measured and implicated as the cause are internal tearing modes with poloidal, m, and toroidal, n, helical mode numbers of m /n =3 /2 and 4/3 observed on external magnetic sensors and m /n =1 /1 activity observed on core soft x-ray emissivity measurements. Even though the edge safety factor passes through and becomes much less than q(a) disruption phenomenology observed.

CANDU severe accident management guidance update

International Nuclear Information System (INIS)

Jones, L.; Popov, N.; Gilbert, L.; Weed, J.

2014-01-01

The CANDU Owners Group (COG) developed a set of generic and initial station-specific Severe Accident Management Guidance (SAMG) documents to mitigate the consequences to the public in the event of a severe accident. The generic portion of the COG SAMG was completed in 2006; the overall project including the station-specific phase was completed in April 2007. Over the years, the CANDU industry and utilities have continuously increased the knowledge base for SAMG and have incorporated various engineered features based on the knowledge obtained. As a result of the event that occurred at the Fukushima Daiiachi nuclear power plant (NPP) in Japan, the Canadian Nuclear Safety Commission (CNSC) established the CNSC Fukushima Task Force. The results of the task force were documented in INFO-0828, CNSC Staff Action Plan on the CNSC Fukushima Task Force Recommendations. Among the recommendation documented in INFO-828 were Fukushima Action Items (FAIs) directed towards the CANDU utilities in Canada; a portion of which are related to SAMG documentation updates and directed at enhancing SAM response. A COG joint project was established to support the closure of the CNSC FAIs and to revise the current CANDU documentation accordingly. This paper provides a high level summary of the COG project scope and results. It also demonstrates that the CANDU SAMG programs in Canada provide robust protection and mitigation of severe accidents. (author)

CANDU severe accident management guidance update

Energy Technology Data Exchange (ETDEWEB)

Jones, L., E-mail: lisa.m.jones@opg.com [Ontario Power Generation, Pickering, ON (Canada); Popov, N., E-mail: nik.popov@rogers.com [Candu Owners Group, Toronto, ON (Canada); Gilbert, L., E-mail: lovell.gilbert@brucepower.com [Bruce Power, Tiverton, ON (Canada); Weed, J., E-mail: jeff.weed@candu.gov [Candu Owners Group, Toronto, ON (Canada)

2014-07-01

The CANDU Owners Group (COG) developed a set of generic and initial station-specific Severe Accident Management Guidance (SAMG) documents to mitigate the consequences to the public in the event of a severe accident. The generic portion of the COG SAMG was completed in 2006; the overall project including the station-specific phase was completed in April 2007. Over the years, the CANDU industry and utilities have continuously increased the knowledge base for SAMG and have incorporated various engineered features based on the knowledge obtained. As a result of the event that occurred at the Fukushima Daiiachi nuclear power plant (NPP) in Japan, the Canadian Nuclear Safety Commission (CNSC) established the CNSC Fukushima Task Force. The results of the task force were documented in INFO-0828, CNSC Staff Action Plan on the CNSC Fukushima Task Force Recommendations. Among the recommendation documented in INFO-828 were Fukushima Action Items (FAIs) directed towards the CANDU utilities in Canada; a portion of which are related to SAMG documentation updates and directed at enhancing SAM response. A COG joint project was established to support the closure of the CNSC FAIs and to revise the current CANDU documentation accordingly. This paper provides a high level summary of the COG project scope and results. It also demonstrates that the CANDU SAMG programs in Canada provide robust protection and mitigation of severe accidents. (author)

Modulation of Brain Activity with Noninvasive Transcranial Direct Current Stimulation (tDCS): Clinical Applications and Safety Concerns

Science.gov (United States)

Zhao, Haichao; Qiao, Lei; Fan, Dongqiong; Zhang, Shuyue; Turel, Ofir; Li, Yonghui; Li, Jun; Xue, Gui; Chen, Antao; He, Qinghua

2017-01-01

Transcranial direct current stimulation (tDCS) is a widely-used tool to induce neuroplasticity and modulate cortical function by applying weak direct current over the scalp. In this review, we first introduce the underlying mechanism of action, the brief history from discovery to clinical scientific research, electrode positioning and montages, and parameter setup of tDCS. Then, we review tDCS application in clinical samples including people with drug addiction, major depression disorder, Alzheimer's disease, as well as in children. This review covers the typical characteristics and the underlying neural mechanisms of tDCS treatment in such studies. This is followed by a discussion of safety, especially when the current intensity is increased or the stimulation duration is prolonged. Given such concerns, we provide detailed suggestions regarding safety procedures for tDCS operation. Lastly, future research directions are discussed. They include foci on the development of multi-tech combination with tDCS such as with TMS and fMRI; long-term behavioral and morphological changes; possible applications in other research domains, and more animal research to deepen the understanding of the biological and physiological mechanisms of tDCS stimulation. PMID:28539894

Comparative approach between nuclear safety and security

International Nuclear Information System (INIS)

2009-04-01

Adopting the definition of nuclear safety and nuclear security as they are specified by IAEA glossaries, this report first outlines that these both notions refer to similar risks but with causes of different nature. They discuss the notions of transparency and confidentiality and outline that security and safety both aims at the protection of population and of the environment. They discuss their organisational principles, notice that both have their own legal and regulatory framework, that authorities have expertise on both, that the responsibility is distributed among operators and the State, and that safety and security cultures are complementary. They analyse the design, exploitation and management principles of security and safety approaches: graded approach, defence-in-depth, synergy between security and safety, same daily monitoring requirement, same necessity to address the return on experience, same need to update a referential, a more constrained exchange of good practices in safety, a necessity to deal with their respective requirements, elaboration of emergency plans, performance of exercises

Flammable gas tank safety program: Technical basis for gas analysis and monitoring

International Nuclear Information System (INIS)

Estey, S.D.

1998-01-01

Several Hanford waste tanks have been observed to exhibit periodic releases of significant quantities of flammable gases. Because potential safety issues have been identified with this type of waste behavior, applicable tanks were equipped with instrumentation offering the capability to continuously monitor gases released from them. This document was written to cover three primary areas: (1) describe the current technical basis for requiring flammable gas monitoring, (2) update the technical basis to include knowledge gained from monitoring the tanks over the last three years, (3) provide the criteria for removal of Standard Hydrogen Monitoring System(s) (SHMS) from a waste tank or termination of other flammable gas monitoring activities in the Hanford Tank farms

The impact of masculinity on safety oversights, safety priority and safety violations in two male-dominated occupations

DEFF Research Database (Denmark)

Nielsen, Kent; Hansen, Claus D.; Bloksgaard, Lotte

2015-01-01

Background Although men have a higher risk of occupational injuries than women the role of masculinity for organizational safety outcomes has only rarely been the object of research. Aim The current study investigated the association between masculinity and safety oversights, safety priority......-related context factors (safety leadership, commitment of the safety representative, and safety involvement) and three safety-related outcome factors (safety violations, safety oversights and safety priority) were administered twice 12 months apart to Danish ambulance workers (n = 1157) and slaughterhouse workers...

FED-A, an advanced performance FED based on low safety factor and current drive

International Nuclear Information System (INIS)

Peng, Y.K.M.; Rutherford, P.H.

1983-08-01

The FED-A study aims to quantify the potential improvement in cost-effectiveness of the Fusion Engineering Device (FED) by assuming low safety factor q (less than 2 as opposed to about 3) at the plasma edge and noninductive current drive (as opposed to only inductive current drive). The FED-A performance objectives are set to be : (1) ignition assuming International Tokamak Reactor (INTOR) plamsa confinement scaling, but still achieving a fusion power amplification Q greater than or equal to 5 when the confinement is degraded by a factor of 2; (2) neutron wall loading of about 1 MW/m 2 , with 0.5 MW/m 2 as a conservative lower bound; and (3) more clearly power-reactor-like operations, such as steady state

Update in Infectious Diseases 2017.

Science.gov (United States)

Candel, F J; Peñuelas, M; Lejárraga, C; Emilov, T; Rico, C; Díaz, I; Lázaro, C; Viñuela-Prieto, J M; Matesanz, M

2017-09-01

Antimicrobial resistance in complex models of continuous infection is a current issue. The update 2017 course addresses about microbiological, epidemiological and clinical aspects useful for a current approach to infectious disease. During the last year, nosocomial pneumonia approach guides, recommendations for management of yeast and filamentous fungal infections, review papers on the empirical approach to peritonitis and extensive guidelines on stewardship have been published. HIV infection is being treated before and more intensively. The implementation of molecular biology, spectrometry and inmunology to traditional techniques of staining and culture achieve a better and faster microbiological diagnosis. Finally, the infection is increasingly integrated, assessing non-antibiotic aspects in the treatment.

IAEA codes and guides for safety of nuclear power plants

International Nuclear Information System (INIS)

Raisic, N.

1980-01-01

The objectives and scope of the Agency's programme of nuclear safety standards are described and the role of these documents in regulation of nuclear power im Member States is discussed. For each of the five areas of safety standards development, i.e. siting, design, operation, quality assurance and governmental organization, a set of principles underlying requirements and recommendations contained in the Code of Practice and Safety Guides will be presented. Safety Guides in each of the five areas will be reviewed in respect of the scope and content. A consideration will be given to the future development of the safety standards and to the revision and updating of the published documents. (orig./RW)

An Integrated Platform for Dynamic Software Updating and its Application in Self-* systems

DEFF Research Database (Denmark)

Gregersen, Allan Raundahl; Jørgensen, Bo Nørregaard; Hadaytullah

2012-01-01

Practical dynamic updating of modern Java applications requires tool support to become an integral part of the software development and maintenance lifecycle. In this paper we present Javeleon, an easy-to-use tool for dynamic updates of Java applications. To support integration with specific...... frameworks, component systems and application servers, Javeleon currently provides tight integration with the NetBeans Platform, facilitating dynamic updating for applications built on top of the NetBeans Platform in an unconstrained manner. Javeleon supports state-preserving unanticipated runtime evolution...

Neural system for updating object working memory from different sources: sensory stimuli or long-term memory.

Science.gov (United States)

Roth, Jennifer K; Courtney, Susan M

2007-11-15

Working memory (WM) is the active maintenance of currently relevant information so that it is available for use. A crucial component of WM is the ability to update the contents when new information becomes more relevant than previously maintained information. New information can come from different sources, including from sensory stimuli (SS) or from long-term memory (LTM). Updating WM may involve a single neural system regardless of source, distinct systems for each source, or a common network with additional regions involved specifically in sensory or LTM processes. The current series of experiments indicates that a single fronto-parietal network (including supplementary motor area, parietal, left inferior frontal junction, middle frontal gyrus) is active in updating WM regardless of the source of information. Bilateral cuneus was more active during updating WM from LTM than updating from SS, but the activity in this region was attributable to recalling information from LTM regardless of whether that information was to be entered into WM for future use or not. No regions were found to be more active during updating from SS than updating from LTM. Functional connectivity analysis revealed that different regions within this common update network were differentially more correlated with visual processing regions when participants updated from SS, and more correlated with LTM processing regions when participants updated from the contents of LTM. These results suggest that a single neural mechanism is responsible for controlling the contents of WM regardless of whether that information originates from a sensory stimulus or from LTM. This network of regions involved in updating WM interacts with the rest of the brain differently depending on the source of newly relevant information.

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

specific plant status. The review of the safety features of 'small series' WWER-1000 plants shows that the main safety concept of these reactors is similar to that of model 320 with respect to the nuclear island arrangement, the amount of safety systems and the main process parameters of the primary and secondary circuits. However, the 'small series' WWER-1000 plants have major deficiencies such as a lack of separation of redundant safety systems and a single set of the reactor protection system for technological parameters which do not meet the current national standards and international practice. Differences in engineering design solutions, quality of manufacture and reliability of equipment have been revealed as deficiencies. About one third of the design safety issues have been identified by operational experience. The majority of safety issues have been identified as deviations from current standards and practices which have evolved since the WWER-1000 NPPs were designed. Much of the backfitting and upgrading work recognized as being required has been or is being performed. This activity was initiated by the WWER Owners Group and since the early 1990s international assistance has played an important role in the process of safety improvement of these NPPs. The current status of plant specific backfitting varies from site to site, depending on national regulatory requirements and the available financial means. The review of the plant specific status also indicates that certain safety issues have already been solved in some units. This report presents the information currently available to the IAEA on safety issues and safety improvement measures in 'small series' WWER-1000 plants. The IAEA intends to update this information regularly and make it available to the interested parties as part of the technical database developed within the framework of the Extra budgetary Programme on the Safety of WWER and RBMK NPPs.

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

specific plant status. The review of the safety features of 'small series' WWER-1000 plants shows that the main safety concept of these reactors is similar to that of model 320 with respect to the nuclear island arrangement, the amount of safety systems and the main process parameters of the primary and secondary circuits. However, the 'small series' WWER-1000 plants have major deficiencies such as a lack of separation of redundant safety systems and a single set of the reactor protection system for technological parameters which do not meet the current national standards and international practice. Differences in engineering design solutions, quality of manufacture and reliability of equipment have been revealed as deficiencies. About one third of the design safety issues have been identified by operational experience. The majority of safety issues have been identified as deviations from current standards and practices which have evolved since the WWER-1000 NPPs were designed. Much of the backfitting and upgrading work recognized as being required has been or is being performed. This activity was initiated by the WWER Owners Group and since the early 1990s international assistance has played an important role in the process of safety improvement of these NPPs. The current status of plant specific backfitting varies from site to site, depending on national regulatory requirements and the available financial means. The review of the plant specific status also indicates that certain safety issues have already been solved in some units. This report presents the information currently available to the IAEA on safety issues and safety improvement measures in 'small series' WWER-1000 plants. The IAEA intends to update this information regularly and make it available to the interested parties as part of the technical database developed within the framework of the Extra budgetary Programme on the Safety of WWER and RBMK NPPs

Radiation safety for site radiography

International Nuclear Information System (INIS)

1986-01-01

This guidance is an update of the 1975 Code of Practice for Site Radiography and is for the use of employers and their radiographers who carry out site work. The subject is discussed under the following headings: Administrative organization, Personnel requirements, Equipment (x-ray and gamma-ray equipment, security, pipeline crawler equipment and safety equipment) Work methods and monitoring, Carriage of sources, Contingency plans, Legal considerations. (U.K.)

Safety Evaluation Report related to the operation of Comanche Peak Steam Electric Station, Units 1 and 2 (Docket Nos. 50-445 and 50-446)

International Nuclear Information System (INIS)

1984-11-01

This supplement reports the status of certain issues that had not been resolved at the time of publication of the Safety Evaluation Report and Supplement 1, 2, 3, and 4 of that report. (Supplement 5, currently in preparation, will document the staff's evaluation findings pertaining solely to an independent design verification, conducted for the applicant by the CYGNA Corporation in late 1983-early 1984, and does not update the status of issues since the release of Supplement 4.)

An Updated Examination of Aviation Accidents Associated with Turbulence, Wind Shear and Thunderstorm

Science.gov (United States)

Evans, Joni K.

2014-01-01

One of the technical challenges within the Atmospheric Environment Safety Technologies (AEST) Project of the Aviation Safety Program was to "improve and expand remote sensing and mitigation of hazardous atmospheric environments and phenomena"1. In 2012, the author performed an analysis comparing various characteristics of accidents associated with different types of atmospheric hazard environments2. This document reports an update to that analysis which was done in preparation for presenting these findings at the 2015 annual meeting of the Transportation Research Board. Specifically, an additional three years of data were available, and a time-trend analysis was added.

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.)

Current state of research on pressurized water reactor safety

International Nuclear Information System (INIS)

Couturier, Jean; Schwarz, Michel; Roubaud, Sebastien; Lavarenne, Caroline; Mattei, Jean-Marie; Rigollet, Laurence; Scotti, Oona; Clement, Christophe; Lancieri, Maria; Gelis, Celine; Jacquemain, Didier; Bentaib, Ahmed; Nahas, Georges; Tarallo, Francois; Guilhem, Gilbert; Cattiaux, Gerard; Durville, Benoit; Mun, Christian; Delaval, Christine; Sollier, Thierry; Stelmaszyk, Jean-Marc; Jeffroy, Francois; Dechy, Nicolas; Chanton, Olivier; Tasset, Daniel; Pichancourt, Isabelle; Barre, Francois; Bruna, Gianni; Evrard, Jean-Michel; Gonzalez, Richard; Loiseau, Olivier; Queniart, Daniel; Vola, Didier; Goue, Georges; Lefevre, Odile

2018-03-01

For more than 40 years, IPSN then IRSN has conducted research and development on nuclear safety, specifically concerning pressurized water reactors, which are the reactor type used in France. This publication reports on the progress of this research and development in each area of study - loss-of-coolant accidents, core melt accidents, fires and external hazards, component aging, etc. -, the remaining uncertainties and, in some cases, new measures that should be developed to consolidate the safety of today's reactors and also those of tomorrow. A chapter of this report is also devoted to research into human and organizational factors, and the human and social sciences more generally. All of the work is reviewed in the light of the safety issues raised by feedback from major accidents such as Chernobyl and Fukushima Daiichi, as well as the issues raised by assessments conducted, for example, as part of the ten-year reviews of safety at French nuclear reactors. Finally, through the subjects it discusses, this report illustrates the many partnerships and exchanges forged by IRSN with public, industrial and academic bodies both within Europe and internationally

Bipolar disorder: an update | Outhoff | South African Family Practice

African Journals Online (AJOL)

Bipolar disorder, characterised by alternating discrete episodes of (hypo)mania and depression, provides unique diagnostic and treatment challenges. Updated diagnostic (DSM-5) and current pharmacological treatment recommendations are briefly reviewed here. Keywords: bipolar disorder; diagnosis; evidence-based ...

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

The update of the accounting procedures in Agricultural Cooperatives.

Directory of Open Access Journals (Sweden)

Rafael Enrique Viña Echevarría

2014-06-01

Full Text Available As part of the implementation of Internal Control in Agricultural Cooperatives from the standards established by the General Controller of the Republic, and the harmonization of accounting procedures Cuban Accounting Standards, It is need to update the accounting procedure manuals to guide and regulate the flows, times and registration basis, considering the current legislation, being these the purpose of the discussion in this investigation. The results focused on organizational dynamics of cooperatives, serving the agricultural cooperative sector and its relation to internal control and accounting management guidelines based on economic and social policy of the Party and the Revolution, as well as updating the procedure manuals. It even showed limitations in the application of internal control procedures and accounting according to the current regulations in Cuba, expressing the need to continue its development.

An update on safety and immunogenicity of vaccines containing emulsion-based adjuvants.

Science.gov (United States)

Fox, Christopher B; Haensler, Jean

2013-07-01

With the exception of alum, emulsion-based vaccine adjuvants have been administered to far more people than any other adjuvant, especially since the 2009 H1N1 influenza pandemic. The number of clinical safety and immunogenicity evaluations of vaccines containing emulsion adjuvants has correspondingly mushroomed. In this review, the authors introduce emulsion adjuvant composition and history before detailing the most recent findings from clinical and postmarketing data regarding the effects of emulsion adjuvants on vaccine immunogenicity and safety, with emphasis on the most widely distributed emulsion adjuvants, MF59® and AS03. The authors also present a summary of other emulsion adjuvants in clinical development and indicate promising avenues for future emulsion-based adjuvant development. Overall, emulsion adjuvants have demonstrated potent adjuvant activity across a number of disease indications along with acceptable safety profiles.

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

International Nuclear Information System (INIS)

Byun, Myung Woo

2009-01-01

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

Update of axion CDM energy density

International Nuclear Information System (INIS)

Huh, Ji-Haeng

2008-01-01

We update cosmological bound on axion model. The contribution from the anharmonic effect and the newly introduced initial overshoot correction are considered. We present an explicit formula for the axion relic density in terms of the QCD scale Λ QCD , the current quark masses m q 's and the Peccei-Quinn scale F a , including firstly introduced 1.85 factor which is from the initial overshoot.

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.

Safety Case for Service Contracts

Energy Technology Data Exchange (ETDEWEB)

Martinez, Israel L.

2014-07-01

Safety cases developed for the Facilities Management and Operations Center (FMOC) are based on the requirements in MN471021, Work Planning and Control Criteria for Safe Design and Operations. The FMOC performs maintenance activities in various locations at Sandia National Laboratories, New Mexico (SNL/NM). SNL/NM consists of more than 6,000,000 square feet of buildings, structures, and site infrastructure on approximately 13,000 acres of land. The FMOC performs approximately 7500 service contract work orders a year to assist with operations and maintenance at the SNL/NM site and facilities. As part of the continual improvement process, this Safety Case will be reviewed and updated, as needed, or at a minimum every three years.

Physics and safety of advanced research reactors

International Nuclear Information System (INIS)

Boening, K.; Hardt, P. von der

1987-01-01

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

Pharmaceutical company perspectives on current safety risk communications in Japan.

Science.gov (United States)

Urushihara, Hisashi; Kobashi, Gen; Masuda, Hideaki; Taneichi, Setsuko; Yamamoto, Michiko; Nakayama, Takeo; Kawakami, Koji; Matsuda, Tsutomu; Ohta, Kaori; Sugimori, Hiroki

2014-01-01

In 1987, a group infection of hepatitis in patients receiving a contaminated fibrinogen product was first reported to the Japanese regulatory agency. Eventually, this serious drug incident involved more than 10,000 cases of infection. In response, the Government of Japan established a responding inspection committee in 2008 to make recommendations for the restructuring of drug regulatory administration. The final report was issued in 2010. One agenda item of this restructuring was the improvement of drug-related safety risk communications. Our research group on drug safety risk communications, which is funded by the Government of Japan, surveyed pharmaceutical companies regarding their perspective on current risk communications. The survey was conducted using an anonymous questionnaire developed for this study which included the three operational domains of targets, contents, and measures of drug risk communication. Fifty-two of the 74 member companies of the Post-marketing Surveillance Subcommittee of the Japan Pharmaceutical Manufacturer's Association participated, and this response rate of more than 70% was considered sufficient to ensure the external validity of the survey results. Results showed that the most highly prioritized aspect of risk messaging was the strength of evidence, and that outcome evaluation of risk communication gained recognition. Further, while physicians and pharmacists were the most prioritized communication targets, pharmacovigilance departments devoted the most resources to regulators, at more than 30%. The Internet was recognized as a useful public source of risk information, whereas Drug Guides for Patients delivered on the web were considered under-recognized. Further discussion of these results with the aim of enhancing the restructuring of the Japanese drug regulatory administration system are warranted.

Safety Culture Monitoring: How to Assess Safety Culture in Real Time?

International Nuclear Information System (INIS)

Zronek, B.; Maryska, J.; Treslova, L.

2016-01-01

Do you know what is current level of safety culture in your company? Are you able to follow trend changes? Do you know what your recent issues are? Since safety culture is understood as vital part of nuclear industry daily life, it is crucial to know what the current level is. It is common to perform safety culture survey or ad hoc assessment. This contribution shares Temelin NPP, CEZ approach how to assess safety culture level permanently. Using behavioral related outputs of gap solving system, observation program, dedicated surveys, regulatory assessment, etc., allows creating real time safety culture monitoring without the need to perform any other activities. (author)

[Drinking water quality and safety].

Science.gov (United States)

Gómez-Gutiérrez, Anna; Miralles, Maria Josepa; Corbella, Irene; García, Soledad; Navarro, Sonia; Llebaria, Xavier

2016-11-01

The purpose of drinking water legislation is to guarantee the quality and safety of water intended for human consumption. In the European Union, Directive 98/83/EC updated the essential and binding quality criteria and standards, incorporated into Spanish national legislation by Royal Decree 140/2003. This article reviews the main characteristics of the aforementioned drinking water legislation and its impact on the improvement of water quality against empirical data from Catalonia. Analytical data reported in the Spanish national information system (SINAC) indicate that water quality in Catalonia has improved in recent years (from 88% of analytical reports in 2004 finding drinking water to be suitable for human consumption, compared to 95% in 2014). The improvement is fundamentally attributed to parameters concerning the organoleptic characteristics of water and parameters related to the monitoring of the drinking water treatment process. Two management experiences concerning compliance with quality standards for trihalomethanes and lead in Barcelona's water supply are also discussed. Finally, this paper presents some challenges that, in the opinion of the authors, still need to be incorporated into drinking water legislation. It is necessary to update Annex I of Directive 98/83/EC to integrate current scientific knowledge, as well as to improve consumer access to water quality data. Furthermore, a need to define common criteria for some non-resolved topics, such as products and materials in contact with drinking water and domestic conditioning equipment, has also been identified. Copyright © 2016 SESPAS. Publicado por Elsevier España, S.L.U. All rights reserved.

Occupational Safety and Health in Venezuela.

Science.gov (United States)

Caraballo-Arias, Yohama

2015-01-01

Venezuela has pioneered a preventive-focused and comprehensive movement for Occupational Safety and Health (OSH) in Latin America. However, despite being an oil-rich country, it has some of the lowest salaries for their workers and highest levels of hyperinflation, devaluation, crime, and violence of the world. Review the current status and challenges on relevant aspects of OSH in Venezuela. Review of literature and documents from national governments, UN agencies, NGOs, and the Venezuelan government concerning OSH and related topics since 1986. Reformed in 2005, the Organic Law on Prevention, Conditions and Environment (LOPCYMAT) was a fundamental moment of change for OSH. Factors which have impacted OSH the strongest are (i) the creation of the National Institute of Occupational Safety and Health (INPSASEL) and (ii) the socioeconomic crisis Venezuela is going through. Venezuela's laws are innovative and yet non-compliance is enormous. Almost half of the population works in the informal sector. Following the International Labor Office projections, 5 people die per day in Venezuela due to occupational accidents or diseases, making health and safety at work a luxury rather than a right. The quality of life for the average worker has deteriorated, affecting not only health but the overall well-being of all Venezuelans. The political and socio-economic situation has led to a mass exodus of more than 1.6 million highly qualified and talented professionals. Many statistics concerning OSH are not updated and are unreliable regarding occupational accidents and diseases. There is a substantial difference between what is written to protect individual Venezuelans in the workplace and the reality of workplace conditions. Substantial governmental actions are needed in the immediate future to improve occupational safety and health of Venezuelan workers. Copyright © 2015 The Author. Published by Elsevier Inc. All rights reserved.

Development of an Updated Societal-Risk Goal for Nuclear Power Safety

Energy Technology Data Exchange (ETDEWEB)

Vicki Bier; Michael Corradini; Robert Youngblood; Caleb Roh; Shuji Liu

2014-07-01

This report briefly summarizes work done in FY 2013 on the subject LDRD. The working hypothesis is that societal disruption should be addressed in a safety goal. This is motivated by the point that the Fukushima disaster resulted in very little public dose, but enormous societal disruption; a goal that addressed societal disruption would fill a perceived gap in the US NRC safety goal structure. This year's work entailed analyzing the consequences of postulated accidents at various reactor sites in the US, specifically with a view to quantifying the number of people relocated and the duration of their relocation, to see whether this makes sense as a measure of societal disruption.

ADAS Update and Maintainability

Science.gov (United States)

Watson, Leela R.

2010-01-01

Since 2000, both the National Weather Service Melbourne (NWS MLB) and the Spaceflight Meteorology Group (SMG) have used a local data integration system (LOIS) as part of their forecast and warning operations. The original LOIS was developed by the Applied Meteorology Unit (AMU) in 1998 (Manobianco and Case 1998) and has undergone subsequent improvements. Each has benefited from three-dimensional (3-D) analyses that are delivered to forecasters every 15 minutes across the peninsula of Florida. The intent is to generate products that enhance short-range weather forecasts issued in support of NWS MLB and SMG operational requirements within East Central Florida. The current LDIS uses the Advanced Regional Prediction System (ARPS) Data Analysis System (AD AS) package as its core, which integrates a wide variety of national, regional, and local observational data sets. It assimilates all available real-time data within its domain and is run at a finer spatial and temporal resolution than current national or regional-scale analysis packages. As such, it provides local forecasters with a more comprehensive understanding of evolving fine-scale weather features. Over the years, the LDIS has become problematic to maintain since it depends on AMU-developed shell scripts that were written for an earlier version of the ADAS software. The goals of this task were to update the NWS MLB/SMG LDIS with the latest version of ADAS, incorporate new sources of observational data, and upgrade and modify the AMU-developed shell scripts written to govern the system. In addition, the previously developed ADAS graphical user interface (GUI) was updated. Operationally, these upgrades will result in more accurate depictions of the current local environment to help with short-range weather forecasting applications, while also offering an improved initialization for local versions of the Weather Research and Forecasting (WRF) model used by both groups.

The update of competence and infrastructure to the near future

International Nuclear Information System (INIS)

Dias, Marcio Soares; Mattos, Joao Roberto Loureiro de

2009-01-01

Currently, the Brazilian nuclear organizations are conducting joint efforts toward the management of existing personnel and infrastructure in order to update their competence to study and develop the nuclear fuel elements for high performance and extended burnup. As contribution to this effort, the Nuclear Technology Development Centre is promoting the update of the fuel rod design codes to ensure they are fit and appropriate to design purposes and to evaluations of the fuel rod performance in accordance with current and near future insertion conditions. Comprehensive models of thermal properties and in-pile behavior of the fuel are in development by the CDTN's expert staff, insertion into performance codes and validation against a representative database as the International Fuel Performance Experiments. The thermal properties of UO 2 and (U,Gd)O 2 have been reviewed and reduced into the analytical models based on a topological view of the matter and its properties. The current status of this project is presented in this paper. (author)

Parallel main-memory indexing for moving-object query and update workloads

DEFF Research Database (Denmark)

Sidlauskas, Darius; Saltenis, Simonas; Jensen, Christian Søndergaard

2012-01-01

of supporting the location-related query and update workloads generated by very large populations of such moving objects. This paper presents a main-memory indexing technique that aims to support such workloads. The technique, called PGrid, uses a grid structure that is capable of exploiting the parallelism...... offered by modern processors. Unlike earlier proposals that maintain separate structures for updates and queries, PGrid allows both long-running queries and rapid updates to operate on a single data structure and thus offers up-to-date query results. Because PGrid does not rely on creating snapshots...... on the same current data-store state, PGrid outperforms snapshot-based techniques in terms of both query freshness and CPU cycle-wise efficiency....

Biological pathways, candidate genes, and molecular markers associated with quality-of-life domains: an update

NARCIS (Netherlands)

Sprangers, Mirjam A. G.; Thong, Melissa S. Y.; Bartels, Meike; Barsevick, Andrea; Ordoñana, Juan; Shi, Qiuling; Wang, Xin Shelley; Klepstad, Pål; Wierenga, Eddy A.; Singh, Jasvinder A.; Sloan, Jeff A.; Abertnethy, Amy P.; Baas, Frank; Barsevick, Andrea M.; Boomsma, Dorret I.; Bottomley, Andrew; Brundage, Michael; Cella, David; Chauhan, Cynthia; Cleeland, Charles S.; Coens, Corneel; Dueck, Amylou C.; Frost, Marlene H.; Hall, Per; Halyard, Michele Y.; van Laarhoven, Hanneke W. M.; Martin, Nicholas G.; Miaskowski, Christine; Mosing, Miriam; Movsas, Benjamin; Oliveira, Joao R.; Patrick, Donald L.; Pedersen, Nancy L.; Raat, Hein; Reeve, Bryce; Stephen, Ristvedt; Ropka, Mary E.; Schwartz, Carolyn; Shi, Quiling; Shinozaki, Gen; Swaab, Dick; Talwalkar, Jayant; Thong, Melissa; van Noorden, Cornelis J. F.; Veenhoven, Ruut; Wagner, Gert; Wierenga, Eddy; Yang, Ping; Zwinderman, Ailko H.

2014-01-01

There is compelling evidence of a genetic foundation of patient-reported quality of life (QOL). Given the rapid development of substantial scientific advances in this area of research, the current paper updates and extends reviews published in 2010. The objective was to provide an updated overview

Improved precision and accuracy for microarrays using updated probe set definitions

Directory of Open Access Journals (Sweden)

Larsson Ola

2007-02-01

Full Text Available Abstract Background Microarrays enable high throughput detection of transcript expression levels. Different investigators have recently introduced updated probe set definitions to more accurately map probes to our current knowledge of genes and transcripts. Results We demonstrate that updated probe set definitions provide both better precision and accuracy in probe set estimates compared to the original Affymetrix definitions. We show that the improved precision mainly depends on the increased number of probes that are integrated into each probe set, but we also demonstrate an improvement when the same number of probes is used. Conclusion Updated probe set definitions does not only offer expression levels that are more accurately associated to genes and transcripts but also improvements in the estimated transcript expression levels. These results give support for the use of updated probe set definitions for analysis and meta-analysis of microarray data.

The in-depth safety assessment (ISA) pilot projects in Ukraine

International Nuclear Information System (INIS)

Kot, C. A.

1998-01-01

Ukraine operates pressurized water reactors of the Soviet-designed type, VVER. All Ukrainian plants are currently operating with annually renewable permits until they update their safety analysis reports (SARs). After approval of the SARS by the Ukrainian Nuclear Regulatory Authority, the plants will be granted longer-term operating licenses. In September 1995, the Nuclear Regulatory Authority and the Government Nuclear Power Coordinating Committee of Ukraine issued a new contents requirement for the safety analysis reports of VVERs in Ukraine. It contains requirements in three major areas: design basis accident (DBA) analysis, probabilistic risk assessment (PRA), and beyond design-basis accident (BDBA) analysis. The DBA requirements are an expanded version of the older SAR requirements. The last two requirements, on PRA and BDBA, are new. The US Department of Energy (USDOE), through the International Nuclear Safety Program (INSP), has initiated an assistance and technology transfer program to Ukraine to assist their nuclear power stations in developing a Western-type technical basis for the new SARS. USDOE sponsored In-Depth Safety Assessments (ISAs) have been initiated at three pilot nuclear reactor units in Ukraine, South Ukraine Unit 1, Zaporizhzhya Unit 5, and Rivne Unit 1. USDOE/INSP have structured the ISA program in such a way as to provide maximum assistance and technology transfer to Ukraine while encouraging and supporting the Ukrainian plants to take the responsibility and initiative and to perform the required assessments

The current CEA/DRN safety approach for the design and the assessment of non-electrical applications of nuclear heat

International Nuclear Information System (INIS)

Fiorini, G.L.; Costa, M.

2000-01-01

This paper presents the basis of the safety approach currently implemented by the Commissariat a l'Energie Atomique - Nuclear Reactor Directorate (CEA/DRN), both for the design and the assessment of innovative systems and future nuclear installations. It is considered that the described approach is applicable to the plants built for non-electrical applications of nuclear heat. This is typically the case of Nuclear Desalination Installations. This approach is the result of the experience maturated, within the context of the CEA/DRN Innovative Programme, through practical applications over several future concepts (both fission and fusion plants). The background of this experience is structured coherently with the European Safety Authorities recommendations, the European Utilities Requirements (EUR) and the ''fundamental safety objectives'' defined by the IAEA. The Defence In Depth principle and its application, by means, among others, of the barrier concept, remains the basis of the safety design process of future nuclear installations. Its adequacy is checked through the safety assessment. The methodology for Lines of Defence (LOD) implementation as well as the one for the LOD architecture assessment is shown and motivated. The document shows that the clear and unambiguous definition of the safety approach provides an essential base for the organisation of the design tasks, being sure that the safety aspects are correctly taken into account and implemented, and for an adequate safety assessment of the final design, both from qualitative point of view as well as for the quantitative safety analysis. (author)

Integrated safety assessment report, Haddam Neck Plant (Docket No. 50-213): Integrated Safety Assessment Program: Draft report

International Nuclear Information System (INIS)

1987-07-01

The integrated assessment is conducted on a plant-specific basis to evaluate all licensing actions, licensee initiated plant improvements and selected unresolved generic/safety issues to establish implementation schedules for each item. Procedures allow for a periodic updating of the schedules to account for licensing issues that arise in the future. The Haddam Neck Plant is one of two plants being reviewed under the pilot program. This report indicates how 82 topics selected for review were addressed, and presents the staff's recommendations regarding the corrective actions to resolve the 82 topics and other actions to enhance plant safety. 135 refs., 4 figs., 5 tabs

Working Memory Updating Latency Reflects the Cost of Switching between Maintenance and Updating Modes of Operation

Science.gov (United States)

Kessler, Yoav; Oberauer, Klaus

2014-01-01

Updating and maintenance of information are 2 conflicting demands on working memory (WM). We examined the time required to update WM (updating latency) as a function of the sequence of updated and not-updated items within a list. Participants held a list of items in WM and updated a variable subset of them in each trial. Four experiments that vary…

Plan for safety case of spent fuel repository at Olkiluoto

International Nuclear Information System (INIS)

Vieno, T.; Ikonen, A.T.K.

2005-02-01

Posiva aims to present the Safety Case supporting the construction license application of the spent fuel repository at Olkiluoto by 2012. An outline and preliminary assessments will be presented in 2009. Interim reporting and an update of the Safety Case plan will be presented in 2006, as required by the authorities. The KBS-3 disposal concept aims at long-term isolation and containment of spent fuel assemblies in durable copper-iron canisters emplaced in a repository to be constructed at a depth between 400 and 600 metres in crystalline bedrock. By 2012, studies on the KBS-3 disposal concept and site investigations at Olkiluoto will have been continued over about thirty years. The construction of an underground rock characterisation facility (called ONKALO) was started in June 2004. The investigations are carried out in close cooperation with the Swedish SKB developing and assessing the same disposal concept at candidate sites, resembling Olkiluoto, at the other side of the Baltic Sea. A safety case is the synthesis of evidence, analyses and arguments that quantify and substantiate the safety, and the level of expert confidence in the safety, of a planned repository. Posiva's Safety Case will be organised in a portfolio including ten main reports, which will be periodically updated according the overall schedule presented in the plan. The Site report describing the present state and past evolution of the Olkiluoto site, as well as the disturbances caused by the construction of ONKALO and the first stage of the repository, forms the geoscientific basis of the Safety Case. The engineering basis is provided by the reports on the Characteristics of spent fuel, Canister design, and Repository design. The Process report containing descriptions and analyses of features, events and processes potentially affecting the disposal system, and the report on the Evolution of site and repository form the scientific basis of the Safety Case. The latter report will describe and

FRMAC Updates

International Nuclear Information System (INIS)

Mueller, P.

1995-01-01

This talks describes updates in the following updates in FRMAC publications concerning radiation emergencies: Monitoring and Analysis Manual; Evaluation and Assessment Manual; Handshake Series (Biannual) including exercises participated in; environmental Data and Instrument Transmission System (EDITS); Plume in a Box with all radiological data stored onto a hand-held computer; and courses given

Constructing a Bayesian network model for improving safety behavior of employees at workplaces.

Science.gov (United States)

Mohammadfam, Iraj; Ghasemi, Fakhradin; Kalatpour, Omid; Moghimbeigi, Abbas

2017-01-01

Unsafe behavior increases the risk of accident at workplaces and needs to be managed properly. The aim of the present study was to provide a model for managing and improving safety behavior of employees using the Bayesian networks approach. The study was conducted in several power plant construction projects in Iran. The data were collected using a questionnaire composed of nine factors, including management commitment, supporting environment, safety management system, employees' participation, safety knowledge, safety attitude, motivation, resource allocation, and work pressure. In order for measuring the score of each factor assigned by a responder, a measurement model was constructed for each of them. The Bayesian network was constructed using experts' opinions and Dempster-Shafer theory. Using belief updating, the best intervention strategies for improving safety behavior also were selected. The result of the present study demonstrated that the majority of employees do not tend to consider safety rules, regulation, procedures and norms in their behavior at the workplace. Safety attitude, safety knowledge, and supporting environment were the best predictor of safety behavior. Moreover, it was determined that instantaneous improvement of supporting environment and employee participation is the best strategy to reach a high proportion of safety behavior at the workplace. The lack of a comprehensive model that can be used for explaining safety behavior was one of the most problematic issues of the study. Furthermore, it can be concluded that belief updating is a unique feature of Bayesian networks that is very useful in comparing various intervention strategies and selecting the best one form them. Copyright © 2016 Elsevier Ltd. All rights reserved.

Update and revision of WHO air quality guidelines for Europe

Energy Technology Data Exchange (ETDEWEB)

Younes, M. [WHO European Centre for Environment and Health, Bilthoven (Netherlands). Bilthoven Div.

1995-12-31

The WHO Air Quality Guidelines for Europe (AQG), published in 1987, have provided a uniform basis for the development of strategies for the control of air pollution, and have contributed to the maintenance and improvement of public health in several countries. The aim of the guidelines is to provide a basis for protecting public health from adverse effects of air pollutants, and for eliminating or reducing to a minimum, those contaminants that are known or likely to be hazardous to human health and wellbeing. Since the publication of the first edition of the AQG, new scientific data in the fields of air pollution toxicology and epidemiology have accumulated and new developments in risk assessment methodologies have taken place, requiring updating and/or revision of the existing guidelines. This fact was recognized during the preparation of the initial work plan of the European Centre for Environment and Health, and it was recommended that the Centre undertake any necessary amendments and extensions to the Air Quality Guidelines. The updating procedure is being carried out in cooperation with the International Programme on Chemical Safety (IPCS) and the Commission of the European Communities (CEC) and will be implemented through working group meetings which require the preparation of working documents on specific air pollutants or mixtures and a final consultation to discuss the updated document.It was initiated by a Planning Meeting which was organized in January 1993. The purpose of the planning meeting was to set the framework for the updating and revision process, in particular to discuss the scope and purpose, the contents and the format of the revised AQG publication, to define the details of and the time schedule for the updating process and to identify the working groups needed and their way of operation. (author)

Update and revision of WHO air quality guidelines for Europe

Energy Technology Data Exchange (ETDEWEB)

Younes, M [WHO European Centre for Environment and Health, Bilthoven (Netherlands). Bilthoven Div.

1996-12-31

The WHO Air Quality Guidelines for Europe (AQG), published in 1987, have provided a uniform basis for the development of strategies for the control of air pollution, and have contributed to the maintenance and improvement of public health in several countries. The aim of the guidelines is to provide a basis for protecting public health from adverse effects of air pollutants, and for eliminating or reducing to a minimum, those contaminants that are known or likely to be hazardous to human health and wellbeing. Since the publication of the first edition of the AQG, new scientific data in the fields of air pollution toxicology and epidemiology have accumulated and new developments in risk assessment methodologies have taken place, requiring updating and/or revision of the existing guidelines. This fact was recognized during the preparation of the initial work plan of the European Centre for Environment and Health, and it was recommended that the Centre undertake any necessary amendments and extensions to the Air Quality Guidelines. The updating procedure is being carried out in cooperation with the International Programme on Chemical Safety (IPCS) and the Commission of the European Communities (CEC) and will be implemented through working group meetings which require the preparation of working documents on specific air pollutants or mixtures and a final consultation to discuss the updated document.It was initiated by a Planning Meeting which was organized in January 1993. The purpose of the planning meeting was to set the framework for the updating and revision process, in particular to discuss the scope and purpose, the contents and the format of the revised AQG publication, to define the details of and the time schedule for the updating process and to identify the working groups needed and their way of operation. (author)

Current role of the USNRC safety research program in support of the regulatory process

International Nuclear Information System (INIS)

Levine, S.

1979-01-01

The current role of the USNRC's safety research program is shown. Some aspects of this role in the wake of the TMI accident are discused as well as some historical perspective on the development of USNRC's program, its relationship with the NRC mission, an overview of the program activities and some recent research results, and finally the impact of the TMI accident in clarifiying needs for expedited and new research activities, including the need for a greatly enhanced use of probabilistic analysis techniques to improve the coherence of its regulatory process. (author)

Current safety issues in the development of geological disposal of radioactive waste in France

International Nuclear Information System (INIS)

Raimbault, P.

2002-01-01

Deep geological disposal of high level and medium level long-lived waste in France is one of the three research paths defined by the law of 30th December 1991 on radioactive waste management. Research should be undertaken on: separation and transmutation of long-lived radionuclides in these waste; reversible or non reversible disposal in deep geological layers supported by investigations in underground laboratories; processes for conditioning and long term surface storage of these waste. In 2006, a global evaluation report on this research should be established by the Government and sent to the French Parliament. On this basis the Parliament should promulgate a law providing new objectives for the research and possibly presenting a framework for a deep disposal process. The French Nuclear Safety Authority has the responsibility to license the underground laboratories foreseen in the second research path and the nuclear facilities involved in the first and third research paths and make sure that existing high level and medium level long-lived waste currently produced are properly managed. It will give its advice on the safety aspects associated to the envisaged future management options. Its main concern is that results obtained in 2006 will be conclusive enough to take decisions for future orientations. Concerning the deep disposal option, under the responsibility of ANDRA (Agence Nationale pour la gestion des Dechets RAdioactifs), the construction of an underground laboratory has been authorized on the Bure site, in eastern France, and the shafts are under construction. The main issue is the level of investigations that may be performed in the host rock in order to support the feasibility study of a disposal concept on this site. Other issues are the elaboration of new safety standards to set a framework for a safety assessment of a disposal concept, the specifications for acceptance of waste packages in a future deep disposal, and relation of safety matters with

Deterministic Safety Analysis for Nuclear Power Plants. Specific Safety Guide (Spanish Edition)

International Nuclear Information System (INIS)

2012-01-01

The IAEA's Statute authorizes the Agency to establish safety standards to protect health and minimize danger to life and property - standards which the IAEA must use in its own operations, and which a State can apply by means of its regulatory provisions for nuclear and radiation safety. A comprehensive body of safety standards under regular review, together with the IAEA's assistance in their application, has become a key element in a global safety regime. In the mid-1990s, a major overhaul of the IAEA's safety standards programme was initiated, with a revised oversight committee structure and a systematic approach to updating the entire corpus of standards. The new standards that have resulted are of a high calibre and reflect best practices in Member States. With the assistance of the Commission on Safety Standards, the IAEA is working to promote the global acceptance and use of its safety standards. Safety standards are only effective, however, if they are properly applied in practice. The IAEA's safety services - which range in scope from engineering safety, operational safety, and radiation, transport and waste safety to regulatory matters and safety culture in organizations - assist Member States in applying the standards and appraise their effectiveness. These safety services enable valuable insights to be shared and I continue to urge all Member States to make use of them. Regulating nuclear and radiation safety is a national responsibility, and many Member States have decided to adopt the IAEA's safety standards for use in their national regulations. For the contracting parties to the various international safety conventions, IAEA standards provide a consistent, reliable means of ensuring the effective fulfilment of obligations under the conventions. The standards are also applied by designers, manufacturers and operators around the world to enhance nuclear and radiation safety in power generation, medicine, industry, agriculture, research and education

Introduction to 'International Handbook of Criticality Safety Benchmark Experiments'

International Nuclear Information System (INIS)

Komuro, Yuichi

1998-01-01

The Criticality Safety Benchmark Evaluation Project (CSBEP) was initiated in 1992 by the United States Department of Energy. The project quickly became an international effort as scientists from other interested countries became involved. The International Criticality Safety Benchmark Evaluation Project (ICSBEP) is now an official activity of the Organization for Economic Cooperation and Development-Nuclear Energy Agency (OECD-NEA). 'International Handbook of Criticality Safety Benchmark Experiments' was prepared and is updated year by year by the working group of the project. This handbook contains criticality safety benchmark specifications that have been derived from experiments that were performed at various nuclear critical facilities around the world. The benchmark specifications are intended for use by criticality safety engineers to validate calculation techniques used. The author briefly introduces the informative handbook and would like to encourage Japanese engineers who are in charge of nuclear criticality safety to use the handbook. (author)

Literature searches on Ayurveda: An update.

Science.gov (United States)